BVY 07-038, Submittal of 2006 Annual Radiological Environmental Operating Report
| ML071380489 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/15/2007 |
| From: | Ted Sullivan Entergy Corp, Entergy Nuclear Operations |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| BVY 07-038 | |
| Download: ML071380489 (109) | |
Text
Entergy Nuclear Operations, Inc.
Veirnoni Yankee P.O. F"Ox 0500) 185 Old Ferry Road Brattieboro, VT 057'02-0500 fTel 802 257 5271 May 15, 2007 BVY 07-038 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) 2006 Annual Radiological Environmental Operating Report In accordance with Vermont Yankee Technical Specification 6.6.E, attached is a copy of the 2006 Annual Radiological Environmental Operating Report. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 2006.
There are no new regulatory commitments contained in this submittal We trust that the information provided is adequate; however, should you have questions or require additional information, please contact David Mannai at (802) 258-5422.
Sincerely, Site Vice President Vermont Yankee Nuclear Power Station Attachment (1) cc:
USNRC Region 1 Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS Vermont Department of Public Service Vermont Division of Occupational and Radiological Health
Docket No. 50-271 BVY 07-038 Vermont Yankee Nuclear Power Station 2006 Annual Radiological Environmental Operating Report
ENTERGY - VERMONT YANKEE Vermont Yankee Nuclear Power Station ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Year 2006 Preparation coordinated brffl Stel henP S1iowsky, Sr.
Reviewed by:
t SS-tephen IC *McAvo, Chiistr Approved for Distribution:
Samuel A.Wender IV, Chemistry Superintendent
TABLE OF CONTENTS
- 1.
IN T R 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.
PR O G R A M D E SIG N...........................................................................................................
5 4.1 M onitoring Z ones......................................................................................................
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...............................................................
42 6.1 Sampling Program Deviations.....................................................................................
42 6.2 Comparison of Achieved LLDs with Requirements...................................................
43 6.3 Comparison of Results with Reporting Levels.............................................................
43 6.4 Changes in Sampling Locations.................................................................................
44 6.5 Data Analysis by Media Type.....................................................................................
44
- 7.
QUALITY ASSURANCE PROGRAM..............................................................................
80 7.1 AREVA NP INC. Environmental Laboratory.............................................................
80 7.2 Teledyne Brown Engineering-Environmental Services (TBE-ES) Laboratory.......
81 7.3 Entergy James A. Fitzpatrick Environm ental Laboratory (JAFEL).............................
85
- 8.
L A N D U SE C E N SU S...............................................................................................................
99 9.
SU M M AR Y...............................................................................................................................
102 10.
R E F E R E N C E S..........................................................................................................................
103
LIST OF TABLES Table Title Page 4.1 Radiological Environmental Monitoring Program.............................
10 4.2 Radiological Environmental Monitoring Locations (N on-TLD )........................................................................
12 4.3 Radiological Environmental Monitoring L ocations (T LD ).................................................................................
14 4.4 Environmental Lower Limit of Detection (LLD)
Sensitivity Requirem ents...................................................................
16 4.5 Reporting Levels for Radioactivity Concentrations in Environm ental Sam ples.................................................................
17 5.1 Radiological Environmental Program Summary...............................
26 5.2 Environmental TLD Data Summary....................................................... 39 5.3 Environmental TLD Measurements........................................................
40 6.1 Summary of Storm Drain System Sediment Sample Analyses.......... 49 6.2 Summary of Storm Drain System Water Sample Analyses............... 49 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations................................................. 50 7.1 JAFEL Interlaboratory Intercomparison Program......................... 93 8.1 Land U se Census Locations................................................... 101 ii
LIST OF FIGURES Fiagre Title Page 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 o f P lant................................................................................................
22 4.6 TLD Locations Greater than 5 Kilometers from P lant............................................................................................
.. 23 6.1-6.27 Environmental Program Trend Graphs...................................................
53 iii
- 1. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Vermont Yankee Nuclear Power Corporation in the vicinity of the Vermont Yankee Nuclear Power Station (VYNPS) in Vernon, Vermont during the calendar year 2006. It 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 to the background radioactivity and radiation that is 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 2006 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 2006 environmental TLD measurements.
Section 6: Provides the results of the 2006 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 ANP, Teledyne Brown Engineering and Entergy Nuclear Fitzpatrick's Laboratory. Included are the laboratory's results of the Analytics Intercomparison Program.
Section 8: Summarizes the requirements and the results of the 2006 Land Use Census.
Section 9: Gives a summary of the 2006 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 radionuclides that these elements have decayed into.
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 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-1 37 (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 readily 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 above (natural and fallout).
3
- 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 2006, 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 are 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 6
Direct Radiation Pathway TLD Monitoring 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 were 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 were 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 ptCi/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.
Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 [lCi/sec, weekly charcoal cartridge collection 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 7
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.
4.3.4 Ground Water Sampling Grab samples are collected quarterly from 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 the contracted 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 influence from it. 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 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 1-13 1.
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 locations (upstream of the plant and in 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-801AS1 and UD-814AS1 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 Control 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, thirteen more 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.) processes them.
9
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (as required by ODCM Table 3.5.1)*
Collection Analysis Exposure Pathway and/or Number of Routine Collection Analysis Sample Media Sample Sampling F
Analysis Frequency Locations Mode requency 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 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 1 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 2006 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone(a)
Stack (km)
Plant I. Airborne AP/CF-11 River Sta. No. 3.3 1
1.9 SSE AP/CF-12 N. Hinsdale, NH 1
3.6 NNW AP/CF-13 Hinsdale Substation I
3.1 E
AP/CF-14 Northfield, MA 1
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-1 1 River Sta. No. 3.3 1
11.8 NNW
- b. Ground WG-1 1 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 1
On-site WT-16 Test Well 202 I
On-site WT-17 Test Well 203 1
On-site WT-18 Test Well 204 I
On-site WG-22 Skibniowsky Well C
13.7 N
- c. Sediment SE-1I 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 2006 VERMONT YANKEE NUCLEAR POWER STATION Exposure Pathway
- 3. Ingestion
- a. Milk
- b. Fish
- c. Mixed Grass Station Code TM-Il TM-14 TM-18 TM-22 TM-24 FH-1 I FH-21 TG-1 1 TG-12 TG-13 TG-14 TG-15 TG-21 TG-40 TC-11 TC-14 TC-18 TC-22 TC-24 Distance From Plant Zone(a)
Stack(km)
Station Description Miller Farm Brown Farm Blodgett Farm Franklin Farm County Farm Vernon Pond Rt.9 Bridge River Sta. No. 3.3 N. Hinsdale, NH Hinsdale Substation Northfield, MA Tyler Hill Rd.
Spofford Lake Gov. Hunt House I
I I
I C
I C
I I
I I
I C
I I
I I
I C
0.8 2.2 3.6 9.7 21.6 0.6 (b) 11.8 1.9 3.6 3.1 11.6 3.1 16.4 Direction From Plant Stack W
S SE WSW N
SSE WNW NNE On-site
- d. Silage Miller Farm Brown Farm Blodgett Farm Franklin Farm County Farm 0.8 2.2 3.6 9.7 21.6 W
S SE WSW 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 2006 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-11 Inner Ring 1
1.6 NNE DR-12 Outer Ring 0
3.6 NNE DR-13 InnerRing I
1.2 NE DR-14 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 (TLD) IN 2006 VERMONT YANKEE NUCLEAR POWER STATION Station Code DR-31 DR-32 DR-33 DR-34 DR-35 DR-36 DR-37 DR-38 DR-39 DR-40 DR-4 I(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 0
I 0
I 0
I 0
Distance From Plant (kM_(d) 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 SB SB SB SB SB SB SB SB SB I
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/rn3)
(pCi/Kg)
(pCi/1)
(pCi/Kg) dry)
Gross-Beta 4
0.01 H-3 3000 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 See ODCM Table 4.5.1 for 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/1)
(pCi/m3)
(pCi/Kg)
(pCi/1)
(pCi/Kg)
(pCi/Kg-dry)
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 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
SW SSW Figure 4-1 Environmental Sampling Locations in Close Proximity to the Plant 18
.5
ý 1 1.5 2
Figure 4-2 Environmental Sampling Locations Within 5 Kin of Plant 19
I 3.
Figure 4-3 Environmental Sampling Locations Greater than 5 Km from Plant 20
0-7",
NW NE
\\ N w
.2
.4 Figure 4-4 TLD Locations in Close Proximity to the Plant 21
Figure 4-5 TLD Locations Within 5 Km of Plant 22
N WT.
Figure 4-6 TLD Locations Greater Than 5 Kin from Plant 23
- 5. RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples that were collected during 2006. 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 2006, 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.
The left-most column of Table 5.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2006 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 2006 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 reporting the means and ranges.
24
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 aposteriori 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 2006 Radiological Environmental Operating Report Vermont Yankee Table 5.1:
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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 GAMMA BE-7 K-40 CS-134 CS-137 RA-226 AC/TH-228 364 28 0.01 0.0107 (312/312)
(0.0003/0.0252)
N/A 0.0842 (24/24)
(0.0390/0.1240)
N/A 0.0295 (3/24)
(<0.0082/0.0770) 0.05 0.0031 (0/24)
(<0.0016/<0.0051) 0.06 0.0020 (0/24)
(<0.0005/<0.0032)
N/A 0.0319 (0/24)
(<0.0237/<0.0479) 0.0319 N/A 0.0081 (0/24)
(<0.0022/<0.0145) 0.0099 (52/52)
(0.0013/0.0198) 0.0685 (4/4)
(0.0520/0.0920) 0.0322 (1/4)
(<0.0094/0.0600) 0.0033 (0/4)
(<0.0020/<0.0041) 0.0023 (0/4)
(<0,0019/<0.0026) 0.0345 (0/4)
(<0,0254/<0.0450) 0.0237 0.0103 (0/4)
(<0.0024/<0.0163) 0.0386 (0/52)
(<0.0104/<0.061 1) 0.0111 (52/52)
(0.0009/0.0227) 0.0955 (4/4)
(0.0607/0.1150) 0.0428 (2/4)
(<0.0 199/0.0770) 0.0039 (0/4)
(<0.0033/<0.0051 )
0.0026 (0/4)
(<0.0022/<0.0032) 0.0367 (0/4)
(<0.0330/<0.0424) 0.0479 0.0103 (0/4)
(<0.0024/<0.0163) 0.0406 (0/52)
(<0.0073/<0.0686) 12 INDICATOR N. HINSDALE, NH 3.6 KM NNW OF SITE 40 INDICATOR GOV. HUNT HOUSE ON-SITE 14 INDICATOR NORTHFIELD, MA 11.6 KM SSE OF SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 14 INDICATOR NORTHFIELD, MA 11.6 KM SSE OF SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 21 CONTROL SPOFFORD LAKE 16.4 KM NNE OF SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 0
0 0
0 AIR IODINE (PCI/CU.METER) 1-131 364 0.07 0.0358 (0/312)
(<0.0010/<0.0686) 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 GAMMA MN-54 24 8
24 4
2.41 (12/12)
(0.440/9.70) 3000 469 (0/4)
(<452/<499)
CO-58 FE-59 CO-60 ZN-65 ZR-95 15 3.54 (0/12)
(<2.52/<4.50) 15 3.92 (0/12)
(<3.02/<5.26) 30 11.4 (0/12)
(<8.6 1/< 14.5) 15 3.65 (0/12)
(<2.74/<4.96) 30 7.90 (0/12)
(<3.39/<11.9) 15 6.96 (0/12)
(<5.43/<8.36) 2.90 (12/12)
(1.00/9.30) 469 (0/4)
(<452/<499) 6.45 (0/12)
(<4.63/<9.19) 6.19 (0/12)
(<4.36/<8.23) 15.6 (0/12)
(<10.0/<20.8) 6.48 (0/12)
(<4.29/<8.48) 15.5 (0/12)
(<7.26/<28.7) 10.8 (0/12)
(<7.05/< 14.6) 2.90 (12/12)
(1.00/9.30) 469 (0/4)
(<452/<499) 6.45 (0/12)
(<4.63/<9.19) 6.19 (0/12)
(<4.36/<8.23) 15.6 (0/12)
(<10.0/<20.8) 6.48 (0/12)
(<4.29/<8.48) 15.5 (0/12)
(<7.26/<28.7) 10.8 (0/12)
(<7.05/<14.6) 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 0
0 0
0 0
0 0
0 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 1-131 CS-134 CS-137 BA-LA-140 RA-226 GROSS BETA 15 13.3 (0/12)
(<8.44/<14.9) 15 3.09 (0/12)
(<2.01/<5.83) 18 3.23 (0/12)
(<2.17/<4.79) 15 10.4 (0/12)
(<8.15/< 13.2) 8.73 (0/12)
(<5.43/< 13.8) 6.03 (0/12)
(<2.88/<9.15) 6.46 (0/12)
(<3.98/<9.21) 9.93 (0/12)
(<5.57/<13.4) 149 (4/12)
(99.9/220) 13.3 (0/12)
(<8.44/<14.9) 6.03 (0/12)
(<2.88/<9.15) 6.46 (0/12)
(<3.98/<9.2 1) 10.4 (0/12)
(<8.15/< 13.2) 149 (4/12)
(99.90/220)
N/A 86.3 (10/12)
(43.3/146) 11 INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 KM SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 13 INDICATOR COB WELL 0.3 KM ON-SITE II INDICATOR PLANT WELL 0.2 KM ON-SITE II INDICATOR PLANT WELL 0.2 KM ON-SITE 0
0 GROUND WATER (PCI/LITER) 20 4
3.66 (16/16)
(2.06/6.00) 2.11 (4/4)
(1.70/2.70) 4.49 (4/4)
(4.00/5.00) 0 0
TRITIUM*
20 3000 456 (0/16)
(<448/<46 1) 0.548 (0/16)
(<0.397/<0.825) 456 (0/4)
(<448/<461) 0.501 (0/4)
(<0.347/<0.619) 456 (0/16)
(<448/<461) 0.60 (0/4)
(<0.420/<0.825)
- Stations 11,12, 13, 14 and 22 have the same average.
1-131 20 1
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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 ZR-95 CS-134 CS-137 20 15 7.28 (0/16)
(<3.20/<9.77) 15 6.34 (0/16)
(<3.10/<10.2) 30 19.6 (0/16)
(<11.4/<25.7) 15 8.39 (0/16)
(<4.69/<11.4) 30 11.2 (0/16)
(<6.31/<20.6) 15 12.7 (0/16)
(<7.32/<14.9) 15 7.72 (0/16)
(<3.21/<9.69) 18 5.73 (0/16)
(<2.79/<9.57) 8.62 (0/4)
(<7.74/<9.85) 9.44 (0/4)
(<8.3 1/< 11.5) 22.1 (0/4)
(< 19.7/<24.9) 7.33 (0/4)
(<5.05/<8.7 1) 12.6 (0/4)
(<1 1.0/<13.9) 14.1 (0/4)
(<13.6/<14.7) 7.53 (0/4)
(<5.16/<9.73) 8.57 (0/4)
(<5.1 1/<10.6) 8.62 (0/4)
(<7.74/<9.85) 9.44 (0/4)
(<8.31/<l11.5) 22.1 (0/4)
(< 19.7/<24.9) 8.82 (0/4)
(<7.98/<10.0) 12.6 (0/4)
(< 11. 0/< 13.9) 14.1 (0/4)
(<13.4/<14.7) 8.42 (0/4)
(<7.43/<8.90) 8.57 (0/4)
(<5.1 1/<10.6) 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KM ONSITE 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE 14 INDICATOR PLANT SUPPORT BLDG WELL 0.3 KM ONSITE 12 INDICATOR VERNON NURSING WELL 2.1 KM SSE OF SITE 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE 0
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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 BA-LA-140 RA-226 GAMMA BE-7 SEDIMENT (PCI/KG DRY) 32 15 11.0 (0/16)
(<6.33/<13.7)
N/A 203 (5/16)
(<124/<275)
N/A 816 (0/30)
(<396/< 1320)
N/A 15391 (30/30)
(8430/20700)
N/A 59.6 (0/30)
(<35.4/<88.0)
N/A 56.6 (1/30)
(<31.2/<l 19)
K-40 MN-54 CO-60 NB-95 12.0 (0/4)
(<9.58/<14.4) 216 (0/4)
(<194/<239) 757 (0/2)
(<518/<996) 14950 (2/2)
(11400/18500) 57.1 (0/2)
(<48.0/<66.1) 48.5 (0/2)
(<44.4/<52.6) 85.3 (0/2)
(<58.6/<112) 58.4 (0/2)
(<52.7/<64.0) 12.0 (0/4)
(<9.581<14.4) 228 (1/4)
(<140/<275) 992 (0/2)
(<673/1310) 20350 (2/2)
(20200/20500) 71.9 (0/2)
(<56.6/<87.1) 93.7 (1/2)
(<68.3/119.)
119 (0/2)
(<85.7/<152) 70.8 (0/2)
(<68.9/<72.7) 22 CONTROL SKIBNIOWSKY WELL 13.7 KM N OF SITE II INDICATOR PLANT WELL 0.2 KM ON-SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 12 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 12 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 24 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 0
0 0
0 0
0 0
0 N/A 95.9 (0/30)
(<49.8/< 152)
CS-134 150 60.1 (0/30)
(<27.8/<74.5) 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 CS-137 BA-LA-140 RA-226 AC-228 TH-228 TH-232 U-238 GROSS BETA 180 128 (26/30)
(<48.3/224)
N/A 967 (0/30)
(<163/<2250)
N/A 1750 (22/30)
(<828/3090)
N/A 1507 (25/30)
(<147/3700)
N/A 1172 (30/30)
(515/2170)
N/A 1000 (30/30)
(434/1630) 103 (2/2)
(78.5/128) 920 (0/2)
(<200/< 1640) 1875 (2/2)
(1300/2450) 1575 (2/2)
(1100/2050) 1119 (2/2)
(737/1500) 869 (2/2)
(627/1110) 5470 (0/2)
(<4800/<6140) 211 (2/2)
(197/224) 1302 (0/2)
(<524/<2080) 2465 (2/2)
(2400/2530) 2675 (2/2)
(2280/3070) 1815 (2/2)
(1460/2170) 1445 (2/2)
(1260/1630) 6855 (0/2)
(<3610/<10100) 19 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 23 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 19 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 12 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 36 INDICATOR NORTH STORM DRAIN OUTFALL
- 0. 1 KM E OF SITE 12 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 KM E OF SITE 18 INDICATOR TEST WELL 204 ON-SITE N/A 5949 (0/30)
(<2660/<10100)
TEST WELLS (PCI/LITER) 8 39.4 (8/8)
(6.27/156.0)
N/A 83.8 (2/2)
(11.5/156) 17 INDICATOR TEST WELL 203 ON-SITE 0
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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 TRITIUM GAMMA K-40 3000 200 (0/8)
(<161/<284)
N/A 8
MN-54 CO-58 FE-59 CO-60 NB-95 1-131 N/A 37.9 (6/8)
(<19.6/48.7) 15 1.48 (0/8)
(<1.04/<2.04) 15 1.62 (0/8)
(<1.13/<2.19) 30 3.66 (0/8)
(<2.54/<5.05) 15 1.52 (0/8)
(<1.06/<2.20) 15 1.71 (0/8)
(<1.20/<2.34) 15 6.26 (0/8)
(<5.25/<7.26)
N/A N/A N/A N/A N/A 225 (0/2)
(<165/<284) 44.8 (2/2)
(40.8/48.7) 1.61 (0/2)
(<1.20/<2.01) 1.76 (0/2)
(<1.37/<2.14) 3.97 (0/2)
(<3.12/<4.81) 1.70 (0/2)
(<1.20/<2.20) 1.83 (0/2)
(<1.31/<2.34) 6.68 (0/2)
(<6.10/<7.26) 17 INDICATOR TEST WELL 203 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 0
0 0
0 0
0 N/A N/A 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 CS-134 CS-137 BA-LA-140 MILK (PCI/LITER) 1-131 SR-89 SR-90 GAMMA BE-7 108 24 24 108 15 1.51 (0/8)
(<0.960/<2.18) 18 1.57 (0/8)
(<1.03/<2.16) 15 4.26 (0/8)
(<3.05/<5.49) 0.652 (0/95)
(<0.351/<0.846)
N/A 6.09 (0/22)
(<2.25/<10.0)
N/A 1.25 (8/20)
(<0.325/2.44)
N/A 60.7 (0/90)
(<32.4/<101)
N/A 1545 (90/90)
(1300/1830) 0.648 (0/18)
(<0.336/<0.844) 5.46 (0/4)
(<3.56/<7.99) 1.21 (2/4)
(<0.860/1.55) 59.5 (0/18)
(<3 1.0/<91.9)
N/A N/A N/A 1.63 (0/2)
(<1.13/<2.12) 1.75 (0/2)
(<1.33/<2.16) 4.72 (0/2)
(<3.94/<5.49) 0.681 (0/5)
(<0.433/<0.845) 6.88 (0/2)
(<3.27/<9.37) 2.02 (3/4)
(< 1. 160/2.44) 62.1 (0/18)
(<43.1/<85.2) 18 INDICATOR TEST WELL 204 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE 18 INDICATOR TEST WELL 204 ON-SITE II INDICATOR MILLER FARM 0.8 KM W OF SITE 18 INDICATOR BLODGETT FARM 3.6 KM SE OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE I I INDICATOR MILLER FARM 0.8 KM W OF SITE II INDICATOR MILLER FARM 0.8 KM W OF SITE 0
0 0
0 K-40 1562 (18/18)
(1400/1760) 1573 (5/5)
(1340/1790) 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 CS-134 CS-137 BA-LA 140 RA-226 AC-TH228 15 8.03 (0/90)
(<2.62/<14.0) 18 7.97 (0/90)
(<4.63/<14.0) 15 9.18.
(0/90)
(<2.96/<14.9)
N/A 170 (21/90)
(72.5/<263)
N/A 29.6 (1/90)
(I4.50/<56.9) 60 32.6 (0/4)
(<26.8/<46.3)
N/A 493 (4/4)
(324/755)
N/A 7240 (4/4)
(3520/17200) 8.32 (0/18)
(<4.77/<13.1) 7.95 (0/18)
(<4.69/<11.7) 9.30 (0/18)
(<5.36/<14.2) 164 (5/18)
(99.7/<248) 30.4 (0/18)
(<16.1/<40.3) 38.1 (0/1)
N/A 507 (1/1)
N/A 9.15 (0/18)
(<4.15/<13.8) 8.24 (0/18)
(<5.79/< 12.8) 10.2 (0/18)
(<6.5 1/< 14.9) 179 (4/18)
(125/<244) 32.4 (0/18)
(<16.5/<56.9) 46.3 (0/1)
N/A 755 (1/1)
N/A 11 INDICATOR MILLER FARM 0.8 KM W OF SITE II INDICATOR MILLER FARM 0.8 KM W OF SITE 11 INDICATOR MILLER FARM 0.8 KM W OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 11 INDICATOR MILLER FARM 0.8 KM W OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 0
0 0
0 0
0 SILAGE (PCI/KG) 1-131 5
GAMMA BE-7 5
0 0
K-40 2920 (1/1)
N/A 17200 (1/1)
N/A 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 CS-134 CS-137 RA-226 AC-TH228 MIXED GRASS (PCI/KG) 60 32.6 (0/4)
(<21.5/<41.5) 80 33.0 (0/4)
(<24.8/<49.3)
N/A 415 (2/4)
(285/507)
N/A 125 (0/4)
(<78/<190) 60 41.9 (0/18)
(<25.8/<58.9)
N/A 2291 (18/18)
(188/10300)
N/A 6400 (18/18)
(4100/9030) 60 40.1 (0/18)
(<19.9/<58.2) 36.1 (0/1)
N/A 36.2 (0/1)
N/A 597 (0/1)
N/A 117 (0/1)
N/A 38.5 (0/3)
(<30.1/<49.1) 41.5 (0/1)
N/A 49.3 (0/1)
N/A 597 (1/1)
N/A 190 (0/1)
N/A 48.3 (0/3)
(<37.3/<58.9) 3944 (3/3)
(311/10300) 7683 (3/3)
(6760/8390) 49.8 (0/3)
(<48.3/<52.0) 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 24 CONTROL COUNTY FARM 21.6 KM N OF SITE 22 INDICATOR FRANKLIN FARM 9.7 KM WSW OF SITE 12 INDICATOR N. HINSDALE, NH 3.6 KM NNW OF SITE 12 INDICATOR N. HINSDALE, NH 3.6 KM NNW OF SITE 13 INDICATOR HINSDALE SUBSTATION 3.1 KM E OF SITE 13 INDICATOR HINSDALE SUBSTATION 3.1 KM E OF SITE 0
0 0
0 1-131 21 21 GAMMA BE-7 2448 (3/3)
(474/3590)
K-40 CS-134 5540 (3/3)
(5000/6580) 42.7 (0/3)
(<36.1/<47.0) 0 0
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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #
NUMBEROF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)
(F)
(F)
NAME NONROUT1NE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS CS-137 RA-226 AC-TH228 GAMMA K-40 80 35.8 (0/18)
(<23.7/<52.8)
N/A 594 (7/18)
(404/<837)
N/A 140 (3/18)
(73.0/<213)
FISH (PCI/KG) 4 MN-54 CO-58 FE-59 CO-60 N/A 5580 (2/2)
(5470/5690) 130 61.9 (0/2)
(<42.6/<81.2) 130 68.3 (0/2)
(<61.2/<75.3) 260 203 (0/2)
(<190/<215) 130 57.4 (0/2)
(<53.5/<61.2) 35.2 (0/3)
(<31.6/<40.6) 566 (1/3)
(446/<686) 133 (0/3)
(<127/<138) 4290 (2/2)
(4210/4370) 63.7 (0/2)
(<60.2/<67.1) 58.5 (0/2)
(<56.4/<60.5) 193 (0/2)
(<163/<223) 55.0 (0/2)
(<49.4/<60.5) 39.3 (0/3)
(<37.8/<42.1) 725 (1/3)
(<592/<828) 169 (1/3)
(<140/208) 5580 (2/2)
(5470/5690) 63.7 (0/2)
(<60.2/<67.1) 68.3 (0/2)
(<61.2/<75.3) 203 (0/2)
(< 190/<215) 57.4 (0/2)
(<53.5/<61.2) 13 INDICATOR HINSDALE SUBSTATION 3.1 KM E OF SITE 12 INDICATOR N. HINSDALE, NH 3.6 KM NNW OF SITE 12 INDICATOR N. HINSDALE, NH 3.6 KM NNW OF SITE II INDICATOR VERNON POND 0.6 KM SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 11 INDICATOR VERNON POND 0.6 KM SSE OF SITE 11 INDICATOR VERNON POND 0.6 KM SSE OF SITE 11 INDICATOR VERNON POND 0.6 KM SSE OF SITE 0
0 0
0 0
0 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, 2006 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:
50-271 Location of Facility: VERNON, VT REPORTING PERIOD:
2006 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 ZN-65 CS-134 CS-137 260 144 (0/2)
(<127/<161) 130 47.7 (0/2)
(<34.5/<60.8) 150 49.5 (0/2)
(<46.8/<52.1)
N/A 7.1 (144/144)
(5.14/8.17) 135 (0/2)
(<127/<142) 66.7 (0/2)
(<50.1/<83.2) 51 (0/2)
(<38.9/<63. 1) 6.8 (8/8)
(5.90/6.78) 144 (0/2)
(<127/<161)
- 66.7 (0/2)
(<50.1/<83.2) 51 (0/2)
(<38.9/<63.1) 8.4 (4/4)
(7.50/9.87)
II INDICATOR VERNON POND 0.6 KM SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 KM NNW OF SITE DR-36 INDICATOR OUTER RING 4.43 KM WNW OF SITE 0
0 0
0 DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.)
2006 TLD DATA 152 38 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 2006)
OFFSITE STATION WITH HIGHEST MEAN INNER RING TLD OUTER RING TLD CONTROL TLDs MEAN*
RANGE*
(NO. MEASUREMENTS)**
MEAN*
RANGE*
(NO. MEASUREMENTS)**
STA.NO./ MEAN*
MEAN*
RANGE*
RANGE*
(NO. MEASUREMENTS)**
(NO. MEASUREMENTS)**
6.8
+/-
0.35 6.1 to 7.8 76 6.9
+/- 0.36 5.6 to 8.1 68 DR-36 8.1 1
0.46 7.5 to 8.7 4
6.7
+/- 0.35 6.4 to 6.9 8
SITE BOUNDARY TLD WITH HIGHEST MEAN STA.NO./ MEAN*
RANGE*
(NO. MEASUREMENTS)-
DR-45 13.2 + 0.75 10.2 to 15.9 4
SITE BOUNDARY TLD MEAN*
RANGE *
(NO. MEASUREMENTS)-
8.4
+/-
0.44 6.6 to 13.2 52 Units are in micro-R per hour.
Each "measurement" is typicallybased on quarterly readings from five TLD elements.
39
TABLE 5.3 ENVIRONMENTAL TILD MEASUREMENTS 2006 (Micro-R per Hour)
Sta.
No.
Description 1 ST QUARTER EXP.
S.D.
E 2ND QUARTER 3RID QUARTER XP.
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-O5 Spofford Lake, NH DR-06 Vernon School DR-07 Site Boundary DR-08 Site Boundary DR-09 Inner Ring DR-10 Outer Ring DR-li Inner Ring DR-12 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 6.20 6.35 6.67 5.64 6.33 6.19 7.58 8.05 5.73 5.11 5.55 5.37 6.27 7.21 6.81 6.91 6.13 6.12 7.35 7.22 6.74 6.76 6.48 5.74 6.26 6.41 6.09 6.08 6.54 5.99 6.49
.5.77 6.66 6.61 6.52 7.50 6.21 6.86 6.14 6.10 0.25 6.01 0.23 7.04 0.22 7.16 0.31 6.33 0.21 7.15 0.22 7.20 0.33 9.13 0.39 9.03 0.33 5.98 0.18 5.76 0.28 6.23 0.22 6.01 0.29 6.57 0.30 7.97 0.18 6.70 0.24 7.37 0.23 6.48 0.25 7.11 0.59 7.82 0.34 7.80 0.48 7.17 0.54 6.99 0.59 6.55 0.24 6.32 0.21 6.93 0.25 7.31 0.27 6.90 0.19 7.09 0.26 7.06 0.34 6.68 0.17 7.19 0.27 6.44 0.24 7.02 0.36 7.43 0.23 6.89 0.32 8.30 0.36 7.04 0.32 7.38 0.33 7.10 0.22 6.67 0.62 0.44 0.48 0.41 0.24 0.38 0.55 0.55 0.43 0.20 0.21 0.32 0.33 0.29 0.29 0.38 0.31 0.26 0.26 0.31 0.36 0.23 0.34 0.32 0.23 0.37 0.39 0.28 0.22 0.31 0.40 0.39 0.31 0.24 0.27 0.41 0.34 0.36 0.30 0.20 5.75
+/-
6.50
+/-
6.94
+/-
7.32
+/-
6.59
+/-
6.45
+/-
8.10
+/-
8.57
+/-
5.96
+/-
5.22
+/-
5.93
+/-
5.58
+/-
6.37
+/-
7.43
+/-
6.50
+/-
6.59
+/-
6.16
+/-
6.31
+/-
7.26
+/-
7.23
+/-
7.67
+/-
7.78
+/-
7.32
+/-
6.65
+/-
7.04
+/-
7.37
+/-
7.45
+/-
7.23
+/-
8.00
+/-
7.05
+/-
7.83
+/-
6.60
+/-
7.36
+/-
6.80
+/-
7.57
+/-
7.88
+/-
6.92
+/-
6.80
+/-
6.70
+/-
6.42
+/-
0.34 0.31 0.33 0.56 0.37 0.40 0.51 0.38 0.34 0.44 0.45 0.52 0.34 0.40 0.41 0.35 0.34 0.36 0.45 0.46 0.39 0.39 0.34 0.40 0.45 0.54 0.50 0.37 0.41 0.44 0.36 0.35 0.40 0.38 0.39 0.53 0.43 0.42 0.36 0.33 4TH QUARTER EXP.
S.D.
6.18
+/-
0.32 7.79
+/-
0.40 8.30
+/-
0.47 6.26
+/-
0.23 7.55
+/-
0.44 8.04
+/-
0.41 8.86
+/-
0.57 9.39
+/-
0.48 6.68
+/-
0.39 6.20
+/-
0.38 6.72
+/-
0.42 6.46
+/-
0.43 6.92
+/-
0.40 8.08
+/-
0.58 7.20
+/-
0.49 7.41
+/-
0.45 7.04
+/-
0.56 7.24
+/-
0.44 8.81
+/-
0.55 8.82
+/-
0.62 6.99
+/-
0.32 6.94
+/-
0.27 6.51
+/-
0.37 6.20
+/-
0.21 6.68
+/-
0.40 7.22
+/-
0.31 6.95
+/-
0.31 7.03
+/-
0.34 7.00
+/-
0.38 6.89
+/-
0.38 7.17
+/-
0.38 7.73
+/-
0.59 7.06
+/-
0.28 7.86
+/-
0.57 6.75
+/-
0.26 8.65
+/-
0.59 6.96
+/-
0.37 8.50
+/-
0.49 7.94
+/-
0.37 7.67
+/-
0.43 ANNUAL AVE.,
EXP.
6.0 6.9 7.3 6.4 6.9 7.0 8.4 8.8 6.1 5.6 6.1 5.9 6.5 7.7 6.8 7.1 6.6 6.7 7.8 7.8 7.1 7.1 6.7 6.2 6.7 7.1 6.9 6.9 7.2 6.7 7.2 6.6 7.0 7.2 6.9 8.1 6.8 7.4 7.0 6.7 40
TABLE 5.3 (cont.)
ENVIRONMENTAL TLD MEASUREMENTS 2006 (Micro-R per Hour)
ANNUAL Sta.
1 ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER AVE.
No.
Description EXP.
S.D.
EXP.
S.D.
EXP.
S.D.
EXP.
S.D.
EXP.
DR-41 Site Boundary 6.93
+/-
0.35 7.63
+/-
0.26 6.82
+/-
0.47 8.23
+/-
0.47 7.4 DR-42 Site Boundary 6.16
+/-
0.40 7.36
+/-
0.24 6.63
+/-
0.39 8.13
+/-
0.52 7.1 DR-43 Site Boundary 6.62
+/-
0.23 8.09
+/-
0.35 7.26
+/-
0.47 8.41
+/-
0.43 7.6 DR-44 Site Boundary 8.43
+/-
0.41 9.74
+/-
0.43 8.36
+/-
0.39 9.95
+/-
0.53 9.1 DR-45 Site Boundary 15.86
+/-
0.91 13.40
+/-
0.83 10.21
+/-
0.45 13.43
+/-
0.79 13.2 DR-46 Site Boundary 8.71
+/-
0.39 9.07
+/-
0.35 8.24
+/-
0.43 9.31
+/-
0.47 8.8 DR-47 Site Boundary 7.53
+/-
0.20 8.13
+/-
0.39 7.33
+/-
0.40 8.15
+/-
0.57 7.8 DR-48 Site Boundary 6.24
+/-
0.31 7.39
+/-
0.57 6.65
+/-
0.33 7.65
+/-
0.75 7.0 DR-49 Site Boundary 6.20
+/-
0.22 6.76
+/-
0.21 6.32
+/-
0.35 6.97
+/-
0.40 6.6 DR-5O Governor Hunt House 6.41
+/-
0.30 7.51
+/-
0.35 6.93
+/-
0.38 7.47
+/-
0.47 7.1 DR-5i Site Boundary 7.41
+/-
0.40 9.23
+/-
0.33 8.33
+/-
0.58 8.89
+/-
0.45 8.5 DR-52 Site Boundary 8.55
+/-
0.55 9.77
+/-
0.47 9.23
+/-
0.48 9.57
+/-
0.49 9.3 DR-53 Site Boundary 8.71
+/-
0.40 10.15
+/-
0.44 9.00
+/-
0.60 10.01
+/-
0.55 9.5 41
- 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 2006, eight 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 2006 were:
a) A South River Station River Water Composite Sampler (ODCM Sample Number VWR-1 1) Water Supply Pump failure was discovered on March 2 9th, 2006 during routine sample collection activities.
A capacitor in the pump control box was discovered to have failed. The capacitor was replaced and the pump was restored to full function. This failure was documented in a Condition Report (CR-VTY-2006-00908) and tracked via WT-VTY-2006-00000 CA-00409.
b) A failure of the Governor Hunt House air sample station (ODCM Sample Number VAPCF-40) was discovered during routine air sample collections on April 9 th, 2006., The sample pump was found to have failed and a new pump was immediately installed.
The station was returned to service immediately.
This failure was documented in a Condition Report (CR-VTY-2006-01003) and tracked via WT-VTY-2006-00000 CA-00429.
c)
The South River Station River Water Composite Sampler (ODCM Sample Number VWR-1 1) was found to be rendered out of service on April 2 7th, 2006 due to the planned removal of the river water pump supplying water to this composite sampler. The pump was removed from service to allow for the calibration of the water temperature probes located in the pump casing. Upon discovery, the pump was returned to service as soon as the probes were recalibrated.
This pump outage was documented in a Condition Report (CR-VTY-2006-01284) and tracked via WT-VTY-2006-00000 CA-00492.
d) The South River Station River Water Composite Sampler (ODCM Sample Number VWR-1 1) was found to be out of service on July 1 0th, 2006. Further investigation revealed that the pump was clogged with river silt and required replacement.
A new pump was installed and the pump was returned to service.
This pump outage was documented in a Condition Report (CR-VTY-2006-02101) and tracked via WT-VTY-2006-00000 CA-00859.
e)
During routine collection of environmental air samples on August 1 5 th, 2006, the South River Station environmental air sampler (ODCM Sample Number VAPCF-11) was discovered to be out of service.
It was determined that the pump had failed due to electrical storms experienced in the area. The pump was replaced and the air sampler restored to service. This pump outage was documented in a Condition Report (CR-VTY-2006-02517) and tracked via WT-VTY-2006-00000 CA-01 192.
f)
The South River Station River Water Composite Sampler (ODCM Sample Number VWR-11) was found to be out of service on October 1Oth, 2006. Further investigation revealed that the pump was clogged with river silt and required replacement.
A new pump was installed and the pump was returned to service. This pump outage was documented in a Condition Report (CR-VTY-2006-03165) and tracked via WT-VTY-2006-00000 CA-0 1543.
42
g) During weekly collection of environmental air samples on October 3 1st, 2006, a short period (approximately 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) of power outage was discovered to have occurred at the air sample station in Spofford, New Hampshire (ODCM Sample Number VAPCF-21). A power outage of this length was experienced by the entire town during repairs on a transmission line in the area. No further actions were taken by Vermont Yankee staff. This pump outage was documented in a Condition Report (CR-VTY-2006-03358) and tracked via WT-VTY-2006-00000 CA-01674.
h) During weekly collection of environmental air samples on November 14 th, 2006, a power outage was discovered at the air sample station at the South River Station (ODCM Sample Number VAPCF-11).
A breaker within the station was reset and power was restored. No further problems were identified.
This pump outage was documented in a Condition Report (CR-VTY-2006-03507) and tracked via WT-VTY-2006-00000 CA-01792.
i) Air sample station outages are reflected in the air sample collection time percentages listed below.
AP/CF #
1st Quarter 2 nd Quarter 3 rd Quarter 4th Quarter 11 100%
100%
94.5%
93.7%
12 100%
100%
100%
100%
13 100%
100%
100%
100%
14 100%
100%
100%
100%
15 100%
100%
100%
100%
21 100%
100%
100%
99.8%
40 94.8%
100%
100%
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 2006, 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 43
environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix 1.
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 2006, no analytical result exceeded a corresponding reporting level requirement in Table 3.5.2 of the ODCM.
6.4 Changes in Sampling Locations The Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual Section 10.2 states that if 4new 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 2006.
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 2006 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, we had converted values that were less than the MDC 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.
44
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) stations and the control (distant from plant) stations. Notable in Figure 6.1 is a distinct annual cycle, with the minimum concentration in the second quarter, and the maximum concentration in the first 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 only four 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-1 1, 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 45
positive in 12 out of 12 indicator samples and 12 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 indicator locations was similar to the mean concentration at the control location in 2006.
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.
6.5.2.2 Ground 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 2006. WG-13 (COB Well), an on-site well location, has been routinely sampled since the second half of 1996. 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 4 out of 4 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 2006. 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 2006, 15 locations were sampled at SE-12 during each of the semi-annual collections. Two samples were collected at SE-1I during the year. Be-7 was not detected in any of 32 samples analyzed. As would be expected, naturally-occurring Potassium-40 (K-40) was detected in all of the samples. Cobalt-60 was detected in I of 32 samples. Radium-226 (Ra-226) was detected in 24 of 32 samples. Actinium-228 was detected in 27 of 32 samples. Thorium-228 (Th-228) was detected in the 32 samples analyzed. Thorium-232 (Th-232) was detected in 32 samples analyzed. Cesium-137 (Cs-137) was detected in 26 out of 30 of the indicator samples and two out of two control samples. The levels of Cs-137 measured at both locations were consistent with what has been measured in the previous several years and with those detected at other New England locations. 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 2006. The test well 46
locations are shown on Figure 4.1 and the results are summarized in Table 5.1 under the media category, Test Well (WT). In 2006, two 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 8 samples collected with levels ranging from 6 to 156 pCi/kg. K-40 was also detected in 6 of the 8 samples. No other radionuclides 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 2006 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 2006 for a total of 21 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 15 of 21 samples as expected. The highest detected concentration for all plant-related radionuclides that were detected in sediment samples was found in sample SE-92, which is also designated by the plant as Manhole 12A.
Water samples were taken from the storm drain system at various access points in 2006 including Manholes MH-8, MH-1 1H, MH-12A, MH-13, and MH-14. Table 6-2 summarizes the analytical results of water samples from the storm drain system in 2006. Naturally-occurring Ra-226 was detected in 15 of the samples. Low levels of gross beta activity were detected in all samples analyzed at concentrations that are typical of any environmental water sample. Tritium (H-3) was not detected in the 24 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 47
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 2006 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 the presence of plant related radionuclides in the storm drain system.
48
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 13/21 1.4 E 3 (0.89-2.02) E 3 MH-12 (SE-95) 1-131 0/21 1.0 E 3 NA MH-12 (SE-95)
Cs-134 0/21 3.9 E 1 NA MH-12A (SE-92)
Cs-137 2/21 2.7 E 1 (1.9-3.4) E 1 MH-12A (SE-92)
Zr-95 0/21 8.3 E 1 NA MH-12 (SE-95)
Co-58 0/21 4.6 E 1 NA MH-12 (SE-95)
Mn-54 0/21 5.1 E I NA MH-12 (SE-95)
Zn-65 0/21 1.0 E 2 NA MH-12 (SE-95)
Fe-59 0/21 1.3 E 2 NA MH-12 (SE-95)
Co-60 9/21 2.9 E 2 (1.0 - 8.5) E 2 MH-12 (SE-95)
Ba/La-140 0/21 2.1 E 2 NA 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.
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 24/24 4.1 E 0 (1.7 - 7.7) E 0 MH-12A (WW-12)
H-3 0/24 4.2 E 2 NA MH-12A (WW-12)
Ra-226 15/24 1.2 E 2 (0.53 - 3.2) E 2 MH-12A (WW-12) 1-131 0/24 9.1 E 0 NA MH-14 (WW-10)
Cs-134 0/24 4.0 E 0 NA MH-12A (WW-12)
Cs-137 0/24 4.7 E 0 NA MH-12A (WW-12)
Zr-95 0/24 8.0 E 0 NA MH-12A (WW-12)
Co-58 0/24 4.5 E 0 NA MH-12A (WW-12)
Mn-54 0/24 4.4 E 0 NA MH-12A (WW-12)
Zn-65 0/24 1.0 E I NA MH-12A (WW-12)
Fe-59 0/24 1.2 E 1 NA MH-12A (WW-12)
Co-60 0/24 4.9 E 0 NA MH-12A (WW-12)
Ba!La-140 0/24 6.5 E 0 NA MH-12A (WW-12)
Radionuclides that were not detected in any sample are not listed The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).
49
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 I OCFR50.75(g) and is presented here in response to ER_95-0704_04 commitments.
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 5/6 3.28E-5 (1.24 -4.46) E-5 Manhole 11 H 0/10 None Detected None Detected Manhole 13 0/15 None Detected None Detected Manhole 8 0/10 None Detected None Detected Manhole 14 0/51 None Detected None Detected Reported per ER_950704_04.
- The fraction of sample analyses yielding detectable measurements 6.5.3 Ingestion Pathways 6.5.3.1 Milk (TM)
Milk samples from cows or goats at several local farms were collected monthly during 2006. 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 8 out of 20 indicator samples and 2 out of 4 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 detected at other New England farms participating in other plant environmental monitoring programs.
50
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 108 samples in 2006. 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 also detected in 2 of the 5 samples. Cs-137 was not detected in any of the five samples. No 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 on three occasions during 2006.
As expected with all biological media, naturally-occurring Be-7 was detected in 21 of the 21 samples.
Naturally-occurring K-40 was detected in all samples. Naturally-occurring Ra-226 was detected in 8 of the 21 samples and naturally occurring Ac-228 was detected in three samples. Cs-137 was not 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 2006. 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 all samples.
As shown in Table 5.1, Cs-137 was not detected in this year's samples. It should be noted that most 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 2006 and previous years are typical of concentrations attributable to global nuclear weapons testing 51
fallout.
No other radionuclides were detected.
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 2006. 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. A slight increase in exposure rates during the last quarter of 2006 is likely the result of no snow cover as well as much warmer temperatures which prevented ground freezing during this period.
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.
52
Environmental Program Trend Graphs 2006 Radiological Environmental Operating Report Vermont Yankee Nuclear Power Station 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, DR01-03 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 53
Figure 6.1 - Gross Beta Measurements on Air Particulate Filters - Quarterly Average Concentrations 0.04 0.035 0.03
, 0.025-E S0.02
" 0.015 0.01 0.00510 4692 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year 0 Indicator Stations
~
-Control Station 54
Figure 6.2 - Gross Beta Measurements on Air Particulate Filters 0.025 0.02
- 0.015 E
.0
- 00.
0.01 0.005 2006 Week Number
-- AP-1 1 River Station U-AP-21 Spofford Lake N H 55
Figure 6.3 - Gross Beta Measurements on Air Particulate Filters 0.025 0.02
" 0.015 S
E
.0
- 0. 0.01 0.005 0
)-,
Do?
2006 Week Number AP-12 North Hinsdale AP-21 Spofford Lake NH 56
Figure 6.4 - Gross Beta Measurements on Air Particulate Filters 0.03 0.025 0.02 E 0.015 0.01 0.005 0
(JTIO)-.JWODO 2006 Week Number AP-13 Hilnsdale Substation AP-21 Spofford Lake NH 4
4ý1 4 4
.936 U1 CA M rQ CA)
Cn 0
-4 W 0 0
57
Figure 6.5 - Gross Beta Measurements on Air Particulate Filters 0.025 0.02
- 0.015 E
0.005 0
2006 Week Number
--AP-14 Northfield MA
-*--AP-21 Spofford Lake NH 58
Figure 6.6 - Gross Beta Measurements on Air Particulate Filters 0.025 0.02
- 0.015 E
?I C. 0.01 0.005 U
2006 Week Number
-+AP-15 Tyler Hill Road
-UAP-21 S pofford Lake N H 59
Figure 6.7 - Gross Beta Measurements of Air Particulate Filters 0.03 0.025 0.02 0.015 CL 0.01 0.005 v
2006 Week Number
--AP-40 Governor Hunt House 4-AP-21 Spofford Lake NH 60
Figure 6.8 - Gross Beta Measurements on River Water Semi-Annual Average Concentration
.J CL 4.00 3.50 3.00 2.50 2.00 1.50 1.00 0.50 0.00 V\\ A /)F--l Vi--I 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year 11WR-1 River Station (3-3)
WR-21 Rt.9 Bridge (3-8) 61
Figure 6.9 - Gross Beta Measurements on Ground Water Semi-Annual Average Concentrations
-J C.,
10.0 9.0 8.0 7.0 6.0 5.0 4.0 3.0 2.0 1.0 0.0 x"~
1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year
-WG-1i1 Plant Well -u-*WG-1 2 Vernon Nursing Wel WG-22 Skibniowsky Well WG-I3 COB Wel
)K-WG-1 4 Engineering Building 62
Figure 6.10 - Cesium 137 in Milk - Annual Average Concentration I-
..J a.
10.0 9.0 8.0 7.0 6.0 5.0 4.0 3.0 2.0 1.0 0.0 I-1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 itched to reoortina < MDA when no activity was detected.
I Year Using MDA values result in a larger number.
- -TM-11 Miller(cow)
TM-14 Brown (cow)
TM-16 Meadow Crest Farm (cow) x -TM-18 BldetFarm (cow)
W*-TM-24 County Farm (control)
--@-TM-22 Franklin (cow)
--- TM-25 Downey-Spencer (goat)
-TM-26 Cheney Hill
~
TM-99 Special Farm 63
Figure 6.11 - Strontium 90 in Milk - Annual Averge Concentrations 4.0 3.5 3.0 2.5 0
2.0 0.
1.5 1.0 0.5 0.0o 1991 1992 1993 1994 1995 1996 1997 1998 Note: In 2005, switched to reporting < MDA when no activity was detected. Averages Year include the MDAs and positive values. Using MDA values result in a larger number.
1999 2000 2001 2002 2003 2004 2006 2005 (g)TM-14 Brown (cow)
TM-18 8lodgett Farm (cow) x TM-24 County Farm (control) w -TM-22 Franklin Farm (cow)
--oTM-25 Downey-Spencer (goat) -+-TM-26 Cheney Hill TM-99 Specila Farm 64
Figure 6.12 - Cesium 137 in Fish - Annual Average Concentrations 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 I
1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Year Note: In 2005 switched to reporting < MDA when no activity was detected. Using MDA values result in a larger number.
FH-1 1 Vernon Pond FH-21 Rt. 9 Bridge (Control) 65
Figure 6.13 - Average Exposure Rate at Inner Ring, Outer Ring and Control TLIDs 9.0 8.5 8.0 7.5 -
7.0 0
6.5 j6.01 5.5 5.0 --
4.5-4.0-1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Retrieval Date Control Inner Ring Outer Ring 66
Figure 6.14 - Exposure Rate at Indicator TLDs, DR01-03 0I 2
10.0 9.5 9.0 8.5 8.0 7.5 7.0.
6.5 6.0 -
5.5 5.0 -
4.5-4.0 -r--
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 DR-01 River Station No. 3.3
-DR-02 North Hinsdale, NH DR-03 Hinsdale Substation 67
Figure 6.15 - Exposure Rate at Indicator TLDs, DR06 & DR-50 I-
._2 2002 Retrieval Date DR-06 Vernon School U DR-50 Gov. Hunt House 68
Figure 6.16 - Exposure Rate at Site Boundary TLDs DR07, 08, 41 & 42 10 9
8 0._
0 7
6 5
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 I -- -- ---
i *-DR-07 Site Boundary
--o-R-08 Site Boundary DR-41 Site Boundary
-x(-
DR-42 Site Boundary 69
Figure 6.17 - Exposure Rate at Site Boundary TLDs - DR43 thru 46 I-0 I-19 18 17 16 15 14-13 12 11 10 9
8 7
6 5
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 0 R-43 Site Boundary DR-44 Site Boundary DR-45 Site Boundary x DR-46 Site Boundary 70
Figure 6.18 - Exposure Rate at Site Boundary TLDs DR47-49 & 51-53 0
12 11 10 9
8 7
6--
5 4
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 SDR-47 Site Boundary UDR-48 Site Boundary DR-49 Site Boundary DR-51 Site Boundary SDR-52 Site Boundary DR-53 Site Boundary 71
Figure 6.19 - Exposure Rate at Inner Ring TLDs DR09, 11, 13 & 15 9
8 7
0.
2j6 5
4L 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 SDR-09 Inner Ring
-a-DR-11 Inner Ring DR-13 Inner Ring
( DR-15 InnerRing 72
Figure 6.20 - Exposure Rate at Inner Ring TLDs DRI7, 19, 21 & 23 11 10 9
0 2
.£ 8
7 6
5 4 !
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date
-~DR-1 7 Inner Ring D-DR-19 In ner Ring DR-21 Inner Ring X*-DR-23 Inner Ring 2007 73
Figure 6.21 - Exposure Rate at Inner Ring TLDs DR25, 27, 29 & 31 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 Retrieval Date
- DR-25 Inner Ring
-DR-27 Inner Ring DR-29 Inner Ring x~ DR-31 Inner Rinj 2007 I!i*iii!iii!
74
Figure 6.22 - Exposure Rate at Inner Ring TLDs DR33, 35, 37 & 39 10 9
8 0
7 6
5 4 -L--
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date 2007 DR-33 Inner Ring DOR-35 Inner Ring DR-7 Inner Ring x DR-39 i
nner Ring 75
Figure 6.23 - Exposure Rate at Outer Ring TLDs DRIO, 12, 14 & 16 10 9
8 0
7 6
5 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date
-.- R-IO0 Outer Ring U-DR-1 2 Outer Ring DR-14 Outer Ring x -DR-16 Outer Ring 2007 76
Figure 6.24 - Exposure Rate at Outer Ring TLDs DR18, 20, 22 & 24 0
0.
11 10.5 10 9.5 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 Retrieval Date 2007 I
DR-18 Outer Ring -
DR-20 Outer Ring DR-22 Outer Ring
( DR-24 Outer Ring 77
Figure 6.25 - Exposure Rate at Outer Ring TLDs DR26, 28, 30 & 32 1n a--
0.
0o I-U 9
8.5 8
7.5 7
6.5 6
55 5 -
4.5 -
4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 Retrieval Date
-.- DR-26 Outer Ring
-WDR-28 Outer Ring DR-30 Outer Ring x -DR-32 Outer Ring 2007 78
Figure 6.26 - Exposure Rate at Outer Ring TLDs DR 34, 36, 38 & 40 0
102 10 --
9.5 9 1 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 Retrieval Date
- DR-34 Outer Ring DR-36 Outer Ring DR-38 Outer Ring x
DR-40 Outer Ring 2007 79
Figure 6.27 - Exposure Rate at Control TLDs DR04 & 05 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 Retrieval Date
-4DR-04 Northfield, MA DR-05 Spofford Lake, NH 2007 80
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) is 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 is 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, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements. The E-LAB employs a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program includes 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 (used in conjunction with the National Institute of Standards and Technology Measurement Assurance Program, NIST MAP) and a third party cross check program administered by Analytics, Inc. Together these programs are targeted to supply QC/QA sources at 5% of the client sample analysis load. In addition a blind duplicate program is conducted through client environmental monitoring programs.
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 is provided by the dosimetry quality assurance testing program. This program includes independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, sets of six dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Section 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 by the Dosimetry Services Group and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the exposures are known to the processor.
Ninety-six performance tests were conducted in 2006 by E-LAB and the third party tester. These tests were made on 15 separate sets of 6 dosimeters. All of the 16 TLD test sets passed the mean bias criteria of +/-20.1%. Of the ninety 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.
81
Percentage of Individual Analyses that passed E-LAB Internal Criteria Summary of Third Party Testing Dosimeter Type Exposure ANSI Category
% (Bias +/- SD)
Period Panasonic Environmental First Half 2006 II, high energy 7.5 +/- 2.4 Second Half II, high energy 4.0 +/- 1.0 2006
- American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semi-Annual QA Status Report.
Note: Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N 13.29-1995 (Draft) Category II, High energy photons (Cs-137 or Co-60).
7.2 Teledyne Brown Engineering -Environmental Services (TBE-ES) Laboratory 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 (1 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.
82
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 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 Stoller, Westinghouse and BWXT 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-eight 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. Below is a list of the media types evaluated:
83
- Air Filter Charcoal (Air Iodine)
Milk
" Soil Vegetation Water 7.2.2.1.2 Analytics Environmental Cross-Check Program Twelve nuclides were evaluated during this reporting period. 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 13 and Series 14). During this reporting period, 19 nuclides were evaluated. All but four of the 19 environmental analyses performed were within the acceptable criteria. In one sample, Cs-134 was evaluated as a false positive by MAPEP although TBE-ES considered the results a non-detect due to the peak not being identified by the gamma software. MAPEP evaluated the activity/uncertainty ratio as being >3 which would indicate a positive result.
MAPEP suggests the Bi-214 is not being differentiated from the Cs-134 and a key line rather than a weighted mean analysis would result in a ration <3.. No further action was required.
A high Strontium-90 activity in MAPEP vegetation is attributed to one of three analyzed samples being too high, biasing the result on the high side. We were unable to determine a reason for the slightly higher result of 2.43 Bq/kg. The Strontium-90 in vegetation failure was bracketed by acceptable results and no Strontium-90 in vegetation was analyzed during the period. No further action was required.
High Plutonium-238 and Plutonium-239/240 activity in MAPEP vegetation is attributed to an insufficient preparation method for isotopic plutonium in vegetation samples. We do not analyze vegetation samples for clients and used the MAPEP samples to determine if our present preparation method was acceptable. No further action was required.
7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, 13 nuclides were analyzed under ERA criteria. All of the environmental analytical results were acceptable.
7.2.2.2 Intra-Laboratory Process Control Program 84
The TBE-ES Laboratory's internal process control program evaluated 1899 individual samples.
7.2.2.2.1 Spikes All 1333 environmental spikes were analyzed with statistically appropriate activity reported for each spike.
7.2.2.2.2 Analytical Blanks During this reporting period, all but 17 of the 1333 environmental analytical blanks analyzed reported less than MDC. The activity detected for the 17 blanks is indistinguishable from natural background.
7.2.2.2.3 Duplicates All except 2 of 783 duplicate sets analyzed were within acceptable limits. Reruns were performed on the failed duplicates sets.
7.2.2.2.4 Non-Conformance Reports There were 16 non-conformance reports issued for this reporting period. No ENNVY data was impacted by the non-conformance in each of these cases.
85
7.3 Entergy Nuclear J. A. Fitzpatrick Environmental Laboratory 7.3.1 QA/QC PROGRAM 7.3.1.1 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 two independent laboratories to provide quality assurance comparison samples. The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S. Department of Commerce's National Institute of Standards and Technology (NIST) in Gaithersburg, Maryland.
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 using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report. The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance for Analytic's sample results.
In addition to the Analytics Program, the JAF Environmental Laboratory participates in the NEI/NIST Measurement Assurance Program. In 1987, the nuclear industry established a Measurement Assurance Program at the National Bureau of Standards (now the National Institute of Standards and Technology) to provide sponsoring nuclear utilities an independent verification, traceable to NIST, of their capability to make accurate measurements of radioactivity, as described in NRC Regulatory Guide 4.15.
The program includes distribution to sponsoring utilities, approximately six times a year.
The samples are prepared by NIST to present specific challenges to participating laboratories. NIST supplies sample media as blind sample spikes. These samples are prepared and analyzed by the JAF Environmental Laboratory and the results are submitted to the Entergy Nuclear Northeast representative, who uses predetermined acceptance criteria methodology for evaluating the laboratory's performance. The performance results along with the NIST Report of Test (Certifies what activities are present in the sample) are forwarded to the laboratory.
86
7.3.2 PROGRAM SCHEDULE Water Gross Beta 1
Water Tritium 4
Water 1-131 2
Water Mixed Gamma 2
Air Gross Beta 2
Air 1-131 2
Air Mixed Gamma 3
Milk 1-131 2
Milk Mixed Gamma 2
Soil Mixed Gamma 1
Vegetation Mixed Gamma 1
TOTAL SAMPLE INVENTORY 22 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.
7.3.4 SAMPLE RESULTS EVALUATION Samples provided by Analytics and NIST 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).
87
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.
<4 No Comparison 4 to 7 0.5-2.0 8 to 15 0.6-1.66 16 to 50 0.75-1.33 51 to 200 0.8-1.25
>200 0.85-1.18 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 Analytics and NIST 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.
88
7.3.5 PROGRAM RESULTS
SUMMARY
The Interlaboratory Comparison Program numerical results are provided on Table7-1.
7.3.5.1 ANALYTICS QA SAMPLES RESULTS Twenty QA blind spike samples were analyzed as part of Analytics 2006 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 84 individual analyses on the 20 QA samples. Of the 84 analyses performed, 82 were in agreement using the NRC acceptance criteria for a 97.6% agreement ratio.
There were two non-conformities in the 2006 program.
7.3.5.1.1 ANALYTICS SAMPLE NONCONFORMITIES Analytics Sample E4882-05, Ce-141 in Water Nonconformity No. 2006-01 A spiked mixed gamma in water sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures. The sample contained a total of ten radionuclides for analysis. Ten of the ten radionuclides present were quantified. Nine of the ten radionuclides were quantified within the acceptable range. The mean result for Ce-141 was determined to be outside the QA Acceptance Criteria resulting in a sample nonconformity. The water sample was analyzed three times using three different detectors. An average Ce-141 value of 64.8 pCi/L was reported.
The known result for the sample was 86.8 pCi/L as determined by the supplier. One of the three reported results was 72 pCi/L and resulted in an agreement when compared to the known of 86.8 pCi/L with a ratio of 0.83. The remaining 2 individual results were outside the acceptance criteria and had ratios to the known that ranged from 0.67 and 0.74. All of the analysis had relatively low count rate, which ranged from 3.9 counts per minute to 4.9 counts per minute.
89
An evaluation of the Ce-141 result was performed. The detector calibrations were reviewed to determine if the efficiency determination in the lower end
(<500 KeV) of the calibration curve exhibited any anomalies. The efficiency curve evaluation showed that shape of the curve and the corresponding efficiency coefficients were within the normal range and compared favorably with the previous calibration. The spectrum and peak search results were examined with no abnormalities identified. Ce-141 decays by beta minus with a 32.5 day half-life and a gamma ray energy of 145 KeV with a yield of 48%. No significant secondary gamma energies are produced in the Ce-141 decay scheme.
The combination of low sample activity and low net counts most likely resulted in an inaccurate sample result. The nonconforming analytical results for this sample media and radionuclide are not routine and does not indicate a programmatic deficiency in the analysis of Ce-141 in water samples or other environmental media. Confidence in the accurate analysis of Ce-141 can be demonstrated by other Ce-141 analytical results. The Ce-141 results for the other Quality Assurance samples analyzed as part of the 2006 Interlaboratory Comparison Program were all acceptable and are summarized below. These results demonstrate that at the time of sample analysis the gamma spectral analysis system was performing properly and was in control.
2006 Ce-141 Results Sample ID Medium JAF Reference Ratio E4883-05 Filter pCi/filter 58.6 +/- 1.6 61.4 +/- 1 0.95 E5002-05 Milk pCi/liter 185.7 + 4.0 184 +/- 3.1 1.01 E5003-05 Soil pCi/g 0.241 + 0.008 0.214 +/- 0.004 1.13 E5005-05 Vegetation pCi/g 0.209 + 0.007 0.223 +/- 0.004 0.94 E5076-05 Water pCi/liter 94.2 + 2.61 88.0 +/- 1.47 1.07 E5077-05 Filter pCi/filter 80.3 + 1.41 78.6 +/- 1.13 1.02 E5078-05 Milk pCi/liter 86.7+2.76 86.0 +/- 1.44 1.01 E4963-09
- Milk pCi/liter 98.4 +/- 3.95 104 +/- 1.5 0.94 E4997-09
- Water pCi/liter 160+19 149 +/- 2.5 1.07 E5073-09
- Vegetation pCi/g 0.162 + 0.003 0.153 +/- 0.002 1.06 E5170-09
- Water pCi/liter 284.3 + 5.6 286 +/- 5.0 0.99 Mean Ratio =
1.02
- Provided by laboratory client, NOT reported in Annual Report These results demonstrate that at the time of sample analysis the gamma spectral analysis system was performing properly and was in control.
Historical results from the 2005 Interlaboratory Comparison program demonstrated the laboratory's ability to analyze Ce-141 accurate in low level environmental sample media. These results are summarized below:
90
2005 Ce-141 Results Sample iD Medium JAF Reference Ratio E-4488-05 Water pCi/liter 235+/-6 221+/-4 1.06 E-4713-05 Water pCi/liter 291+/-4 282+/-5 1.03 E-4489-05 Filter pCi/filter 157+/-3 155+/-3 1.01 E-4714-05 Filter pCi/filter 176+/-3 165+/-3 1.07 E-4585 Soil pCi/kg 173+/-2 182+/-3 0.95 E-4584-05 Milk pCi/liter 101+/-5 92+/-2 1.09 E-4715-05 Milk pCi/liter 237+/-4 233+/-4 1.02 E-4587 Vegetation pCi/kg 178+/-9 174+/-3 1.02 NIST 1801-20 Filter pCi/filter 1.89E5+/-475 1.96E5+/-2176 0.96 NIST-1800-10 Water pCi/G 1.47E5+/-441 1.48E5+/--1125 0.99 Mean Ratio =
1.02 The mean ratio for these samples relative to the known (reference) value was 1.02. The 2006 nonconformity is considered to be an isolated instance. The Ce-141 results for 2005 and 2006 program demonstrate that there is no systematic error or persistent low bias present in the analysis of samples for Ce-141 in water or other environmental sample media. No corrective actions were implemented as a result of this nonconformity.
Analytics Sample E5221-05, Gross Beta in Water Nonconformity No. 2006-02 A water sample, spiked with Cs-137, supplied by Analytics was analyzed for gross beta activity in accordance with standard laboratory procedures. Half of the 1 liter sample provided was evaporated such that any remaining residue would remain in a 2 inch stainless steel planchet. The planchet was then counted 3 times on a low background counter (LBC). An average Gross Beta value of 173 pCi/L was determined and reported for the sample.
The known value for the sample was 249 pCi/L as determined by Analytics.
The acceptable ratio of agreement for this sample was determined to be 0.8 to 1.25. The calculated ratio of sample results divided by the known value was 0.69, which fell outside the QA Acceptance Criteria. An investigation into the QA nonconformity was initiated.
A thorough review of all raw data and calculations used to determine the reported gross beta value was conducted with no errors noted. The original stainless steel planchet was then reanalyzed on a different LBC with no appreciable difference in the resulting gross beta value.
91
The remaining 500ml ofE5221-05 was then analyzed by gamma spectroscopy, which confirmed Analytics known Cs-137 activity.
Following the confirmation of the samples Cs-137 concentration, a duplicate gross beta analysis was performed on the remaining sample in accordance with standard laboratory procedures. A value of 245 pCi/L was obtained on the backup gross beta analysis, equivalent to 98% recovery of the known value.
Based on the difference between the initial and backup results, it is believed that some of the sample residue was removed from the original stainless steel planchet prior to counting. The missing material equates to 26cpm or 68dpm. All equipment used to process the original sample was checked for loose radioactive material, none was detected. The following procedure revision has been submitted to address this nonconformity: Add "Use caution when evaporating samples. Boiling or spattering may cause substantial sample losses and cross-contamination."
Historical Water Gross Beta Results Simple ID Medium JAF-Reference '." Ratio QAP-58 (2003)
Water Bq/liter 588+/-7 627+/-10 0.937 QAP-59 (2003)
Water Bg/liter 1796+/-17 1948+/-195 0.922 QAP-0403 (2004)
Water Bq/liter 1105+/-17 1170+/-117 0.944 A19773-05 (2005)
Water pCi/mI 1802+/-2 1830+/-46 0.985 E4458-80 (2005)
Water pCi/L 260+/-1.4 268+/-8.9 0.970 Mean Ratio =
0.95 The mean ratio for these samples relative to the known (reference) value was 0.95. The 2006 nonconformity is considered to be an isolated instance. The results for 2003 through 2005 demonstrate that there is no systematic error present in the analysis of samples for gross beta in water.
7.3.5.2 NIST QA SAMPLES RESULTS In 2006, JAF Environmental Laboratory participated in the NEI/NIST Measurement Assurance Program. Two QA blind spike samples were analyzed.
The following sample media were evaluated as part of the comparison program.
Air Particulate Filter: Mixed Gamma Emitters Water: 1-131, Tritium The JAF Environmental Laboratory performed 7 individual analyses on the two QA samples. Of the 7 analyses performed, 7 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.
There were no non-conformities in the 2006 program.
92
j 7.3.5.3 NUMERICAL RESULTS TABLES TABLE 7-1 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/filter +1 sigma pCi/filter +2 sigma (1)
EVALUATION 6/8/2006 E5001-05 Filter Gross Beta 64.8
+/-
1.20 60.0
+/-
2.00 1.08 Acceptable 1-2/7/2006 E5171-05 Filter Gross Beta 99.5
+/-
1.45 86.0
+
2.87 1.16 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
Tritium Analysis of Water REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/liter +1 sigma pCi/liter +2 sigma (1)
EVALUATION 3/23/2006 E4881-05 Water H-3 4530 107 4210
+/-
140 1.08 Acceptable 7/14/2006 E5059-05 Water H-3 933
+/-
84 750
+
25 1.24 Acceptable 9/14/2006 E5080-05 Water H-3 832
+/-
82 903
+/-
30 0.92 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
Gross Beta Analysis of Water REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/liter +1 sigma pCi/liter +2 sigma (1)
EVALUATION 12/7/2006 E5221-05 Water Gross Beta 173.0
+/-
2.18 249
+/-
8.29 0.69 Not Acceptable(2)
(1) Ratio = Reported/Analytics (See Section 7.3).
(2) Corrective action taken by J. A. Fitzpatrick Env. Lab.
- Sample provided by Analytics, Inc.
1-131 Gamma Analysis of Air Charcoal REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCJ +A sigma pCL +2 sigma (1)
EVALUATION 6/8/2006 E5004-05 Air 1-131 63.3
+/-
2.42 66.0
+/-
2.20 0.96 Acceptable 9/14/2006 E5079-05 Air 1-131 97.2
+
2.5 91.9
+/-
3.06 1.06 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
93
TABLE 7-1 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/liter +1 sigma pCi/liter +2 sigma (1)
EVALUATION 3/23/2006 E4882-05 Water Ce-141 64.8
+
3.7 86.8
+
2.9 0.75 Not Acceptable (2)
Cr-51 263.0
+/-
17.8 234.0
+
7.8 1.12 Acceptable Cs-134 107.0
+/-
3.4 101.0
+/-
3.4 1.06 Acceptable Cs-137 71.8
+
2.9 74.3
+
2.5 0.97 Acceptable Co-58 79.0
+
3.1 87.5
+
2.9 0.90 Acceptable Mn-54 85.1
+
3.1 78.1
+
2.6 1.09 Acceptable Fe-59 79.5
+
3.6 72.4
+
2.4 1.10 Acceptable Zn-65 156.0
+/-
6.3 148.0
+
4.9 1.05 Acceptable Co-60 104.0
+
2.5 107.0
+
3.6 0.97 Acceptable 1-131**
71.9
+/-
0.9 67.4
+
2.3 1.07 Acceptable 9/14/2006 E5076-05 Water Ce-141 94.2
+/-
2.6 88.0
+
2.9 1.07 Acceptable Cr-51 288.7
+
13.1 288.0
+
9.6 1.00 Acceptable Cs-134 94.1
+
1.9 87.0
+
2.9 1.08 Acceptable Cs-137 173.0
+
2.4 179.0
+
6.0 0.97 Acceptable Co-58 115.0
+
2.1 112.0
+
3.7 1.03 Acceptable Mn-54 124.3
+
2.1 115.0
+
3.8 1.08 Acceptable Fe-59 47.9
+
1.9 44.7
+
1.5 1.07 Acceptable Zn-65 148.0
+
3.9 148.0
+
4.9 1.00 Acceptable Co-60 139.0 1.7 137.0 4.6 1.01 Acceptable 1-131**
86.1
+
1.2 79.9 2.66 1.08 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
(2) Corrective action taken by J. A. Fitzpatrick Env. Lab.
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
94
TABLE 7-1 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Milk REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/liter +1 sigma pCi/liter +/-2 sigma (1)
EVALUATION 6/8/2006 E5002-05 Milk Ce-141 185.7
+
4.0 184.0
+
6.1 1.01 Acceptable Cr-51 257.7
+/-
16.9 259.0
+
8.6 0.99 Acceptable Cs-134 128.0
+/-
3.0 127.0
+/-
4.2 1.01 Acceptable Cs-137 112.7
+
2.8 117.0
+
3.9 0.96 Acceptable Co-58 98.8
+
2.6 100.0 4
3.3 0.99 Acceptable Mn-54 153.3
+
3.2 146.0
+
4.9 1.05 Acceptable Fe-59 94.8 3.4 93.6 3.1 1.01 Acceptable Zn-65 191.0 6.0 185.0 6.2 1.03 Acceptable Co-60 127.3 2.3 129.0 4.3 0.99 Acceptable 1-131**
61.9 0.9 63.2 2.1 0.98 Acceptable 9/14/2006 E5078-05 Milk Ce-141 86.7 2.8 86.0 2.9 1.01 Acceptable Cr-51 285.3 14.2 282.0 9.4 1.01 Acceptable Cs-134 89.5 2.2 85.0 2.8 1.05 Acceptable Cs-137 170.0 2.4 175.0 5.8 0.97 Acceptable Co-58 105.0 2.3 109.0 3.7 0.96 Acceptable Mn-54 117.7 2.2 113.0 3.8 1.04 Acceptable Fe-59 47.5 2.4 43.7 1.5 1.09 Acceptable Zn-65 147.7
+/-
4.2 145.0 4.8 1.02 Acceptable Co-60 129.3
+/-
1.8 134.0 4.5 0.97 Acceptable 1-131**
72.7 1.3 73.8 2.46 0.99 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
- Result determined by Resin Extraction/Gamma Spectral Analysis.
95
TABLE 7-1 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/filter +1 sigma pCi/filter +2 sigma (1)
EVALUATION 3/23/2006 E4883-05 Filter Ce-141 58.6
+/-
1.60 61.4
+/-
2.05 0.95 Acceptable Cr-51 169.0
+/-
10.3 166.0
+/-
5.52 1.02 Acceptable Cs-134 74.0
+/-
3.90 71.5
+
2.38 1.03 Acceptable Cs-137 51.8
+/-
2.10 52.5
+/-
1.75 0.99 Acceptable Co-58 60.5
+/-
2.40 61.9
+/-
2.06 0.98 Acceptable Mn-54 61.5
+/-
2.40 55.3 1.84 1.11 Acceptable Fe-59 55.6
+/-
2.90 51.3
+/-
1.71 1.08 Acceptable Zn-65 115.0
+/-
5.50 104.0
+/-
3.48 1.11 Acceptable Co-60 72.5
+/-
2.10 75.6 2.52 0.96 Acceptable 9/14/2006 E5077-05 Filter Ce-141 80.3
+/-
1.41 78.6
+/-
2.62 1.02 Acceptable Cr-51 266.3 4
9.88 257.0
+/-
8.57 1.04 Acceptable Cs-134 84.1
+/-
2.03 77.7
+/-
2.59 1.08 Acceptable Cs-137 159.7
+/-
2.24 160.0
+/-
5.33 1.00 Acceptable Co-58 101.3
+/-
2.03 99.8
+/-
3.33 1.01 Acceptable Mn-54 112.0
+/-
2.01 103.0
+/-
3.42 1.09 Acceptable Fe-59 46.1
+/-
1.98 39.9
+/-
1.33 1.15 Acceptable Zn-65 147.7
+
4.09 132.0
+
4.41 1.12 Acceptable Co-60 119.7
+/-
1.71 122.0
+/-
4.07 0.98 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
Gamma Analysis of Soil REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/gram +1 sigma pCi/gram +2 sigma (1)
EVALUATION 6/8/2006 E5003-05 Soil Ce-141 0.241
+/-
0.008 0.214
+/-
0.007 1.13 Acceptable Cr-51 0.349
+/-
0.036 0.302
+
0.010 1.16 Acceptable Cs-134 0.162
+/-
0.006 0.147
+/-
0.005 1.10 Acceptable Cs-137 0.249
+
0.007 0.237
+/-
0.008 1.05 Acceptable Co-58 0.114
+/-
0.004 0.117
+
0.004 0.97 Acceptable Mn-54 0.185
+/-
0.006 0.170
+/-
0.006 1.09 Acceptable Fe-59 0.120
+/-
0.007 0.109
+/-
0.004 1.10 Acceptable Zn-65 0.236
+/-
0.010 0.216
+/-
0.007 1.09 Acceptable Co-60 0.155
+/-
0.004 0.150
+/-
0.005 1.04 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
96
TABLE 7-1 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation REFERENCE SAMPLE JAF LAB LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/gram +/-1 sigma pCi/gram +2 sigma (1)
EVALUATION 6/8/2006 E5005-05 Vegetation Ce-141 0.209
+/-
0.007 0.223
+
0.007 0.94 Acceptable Cr-51 0.293
+
0.034 0.315 0.011 0.93 Acceptable Cs-134 0.159
+
0.007 0.154 0.005 1.03 Acceptable Cs-137 0.127
+/-
0.006 0.143 0.005 0.89 Acceptable Co-58 0.109
+/-
0.006 0.122 0.004 0.90 Acceptable Mn-54 0.160
+/-
0.006 0.178 0.006 0.90 Acceptable Fe-59 0.105
+/-
0.008 0.114 0.004 0.92 Acceptable Zn-65 0.207
+/-
0.013 0.225 0.008 0.92 Acceptable Co-60 0.140
+
0.005 0.156
+
0.005 0.90 Acceptable (1) Ratio = Reported/Analytics (See Section 7.3).
- Sample provided by Analytics, Inc.
97
TABLE 7-1 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Analysis of water SAMPLE JAF LAB REFERENCE LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/gram +/-1 sigma pCi/gram +/-2 sigma (1)
EVALUATION 2/15/2006 1831-3 Water 1-131 2.06E+06
+/-
2.77E+04 2.09E+06
+/-
1.47E+04 0.99 Acceptable H-3 h 12E+06
+/-
3.11E+03 1.11E+06
+/-
8.86E+03 1.01 Acceptable (1) Ratio = Reported/NIST (See Section 7.3).
- Sample provided by NIST Gamma Analysis of Filter SAMPLE JAF LAB REFERENCE LAB*
RATIO DATE ID NO.
MEDIUM ANALYSIS pCi/filter l sigma pCi/filter +/-2 sigma (1)
EVALUATION 6/8/2006 1851-16 Filter Mn-54 3.08E+04
+/-
158 2.80E+04
+/-
280 1.10 Acceptable Co-57 3.74E+04
+/-
94 3.36E+04
+/-
336 1.11 Acceptable Fe-59 1.01E+05
+/-
1418 8.91E+04
+/-
891 1.13 Acceptable Se-75 5.24E+04
+/-
508 5.61E+04
+/-
561 0.93 Acceptable Cs-134 3.OOE+04
+/-
143 2.76E+04
+/-
276 1.09 Acceptable (1) Ratio Reported/NIST (See Section 7.3).
- Sample provided by NIST 98
7.
3.6 REFERENCES
7.3.6.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.
7.3.6.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).3 99
- 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 2006 Land Use Census was conducted in the summer of 2006 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 is 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 from year 2001 occurred for the 2006 census, therefore no revisions of the 2001 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 2006 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 2006 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.
100
TABLE 8.1 2006 LAND USE CENSUS LOCATIONS*
SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi)
Km (Mi)
N 1.5(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 2.8(1.8)
SE 2.0(1.2) 3.6 (2.2) Cows**
SSE 2.1 (1.3)
S 0.5 (0.3) 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) 7.5 (4.7) Cows NW 2.6(1.6)
NNW 2.6(1.6)
- 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.
101
- 9.
SUMMARY
During 2006 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 800 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 ground water, 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-137 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.
102
- 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.
103