ML021300024

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2001 Annual Radiological Environmental Operating Report
ML021300024
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 04/30/2002
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, NRC/FSME
References
B18648
Download: ML021300024 (117)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station

Dom inio Rope Ferry Road Waterford, CT 06385 AFAR 3Q 20i2 Docket Nos. 50-245 50-336 50-423 B18648 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 2001 Annual Radiological Environmental Operating Report This document transmits the Millstone Nuclear Power Station Annual Radiological Environmental Operating Report, in accordance with the requirements of Section 5.7.2 of the Millstone Unit No. 1 Permanently Defueled Technical Specifications and of Sections 6.9.1.6a and 6.9.1.3 of the Unit No. 2 and Unit No. 3 Technical Specifications, respectively.

There are no regulatory commitments contained within this submittal.

If you have any questions concerning this submittal, please contact Mr. David A. Smith at (860) 437-5840.

Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

JS Allih Price Slite'Vice President - Millstone Enclosure (1) cc: H. J. Miller, Region I Administrator J. B. Hickman, NRC Project Manager, Millstone Unit No. 1 T. J. Jackson, NRC Inspector, Region I, Millstone Unit No. 1 R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 V. Nerses, NRC Senior Project Manager, Millstone Unit No. 3 NRC Senior Resident Inspector, Millstone Unit No. 3

Docket Nos. 50-245 50-336 50-423 B18648 Enclosure 1 Millstone Nuclear Power Station, Unit Nos. 1, 2 and 3 Annual Radiological Environmental Operating Report Radiological Environmental Monitoring Program Januarv 1. 2001 - December 31, 2001

Millstone Power Station Annual RadiologicalEnvironmental OperatingReport January 1, 2001 - December 31, 2001 By Dominion Nuclear Connecticut, Inc.

Waterford, Connecticut Iy  :'N f ~t!

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT MILLSTONE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2001 MILLSTONE UNIT 1, DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET NO. 50-336 MILLSTONE UNIT 3, DOCKET NO. 50-423 By the Dominion Nuclear Connecticut, Inc.

Waterford, Connecticut

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

1-1

2. PROGRAM DESCRIPTION 2-1 2.1. Sampling Schedule and Locations 2-1 2.2. Samples Collected During Report Period 2-7
3. RADIOCHEMICAL RESULTS 3-1 3.1. Summary Table 3-1 3.2. Data Tables 3-20
4. DISCUSSION OF RESULTS 4-1 4.1. Gamma Exposure Rate (Table 1) 4-1 4.2. Air Particulate Gross Beta Radioactivity (Table 2) 4-3 4.3. Airborne Iodine (Table 3) 4-3 4.4. Air Particulate Gamma (Table 4A-D) 4-5 4.5. Air Particulate Strontium 4-5 4.6. Soil (Table 6) 4-5 4.7. Cow Milk (Table 7) 4-5 4.8. Goat Milk (Table 8) 4-6 4.9. Pasture Grass and Feed (Table 9) 4-7 4.10. Well Water 4-7 4.11. Reservoir Water 4-7 4.12. Fruits and Vegetables (Table 12) 4-7 4.13. Broad Leaf Vegetation (Table 13) 4-8 4.14. Seawater (Table 14) 4-8 4.15. Bottom Sediment (Table 15) 4-9 4.16. Aquatic Flora (Table 16) 4-10 4.17. Fish (Tables 17A and 17B) 4-10 4.18. Mussels (Table 18) 4-10 4.19. Oysters (Table 19) 4-10 4.20. Clams (Table 20) 4-12 4.21. Scallops 4-12 4.22. Lobsters (Table 22) 4-12
5. OFFSITE DOSE EQUIVALENT COMMITMENTS 5-1
6. DISCUSSION 6-1 APPENDIX A - LAND USE CENSUS FOR 2001 A-1 APPENDIX B - DNC QA PROGRAM B-1 APPENDIX C -

SUMMARY

OF INTERLABORATORY COMPARISONS C-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

1. EXECUTIVE

SUMMARY

The radiological environmental monitoring program for the Millstone Power Station was continued for the period January through December 2001, in compliance with the Technical Specifications and the Radiological Effluent Monitoring and Offsite Dose Calculation Manual.

This annual report was prepared by the Nuclear Fuel Engineering group of Dominion Nuclear Connecticut, Inc. (DNC). Sample collection and preparation were performed by Millstone staff. Gamma exposure rate measurements and laboratory analyses were performed by Duke Engineering and Services Environmental Laboratory (DESEL).

Thermoluminescent dosimeters (TLDs) were used to measure direct gamma exposure in the vicinity of the station and as far away as 14 miles. Radiochemical and radiological counting analyses of samples were performed to detect the presence of any station related radioactivity.

Samples included air particulate and iodine filters, goat milk, pasture grass, broad leaf vegetation, fruits, vegetables, sea water, bottom sediment, aquatic flora, fish, mussels, oysters, clams, and lobsters. In evaluating the results 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. This 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 cosmically produced radioactivity, 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 station related radioactivity.

Millstone Unit 1 is permanently shutdown. Unit 2 had an overall capacity factor of 95.3% for 2001. Millstone Unit 3 had a scheduled refueling outage starting on Feb. 3 and operated at essentially 100% power after restart for an overall capacity factor of 80.8% for 2001. The radioactive releases of gaseous effluents in 2001 were comparable to years when one or more units operated for the majority of the year. Radioactive releases in liquid effluents continue to be low.

No station effects were detected in terrestrial media. The predominant radioactivity, except for a few aquatic sample results, was that from outside sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following station related radionuclides: Silver-i lOnm and Tritium. Due to the decreasing trend in 1-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station liquid effluent releases, a corresponding decrease is observed in measured levels of radionuclides in the environment. Doses from the 2001 measured levels are well below those required by each Unit's Safety Technical Specifications (I1OCFR50 Appendix I, Design Guidelines).

Cesium- 137 and Strontium-90 were measured in goat milk as a result of nuclear weapons testing in the 1960's and not the result of station operation. This can be concluded because insufficient quantities of these isotopes have been released by the station to account for the measured concentrations and the presence of these isotopes have been consistently declining since the early 1960's after signing of the Nuclear Test Ban Treaty.

The radiation dose (dose equivalent commitment) to the general public from the station'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 as a result of station operation was 0.08 millirem. This dose is 0.3 percent of the standard (i.e., 25 millirem to the whole body at the station site boundary) as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public.

Historically, the average whole body dose for a member of the public residing within 50 miles of the station is generally three orders of magnitude less than the maximum individual whole body dose. 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. Station related doses are even a smaller fraction of the natural background. Therefore, the station related doses have insignificant public health consequences.

1-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

2. PROGRAM DESCRIPTION 2.1. Sampling Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Tables 2-1 and 2-2 and Figures 2.1-1 and 2.1-2. The program as described here includes both required samples as specified in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual and any extra samples.

2-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Table 2-1 Enviromnental Monitoring Program Sampling Types and Locations On-site - I U.6 I LL), Air I-arnculate, iodine, Vegetation On-site - Weather Shack 0.3 Mi, S TLD, Air Particulate, Iodine On-site - Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, Iodine On-site - Albacore Drive 1.0 Mi, N TLD, Air Particulate, Iodine MP3 Discharge 0.1 Mi, SSE TLD Quarry Discharge 0.3 Mi, SSE TLD Environmental Lab Dock 0.3 Mi, SE TLD Environmental Lab 0.3 Mi, SE TLD Bay Point Beach 0.4 Mi, W TLD Pleasure Beach 1.2 MiE TLD, Air Particulate, Iodine New London Country Club 1.6 Mi, ENE TLD, Air Particulate, Iodine Fisher's Island, NY 8.7 Mi, ESE TLD Fisher's Island, NY 8.7 Mi, ESE Air Particulate Mystic, CT 11.5 Mi, ENE TLD Ledyard, CT 12.0 Mi, NE TLD Norwich, CT 14.0 Mi, N TLD, Air Particulate, Iodine Old Lyme, CT 8.8 Mi, W TLD Site Boundary 0.5 Mi, NE Vegetation Golden Spur 4.7 Mi, NNW Bottom Sediment Goat Location #1 2.0 Mi, N Milk Goat Location #2 5.2 Mi, NNE Milk Goat Location #4 29.0 Mi, NNW Milk Within 10 Miles Within 10 Miles Fruits & Vegetables Beyond 10 Miles Beyond 10 Miles Fruits & Vegetables Niantic 1.7 Mi, WNW TLD, Air Particulate, Iodine Two Tree Island 0.8 Mi, SSE Mussels West Jordan Cove 0.4 Mi, NNE Clams Niantic Shoals 1.5 Mi, NNW Mussels Niantic Shoals 1.8 Mi, NW Bottom Sediment, Oysters Niantic Shoals 1.8 Mi, NW Scallops Vicinity of Discharge Bottom Sediment, Oysters, Lobster, Fish, Seawater Vicinity of Discharge Fucus Seaside Point 1.8 Mi, ESE Bottom Sediment Seaside Point 1.8 Mi, ESE Fucus Thames River Yacht Club 4.0 Mi, ENE Bottom Sediment Thames River Yacht club 4.0 Mi, ENE Oysters

  • Key: I - Indicator C - Control X - Extra - sample not required by REMODCM
    • The release points are the MP1 stack for terrestrial locations and the quarry cut for aquatic locations.

2-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Niantic Bay 0.3 Mi, WNW Lobster, Fish Niantic Bay 0.3 Mi, WNW Bottom Sediment, Seawater, Clams Black Point 3.0 Mi, WSW Oysters Black Point 3.0 Mi, WSW Bottom Sediment, Fucus Giant's Neck 3.5 Mi, WSW Bottom Sediment, Oysters, Seawater Giant's Neck 3.5 Mi, WSW Lobster Waterford Shellfish Bed #1 1.0 Mi, NW Clams Jordon Cove Bar 0.8 Mi, NE Clams Quarry Fish, Oysters Myrock Avenue 3.2 Mi, ENE TLD Billow Road 2.4 Mi, WSW TLD Black Point 2.6 Mi, SW TLD Onsite - Schoolhouse 0.1 Mi, NNE TLD Onsite Access Road 0.5 Mi, NNW TLD Old Lyme - Hillcrest Ave. 4.6 Mi, WSW TLD East Lyme - W. Main St. 4.5 Mi, W TLD East Lyme - Corey Rd. 3.4 Mi, WNW TLD East Lyme - Society Rd. 3.6 Mi, NW TLD East Lyme - Manwaring Rd. 2.1 Mi, W TLD East Lyme - Smith Ave. 1.5 Mi, NW TLD Waterford - River Rd. 1.1 Mi, NNW TLD Waterford - Gardiners Wood Rd. 1.4 Mi, NNE TLD Waterford - Magonk Point 1.8 Mi, ESE TLD New London - Mott Ave. 3.7 Mi, E TLD New London - Ocean Ave. 3.6 Mi, ENE TLD Waterford -Miner Ave. 3.4 Mi, NNE TLD Waterford - Parkway South 4.0 Mi, N TLD Waterford - Boston Post Rd. 4.3 Mi, NNW TLD East Lyme - Columbus Ave. 1.9 Mi, WNW TLD Waterford - Jordon Cove Rd. 0.8 Mi, NE TLD Waterford - Shore Rd. 1.1 Mi, ENE TLD Waterford - Bank St. 3.2 Mi, NE TLD NAP Parking Lot - Fitness Center 0.4 Mi, NW TLD

  • Key: I - Indicator C - Control X - Extra - sample not required
    • The release points are the MP1 stack for terrestrial locations and the quarry cut for aquatic locations.

2-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Table 2-2 Sampling Frequency & Type of Analysis

1. Gamma Dose - 40a Quarterly Gamma Dose - Quarterly Environmental TLD
2. Airborne Particulate 8 Continuous sampler - Gross Beta - Weekly weekly filter change Gamma Spectrum - Quarterly on composite (by location), and on individual sample if gross beta is greater than 10 times the mean of the weekly control station's gross beta results
3. Airborne Iodine 8 Continuous sampler - I-131 - Weekly weekly canister change
4. Vegetation 5 One sample near middle Gamma Isotopic on each sample and one near end of growing season
5. Milk 3 Semimonthly when animals Gamma Isotopic and 1-131 on each are on pasture; monthly at sample; Sr-89 and Sr-90 on other times. quarterly composite 5a. Pasture Grass 4 Sample as necessary to Gamma Isotopic and I-131 on each substitute for unavailable sample milk
6. Sea Water 2 Continuous sampler with a Gamma Isotopic and Tritium on monthly collection at each sample.

indicator location.

Quarterly at control location

- Composite of 6 weekly grab samples.

7. Bottom Sediment 5 Semiannual Gamma Isotopic on each sample 7a. Soil 3 Quarterly Gamma Isotopic on each sample
8. Fin Fish-Flounder 2 Quarterly Gamma Isotopic on each sample and one other type of edible fin fish
9. Mussels 2 Quarterly Gamma Isotopic on each sample (edible portion) l
10. Oysters 4 Quarterly Gamma Isotopic on each sample (edible portion)
11. Clams 2 Quarterly Gamma Isotopic on each sample (edible portion)
12. Lobster 2 Quarterly Gamma Isotopic on each sample (edible portion) II (a) Two or more TLDs or TLD with two or more elements per location.

2-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Enviromnental Operating Report 2001 Millstone Station Fivure 2. 1-1 Millstone Sampling Locations 2-5

Dom inion Nuclear Connecticut, inc. Annual Radiological Environmental Operating Repot 2001 Millstne.Station Figure 2.1-2 Millstone Sampling Locations (Within 2 miles) 2-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 2.2. Samples Collected During Report Period The following table summarizes the number of samples of each type collected and analyzed during 2001:

Gamma Exposure 160 160 4 (Environmental TLD)

Air Particulates 424 424 0 Air Iodine 424 424 0 Soil 12 31 0 Goat Milk 57 242,3 1 Pasture Grass Variable 2 33 1 Fruit and Vegetables 8 8 0 Broad Leaf Vegetation 6 6 14 Sea Water 16 16 8 Bottom Sediment 10 10 14 Aquatic Flora 0 0 16 Fish 16 134 4 Mussels 8 8 0 Oysters 16 16 8 Clams 8 8 8 Lobster 8 8 4 Total All Types 1,173 1,161 82

'Requirement to sample soil did not become effective until the 4th quarter of 2001.

2 Pasture grass sampled as necessary to substitute for unavailable milk.

3Due to sample unavailability, less than required milk samples were collected 4 First quarter sample of Flounder and Other fish were unavailable from the vicinity of discharge location (32). First quarter sample of Flounder from location (35) was unavailable. Multiple attempts were made to collect these samples.

2-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

3. RADIOCHEMICAL RESULTS 3.1. Summary Table In accordance with the Radiological Effluent Monitoring Manual (REMM),Section I.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 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 data summaries. The data summaries include the extra 'X samples collected throughout the year. These samples are taken in an effort to enhance program monitoring effectiveness or are the results of special studies.

3-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 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 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 = 4.66 Sb E*V

  • 2.22
  • Y
  • exp (-)At) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)

X 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 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. As shown in the equation above, for composite samples taken over a period of time, the LLD is decayed to the end of the sample period.

B. Analytical results are handled as recommended by HASL ("Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham) and 3-18

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 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 report levels of Table E-2 of the Radiological Effluent Monitoring ManuaL D. First number is the number of indicator measurements, the second is the number of control measurements.

E. Assuming 270 m3 F. Assuming 1080 mi3 G. LLD for leafy vegetables.

H. LLD from the end of the sample period.

3-19

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 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 3c;).

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
2. Air Particulates, Gross Beta Radioactivity
3. Air Particulates, Weekly I-131
4. Air Particulates, Quantitative Gamma Spectra
5. Air Particulates, Quarterly Strontium*
6. Soil
7. Milk - Dairy Farms*
8. Milk - Goat Farms
9. Pasture Grass 1O.Well Water*

11 .Reservoir Water*

12.Fruits & Vegetables 13.Broad Leaf Vegetation 14.Seawater 15.Bottom Sediment 16Aquatic Flora 17.Fin Fish 18.Mussels 19.0ysters 20.Clams 21.Scallops*

22.Lobster (and Crabs)

  • This type of sampling or analysis was not performed, therefore there is no table.

3-20

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

4. DISCUSSION OF RESULTS This section summarizes the results of the analyses of environmental media sampled. DNC 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. Few impacts of the station operation on the environment were observed. Sub-sections contain a description of each particular media or potential exposure pathway.

Naturally occurring nuclides such as Be-7, K-40, Ra-226 and Th-228 were detected in numerous samples. Be-7, which is produced by cosmic processes, was observed predominantly in airborne and vegetation samples.

Ra-226 and Th-228 results were variableand are generally at levels higher than plant related radionuclides.

Cs-137 and Sr-90 were observed at levels similar to those of past years.

The levels of Cs-137 and Sr-90 detected were the result of atmospheric nuclear weapons testing in the 1960's.

4.1. Gamma Exposure Rate (Table 1)

Gamma exposure rate is determined from the integrated exposure measured over a quarter using CaSO4 (Tm) Panasonic model UD-804 ASx thermoluminescent dosimeters (TLDs). In 2000, the TLDs (Victoreen glass bulb CaF2 (Mn)) which historically were used to measure radioactivity around Millstone for over 20 years were replaced with the Panasonic TLDs. The new Panasonic dosimeters have a lower response than the Victoreen dosimeters. Results from 2000 and 2001 show a 15% to 20% lower response when compared to trended results for previous years. This lower response is consistent for all locations, including both indicator and control locations.

The dosimeters are strategically placed at a number of on-site locations, as well as at inner and outer off-site locations. Starting in 2001, the collection of TLDs was changed from monthly to quarterly and additional locations were incorporated into the REMODCM for measurement. The number of measurements was increased from 17 required and 5 'extra' locations in 2000 to 40 required and 1 'extra' location in 2001. The one 'extra' location (66X - Fitness Center) is being measured quarterly since this location is accessible by members of the public who use the onsite fitness facility outside of the plant protected area. The exposure rate measurements in Table 1 show the results for all 41 locations measured. Trends similar to those of past years are observed.

These measurements demonstrate the general variations in background radiation between the various on-site and off-site 4-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station locations and include gamma exposure from all sources of radioactivity. For example, the Weather Shack (location 02), MP3 Discharge (location 05), Environmental Laboratory (location 08),

and Corey Road (location 48) experience higher exposure rates due to their proximity to granite beds and stone wall fence. In addition, the Ledyard control location (location 14C) experiences relatively higher background exposure rates than the other control locations at Mystic, Norwich, and Old Lyme (locations 13C, 15C, and 16C). The only appreciable effect seen in the TLD data is that attributable to the variation in the background radiation which is consistent with previous years.

Figure 4.1-1 shows a historical trend of TLD exposure rate measurements, comparing an annual average of all indicator TLDs, an annual average of all control TLDs, and the annual average of the two most critical indicator locations which are used to represent the two closest site boundary residences in the North-northwest and Northeast directions. Examination of the average measurements since 1990 show interesting site changes and site characteristics. For example, the average of all indicator locations up through 1995 when Unit 1 was still in operation display the effects of N-16 BWR turbine building skyshine to immediate areas onsite. As discussed in previous annual reports, the effects of skyshine at onsite monitoring stations were increases as high as 6 uR/hr at certain onsite locations. Skyshine decreased rapidly with distance and was indistinguishable from normal background measurements at the closest offsite monitoring stations. Also apparent in Figure 4.1-1 is the replacement of the historical Victoreen TLD monitoring system with the Panasonic system in year 2000. The difference in response between the two systems is very apparent with the new Panasonic TLDs reading 15% to 20%

lower. The figure also relates the difference in critical indicator locations (1) and (3) and the annual average of all indicator TLDs to the annual average of the control TLDs collected and measured during coincident periods throughout the year. The exposure measurements of many indicator locations onsite are under the influence of natural background exposure differences caused by the many granite out-croppings typical of the Millstone area.

Historical data evaluation has shown that TLD sample locations in the vicinity of granite can be dramatically influenced by natural radioactivity contained within the granite. As shown in Figure 4.1-1, the annual average of the indicator TLDs and one of the critical indicator locations are slightly higher in gamma exposure rate than the average control gamma exposure rate. This difference is the result of the nearby granite. For conservatism, if the difference were the result of plant operation (e.g., storage of radioactive waste on-site, gaseous effluents, etc.) an assessment of the resulting dose 4-2

Dominion Nuclear Connectcut, Inc. Annual Radiological Environmental Operating Report 2001 Milltone Station were the result of plant operation (e.g., storage of radioactive waste on-site, gaseous effluents, etc.) an assessment of the resulting dose consequences assuming constant year-round residency is shown in Section 5 as not exceeding 4.4 mrem.

Figure 4.1-1 MILLSTONE TLDs u0lhr Historical Annual Gamma Exposure Rate 12

  • AIIindicator PlControls
  • Indicator Loc 1 e Icator La 3 10 a

S 4.2. Air Particulate Gross Beta Radioactivity (Table 2)

Air is continuously sampled at one outer ring and seven inner ring locations by passing it through glass fiber particulate filters. These are collected weekly and analyzed for gross beta radioactivity.

Results are shown on Figure 4.2-1 and Table 2. Gross beta activity remained at levels similar to that seen over the last decade. Inner and outer ring monitoring locations continue to show no significant variation in measured activities (see Figure 4.2-2). This indicates that any station contribution is not measurable.

4.3. Airborne lodire (Table 3)

Charcoal cartridges are included at all of the Radiological Effluent Monitoring Manual (REMM) required air particulate stations for the collection of atmospheric iodine. These cartridges are analyzed on a weekly basis for 1-13 1. No detectable levels of 1-131 were seen in the 2001 charcoal samples.

4-3 Cc&

Dominion Nuclear Connecticut, Inc. Annual Radiological Enviromnental Operating Report 2001 Millstone Station Figure 4-1 MILLSTONE AIR PARTICULATE pCi/m3 2001 Gross Beta Radioactivity 0.035 - -

0.03 -_

0.025 --

0.02 -4 0.015 -

0.01 -

Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Figure 4.2-2 MILLSTONE AIR PARTICULATE pCi/m3 5 Year Historical Gross Beta Radioactivity 0.035 0.03 Il l+ Indicatorsl Controls EM 0.025 0.02 km000 0)0 000 0.015

- - A ' - ' 0 ' O 0' 0 ' ')' ' I 0.01

.- Y, L - 9 9 9 9 9 9 (n

0) 0) 0) 0 0) 0 0 ) 0) 0) 0) 0) 0 0 0 0) 0 0)- L -C 3 - a >

- E E - Z E E (0 Z E 'n z 4-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 4.4. Air Particulate Gamma (Table 4A-D)

The air particulate samples that are utilized for the weekly gross beta analyses are composited and analyzed quarterly for gamma emitting isotopes. The results, as shown in Tables 4A - 4D, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. No other positive results were seen. These analyses indicate the lack of station effects.

4.5. Air Particulate Strontium Table 5 in past years was used to report the measurement of Sr-89 and Sr-90 in quarterly composited air particulate filters. Because previous data has shown the lack of detectable station activity in this media, the requirement for these measurements was removed from the Radiological Effluent Monitoring Manual (REMM) and analyses have been discontinued. The fact that milk samples are a much more sensitive indicator of fission product existence in the environment, prompted the decision for discontinuation. In the event of widespread station related contamination or special events such as the Chernobyl incident, these measurements may be made. Historically, when world events created conditions to cause these measurements to be detectable, no difference was noted between indicator and control locations. This further confirns that detectable levels were not plant related.

4.6. Soil (Table 6)

Millstone resumed collection of soil as a required media type in the fourth quarter of 2001. It has not been sampled for over fifteen years largely due to the fact that when it was previously sampled, no detectable station activity was observed. No station detectable activity is seen in Table 6 soil samples taken this year either, and that trend is expected to continue. However, baseline activity levels for isotopes such as Cs-137 from past weapons testing fallout will prove useful years into the future when site characterization and decommissioning of the station become the focus after License termination. This media will be collected quarterly from one control and two indicator locations.

4.7. Cow Milk (Table 7)

The most sensitive indicator of fission product existence in the terrestrial environment is usually milk samples. This, in 4-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station combination with the fact that milk is a widely consumed food, results in this pathway usually being the most critical.

Unfortunately, since 1996 al dairy (cow) farms close enough (i.e.

within 10 miles) to Millstone to be considered an indicator location have been out of business. Therefore, the sampling of cow milk has stopped until such time that a new dairy farm goes into business. Each year a Land Use Census is used to identify locations of milk animals that should be included in the monitoring program. It is performed annually and is maintained by observations, door-to-door surveys and consulting with local agriculture authorities. The 2001 census can be seen in Appendix A. If and when a new dairy farm business starts within a distance to be considered an indicator location to measure levels of station radioactivity, the collection of cow milk will resume.

4.8. Goat Milk (Table 8)

Goat milk samples can be a more sensitive indicator of fission products in the terrestrial environment than cow milk samples.

This is dependent on a number of parameters, including:

metabolism of these animals, feeding habits, and feed type. During past weapons testing periods, samples taken at certain locations indicated higher uptake than others. This was especially apparent in past samples collected in the immediate area around Millstone (see previous Annual Operating Reports). One of these sites, location 22 (5.2 Mi. NNE), sampled only since 1994, exhibits this trend showing higher Sr-90 and Cs-137 concentrations. See Section 6.0 for further discussion of Sr-90 and Cs-137 in goat milk.

Goat milk was unavailable all year from location 21 (2.0 Mi. N).

Per requirements, pasture grass or feed is collected as a substitute when milk cannot be collected (see 4.9. Pasture Grass and Feed).

As in years past, Cs-137 and Sr-90 were observed in goat milk.

Based on facts presented in Section 6.0, examination of effluent release totals for these isotopes showing insufficient quantities to account for such measurements, the lack of any positive indications of Sr-89 and Cs-134 which are chemically similar and generally release in comparable quantities, and the trend since the early 1960's showing consistent declining presence of Cs-137 and Sr-90, it is concluded their presence is the result of residual radioactivity deposited into the environment from past nuclear weapons testing fallout.

4-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station No station related 1-131 was seen in this media. For over a decade, no detectable levels of I-131 have been seen in goat milk samples except for the period immediately following the Chernobyl accident.

Strontium analysis frequency is quarterly. The samples collected within each quarter from each sample location are composited and analyzed at the end of each quarter.

4.9. Pasture Grass and Feed (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. Feed (e.g., hay) is sampled whenever pasture grass is unavailable.

No station effects were seen in pasture grass and feed samples.

Similar to that observed in goat milk, the Cs-137 values at indicator and control locations are comparable and would indicate that the levels observed are the result of residual weapons testing fallout.

4.10. Well Water Well water samples are not required by the REMM. Data from 1973-1985 showed the lack of detectable station activity in this media. The sampling of well water was discontinued in 1985.

4.11. Reservoir Water 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. In the event of widespread station related contamination, these samples may be collected.

4.12. Fruits and Vegetables (Table 12)

Consistent with past years, this media did not show any station effects. Naturally occurring K-40 was detected in all samples.

4-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 4.13. Broad Leaf Vegetation (Table 13)

Consistent with past years, this media did not show any station effects. Positive indications of Cs-137 were observed in three samples, each from different locations and different times in the year. These levels are comparable to those observed in past years and are due to fallout.

This media can show early and sensitive indication of releases from the station from both unplanned releases and normal operations.

Therefore, to enhance program monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, April - October, even though requirements are to collect twice a year.

Due to minor fuel pin failure in Unit 2, elevated concentrations of iodine were measured in station effluents at the end of April. Extra samples of milk, pasture grass and broad leaf vegetation were collected in an attempt to measure possible environmental presence of iodine from these releases. Locations for sampling were selected based on the prevailing winds during the station measured releases. None of the special samples nor the normal air iodine samples collected show any detectable I-131 in the environment.

The analysis of this media for strontium was discontinued in 1997.

Data from past years has shown the lack of station related strontium activity in this media.

4.14. Seawater (Table 14)

Samples from the vicinity of discharge (32) are continuous composites collected monthly and samples from Giants Neck (37C) are quarterly composites of weekly grab samples. Millstone increased the required sampling frequency for composite samples from the vicinity of discharge to a monthly basis to increase monitoring effectiveness.

Naturally occurring K-40 was seen in all samples. Station related tritium (H-3) was observed from the vicinity of discharge sample location (32) during various periods throughout the year. Figure 4.14-1 shows a ten year trend of tritium releases in Millstone liquid effluents versus measured environmental concentrations from the vicinity of discharge location. As can be noted from the figure, since the restart of Unit 3 in 1998 and Unit 2 in 1999, tritium releases in liquid effluents have risen to levels at or above 4-8

ones Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Uperating Ker port MMUI Millstone Station those observed during the pre-shutdown period. Tritium is generated during operation from fission and neutron reactions.

Tritium builds up in the reactor coolant in each fuel cycle.

Measured plant related levels of H-3 insea water from the immediate vicinity of discharge have been observed throughout the operation of Millstone's nuclear units. The sample is taken directly from liquid effluent flow prior to dilution into Long Island Sound.

Dilution studies performed on this discharge have determined that a dilution factor of 3 is appropriate to estimate concentrations immediately outside the quarry within a near-field area. After dilution, the concentration of tritium expected in the immediate area of the Sound would approach undetectable levels at the required LLD.

Figure 4.14-1 MILLSTONE LIQUID H-3 RELEASE VERSUS SEA WATER CONC.

I I 600 600 l 0TYear Historical Trend I 1500- l Curies 1400 -- ll uCi/ci 1300 -

1200 1100 1000 900 800 700 1 At \

700 400- A412A a m p 200 100 0

I _~ C CC CC vC CC CC 10 C (D CC CC C CC 0 CC 8 0 0 I 4.15. Bottom Sediment (Table 15)

Similar to last year, Cs- 137 was detected in one sample from Golden Spur (30X). The Golden Spur area is a fresh water area and the levels of Cs- 137 at this location are comparable to those observed in past river water sediments taken up the Connecticut River. Due to this and the relative distance and direction of the Golden Spur location, the Cs- 137 detected is not plant related. No 4-9

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station indications of plant related activity were observed in any of the bottom sediment samples in 2001.

4.16. Aquatic Flora (Table 16)

Sampling of this media provides useful information because it is very sensitive to station discharges. However, no station related radioactivity was detected in aquatic flora in 2001.

4.17. Fish (Tables 1 7A and 1 7B) 4.17.1. Flounder (Table 17A)

The activity in Flounder is the same as that seen for the past decade. No activity was observed except for the naturally occurring radionuclides.

4.17.2. Fish - Other (Table 17B)

The activity in other fish is the same as that seen for the past decade. No activity was observed in this media except for naturally occurring radionuclides, including samples taken from within the quarry.

4.18. Mussels (Table 18)

Like last year, this sampling media showed no station related radioactivity at all locations.

4.19. Oysters (Table 19)

All locations, except for the quarry, utilize stocked oysters. Trays are kept at these sampling areas to guarantee samples and facilitate sample collection. Native oysters are sampled at the quarry (location 40X) which is an extra location.

Station related Ag-l Om was observed in samples from within the station discharge area (locations 32 and 40X1. In general, the quarry oysters show the highest activity. Although location 32 is labeled as vicinity of the discharge, it is actually at the end of the quarry. No station related activity was observed in samples from beyond the station discharge area.

4-10

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station In years past, high levels of Zn-65 were typically observed in oysters caused by their distinct capacity to accumulate zinc.

Studies have shown that oysters can accumulate as much as 50 times or more the amount of zinc compared to most other seafoods (Wolfe, 1979). A remarkable dependency exists between the Zn-65 concentration measured in the native quarry oysters and the amount of Zn-65 discharged into the environment. However, since the permanent shutdown of Millstone Unit 1 in 1996, the discharges of Zn-65 in liquid effluents have dropped off dramatically. In 2001, no Zn-65 was released in liquid effluents and no Zn-65 was detected in oysters. Figure 4.19-1, shows the incredible historical trend that exists between Zn-65 releases and measured concentrations in quarry oysters. The decreasing trend in effluent radioactive releases is apparent in both the curies released and the measured concentrations in oysters.

Figure 4.19-2 shows a similar trend of Ag-11Om concentration in quarry oysters compared with liquid effluent curies of Ag-i lOm discharged. Again, the dependency between Ag-i lOim discharged and the Ag-lOm concentration measured in the native quarry oysters is apparent. The historical sensitivity between station measured effluent discharges of Zn-65 and Ag-liOm when compared to environmental measured concentrations has provided a basis for Millstone to adjust the bio-accumulation factors for Zn-65 and Ag-110in used in the standard industry effluent dose consequence codes. See Section 5 of this year's and previous years' Annual Radiological Environmental Operating Reports for a comparison of the two methods which has allowed for such adjustments in the past (i.e., dose from the station's measured radioactive discharges input into conservative models versus actual measurements of the concentrations of radioactivity in environmental media to calculate annual dose commitment from consumption).

Because no station activity was observed at locations beyond the station discharge area and since the two locations in the quarry are on-site and not available for public use, the actual concentration of radionuclides in oysters available for public consumption is much less. The near-field dilution factor for liquid discharges from the Millstone quarry discharge is a factor of 3.

The dose consequence of the station related radioactivity via this pathway is discussed in Section 5.0.

4-11

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 4.20. Clams (Table 20)

Occasionally this media indicates the presence of station related radioactivity.

No station related radioactivity was observed in any of the clam samples taken in 2001.

4.21. Scallops Scallops are not required by the REMM. However, attempts are made to sample this media to confirm station effects because scallops are available for public consumption. No scallop samples were available in 2001.

4.22. Lobsters (Table 22)

Like last year, no station related radioactivity was detected in this sample media in 2001.

4-12

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Figure 4.19-1 Zn-65 COMPARISON Curies Curies Discharged vs. Native Oyster Conc. Conc. (pCi/gram) 0.1 - 1UU 7~ KL- I I

+ Curies Discharged Oyster Conc. I 0.01 0.001 7?

At I 1 1 1 1 11u l _ rall IV w-w^1

- 10

- 1.

0.0001 - -

0.1 n nnnni u.uuuu,

-_ _w - - 0.01 0.000001 .................

0 0 N0 0) 0 Y

4 0)

.. I .......

. <0 N (0

I...........

0) 0

- 0.001 (w0 (0 ( (0 0) 0) 0) 0) OM 0 0 0) 0 0 0 a aa a 8 _ aa a)_9 Quarter Figure 4.19-2 Ag-lOrm COMPARISON Curies Curies Discharged vs. Native Oyster Conc. Conc. (pCi/gram) 0.1 100 4 s

/t C A * +~ Curies DischargeI.

oOyster Conc.

0.01 0.001 VvF 10 1

0.0001  ?"I 0.1

_ I _ _ .AA 0.00001 0.01 0.000001 0.001 a a a a a a a a a a a a a a Quarter 4-13

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

5. OFFSITE 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 calculations of direct dose from sources onsite and 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 calculation of the maximum dose consequences to individuals. The results of these computations have been submitted to the NRC in the Radioactive Effluent Release Report written in accordance with the Radiological Effluent Monitoring Manual,Section I.F.2. This method, which is usually conservative (i.e., computes higher doses than that which actually occur) has the advantage of approximating an upper bound to the dose consequences. This is important in those cases where the actual dose consequence cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques.

The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., fish, shellfish) and then computes the dose consequences resulting from the consumption of these foods.

The results of both methods are compared in Table 5.1 for those pathways where a potential dose consequence exists and a comparison is possible.

The doses presented in this table are calculated at the location of maximum effect from the station effluents for that pathway and for the critical age group. For example, the external gamma dose from gaseous effluents is calculated for the site boundary location which is not only the nearest but also has the greatest directional wind frequency and fish and shellfish doses are calculated assuming they are from an area within 500 feet of the station discharge.

Summarizing the data in Table 5.1:

MAXIMUM TOTAL INDIVIDUAL DOSES:

WHOLE BODY = 0.08 mrem GI(LLI) = 0.02 mrem The organ GI(LLI) dose is essentially all attributable to the liquid pathway.

A significant portion of the whole body dose is due to a conservative determination of dose (-0.06 mrem) to the nearest resident as a result of direct radiation from on-site radioactive waste operation/storage facilities and continuous occupancy. The whole body and maximum organ dose attributable from station effluents includes conservative assessments using Method 2.

5-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Since the maximum dose consequence to an individual is at the location of highest dose consequence, doses will be less for all other locations. The average whole body dose to an individual within 50 miles historically is on the order of 1000 times less than the maximum individual whole body dose.

In order to provide perspective on the doses in Table 5.1, the standards for 2001 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 to any other organ. These standards are a fraction of the normal background radiation dose of approximately 284 mrem per year and are designed to be inconsequential in regard to public health and safety. Since station related doses are even a smaller fraction of natural background, they have insignificant public health consequences. In fact, the station related doses to the maximum individual are less than 10% of the variation in natural background in Connecticut.

5-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS MILLSTONE POWER STATION 2001 Annual Dose (millirem) 5-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE 5.1 (Cont.)

COMPARISON OF DOSE CALCULATION METHODS MILLSTONE POWER STATION 2001 Annual Dose (millirem) 5-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Notes:

1. Except for direct dose, method 1 uses measured station discharges and meteorological data as input parameters to transport-to-man models which conservatively calculate dose to people; method 2 uses actual measured concentrations in environmental media to estimate the dose.
2. 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.
3. ND - Not Detectable - No station related activity could be detected above natural background or above the minimum detectable level (MDL).
4. The dominant source of direct dose from the station is from operation/storage of radioactive waste facilities. Storage of radioactive waste in areas designated onsite is limited by design and operation to ensure that the maximum direct dose from each area at the site boundary does not exceed one millirem. Actual exposure from each throughout the year was maintained much less than this operational limit.

Each facility is monitored onsite by the Radiation Protection Department using TLDs. The exposure measured for each facility TLD was corrected for distance to the nearest site boundary residence. The resultant exposure was conservatively multiplied by 1.5 to account for skyshine. These maximum estimated doses from each facility were summed for a cumulative site commitment of approximately 0.06 millirem.

5. Measured dose was derived from monthly TLD readings. There are two residences which qualify as the closest residence, each has a TLD near enough to use as an estimate to each residence. The one with the highest average dose rate was used to estimate the direct dose to the closest residence. A background dose rate was subtracted. This background was derived from the average of the five control TLD locations. This method is very conservative assuming natural exposure influences, such as granite, are actually plant related exposure. This method provides a bounding high value. The exposure measurements of the select indicator locations are influenced by natural background exposure differences caused by the many granite out-croppings typical of the Millstone area. Historical data evaluation has shown that TLD sample locations in the vicinity of granite can be dramatically influenced by natural radioactivity contained within the granite.
6. GI (LLI) - Gastrointestinal Tract - Lower Large Intestine.
7. ND - Not Detectable - measurements for 2001 show no detectable station related acitivity. TLD's cannot detect levels which are such a small fraction of natural background.
8. Based on measured levels in vicinity of discharge and quarry oysters. A measured near field dilution factor of 3 was used to adjust for the fact that these oysters are on-site and inaccessible to the public. This factor adjusts the measured on-site concentration to that which could occur to a public accessible off-site location after dilution of the effluent by the Long Island Sound.

5-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station

6. DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many factors. Those factors depend upon the media being 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 of land management (e.g., irrigation), pasturing habits of animals, and type of pasturage. Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.

Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk samples. This is an important problem because this product is widely consumed and fission products readily concentrate in this media. Some of these fission products, such as I-131 and Sr-89 are relatively short-lived. Therefore they result from either station effluents, nuclear weapons tests or nuclear incidents (e.g. Chernobyl). Sr-89's lifetime is longer than I-131's, therefore it must be remembered that it will remain around for much longer periods of time. Problems are caused by the long-lived fission products, Sr-90 and Cs-137. These isotopes are still remaining from the high weapons testing era of the 1960's. This results in measurable amounts of Sr-90 and Cs-137 appearing in milk samples. Distinguishing between this "background" of fallout activity and station effects is a difficult problem.

In reviewing the historical and present Sr-90 and Cs-137 measured in cow and goat milk in the areas around Millstone 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 station. The station's effluents might at first appear to be responsible.

However, the investigation of the following facts proves this conclusion wrong.

(1)IThe stations accurately measure many fission products, including Sr-90 and Cs-137 in their releases. Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated. These calculations (generally conservative, see Section 5.0) show that insufficient quantities 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 station 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-6-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 90 was station related. No station related Sr-89 has been detected in milk samples.

(3) Similar to Sr-89, Cs-134 can be used as an indication of station related Cs-137. Although not as conclusive as Sr-89, the lack of any measurable Cs-134 in any of the milk samples suggests that the Cs- 137 is not station related. This is further confirmed by the evaluation of the air particulate data. The only occurrences of detectable Cs-134 in milk resulted from the Chemobyl incident.

(4) Dairy milk sampling in Connecticut began in the 1960's, several years prior to nuclear station operation. The highest levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2), were measured in the years prior to station operation. Samples taken in the immediate station areas have always shown higher levels of weapons related fallout than samples taken from the Central Connecticut Region (CT Pooled Milk). Radioactivity levels of fallout related Sr-90 and Cs-137 have decreased significantly since the 1964 Nuclear Test Ban Treaty due to decay.

(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, in the past 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.

(6) In the past when a goat farm operated near Millstone (2.0 Mi - ENE),

the highest levels of Sr-90 and Cs-137 were typically indicated. This same farm 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 had the ability for higher reconcentration. Special studies performed at this and other farms failed to find any link to the station.

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.

Dominion 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 maximum individual from any station related activity has been performed and shows that in all cases the exposure is insignificant.

The Connecticut Department of Environmental Protection performs an independent check on certain environmental program analyses. The results of their analyses are comparable to the results from this 6-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station program's analyses. These comparisons can be used as a cross-reference to verify measured station activity.

6-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station Figure 6-1 Strontium-90 in Milk pCi/liter 61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 99 Year Figrure 6-2 Cesium-137 in Milk 1Eciflilter 0 -r 140 C ooled Milk 120 I I -in-- Haddam area Milk

-A,-- Millstone area Milk 100 80 60 40 F1*,4 - ~ A-20 - - -

U T rIrIr~rI FUU I.II~ IIII. Irr~-

61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 99 Year Dairy milk is no longer available in the Millstone area, Haddam Neck no longer collects milk, and CT Pooled milk has not been collected by the State of CT since 1994. Graphs provided to, show historical trends.

CY Start-up occurred: July 24, 1967 MIP1Start-up occurred: October 26,1970 MIP2 Start-up occurred: October 17, 1975 MIP3 Start-up occurred: January 23, 1986 6-4

Dominion Nuclear Connecticut, Inc. &entalOperating Report 2001 Annual Radiological Environmn Millstone Station APPENDIX A LAND USE CENSUS FOR 2001-A-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE A-1 Dairy Cows Within 15 miles of Millstone Point- 2001 Direction Distance Name and Address # of Cows N 14 M Kevin Dubicki 62 Wawecus Farm Dairy 226 Wawecus Hill Rd.

Norwich, CT 06360 NE 13.5 M Henry Morgan 65 Morgan Farm 512 Shewville Rd.

Ledyard, CT 06339 WNW 11M John Tiffany II 100 Tiffany Farms 156 Sterling City Road Lyme, CT 06371 NNW 11.5 M Eugene Wilczewski 54 Salem Valley Farm Dairy 200 Darling Road Salem, CT 06420 NNW 13 M Stuart Gadbois 220 Maegog Farms 40 Old Colchester Rd.

Salem, CT 06420 Note: No cowfarms on this list are used for sampling, allfarms are greaterthan ten miles distancefrom plant.

A-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE A-2 Dairy Goats Within 20 miles of Millstone Point- 2001 Direction Distance Name and Address # of Goats N 2M Mrs. John Mingo 6 69 Spithead Road Waterford, CT 06385 LOCATION 21 NNE 5.2 M Allen Moran 8 122 Dayton Rd.

Waterford, CT 06385 LOCATION 22 NE 10.6 M Laura Behan

  • 189 Quaker Farm Rd.

Mystic, CT 06355 NE 8.6 M Arthur Hiles 0 2 Daboll Rd.

Groton, CT 06340 ENE 2M Berton Smith 0 16 Braman Rd.

Waterford, CT 06385 ENE 13.1 M Phyllis Borges 1 212 Deans Mill Road Stonington, CT 06378 ENE 15.3 M Veronica Ploof 2 73 Palmerneck Road Pawcatuck, CT 06379 ENE 16.4 M Grace White 8 1 Providence NL Tpk.

North Stonington, CT 06359 WNW 18.1 M Virginia Marshall 2 178 Old Chester Rd.

Haddam, CT 06438

  • Unable To Contact As Of This Time
    • Control station listed, distance greaterthan 20 miles from Millstone A-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE A-2 Dairy Goats Within 20 miles of Millstone Point- 2001 Direction Distance Name and Address # of Goats NW 17.3 M Kelsey Humble 5 98 Ballahack Rd.

East Haddam, CT 06423 NNW 18.5 M Theodore Powell 15 31 O'Connell Road Colchester, CT 06415 NNW 29 M** Kathy Waters 25 215 Burnt Hill Road Hebron, CT 06248 LOCATION 24 N 20 M Babe Farm 1 13 Jurczyk Rd.

North Franklin, CT 06264 NNW 19.8 M Russell Baker

  • 187 North Moodus Rd.

East Haddam, CT 06423

  • Member of the American Dairy Goat Association; unable to contact as of this time.

A-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE A-3 2001 Resident Survey!

Distance to Downwind Closest Resident Direction (meters)

N 1500 NNE 860 NE 790 ENE 1580 E 1500 ESE 1690 SE N/A SSE N/A S N/A SSW N/A SW 3700 WSW 3190 W 2870 WNW 2470 NW 2110 NNW 780

  • N/A - not applicable(over water sectors).

e Distanceswere measured in 2001 using GPS.

A-S

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station TABLE A-4 2001 Garden Survevo Distance to Downwind Closest Garden Direction (meters)

N 1495 NNE 875 NE 745 ENE 1605 E 1505 ESE 1865 SE N/A SSE N/A S N/A SSW N/A SW 3845 WSW 3325 W 2955 WNW 2475 NW 2295 NNW 1255

  • N/A - not applicable (over water sectors).

e Distances were measured in 2001 using GPS.

A-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station APPENDIX B DNC fA PROGRAM B-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station INTRODUCTION DNC maintains a independent non-required 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.

DNC QA PROGRAM Appraisals are conducted on services provided by the primary (Duke) radioanalysis contractor. During 2001 the program requirement to conduct an appraisal of the primary contractor laboratory was satisfied by participation in the annual audit by the Laboratory Quality Control Audit Committee (LQCAC), a joint effort by clients serviced by the contractor. The primary contractor was also audited by other organizations such as the Millstone Nuclear Oversight Department.

This program includes spikes of various sample media, duplicate samples, and TLD spikes. Sample spikes are a check on the accuracy of results of the contractor's radioanalyses. Duplicate samples test the contractor's precision, or reproducibility of results, by comparing analytical results of split samples.

The number and type of DNC QA Program quality control samples are defined in DNC Radiological Engineering Instruction RAB B-3, "Quality Control of Radiological Environmental Monitoring Program Sample Analyses."

Starting in 2001, Millstone assumed the role of collection and processing of environmental samples in support of the Millstone REMP. This included the implementation of the independent non-required QA program. New personnel, procedures, facilities, equipment and processes were used in the spiking of environmental sample media in 2001. This presented conditions for human performance problems of unfamiliar tasks, qualification, training and coaching. Growing pains were experienced as the spiking program progressed throughout the year. Investigations into acceptance criteria failures for various sample media uncovered barrier failures of the DNC internal processes governing spike preparation, storage, calculations and technique. Spike data collected as part of this extra effort throughout the year provided little if any valuable information on laboratory accuracy due mainly to the lack of confidence in the spiking program. Corrective actions taken due to these failures have or are in progress to prevent recurrence of problems and mistakes. Continuation of this program in 2002 is expected to provide useful quality assurance information on laboratory performance as it has in past years.

The analysis of duplicate samples and TLD spikes did provide valuable information on laboratory performance in 2001 even though the spiking of environmental media did not. Blind duplicate samples of oysters collected within 500 feet of discharge which typically contain trace quantities of plant B-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station within 500 feet of discharge which typically contain trace quantities of plant related radioactivity are sent quarterly to test laboratory reproducibility.

Spike testing of environmental TLDs involves the exposure of four TLDs each calendar quarter. Readouts of the spiked TLDs are compared to the known radiation exposure. The comparison results must satisfy acceptance criteria in DNC Radiological Engineering Instruction 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 The DNC QA Program is a "good practice" effort to monitor REMP radioanalysis performance. Other QA programs performed in 2001 and credited as required QA practices include:

1. Duke's internal QA program. In addition to the DNC 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 interlaboratory comparison program is required by station Technical Specifications. The Analytics comparison satisfies this requirement.
3. Duke's participation in National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP) and DOE's Environmental Measurements Laboratory QAP Program. Duke participates in these interlaboratory QA programs because of other clients' needs, not because of nuclear power station environmental sample analyses RESULTS OF QA PROGRAMS FOR CONTRACTOR SAMPLE RADIOANALYSES The DNC and other QA Programs indicated that Duke's environmental radiological analysis program was adequate in 2001. For the DNC QA program, a total of 84 QA samples and sixteen spiked TLDs were submitted to Duke in 2001 and analyzed. All QA TLDs were within the acceptance criterion of 20% of the spiked value. Four of the QA samples were duplicate oyster samples. All duplicate oyster samples were within the acceptance criterion.

Even though the spiking of environmental media which is the bulk of the 84 analyses performed in 2001 did not provide any useful data in regard to laboratory performance (see discussion above), it did provide opportunities to observe the laboratories willingness to investigate proposed problems and their professionalism and desire to provide high quality results.

B-3

~~~- - -A Annual Radiological Environmental Operating Report 2001 Dominion Nuclear Connecticut, Inc.

Millstone Station APPENDIX C

SUMMARY

OF INTERLABORATORY COMPARISONS C-1

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station 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 in terms of sample number, matrices, and nuclides. It was modified to more closely match the media mix presently being processed by DESEL and includes:

. milk for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses once per quarter,

  • milk for Sr-89 and Sr-90 analyses during the 3rd quarter,

. water for gamma (10 nuclides) and low-level (LL) Iodine-131 analyses during the 1st and 3rd quarters,

  • water tritium analysis during the 2nd quarter,
  • air filter for gamma (9 nuclides) analyses during the 2nd quarter, and
  • air filter for gross beta analysis during the 1st and 3rd quarter.

In addition to the Analytics Intercomparison Program, DESEL also participates in two other intercomparsion programs which include radionuclides and media similar to those required by the Millstone program.

These two programs are the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP) and the U.S. DOE Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP).

RESULTS Intercomparison program results are evaluated using DESEL's internal bias acceptance criterion. The criterion is defined as within 25% of the known strontium value for samples containing both Sr-89 and Sr-90 and within 15%

of the known value for other radionuclides, or within two sigma of the known value. Any sample analysis result which does not pass the criteria is investigated by DESEL.

Analytics Intercomparison Program results are included on pages C-3 through C-8 for the fourth quarter of 2000 through the third quarter of 2001.

A total of 101 samples were analyzed with 98 passing criteria, a 97% success rate. Investigation have been completed or are ongoing for the three failed sample analyses (see footnotes in tables).

C-2

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Number Year M ia Nuc.*d Units. Value Value A nali Evaluation E2477-162 4th/00 Filter Sr-89 pCi 59.57 85 0.70 Non-Agreement*

E2477-162 4th/00 Filter Sr-90 pCi 42.4 41 1.03 Agreement E2478-162 4th/0O Filter Gross Alpha pCi 20.27 21 0.97 Agreement E2478-162 4th/GO Filter Gross Beta pCi 136.07 114 1.19 Agreement E2479-162 4th/00 Water H-3 pCi/L 9656.67 10082 0.96 Agreement E2480-162 4th/00 Milk 1-131 pCi/L 86.23 85 1.01 Agreement E2480-162 4th/GO Milk 1-131 LL pCi/L 88.87 85 1.05 Agreement E2480-162 4th/00 Milk Ce-141 pCi/L 361.63 356 1.02 Agreement E2480-162 4th/GO Milk Cr-51 pCi/L 521.33 503 1.04 Agreement E2480-162 4th/00 Milk Cs-134 pCi/L 84.27 85 0.99 Agreement E2480-162 4th/GO Milk Cs-1 37 pCi/L 203.77 199 1.02 Agreement E2480-162 4th/GO Milk Co-58 pCi/L 79 76 1.04 Agreement E2480-162 4th/00 Milk Mn-54 pCi/L 161.5 152 1.06 Agreement E2480-162 4th/00 Milk Fe-59 pCi/L 92.6 82 1.13 Agreement E2480-162 4th/GO Milk Zn-65 pCi/L 147.63 148 1.00 Agreement E2480-162 4th/00 Milk Co-60 pCi/L 184.63 184 1.00 Agreement

  • CR 01-16 Issued, Sr-89:90 ratio below DESEL standard 1:1 requirement.

C-3

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Civilizationgua em :~;-U Ratio S.mp.e u rt S...

. ............ r.. K E2592-162 1st/01 Water 1-131 pCi/L 88 90 0.98 Agreement E2592-162 1stV01 Water 1-131 LL pCi/L 89 90 0.99 Agreement E2592-162 1st/01 Water Ce-141 pCi/L 100 94 1.06 Agreement E2592-162 1st/O1 Water Cr-51 pCi/L 236 242 0.98 Agreement E2592-162 1st01 Water Cs-134 pCi/L 120 129 0.93 Agreement E2592-162 1st/01 Water Cs-137 pCi/L 97 102 0.95 Agreement E2592-162 1stV01 Water Co-58 pCi/L 48 48 1.00 Agreement E2592-162 1st/01 Water Mn-54 pCi/L 103 101 1.02 Agreement E2592-162 1st/01 Water Fe-59 pCi/L 88 84 1.05 Agreement E2592-162 1st/01 Water Zn-65 pCVL 187 186 1.01 Agreement E2592-162 1st/01 Water Co-60 pCi/L 144 147 0.98 Agreement E2592-162 Ist/01 Water Gross Alpha pCi/L 40 39 1.03 Agreement E2592-162 1st/01 Water Gross Beta pCi/L 300 268 1.12 Agreement E2597-162 1st/01 Water Am-241 pCi/L 5.6 6.0 0.93 Agreement E2597-162 1st/01 Water Pu-238 pCi/L 7.2 7.5 0.96 Agreement E2597-162 I st/O1 Water Pu-239 pCi/L 5.5 5.5 1.00 Agreement E2597-162 1st/01 Water Np-237 pCi/L 9.6 7.9 1.22 Non-Agreement*

E2597-162 I st/01 Water Cm-244 pCi/L 5.6 6.3 0.89 Agreement E2597-162 1st/01 Water Ra-226 pCi/L 51 50 1.02 Agreement E2597-162 1st/01 Water Ra-228 pCi/L 63 63 1.00 Agreement

  • CR 01-41 Issued. Np-237 failed high due to glassware contamination.

C-4

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION SaVmpnle -iQuarerl l SampleS i:A  ;;;~; b-X:

Si~

Kn~own DS tt:SN :tt~~+:;; ;::i;:Reported;::

Numbe Yelar Medi intNucid Vau Vau Anlyic Evauaio E2595-162 1st/01 Milk 1-131 pCi/L 78 77 1.01 Agreement E2595-162 1st/01 Milk I-131 LL pCi/L 74 77 0.96 Agreement E2595-162 1st/01 Milk Ce-141 pCi/L 166 162 1.02 Agreement E2595-162 1st/01 Milk Cr-51 pCi/L 455 418 1.09 Agreement E2595-162 1st/01 Milk Cs-134 pCi/L 217 223 0.97 Agreement E2595-162 1st/01 Milk Cs-137 pCi/L 173 176 0.98 Agreement E2595-162 1st/01 Milk Co-58 pCi/L 86 82 1.05 Agreement E2595-162 I st/01 Milk Mn-54 pCi/L 185 175 1.06 Agreement E2595-162 1st/01 Milk Fe-59 pCi/L 151 146 1.03 Agreement E2595-162 1st/01 Milk Zn-65 pCi/L 328 322 1.02 Agreement E2595-162 1stV01 Milk Co-60 pCi/L 252 254 0.99 Agreement E2598A-1 62 1nd/01 Filter Gross Alpha pCi 30 30 1.00 Agreement E2598A-1 62 1nd/01 Filter Gross Beta pei 229 211 1.18 Agreement C-5

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION SupReported K E2670-162 2st/01 Milk 1-131 pCi/L 63 69 0.91 Agreement E2670-162 2stV01 Milk 1-131 LL pCi/L 66 69 0.96 Agreement E2670-162 2st/01 Milk Ce-141 pCi/L 165 163 1.01 Agreement E2670-162 2stV01 Milk Cr-51 pCi/L 228 224 1.02 Agreement E2670-162 2st/01 Milk Cs-134 pCi/L 131 134 0.98 Agreement E2670-162 2stV01 Milk Cs-137 pCi/L 128 121 1.06 Agreement E2670-162 2st/01 Milk Co-58 pCi/L 97 96 1.01 Agreement E2670-162 2stV01 Milk Mn-54 pCi/L 154 150 1.03 Agreement E2670-162 2stV01 Milk Fe-59 pCUL 91 88 1.03 Agreement E2670-162 2st/01 Milk Zn-65 pCi/L 180 182 0.99 Agreement E2670-162 2st/01 Milk Co-60 pCi/L 138 135 1.03 Agreement E2666-162 2nd/01 Filter Ce-1 41 pO 91 96 0.95 Agreement E2666-162 2nd/01 Filter Cr-51 pCi 130 132 0.98 Agreement E2666-162 2nd/01 Filter Cs-1 34 pO 74 79 0.94 Agreement E2666-162 2nd/01 Filter Cs-1 37 pCi 77 71 1.08 Agreement E2666-162 2nd/01 Filter Co-58 pCi 57 57 1.00 Agreement E2666-162 2nd/01 Filter Mn-54 pCi 99 88 1.13 Agreement E2666-162 2nd/01 Filter Fe-59 pCi 58 51 1.14 Agreement E2666-162 2nd/01 Filter Zn-65 pL 118 107 1.10 Agreement E2667-162 2nd/01 Filter Sr-89 pCi 89 84 1.06 Agreement E2667-162 2nd/01 Filter Sr-90 pCi 75 64 1.17 Agreement E2669-162 2nd/01 Water H-3 pCi/L 7007 7494 0.94 Agreement C-6

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION

.....0

..=

S.n

. ' -; ?A ' . .............

- 1 p1  ;

S. . 4 1,; ........

Smpe SaplQarer u l d ....... 0 eportied: Kn;own DSL Numbern Y~r ei Nuclde nitsau Vle Aalytcs Eauato E2809-162 3rd/01 Milk 1-131 pCUL 90 91 0.99 Agreement E2809-162 3rd/01 Milk 1-131 LL pCi/L 91 91 1.00 Agreement E2809-162 3rd/01 Milk Ce-141 pCi/L 131 121 1.08 Agreement E2809-162 3rd/01 Milk Cr-51 pCi/L 374 366 1.02 Agreement E2809-162 3rd/01 Milk Cs-134 pCi/L 157 160 0.98 Agreement E2809-162 3rd/01 Milk Cs-137 pCi/L 323 319 1.01 Agreement E2809-162 3rd/01 Milk Co-58 pCi/L 182 177 1.03 Agreement E2809-162 3rd/01 Milk Mn-54 pCi/L 211 205 1.03 Agreement E2809-162 3rd/01 Milk Fe-59 pCi/L 87 86 1.01 Agreement E2809-162 3rd/01 Milk Zn-65 pCi/L 261 254 1.03 Agreement E2809-162 3rd/01 Milk Co-60 pCi/L 274 266 1.03 Agreement E2806-162 3rd/01 Water 1-131 pCi/L 63 75 0.95 Agreement E2806-162 3rd/01 Water 1-131 LL pCi/L 62 75 1.05 Agreement E2806-162 3rd/01 Water Ce-141 pCi/L 96 191 1.00 Agreement E2806-162 3rd/01 Water Cr-51 pCi/L 275 230 0.95 Agreement E2806-162 3rd/01 Water Cs-134 pCi/L 113 128 0.95 Agreement E2806-162 3rd/01 Water Cs-1 37 pCi/L 234 218 1.03 Agreement E2806-162 3rd/01 Water Co-58 pCi/L 132 60 0.97 Agreement E2806-162 3rd/01 Water Mn-54 pCi/L 153 89 1.04 Agreement E2806-162 3rd/01 Water Fe-59 pCUL 66 54 1.03 Agreement E2806-162 3rd/01 Water Zn-65 pCi/L 184 134 0.97 Agreement E2806-162 3rd/01 Water Co-60 pCi/L 195 193 1.01 Agreement C-7

Dominion Nuclear Connecticut, Inc. Annual Radiological Environmental Operating Report 2001 Millstone Station DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION

, I

..S~r Number e .x.tr yoeari

~am~

edfia Nclie na Repr:teKnwESpELJ~~i e- Analytics Ealuai toValue E2805-162 3rd/01 Water Gross Alpha pCi/L 84 78 1.08 Agreement E2805-162 3rd/01 Water Gross Beta pCi/L 175 205 0.85 Agreement E2808-162 3rd/01 Filter Gross Alpha pCi 51 50 1.02 Agreement E2808-162 3rd/01 Filter Gross Beta PO 136 133 1.02 Agreement E2807-162 3rd/01 Water Sr-89 pCi/L 87 85 1.02 Agreement E2807-162 3rd/01 Water Sr-90 pCi/L 61 59 1.03 Agreement E2807-162 3rd/01 Milk Sr-89 pCi/L 121 75 1.61 Non-Agreement*

E2807-162 3rd/01 Milk Sr-90 pCi/L 49 50 0.98 Agreement

  • CR 02-01 issued. Sr-89 failed high, investigation ongoing.

C-8

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