BVY 11-040, Submittal of 2010 Annual Radiological Environmental Operating Report
| ML11132A135 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/09/2011 |
| From: | Wanczyk R Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 11-040 | |
| Download: ML11132A135 (122) | |
Text
En tergy Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 Robert J. Wanczyk Licensing Manager BVY 11-040 May 9, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
2010 Annual Radiological Environmental Operating Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28
Dear Sir or Madam,
In accordance with Vermont Yankee Technical Specification 6.6.E, attached is a copy of the 2010 Annual Radiological Environmental Operating Report. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 2010.
There are no new regulatory commitments being made in this submittal.
Should you have any questions concerning this submittal, please contact me at (802) 451-3166.
Sincerely,
[RJW/JTM] : Annual Radiological Environmental Operating Report - Year 2010 cc listing (next page) jT~5
BVY 11-040 / page 2 of 2 cc:
Mr. William Dean, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, Vermont 05354 Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-00 Massachusetts Department of Public Health Radiation Control Program Attn: Bob Walker, Director Schrafft Center - Suite 1 M21 529 Main Street Charlestown, MA 02129 John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 017021 DHHS/DPHS Dennis P. O'Dowd, Administrator Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504
ENTERGY - VERMONT YANKEE Vermont Yankee Nuclear Power Station ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Year 2010 Prepared by:/
Steph '
P Fs 0
Sr Environ en Specialist (REMP) bate Reviewed by:
./CN.5
/3-[2v It Stelhen C. McAvoy, ChemistryvSupervisor WDale Approved for Distribution:
/10*
/-S113 L-i effery A. -fardy, Chemistry Manager Date
TABLE OF CONTENTS
- 1.
IN TR O D U C T IO N.....................................................................................................................
1
- 2.
BACKGROUND RADIOACTIVITY...................................................................................
2 2.1 Naturally Occurring Background Radioactivity.............................................................
2 2.2 Man-Made Background Radioactivity..........................................................................
3
- 3.
GENERAL PLANT AND SITE INFORMATION.................................................................
4
- 4.
PROGRAM DESIGN...........................................................................................................
5 4.1 Monitoring Zones......................................................................................................
6 4.2 Pathw ays M onitored.....................................................................................................
6 4.3 Descriptions of Monitoring Programs............................................................................
7 5
RADIOLOGICAL DATA
SUMMARY
TABLES..............................................................
24
- 6.
ANALYSIS OF ENVIRONMENTAL RESULTS..............................................................
47 6.1 Sampling Program Deviations.....................................................................................
47 6.2 Comparison of Achieved LLDs with Requirements...................................................
48 6.3 Comparison of Results with Reporting Levels.............................................................
48 6.4 Changes in Sampling Locations.................................................................................
49 6.5 Data Analysis by Media Type.....................................................................................
49
- 7.
QUALITY ASSURANCE PROGRAM..............................................................................
86 7.1 AREVA NP INC. Environmental Laboratory.............................................................
86 7.2 Teledyne Brown Engineering-Environmental Services (TBE-ES) Laboratory.......
88 7.3 Entergy James A. Fitzpatrick Environmental Laboratory (JAFEL)............................
91
- 8.
LA N D U SE C EN SU S...............................................................................................................
112
- 9.
SU M M A R Y..............................................................................................................................
114
- 10.
R EFE R E N C E S..........................................................................................................................
116 i
LIST OF TABLES Table Title Page 4.1 Radiological Environmental Monitoring Program.............................
10 4.2 Radiological Environmental Monitoring Locations (Non-TLD).......................................................................
12 4.3 Radiological Environmental Monitoring Locations (TLD ).................................................................................
14 4.4 Environmental Lower Limit of Detection (LLD)
Sensitivity Requirements...................................................................
16 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples................................................................
17 5.1 Radiological Environmental Program Summary..............................
27 5.2 Environmental TLD Data Summary.................................................
44 5.3 Environmental TLD Measurements...................................................
45 6.1 Summary of Storm Drain System Sediment Sample Analyses........... 53 6.2 Summary of Storm Drain System Water Sample Analyses............... 54 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations............................................. 55 7.3.1 JAFEL Error Resolution...................................................... 93 7.3.2 JAFEL Numerical Results Tables........................................... 95 8.1 Land Use Census Locations................................................... 113 ii
LIST OF FIGURES Figure Title Pai 4.1 Environmental Sampling Locations in Close Proximity to the Plant..............................................................
18 4.2 Environmental Sampling Locations Within 5 Kilometers of Plant................................................................
19 4.3 Environmental Sampling Locations.
Greater than 5 Kilometers from Plant...................................................
20 4.4 TLD Locations in Close Proximity to the P lant...............................................................................................
2 1 4.5 TLD Locations Within 5 Kilometers of Plant..................................................................................................
22 4.6 TLD Locations Greater than 5 Kilometers from Plant...............................................................................................
23 6.1-6.27 Environmental Program Trend Graphs...................................................
59 iii
- 1. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Entergy-Vermont Yankee in the vicinity of the Vermont Yankee Nuclear Power Station (VYNPS) in Vernon, Vermont during the calendar year 2010. The analyses of samples collected indicated that no plant-generated radioactive material was found in any location off site. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. Measured values were several orders of magnitude below reportable levels listed in Table 4.5 of this report. Except for sample deviations listed in Section 6.1, all other samples were collected and analyzed as required by the program.
This report is submitted annually in compliance with plant Technical Specification 6.6.E. The remainder of this report is organized as follows:
Section 2: Provides an introductory explanation of background radioactivity and radiation detected in the plant environs.
Section 3: Provides a brief description of the Vermont Yankee Nuclear Power Station site and its environs.
Section 4: Provides a description of the overall REMP program design. Included is a summary of the Vermont Yankee Nuclear Power Station (VYNPS) Off-Site Dose Calculation Manual (ODCM) requirements for REMP sampling, tables listing all locations sampled or monitored in 2010 with compass sectors and distances from the plant, and maps showing each REMP location. Tables listing Lower Limit of Detection requirements and Reporting Levels are also included.
Section 5: Consists of the summarized data as required by the VYNPS ODCM. The tables are in a format similar to that specified by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Also included is a summary of the 2010 environmental TLD measurements.
Section 6: Provides the results of the 2010 monitoring program. The performance of the program in meeting regulatory requirements as given in the ODCM is discussed, and the data acquired during the year are analyzed.
Section 7: Provides an overview of the Quality Assurance programs used at AREVA Framatome ANP Environmental Laboratory, Teledyne Brown Engineering and Entergy James A. Fitzpatrick's Environmental Laboratory.
Section 8: Summarizes the requirements and the results of the 2010 Land Use Census.
Section 9: Gives a summary of the 2010 Radiological Environmental Monitoring Program.
1
- 2. BACKGROUND RADIOACTIVITY Radiation or radioactivity potentially detected in the Vermont Yankee environment can be grouped into three categories. The first is "naturally-occurring" radiation and radioactivity. The second is "man-made" radioactivity from sources other than the Vermont Yankee plant. The third potential source of radioactivity is due to emissions from the Vermont Yankee plant. For the purposes of the Vermont Yankee REMP, the first two categories are classified as "background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate.
2.1 Naturally Occurring Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate categories: "primordial radioactivity,"
"cosmogenic radioactivity" and "cosmic radiation." "Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth. Included in this category are the newly-formed "daughter" radionuclides descending from these original elements. A few of the more important radionuclides in this category are Uranium-238 (U-238), Thorium-232 (Th-232), Rubidium-87 (Rb-87), Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn-222). Uranium-238 and Thorium-232 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in air, and its daughter products are detectable on air sampling filters.
Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2).
The second sub-category of naturally-occurring radiation and radioactivity is "cosmogenic radioactivity."
This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree, in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Beryllium-7 (Be-7). Beryllium-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).
2
The third sub-category of naturally-occurring radiation and radioactivity is "cosmic radiation." This consists of high energy atomic and sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The majority of this radiation comes from outside of our solar system, and to a lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation.
Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection. This "direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs).
2.2 Man-Made Background Radioactivity The second source of "background" radioactivity in the Vermont Yankee environment is from "man-made" sources not related to the power plant. The most recent contributor (prior to year 2011) to this category was the fallout from the Chernobyl accident in April of 1986, which was detected in the Vermont Yankee environment and other parts of the world. A much greater contributor to this category, however, has been fallout from atmospheric nuclear weapons tests. Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. (A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.)
Atmospheric testing was conducted by the People's Republic of China as recently as October 1980. Much of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).
The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this fallout has decayed into stable elements, but the residual radioactivity is still readily detectable in environmental samples worldwide. The two predominant radionuclides are Cesium-i137 (Cs-I 37) and Strontium-90 (Sr-90). They are found in soil and in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides are also often detected in milk.
Other potential "man-made" sources of environmental "background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and industry. These, collectively, are insignificant on a global scale when compared to the sources discussed 3
above (natural and fallout).
- 3. GENERAL PLANT AND SITE INFORMATION The Vermont Yankee Nuclear Power Station is located in the town of Vernon, Vermont in Windham County. The 130-acre site is on the west shore of the Connecticut River, immediately upstream of the Vernon Hydroelectric Station. The plant site is bounded on the north, south and west by privately-owned land, and on the east by the Connecticut River. The surrounding area is generally rural and lightly populated, and the topography is flat or gently rolling on the valley floor.
Construction of the single unit 540 megawatt BWR (Boiling Water Reactor) plant began in 1967. The pre-operational Radiological Environmental Monitoring Program, designed to measure environmental radiation and radioactivity levels in the area prior to station operation, began in 1970. Commercial operation began on November 30, 1972. An Extended Power Uprate, conducted in 2006, resulted in the present generation capacity of 650 megawatts electric.
4
- 4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Vermont Yankee Nuclear Power Station (VYNPS) was designed with specific objectives in mind. These are:
To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.
To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
To verify the adequacy and proper functioning of station effluent controls and monitoring systems.
To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
The program was initiated in 1970, approximately two years before the plant began commercial operation. It has been in operation continuously since that time, with improvements made periodically over those years.
The current program is designed to meet the intent of NRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants; the NRC Radiological Assessment Branch Technical Position of November 1979, An Acceptable Radiological Environmental Monitoring Program; and NRC NUREG-0473, Radiological Effluent Technical Specifications for BWRs. The environmental TLD program has been designed and tested around NRC Regulatory Guide 4.13, Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications. The quality assurance program is designed around the guidance given in NRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment.
The sampling requirements of the REMP are given in the Off-Site Dose Calculation Manual Table 3.5.1 and are summarized in Table 4.1 of this report. The identification of the required sampling locations is given in the Off-Site Dose Calculation Manual (ODCM), Chapter 7. These sampling and monitoring locations are shown graphically on the maps in Figures 4.1 through 4.6 of this report.
5
The Vermont Yankee Chemistry Department conducts the radiological environmental monitoring program and collects all airborne, terrestrial and ground water samples. VYNPS maintains a contract with Normandeau Associates to collect all fish, river water and river sediment samples. In 2010, analytical measurements of environmental samples were performed at the Entergy Nuclear Northeast J. A.
Fitzpatrick N.P.P Environmental laboratory in Oswego, New York. TLD badges are posted and retrieved by the Vermont Yankee Chemistry Department, and were analyzed by the AREVA NP INC.
Environmental Laboratory in Westborough, Massachusetts.
4.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. Monitoring locations within the first zone are called "indicators." Those within the second zone are called "controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity and radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.
4.2 Pathways Monitored Four pathway categories are monitored by the REMP. They are the airborne, waterborne, ingestion and direct radiation pathways. Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:
Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radioiodine) Sampling Waterborne Pathways River Water Sampling Ground Water Sampling Sediment Sampling Ingestion Pathways Milk Sampling Silage Sampling Mixed Grass Sampling Fish Sampling Direct Radiation Pathway TLD Monitoring 6
4.3 Descriptions of Monitoring Programs 4.3.1 Air Sampling Continuous air samplers are installed at seven locations. (Five are required by the VYNPS ODCM.) The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing air through a 50 mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. The filters are collected on a weekly frequency and, to allow for the decay of radon daughter products, the analysis for gross beta radioactivity is delayed for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The weekly filters are composited by location at the environmental laboratory for a quarterly gamma spectroscopy analysis.
If the gross-beta activity on an air particulate sample is greater than ten times the yearly mean of the control samples, ODCM Table 3.5.1, Note c, requires a gamma isotopic analysis on the sample.
Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 /Ci/sec, weekly air particulate collection from the plant stack is required by ODCM Table 3.5.1, Note h.
4.3.2 Charcoal Cartridge (Radioiodine) Sampling Continuous air samplers are installed at seven locations. (Five are required by the ODCM Table 3.5.1.)
The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. A 60 cc TEDA-impregnated charcoal cartridge is located downstream of the air particulate filter described in Section 4.3.1 above. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. These cartridges are collected and analyzed weekly for 1-131.
i Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 ACi/sec, weekly charcoal cartridge collection from the plant stack is required, pursuant to ODCM Table 3.5.1, Note h.
4.3.3 River Water Sampling An automatic compositing sampler is maintained at the downstream sampling location by the Vermont Yankee Chemistry Department staff. Normandeau Associates personnel maintain the pump that delivers river water to the sampler. The sampler is controlled by a timer that collects a frequent aliquot of river water. An additional grab sample is collected monthly at the upstream control location. Each sample is analyzed for gamma-emitting radionuclides. Although not required by the VYNPS ODCM, a gross-beta analysis is also performed on each sample. The monthly composite and grab samples are composited by location by the contracted environmental laboratory for a quarterly tritium (H-3) analysis.
7
4.3.4 Ground Water (Deep Well Potable Water) Sampling Grab samples are collected quarterly from up to four indicator locations and one control location. Only one indicator and one control are required by the VYNPS ODCM. Each sample is analyzed for gamma-emitting radionuclides and H-3. Although not required by the VYNPS ODCM, a gross-beta analysis is also performed on each sample.
4.3.5 Sediment Sampling River sediment grab samples are collected semiannually from the downriver location and at the North Storm Drain Outfall by Normandeau Associates. Each sample is analyzed at an offsite environmental laboratory for gamma-emitting radionuclides.
4.3.6 Milk Sampling When milk animals are identified as being on pasture feed (May through October), milk samples are collected twice per month from that location. Throughout the rest of the year, and for the full year where animals are not on pasture, milk samples are collected on a monthly schedule. Three locations are chosen as a result of the annual Land Use Census, based on meteorological dispersion calculations. The fourth location is a control, which is located sufficiently far away from the plant to be outside any potential plant influence. Other samples may be collected from locations of interest.
Immediately after collection, each milk sample is refrigerated and then shipped to the contracted environmental laboratory. Each sample is analyzed for gamma-emitting radionuclides. A separate low-level 1-131 analysis is performed to meet the Lower Limit of Detection requirements in the ODCM.
Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on quarterly composited samples.
4.3.7 Silage (Chopped Corn or Grass) Sampling Silage samples are collected at the milk sampling location at the time of harvest, if available. The silage from each location is shipped to the contracted environmental laboratory where it is analyzed for gamma-emitting radionuclides. Although not required by the ODCM, the silage samples are analyzed for low-level I-131.
8
4.3.8 Mixed Grass Sampling At each air sampling station, a mixed grass sample is collected quarterly, when available. Enough grass is clipped to provide the minimal sample weight needed to achieve the required Lower Limit of Detection (LLD). The mixed grass samples are analyzed for gamma-emitting radionuclides. Although not required by the ODCM, the grass samples are analyzed for low-level 1-131.
4.3.9 Fish Sampling Fish samples are collected semiannually at two Connecticut River locations (upstream of the plant and in the Vernon Pond) by Normandeau Associates. The samples are frozen and delivered to the environmental laboratory where the edible portions are analyzed for gamma-emitting radionuclides.
4.3.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801 AS] and UD-814AS 1 calcium sulfate dosimeters are used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic screen cylinder. This cylinder is attached to an object such as a fence or utility pole.
A total of 40 stations are required by the ODCM. Of these, 24 must be read out quarterly, while those from the remaining 16 incident response (outer ring) stations need only be de-dosed (annealed) quarterly, unless an ODCM gaseous release limit was exceeded during the period. Although not required by the ODCM, the TLDs from the 16 outer ring stations are read out quarterly along with the other stations' TLDs. In addition to the TLDs required by the ODCM, more than thirteen are typically posted at or near the site boundary. The plant staff posts and retrieves all TLDs, while the contracted environmental laboratory (AREVA NP Inc. and now Stanford Dosimetry) provides processing.
9
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (as required by ODCM Table 3.5.1)*
Exposure Pathway Collection Analysis and/or Number of Routine Collection Analysis Sample Media Sample Sampling Frequency Analysis Frequency Locations Mode Type
- 1. Direct Radiation (TLDs) 40 Continuous Quarterly Gamma dose; Outer Each TLD Ring - dc-dose only, unless gaseous release Control was exceeded
- 2. Airborne (Particulates 5
Continuous Weekly Particulate Sample:
and Radioiodine)
Gross Beta Each Sample Gamma Isotopic Quarterly Composite (by location)
Radioiodine Canister:
Each Sample 1-131
- 3. Waterborne
- a. Surface water 2
Downstream.
Monthly Gamma Isotopic Each Sample Automatic Tritium (H-3)
Quarterly Composite composite Upstream: grab
- b. Ground water 2
Grab Quarterly Gamma Isotopic Each Sample Tritium (H-3)
Each Sample
- c. Shoreline Sediment 2
Downstream: grab Semiannually Gamma Isotopic Each Sample N. Storm Drain Outfall: grab 0
See ODCM Table 3.5.1 for complete footnotes.
10
TABLE 4.1, cont.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (as required by ODCM Table 3.5.1)*
Exposure Pathway Collection Analysis and/or Nominal Nominal Sample Media Number of Routine Sampling Collection Analysis Analysis Sample Mode Frequency Type Frequency Locations
- 4. Ingestion
- a. Milk 4
Grab Monthly Gamma Isotopic Each sample (Semimonthly 1-131 Each sample when on pasture)
- b. Fish 2
Grab Semiannually Gamma Isotopic on Each sample edible portions
- c. Vegetation Grass sample I at each air Grab Quarterly when Gamma Isotopic Each sample sampling available station Silage sample 1 at each milk Grab At harvest Gamma Isotopic Each sample sampling station
- See ODCM Table 3.5.1 for complete footnotes.
11
TABLE 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2010 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone(')
Stack (kin)
Plant I. Airborne AP/CF-I I River Sta. No. 3.3 I
1.9 SSE AP/CF-12 N. Hinsdale, NH I
3.6 NNW AP/CF-13 Hinsdale Substation I
3.1 E
AP/CF-14 Northfield, MA I
11.6 SSE AP/CF-15 Tyler Hill Road I
3.1 WNW AP/CF-21 Spofford Lake C
16.4 NNE AP/CF-40 Gov. Hunt House I
On-site
- 2. Waterborne
- a. Surface WR-II River Sta. No. 3.3 I
11.8 NNW
- b. Ground WG-1 I Plant Well I
0.2 On-site WG-12 Vernon Nursing Well I
0.3 On-site WG-14 Plant Support Bldg (PSB) Well I 0.3 On-site WT-14 Test Well 201 I
On-site WT-16 Test Well 202 I
On-site WT-17 Test Well 203 I
On-site WT-18 Test Well 204 I
On-site WG-22 Copeland Well C
13.7 N
- c. Sediment SE-1I1 Shoreline Downriver I
0.6 SSE SE-12 North Storm Drain Outfall I
0.1 E
12
TABLE 4.2, cont.
RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2010 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Pathway Stack
- 3. Ingestion
- a. Milk Station Code From Plant Zone(*)
Stack(km)
From Plant Station Description
- b. Fish
- c. Mixed Grass
- d. Silage TM-11 TM-14 TM-18 TM-20 TM-22 TM-24 FH-1 1 FH-21 TG-11 TG-12 TG-13 TG-14 TG-15 TG-21 TG-40 TC-1 I TC-14 TC-18 TC-20 TC-22 TC-24 Miller Farm Brown Farm Blodgett Farm Dunklee Farm (Vern-Mont)
Franklin Farm County Farm C
9.7 C
21.6 Vernon Pond Rt.9 Bridge I
I I
C River Sta. No. 3.3 N. Hinsdale, NH Hinsdale Substation Northfield, MA Tyler Hill Rd.
Spofford Lake Gov. Hunt House Miller Farm Brown Farm Blodgett Farm Dunklee Farm (Vern-Mont)
Franklin Farm County Farm I
C I
I I
I I
C I
0.8 2.2 3.6 5.5 0.68b) 11.8 1.9 3.6 3.1 11.6 3.1 16.4 0.8 2.2 3.6 5.2 w
S SE S
WSW N
SSE WNW NNE On-site W
S SE S
WSW I
I I
C C
9.7 C
21.6 N
(a) I = Indicator Stations; C = Control Stations (b) Fish samples are collected anywhere in Vernon Pond, which is adjacent to the plant (see Figure 4.1).
13
TABLE 4.3 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2010 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone*a)
(kin) (d)
Plant(d)
DR-I River Sta. No. 3.3 I
1.6 SSE DR-2 N. Hinsdale, NH I
3.9 NNW DR-3 Hinsdale Substation I
3.0 E
DR-4 Northfield, MA C
11.3 SSE DR-5 Spofford Lake C
16.5 NNE DR-6 Vernon School I
0.52 WSW DR-7 Site Boundary(c)
SB 0.28 W
DR-8 Site Boundary SB 0.25 SSW DR-9 Inner Ring I
1.7 N
DR-10 Outer Ring 0
4.5 N
DR-Il Inner Ring I
1.6 NNE DR-12 Outer Ring 0
3.6 NNE DR-13 InnerRing I
1.2 NE DR-1 4 Outer Ring 0
3.9 NE DR-15 Inner Ring I
1.5 ENE DR-16 Outer Ring 0
2.8 ENE DR-17 Inner Ring I
1.2 E
DR-18 Outer Ring 0
3.0 E
DR-19 Inner Ring I
3.7 ESE DR-20 Outer Ring 0
5.3 ESE DR-21 Inner Ring I
1.8 SE DR-22 Outer Ring 0
3.3 SE DR-23 Inner Ring I
2.0 SSE DR-24 Outer Ring 0
3.9 SSE DR-25 Inner Ring I
1.9 S
DR-26 Outer Ring 0
3.8 S
DR-27 Inner Ring I
1.1 SSW DR-28 Outer Ring 0
2.2 SSW DR-29 Inner Ring I
0.9 SW DR-30 Outer Ring 0
2.4 SW 14
TABLE 4.3, cont.
RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS VERMONT YANKEE NUCLEAR POWER STATION (TLD) IN 2010 Station Code DR-31 DR-32 DR-33 DR-34 DR-35 DR-36 DR-37 DR-38 DR-39 DR-40 DR-4 1(b)
DR-42 (b)
DR-43 (b)
DR_44(b)
DR-45 (b)
DR-46 (b)
DR-47 (b)
DR-48 (b)
DR-49 (b)
DR-50 (b)
DR-51 (b)
DR-52 (b)
DR-53 (b)
Station Description Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Gov. Hunt House Site Boundary Site Boundary Site Boundary Zone(a)
I 0
I 0I 0I 0I SB SB SB SB SB SB SB SB SB I
SB SB SB Distance From Plant (kM)(ýd) 0.71 5.1 0.66 4.6 1.3 4.4 2.8 7.3 3.1 5.0 0.38 0.59 0.44 0.19 0.12 0.28 0.50 0.82 0.55 0.35 0.26 0.24 0.21 Direction From Plant(d)
WSW WSW WNW W
WNW WNW NW NW NNW NNW SSW S
SSE SE NE NNW NNW NW WNW SSW W
SW WSW (a)
I = Inner Ring TLD; 0 = Outer Ring Incident Response TLD; C =Control TLD; SB = Site Boundary TLD.
(b)
This location is not considered a requirement of ODCM Table 3.5.1.
(c)
DR-7 satisfies ODCM Table 3.5.1 for an inner ring direct radiation monitoring location. However, it is averaged as a Site Boundary TLD due to its close proximity to the plant.
(d)
Distance and direction is relative to the center of the Turbine Building for direct radiation monitors.
15
TABLE 4.4 ENVIRONMENTAL LOWER LIMIT OF DETECTION (LLD) SENSITIVITY REQUIREMENTS Airborne Particulates Sediment Water or Gases Fish Milk Vegetation (pCi/Kg -
Analysis (pCi/1)
(pCi/m3)
(pCi/Kg)
(pCi/1)
(pCi/Kg) dry)
Gross-Beta 4
0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15
- If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
See ODCM Table 4.5.1 for additional explanatory footnotes.
16
TABLE 4.5 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulates or Gases Fish Milk Food Product Sediment Analysis Water (pCi/m 3)
(pCi/Kg)
(pCi/)
(pCi/Kg)
(pCi/Kg-dry)
(pCi/l)
H-3 20,000(a)
Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 3000(b)
Zn-65 300 20,000 Zr-Nb-95 400 1-131 0.9 3
100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) Reporting Level for drinking water pathways. For non-drinking water, a value of 30,000 pCi/liter may be used.
(b) Reporting Level for grab samples taken at the North Storm Drain Outfall only.
See ODCM Table 3.5.2 for additional explanatory footnotes.
17
Figure 4.1 Environmental Sampling Locations In Close Proximity to Plant 18
I N
\\NI>
N U I
I 1
Figure 4.2 Environmental Sampling Locations Within 5 Km of Plant 19 I
Figure 4.3 Environmental Sampling Locations Greater than 5 Km from Plant 20
NNW Fenceline OR-48~-5 W
ID\\ 4, eno Pn Mie AD.R-33, Fiur 4 ThermoluiecntDsmtr oain WSIn00 Close P i
t A
0 44
,/
R-31 A
Figure
- n.
Thermlmn en t Doimte Locations1 WSW C s Poiit o
ln 21
NNH DR-39 I
I il SW Miles 0.2.4.6.8 Figure 4.5 Thermoluminescent Dosimeter Locations Within 5 Km of Plant 22
1 I
N N
NN*'
NW N 17.
P D~K I
i l
6 4
Ait DR-IP2 DR-4 SL, Figure 4.6 Thermoluminescent Dosimeter Locations Greater than 5 Km from Plant 23
- 5. RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples that were collected during 2010. These results, shown in Table 5.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide. The units for each media type are also given.
In 2010, Vermont Yankee contracted with one laboratory for primary analyses of the environmental samples. A second laboratory was used to cross-check the first laboratory for selected samples and to analyze other samples for hard-to-detect radionuclides (such as Strontium-89 and 90).
The left-most column of Table 5.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2010 and the number of measurements which exceeded the Reporting Levels found in Table 3.5.2 of the VYNPS Off-site Dose Calculation Manual. The latter are classified as "Non-routine" measurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements as specified in the ODCM Table 4.5.1.
The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media. The target LLD for any analysis is typically 50 percent of the most restrictive required LLD.
Occasionally the required LLD may not be met. This may be due to malfunctions in sampling equipment or lack of sufficient sample quantity which would then result in low sample volume. Delays in analysis at the laboratory could also be a factor. Such cases, if and when they should occur, would be addressed in Section 6.2.
For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the Indicator stations, which are within the range of influence of the plant and which could be affected by its operation; (2) the Control stations, which are beyond the influence of the plant; and (3) the station which had the highest mean concentration during 2010 for that radionuclide. Direct radiation monitoring stations (using TLDs) are grouped into Inner Ring, Outer ring, Site Boundary and Control.
In each of these columns, for each radionuclide, the following statistical values are given:
The mean value of all concentrations, including those results that are less than the a posteriori LLD for that analysis.
The minimum and maximum concentration, including those results that are less than the a posteriori LLD. In previous years, data less than the a posteriori LLD were converted to zero for purposes of 24
reporting the means and ranges.
The "Number Detected" is the number of positive measurements.
A measurement is considered positive when the concentration is greater than three times the standard deviation in the concentration and greater than or equal to the a posteriori LLD (Minimum Detectable Concentration or MDC).
The "Total Analyzed" for each column is also given.
Each single radioactivity measurement datum in this report is based on a single measurement of a sample.
Any concentration below the a posteriori LLD for its analysis is averaged with those values above the a posteriori LLD to determine the average of the results. Likewise, the values are reported in ranges even though they are below the a posteriori LLD. To be consistent with normal data review practices used by Vermont Yankee, a "positive measurement" is considered to be one whose concentration is greater than three times its associated standard deviation, is greater than or equal to the a posteriori LLD and satisfies the analytical laboratory's criteria for identification.
The radionuclides reported in this section represent those that: 1) had an LLD requirement in Table 4.5.1 of the ODCM, or a Reporting Level listed in Table 3.5.2 of the ODCM, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of special interest for any other reason. The radionuclides routinely analyzed and reported by the environmental laboratory (in a gamma spectroscopy analysis) were: Th-232, Ba/La-140, Be-7, Co-58, Co-60, Cs-134, Cs-137, Fe-59, K-40, Mn-54, Zn-65 and Zr-95.
Data from direct radiation measurements made by TLDs are provided in Table 5.2. The complete listing of quarterly TLD data is provided in Table 5.3.
25
Radiological Environmental Program Summary 2010 Radiological Environmental Operating Report Vermont Yankee Table 5.11:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Sample Medium:
Air Particulate (AP)
Charcoal Cartridge (CF)
River Water (WR)
Ground Water (WG)
Sediment (SE)
Test Well (WT)
Milk (TM)
Silage (TC)
Mixed Grass (TG)
Fish (FH) 26
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS AIR PARTICULATE (PCI/CU.METER)
GROSS BETA 363 GAMMA BE-7 28 0.01 0.0105 (311/311)
(0.0010/0.0290)
N/A 0.1070 (24/24)
(0.0532/0.1542)
N/A 0.0361 (7/24)
(<0.0068/0.0962) 0.05 0.0030 (0/24)
(<0.0016/<0.0039)
K-40 CS-134 CS-137 0.0098 (52/52)
(0.0010/0.0240) 0.1190 (4/4)
(0.0715/0.1589) 0.0361 (1/4)
(<0.0077/0.0927) 0.0035 (0/4)
(<0.0028/<0.0042) 0.0024 (0/4)
(<0.0019/<0.0034) 0.0308 (0/4)
(<0.0207/<0.0398) 0.0060 (0/4)
(<0.0020/<0.0086) 0.0369 (0/52)
(<0.0210/<0.0583) 0.0112 (52/52)
(0.0020/0.0250) 0.1275 (4/4)
(0.0737/0.1542) 0.0559 (2/4)
(<0.0201/0.0913) 0.0035 (0/4)
(<0.0028/<0.0042) 0.0025 (0/4)
(<0.0022/<0.0030) 0.0332 (0/4)
(<0.0275/<0.0437) 0.0088 (0/4)
(<0.0022/<0.0122) 0.0369 (0/52)
(<0.0210/<0.0583) 12 INDICATOR N. HINSDALE, NH 3.6 KILOMETERS NNW OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 15 INDICATOR TYLER HILL ROAD 3.1 KILOMETERS WNW OF SITE 21 CONTROL SPOFFORD LAKE 16.4 KILOMETERS NNE OF SITE 15 INDICATOR TYLER HILL ROAD 3.1 KILOMETERS WNW OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 14 INDICATOR NORTHFIELD. MA 11.6 KILOMETERS SSE OF SITE 21 CONTROL SPOFFORD LAKE 16.4 KILOMETERS NNE OF SITE 0.06 0
0.0019 (0/24)
(<0.0004<0.0030) 0 0
0 0
0 0
0 RA-226 AC/TH-228 N/A 0.0291 (0/24)
(<0.0180/<0.0437)
N/A 0.0075 (0/24)
(<0.0019/<0.0122) 0.07 0.0332 (0/311)
(<0.0058/<0.0682)
AIR IODINE (PCI/CU.METER) 1-131 363 27 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS RIVER WATER (PCI/LITER)
GROSS BETA TRITIUM
- 24 1.37 (11/12)
(0.650/2.01) 412 (0/4)
(<398/<421) 1.04 (10/12)
(<0.500/1.78) 412 (0/4)
(<398/<421) 1.37 (11/12)
(0.650/2.01) 412 (0/4)
(<398/<421)
II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 0
0 3000
- Stations II and 21 have the same average.
GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 24 15 1.97 (0/12)
(<0.609/<2.84) 15 2.20 (0/12)
(<0.786/<2.85) 30 6.28 (0/12)
(<2.43/<8.79) 15 2.02 (0/12)
(<0.585/<2.75) 30 3.90 (0/12)
(<0.831/<5.80) 15 4.05 (0/12)
(<1.41/<5.79) 4.70 (0/12)
(<1.91/<7.02) 4.39 (0/12)
(<2.01/<6.28) 12.9 (0/12)
(<6.59/<23.4) 5.05 (0/12)
(<1.86/<8.45) 12.3 (0/12)
(<2.66/<20.5) 7.45 (0/12)
(<3.49/< 11.6) 4.70 (0/12)
(<1.91/<7.02) 4.39 (0/12)
(<2.01/<6.28) 12.9 (0/12)
(<6.59/<23.4) 5.05 (0/12)
(<1.86/<8.45) 12.3 (0/12)
(<2.66/<20.5) 7.45 (0/12)
(<3.49/<11.6) 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 28 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS RIVER WATER (PCI/LITER) 1-131 CS-134 CS-137 BA-LA-140 RA-226 GROSS BETA TRITIUM
- 15 9.52 (0/12)
(<6.68/<12.6) 15 1.67 (0/12)
(<0.448/<2.66) 18 1.96 (0/12)
(<0.593/<3.04) 15 6.27 (0/12)
(<4.84/<8.61)
N/A 79.4 (12/12)
(54.4/122) 4 3.71 (16/16)
(1.51/6.41) 7.75 (0/12)
(<3.92/<14.7) 3.44 (0/12)
(<1.95/<5.17) 4.80 (0/12)
(<1.84/<8.03) 8.19 (0/12)
(<4.93/< 12.9) 95.8 (9/12)
(53.2/<156) 1.67 (5/5)
(1.12/2.23) 412 (0/5)
(<400/<420) 9.52 (0/12)
(<6.68/<12.6) 3.44 (0/12)
(<1.95/<5.17) 4.80 (0/12)
(<1.841<8.03) 8.19 (0/12)
(<4.93/<12.9) 95.8 (9/12)
(53.2/<156) 6.02 (1/1)
N/A 412 (0/5)
(<400/<420)
II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 13 INDICATOR COB WELL 0.3 KILOMETERS ON-SITE 22 CONTROL COPELAND WELL 13.7 KILOMETERS N OF SITE 0
0 0
0 0
0 GROUND WATER (PCI/LITER)
(ODCM term for potable water wells) 21 21 2000 409 (0/16)
(<400/<420)
- Stations 14 and 22 have the same average. Station 14 has a minimum value of 406 and station 22 has a minimum value of 400.
1-131 21 0.510 (0/16)
(<0.375/<0.928) 0.600 (0/5)
(<0.4401<0.800) 0.627 (0/5)
(<0.490/<0.928) 11 INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 0
29 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS GROUND WATER (PCI/LITER)
GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 20 15 6.18 (0/16)
(<4.23/<10.72) 15 5.13 (0/16)
(<3.39/<7.34) 30 17.6 (0/16)
(<14.3/<27.0) 15 7.57 (0/16)
(<5.77/< 10.7) 30 10.3 (0/16)
(<8.20/< 14.4) 15 12.0 (0/16)
(<7.28/< 14.9) 15 5.58 (0/16)
(<3.89/<7.86) 18 4.92 (0/16)
(<3.34/<8.39) 7.06 (0/5)
(<4.38/<8.96) 6.75 (0/5)
(<4.04/<8.78) 18.3 (0/5)
(<11.0/<22.7) 7.13 (0/5)
(<5.06/<8.90) 9.77 (0/5)
(<5.92/< 12.6) 10.5 (0/5)
(<6.97/<13.7) 5.10 (0/5)
(<2.92/<8.15) 6.28 (0/5)
(<2.63/<9.75) 7.06 (0/5)
(<4.38/<8.96) 6.75 (0/5)
(<4.04/<8.78) 20.7 (0/5)
(<17.6/<27.0) 8.96 (0/5)
(<7.51/<10.7) 11.8 (0/5)
(<9.97/< 14.4) 14.2 (0/5)
(<12.8/<14.9) 6.04 (0/5)
(<4.59/<7.86) 6.86 (0/1)
N/A 22 CONTROL COPELAND WELL 13.7 KILOMETERS N OF SITE 22 CONTROL COPELAND WELL 13.7 KILOMETERS N OF SITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE OF SITE 13 INDICATOR COB WELL 0.3 KILOMETERS ON-SITE 0
0 0
0 0
0 0
30 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS GROUND WATER (PCI/LITER)
BA-LA-140 RA-226 GAMMA BE-7 15 10.2 (0/16)
(<7.02/<14.4)
N/A 213 (4/16)
(<149/<304)
N/A 941 (1/34)
(<271/< 1970)
SEDIMENT (PCI/KG DRY) 36 K-40 MN-54 CO-60 NB-95 CS-134 N/A 16241 (34/34)
(9140/21900)
' 9.12 (0/5)
(<6.24/<13.6) 156 (1/5)
(101/<211) 717 (1/2)
(<472/962) 12050 (2/2)
(11900/12200) 49 (2/2)
(<41.7/<55.9) 42.2 (0/2)
(<31.6/<52.7) 80.3 (0/2)
(<58.6/< 102) 41 (0/2)
(<33.5/<48.3) 11.4 (0/5)
(<9.02/<14.4) 248 (3/5)
(206/<282) 1395 (0/2)
(<1210/<1580) 19850 (2/2)
(19000/20700) 116 (0/2)
(<94.2/< 13 8) 157 (1/2)
(<74.9/240) 170 (0/2)
(<151/<188) 71 (0/2)
(<68.0/<73.0) 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KILOMETERS ONSITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 29 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 31 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 0
0 0
0 0
0 0
0 N/A 72.0 (0/34)
(<22.1/<138)
N/A 71.2 (1/34)
(<16.9/240)
N/A 109 (0/34)
(<29.7/<206) 150 54.7 (0/34)
(<18.2/<73.7) 31 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SEDIMENT (PCI/KG DRY)
CS-137 BA-LA-140 RA-226 AC-228 TH-228 TH-232 U-238 AM-241 180 107.0 (19/34)
(<25.7/22 1)
N/A 636 (0/34)
(<131/<1140)
N/A 2053 (19/34)
(<746/3680)
N/A 1924 (26/34)
(< 106/4640)
N/A 1321 (34/34)
(484/2190)
N/A 1146 (34/34)
(452/1660)
N/A 7355 (34/34)
(2100/12700)
N/A 95.0 (0/4)
(2100/12700) 68 (1/2)
(66.2/<69.8) 460 (0/2)
(<322/<597) 1345 (2/2)
(1200/1490) 1690 (2/2)
(1170/2210) 958 (2/2)
(835/1080) 933 (2/2)
(886/980) 5075 (2/2)
(4140/6010) 103 (0/2)
(<8.80/< 198) 150 (1/2)
(<78.3/221) 913 (0/2)
(<685/<1 140) 2825 (2/2)
(2650/3000) 3915 (2/2)
(3190/4640) 1725 (2/2)
(1260/2190) 1385 (2/2)
(1340/1430) 10400 (2/2)
(10000/10800) 103 (0/2)
(<8.80/< 198) 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 35 INDICATOR NORTH STORM DRAIN OUTFALL
- 0. 1 KILOMETERS E OF SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 35 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 6
32 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SEDIMENT (PCI/KG DRY)
CM-242 CM-243/244 FE-55 H-3 NI-63 PU-238 PU-239/240 PU-241 6
6 6
6 6
6 6
6 N/A 68.9 (0/4)
(<0.821/<149)
N/A 156 (0/4)
(<2.16/<369)
N/A 11398 (0/4)
(<5890/<13500)
N/A 1628 (0/4)
(<899/<2350)
N/A 444 (0/4)
(<384/<503)
N/A 71.4 (0/4)
(<7.44/< 159)
N/A 45.4 (0/4)
(<2.72/< 108)
N/A 6455 (0/4)
(<4930/<9340) 62.1 (0/2)
(<4.11/< 120) 176 (0/2)
(<3.56/<349) 11445 (0/2)
(<5790/<17100) 1649 (0/2)
(<857/<2440) 447 (0/2)
(<396/<498) 92.1 (0/2)
(<8.1 8/< 176) 23.0 (0/2)
(<3.8 1/<42.2) 6545 (0/2)
(<5670/<7420) 74.9 (0/2)
(<0.821/< 149) 186 (0/2)
(<2.16/<369) 13150 (0/2)
(< 12800/<k 3500) 1649 (0/2)
(<857/<2440) 447 (0/2)
(<396/<498) 92.1 (0/2)
(<8.18/<176) 55.6 (0/2)
(<3.14/< 108) 7585 (0/2)
(<5830/<9340) 11 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 11 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE II INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 10 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 10 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 0
0 0
0 0
0 0
0 33 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SEDIMENT (PCI/KG DRY)
PU-242 SR-89 SR-90 U-234 U-235 U-238 6
6 3
3 3
N/A 28.4 (0/4)
(<5.83/<63.0)
N/A 1156 (0/4)
(<286/<3130)
N/A 184 (0/4)
(<98.0/<395)
N/A 153 (1/2)
(<86.8/219)
N/A 19.2 (0/2)
(<14.9/<23.5)
N/A 164 (1/2)
(<100/228) 4 9.94 (20/20)
(4.02/18.3) 30.0 (0/2)
(<2.34/<57.7) 408 (0/2)
(<304/<512) 98.3 (0/2)
(<91.6/< 105) 330 (1/1)
N/A 34.4 (0/2)
(<5.83/<63.0) 1853 (0/2)
(<577/<3130) 254 (0/2)
(<113/<395) 330 (1/1)
N/A 10 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 10 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 10 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL
- 0. 1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 21 CONTROL NORTH STORM DRAIN OUTFALL 0.1 KILOMETERS E OF SITE 0
0 0
0 45.6 (0/1)
N/A 334 (1/1)
N/A N/A N/A 45.6 (0/1)
N/A 334 (1/I)
N/A TEST WELLS (PCI/LITER)
(Nuclear Energy Institute Groundwater Protection Initiative Samples)
GROSS BETA TRITIUM 20 20 15.9 (5/5)
(13.9/18.3) 414 (0/5)
(<247/<515) 14 INDICATOR TEST WELL 201 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 0
0 0
3000 398 (0/20)
(<244/<527) 34 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS TEST WELLS (PCI/LITER)
(Nuclear Energy Institute Groundwater Protection Initiative Samples)
GAMMA K-40 20 MN-54 CO-58 FE-59 CO-60 NB-95 1-131 CS-134 N/A 27.3 (3/20)
(<7.01/1 11) 15 1.58 (0/20)
(<0.692/<3.20) 15 1.96 (0/20)
(<0.867/<3.87) 30 4.34 (0/20)
(<2.01/<7.57) 15 1.54 (0/20)
(<0.702/<3.39) 15 2.03 (0/20)
(<0.886/<3.65) 15 35.2 (0/20)
(<4.97/<218) 15 1.49 (0/20)
(<0.690/<3.16)
N/A N/A N/A N/A N/A N/A N/A N/A 31.6 (1/5)
(<7.01/111) 1.63 (0/5)
(<1.00/<2.87) 2.06 (0/5)
(<1.12/<3.83) 4.50 (0/5)
(<2.29/<6.96) 1.67 (0/5)
(<0.949/<3.39) 2.16 (0/5)
(<0.886/<3.57) 49.9 (0/5)
(<6.73/<218) 1.59 (0/5)
(<0.690/<2.64) 14 INDICATOR TEST WELL 201 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 0
0 0
0 0
0 0
0 35 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS TEST WELLS (PCI/LITER)
(Nuclear Energy Institute Groundwater Protection Initiative Samples)
CM-242 CM-243/244 FE-55 PU-238 PU-239/240 4
4 4
4 18 1.63 (0/20)
(<0.928/<3.18) 15 10.2 (0/20)
(<2.01/<31.9)
N/A 0.164 (0/4)
(<0.114/<0.190)
N/A 0.075 (0/4)
(<0.036/<0.126)
N/A 0.109 (0/4)
(<0.045/<0.178)
N/A 66.0 (0/4)
(<4.25/<119)
N/A 0.112 (0/4)
(<0.072/<0.145)
N/A 0.113 (0/4)
(<0.093/<0.130)
N/A N/A N/A 1.72 (0/5)
(<0.938/<2.59) 11.3 (0/5)
(<2.54/<31.9) 0.190 (0/1)
N/A N/A 0.126 (0/1)
N/A N/A 0.178 (0/1)
N/A N/A 119 (0/1)
N/A N/A 0.145 (0/1)
N/A 16 INDICATOR TEST WELL 202 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 0
0 0
0 0
0 0
0 4
N/A 0.130 (0/1)
N/A 36 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS TEST WELLS (PCI/LITER)
(Nuclear Energy Institute Groundwater Protection Initiative Samples)
PU-241 PU-242 SR-89 SR-90 4
4 4
N/A 13.9 (0/4)
(<11.8/<16.8)
N/A 0.045 (0/4)
(<0.021/<0.056)
N/A 7.40 (0/4)
(<5.74/<8.56)
N/A 1.03 (0/4)
(<0.806/<1.27)
N/A 16.8 (0/1)
N/A N/A 0.056 (0/1)
N/A N/A 8.56 (0/I)
N/A N/A 1.27 (0/1)
N/A 14 INDICATOR TEST WELL 201 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 0
0 0
MILK (PCI/LITER) 1-131 105 1
0.518 (0/54)
(<0.440/<0.735)
SR-89 SR-90 GAMMA BE-7 23 23 105 N/A 4.50 (0/12)
(<1.71/<7.21)
N/A 1.29 (4/12)
(<0.540/2.07)
N/A 53.7 (0/54)
(<37.3/<76.5)
(0/51)
(<0.422/<0.926) 4.22 (0/1I)
(<1.93/<7.48) 1.14 (4/11)
(<0.481/<2.45) 57.8 (0/51)
(<35.9/<84.5) 0.739 (0/15)
(<0.422/<0.926) 5.15 (0/4)
(<2.02/<7.21) 1.47 (3/4)
(<0.730/2.45) 61.5 (0/18)
(<44.8/<78.5) 20 CONTROL DUNKLEE FARM 5.5 KILOMETERS S OF SITE II INDICATOR MILLER FARM 0.8 KILOMETERS W OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 24 CONTROL COUNTY FARM 21.6 KILOMETERS N OF SITE 0
0 37 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HGIIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS MILK (PCI/LITER)
K-40 CS-134 CS-137 BA-LA140 RA-226 AC-TH228 N/A 1525 (54/54)
(1257/1970) 15 5.83 (0/54)
(<2.94/<1 1.2) 18 7.06 (0/54)
(<4.57/<10.4) 15 8.25 (0/54)
(<4.42/<I13.2)
N/A 147 (12/54)
(77.1/216)
N/A 25.7 (0/54)
(< 16.2/<38.0) 60 26.9 (0/3)
(<21.9/<31.0)
N/A 607 (3/3)
(453/782) 1646 (51/51)
(1375/2092) 6.34 (0/51)
(<3.45/<I11.1) 7.27 (0/51)
(<4.47/<1 1.0) 8.64 (0/51)
(<4.41/< 14.5) 151 (12/51)
(70.5/<206) 26.0 (1/51)
(12.1/<44.0) 33.8 (0/3)
(<19.0/<51.4) 547 (3/3)
(395/800) 1723 (18/18)
(1420/2092) 7.03 (0/18)
(<4.51/<I11.1) 7.68 (0/18)
(<5.46/< 10.4) 9.34 (0/18)
(<6.35/< 13.2) 160 (3/18)
(79.0/<200) 28.0 (0/18)
(12.1/<40.2) 51.4 (0/1)
N/A 800 (1/1)
N/A 24 CONTROL COUNTY FARM 21.6 KILOMETERS N OF SITE 24 CONTROL COUNTY FARM 21.6 KILOMETERS N OF SITE 18 INDICATOR BLODGETT FARM 3.6 KILOMETERS SE OF SITE 18 INDICATOR BLODGETT FARM 3.6 KILOMETERS SE OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 24 CONTROL COUNTY FARM 21.6 KILOMETERS N OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 0
0 0
0 0
0 0
SILAGE (PCI/KG) 1-131 6
6 GAMMA BE-7 0
38 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SILAGE (PCIIKG)
K-40 CS-134 CS-137 RA-226 AC-TH228 N/A 4630 (3/3)
(3871/5171) 60 25.3 (0/3)
(<21.0/<31.7) 80 23.0 (0/3)
(<21. 1/<26.2)
N/A 431 (0/3)
(<344/<538)
N/A 95.2 (0/3)
(<59.6/< 139) 60 35.1 (0/18)
(< 18.9/<56.8)
N/A 1325 (16/18)
(112/5148)
N/A 7624 (18/18)
(5067/10850) 9309 (3/3)
(4186/18780) 34.7 (0/3)
(<21.3/<58.3) 37.1 (0/3)
(<22.7/<52.7) 592 (2/3)
(251/923) 120 (0/3)
(<72.0/<176) 35.8 (0/3)
(<30.7/<40.6) 1988 (2/3)
(<276/4351) 5976 (3/3)
(3780/7335) 18780 (I/I)
N/A 58.3 (0/1)
N/A 52.7 (0/1)
N/A 923 (1/1)
N/A 176 (0/1)
N/A 39.1 (0/3)
(<28.6/<56.8) 2064 (3/3)
(<765/4304) 8921 (3/3)
(7652/10850) 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 22 CONTROL FRANKLIN FARM 9.7 KILOMETERS WSW OF SITE 40 INDICATOR GOV. HUNT HOUSE ON-SITE 40 INDICATOR GOV. HUNT HOUSE ON-SITE 14 INDICATOR NORTHFIELD, MA 11.6 KILOMETERS SSE SITE 0
0 0
0 0
0 MIXED GRASS (PCI/KG) 1-131 21 21 GAMMA BE-7 0
0 K-40 39 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS MIXED GRASS (PCI/KG)
CS-134 CS-137 RA-226 AC-TH228 60 36.9 (0/18)
(<19.9/<59.5) 80 36.6 (0/18)
(<21.6/<56. 1)
N/A 604 (9/18)
(<367/1372)
N/A 138 (1/18)
(<69.2/245)
N/A 2916 (16/17)
(1910/4170) 130 52.5 (0/17)
(<26.1/<244) 130 54.7 (0/17)
(<32.6/<163) 260 133 (0/17)
(<75.0/<294) 24.6 (0/3)
(< 19.5/<27.5) 32.8 (0/3)
(<23.4/<37.6) 652 (1/3)
(573/<704) 126 (0/3)
(<85.9/<156) 2871 (17/17)
(1020/4920) 39.0 (0/17)
(<15.4/<55.0) 52.3 (0/17)
(<16.7/<116) 147 (0/17)
(<47.3/<526) 38.5 (0/3)
(<26.5/<59.5) 41.0 (0/3)
(<29.1/<56.1) 817 (1/3)
(<427/1372) 151 (1/3)
(<69.2/245) 2916 (16/17)
(1910/4170) 52.5 (0/17)
(<26.1/<244) 54.7 (0/17)
(<32.6/<163) 147 (0/17)
(<47.3/<526) 13 INDICATOR HINSDALE SUBSTATION 3.1 KILOMETERS E SITE 13 INDICATOR HINSDALE SUBSTATION 3.1 KILOMETERS E SITE II INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 KILOMETERS SSE SITE I I INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 0
0 0
FISH (PCI/KG)
UAMMA K40 34 MN-54 CO-58 FE-59 0
0 0
0 40 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS FISH (PCI/KG)
CO-60 ZN-65 CS-134 CS-137 GROSS BETA TRITIUM AM-241 CM-242 130 46.8 (0/17)
(<13.8/<201) 260 98.1 (0/17)
(<57.8/<317) 130 50.2 (0/17)
(<23.4/<229) 150 53.8 (0/17)
(<23.8/<22 1)
N/A 17.3 (2/2)
(12.8/21.8)
N/A 181 (0/8)
(<16.1/<392)
N/A 13.5 (0/16)
(<2.62/<83.7)
N/A 7.67 (0/16)
(<0.759/<56.8) 38.4 (0/17)
(<15.9/<63.3) 88.9 (0/17)
(<38.4/<124) 37.8 (0/17)
(<13.9/<51.0) 44.0 (0/17)
(<15.3/<73.8) 17.9 (2/2)
(12.1/23.6) 132 (0/8)
(<16.0/<260) 17.3 (0/16)
(<1.20/<110) 8.15 (0/16)
(<0.638/<52.5) 46.8 (0/17)
(<13.8/<201 )
98.1 (0/17)
(<57.8/<317) 50.2 (0/17)
(<23.4/<229) 53.8 (0/17)
(<23.8/<221) 17.9 (2/2)
(12.1/23.6) 181 (0/8)
(<16.1/<392) 17.3 (0/16)
(<1.20/<110) 8.15 (0/16)
(<0.638/<52.5)
II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE 11 INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE I I INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 1
INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 0
4 16 32 32 41 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS FISH (PCI/KG)
CM-243/244 FE-55 NI-63 PU-238 PU-239/240 PU-241 PU-242 SR-89 32 32 32 32 32 32 32 32 N/A 16.1 (0/16)
(<0.759/<115)
N/A 1834 (0/16)
(<609/<9490)
N/A 198 (0/16)
(<109/<367)
N/A 17.9 (0/16)
(<2.3 1/< 103)
N/A 10.5 (0/16)
(<1.09/<55.1)
N/A 1798 (0/16)
(<164/<11900)
N/A 6.48 (0/16)
(<0.629/<52.3)
N/A 106 (0/16)
(<53.4/<292) 19.1 (0/16)
(<0.638/<135) 1861 (0/16)
(<624/<4490) 212 (0/16)
(<109/<391) 10.8 (0/16)
(<2.25/<82.3) 7.70 (0/16)
(<1.30/<60.1) 1262 (0/16)
(<172/<10700) 4.67 (0/16)
(<0.728/<38.0) 118 (0/16)
(<46.2/<370) 19.1 (0/16)
(<0.638/<135) 1861 (0/16)
(<624/<4490) 212 (0/16)
(<109/<39 1) 17.9 (0/16)
(<2.31/<103) 10.5 (0/16)
(<1.09/<55.1) 1798 (0/16)
(<164/<11900) 6.48 (0/16)
(<0.629/<52.3) 118 (0/16)
(<46.2/<370) 21 CONTROL RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 21 RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE I I INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE II INDICATOR VERNON POND 0.6 KILOMETERS SSE OF SITE 21 RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE 0
0 42 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR TIE VERMONT YANKEE NUCLEAR POWER PLANT, 2010 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS FISH (PCI/KG)
SR-90 32 N/A 56.2 (0/16)
(<34.5/< 125)
N/A 7.03 (151/151)
(5.58/9.43) 71.6 (0/16)
(<27.7/<230) 6.76 (8/8)
(5.89/7.51) 71.6 (0/16)
(<27.7/<230) 9.08 (4/4)
(8.46/9.43) 21 RT. 9 BRIDGE 11.8 KILOMETERS NNW OF SITE DR-08 INDICATOR SITE BOUNDARY 0.25 KILOMETERS SSW OF SITE 0
DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)
159 0
43 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
TABLE 5.2 ENVIRONMENTAL TLD DATA
SUMMARY
VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 2010)
OFFSITE STATION WITH HIGHEST MEAN INNER RING TLD OUTER RING TLD CONTROL TLDs MEAN*
RANGE*
(NO. MEASUREMENTS)*
6.90
+
0.35 5.70 to 8.13 75 MEAN*
RANGE*
(NO. MEASUREMENTS)**
7.00
+/-
0.35 5.60 to 8.70 68 STA.NO./ MEAN*
MEAN*
RANGE*
RANGE*
(NO. MEASUREMENTS)**
(NO. MEASUREMENTS)**
DR-36 8.20
+/-
0.37 7.39 to 8.65 4
6.77 +/- 0.32 5.89 to 7.51 8
SITE BOUNDARY TLD WITH HIGHEST MEAN STA.NO./ MEAN*
RANGE*
(NO. MEASUREMENTS)**
DR-45 14.00 + 1.60 12.47 to 16.12 4
SITE BOUNDARY TLD MEAN*
RANGE *
(NO. MEASUREMENTS)**
8.80
+/-
0.40 6.10 to 16.12 60 Units are in micro-R per hour.
- Each "measurement" is typically based on quarterly readings from five TLD elements.
44
TABLE 5.3 ENVIRONMENTAL TLD MEASUREMENTS 2010 (Micro-R per Hour)
Sta.
No.
Description 1 ST QUARTER EXP.
S.D.
2ND QUARTER 3RD QUARTER 4TH QUARTER EXP.
S.D.
ANNUAL AVE.
EXP.
EXP.
S.D.
EXP.
S.D.
DR-01 River Sta. No. 3.3 DR-02 N Hinsdale, NH DR-03 Hinsdale Substation DR-04 Northfield, MA DR-05 Spofford Lake, NH DR-06 Vernon School DR-07 Site Boundary DR-08 Site Boundary DR-09 Inner Ring DR-10 Outer Ring DR-11 Inner Ring DR-1 2 Outer Ring DR-13 Inner Ring DR-14 Outer Ring DR-15 Inner Ring DR-16 Outer Ring DR-17 Inner Ring DR-18 Outer Ring DR-19 Inner Ring DR-20 Outer Ring DR-21 Inner Ring DR-22 Outer Ring DR-23 Inner Ring DR-24 Outer Ring DR-25 Inner Ring DR-26 Outer Ring DR-27 Inner Ring DR-28 Outer Ring DR-29 Inner Ring DR-30 Outer Ring DR-31 Inner Ring DR-32 Outer Ring DR-33 Inner Ring DR-34 Outer Ring DR-35 Inner Ring DR-36 Outer Ring DR-37 Inner Ring DR-38 Outer Ring DR-39 Inner Ring DR-40 Outer Ring 6.41
+
0.52 6.25
+
0.45 6.08
+
0.28 6.36
+ 0.30 6.3 6.26
+
0.30 7.13
+
0.39 6.88
+
0.30 7.45
+ 0.27 6.9 6.91
+
0.45 7.75
+
0.44 7.45
+
0.31 7.87
+ 0.34 7.5 5.89
+
0.31 6.87
+
0.29 6.15
+
0.23 6.77
+ 0.30 6.4 6.24
+
0.40 7.43
+
0.35 7.28
+
0.38 7.51
+ 0.34 7.1 6.65
+
0.27 7.01
+
0.29 7.39
+
0.37 7.13
+ 0.34 7.0 8.32
+
0.42 8.05
+
0.42 8.55
+
0.32 8.93
+ 0.34 8.5 9.31
+
0.52 8.46
+
0.37 9.43
+
0.43 9.12
+ 0.46 9.1 6.46
+
0.33 7.33
+
0.44 6.47
+
0.31 6.95
+ 0.44 6.8 5.58
+
0.34 6.10
+
0.45 5.67
+
0.31 6.04
+ 0.27 5.9 5.70
+
0.43 6.40
+
0.40 6.18
+
0.25 6.55
+ 0.28 6.2 5.60
+
0.25 6.29
+
0.28 5.96
+
0.24 6.23
+ 0.31 6.0 6.27
+
0.38 7.07
+
0.32 6.41
+
0.33 6.97
+ 0.34 6.7 7.14
+
0.45 8.34
+
0.30 8.27
+
0.37 8.04
+ 0.44 8.0 6.55
+
0.30 7.47
+
0.33 6.91
+
0.31 7.12
+ 0.31 7.0 7.00
+
0.26 7.61
+
0.33 7.29
+
0.53 7.84
+ 0.35 7.4 6.33
+
0.42 6.67
+
0.33 6.45
+
0.29 7.03
+ 0.35 6.6 6.44
+
0.33 7.22
+
0.29 6.89
+
0.26 7.18
+ 0.33 6.9 6.92
+
0.31 8.13
+
0.36 7.59
+
0.31 8.02
+ 0.42 7.7 6.80
+
0.36 7.90
+
0.35 7.46
+
0.29 7.77
+ 0.34 7.5 6.34
+
0.49 6.95
+
0.26 6.85
+
0.29 7.10
+ 0.30 6.8 6.87
+
0.47 7.20
+
0.31 6.85
+
0.40 7.20
+ 0.45 7.0 5.85
+
0.24 6.32
+
0.30 6.38
+
0.76 6.27
+ 0.34 6.2 5.66
+
0.23 6.24
+
0.29 6.27
+
0.64 6.19
+ 0.28 6.1 6.55
+
0.35 6.94
+
0.35 6.70
+
0.27 6.70
+ 0.32 6.7 6.18
+
0.37 7.22
+
0.29 7.14
+
0.26 7.14
+ 0.34 6.9 6.40
+
0.29 6.81
+
0.38 6.71
+
0.37 6.82
+ 0.30 6.7 6.49
+
0.33 7.32
+
0.43 6.98
+
0.31 7.20
+ 0.36 7.0 7.90
+
0.46 7.13
+
0.36 6.81
+
0.35 7.24
+ 0.37 7.3 6.35
+
0.45 7.09
+
0.33 6.93
+
0.38 6.96
+ 0.54 6.8 6.55
+
0.22 7.19
+
0.34 6.97
+
0.23 6.95
+ 0.40 6.9 6.12
+
0.29 6.91
+
0.39 7.30
+
0.39 6.43
+ 0.37 6.7 7.01
+
0.42 7.81
+
0.63 7.45
+
0.40 7.22
+ 0.29 7.4 6.62
+
0.34 7.29
+
0.32 7.14
+
0.28 7.44
+ 0.33 7.1 6.63
+
0.37 7.06
+
0.30 7.08
+
0.44
+
6.9 7.39
+
0.31 8.65
+
0.36 8.34
+
0.35 8.38
+ 0.46 8.2 6.70
+
0.25 7.16
+
0.31 7.00
+
0.28 7.15
+ 0.44 7.0 7.02
+
0.23 7.45
+
0.38 7.49
+
0.28 7.78
+ 0.34 7.4 6.79
+
0.38 7.26
+
0.32 7.17
+
0.31 7.16
+ 0.31 7.1 6.80
+
0.26 7.06
+
0.47 7.15
+
0.34 7.18
+ 0.31 7.1 Note: Blank spaces indicate missing TLDs 45
TABLE 5.3 (cont.)
ENVIRONMENTAL TLD MEASUREMENTS 2010 (Micro-R per Hour)
Sta.
No.
Description 1ST QUARTER EXP.
S.D.
2ND QUARTER 3RD QUARTER 4TH QUARTER EXP.
S.D.
EXP.
S.D.
EXP.
S.D.
ANNUAL AVE.
EXP.
DR-07 Site Boundary DR-08 Site Boundary DR-41 Site Boundary DR-42 Site Boundary DR-43 Site Boundary DR-44 Site Boundary DR-45 Site Boundary DR-46 Site Boundary DR-47 Site Boundary DR-48 Site Boundary DR-49 Site Boundary DR-50 Governor Hunt House DR-51 Site Boundary DR-52 Site Boundary DR-53 Site Boundary 8.32
+ 0.42 8.05
+ 0.42 8.55
+ 0.32 8.93
+ 0.34 9.31
+ 0.52 8.46
+ 0.37 9.43
+ 0.43 9.12
+ 0.46 7.45
+
0.25 7.53
+
0.44 7.68
+
0.29 7.69
+ 0.30 6.69
+
0.23 7.30
+
0.38 7.70
+
0.53 7.25
+ 0.32 7.74
+
0.39 7.85
+
0.32 8.14
+
0.27 8.19
+ 0.38 10.15
+
0.74 8.58
+
0.36 11.05
+
0.49 10.18
+ 0.41 14.11
+
0.81 12.47
+
0.65 13.10
+
0.49 16.12
+ 1.02 10.67
+
0.45 9.29
+
0.34 9.82
+
0.39 9.81
+ 0.40 8.19
+
0.25 8.22
+
0.37 8.55
+
0.34 8.61
+ 0.33 6.37
+
0.25 6.10
+
0.25 6.16
+
0.27 6.39
+ 0.27 6.38
+
0.31 6.84
+
0.30 6.76
+
0.31 6.73
+ 0.31 7.33
+
0.28 7.21
+
0.42 7.91
+
0.29 7.87
+ 0.40 9.07
+
0.34 8.56
+
0.33 8.99
+
0.37 9.50
+ 0.47 10.02
+
0.43 9.19
+
0.57 10.00
+
0.56 9.72
+ 0.49 10.54
+
0.47 9.63
+
0.35 10.12
+
0.41 10.22
+ 0.33 8.5 9.1 7.6 7.2 8.0 10.0 14.0 9.9 8.4 6.3 6.7 7.6 9.0 9.7 10.1 46
- 6.
ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations Off-site Dose Calculation Manual Control 3.5.1 allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons."
In 2010, five deviations were noted in the REMP.
These deviations did not compromise the program's effectiveness and are considered typical with respect to what is normally anticipated for any radiological environmental program. The specific deviations for 2010 were:
a) The South River Station River Water pump which provides a river water sample to the composite sampler at this location was found to be out of service on February 12, 2010. It was determined that the water pump had ceased function as a result of a wire nut that had loosened during the starting and stopping of the pump. The wire nut was replaced with a newer, tighter version by the contractor electrician and returned to service on February 25, 2010. No additional problems were noted with the electrical service to this pump for the remainder of the year.
b) The Governor Hunt House air sample station (AP/CF-40) was taken out of service during the plant refueling outage due to bus work and bus swaps. This occurred intermittently during the period May 4 th through May 18 th, 2010 (Weeks 19 and 20). This station is supplied with electrical power from the plant and no alternative power source was available during this period. This station is not required by the Vermont Yankee REMP c) The South River Station River Water pump which provides a river water sample to the composite sampler at this location was found to be out of service on August 1 8th, 2010. It was determined that the water pump had ceased function due to significant clogging with river silt. The water pump was replaced and flow was restored to the sampler on August 23, 2010.
d) During a review of air sample collection data from the Northfield Massachusetts Air Sample station (AP/CF-14) on August I0 th, 2010, it was determined that approximately 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> of sample collection time had been lost during week 32 of 2010. The station fuse was blown and a new fuse was installed. Severe electrical storms had been experienced in the area during this collection period.
No further problems were noted and the station performed satisfactorily for the remainder of the year.
e) Thermoluminescent Dosimeter (TLD) DR-35 was determined to be missing at the end of the fourth quarter 2010 TLD changeout during the week of January I0 th, 2011.
The TLD was located in a special holder on a telephone pole adjacent to Rte. 142 (Ft. Bridgman Road) approximately two miles north of the plant site. The holder, as well as the TLD, was missing. No trace of the holder, or the TLD, was found in the immediate area around the telephone pole. A new holder was affixed to the telephone pole and the TLD for the first quarter 2011 was placed in the holder. Subsequently, during the TLD changeout of the first quarter 2011 (week of April 12th, 2011) the TLD and holder were found at the base of the power pole. The holder had apparently been knocked off the power pole by snowplowing activities and was hidden by extremely deep snow banks during the week of January 1 0 th, 2011.
47
f) Air sample station outages are reflected in the air sample collection time percentages listed below.
AP/CF #
1st Quarter 2nd Quarter 3rd Quarter 41h Quarter 11 99.6%
99.7%
99.9%
100%
12 99.9%
99.8%
99.9%
100%
13 99.7%
99.8%
100%
100%
14 100%
98.9%
94.1%
100%
15 99.2%
99.5%
100%
100%
21 99.6%
99.9%
99.9%
99.9%
40 99.6%
86.0%
98.7%
100%
6.2 Comparison of Achieved LLDs with Requirements Table 4.5.1 of the VYNPS ODCM (also shown in Table 4.4 of this report) gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. On occasion, an LLD is not achievable due to a situation such as a low sample volume caused by sampling equipment malfunction or limited sample availability. In such a case, ODCM 10.2 requires a discussion of the situation. At the contracted environmental laboratory, the target LLD for the majority of analyses is 50 percent of the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2 times greater than that required by the VYNPS ODCM.
For each analysis having an LLD requirement in ODCM Table 4.5.1, the a posteriori (after the fact) LLD calculated for that analysis was compared with the required LLD. During 2010, all sample analyses performed for the REMP program achieved an a posteriori LLD less than the corresponding LLD requirement.
6.3 Comparison of Results with Reporting Levels ODCM Section 10.3.4 requires written notification to the NRC within 30 days of receipt of an analysis result whenever a Reporting Level in ODCM Table 3.5.2 is exceeded.
Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.
Environmental concentrations are averaged over the calendar quarters for the purposes of this comparison. The Reporting Levels are intended to apply only to measured levels of radioactivity due to plant effluents. During 2010, no analytical result exceeded a corresponding reporting level requirement in Table 3.5.2 of the ODCM.
48
6.4 Changes in Sampling Locations The Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual Section 10.2 states that if "new environmental sampling locations are identified in accordance with Control 3.5.2, the new locations shall be identified in the next Annual Radiological Environmental Operating Report."
There were no required sampling location changes due to the Land Use Census conducted in 2010.
Milk collection from Dunklee farm (Vern-Mont Farm in Vernon) commenced in April, 2010 at the request of the farm owner. At this time, all dairy farms in Vernon are supplying milk for analysis.
This year Vermont Yankee is continuing to add data from the on-site air sampling station, AP/CF 40, at the Governor Hunt House. This location has been used continuously as a demonstration since early in the program, but the data had not previously been included in this report.
6.5 Data Analysis by Media Type The 2010 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration in the units of the sample (volume or weight).
An analysis is considered to yield a "detectable measurement' when the concentration exceeds three times the standard deviation for that analysis and is greater than or equal to the Minimum Detectable Concentration (MDC) for the analysis. With respect to data plots, all net concentrations are plotted as reported, without regard to whether the value is "detectable" or "non-detectable." In previous years, values that were less than the MDC were converted to zero.
6.5.1 Airborne Pathways 6.5.1.1 Air Particulates (AP)
The periodic air particulate filters from each of the seven sampling sites were analyzed for gross-beta radioactivity. At the end of each quarter, the filters from each sampling site were composited for a gamma analysis. The results of the air particulate sampling program are shown in Table 5.1 and Figures 6.1 through 6.7.
Gross beta activity was detected in all air particulate filters that were analyzed. As shown in Figure 6.1, there is no significant difference between the quarterly average concentrations at the indicator (near-plant) 49
stations and the control (distant from plant) stations. Notable in Figure 6.1 is a distinct annual cycle, with the minimum concentration in the fourth quarter, and the maximum concentration in the third quarter.
Figures 6.2 through 6.7 show the weekly gross beta concentration at each air particulate sampling location compared to the control air particulate sampling location at AP-21 (Spofford Lake, NH). Small differences are evident and expected between individual sampling locations. Figure 6.2 clearly demonstrates the distinct annual cycle, with the minimum concentration in the second quarter, and the maximum concentration in the first quarter.
It can be seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year. The measurements from control station AP-21 vary similarly, indicating that these fluctuations are due to regional changes in naturally-occurring airborne radioactive materials, and not due to Vermont Yankee operations.
There were two naturally-occurring gamma-emitting radionuclides detected on the air particulate filters during this reporting period. Be-7, a naturally-occurring cosmogenic radionuclide, was detected on 28 of 28 filter sets analyzed. K-40 was detected on eight out of 28 analyzed. Ra-226 and Ac/Th-228 were not detected in the 28 filter sets analyzed.
6.5.1.2 Charcoal Cartridges (CF)
Charcoal cartridges from each of the seven air sampling sites were analyzed for 1-131 each time they were collected. The results of these analyses are summarized in Table 5.1. As in previous years, no 1-131 was detected in any charcoal cartridge.
6.5.2 Waterborne Pathways 6.5.2.1 River Water (WR)
Aliquots of river water were automatically collected periodically from the Connecticut River downstream from the plant discharge area and hydro station, location WR-11, with the exception of the two events of short duration when the sampling equipment was out of service (see Section 6.1). Monthly grab samples were also collected at the upstream control location, also on the Connecticut River, location WR-21. The composited samples at WR-1 1 were collected monthly and sent along with the WR-21 grab samples to the contracted environmental laboratory for analysis. Table 5.1 shows that gross-beta measurements were positive in 11 out of 12 indicator samples and 10 out of 12 control samples, as would be expected, due to naturally-occurring radionuclides in the water. As seen in Figure 6.8, the mean concentration of the 50
indicator locations was similar to the mean concentration at the control location in 2010.
For each sampling site, the monthly samples were composited into quarterly samples for H-3 (Tritium) analyses. None of the samples contained detectable quantities of H-3.
There was one naturally-occurring gamma-emitting radionuclides detected in river water samples during this reporting period. Ra-226, a naturally-occurring primordial radionuclide, was detected in 21 of 24 samples analyzed.
6.5.2.2 Ground Water - Potable Drinking Water (WG)
Quarterly ground water (deep wells supplying drinking water to the plant and selected offsite locations) samples were collected from four indicator locations (only one is required by VYNPS ODCM) and one control location during 2010. WG-13 (COB Well), an on-site well location, has been routinely sampled since the second half of 1996. (WG-13 was discontinued as a drinking water well location in early February, 2010 due to concerns about leakage from plant systems in the general area of the well.) In 1999, WG-14 (PBS Well) another on-site well location was added to the program. Table 5.1 and Figure 6.9 show that gross-beta measurements were positive in 16 out of 16 indicator samples and in 5 out of 5 control samples. The beta activity is due to naturally-occurring radionuclides in the water. The levels at all sampling locations, including the higher levels at station WG-13, were consistent with those detected in previous years. Naturally occurring Ra-226 was also detected in five samples and is naturally-occurring. No other gamma-emitting radionuclides or tritium were detected in any of the samples.
6.5.2.3 Sediment (SE)
Semi-annual river sediment grab samples were collected from two indicator locations during 2010. The North Storm Drain Outfall location (SE-12) is an area where up to 40 different locations can be sampled within a 20 ft by 140 ft area. In 2010, 18 locations were sampled at SE-I12 during each of the semi-annual collections. Two samples were collected at SE-I I during the year. Be-7 was detected in two of the 36 samples analyzed. As would be expected, naturally-occurring Potassium-40 (K-40) was detected in all of the samples. Cobalt-60 was detected in one of the 36 samples. Radium-226 (Ra-226) was detected in 21 of 36 samples. Actinium-228 was detected in 28 of 36 samples. Thorium-228 (Th-228) was detected in all 36 samples analyzed. Thorium-232 (Th-232) was detected in all 36 samples analyzed. Urainium-238 (U-238) was detected in all of the 36 samples. Cesium-137 (Cs-137) was detected in 19 out of 34 of the indicator samples and one of the two control samples. The levels of Cs-137 measured were consistent with what has been measured in the previous several years and with those detected at other New England locations. The sediment samples were also analyzed for hard-to-detect radionuclides Am-241, Cm-242, Cm-243/244, Fe-55, H-3, Ni-63 Pu-238, Pu-239/240, Pu-241, Pu-242, Sr-89, Sr-90, U-234, U-235 and U-51
238. Naturally-occurring Uranium-234 and Uranium-238 were detected in the indicator location SE-11 and control location SE-21. All other hard-to-detect radionuclides were not detected. Other plant-related radionuclides are reported in trace quantities in Table 5.1 SE.
Also see section 6.5.2.6 for more information.
6.5.2.4 Test Wells (WT)
During 1996, sampling was initiated at test wells around the outer edges of an area in the south portion of the VYNPS site where septic sludge is spread. This sampling continued through 2010. The test well locations are shown on Figure 4.1 and the results are summarized in Table 5.1 under the media category, Test Well (WT). In 2010, five samples were taken at each of the four locations and all were analyzed for gamma isotopic, gross beta and H-3 activity.
Prior to the gross beta analysis, each sample was filtered through a 0.45 micron Gelman Tuffryn membrane filter. Gross beta activity was detected in all 20 samples collected with levels ranging from 4.0 to 18.3 pCi/kg. K-40 was also detected in three of the 20 samples. No other radionuclides were detected.
The test wells were also analyzed for Am-241, Cm-242, Cm-243/244, Fe-55, Pu-238, Pu-239/240, Pu-241, Pu-242, Sr-89 and Sr-90. No analytes were detected.
6.5.2.5 Storm Drain System The presence of plant-related radionuclides in the onsite storm drain system has been identified in previous years at Vermont Yankee (VY). As a consequence, a 50.59 evaluation of radioactive materials discharged via the storm drain system was performed in 1998.
This assessment was in response to Information and Enforcement Bulletin No. 80-10 and NRC Information Notice No. 91-40. The evaluation demonstrated that the total curies released via the VYNPS storm drain system are not sufficient to result in a significant dose (i.e. dose does not exceed 10% of the technical specification objective of 0.3 millirem per year to the total body, and 1.0 millirem per year to the target organ for the maximally exposed receptor). Water and sediment in the onsite storm drain system was routinely sampled throughout 2010 at various points. The results of this sampling are summarized below.
Sediment samples were taken from the storm drain system at onsite manhole locations in 2010 for a total of 12 samples. All samples were analyzed for gamma emitting isotopes. Table 6-1 summarizes the analytical results of the sediment samples. The naturally-occurring isotope Ra-226 was found in 9 of 12 samples as expected. The highest detected concentration for all plant-related radionuclides that were detected in sediment samples was found in sample SE-95, which is also designated by the plant as Manhole 12.
52
The presence of Cobalt-60 and Cesium-137 was detected in storm water discharge pipes between Manhole-12 and Manhole-21 and also between Manhole-4 and Manhole-8 during routine cleaning of the storm drain system. Cobalt-60 was detected at up to a maximum of 63 picocuries per kilogram of sediments. Cesium-137 was detected at up to 396 picocuries per kilogram of sediments. This sediment was removed and disposed of as radwaste. Since this material was contained on VY property, no formal report was necessary at the time of discovery. However, it was determined that this information should be included in this report as part of the Storm Drain System section.
Table 6.1 Summary of Storm Drain System Sediment Sample Analyses*
Isotope No. Detected**
Mean Range Station With Highest (pCi/kg)
(pCi/kg)
Detected Concentration Ra-226 9/12 12.2 E 2 (0.58-1.65) E 3 MH-12A (SE-92)
Cs-137 2/12 1.2 E 2 (0.32-7.04) E 2 MH-12 (SE-95)
Mn-54 1/12 0.6E2 (0.36-1.53)E2 MH-12 (SE-95)
Co-60 2/12 4.5 E 2 (0.33 - 42.0) E 2 MH-12 (SE-95)
Zn-65 1/12 1.5 E 2 (0.50- 8.00) E 2 MH-12 (SE-95)
Radionuclides that were not detected in any sample are not listed
- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).
The mean and the range are determined only from the samples where activity was >3 standard deviations.
Water samples were taken from the storm drain system at various access points in 2010 including Manholes MH-8, MH-1 IH, MH-12A, MH-13, and MH-14. Table 6-2 summarizes the analytical results of water samples from the storm drain system (MH-12A and MH-14) in 2010. Naturally-occurring Ra-226 was detected in 12 of the samples. Low levels of gross beta activity were detected in 21 of 24 samples analyzed, at concentrations that are typical of any environmental water sample. Tritium (H-3) was not detected in the 22 samples analyzed.
In 1998, an additional dose assessment was performed that incorporated all of the 1998 storm drain system analytical results (including both sediment and water). The dose assessment was performed using the maximum measured concentration of radionuclides in 1998, and a conservative estimate of the volume of sediment and water discharged via the storm drain system. The results of this dose assessment are estimates of the total body and maximum organ dose equaling 3.2% and 1.6% of the corresponding Technical Specification dose limits respectively. Therefore, there was no significant dose impact from plant-related radionuclides in the storm drain system in 1998. The sampling conducted in 2010 indicates that the presence of radionuclides in the storm drain system has not changed significantly. Therefore, the storm drain system remains an insignificant impact to dose. The VYNPS staff will continue to monitor 53
the presence of plant related radionuclides in the storm drain system.
Table 6.2 Summary of Storm Drain System Water Sample Analyses*
Isotope No. Detected **
Mean Range Station With Highest (pCi/L)
(pCi/L)
Detected Concentration Gross Beta 21/22 3.5 E 0 (0.8 - 8.1) E 0 MH-12A (WW-1 2)
H-3 0/22 NA NA Ra-226 12/24 1.LE 1 (0.43 - 1.56) E 2 MH-12A (WW-12) 1-131 0/22 NA NA Cs-134 0/22 NA NA Cs-137 0/22 NA NA ZrNb-95 0/22 NA NA Co-58 0/22 NA NA Mn-54 0/22 NA NA Zn-65 0/22 NA NA Fe-59 0/22 NA NA Co-60 0/22 NA NA B a/La-140 0/22 NA NA Radionuclides that were not detected in any sample are not listed
- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).
6.5.2.6 Air Compressor Condensate and Manhole Sampling Results The presence of tritium in station air compressor condensate and manholes (Storm Drain System) has been identified since 1995 (ER_95-0704). An evaluation has been performed (S.R.1592) which states
"...leakage of tritium found in the storm drains (manholes) to ground water beneath the site will be transported by natural ground water gradient to the Connecticut River. However, at the current measured concentrations and postulated leak rate from the storm drains, the offsite dose impact is not significant
(<2.4E-5 mrem/year)."
Data provided in Table 6.3 will be filed under the requirements of 10CFR50.75(g) and is presented here in response to ER_95-0704_04 commitments. Because of revisions in the security arrangements at the plant site, there was no water available for collection in Manholes 1IH, 13 and 8 during 2010.
54
Table 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations*
Sample No.
Mean Range Location Detected**
(microcuries/ml)
(microcuries/ml)
Air Compressor Condensate 8/8 3.49E-5 (0.86-9.16) E-5 Manhole 1 IH 0/0 No Sample Available No Sample Available Manhole 13 0/0 No Sample Available No Sample Available Manhole 8 0/0 No Sample Available No Sample Available Reported per ER_950704_04.
- The fraction of sample analyses yielding detectable measurements 6.5.2.7 Groundwater Monitoring Wells Samples Results (WS)
Leakage from primary system piping between the Augmented Off Gas (AOG) Building and the Turbine Building was identified early in 2010. A large pool of subsurface water became contaminated with Tritium as a result of this leak. A large number of new groundwater sample wells were installed and a significant effort was mounted to find the leak and fix it. Presently, mitigation efforts have resulted in the extraction of more than 300000 gallons of trititated water from this subsurface pool. Dose calculations have been performed assuming that this under ground plume of contaminated water is moving towards and into the Connecticut River. The dose impacts and other details of this event are provided in the year 2010 Annual Radioactive Effluent Release Report.
6.5.3 Ingestion Pathways 6.5.3.1 Milk (TM)
Milk samples from cows at several local farms were collected monthly during 2010. Twice-per-month collections were made during the "pasture season" since the milking cows or goats were identified as being fed pasture grass during that time. Each sample was analyzed for 1-131 and other gamma-emitting radionuclides. Quarterly composites (by location) were analyzed for Sr-89 and Sr-90.
As expected, naturally-occurring K-40 was detected in all samples. Also expected was Sr-90. Sr-90 was detected in four out of 12 indicator samples and four out of eleven control samples. Although Sr-90 is a by-product of nuclear power plant operations, the levels detected in milk are consistent with that expected from worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident. The Sr-90 levels shown in Table 5.1 and Figure 6.11 are consistent with those 55
detected at other New England farms participating in other plant environmental monitoring programs.
This radionuclide and Cs-137 are present throughout the natural environment as a result of atmospheric nuclear weapons testing that started primarily in the late 1950's and continued through 1980. They are found in soil and vegetation, as well as anything that feeds upon vegetation, directly or indirectly. The detection of Cs-137 in environmental milk samples is expected and has been detected in previous years.
Cs-137 was not detected in any of the 90 samples in 2010. See Figure 6.10. It should be noted here that most of the Cs-137 concentrations and many of the Sr-90 concentrations shown on Figures 6.10 and 6.11, respectively, are considered "not detectable." All values have been plotted, regardless of whether they were considered statistically significant or not. As shown in these figures, the levels are also consistent with those detected in previous years near the VYNPS plant. There is also little actual difference in concentrations between farms.
6.5.3.2 Silage (TC)
A silage sample was collected from each of the required milk sampling stations during October. Each of these was analyzed for gamma-emitting radionuclides and 1-131. As expected with all biological media, naturally-occurring Be-7 and K-40 were detected in all samples. Naturally-occurring Ra-226 was not detected in two of the three control locations. No Cs-137 or 1-131 was detected in any sample.
6.5.3.3 Mixed Grass (TG)
Mixed grass samples were collected at each of the air sampling stations during three of the four quarters of 2010. As expected with all biological media, naturally-occurring Be-7 was detected in 18 of the 21 samples.
Naturally-occurring K-40 was detected in all samples.
Naturally-occurring Ra-226 was detected in ten of the 21 samples. Cs-I137 was not detected in any of the samples.
6.5.3.4 Fish (FH)
Semiannual samples of fish were collected from two locations in both spring and fall of 2010 for the VY REMP. Fish were also collected in response to the detection of tritium in subsurface water under the plant site in January, 2010. Several species are collected such as Walleye, Small Mouth Bass, Large Mouth Bass, Yellow Perch, White Perch, and Rock Bass. The edible portions of each of these were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally-occurring K-40 was detected in 33 of 34 samples. In addition to the analysis of edible portions, the inedible portions were also analyzed in response to the tritium leak. These fish were also analyzed for Gross Beta, H-3, Am-241, Cm-242, Cm-243/244, Fe-55, Ni-63, Pu-2328, Pu-239/240, Pu-241, Pu-242, Sr-89 and Sr-90.
56
Strontium 90 was detected in some of the inedible portions (bones, guts and skin are included in the
'inedible' portion). This is the first year in the VY REMP program that fish has been analyzed for Hard-to-Detects such as Strontium-90. The results were compared to studies done in the Hudson River by New York State officials and it was concluded that the Strontium-90 detected is a result of weapons-testing era fallout to the environment and not produced by nuclear power plants.
As shown in Table 5.1, Cs-137 was not detected in this year's samples. It should be noted that the majority of the Cs-137 concentrations plotted in Figure 6.12 are considered "not detectable." All values were plotted regardless of whether they were considered statistically significant or not. The Cs-137 levels plotted for 2010 and previous years are typical of concentrations attributable to global nuclear weapons testing fallout.
6.5.4 Direct Radiation Pathway Direct radiation was continuously measured at 53 locations surrounding the Vermont Yankee plant with the use of thermoluminescent dosimeters (TLDs).
In 1999, DR-53 was added on the site boundary. The TLDs are collected every calendar quarter for readout at the environmental laboratory. The complete summary of data may be found in Table 5.3.
From Tables 5.2 and 5.3 and Figure 6.13, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not significantly different in 2010. This indicates no significant overall increase in direct radiation exposure rates in the plant vicinity. It can also be seen from these tables that the Control TLD mean exposure rate was not significantly different than that at the Inner and Outer Rings. Figure 6.13 also shows an annual cycle at both indicator and control locations. The lowest point of the cycle occurs usually during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another Upon examining Figure 6.17, as well as Table 5.2, it is evident that in recent years, station DR-45 had a higher average exposure rate than any other station. This location is on-site, and the higher exposure rates are due to plant operations and activities in the immediate vicinity of this TLD. There is no significant dose potential to the surrounding population or any real individual from these sources since they are located on the back side of the plant site, between the facility and the river. The same can be said for station DR-46, which has shown higher exposure rates in previous years.
57
Environmental Program Trend Graphs 2010 Radiological Environmental Operating Report Vermont Yankee Graphs:
6.1 - Gross Beta Measurements on Air Particulate Filters (Average Concentrations) 6.2 - Gross Beta Measurements on Air Particulate Filters (11) 6.3 - Gross Beta Measurements on Air Particulate Filters (12) 6.4 - Gross Beta Measurements on Air Particulate Filters (13) 6.5 - Gross Beta Measurements on Air Particulate Filters (14) 6.6 - Gross Beta Measurements on Air Particulate Filters (15) 6.7 - Gross Beta Measurements on Air Particulate Filters (40) 6.8 - Gross Beta Measurement on River Water (Average Concentrations) 6.9 - Gross Beta Measurement on Ground Water (Average Concentrations) 6.10 - Cesium-137 in Milk (Annual Average Concentrations) 6.11 - Strontium 90 in Milk (Annual Average Concentrations) 6.12 - Cesium-137 in Fish (Annual Average Concentrations) 6.13 - Exposure Rate at Inner Ring, Outer Ring, and Control TLDS 6.14 - Exposure Rate at Indicator TLDS, DRO1-03 6.15 - Exposure Rate at Indicator TLDS, DR 06,50 6.16 - Exposure Rate at Site Boundary TLDS, DR 07 - 08, 41 - 42 6.17 - Exposure Rate at Site Boundary TLDS, DR 43-46 6.18 - Exposure Rate at Site Boundary TLDS, DR 47-49, 51-53 6.19 - Exposure Rate at Inner Ring TLDS, DR 09-15(odd) 6.20 - Exposure Rate at Inner Ring TLDS, DR-17-23 (odd) 6.21 - Exposure Rate at Inner Ring TLDS,DR 25-31 (odd) 6.22 - Exposure Rate at Inner Ring TLDS, DR 33-39 (odd) 6.23 - Exposure Rate at Outer Ring TLDS, DR 10 - 16 (even) 6.24 - Exposure Rate at Outer Ring TLDS, DR 18-24 (even) 6.25 - Exposure Rate at Outer Ring TLDS, DR 26-32 (even) 6.26 - Exposure Rate at Outer Ring TLDS, DR 34-40 (even) 6.27 - Exposure Rate at Control TLDS, DR 04-05 58
Figure 6.1 - Gross Beta Measurements on Air Particulate Filters - Quarterly Average Concentrations 0.04 0.035 0.03 gD*.025 2E 0.02 0.015 0.0 1 --
0,005 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year
- Indicator Stations E5Control Station 59
Figure 6.2 - Gross Beta Measurements on Air Particulate Filters E
0 3
C.
0.03 0.025 0.02 0.015 0.01 0.005 0
oW4Cu-4W 0-2010 Week Number
- -AP-1 I River Station 0
AP-21 Spofford Lake NH 60
Figure 6.3 - Gross Beta Measurements on Air Particulate Filters 0.03 0.025 0.02 E
.0 C.)
0 0.
0.015 0.01 0.005 0
2010 Week Number 0 -AP-12 North Hinsdale 0-AP-21 Spofford Lake NH 61
Figure 6.4 - Gross Beta Measurements on Air Particulate Filters 0.03 0025 0.02 0.0215' I-N 0.015 Uk 0.005 0
K)
W,
-A. M,.
O)
-4 CO-.
N IQ PJ K)*
N' N')
--,N) K3 N0 W W. w* wO w~ w" w, w0 w,,
w I,
P. 4
" O4 b.- Ci Cn 0
n CI, 2010 Week Number AP-13 Hlnsdale Substation U AP-21 Spofford Lake NH 62
Figure 6.5 - Gross Beta Measurements on Air Particulate Filters 4)
E
.0 U
0.
0.03 0.025 0.02 0.015 0.01 0.005 0
2010 Week Number AP-14 Norteld MA AP-21 Spofford Lake NH 63
Figure 6.6 - Gross Beta Measurements on Air Particulate Filters L.
0S E
CL 0.03 0.025 0.02 0.015 0.01 0.005 0
C)-N)w4CnM-4ww 2010 Week Number 0 AP-15 Tyler Hill Road 0
AP-21 Spofford Lake NH 64
Figure 6.7 - Gross Beta Measurements of Air Particulate Filters 0.035 0.03 0.025 I-E C,£ 0.
0.02 0.015 0.01 0.005 0
0 rJ W.4, Cn M -4 W (D -
rQ "
N) IQ "
tQ " rQ NJ " W W W W W W W W W W
.4,.9ý. t Jý,.0, -1ý, o. 4ý6 0 Cn M 0 MM-4WOa""W MM-4WOa""W 2010 Week Number AP-40 Govemor Hunt House 6
AP-21 Spofford Lake NH 65
Figure 6.8 - Gross Beta Measurements on River Water Semi-Annual Average Concentration
.-J 0.
4.00 3.50 3.00 2.50 2.00 1.50 1.00 0.50 n nn 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year
-"1-WR-11 River Station (3-3)
WR-21 Rt9 Brdge (3-8) 66
Figure 6.9 - Gross Beta Measurements on Ground Water Semi-Annual Average Concentrations 10.0 9.0 8.0 7.0-------
6.0 S5.0 4.0 3.0 2.0 1.0 0.0 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year
--- WG-11 Plant Well WG-12 Vernon Nursing Well WG-22 Skibniowsky Well
- WG-13 COB Well W*WG-14 Engineering Building 67
Figure 6.10 - Cesium 137 in Milk - Annual Average Concentration 10.0-9.0 8.0 7.0 Note: In 2005, milk samples analyzed at a new envronmentat laboratory with higher MVDA values for Cs-137.
6.0 5.0 4.0 3.0 2.0 1.0 0.0 4 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year 68
Figure 6.11 - Strontium 90 in Milk - Annual Average Concentrations
.J C.,
4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 --
1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year TM-1I MIler (cow)
-U-TM-22 Franklin Farm (cow)
-'-TM-14 Brown (cow)
-*-TM-25 Downey-Spencer (goat)
TM-18 Blodgett Farm (cow)
-+-TM-26 Cheney Hil
-TM-24 County Farm (control)
-TM-20 Dunklee Farm (cow) 69
Figure 6.12 - Cesium 137 in Fish - Annual Average Concentrations 80.0 70.0 60.0 Note: In 2005 fish samples were sent to a new environmental laboratory with higher MDA for Cesium-137 in fish.
50.0 40.0 30.0 20.0 10.0 0.0 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year 70
Figure 6.13 -Average Exposure Rate at Inner Ring, Outer Ring and Control TLDs 9.0 8.5 8.0 7.5 7.0 0
S6.0-5.5 5.0 4.5 4.0 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date
--4-Control Inner Ring Outer Ring 71
Figure 6.14 - Exposure Rate at Indicator TLDs, DROI-03 10.0 9.5 9.0 8.5 8.0 7.5 7.0 I-,
0.
xzi~xAll-~z7\\ATh71~k~
I 6.
5.
5.
4.
4.
0 5
5 -
0 -
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-01 River Station No. 3.3 DR-02 North Hinsdale, NH DR-03 Hinsdale Substation I
72
Figure 6.15 - Exposure Rate at Indicator TLDs, DR06 & DR-50 10.0 9.5 9.0 8.5 8.0 0
7.5 I-
- 0.
7.0 6.0 5.5 5.0 4.5 -
4.0 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-06 Vernon School U DR-50 Gov. Hunt House 73
Figure 6.16 - Exposure Rate at Site Boundary TLDs DR07, 08, 41 & 42 11 10 9
0 2
I-8 7
6 5
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-07 Site Boundary
-U-DR-08 Site Boundary DR-41 Site Boundary DR-42 Site Boundary 74
Figure 6.17 - Exposure Rate at Site Boundary TLDs - DR43 thru 46 19 18 17 16 15 14
" 13 0
12
, 11 10 9
8 7
6 5
L ~vc;N syp~
I72VA1 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-44 Site Boundary
- DR-43 Site Boundary DR-45 Site Boundary DR-46 Site Boundry 75
Figure 6.18 - Exposure Rate at Site Boundary TLDs DR47-49 & 51-53 I-0 h.
0.
0 12 11 10 9
81 7
4 I
0 I
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Ratriaval Danta DR-47 Site Boundary V DR-52 Site Boundary M DR-48 Site Boundary S DR-53 Site Boundary DR-49 Site Boundary
-DR-5I Site Boundary 76
Figure 6.19 - Exposure Rate at Inner Ring TLDs DR09, 11, 13 & 15 9
8 0
I..
06 m.
7 6
5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date U
DR-1I Inner Ring
- DR-09 Inner Ring DR-1 3 Inner Ring DR-15 Inner Ring 77
Figure 6.20 - Exposure Rate at Inner Ring TLDs DRI7, 19, 21 & 23 11 10 9
0 E.
8 7
6 5
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-17 Inner Ring DR-19 Inner Ring DR-21 Inner Ring m DR-23 Inner Ring 78
Figure 6.21 - Exposure Rate at Inner Ring TLDs DR25, 27, 29 & 31 I-I--
0.
0_
9 8.5 8
7.5 7
6.5 6
5.5 5
4.5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-25 Inner Ring G DR-27 Inner Ring DR-29 Inner Ring X DR-31 Inner Ring 79
Figure 6.22 - Exposure Rate at Inner Ring TLDs DR33, 35, 37 & 39 10 9
8 0
C.
0.
7 6
5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-33 Inner Ring U
DR-35 Inner Ring DR-37 Inner Ring DR-39 Inner Ring 80
Figure 6.23 - Exposure Rate at Outer Ring TLDs DRIO, 12, 14 & 16 10 9
8 0
- o. 7 h.
6 5
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-1 0 Outer Ring DR-12 Outer Ring DR-14 Outer Ring X DR-6 Outer Ring 81
Figure 6.24 - Exposure Rate at Outer Ring TLDs DRI8, 20, 22 & 24 11 105 10 9.5 9
8.5 0
8 4-C.
7.5 2
7 6.5 6
5.5J 5
4.5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-18 Outer Ring -U-DR-20 Outer Ring DR-22 Outer Ring X DR-24 Outer Ring 82
Figure 6.25 - Exposure Rate at Outer Ring TLDs DR26, 28, 30 & 32
-I-I..
0._
9 8.5 8
7.5 7
6.5 6
5.5 5
4.5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date 0 DR-26 Outer Ring U
DR-28 Outer Ring DR-30 Outer Ring DR-32 Outer Ring 83
Figure 6.26 - Exposure Rate at Outer Ring TLDs DR 34, 36, 38 & 40 10 9.5 9
8.5 8
411 I
0 0
0.
0E 7.5 7
0.0 6
5.5 5
4.5 4 ý-
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date
$-DR-34 Outer Ring U DR-36 Outer Ring DR-38 Outer Ring DR-40 Outer Ring 84
Figure 6.27 - Exposure Rate at Control TLDs DR04 & 05 9
I-03-0.
0I..
8.5 8
7.5 7
6.5 6
5.5 5
4.5 4
I 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Retrieval Date DR-04 Northfield, MA M*DR-05 Spofford Lake, NH I
85
7 QUALITY ASSURANCE PROGRAMS 7.1 AREVA NP Environmental Laboratory 7.1.1 The quality assurance program at the AREVA NP Environmental Laboratory (E-LAB) was designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance was applied to all steps of the measurement process, including the collection, measurement and reporting of data, as well as the record keeping of the final results. Quality control, as part of the quality assurance program, provided a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements. The E-LAB employed a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program included the use of controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits by external groups, a laboratory quality control program, and staff training by the Laboratory QA Officer and a third party cross check program administered by Analytics, Inc. Together these programs were targeted to supply QC/QA sources at 5% of the client sample analysis load. In addition a blind duplicate program was conducted through client environmental monitoring programs.
In the fourth quarter, 2010, the AREVA E-LAB TLD program was taken over by Stanford Dosimetry. Stanford Dosimetry is carrying forward the QA program developed by AREVA into year 2011 and beyond.
7.1.2 Environmental TLD Quality Assurance Program Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the E-LAB was provided by the dosimetry quality assurance testing program.
This program included independent third party performance testing by Battelle Pacific Northwest Labs (typically semi-annually) and internal performance testing conducted by the Laboratory QA Officer. Under these programs, sets of six dosimeters were irradiated to ANSI specified testing criteria and submitted for processing as "unknowns."
The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performance.
Instrumentation
- checks, although routinely performed and 86
representing between 5-10% of the TLDs processed, are not presented in this report.
Eighty four performance tests were conducted in 2010 by the E-LAB (In-house and Third party).
These tests were made on fourteen separate sets of six dosimeters. All of the fourteen TLD test sets passed the mean bias criteria of
+/-20.1%.
Of the one hundred and two individual measurements, 100% of the dosimeter evaluations met the E-LAB Internal Acceptance Criteria for bias
(+/-20.1%) and precision (+/-12.8%). Third Party QC results are summarized below.
Percentage of Individual Analyses that passed E-LAB Internal Criteria January - December 2010(1) (2)
Dosimeter Type Number
% Passed Bias Criteria
% Passed Precision Criteria Tested Panasonic Environmental 84 100 100 (1) This table summarizes results of tests conducted by the E-Lab and the Third Party tester.
(2) Environmental Dosimeter results are free in air.
Summary of Third Party Testing January - December 2010(l (2)
Dosimeter Type Exposure Period ANSI Category
% (Bias +/- SD)
Panasonic Environmental First Half 2010 II, high energy
-2.2 +/- 1.1 Panasonic Environmental Second Half 2010 II, high energy
-1.5 +/- 1.4 (1) Performance criteria are the same as the internal criteria.
(2) Results are expressed as the delivered exposure for environmental TLD.
1995 (Draft) Category II, High energy photons (Cs-I137 or Co-60).
ANSI HPS N13.29-Percentage of Mean Dosimeter Analyses (N=6) which Passed Tolerance Criteria January-December 2010(1) (2)
Dosimeter Type Number of Evaluations I % Passed Tolerance Limit Panasonic Environmental (2) 14 100 (1) This table summarizes results of tests conducted by the E-Lab and the Third Party tester.
(2) Environmental Dosimeter results are free in air.
87
7.2 Teledyne Brown Engineering Laboratory -Environmental Services (TBE-SE) 7.2.1 Operational Quality Control Scope 7.2.1.1 Inter-laboratory The TBE-ES Laboratory QC Program is designed to monitor the quality of analytical processing associated with environmental, effluent (I OCFR Part 50), and waste characterization (1 OCFR Part
- 61) samples.
Quality Control of environmental radioanalyses involves the internal process control program and independent third party programs administered by Analytics, Inc and Environmental Resource Associates (ERA).
TBE-ES participates in the Quality Assessment Program (QAP) administered by the Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP). The MAPEP is a set of performance evaluation samples (e.g. water, soil, air filters, etc.) designed to evaluate the ability and quality of analytical facilities performing sample measurements which contain hazardous and radioactive (mixed) analytes.
Quality Control for radioanalyses during this reporting period was divided among internal process check samples, third party process checks prepared by Analytics, Inc. (which was submitted by users or secured directly by TBE-ES for QC purposes), ERA, and DOE's MAPEP.
7.2.1.2 Intra-laboratory The internal Quality Control program is designed to include QC functions such as instrumentation checks (to ensure proper instrument response), blank samples (to which no analyte radioactivity has been added), instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and process controls. Both process control and qualification analyses samples seek to mimic the media type of those samples submitted for analyses by the various laboratory clients. These process controls (or process checks) are either actual samples submitted in duplicate in order to evaluate the accuracy of laboratory measurements, or blank samples which have been "spiked" with a known quantity of a radioisotope that is of interest to laboratory clients. These QC samples, which represent either "single" or "double-blind" unknowns, are intended to evaluate the entire radiochemical and radiometric process.
To provide direction and consistency in administering the quality assurance program, TBE-ES has developed and follows an annual quality control and audit assessment schedule. The plan describes the scheduled frequency and scope of Quality Assurance and Control considered necessary for an adequate QA/QC program conducted throughout the year. The magnitude of the process control program combines both internal and external sources targeted at 5% of the routine sample analysis load.
7.2.1.3 QA Program (Internal and External Audits)
During each reporting period at least one internal assessment is conducted in accordance with the pre-established TBE-ES Quality Control and Audit Assessment Schedule. In addition, the laboratory may be audited by prospective customers during a pre-contract audit, and/or by existing clients who wish to conduct periodic audits in accordance with their contractual 88
arrangements. The Nuclear Utilities Procurement Issues Committee (NUPIC) conducts audits of TBE-ES as a function of a Utilities Radiological Environment Measurement Program (REMP).
TBE-ES Laboratory-Knoxville has successfully completed the New York State Department of Health's Environmental Laboratory Approval Program (NELAP), Nuclear Fuel Services, Manufacturing Sciences Corporation and State of Tennessee audits. These audits were each a comprehensive review of TBE-ES's Quality and Technical programs used to assess the laboratory's ability to produce accurate and defensible data. No significant deficiencies, which would adversely impact data quality, were identified during any of these audits. Administrative findings identified during these inspections are usually addressed promptly, according to client specifications.
7.2.2 Analytical Services Quality Control Synopsis 7.2.2.1 Results Summary 7.2.2.1.1 Environmental Services Quality Control During this annual reporting period, twenty-seven nuclides associated with six media types were analyzed by means of the laboratory's internal process control, Analytics, ERA and DOE quality control programs. Media types representative of client company analyses performed during this reporting period were selected. The results for these programs are presented in Tables 7.2.
Below is a synopsis of the media types evaluated:
Air Filter Charcoal (Air Iodine)
Milk Soil Vegetation Water 7.2.2.1.2 Analytics Environmental Cross-Check Program Thirteen nuclides were evaluated during this reporting period. Iron-55 in water was added to the Analytics program and removed from the DOE MAPEP program in 2010 due to the low level of Fe-55 activity in the MAPEP samples. All environmental analyses performed were within the acceptable criteria.
7.2.2.1.3 Summary of Participation in the Department of Energy (DOE) Monitoring Program TBE-ES participated in the semi annual Mixed Analyte Performance Evaluation Program (MAPEP) for liquid, air particulate, soil, and vegetation analyses (MAPEP-Series 22 and 23). During this reporting period, 18 nuclides were evaluated. All but one of the 18 environmental analyses performed were within the acceptable criteria. In one water sample, Pu-238 and Pu-239/240 failed low. It is believed a more hearty preparation method will resolve the problem. The sample is being rerun using a fusion preparation method. No Vermont Yankee samples were affected during this period.
89
7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, 13 nuclides were analyzed under ERA criteria. Gross alpha in an air particulate by digestion method was added to the ERA program in May 2010.
All but one of the environmental analytical results were acceptable. The Sr-89 in water sample was evaluated as failed with a ratio of 1.14. TBE considers this an acceptable result. No action was taken. The Zn-65 in water sample was evaluated as failed low.
The result was incorrectly submitted as 11.0 pCi/L. The actual result was 111.0 pCi/L, which compared well with the known value of 102 pCi/L.
7.2.2.2 Intra-Laboratory Process Control Program The TBE-ES Laboratory's internal process control program evaluated 5046 individual samples.
7.2.2.2.1 Spikes All but 10 of the 1545 environmental spikes were analyzed with statistically appropriate activity reported for each spike. The affected work orders were reanalyzed or a case narrative documented the reason the sample could not be reanalyzed.
7.2.2.2.2 Analytical Blanks During this reporting period, all but four of the 1545 environmental analytical blanks analyzed reported less than MDC. The activity detected for the four blanks is indistinguishable from natural background.
7.2.2.2.3 Duplicates All but two of 1956 duplicate sets analyzed were within acceptable limits. One of the duplicate sets was not homogeneous and could not be dried and blended because of the requested analysis. The other duplicate set was not rerun at the request of the client.
7.2.2.2.4 Non-Conformance Reports There were nine non-conformance reports issued for this reporting period. No ENNVY data was impacted by the non-conformance in each of these cases.
90
7.3 J.A. FITZPATRICK ENVIRONMENTAL LABORATORY
- QUALITY ASSURANCE /
QUALITY CONTROL PROGRAM 7.3.1. PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring.
To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.
Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the JAF Environmental Laboratory using standard laboratory procedures. Analytics issues a statistical summary report of the results. The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.
The JAF Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples.
The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts.
91
7.3.2 PROGRAM SCHEDULE SAMPLE PROVIDER SAMPLE LABORATORY ECKERT&IEER MEDI ANAYSISECKERT & ZIEGLER MEDIA ANALYSISANLTC ANALYTICS Water Gross Beta 3
Water Tritium 5
Water 1-131 4
Water Mixed Gamma 4
Air Gross Beta 3
Air 1-131 4
Air Mixed Gamma 2
Milk 1-131 3
Milk Mixed Gamma 3
Soil Mixed Gamma 1
Vegetation Mixed Gamma 2
TOTAL SAMPLE INVENTORY 34 7.3.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.
7.3.3.1 SAMPLE RESULTS EVALUATION Samples provided by Analytics are evaluated using what is specified as the NRC method.
This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).
92
An Environmental Laboratory analytical result is evaluated using the following calculation:
The value for the error resolution is calculated.
The error resolution =
Reference Result Reference Results Error (1 sigma)
Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given.
The value for the ratio is then calculated.
Ratio of Agreement QC Result Reference Result If the value falls within the agreement interval, the result is acceptable.
TABLE 7.3.1 ERROR RESOLUTION RATIO OF AGREEMENT
< 4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 51 to 200 0.8 to 1.25
>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately +/- 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.
93
7.3.4 PROGRAM RESULTS
SUMMARY
The Interlaboratory Comparison Program numerical results are provided on Table 7.2.2.
7.3.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2010 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.
" Air Charcoal Cartridge: 1-131
" Air Particulate Filter: Mixed Gamma Emitters, Gross Beta Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta Soil: Mixed Gamma Emitters Milk: 1-131, Mixed Gamma Emitters Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 129 individual analyses on the 34 QA samples. Of the 129 analyses performed, 129 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.
There were no nonconformities in the 2010 program.
94
7.3.4.2 NUMERICAL RESULTS TABLES TABLE 7.3.2 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
MEDIUM ANALYSIS pCi +/- 1 sigma pCi +/-1 sigma RATIO (1) 06/17/2010 E7090-05 Filter 8.61E+01
+/-
2.30E+00 GROSS 8.15E+01
+/-
2.24E+00 8.04E+01 +/- 1.34E-i-1.05 A
BETA 8.63E+01
+/-
2.30E+00 Mean= 8.46E+01
+/-
1.31E+00 06/17/2010 E7097-09 Filter 5.99E+01
+/-
1.92E+00 GROSS 5.89E+01
+/-
1.91E+00 539E+01
+/- 9.01E-01 1.10 A
BETA 5.98E+01
+/-
1.92E+00 Mean= 5.95E+01
+/-
1.I1E+00 12/09/2010 E7354-05 Filter 9.69E+01
_+/- 1.39E+00 GROSS 9.46E+01
_+/- 1.38E+00 8.92E+01
+/- I.49E+0 1.07 A
BETA 9.39E+01
+/-
1.37E+00 Mean= 9.51E+0 I
+/-
7.98E-01 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 95
TABLE 7.3.2 (Continued)
Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
MEDIU1 ANALYSI pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (1) 3/18/2010 E7020-05 Water H-3 3.48E+03
+/-
1.53E+02 3.57E+03
+/-
.53E+02 3.41E+03 5.70E+01 1.03 A
3.53E+03
+/-
1.53E+02 Mean= 3.53E+03
+/-
8.83E+01 06/17/2010 E7089-05 Water H-3 1.14E+03
+/-
1.33E+02 1.13E+03
+/-
1.32E+02 1.04E+03
+/-
1.32E+02 1.00E+03
+/-
1.29E+02 9.58E+02 1 1.60E+0I 1.13 A
1.07E+03
+/-
1.30E+02 1.13E+03
+/-
1.30E+02 Mean=
1.09E+03
+/-
5.35E+01 9/16/2010 E7187-05 Water H-3 8.82E+02
+/-
1..3 1 E+02 8.54E+02
+/-
1.31E+02 8.96E+02 +/-
1.50E+01 1.01 A
9.74E+02
+/-
1.32E+02 Mean= 9.03E+02
+/-
7.58E+01 12/9/2010 E7329-09 Water H-3 1.00E+04
+/-
2.04E+02 1.OE+04
+/-
2.04E+02 9.96E+03 +/- 1.66E+02 1.00 A
9.9 tE+03
+/-
2.04E+02 Mean= 9.98E+03
+/-
1.1 8E+02 12/9/2010 E7330-09 Water H-3 9.78E+03
+/-
2.03E+02 9.83E+03
+/-
2.03E+02 9.96E+03 +/-
1.66E+0 0.99 A
1.01E+04
+/-
2.05E+02 Mean= 9.90E+03
+/-
1.18E+02 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 96
TABLE 7.3.2 (Continued)
Gross Beta Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter 1 sigma RATIO (1) 03/18/2010 E7023-05 Water 2.58E+02
+/-
2.50E+00 GROSS 2.57E+02
+/-
2.50E+00 2.60E+02 4.35E+00 0.98 A
BETA 2.54E+02
+/-
2.50E+00 Mean = 2.56E+02
+/-_ 1.44E+00 06/17/2010 E7095-05 Water 1.78E+02
+/-
2.1OE+00 GROSS 1.78E+02
+/-
2.1OE+00 1.88E+02 3.14E+00 0.95 A
BETA 1.79E+02
+/-
- 2. 1OE+00 Mean=
1.78E+02
+/-
1.21E+00 09/16/2010 E7192-05 Water 2.30E+02
+/-
2.40E+00 GROSS 2.28E+02
+/-
2.40E+00 BETA 2.26E+02
+/-
2.40E+00 2.18E+02
+/- 3.64E+00 1.04 A
2.25E+02
+/-
2.40E+00 1 Mean =
2.27E+02
+/-
1.20E+00 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 97
TABLE 7.3.2 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
MEDIUM ANALYSIS pCi +/-1 sigma pCi +1 sigma RATIO (1) 3/18/2010 E6993-09 Air 8.62E+0I
+/-
2.23E+00 8.27E+01
-+/- 2.88E+00 1-131 8.1OE+-01
-+/- 1.81E+00 8.52E+01
+/-
1.42E+00 0.99 A
8.90E+01
+/-
3.65E+00 Mean = 8.47E+0 I +/-
.37E+00 06/17/2010 E7093-05 Air 7.94E+01
_+/- 1.45E+00 1-131 7.64E+01
+/-
2.98E+00 798E+01
+/- 1.33E+00 0.99 A
8.08E+01
_+/- 3.07E+00 Mean = 7.89E+01
+/-
1.51E+00 9/16/2010 E7191-05 Air 6.01E+01
+/-
1.25E+00 6.39E+01
+/-+ 2.24E+00 1-131 6.OOE+01
_+/- 1.00E+00 1.03 A
6.06E+01
_+/- 2.OOE+00 Mean = 6.15E+0I
+/-
1.08E+00 9/16/2010 E7183-09 Air 6.09E+01
+/-
2.23E+00 1-131 6.19E+01
+/-
2.83E+00 5.97E+0I
+/-
9.97E-01 1.03 A
6.08E+01
+/-
2.98E+00 Mean =
6.12E+01
+/-
1.56E+00 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 98
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
IMEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma I RATIO (])
3/18/2010 E7021-05 Water Ce-141 2.73E+02 2.7 1E+02 2.75E+02 Mean = 2.73E+02
+/-
+
7.49E+00 3.53E+00 7.24E+00 3.67E+00 2.63E+02
+/- 4.40E+00 1.04 A
3.42E+02
+/-
2.97E+01 Cr-51 3.84E+02
+/-
1.29E+01 3.64E+02 +/- 6.08E+00 1.03 A
3.98E+02
+/-
2.76E+01 Mean = 3.75E+02
+/-
1.42E+01 2.03E+02
+/-
5.40E+00 Cs-134 1.91E+02
+/-
5.85E+00 1.79E+02
+/- 2.99E+00 1.09 A
1.91E+02
+/-
3.29E+00 Mean =
1.95E+02
+/-
2.87E+00 1.64E+02
+/-
5.04E+00 Cs-137 1.56E+02
+/-
5.67E+00 1.59E+02
+/- 2.66E+00 1.01 A
1.60E+02
+/-
2.90E+00 Mean=
1.60E+02
+/-
2.71E+00 1.47E+02
+/-
4.50E+00 1.46E+02
+/-
5.39E+00 Co-58 1.44E+02
+/- 2.40E+00 1.03 A
1.5 1E+02
+/-
2.73E+00 Mean=
1.48E+02
+/-
2.5 1E+00 2.24E+02
+/-
5.62E+00 2.24E+02
+/-
6.45E+00 Mn-54 222E+02
+/-
337E+00 2.09E+02
+/- 3.49E+00 1.07 A
Mean =
2.23E+02
+/-
3.07E+00 1.48E+02
+/-
5.43E+00 Fe-59 1.54E+02
+/-
6.52E+00 1.38E+02
+/- 2.31E+00 1.09 A
1.52E+02
+/-
3.26E+00 Mean =
1.51E+02
+/-
3.03E+00 2.92E+02
+/-
1.02E+0I Zn-65 2.66E+02
+/-
1.14E+0 2.56E+02 +/- 4.27E+00 1.09 A
2.77E+02
+/-
5.88E+00 Mean = 2.79E+02
+/-
5.45E+00 1.85E+02
+/-
3.89E+00 Co-60 1.91E+02
+/-
4.64E+00 1.85E+02
+/- 3.08E+00 1.03 A
1.92E+02
+/-
2.41E+00 Mean =
1.90E+02
+/-
2.17E+00 1-131**
7.11 E+01 7.53E+01 7.43E+01 Mean = 7.36E+01
+
+
+
+
7.18E-01 1.91 E+00 1.79E+00 9.05E-01 7.22E+01
+/- 1.21E+OC 1.02 A
(1) Ratio = Reported/Analytics.
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 99
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
IMEDIUMI ANALYSIS pCi/liter +/-1 sigma pCi/liter +1 sigma RATIO (1) 6/17/2010 E7096-09 Water Ce-141 1.70E+02 1.74E+02 1.74E+02 Mean =
1.73E+02
+
+
+
+
3.17E+00 2.83E+00 5.76E+00 2.39E+00 1.61E+02
+/- 2.68E+00 1.07 A
5.26E+02 t
1.5]E+01 Cr-51 5.12E+02
+/-
1.62E+01 4.94E+02
+/- 8.25E+00 0.99 A
4.31E+02
+/-
2.96E+01 Mean = 4.90E+02
+/-_ 1.23E+01 2.01E+02
+/-
2.33E+00 1.92E+02
_+ 2.77E+00 Cs-134 1.92E+02
+/-
2.77E+00 1.83E+02
+/- 3.06E+00 1.08 A
2.02E+02
+/-
5.04E+00 Mean =
1.98E+02
+/-
2.07E+00 2.26E+02
+/-
2.44E+00 Cs-137 2.22E+02
+/-
2.74E+00 2.18E+02
+/- 3.65E+00 1.04 A
2.30E+02
+/-
5.25E+00 Mean =
2.26E+02
+/-
2.13E+00 1.57E+02
+/-
2.11E+00 Co-58 1.55E+02
+/-
2.49E+00 1.47E+02
+/- 2.46E+00 1.07 A
1.61E+02
+/-
4.68E+00 Mean =
1.58E+02
+/-_ 1.90E+00 2.7 1E+02
+/-
2.63E+00 Mn-54 2.74E+02
+/-
3.01E+00 246E+02
+/- 4.11E+00 1.10 A
2.67E+02
+/-
5.56E+00 Mean =
2.7 1E+02
+/-
2.28E+00 1.89E+02
+/-
2.77E+00 Fe-59 1.91E+02
+/-
3.27E+00 1.73E+02
+/- 2.89E+00 1.08 A
1.80E+02
+/-
5.96E+00 Mean =
1.87E+02
+/-
2.45E+00 3.29E+02
+/-
4.42E+00 3.34E+02
_+/- 5.42E+00 Zn-65 3.00E+02
+/- 5.00E+00 1.11 A
3.38E+02
+/-
1.01E+01 Mean = 3.34E+02
+/-
4.1OE+00 2.99E+02
+/-
2.06E+00 Co-60 2.99E+02
+/-
2.44E+00 2.86E+02
+/- 4.78E+00 1.05 A
3.00E+02
+/-
4.55E+00 Mean =
2.99E+02
+/-_ 1.85E+00 1-131**
8.15E+01 8.24E+0 I 7.94E+0 I Mean=
8.11E+01
+
+
+
+
2.25E+00 2.76E+00 4.13E+00 1.36E+00 7.89E+0 I
+/- 1.32E+00 1.03 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 100
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE ]
JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
[MEDIUM ANALYSIS pCi/liter +/-1 sigma pCi/liter +/-1 sigma RATIO (1) 9/16/2010 E7188-05 Water Ce-141 1.77E+02 1.80E+02 1.8 1E+02 Mean =
1.79E+02
+
+
+
+
5.28E+00 5.73E+00 3.26E+00 2.82E+00 1.65E+02
+/- 2.76E+00 1.09 A
3.44E+02
+/-
2.19E+01 Cr-51 3.07E+02
+/-
2.85E+01 2.97E+02
+/- 4.95E+00 1.06 A
2.96E+02
+/-
1.48E+01 Mean=
3.16E+02
+/-
1.30E+01 1.22E+02
+/-
3.92E+00 Cs-134 1.23E+02
+/-
5.49E+00 1.18E+02
+/- 1.97E+00 1.05 A
1.27E+02
+/-
2.77E+00 Mean =
1.24E+02
+/-
2.43E+00 1.26E+02
+/-
3.82E+00 Cs-137 1.28E+02
+/-
5.01E+00 1.20E+02
+/- 2.OOE+00 1.05 A
1.25E+02
+/-
2.61E+00 Mean =
1.26E+02
+/-
2.27E+00 1.03E+02
+/-
3.43E+00 1.02E+02
+/-+ 4.76E+00 Co-58 9.35E+01
+/- 1.56E+00 1.09 A
1.02E+02
+/-
2.29E+00 Mean =
1.02E+02
+/-
- 2. 1OE+00 1.75E+02
+/-
4.26E+00 Mn-54 1.70E+02
+/-
5.72E+00 1.52E+02
+/- 2.53E+00 1.11 A
1.62E+02
+/-
2.88E+00 Mean =
1.69E+02
+/-
2.56E+00 1.36E+02
+/-
4.41E+00 Fe-59
.31E+02
+/-
6.05E+00
- 1. 16E+02
+/- 1.93E+00 1.13 A
1.25E+02
+/-
3.16E+00 Mean=
1.31E+02
+/-
2.71E E+00 2.98E+02
+/-
8.60E+00 Zn-65 2.99E+02
+/-
1.18E+01 2.59E+02
+/- 4.32E+00 1.11 A
2.69E+02
+/-
5.86E+00 Mean =
2.89E+02
+/-
5.24E+00 2.3 1E+02
+/-
3.65E+00 Co-60 2.29E+02
+/-
4.92E+00 2.17E+02
+/- 3.62E+00 1.06 A
2.28E+02
+/-
2.54E+00 Mean =
2.29E+02
+/-
2.2 1E+00 1-131**
Mean =
6.90E+0 I 6.42E+0 1 6.61 E+0 I 6.64E+0 I
+
+
+
+
1.37E+00 1.45E+00 9.53E-01 7.37E-0I 6.44E+01
+/-
1.08E+00 1.03 A
Mean
=
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 101
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE I
ID NO.
I MEDIUMI ANALYSISI pCi/liter +/-1 sigma I
pCi/liter +/-1 sigma
[ RATIO (1) 12/9/2010 E7331-09 Water Cr-51 4.9 1E+02 5.43E+02 5.16E+02 4.58E+02 Mean = 5.02E+02
+
+
+
+
2.87E+0 I 3.76E+01 2.87E+01I 1.97E+01I 1.47E+01 4.55E+02 +/- 7.59E+00 1.10 A
1.69E+02
+/-
5.25E+00 1.67E+02
+/-
6.23E+00 Cs-134 1.65E+02
+/-
4.60E+00 1.57E+02
+/- 2.62E+00 1.07 A
1.74E+02
+/-
3.22E+00 Mean =
1.69E+02
+/-
2.47E+00 1.75E+02
+/-
4.94E+00 1.72E+02
+/-
5.94E+00 Cs-137 1.92E+02
+/-
4.68E+00 1.86E+02
+/- 3.10E+00 0.97 A
1.80E+02
+/-
3.30E+00 Mean =
1.80E+02
+/-
2.40E+00 1.00E+02
+/-
4.24E+00 9.84E+01
+/-
4.80E+00 Co-58 8.82E+01
+/-
3.81E+00 9.00E+01
+/-
1.50E+00 1.06 A
9.50E+01
+/-
2.65E+00 Mean = 9.54E+0I
+/-
1.98E+00 1.27E+02
+/-
4.46E+00 1.28E+02
+/-
5.50E+00 Mn-54 1.35E+02
+/-
4.23E+00 1.19E+02
+/- 1.99E+00 1.09 A
1.29E+02
+/-
3.09E+00 Mean=
1.30E+02
+/-
2.20E+00 1.45E+02
+/-
5.91E+00 1.52E+02
+/-
7.49E+00 Fe-59 1.63E+02
+/-
5.62E+00 1.31E+02
+/- 2.18E+00 1.16 A
1.48E+02
+/-
3.96E+00 Mean=
1.52E+02
+/-
2.94E+00 1.84E+02
+/-
8.71E+00 1.98E+02
+/-
1.17E+01 Zn-65 1.78E+02
+/-
8.42E+00 1.74E+02
+/- 2.90E+00 1.08 A
1.94E+02
+/-
5.99E+00 Mean =
1.89E+02
+/-
4.47E+00 3.1OE+02
+/-
4.96E+00 3.17E+02
+/-
6.06E+00 Co-60 3.09E+02
+/-
4.57E+00 3.00E+02 +/- 5.01E+00 1.04 A
3.11E+02
+/-
3.28E+00 Mean=
3.12E+02
+/-
2.41E+00 1-131**
1.02E+02 1.02E+02 9.89E+01 Mean =
1.01E+02
+
+
+
+/-
4.19E+00 3.8 1E+00 3.5 1E+00 2.22E+00 1.00E+02
+/-
1.67E+00 1.01 (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 102
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
IMEDIUM ANALYSISJ pCi/liter +/-1 sigma I
pCi/liter +/-1 sigma RATIO (1) 3/18/2010 E6994-09 MILK Ce-141 2.68E+02 2.57E+02 2.68E+02 2.89E+02 Mean = 2.70E+02
+/-
+
+_
+
5.38E+00 5.37E+00 1.13E+0I 1.22E+01 4.58E+00 2.61E+02
+/- 4.36E+OC 1.04 A
3.55E+02
+/-
2.53E+01 3.72E+02
+/-
2.34E+01 Cr-51 3.55E+02
+/-
5.27E+01 3.61E+02
+/- 6.03E+00 0.93 A
2.65E+02
+/-
5.45E+01 Mean =
3.37E+02
+/-
2.08E+01 1.79E+02
+/-
3.95E+00 1.79E+02
+/-
4.62E+00 Cs-134 1.88E+02
+/-
9.01E+00 1.78E+02
+/- 2.97E+00 1.00 A
1.68E+02
+/-
9.01E+00 Mean=
1.78E+02
+/-
3.53E+00 1.60E+02
+/-
3.88E+00 1.51E+02
+/-
3.78E+00 Cs-137 1.64E+02
+/-
8.33E+00 1.58E+02
+/- 2.64E+00 1.02 A
1.68E+02
+/-
8.03E+00 Mean=
1.61E+02
+/-
3.19E+00 1.44E+02
+/-
4.03E+00 1.39E+02
+/-
3.85E+00 Co-58 1.47E+02
+/-
8.42E+00 1.43E+02
+/- 2.38E+00 1.00 A
1.43E+02
+/-
7.40E+00 Mean =
1.43E+02
+/-
3.13E+00 2.15E+02
+/-
4.39E+00 2.22E+02
+/-
4.68E+00 Mn-54 2.24E+02
+/-
9.49E+00 2.07E+02
+/- 3.46E+00 1.04 A
2.01E+02
+/-
8.96E+00 Mean = 2.15E+02
+/-
3.64E+00 1.58E+02
+/-
5.27E+00 1.44E+02
+/-
5.27E+00 Fe-59 1.66E+02
+/-
1.03E+01 1.37E+02
+/- 2.29E+00 1.08 A
1.25E+02
+/-
9.91E+00 Mean=
1.48E+02
+/-
4.03E+00 2.67E+02
+/-
8.17E+00 2.75E+02
+/-
8.77E+00 Zn-65 2.56E+02
+/-
1.73E+01 2.54E+02
_ 4.24E+00 1.05 A
2.70E+02
+/-
1.75E+01 Mean=
2.67E+02
+/-
6.84E+00 1.79E+02
+/-
3.25E+00 1.83E+02
+/-
3.41E+00 Co-60 1.81E+02
+/-
6.73E+00 1.83E+02
- 3.06E+00 0.99 A
1.82E+02
+/-
6.34E+00 Mean=
1.81E+02
+/-
2.59E+00 1-131**
6.62E+0 I 7.40E+0I 6.96E+0 I Mean = 6.99E+01
+
+
+
+
7.99E+00 4.47E+00 1.09E+01 3.56E+00 7.40E+01
+/-
1.24E+00 0.95 A
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 103
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB* I DATE I
ID NO.
IMEDIUMj ANALYSIS pCi/liter +/- 1 sigma I
pCi/liter +/- 1 sigma RATIO (1) 06/17/2010 E7091-05 MILK Ce-141 1.25E+02 1.12E+02 1.20E+02 Mean =
1.19E+02
+
+/-
6.24E+00 3.98E+00 3.14E+00 2.68E+00 1.1OE+02
+/-
1.84E+00 1.08 A
3.59E+02
+/-
2.85E+01 Cr-51 3.27E+02
+/-
2.01E+0 3.39E+02
+/- 5.66E+00 1.03 A
3.62E+02
+/-
1.54E+01 Mean =
3.49E+02
+/-
1.27E+01I 1.42E+02
+/-
4.64E+00 Cs-134 1.31E+02
+/-
3.44E+00 1.26E+02 +/- 2.10E+00 1.07 A
1.32E+02
+/-
2.43E+00 Mean =
1.35E+02
+/-
2.09E+00 1.49E+02
+/-
4.82E+00 Cs-137 1.51E+02
+/-
3.23E+00 1.50E+02
+/- 2.51E+00 1.00 A
1.48E+02
+/-
2.48E+00 Mean =
1.49E+02
+/-
2.1 OE+00 1.16E+02
+/-
4.40E+00 Co-58 1.06E+02
+/-
3.02E+00 1.0OE+02 +/- 1.69E+00 1.09 A
1.09E+02
+/-
2.34E+00 Mean =
1.1 OE+02
+/-_ 1.94E+00 1.87E+02
+/-
5.30E+00 Mn-54 1..84E+02
+/-
3.59E+00 169E+02
+/- 2.82E+00 1.09 A
1.82E+02
+/-
2.67E+00 Mean=
1.84E+02
+/-
2.31E+00 1.34E+02
+/-
5.61E+00 Fe-59 1.24E+02
+/-
4.OE+00 1. 19E+02
+/- 1.98E+00 1.10 A
1.34E+02
+/-
3.04E+00 Mean=
1.31E+02
+/-
2.53E+00 2.37E+02
+/-
8.94E+00 Zn-65 2.17E+02
+/-
6.80E+00 206E+02
+/- 3.44E+00 1.10 A
2.25E+02
+/-
4.84E+00 Mean =
2.26E+02
+/-
4.08E+00 1.97E+02
+/-
4.13E+00 Co-60 2.05E+02
+/-
2.91.E+00 197E+02 +/- 3.28E+00 1.02 A
2.OOE+02
+/-
2.21E+00 Mean = 2.01E+02
+/-
1.84E+00 1-131 1-13 1 **
9.92E+0 I 9.79E+0 I 9.89E+0 I 7.87E+01 8.03E+0 I 7.97E+0 I Mean=
8.91E+01
+
+
+/-
+/-
+/-
5.23E+00 3.75E+00 2.6 1E+00 2.26E+00 2.25E+00 2.65E+00 1.35E+00 9.69E+01
+/- 1.62E+OC 0.92 A
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 104
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
IMEDIUM ANALYSIS pCi/liter +/- 1 sigma pCi /liter +/- I sigma RATIO (1) 9/16/2010 E7190-05 MILK Ce-141 1.35E+02 1.40E+02 1.34E+02 1.35E+02 Mean =
1.36E+02
+
+
+
+
+
4.99E+00 6.52E+00 2.58E+00 5.26E+00 2.52E+00 1.30E+02
+/- 2.17E+00 1.05 A
2.49E+02
+/-
2.21E+0I 2.27E+02
+/-
2.7 1E+0I Cr-51 2.33E+02 1 1.05E+01 2.34E+02
+
3.90E+00 0.99 A
2.16E+02 2.56E+0I Mean=
2.3 1E+02
+
1.11E+01 9.92E+01
+
4.27E+00 8.97E+01
+
4.93E+00 Cs-134 9.70E+01 I 1.86E+00 9.30E+01
+
1.55E+00 1.03 A
9.80E+01
+/-
4.44E+00 Mean =
9.60E+01
+/-
2.03E+00 9.91E+0I
+/-
3.97E+00 9.37E+01
+/-
4.70E+00 Cs-137 9.49E+01 1 1.85E+00 9.45E+0I
+
1.58E+00 1.01 A
9.23E+01
+/-
4.43E+00 Mean=
9.50E+01
-+/-
1.95E+00 8.06E+01
+/-
3.62E+00 7.76E+01
+/-
4.54E+00 Co-58 7.55E+01 1 l.63E+00 7.37E+01
+/-
1.23E+00 1.03 A
7.04E+01 I 4.30E+00 Mean=
7.60E+01 1 1.85E+00 1.22E+02
+/-
4.15E+00 1.18E+02
+/-
5.14E+00 Mn-54 1.28E+02
+
2.02E+00 1.19E+02
+/- 1.99E+00 1.03 A
1.24E+02
+/-
5.06E+00 Mean=
1.23E+02
+/-
2.14E+00 9.75E+01
+/-
4.86E+00
- 1. 14E+02 6.59E+00 Fe-59 1.03E+02
+
2.32E+00 9.11E+01
+/-
1.52E+00 1.14 A
1.01E+02
+
5.87E+00 Mean=
1.04E+02 2.58E+00 2.16E+02 8.69E+00 1.79E+02
+
1.13E+0I Zn-65 2.20E+02 3.99E+00 2.04E+02
+/- 3.40E+00 1.01 A
2.12E+02 1 l.05E+01 Mean =
2.07E+02
+/-
4.54E+00 1.79E+02
+/-
3.90E+00 1.82E+02
+/-
4.79E+00 Co-60 1.73E+02
+
1.78E+00 1.71E+02
+/-
2.85E+00 (1.03 A
1.70E+02
+/-
4.43E+00 Mean =
1.76E+02
+/-
1.95E+00 1-131**
8.62E+01 8.50E+01 8.61E+01 Mean =
8.58E+01
+
+
+
+
1.61E+00 1.23E+00 1.67E+00 8.75E-01 9.41E+01
+
1.57E+00 0.91 A
I (1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
A=Acceptable U=Unacceptable 105
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter I SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO. IMEDIU ANALYSI pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 3/18/2010 E7022-05 FILTER Ce-141 2.08E+02 2.18E+02 2.14E+02 Mean = 2.13E+02
+
+
+
+
3.64E+00 3.88E+00 4.19E+00 2.26E+00 2.04E+02 +/- 3.40E+0(
1.05 A
2.97E+02
+/-
1.61E+01 Cr-51 2.57E+02 +/-
1.62E+01 2.81E+02 +/- 4.70E+0(
1.02 A
3.07E+02
+/-
1.80E+01 Mean = 2.87E+02
+/-
9.69E+00 1.55E+02
+/-
4.98E+00 Cs-134 1.50E+02
+/-
5.13E+00 1.38E+02 +/- 2.31E+0 1.09 A
1.48E+02
+/-
5.24E+00 Mean = 1.5 1E+02
+/-
2.95E+00 1.25E+02
+/-
3.96E+00 Cs-137 1.32E+02
+/-
4.21E+00 1.23E+02 +/- 2.05E+0(
1.02 A
1.21E+02
+/-
4.14E+00 Mean = 1.26E+02
+/-
2.37E+00 1.16E+02
+/-
3.89E+00 Co-58 1..17E+02
+/-
4.01E+00 I11E+02 +/- 1.86E+0(
1.05 A
1.18E+02
+/-
3.93E+00 Mean = 1.17E+02
+/-
2.28E+00 1.76E+02
+/-
4.64E+00 Mn-54 1.84E+02
+/-
5.17E+00 1.62E+02 +/- 2.70E+0(
1.10 A
1.77E+02
+/-
4.98E+00 Mean = 1.79E+02
+/-
2.85E+00 1.22E+02
+/-
4.88E+00 Fe-59 1.16E+02
+/-
5.13E+00 1.07E+02 +/- 1.78E+0C 1.12 A
1.23E+02
+/-
5.25E+00 Mean =
1.20E+02
+/-
2.94E+00 2.31E+02
+/-
8.72E+00 Zn-65 2.28E+02
+/-
9.46E+00 1.98E+02 +/- 3.30E+0 1.12 A
2.05E+02
+/-
8.99E+00 Mean= 2.21E+02
+/-
5.23E+001 Co-60 1.36E+02 1.37E+02 1.43E+02 Mean = 1.39E+02
+_
+_
_+
3.50E+00 3.73E+00 3.59E+00 2.08E+00 1.43E+02 +/- 2.38E+OC 0.97 A
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 106
TABLE 7.3.2(Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE I ID NO.
IMEDIUMI ANALYSIS I pCi +/-1 sigma pCi +/-1 si gma RATIO (1) 9/16/2010 E7189-05 FILTER Ce-141 1.28E+02 1.30E+02 1.26E+02 Mean =
1.28E+02
,+
,+
,+
2.65E+00 2.67E+00 1.38E+00 1.34E+00 1.26E+02
+/-
2.10E+00 1.02 A
2.28E+02
+/-
1.35E+01 Cr-51 2.28E+02
+/-
1.38E+0 2.26E+02
+/- 3.77E+00 1.01 A
2.3 I E+02
+/-
6.90E+00 Mean =
2.29E+02
+/-
6.83E+00 1.02E+02
+/-
3.84E+00 Cs-134 9.09E+01
+/-
3.81E+00 8.98E+01
+/- 1.50E+00 1.10 A
1.04E+02
+/-
1.68E+00 Mean =
9.90E+01
-+/- 1.89E+00 8.80E+01
+/-
3.28E+00 Cs-137 8.79E+01
+/-
3.17E+00 9.13E+01
+/- 1.52E+00 0.98 A
9.29E+01
+/-
1.47E+00 Mean =
8.96E+01
-+/- 1.60E+00 7.25E+01
-+/- 2.96E+00 Co-58 7.27E+01
+/-
2.96E+00 7.12E+01
+/-
1.19E+00 1.03 A
7.51E+01
+/-
1.38E+00 Mean = 7.34E+01 1.47E+00 1.24E+02
+/-
3.84E+00 Mn-54 1.25E+02
+/-
3.94E+00 1.15E+02
+/-
1.93E+00 1.09 A
1.26E+02
+/-
1.76E+00 Mean =
1.25E+02
+/-
1.93E+00 1.02E+02
+/-
4.39E+00 Fe-59 1.05E+02
+/-
4.56E+00 8.81E+01
+/- 1.47E+00 1.17 A
1.02E+02
+/-
1.92E+00 Mean =
1.03E+02
+/-
2.20E+00 2.24E+02
+/-
8.24E+00 2.22E+02
_+ 8.46E+00 Zn-65 2.22E+02
+/-
8.46E+00 1.97E+02
+/- 3.29E+00 1.14 A
2.27E+02
+/-
3.58E+00 Mean =
2.24E+02
+/-+ 4.1lIE+00 Co-60 1.70E+02 1.63E+02 1.70E+02 Mean =
1.68E+02
,+
,+
.+
,+
3.58E+00 3.54E+00 1.56E+00 1.76E+00 1.65E+02
+/- 2.75E+00 1.02 A
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 107
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE ID NO.
MEDIUM ANALYSIS pCi/g +/-1 sigma I
pCi/g +/-1 sigma RATIO (1) 6/17/2010 E7092-05 SOIL Ce-141 2.89E-0 I 2.47E-0 I 2.33E-01 2.87E-0I Mean =
2.64E-01
+/-
+_
+
+
1.03E-02 1.73E-02 2.38E-02 1.09E-02 8.26E-03 2.51E-01 t
4.19E-03 1.05 A
8.52E-01
+/-
5.18E-02 Cr-51 8.56E-0I
+/-
9.65E-02 7.71E-01
+/-
1.29E-02 1.13 A
9.16E-0I
+/-
5.34E-02 Mean =
8.75E-0I
+/-
4.06E-02 3.19E-01
+/-
7.72E-03 3.23E-01
+/-
1.48E-02 Cs-134 3.45E-0I
+/-
2.16E-02 2.86E-01
+/- 4.78E-03 1.15 A
3.29E-01
+/-
8.49E-03 Mean=
3.29E-01
+/-
7.15E-03 4.44E-01
+/-
8.48E-03 4.63E-01
+/-
1.71E-02 Cs-137 4.52E-0I
+/-
2.36E-02 4.32E-01
+/- 7.21E-03 1.05 A
4.52E-0I
+/-
9.04E-03 Mean =
4.53E-01
+/-
7.92E-03 2.54E-01
+/-
6.62E-03 2.62E-01
+/-
1.44E-02 Co-58 2.36E-01
+/-
2.06E-02 2.30E-0I
+/- 3.84E-03 1.08 A
2.37E-0I
+/-
7.68E-04 Mean =
2.47E-0I
+/-
6.50E-03 4.17E-01
+/-
8.49E-03 3.97E-01
+/-
1.66E-02 Mn-54 4.15E-01
+/-
2.33E-02 3.85E-01
+/- 6.43E-03 1.07 A
4.21E-01
+/-
8.54E-03 Mean =
4.13E-01
+/-
7.76E-03 3.01E-01
+/-
9.44E-03 3.01E-0l
+/-
1.97E-02 Fe-59 2.71E-01
+/-
2.89E-02 2.70E-01
+/- 4.51E-03 1.09 A
3.03E-01
+/-
1.02E-02 Mean=
2.94E-01
+/-
9.41E-03 5.12E-01
+/-
1.43E-02 4.94E-0l
+/-
2.83E-02 Zn-65 5.36E-0I
+/-
4.23E-02 4.68E-01
+/- 7.82E-03 1.09 A
5.07E-01
+/-
1.48E-02 Mean =
5.12E-01
+/-
1.37E-02 Co-60 4.74E-0 I 4.56E-01 4.78E-01 4.68E-0 1 Mean =
4.69E-0 I
+
+
+
+
+/-
6.60E-03 1.36E-02 1.93E-02 6.79E-03 6.36E-03 4.47E-01
+/- 7.46E-03 1.05 (I) Ratio = Reported/Analytics.
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 108
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE I
ID NO.
IMEDIUMI ANALYSIS I pCi/l +1 sigma pCi/g +/-1 sigma RATIO (1) 6/20/2010 E7094-05 VEG Ce-141 2.06E-0 1 2.03E-01 2.15E-01 Mean =
2.08E-01
+
+
+
+
9.86E-03
- 1. 14E-02
- 6. 1 OE-03 5.42E-03 2.2 1E-01
+/- 3.69E-03 0.94 A
5.72E-01
+/-
4.94E-02 Cr-51 6.32E-01
+/-
6.34E-02 6.80E-01
+/-
1.14E-02 0.88 A
6.00E-01
+/-
3.30E-02 Mean =
6.01E-01
+/-
2.90E-02 2.68E-01
+/-
9.60E-03 Cs-134 2.66E-0
+/-
1.36E-02 2.52E-01
+/- 4.21E-03 1.08 A
2.81E-0I
+/-
7.29E-03 Mean =
2.72E-01
+/-
6.06E-03 2.83E-01
+/-
9.37E-03 Cs-137 2.91E-01 1.23E-02 3.01E-01
+/- 5.03E-03 0.95 A
2.84E-01
+/-
6.37E-03 Mean =
2.86E-01
+/-
5.57E-03 2.02E-0I
+/-
8.49E-03 Co-58 2.09E-01 1 11E-02 203E-01
+/- 3.39E-03 0.99 A
1.89E-01
+/-
5.44E-03 Mean =
2.OOE-01
+/-
5.OOE-03 3.49E-01 1.04E-02 Mn-54 3.36E-01 1-35E-02 3.39E-01
+/- 5.66E-03 1.00 A
3.34E-01
+/-
7.03E-03 Mean =
3.40E-01
+/-
6.14E-03 2.33E-01
+/-
1.17E-02 Fe-59 2.25E-0 I 1.50E-02 2.38E-01
+/- 3.97E-03 0.98 A
2.39E-01
+/-
7.96E-03 Mean =
2.32E-01
+/-
6.87E-03 4.18E-01
+/-
1.89E-02 Zn654.27E-01
+/-
2.48E-02 Zn-65 4.2E-0
.E-02
- 4. 12E-01
+/- 6.88E-03 1.02 A
4.16E-01
+/-
1.35E-02 Mean =
4.20E-0 1
+/-
3.81E-01
+
+
+
+
8.39E-03 1.12E-02 5.8 1E-03 5.05E-03 3.94E-01
+/- 6.58E-03 0.97 A
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 109
TABLE 7.3.2 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*
DATE I
ID NO.
IMEDIUM ANALYSISI pCi/g +/-1 sigma I
pCi/g +/-1 sigma I RATIO (1) 9/16/2010 E7184-09 VEG Ce-141 4.78E-01 5.20E-0 I 5.09E-0 I 5.OOE-0 1 Mean =
5.02E-01
+
+
+/-
+
1.16E-02 2.06E-02 1.92E-02 1.45E-02 8.43E-03 4.79E-01
+/-
8.OOE-03 1.05 A
8.81E-01
+/-
5.64E-02 9.73E-01
+/-
1.07E-01 Cr-51 9.45E-01
+/-
1.01E-01 8.59E-01
+/-
1.43E-02 1.08 A
9.13E-01
+/-
6.68E-02 Mean =
9.28E-01
+/-
4.28E-02 3.98E-01
+/-
l.16E-02 3.54E-0I
+/-
2.20E-02 Cs-134 3.88E-01
+/-
2.19E-02 3.42E-01
+/- 5.71E-03 1.13 A
4.08E-01
+/-
1.40E-02 Mean =
3.87E-01
+/-
8.99E-03 3.61E-01
+/-
1.05E-02 3.42E-01
+/-
1.85E-02 Cs-137 3.41E-01
+/-
1.83E-02 3.47E-01
+/- 5.79E-03 1.01 A
3.57E-01
+/-
1.30E-02 Mean =
3.50E-0I
+/-
7.73E-03 3.03E-01
+/-
1.01E-02 2.48E-0I
+/-
1.75E-02 Co-58 2.63E-01
+/-
1.83E-02 2.71E-01
+/- 4.53E-03 1.03 A
3.07E-01
+/-
1.22E-02 Mean =
2.80E-01
+/-
7.47E-03 5.04E-01
+/-
1.23E-02 4.83E-01
+/-
2.12E-02 Mn-54 4.79E-01
+/-
2.12E-02 4.39E-01
+/- 7.33E-03 1.10 A
4.68E-01
+/-
1.42E-02 Mean =
4.84E-01
+/-
8.85E-03 3.87E-01
+/-
1.39E-02 4.28E-01
+/-
2.64E-02 Fe-59 3.99E-01
+/-
2.48E-02 3.35E-01
+ 5.59E-03 1.18 A
3.66E-01
+/-
1.65E-02 Mean =
3.95E-01
+/-
1.05E-02 8.15E-01
+/-
2.57E-02 8.02E-01
+/-
4.46E-02 Zn-65 7.65E-01
+/-
4.48E-02 7.49E-01
+/-
1.25E-02 1.06 A
7.82E-01
+/-
3.00E-02 Mean=
7.91E-01
+/-
1.86E-02 Co-60 6.60E-0 l 6.69E-0 1 6.87E-0 I 6.39E-0 I Mean =
6.64E-01
+/-
+/-
+/-
+/-
+
- 1. 11 E-02 1.95E-02 1.94E-02 1.25E-02 8.05E-03 6.28E-01
+/-
1.05E-02 1.06 A
(1) Ratio = Reported/Analytics.
(1) Ratio = Reported/Analytics.
- Sample provided by Analytics, Inc.
A=Acceptable U=Unacceptable 110
7.
3.5 REFERENCES
7.3.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.
7.3.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).
111
- 8.
Land Use Census The Vermont Yankee Nuclear Power Station Off-site Dose Calculation Manual 3/4.5.2 requires that a Land Use Census be conducted annually between the dates of June 1 and October 1. The census identifies the locations of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles of the plant. The census also identifies the nearest milk animal (within three miles of the plant) to the point of predicted highest annual average D/Q (deposition factor for dry deposition of elemental radionuclides and other particulates) value due to elevated releases from the plant stack in each of the three major meteorological sectors. The 2010 Land Use Census was conducted in the summer of 2010 in accordance with the ODCM.
Following the collection of field data and in compliance with Off-site Dose Calculation Manual (ODCM)
Section 10.1, a dosimetric analysis would be performed to compare the census locations to the "critical receptor" identified in the ODCM. This critical receptor is the location that is used in the Method 1 screening dose calculations found in the ODCM (i.e. the dose calculations done in compliance with ODCM Surveillance 4.3.3). If a census location has a 20% greater.potential dose than that of the critical receptor, this fact must be announced in the annual Radioactive Effluent Release Report for that period. A re-evaluation of the critical receptor would also be done at that time. No changes in the census data from year 2008 occurred in the 2010 census; therefore no revisions of the 2008 calculations were required.
Pursuant.to ODCM 3.5.2.a, a dosimetric analysis would be performed, using site specific meteorological data, to determine which milk animal locations would provide the optimal sampling locations. If any location had experienced a 20% greater potential dose commitment than at a currently sampled location, the new location would be/ added to the routine environmental sampling program in replacement of the location with the lowest calculated dose (which is eliminated from the program). The 2010 Land Use Census did not identify any locations, meeting the criteria of ODCM Table 3.5.1, with a greater potential dose commitment than at currently sampled locations. No changes to the Radiological Environmental Monitoring Program (REMP) were required based on the Land Use Census.
The results of the 2010 Land Use Census are included in this report in compliance with ODCM 4.5.2 and ODCM 10.2. The locations identified during the census may be found in Table 8.1.
112
TABLE 8.1 2010 LAND USE CENSUS LOCATIONS*
SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi)
Km (Mi)
N 1.4 (0.9)
NNE 1.4 (0.9) 5.5 (3.4) Cows NE 1.3 (0.8)
ENE 1.0 (0.6)
E 0.9 (0.6)
ESE 1.9(1.1)
SE 2.0 (1.2) 3.6 (2.2) Cows**
SSE 2.1 (1.3)
S 0.6 (0.4) 2.2 (1.4) Cows**
SSW 0.5 (0.3)
SW 0.4 (0.3) 8.2 (5.1) Cows WSW 0.5 (0.3)
W 0.6 (0.4) 0.8 (0.5) Cows WNW 1.1 (0.7)
NW 2.3(1.4)
NNW 1.7(1.0)
- Sectors and distances are relative to the plant stack as determined by a Global Positioning System survey conducted in 1997.
- Location of nearest milk animal within 3 miles of the plant to the point of predicted highest annual average D/Q value in each of the three major meteorological sectors.
113
- 9.
SUMMARY
During 2010 as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Vermont Yankee Nuclear Power Station environment. Over 1000 samples were collected (including TLDs) over the course of the year, with a total of over 2700 radionuclide or exposure rate analyses performed. The samples included groundwater, river water, sediment, fish, milk, silage, mixed grass, storm drain sediment, and storm drain water. In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.
Three of the objectives of the Radiological Environmental Monitoring Program (REMP) are:
To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.
To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
To verify the adequacy and proper functioning of station effluent controls and monitoring systems..
Low levels of radioactivity from three sources (discussed below) were detected in samples collected off-site as a part of the radiological environmental monitoring program. Most samples had measurable levels of naturally-occurring K-40, Be-7, Th-232 or radon daughter products. These are the most common of the naturally-occurring radionuclides.
Samples of milk and sediment contained fallout radioactivity such as Cs-I137 and Sr-90 from atmospheric nuclear weapons tests conducted primarily from the late 1950s through 1980.
Several sediment samples from onsite locations (from the plant storm drain system) had low levels of radioactivity resulting from emissions from the Vermont Yankee plant. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. Measured values were several orders of magnitude below reportable levels listed in Table 4.5.
Tritium, at concentrations significantly higher than background levels, was detected in on-site groundwater monitoring wells installed in 2007 and in 2010 in response to industry events and the 114
discovery of primary system leakage from underground Augmented Off Gas (AOG) System condensate return piping into the subsurface groundwater pool under the plant site. The leakage from this piping was terminated in early February, 2010. Extensive sampling and analysis was performed on groundwater samples and other media throughout all of year 2010. Further steps to remediate the contamination of the subsurface groundwater layer under the plant site are underway. More detail of this event is provided in the 2010 Annual Radioactive Effluent Release Report.
115
- 10. REFERENCES
- 1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2. NCRP Report No. 94, Exposure of the Population in the United States and Canada from Natural Background Radiation, National Council on Radiation Protection and Measurements, 1987.
- 3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.
- 4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, Harwood Academic Publishers, New York, 1984.
- 5. Till, John E. and Robert H. Meyer, ed., Radiological Assessment - A Textbook on Environmental Dose Analysis, NUREG/CR-3332, U.S. Nuclear Regulatory Commission, Washington, D.C.,
1983.
- 6. NUREG/CR-3130, Influence of Leach Rate and Other Parameters on Groundwater Migration, February 1983.
116