ML051240297
| ML051240297 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/26/2005 |
| From: | Jesse Rollins Yankee Atomic Electric Co |
| To: | Document Control Desk, NRC/FSME |
| References | |
| BYR 2005-042 | |
| Download: ML051240297 (126) | |
Text
YANKEE ATOMIC ELECTRIC COMPANY Telephone (413) 424-5261 49 Yankee Road, Rowe, Massachusetts 01367
'IANIE April 26, 2005 BYR 2005-042 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
License No. DPR-3 (Docket No. 50-29)
Subject:
2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Yankee Atomic Electric Company (YAEC) herewith submits the enclosed 2004 Annual Radiological Environmental Operating Report. This document provides a summary of the findings of the Radiological Environmental Monitoring Program (REMP) conducted by YAEC in the vicinity of the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts. This information is submitted in accordance with the YNPS Defueled Quality Assurance Program (YDQAP).
Should you have questions regarding the enclosed document, please contact the undersigned at (413) 424-2300.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY a-,.Jack D.ee2 Rollins Regulatory Affairs Manager Enclosure cc: J. Hickman, USNRC, Project Manager R. B. Bellamy, USNRC, Region I
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR)
YANKEE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1, 2004 - DECEMBER 31, 2004 DOCKET NO. 50-29 LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts AREVA DOC. 47-.W)1"-M
TABLE OF CONTENTS 1.0 EXECUTIVE
SUMMARY
.......................... 1
2.0 INTRODUCTION
............. 2 2.1 Gcn Plant eralSite Information .......................... 2 2.2 Program Dcsagn ............. 2 2.3 Monitoring Zones............. 3 2.4 Pathways Monitored ......................... .. 3 2.5 Dcscriptions of Monitoring Programs .......................... 4 2.5.1 Air Particulate Sampling .................... 4 2.5.2 River Water Sampling ..................... 4 2.5.3 Ground Water Sampling .................... 5 2.5.4 Storm Drain Water Sampling .................... 5 2.5.5 Sediment Sampling ..................... 5 2.5.6 Fish Sampling .......... 5 2.5.7 Food Product Sampling .................. 6 2.5.8 Maple Syrup Sampling ................ 6 2.5.9 TLD Monitoring ... . . . . .6 3.0 RADIOLOGICAL DATA
SUMMARY
TABLES ..................................... 22 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS ..................................... 35 4.1 Sampling Program Deviations ..................................... 35 4.2 Comparison of Achieved LLDs with Requirements ...................................... 35 4.3 Results Compared Against Reporting Levels ..................................... 35 4.4 Data Analysis by Media Type ..................................... 36 4.4.1 Air Particulates . .. . . . 36 4.4.2 Rivr Water ............. 37 4.4.3 GroundWater ............ 38 4.4.4 Storm Drain Water ...... 39 4.4.5 Sedimnt ............. 39 4.4.6 Fish. ............ 3 4.4.7 Food ............ 44 4.4.8 Maple ............ 44 4.4.9 Direct Radiation ............ 45 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS ...................................... 48
6.0 REFERENCES
...................................... 49 APPENDIX A - LAND USE CENSUS FOR 2004 .. A-I APPENDIX B - QUALITY ASSURANCE PROGRAM
SUMMARY
. .B-I APPENDIX C -
SUMMARY
OF 2004 REMP DATA .. C-I
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 1.0 EXECUTIVE
SUMMARY
The radiological environmental monitoring program for the Yankee Nuclear Power Station (YNPS) continued for the period January through December 2004, in compliance with the Yankee Decommissioning Quality Assurance Program (YDQAP), Appendix D, Section F.2.a, and the Off-Site Dose Calculation Manual (ODCM).
This annual report was prepared for the Yankee Atomic Electric Company (YAEC) by the Nuclear & Radiation Engineering Group of AREVA (Framatome ANP). Normandeau Associates performed sample collection and field preparation. Gamma exposure rate measurements and laboratory analyses were performed by AREVA Framatome ANP Environmental Laboratory (E-LAB).
Thermoluminescent dosimeters (TLDs) were used to measure direct gamma exposure in the vicinity of the plant and as far away as 22.2 kilometers. Radiochemical and radiological analyses of samples were performed to detect the presence of any plant-related radioactivity. Samples collected include air-particulate filters, broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, and fish.
In evaluating the results of those analyses it is necessary to consider the variability of natural and man-made sources of radioactivity, distribution in the environment and uptake in environmental media. This variability is dependent on many factors including plant release rates, past spatial variability of radioactive fallout from nuclear weapons tests and on-going redistribution of the fallout, contribution from cosmically produced radioactivity, ground water dynamics, soil characteristics, farming practices, and feed type. Any one of these factors could cause significant variations in measured levels of radioactivity. Therefore, these factors need to be considered in order to properly explain any variations in radiation detected and to distinguish between natural and station related radioactivity.
Yankee Nuclear Power Station (YNPS) was permanently shutdown in 1991. Activities at the YNPS site are now focused on fuel storage, site remediation and facility decommissioning. Most of the permanent structures are removed. Although the facility no longer generates power, decommissioning activities include discharging of liquids, such as ground water intrusion to building foundations, containing residual radioactivity and local area monitoring for any release of airborne radioactivity during building demolition. All levels of radioactivity released are significantly lower than releases during plant operation. The radiological monitoring of the environment through this REMP program will continue through plant decommissioning activities to assure the health and safety of the public are maintained at all times.
The predominant radioactivity detected by the monitoring program was that from non-plant sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As has been typical of previous years, plant-related radioactivity was observed in some of the monitoring samples. The specific observations of possible plant effects included Cesium-137 in bottom sediment near the plant discharge point and tritium in ground water and storm water samples due to monitored releases. Air particulate analysis results demonstrated that no plant-related airborne particulate activity was present in samples collected beyond the site boundary.
During 2004, there were no changes made to the radiological environmental monitoring program. However, supplemental environmental air particulate monitoring in the vicinity of on-site building demolition activities was initiated to validate effluent release (demolition airborne dust) monitoring assumptions. Results of those analyses are included in this report although they are not part of the formal REMP sampling.
I
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
2.0 INTRODUCTION
2.1 GENERAL PLANT SITE INFORMATION The Yankee Nuclear Power Station (YNPS) is located on a site of over 1800 acres in a predominantly rural area of northwestern Massachusetts, three-quarters of a mile south of the Vermont border. The plant site resides in the town of Rowe, Massachusetts, approximately 9 air miles east-northeast of North Adams, Massachusetts.
The surrounding area is heavily forested and lightly populated. Hills bounding the river valley rise 500 to 1000 feet above the site, reaching elevations of 2100 feet.
The Deerfield River is used extensively for hydroelectric power generation both upstream and downstream of YNPS. Sherman Dam, immediately adjacent to YNPS, operates as a hydroelectric generating station. Sherman Pond, the impoundment behind this dam, had been used as a source of cooling water for YNPS.
YNPS voluntarily shut down on October 1, 1991 after 31 years of operation. The plant is involved in the process of decommissioning which involves the disassembly and removal of the plant components and structures. This process is taking place in strict conformance with USNRC regulations. Oversight of the decommissioning process will also continue from the U.S. Environmental Protection Agency, the Massachusetts Department of Environmental Protection, Massachusetts Department of Public Health, and Massachusetts Emergency Management Agency.
The radiological environmental monitoring program for YNPS continued during 2004 and will continue throughout the decommissioning period until its I0CFR50 license is terminated.
2.2 PROGRAM DESIGN The Radiological Environmental Monitoring Program for the YNPS was designed with specific objectives in mind. These were:
- To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by YNPS activities.
- To provide assurance to regulatory agencies and the public that the environmental impact from YNPS is known and within anticipated limits.
- To verify the adequacy and proper functioning of plant 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.
These objectives will continue to be in force, to varying degrees, throughout decommissioning activities at the YNPS site. Due to the shutdown status of the plant and relatively low quantities of radioactive material remaining on the site, some of the objectives have a different degree of importance than in the past.
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 The radiological environmental monitoring program was initiated in 1958, approximately two years before the plant began operation in 1960. It has been in operation continuously since that time, with improvements made periodically over those years. The program continued without modification following the shutdown of the plant in 1991 and was reduced in scope beginning in 1997 primarily to reflect the absence of short lived radionuclides in various pathways resulting from the plant shutdown (no source of production) and the individual radionuclides short half-life (long decay time since the shutdown).
The program was designed to meet the intent of NRC Regulatory Guide 4. 1, PrograinsforMonitoring Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specfi cationsforNuclearPower Plants; the NRC Branch Technical Position of November 1979 entitled, An Acceptable RadiologicalEnvironmentalMonitoring Programn;and NRC NUREG-0472, RadiologicalEffluent Technical SpecificationsforPWVR s.
The environmental TLD program was designed and tested around NRC Regulatory Guide 4.13, Performance Testing and ProceduralSpecificationisforThermoluminescence Dosimntiy: EEzvironmentalApplications. The quality assurance program was designed around the guidance given in NRC Regulatory Guide 4.15, Quality Assurancefor RadiologicalMonitoring Programs(Normal Operations)- Effluent Streams and the Environment.
The sampling requirements of the REMP are given in Table 4.1 of the ODCM and in Table 2.1 of this report.
The identification of the required sampling locations is given in Table 4.4 of the ODCM and in Tables 2.2 and 2.3 of this report. The sampling and monitoring locations are shown graphically on the maps in Figures 2.1 through 2.6.
2.3 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. The first area locations are called "indicators", and the second area locations are called "controls." The distinction between the two areas, 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 areas aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to plant activities and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.
2.4 PATHWAYS MONITORED Four pathway categories are monitored by the REMP. They are 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:
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
- Airborne Pathway
- Air Particulate Sampling Section 2.5.1
- Waterborne Pathways
- River Water Sampling Section 2.5.2
- Ground Water Sampling Section 2.5.3
- Storm Drain Water Sampling Section 2.5.4
- Sediment Sampling Section 2.5.5
- Ingestion Pathways
- Fish Sampling Section 2.5.6
- Food Product (fruits & vegetables, Section 2.5.7 broad Ieaf vegetation)
- Maple Syrup Sampling Section 2.5.8
- Direct Radiation Pathway
- TLD Monitoring Section 2.5.9
2.5 DESCRIPTION
S OF MONITORING PROGRAMS Sample types and frequency of analysis are given in Table 2.1. The sample locations are listed in Table 2.2 and Table 2.3 and shown in Figures 2.1 - 2.7. ODCM lower limits of detection (LLDs) and required reporting levels are listed in Tables 2.4 and 2.5. The program as described here includes both required samples as specified in the Off-Site Dose Calculation Manual (ODCM) and any extra samples. Following is a detailed description of the sampling program for 2004:
2.5.1 Air Particulate Sampling Continuous air samplers are installed at six locations, five of which are required by the YNPS 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 47-mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. The filters are collected biweekly, and, to allow for the decay of radon daughter products, they are held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at the E-LAB before being analyzed for gross-beta radioactivity (indicated as GR-B in the data tables). The biweekly filters are composited by location at the E-LAB for a quarterly gamma spectroscopy analysis.
In addition to station AP-I 1, which doubles as a REMP and demolition air particulate (DAP) monitor located just outside the site, three new airborne monitoring surveillance locations were established on-site for the detection of possible airborne radionuclides associated with demolition work. This monitoring is intended to provide supporting information, from onsite monitoring of potential airborne releases. Results of those analyses are included in this report although they are not part of the REMP sampling.
2.5.2 River Water Sampling An automatic composite sampler is located at one downstream sampling location. The sampler is controlled by timers that collect an aliquot of river water at least every two hours over a period of one month. In addition, 4
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 river water grab samples are collected monthly at Sherman Pond, near the plant site, and at one upstream location (control). All river water samples are preserved with HCL and NaHSO 3 or HNO 3 at the laboratory to prevent the plate-out of potentially present radionuclides on the container wall over time. Each sample is analyzed for gross-beta and gamma-emitting radionuclides. The monthly samples are composited quarterly by location at the E-LAB for a H-3 analysis. The monthly H-3 samples are also analyzed as a non ODCM requirement.
2.5.3 Ground Water Sampling Grab samples arc collected monthly from two on-site locations. The ODCM requires samples to be collected at least once per quarter. Each sample is required by the ODCM to be analyzed for gamma-emitting radionuclides and H-3. Samples are also analyzed for gross beta activity, which is not an ODCM requirement.
Gross beta analyses are performed to gather additional data that may help to provide early detection of plant-related activity.
2.5.4 Storm Drain Water Sampling Grab samples are collected monthly or as available from the East and West Storm Drains. These are not ODCM required sampling locations. This water is comprised of a network of storm drains connected to parking areas, associated facility, and administration building, as well as groundwater and precipitation (including snowmelt) draining from the east side and west side of the plant facility. The storm drains are utilized for construction de-watering discharges in accordance with the plant's ODCM and NPDES requirements. Each sample is analyzed for gross-beta and gamma-emitting radionuclides and H-3.
2.5.5 Sediment Sampling Shoreline sediment cores are collected semiannually from two locations, one upstream and one downstream of the plant. At each location, six two-inch inner diameter plastic coring tubes are driven into the sediment at least six inches deep. The cores are carefully extracted and kept in an upright position and frozen prior to delivery to the E-LAB. At the E-LAB, the frozen cores are cut into 5 cm (two-inch) segments. For each location, the 0-5 cm segments are blended into a single sample, as are the 5-10 cm and 10-15 cm segments. These composite samples are then analyzed for gamma-emitting radionuclides.
An additional bottom sediment core is collected semiannually in Sherman Pond near the plant discharge. A Wildco K. B. Core Sampler, fitted with a plastic coring tube, is dropped from a boat. Six cores are collected here, and are processed and analyzed as described above.
2.5.6 Fish Sampling Fish samples are collected semiannually at two locations (upstream of the plant and in Sherman Pond). A gill net is set overnight from a boat, and mixed species of fish are removed the following day. The species typically collected are yellow perch, smelt, pickerel, trout, bullheads or suckers. However, the makeup of any individual catch could be dominated by a single species available at the time. No attempt is made to differentiate sample analysis by fish species, such as those who primarily feed on the bottom and are closer to any radioactivity deposited in bottom sediments, from those species that feed higher in the water column. The fish samples are frozen and delivered to the E-LAB where the edible portions are analyzed for gamma-emitting radionuclides.
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 2.5.7 Food Product Sampling Food products are collected annually (at harvest) at three locations. The samples are either tuberous vegetables, above-ground vegetables, or fruit. Two indicator locations are chosen as a result of the annual Land Use Census and meteorological dispersion calculations. The third location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it. The edible portions of the samples are then analyzed at the E-LAB for gamma-emitting radionuclides.
2.5.8 Maple Syrup Sampling Maple syrup is an important commercial product in northern New England, including the YNPS plant environs.
Consequently, samples are collected annually from two locations although there is no ODCM requirement.
These samples are collected from the syrup manufacturer as a finished product, that is, following the boiling down of the maple sap, which in theory, concentrates any radioactive particulates in the media, thereby increasing the probability of detection. Since the samples have already been boiled down as part of the syrup production process, no preservatives are needed in the samples. Following collection, the samples are analyzed at the E-LAB for gamma-emitting radionuclides. It should be noted that because of the boiling down and filtering of the sap, the resulting radionuclide measurements do not represent actual environmental concentrations. It is estimated that the resulting syrup has been concentrated by a factor of from 15 to 120 times the original sap, depending mostly on the time of the season that the sap was collected.
2.5.9 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801ASI and UD-814ASI 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-screened container. This container is attached to an object such as a tree, fence or utility pole. TLDs are posted at 33 locations, with 24 of these stations required by the ODCM. All the TLDs are read out quarterly. Normandeau posts and retrieves all TLDs, while the E-LAB processes them.
During 2002, new sets of 16 TLDs were installed at locations to monitor the Independent Spent Fuel Storage Installation (ISFSI) prior to, during and following completion of fuel transfer. These locations are listed in Table 2.3. In 2004, one of the ISFSI TLD locations (IF-18) was relocated about 60 feet closer to the storage pad. This was necessary when the Screen Well House, upon which the TLD had been mounted, was demolished as part of site decommissioning activities. The ISFSI TLD monitoring is not part of the REMP program but will be incorporated in the program following structure demolition and license termination.
6
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Yankee Nulcear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.1 Radiological Environmental Monitoring Program (Sample Types, Collection Frequency, Analysis Requirements)
(as required by ODCM Table 4.1)
Collection Analysis Exposure Pathway Number of Routine Collection Analysis Analysis And/or Sample Media Sample Locations Sampling Frequency Type Frequency Mode
- 2. Airborne: Particulates 5 Continuous Once per two Gross Beta Each Sample weeks Gamma Isotopic Quarterly Composite by Location
- 3. Waterborne
- a. Surface Water I Composite at two Monthly Gross Beta Each Sample hour intervals- Gamma Isotopic Each Sample Downstream Tritium (H-3) Quarterly Composite I Grab -Upstream Monthly
- c. Shoreline Sediment I Grab Semiannually Gamma Isotopic Each Sample
- Does not include Site Restricted Area fence locations and those TLDs associated with ISFSI pad monitoring.
7
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Yankee Nulcear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2..1 (ContinuedINI)
Radiological Environmental Monitoring Program (Sample Types, Collection Frequency, Analysis Requirements)
(As required by ODCM Table 4.1)
Collection Analysis Exposure Pathway Andlor Nominal Number Routine Nominal Analysis Analysis Sample Media of Sampling Collection Type Frequency Sample Locations Mode Frequency
- 4. Ingestion
- a. Fish 2 Grab Semiannually Gamma Isotopic on edible Each sample (or seasonal if portions appropriate)
- b. Food Products Tuberous or above ground 3 Grab At harvest Gamma Isotopic on edible Each sample vegetables, or fruit portion 8
Yank~ee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.2 Radiological Environmental Monitoring Locations (non-TLD) in 2004 Yankee Nuclear Power Station Distance Exposure Station From Plant Direction Pathwav Code Station Description Myca Stack (Mm) From Plant Stack
- 1. Airborne AP-I I(DAP-4) Observation Stand I 0.5 N AP-12 Monroe Bridge I 1.1 SW AP-13 Rowe School I 4.2 SE AP-14 Harriman Station I 3.2 N AP-21 Williamstown, MA C 22.2 W AP-31
- YAEC Visitor's Center I 0.8 SW DAP- I
- DEMCO Trailer DI 0.1 NE
- 2. Waterborne
- a. Surface WR-1 I Bear Swamp Lower 6.3 Down-river WR-21 Harriman Reservoir C 10.1 Up-river WR-31* Sherman Pond 0.1 N
- b. Ground WG--I I Plant Potable I On-site WG-12 Sherman Spring I 0.2 NW
- c. Storm Drain WW-5I
- East Storm Drain I On-site WW-52* West Storm Drain I On-site
- Sherman Pond I 0.1 N
- 3. Ingestion
- a. Fish FH-I I Sherman Pond I 1.5 Near Discharge FH-21 Harriman Reservoir C 10.1 Up-river a I=Indicator Station, C=Control Station, DI=Demolition release indicators (Not part of REMP).
- Additional stations not required by the ODCM Radiological Environmental Monitoring Program (ODCM Table 4.4).
9
Yank~ee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.2 (Continued)
Radiological Environmental Monitoring Locations (non-TLD) in 2004 Yankee Nuclear Powver Station Distance Exposure Station From Plant Direction Pathway Code Station Description TVPca (kin) From Plant
- b. Food Products TF- II Monroe Bridge, MA I 1.3 SW TF- 13 Monroe, MA I 1.9 WNW TF-2 1 Williamstown, MA C 21.0 WSW MS-33* Rowe, MA I 1.0 S (Maple Syrup)
MS-45* Florida, MA C 10.5 WSW' (Maple Syrup) a I=Indicator Station, C=Control Station, DI=Demolition release indicators (Not part of REMP)..
- Additional stations not required by the ODCM Radiological Environmental Monitoring Program 10
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.3 Radiological Environmental Monitoring Locations (TLD) in 2004 Yankee Nuclear Power Station Distance From Plant Direction Station Code Station Description Tj pa (km){ From Plant GM-I YAEC Visitors' Center I 0.8 SW GM-2 Observation Stand I 0.5 NW GM-3 Rowe School I 4.2 SE GM-4 Harriman Station I 3.2 N GM-5 Monroe Bridge I 1.1 SW GM-6 Readsboro Road Barrier I 1.3 N GM-7 Whitingham Line I 3.5 NE GM-8 Monroe Hill Barrier I 1.8 S GM-9 Dunbar Brook I 3.2 SW GM-10 Cross Road l 3.5 E GM-I I Adams High Line l 2.1 WNW GM-12 Readsboro, VT l 5.5 NNW GM-13 b Restricted Area Fence 1 0.08 WSW GM-14b Restricted Area Fence F 0.11 WNW GM-15 b Restricted Area Fence E 0.08 NNW GM-16 Restricted Area Fence F 0.13 NNE GM-17b Restricted Area Fence F 0.14 ENE GM-18b Restricted Area Fence F 0.14 ESE GM-19 b Restricted Area Fence F 0.16 SE GM-20b Restricted Area Fence F 0.16 SSE GM-21 b Restricted Area Fence F 0.11 SSW GM-22 Hcartwellville, VT C 12.6 NNW GM-23 Williamstown Substation C 22.2 W GM-25 Whitingham, VT F 7.7 NNE GM-27 t 9 Road Number 7.6 ENE GM-29 Route 8A 0 8.2 ESE a I = Indicator TLD; C = Control TLD; 0 = Outer Ring TLD; F = Fence line TLD, IF=ISFSI.
b These TLDs are located inside of the site boundary and not, therefore, part of the REMP program. These were placed inside of the site boundary to provide early indication of the potential increase in site boundary dose due to plant-related activities.
GM station distances and direction are from the plant stack.
11
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.3 (Continued)
Radiological Environmental Monitoring Locations (TLD) in 2004 Yankee Nuclear Powver Station Distance From Direction Station Code Station Description Typea Plant/ISFSI From (kim) Plant/ISFSI GM-31 Legate Hill Road 0 7.6 SSE GM-32 Rowe Road 0 7.9 S GM-33 Zoar Road 0 6.9 SSW GM-35 Whitcomb Summit 0 8.6 WSW GM-36 Tilda Road 0 6 .6 W GM-38 West Hill Road 0 6.6 NW GM40 Readsboro Road I 0.7 W IF-1 ISFSI Security Fence IF 0 .02 d WNW IF-2 e Observation Stand IF 0.56d NW I ISFSI Security Fence IF 0.02 d N IF4 ISFSI Security Fence IF 0.03 d NE IF-ISFSI Security Fence IF 05 d E IF-6C ISFSI Security Fence IF 0.02 d SE IF-7 c ISFSI Security Fence IF 0.02 d S IF-8C ISFSI Security Fence IF o.o0 d SW IF e Restricted Area Fence IF 0.05 d SE IF-10 Restricted Area Fence IF 0.05 d SSE IF-Ie Restricted Area Fence IF 0.14 d SW IF-12C Restricted Area Fence IF 0.21 d N IF-180 YNPS CW Intake IF 0.24 d NNW IF-I9 RISFSI Security Fence Admin. Building IF 0.17 d W IF-20 C ISFSI Security Fence Gatehouse IF 0.24 d WNW IF40 Readsboro Road IF 0.70 d WNW a I = Indicator TLD; C = Control TLD; 0 = Outer Ring TLD; F = Fenceline TLD, IF = ISFSI GM station distances and direction are from the former plant stack.
d IF station distances and direction from ISFSI pad.
C These TLDs monitor (tie YNPS ISFSI and are not part of the REMP program.
12
Yankeec Nuclear Power Station Annual Radiological Environmcntal Operating Report 2004 TABLE 2.4 Environmental Lower Limit of Detcction (LLD) Sensitivity Requirements from ODCM Table 4.3 Airborne Food Water Particulates Fish Product Sediment Analysis (pCi/) or Gases (pCi/m3 ) (pCi/kg) (pCi/kg) (pCi/kg -dry)
(wet) (wet)
Gross-Beta 4 0.01 H-3 2000 Co-58,60 15 130 Cs-134 15 0.05 130 60 150 Cs-137 18 0.06 150 80 180 13
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.5 Reporting Levels for Radioactivity Concentrations In Environmental Samples from ODCM Table 4.2 Airborne Particulates Fish Food Product Analysis Water or Gases (pCi/m 3 (pCi/kg) (pci/k-g)
(pCiIl)* (wet)
H-3 30000 Mn-54 1000 l 30000 Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 Cs-134 30 10 1000 1000 Cs-137 50 20 2000 2000 Reporting Level for non-drinking water pathways.
14
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.1 Radiological Environmental Sampling Locations Within 1 Mile of Yankee Nuclear Power Station N
. . I. . . . . . . . . . . . . . .. . . . .. . . . ........
ssachusetts Sherman Pond b 1YNPS
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.2 Radiological Environmental Sampling Locations Within 12 Miles of Yankee Nuclear Power Station x1 Harriman Resei A X )E-21 AP-14 S \ \<< WR-21 \
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 3 Figure 2.3 Radiological Environmental Sampling Locations Outside 12 Miles of Yankee Nuclear Power Station rriman Reservoir l i; ' ; Vermot YNPS Mass chu l~~ h 0~=V sm U 1 I
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.4 Environmental TLD Monitoring Locations Within 1 Mile of Yankee Nuclear Power Station 18
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.5 Environmental TLD Monitoring Locations Within 12 Miles of Yankee Nuclear Power Station 4N N NN . N GM-22 arrimaF eserv~ir GM-25
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Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.6 Environmental TLD Monitoring Locations Outside of 12 Miles from Yankee Nuclear Power Station 20 N
Yank;cc Nuclear Power Station Annual Radiological Environmcntal Operating Report 2004 Figure 2.7 Environmental TLD Monitoring Locations For the ISFSI Facility at the Yankee Nuclcar Power Station Io 0.l sCaL 21
Yankecc Nuclear Power Station Annual Radiological Environmental Operating Report 2004 3.0 RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples that were collected during 2004. These results, shown in Table 3.1, 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 for the pathways described in Section 2.3. A comparison of indicator stations versus control stations is presented. Table 3.2 provides the same information for TLD direct radiation measurements.
The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 2004, and the number of measurements which exceeded the Reporting Levels found in Table 4.2 of the YNPS ODCM. The latter are classified as "Non-routine" results. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides, which have detection capability requirements as specified in the ODCM Table 4.3. 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 30-40 percent of the most restrictive required LLD. Occasionally the required LLD is not met. This is usually due to malfunctions in sampling equipment, which result in low sample volume. Such cases are addressed in Section 4.2.
For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (I) the Indicator stations, which are within the range of influence of the plant and which could conceivably be affected by plant activities; (2) the station which had the highest mean concentration during 2004 for that radionuclide; and (3) the Control stations, which are beyond the influence of the plant. Direct radiation monitoring stations (using TLDs) are grouped into Indicator, Outer Ring, Fenceline and Control stations.
In each of these columns, for each radionuclide, the following are given:
- The mean value of all concentrations including negative values and values that are not considered "detectable".
- The lowest and highest concentration.
- The number of detectable measurements divided by the total number of measurements.
A sample is considered to yield a "detectable measurement" when the concentration exceeds three times its associated standard deviation. The standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure.
The radionuclides reported in this section represent those that: I) had a Reporting Level listed in Table 4.2 of the ODCM or, a LLD requirement in Table 4.3 of the ODCM, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of specific interest for any other reason. The radionuclides that are routinely analyzed and reported by the E-LAB in a gamma spectroscopy analysis includes: Ac-Th-228, Ag-108m, Ag-I 10m, Ba-140, Be-7, Ce-141, Cc-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59,1-131, K-40, La-140, Mn-54, Nb-95, Ru-103, Ru-106, Sb-124, Sb-125, Se-75, Zn-65 and Zr-95. In no case did a radionuclide not shown in Table 3.1 appear as a "detectable measurement" during 2004.
Data from direct radiation measurements made by TLDs are provided in Table 3.2 in a format essentially the same as above. The complete listing of quarterly TLD data is provided in Table 3.3. Table 3.4 contains a list of new TLDs placed to monitor the YNPS ISFSI. Locations of these, including two located offsite, are shown in Figures 2.4 and 2.7.
22
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January- December 2004)
MEDIUM: Air Particulates (AP) UNITS: pCilcubic meter Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected"' No. Detected--- No. Detected",
GR-B (162) 0.01 2.OE -2 13 2.4E -2 1.8E -2 (0) ( 6.2 - 39.7)E -3 ( 1.5 - 4.0)E -2 ( 1.2 - 3.3)E -2 (135/ 135) (27/ 27) (27/ 27)
Be-7 (24) 9.2E -2 13 1.1E -1 9.4E -2 (0) ( 5.1 - 14.9)E -2 ( 6.2 - 14.9)E -2 ( 6.2 - 11.8)E -2 (20/ 20) (4/ 4) (4/ 4)
Co-58 (24) -1.2E -4 14 2.8E -4 -1.9E -4 (0) ( -1.0 - 0.8)E -3 ( -4.3 - 8.4)E -4 ( -7.0 - 6.1)E -4 (0/ 20) (0/ 4) (0/ 4)
Co-60 (24) 4.1E -5 31 4.1E -4 -3.OE -4 (0) ( -1.0 - 0.8)E -3 ( 2.2 - 7.9)E -4 I -7.2 - 1.9)E -4 (0/ 20) (0/ 4) (0/ 4)
Cs-1 34 (24) 0.05 2.OE -5 14 2.6E -4 -3.7E -5 (0) ( -6.8 - 7.0)E -4 ( 0.0 - 5.9)E -4 ( -1.9 - 2.5)E -4 (0/ 20) (0/ 4) (0/ 4)
Cs-1 37 (24) 0.06 -9.1E -5 13 3.6E -4 -1.3E -4 (0) I -1.3 - 0.8)E -3 ( -4.2 - 8.2)E -4 ( -1.3 - 1.1)E -3 (0/ 20) (0/ 4) (0/ 4) 23 The only radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"'Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 4.2.
"I The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.
Yankecc Nuclear Piower Station Annual Radiological Environmental Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Fish (FHl UNITS: DCilkQ Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected No. Detected No. Detected'..
K-40 (4) 2.8E 3 3.5E 3 3.5E 3 (0) ( 2.3 - 3.4)E 3 ( 3.5 - 3.6)E 3 ( 3.5 - 3.6)E 3 (2/ 2) (2/ 2) (2/ 2)
Mn-54 (4) 130 -3.OE 0 9.OE 0 9.OE 0 (0) ( -1.6 - 1.0)E 1 ( 1.0 - 17.0)E 0 ( 1.0 - 17.0)E 0 (0/ 2) (0/ 2) (0/ 2)
Co-58 (4) 130 1.5E 1 1.5E 1 3.5E 0 (0) ( 1.0 - 0.9)E2 ( 1.0 - 1.9)E 1 -1.6 - 2.3)E 1 (0/ 2) (0/ 2) (0/ 2)
Fe-59 (4) -5.OE 0 -5.OE 0 -5.3E 1 (0) ( -2.2 - 1.2)E 1 -2.2 - 1.2)E 1 -1.3 - 0.3)E 2 (0/ 2) (0/ 2) (0/ 2)
Co-60 (4) 130 -5.OE -1 6.OE 0 6.OE 0 (0) ( -1.1 - 1.0)E 1 -2.0 - 14.0)E 0 -2.0 - 14.0)E 0 (0/ 2) (0/ 2) (0/ 2)
Zn-65 (4) 260 1.2E 1 1.2E 1 -3.1E 1 (0) ( 0.0 - 2.3)E 1 ( 0.0 - 2.3)E 1 -3.7 - -2.5)E 1 (0/ 2) (0/ 2) (0/ 2)
Cs-134 (4) 130 4.8E 0 4.8E 0 1.3E 0 (0) ( 2.6 - 7.1)E 0 ( 2.6 - 7.1)E 0 C -2.0 - 4.5)E 0 (0/ 2) (0/ 2) (0/ 2)
Cs-1 37 (4) 150 3.7E 1 3.7E 1 7.5E 0 (0) ( 3.5 - 3.9)E 1 ( 3.5 - 3.9)E 1 -6.0 - 21.0)E 0 (0/ 2) (0/ 2) (0/ 2) 24 The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 4.2.
- - The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.
Yankeec Nuclear Power Station Annual Radiological Environmcntal Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Manle Svrun (MS) UNITS: Cli/ka Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected--- No. Detected- No. Detected'
Be-7 (2) 1.8E 1 33 1.8E 1 8.OE 0 (0)
(0/ 1) (0/ 1) (0/ 1)
K-40 (2) 1.9E 3 33 1.9E 3 1.5E 3 (0)
(1/ 1) (1/ 1) (1/ 1)
Mn-54 (2) -9.OE -1 45 9.OE -1 9.OE -1 (0)
(0/ 1) (o/ 1) (O/ 1)
Co-57 (2) -1.3E 0 45 O.OE 0 O.OE 0 (0)
(O/ 1) (0/ 1) (0/ 1)
Co-58 (2) 3.0E -1 45 2.2E 0 2.2E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Fe-59 (2) 1.6E 1 33 1.6E 1 1.2E 1 (0)
(0/ 1) (Of 1) (O/ 1)
Co-60 (2) -1.OE 0 45 4.OE 0 4.0E 0 (0)
(O/ 1) (O/ 1) (0/ 1)
Zn-65 (2) -1.1E 1 45 8.3E 0 8.3E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Zr-95 (2) 6.0E -1 45 2.2E 0 2.2E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Ru-1 03 (2) -2.1E 0 33 -2.1E 0 -3.4E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Ru-106 (2) 2.5E 1 33 2.5E 1 -2.OE 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Ag-11im (2) -4.5E 0 45 2.5E 0 2.5E 0 (0)
(0/ 1) (0/ 1) (0/ 1) 25 The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section Sof this report for a discussion of other radionuclides that were analyzed.
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 4.2.
- -- The traction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown In parentheses.
Yanlkee Nuclear Powcr Station Annual Radiological Environmcntal Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Maple SYrup (MS) UNITS: PClkq Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected--- No. Detected--- No. Detected'--
Sb-1i24 (2) 2.3E 0 33 2.3E 0 -1.2E 0 (0)
(0/ 1) (0/ 1) (o/ 1) 1-131 (2) -4.1E 0 45 5.6E 0 5.6E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Cs-134 (2) 60 -8.0E -1 33 -8.0E -1 -2.7E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Cs-137 (2) 80 2.0E 1 33 2.OE I 1.4E 1 (0)
(1/ 1) (1/ 1) (1/ 1)
Ba-1 40 (2) 8.0E -1 33 8.OE -1 -4.OE -1 (0)
(0/ 1) (0/ 1) (0/ 1)
Ce-1 41 (2) -3.6E 0 45 -2.7E 0 -2.7E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Ce-1 44 (2) 1.2E 1 33 1.2E 1 4.OE 0 (0)
(01 1) (0/ 1) (0/ 1)
Th-232 (2) 2.6E 0 45 3.6E 0 3.6E 0 (0)
(0/ 1) (0/ 1) (0/ 1) 26
'The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels In OCM Table 4.2.
-- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.
Yankecc Nuclcar Powcr Station Annual Radiological Environmental Operating Rcport 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January- December 2004)
MEDIUM: Sediment (SE) UNITS: pCifkq dry Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected--- No. Detected--- No. Detected---
Be-7 (18) 8.BE 1 91 3.OE 2 -4.7E 1 (0) ( -4.3 - 7.7)E 2 I -2.7 - 7.7)E 2 ( -4.1 - 2.3)E 2 (0/ 12) (0/ 6) (0/ 6)
K-40 (18) 2.OE 4 9S 2.5E 4 1.SE 4 (0) ( 9.7 - 26.4)E 3 ( 2.3 - 2.6)E 4 ( 1.3 - 1.S)E 4 (12/ 12) (6/ 6) (6/ 6)
Co-58 (18) -6.1E 0 91 -3.8E 0 -1.2E 1 (0) ( -7.2 - 4.1)E 1 ( -5.9 - 4.1)E 1 ( -3.6 - 0.4)E 1 (0/ 12) (0/ 6) (0/ 6)
Co-60 (18) -4.3E 0 21 1.2E 1 1.2E 1 (0) ( -5.4 - 4.3)E 1 ( 0.0 - 2.6)E 1 ( 0.0 - 2.6)E 1 (0/ 12) (0/ 6) (0/ 6)
Cs-134 (18) 150 3.5E 0 91 5.OE 0 9.7E -1 (0) ( -8.0 - 9.5)E 1 ( -8.0 - 9.5)E 1 ( -2.5 - 5.2)E 1 (0/ 12) (0/ 6) (0/ 6)
Cs-137 (18) 180 6.1E 2 91 1.lE 3 1.7E 2 (0) ( -1.6 - 135.7)E 1 ( 8.4 - 13.6)E 2 ( 6.3 - 27.8)E 1 (9/ 12) (6/ 6) (4/ 6)
Th-232 (18) 1.4E 3 91 2.OE 3 6.OE 2 (0) ( 5.5 - 22.2)E 2 ( 1.7 - 2.2)E 3 ( 3.7 - 8.6)E 2 (12/ 12) (6/ 6) (6/ 6) 27
'The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"Non-Routine refers to those radionuciides that exceeded the Reporting Levels In ODCM Table 4.2.
"I The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown In parentheses.
Yankee Nuclear Power Station Annual Radiological Environmcntal Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Food Crop (TF) UNITS: pCi/kq Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected'*' No. Detected- No. Detected",
K-40 (3) 3.3E 3 13 5.5E 3 1.9E 3 (0) ( 9.8 - 55.2)E 2 (2/ 2) (1/ 1) (1/ 1)
Co-58 (3) -1.0E -1 13 4.6E 0 -6.3E 0 (0) ( -4.8 - 4.6)E 0 (0/ 2) (0/ 1) (0/ 1)
Co-60 (3) 6.6E 0 13 2.6E 1 1.0E 1 (0) ( -1.3 - 2.6)E 1 (0/ 2) (0/ 1) (0/ 1) 1-131 (2) -1.5E 1 21 3.0E 0 3.0E 0 (0)
(0/ 1) (0/ 1) (0/ 1)
Cs-134 (3) 60 -1.2E 1 21 -2.7E 0 -2.7E 0 (0) ( -1.5 - -0.9)E 1 (0/ 2) (0/ 1) (0/ 1)
Cs-137 (3) 80 -1.0E 1 13 -2.6E 0 -8.8E 0 (0) ( -1.8 - -0.3)E 1 (0/ 2) (0/ 1) (0/ 1) 28
- The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2.
"I The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown In parentheses.
Yankec Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Ground Water (WG) UNITS: pCi/liter Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected' No. Detected," No. Detected-
GR-B (24) 4 4.4E 0 12 5.8E 0 NO DATA (0) ( 1.5 - 9.0)E 0 ( 3.2 - 9.0)E 0 (17/ 24) (11/ 12)
H-3 (24) 2000 1.2E 2 12 2.2E 2 NO DATA (0) ( -2.5 - 5.9)E 2 t -1.0 - 59.0)E 1 (3/ 24) (3/ 12)
Mn-54 (24) 15 8.0E -2 12 5.OE -1 NO DATA (0) -3.6 - 3.2)E 0 t -2.6 - 3.2)E 0 (0/ 24) (0/ 12)
Co-58 (24) 15 -6.4E -1 12 -5.5E -1 NO DATA (0) -2.6 - 2.2)E 0 t -2.6 - 2.2)E 0 (0/ 24) (0/ 12)
Fe-59 (24) 1.OE 0 11 2.5E 0 NO DATA (0) -7.9 - 16.0)E 0 t -7.9 - 16.0)E 0 (0/ 24) (0/ 12)
Co-60 (24) 15 5.3E -1 11 8.6E -1 NO DATA (0) -3.4 - 3.3)E 0 t -1.8 - 3.2)E 0 (0/ 24) (0/ 12)
Zn-65 (24) 30 -2.4E 0 11 -1.1E 0 NO DATA (0) -1.3 - 1.1)E 1 ( -1.2 - 1.1)E 1 (0/ 24) (0/ 12)
Zr-95 (24) 15 3.7E -1 11 1.5E 0 NO DATA (0) -7.8 - 6.8)E 0 ( -3.6 - 6.8)E 0 (0/ 24) (0/ 12) 1-131 (24) -1.6E 0 11 -2.9E -1 NO DATA (0) -1.2 - 1.4)E 1 ( -6.4 - 2.8)E 0 (0/ 24) (0/ 12)
Cs-1 34 (24) 15 1.OE -1 11 1.2E -1 NO DATA (0) -2.0 - 2.6)E 0 ( -2.0 - 1.8)E 0 (0/ 24) (0/ 12)
Cs-137 (24) 18 -4.3E -1 12 9.2E -2 NO DATA (0) -2.4 - 3.2)E 0 ( -2.1 - 3.2)E 0 (0/ 24) (0/ 12)
Ba-1 40 (24) 3.8E -1 12 1.7E 0 NO DATA (0) ( -6.1 - 17.4)E 0 ( -3.1 - 17.4)E 0 (0/ 24) (0/ 12) 29 The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 4.2.
"I The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.
Yankec Nucicar Power Station Annual Radiological Environmental Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: River Water fWR) UNITS: pClikq Indicator Stations Station With Highest Mean Control Stations Radionuclides- Mean
- Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected-.. No. Detected--- No. Detected---
GR-B (36) 4 2.3E 0 11 2.8E 0 1.6E 0 (0) ( 3.2 - 69.0)E -1 ( 8.9 - 69.0)E -1 ( 2.6 - 24.4)E -1 (5/ 24) (4/ 12) (O0 12)
H-3 (49) 2000 -5.8E 1 31 -1.2E 1 -7.6E 1 (0) ( -1.0 - 0.8)E 3 ( -7.9 - 5.5)E 2 ( -6.7 - 4.8)E 2 (O/ 33) (Of 17) (O0 16)
Mn-54 (36) 15 -2.7E -1 31 -1.4E -1 -8.7E -1 (0) ( -2.8 - 2.2)E 0 ( -2.2 - 1.7)E 0 ( -5.0 - 1.2)E 0 (O/ 24) (0/ 12) (O/ 12)
Co-58 (36) 15 -8.6E -1 21 -3.0E -1 -3.OE -1 (0) ( -5.4 - 2.1)E 0 ( -2.0 - 4.3)E 0 -2.0 - 4.3)E 0 (O/ 24) (0/ 12) (O0 12)
Fe-59 (36) -2.OE 0 31 -3.8E -1 -1.8E 0 (0) -1.0 - 0.6)E 1 ( -1.0 - 0.6)E 1 -7.9 - 5.6)E 0 (O/ 24) (O0 12) (O0 12)
Co-60 (36) 15 7.OE -1 31 1.1E 0 1.0E 0 (0) -3.4 - 4.3)E 0 ( -3.4 - 4.3)E 0 -1.5 - 3.1)E 0 (O0 24) (O0 12) (O0 12)
Zn-65 (36) 30 -1.3E 0 21 8.2E -1 8.2E -1 (0) -1.5 - 1.0)E 1 ( -8.1 - 7.9)E 0 -8.1 - 7.9)E 0 (O/ 24) (Of 12) (O/ 12)
Zr-95 (36) 15 -2.2E -1 31 8.3E -1 5.3E -1 (0) -6.9 - 6.9)E 0 ( -2.9 - 6.9)E 0 -9.6 - 8.7)E 0 (0/ 24) (O0 12) (O0 12) 1-131 (36) 5.OE -1 31 2.3E 0 8.OE -1 (0) -1.1 - 0.8)E 1 ( -2.0 - 7.1)E 0 -1.1 - 1.3)E 1 (0/ 24) (0/ 12) (O0 12)
Cs-134 (36) 15 2.8E -1 21 6.7E -1 6.7E -1 (0) -2.8 - 3.8)E 0 ( -3.0 - 3.7)E 0 -3.0 - 3.7)E 0 (0/ 24) (O0 12) (Of 12)
Cs-1 37 (36) 18 -3.7E -1 11 1.3E -1 -2.5E -2 (0) -3.6 - 2.8)E 0 ( -1.8 - 2.8)E 0 -2.9 - 2.8)E 0 (O0 24) (0/ 12) (Of 12)
Ba-140 (36) 6.5E -1 31 1.3E 0 6.6E -1 (0) -1.3 - 0.8)E 1 ( -2.5 - 5.6)E 0 -4.7 - 8.5)E 0 (O/ 24) (Of 12) (O/ 12) 30
'The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
"Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 4.2.
- -- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) Is shown In parentheses.
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Storm Drain Water (WW) UNITS: PCikq Indicator Stations Station With Highest Mean Control Stations Radionuclides' Mean Station Mean Mean (No. Analyses) Required Range Range Range Non-Routine" LLD No. Detected.. No. Detected No. Detected-GR-B (18) 4 9.6E 0 1.3E 1 NO DATA (0) ( 4.0 - 16.3)E 0 ( 8.9 - 15.3)E 0 (18/ 18) (8/ 8)
H-3 (18) 2000 4.9E 1 1.3E 2 NO DATA (0) ( -6.6 - 16.3)E 2 -6.6 - 16.3)E 2 (1/ 18) (1/ 8)
Mn-54 (18) 15 -9.1E -1 -5.OE -1 NO DATA (0) ( -5.6 - 3.7)E 0 -2.9 - 3.7)E 0 (0/ 18) (0/ 10)
Co-58 (18) 15 -6.7E -2 -6.OE -2 NO DATA (0) ( -4.9 - 2.4)E 0 -4.9 - 2.3)E 0 (0/ 18) (0/ 10)
Fe-59 (18) 2.8E -2 1.8E -1 NO DATA (0) -5.6 - 7.2)E 0 -4.2 - 6.5)E 0 (0/ 18) (0/ 8)
Co-60 (1 8) 15 2.3E -1 8.2E -1 NO DATA (0) ( -2.7 - 6.1)E 0 -1.4 - 6.1)E 0 (0/ 18) (0/ 10)
Zn-65 (18) 30 -2.4E 0 -1.3E 0 NO DATA (0) ( -8.5 - 7.9)E 0 -7.2 - 7.9)E 0 (0/ 18) (0/ 10)
Zr-95 (18) 15 4.2E -1 5.OE -1 NO DATA (0) ( -3.6 - 3.4)E 0 -3.6 - 3.4)E 0 (0/ 18) (0/ 10) 1-131 (18) 7.9E -1 2.4E 0 NO DATA (0) ( -9.2 - 8.0)E 0 -4.9 - 8.0)E 0 (0/ 18) (0/ 10)
Cs-134 (18) 15 -5.4E -1 -5.OE -1 NO DATA (0) -3.3 - 2.9)E 0 -3.3 - 2.9)E 0 (0/ 18) (0/ 10)
Cs-137 (18) 18 1.3E -1 5.9E -1 NO DATA (0) -3.1 - 3.2)E 0 -2.5 - 3.2)E 0 (0/ 18) (0/ 8)
Ba-140 (18) 7.5E -1 7.6E -1 NO DATA (0) -7.2 - 6.9)E 0 -7.2 - 6.9)E 0 (0/ 18) (0/ 8) 31
-The only radionuclides reported In this table are those with LLD requirements, those for which positive radioactivity was detected, or which were considered Important due to past effluent history. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
-'Non-Routine refers to those radionuclides that exceeded the Reporting Levels In ODCM Table 4.2.
- The traction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown In parentheses.
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 3.2 ENVIRONMENTAL TLD DATA
SUMMARY
(JANUARY - DECEMBER 2004)
IR/lir INDICATOR TlDs OUTER RING TlDs FENCEITNF Tl,)s** CONTROL TLT)S MEAN MEAN MEAN MEAN RANGE RANGE RANGE RANGE (NO. MEASUREMENTS)* (NO. MEASUREMENTS)* (NO. MEASUREMENTS)* (NO. MEASUREMENTS)*
6.7 + 0.4 6.6 +/- 0.4 12.9 +/- 0.7 7.4 +/- 0.5 5.0 - 8.2 4.6 - 10.3 5.9 - 34.7 5.9 - 8.4 (52) (36) (36) (8)
OFFSITE STATION WITH HIGHEST MEAN MEAN STA. RANGE NO. (NO. MEASUREMENTS)*
GM-38 8.4 +/- 0.4 6.4 - 10.3 4
- Each measurement is based on quarterly readings from five TLD elements. Measurement units are pR/hr.
- Not part of REMP Program (TLD locations are inside the site boundary). Increased exposure rates are due to fuel placement on the ISFSI which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.
32
Yankee Nuclear Power Station Annual Radiological Environmental Operating Rcport 2004 TABLE 3.3 2004 ENVIRONMENTAL TLD MEASUREMENTS*
(Micro-R per hour)
Annual 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Average Sta.
No. Description Expos. *SD.. Expos. +/-SD-.. Expos. +/-SD-.. ExDpos. SD--- Expos.
GM01 YNPS Visitors Center 5.00 +/-0.23 6.99 +/-0.77 6.36 +/-0.29 6.26 +/-0.36 6.2 GM02 Observation Stand 6.02 +/-0.27 7.34 +/-0.85 7.04 +/-0.38 6.83 +/-0.42 6.8 GM03 Rowe School 4.99 +/-0.31 6.35 +/-0.70 5.66 +/-0.31 5.80 +/-0.33 5.7 GM04 Harriman Station. 5.51 +/-0.35 6.58 +/-0.88 6.48 +/-0.27 6.52 +/-0.26 6.3 GM05 Monroe Bridge 6.53 +/-0.29 7.55 +/-0.81 7.28 +/-0.34 7.65 +/-0.24 7.3 GM06 Readsboro Rd. Barrier 5.77 +/-0.33 7.69 +/-0.59 7.81 +/-0.30 7.64 +/-0.40 7.2 GM07 Whitingharn Line 6.24 +/-0.43 7.76 +/-1.00 7.86 +/-0.28 7.81 +/-0.26 7.4 GM08 Monroe Hill Barrier 5.55 +/-0.30 6.33 +/-0.67 6.35 +/-0.31 6.54 +/-0.43 6.2 GM09 Dunbar Brook 5.63 +/-0.29 7.07 +/-0.61 7.40 +/-0.33 7.62 +/-0.26 6.9 GM10 Cross Road 6.06 +/-0.31 6.20 +/-0.88 7.04 +/-0.23 6.78 +/-0.30 6.5 GM1 1 Adams High Line 5.37 +/-0.30 6.36 +/-0.55 7.04 +/-0.37 6.50 +/-0.34 6.3 GM12 Readsboro, VT 7.05 +/-0.32 7.65 +/-0.88 7.80 +/-0.29 8.20 +/-0.36 7.7 GM13 Indust. Area Fence" 7.52 +/-0.30 10.03 +/-0.63 9.88 +/-0.36 10.17 +/-0.49 9.4 GM14 Indust. Area Fence" 6.31 +/-0.35 7.56 +/-0.63 7.61 +/-0.43 7.44 +/-0.39 7.2 GM15 Indust. Area Fence" 6.51 +/-0.30 7.30 *0.58 7.88 +/-0.37 8.25 +/-0.34 7.5 GM16 Indust. Area Fence" 5.93 +/-0.36 6.12 +/-0.77 7.15 +/-0.47 6.96 +/-0.30 6.5 GM17 Indust. Area Fence" 6.77 +/-0.34 7.66 +/-0.68 8.59 +/-0.56 8.72 +/-0.41 7.9 GM18 Indust. Area Fence" 16.32 +/-0.94 25.62 +/-1.25 25.83 +/-0.88 27.33 +/-1.26 23.8 GM19 Indust. Area Fence" 33.86 +/-1.54 32.03 +/-1.97 32.44 +/-1.23 34.68. +/-1.22 33.3 GM20 Indust. Area Fence" 12.24 +/-0.56 13.37 +/-0.79 14.18 +/-0.57 13.84 +/-0.55 13.4 GM21 Indust. Area Fence" 6.44 +/-0.35 7.28 +/-0.61 7.85 +/-0.32 8.44 +/-0.51 7.5 GM22 Heartwellville, VT 5.88 +/-0.38 7.41 *0.69 7.61 *0.31 7.74 +/-0.34 7.2 GM23 Williamstown.Subst. 7.29 +/-0.32 7.10 +/-0.65 7.91 +/-0.43 8.41 *0.78 7.7 GM25 Whitingham 4.56 +/-0.23 4.91 +/-0.52 6.05 +/-0.41 5.81 +/-0.22 5.3 GM27 No.9 Road 4.83 +/-0.24 5.13 +/-0.61 6.54 +/-0.27 6.25 +/-0.23 5.7 GM29 Route 8A 4.91 *0.23 4.68 +/-0.54 5.83 +/-0.32 5.76 +/-0.26 5.3 GM31 Legate Road 5.50 +/-0.32 5.47 *0.52 6.45 +/-0.28 6.42 +/-0.22 6.0 GM32 Rowe Road 5.80 +/-0.35 7.93 +/-0.63 6.98 *0.33 7.00 +/-0.46 6.9 GM33 Zoar Road 6.26 +/-0.29 7.83 +/-0.81 7.35 +/-0.28 7.82 +/-0.30 7.3 GM35 Whitcomb Subst. 6.61 +/-0.82 7.84 +/-0.62 7.76 +/-0.32 7.88 +/-0.27 7.5 GM36 Tilda Road 5.93 +/-0.52 7.29 +/-0.87 7.53 +/-0.36 7.01 +/-0.25 6.9 GM38 West Hill Rd 6.43 +/-0.36 8.70 +/-0.67 8.25 +/-0.35 10.27 +/-0.33 8.4 GM40 Readsboro Rd 5.24 +0.27 7.14 +/-0.64 7.47 +/-0.42 7.49 +/-0.38 6.8
- Each measurement' is based on quarterly readings from five TLD elements.
- - Not part of the REMP Program. Increased exposure rates inside the site boundary are due to fuel placement on the ISFSI which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.
- -- SD: Standard Deviation 33
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 3.4 2004 ISFSI TLD MEASUREMENTS*
(Micro-R per hour)
Annual 1st Quarter 2nd Quarter 3rd Quarter 4 th Quarter Average Sta.
No. Description Expos. +/-SD-.. Expos. +/-SD^.. Expos. +/-SD- Expos. tSD-.. Exnos.
IF-1 ISFSI Security Fence" 360.27 +/-29.29 371.24 +/-23.15 349.51 +/-34.19 329.34 +/-26.38 352.6 IF-2 Observation Stand" 5.39 +/-0.21 5.91 +/-1.00 6.58 +/-0.35 6.56 +/-0.28 6.1 IF-3 ISFSI Security Fence" 460.94 +/-12.88 428.8 +/-17.09 423.26 t1 4.88 428.82 +/-20.45 435.5 IF-4 ISFSI Security Fence" 135.2 t5.74 136.54 +/-8.37 131.8 t1 0.42 134.5 IF-5 ISFSI Security Fence" 261.41 t7.83 268.44 +/-14.68 247.15 +/-8.63 271.5 +/-1 1.90 262.1 IF-6 ISFSI Security Fence" 350.18 +/-8.08 351.16 +/-28.76 321.14 +/-1 9.13 339.94 +/-12.23 340.6 IF-7 ISFSI Security Fence" 190.21 +/-21.29 187.44 t9.15 176.9 +/-6.43 181.92 +/-5.09 184.1 IF-8 ISFSI Security Fence" 28.6 t2.03 29.31 +/-1.58 27.93 +/-1.97 30.08 +/-1.68 29.0 IF-9 Restricted Area Fence" 48.1 +/-1.51 48.31 +/-2.85 47.26 +/-2.17 51.63 +/-1.87 48.8 IF-10 Restricted Area Fence" 22.1 +/-1.47 23.58 +/-1.45 22.02 +/-1.44 23.69 +/-0.68 22.8 IF-11 Restricted Area 9.18 +/-0.42 11.75 +/-0.84 11.21 +/-0.49 12.08 +/-1.13 11.1 Fence" IF-12 Restricted Area Fence" 6.3 +/-0.36 7.84 +/-0.89 7.64 +/-O.31 7.6 *0.37 7.3 IF-18 YNPS CW Intake" (a) 6.09 +/-0.23 6.80 +/-0.82 7.59 +/-0.42 8.4 +/-0.52 7.2 IF-19 ISFSI Security Fence Admin. Building" 7.62 t0.23 9.52 +/-0.78 9.13 +/-0.35 9.16 +/-0.43 8.9 IF-20 ISFSI Security Fence Gatehouse" 6.96 +/-0.23 7.38 +/-2.74 7.74 +/-0.29 8.05 +/-0.31 7.5 IF-40 Readsboro Road" 5.27 +/-0.23 7.09 +/-0.67 7.23 +/-0.30 6.81 +/-0.44 6.6
- Each 'measurement" is based on quarterly readings from five TLD elements.
- Not part of the REMP Program. Increased exposure rates inside the site boundary are due to fuel placement on the ISFSI which began in the 2nd half of 2002. Fuel and GTCC placement was completed in June 2003.
- -- SD: Standard Deviation.
(a) Note: In 2004. IF-18 was relocated about 60 feet closer to the storage pad. This was necessary when the Screen Well House, upon which the TLD had been mounted, was demolished as part of site decommissioning activities.
34
Yank~ee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS 4.1 SAMPLING PROGRAM DEVIATIONS ODCM Control 4.1 allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment." There were no program deviations noted in the REMP during 2004. Routine non-REMP sample collection encountered only two departures from the planned sample collection schedule:
- On January 31 2004 the West and East Storm Drain samples were not collected because water was not available due to ice and snow blockage. (WW-52, WW-51, respectively).
- The TLD station IF-4 provided no data for the first quarter of 2004.
4.2 COMPARISON OF ACHIEVED LLDS WITH REQUIREMENTS Table 4.3 of the ODCM (Table 2.4 in this report) gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. On occasion, an LLD is not achieved due to situations such as a low sample volume caused by sampling equipment malfunction. In such a case, Control 7.1 of the ODCM requires a discussion of the situation in the Annual Radiological Environmental Operating Report. At the E-LAB, the target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times better than that required by the YNPS ODCM.
For each analysis having an LLD requirement in ODCM Table 4.3, the a posteriorior after the fact LLD (or minimum detectable concentration - MDC) calculated for that analysis was compared with the required a prioriLLD. Of the more than 572 analyses performed with a specified LLD requirement in 2004, no sample failed to meet the requirements of Table 4.3 of the ODCM. One analysis of a water sample from a storm drain, which is not part of the REMP program sampling, failed to meet the specified detection level. This condition is noted in the summary table contained in Appendix C and is as follows:
- For a storm water sample analysis from station WW-5 1, the typical LLD for Gross Beta for a sample collected 3/29/04 was not reached. This was consistent with ODCM Table 4.3 footnote c which indicates that where measured concentrations, minus the five-sigma counting statistics, is found to exceed the specified LLD, the sample does not have to be analyzed to meet the specified LLD. In this case, the measured concentration was greater than eight times the standard deviation.
4.3 RESULTS COMPARED AGAINST REPORTING LEVELS ODCM Control 4.I.a. requires the written notification to the NRC within 30 days whenever a Reporting Level in ODCM Table 4.2 is exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix 1. It should be noted that environmental concentrations are averaged over calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant effluents. During 2004, no Reporting Levels were exceeded.
35
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 4.4 DATA ANALYSIS BY MEDIA TYPE The 2004 REMP data for each media type are discussed below. These are arranged in the same order as in Table 3. 1, and are further categorized by pathway. Graphical plots of monitoring data are also shown in Figures 4-1 to 4-1 1.
With respect to data plots, all values are plotted, whether they are "detectable" or "non-detectable."
4.4.1 Air Particulates (See Figures 4.1 &4.2)
Biweekly air particulate filters are obtained from each of the six REMP sampling sites. Five are indicators stations, AP-11, -12, -13, -14, and -31 in the plant vicinity, and one is a control station, AP-3 1in Williamstown, MA. Filters are analyzed for gross-beta radioactivity. At the end of each quarter, the individual filters collected during the quarter from each sampling site were composited for a gamma analysis. The results of the biweekly air-particulate sampling program are shown in Table 3.1 and Figures 4-1 through 4-2.
Supplemental environmental air particulate monitoring to assess building demolition activities was initiated to validate effluent release (demolition airborne dust) monitoring. Results of those analyses are included in summary data in Appendix C of this report, although they are not part of the REMP sampling.
Figure 4.1 Gross-Beta Measurements on Air Particulate Filters (Quarterly Averages) 0.05 0.05
- Control 4 Indicators 0.04 - 0.04 S 0.03 - 0.03 E
'0.02 -20.02 0.01 - 0.01 0 0 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 36 C07
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 As shown in Figure 4-1, there has been no significant difference between the concentration at the indicator (near-plant) stations and the control (distant from plant) stations.
Figure 4-2 shows the biweekly gross beta concentration at each air particulate sampling location required by the ODCM along with the control air particulate sampling location at AP-21 (Williamstown, MA). It can be seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year. This is due principally to seasonal variations and the related effects on naturally occurring terrestrial radionuclide emissions. 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 YNPS operations. Table 3.1 shows that the mean concentration from indicator stations, on the average, are similar to those from control locations, further supporting this conclusion.
Figure 4-2 Yankee Rowe Bi-Weekly Air Particulate Gross Beta Analysis Results 0.05 0.045
,¢ 0.04 i 0.035 a
.° 0.03 E
t 0.025 I
0C Q 0.02 E 0.015 Q 0.01 0.005 o _-
Jan-03 Jan-03 Mar-03 Apr-03 May-03 May-03 Jun-03 Jul-03 Aug-03 Sep-03 Oct-03 Nov-03 Dec-03 Reference Date of Sample During 2004 supplemental environmental air particulate monitoring in the vicinity of on-site building demolition activities was initiated to validate effluent release (demolition airborne dust) monitoring. This consists of four non-REMP sample locations, DAP- 1, 2, 3 and 4. No plant-related radioactivity was detected in samples from these location in 2004. Results are provided in Appendix C.
4.4.2 River Water (See Figure 4-3)
Aliquots of river water were automatically collected every two hours from the Deerfield River downstream from the plant (WR-I I at Bear Swamp Lower Reservoir). These composited samples were collected monthly and sent to the E-LAB for gamma, tritium, and gross beta analyses. Monthly grab samples were also collected at the Harriman Reservoir control location and at Sherman Pond near the discharge area (WR-21 and -31, respectively).
Table 3.1 shows that gross-beta measurements were positive in five of the twenty-four samples collected, an extent that 37
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 might be expected, due to naturally-occurring radionuclides in the water. The historical concentrations at the indicator and control locations have not been significantly different, as shown in Figure 4-3, except during the last half of 1992, 1998-1999, and in 2002 when the levels at WR-11 were slightly elevated relative to the control, but no tritium or other plant related gamma emitter was detected in either sample set in 2002. This was attributed to naturally-occurring radioactivity as discussed in the earlier Annual Radiological Environmental Operating Reports. For 2004, the indicator station gross beta results averaged above the control station values by a small amount, with both the indicator and control station averages generally in close agreement, suggesting no significant difference between the control location and indicator samples in 2004. In addition, no tritium or gamma spectroscopy analyses found detectable levels of plant-related radioactivity in any of the 2004 river water samples.
Figure 4-3 Grss-Beta Measurements of River Water (Semi-Annual Averages) 4 3
2 0
- § _8
- _ * §* § 8 4.4.3 Ground Water (See Figure 4-4)
Monthly ground water samples were collected from two on-site locations during 2004, the plant potable water well and Sherman Spring, WG- II and -12, respectively (only quarterly samples are required by ODCM Table 4.1). Table 3.1 shows that gross-beta measurements were positive in most of the samples, an outcome typical for ground water samples. This is due to naturally-occurring radionuclides in the water.
Tritium was detected in three of twelve samples from WG- 12 (Sherman Spring) during August, September and October 2004. Concentrations are just above MDC levels and generally were within the range of values for the past 8 years during which a steadily decreasing concentration of H-3 has been detected (Figure 4-4). The source of H-3 in ground water as seen at Sherman Spring has long been associated with leaks which occurred in the early 1960's from 38
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 the plant's Ion Exchange Pit Over the last 40 years the concentration of H-3 has decreased to levels near the detection sensitivity of the lab analysis for that nuclide. Water from Sherman Spring flows into the Deerfield River. Neither the Deerfield River nor Sherman Spring is used for drinking water. No gamma-emitting radionuclides or plant-related radioactivity were detected in any of the ground water samples.
Fieure 4-4 Tritium In Ground Water Station WG-12, Sherman Spring 1700 1200i E 700-200 V W
-300
- Note that these samples are not required by the REMP program.
-800 1996 1997 1998 1999 2000 2001 2002 2003 2004 4.4.4 Storm Drain Water Monthly grab samples were collected from the East and West Storm Drains (WW-51 and 52, respectively) when available during 2004. Each sample was analyzed for gross-beta and gamma-emitting radionuclides and H-3. Gross-beta measurements were positive in most of the samples taken, as expected. The levels are consistent with those from previous years. No plant-related gamma-emitting radionuclides were detected in any of the samples. H-3 was detected in one sample during June when permitted liquid releases were made from the site. Some of those releases contained H-3, with all discharges for that nuclide at levels meeting allowable concentrations per the ODCM. The water from site storm drains discharges to the Deerfield River, which is not used for drinking water.
4.4.5 Sediment (See Figures 4-5, 4-6, & 4-7)
Semiannual sediment core samples were collected from three locations during 2004. Indicator stations SE-91 and SE-11 are located in Sherman Pond and downstream about 24 river miles at No. 4 Dam in Charlemont, MA, respectively.
Control station SE-21 is located upstream (control) at Harriman Reservoir. Each sample is segmented by depth (0-5, 5-10, 10- 15 cm) and analyzed for gamma-emitting radionuclides. As would be expected, naturally-occurring K-40 and Th-232 were detected in most of the samples. In addition to those naturally-occurring radionuclides, Cs-137 was detected in 15 of 18 segments from SE-91 and SE-I I locations and in 4 of 6 segments from the SE-21 location. These results are consistent with what has been measured in previous years. Presence of Cs-137 is attributed to nuclear weapons testing fallout at Station SE-I I and SE-21 as the far downstream location and the upstream control location indicate similar levels of Cs-137. Samples from Station SE-91, near the plant have in general about 7 times higher Cs-39
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 137 concentration, attributable in part to plant licensed discharges. In past year's, sediment analysis at SE-91 have also shown positive indication of Co-60 which can be related to plant discharges, though no current measurements for Co-60 give positive indication of its presence, contrary to its expectation as it has been identified in measurements taken of in-plant samples. However, it should be noted that Station SE-91 is taken from bottom of the Sherman Pond and is high in organic material which has been found to concentrate fallout Cs-137 more than soils/sediments low in organic material. Stations SE- lI and SE-21 are taken from the shoreline and have not typically been seen to have the same organic material content as in SE-91. Results for station SE-l 1 are relatively low for Cs-137, but consistent with low values measured in the past several years, as shown in Figure 4.-5.
FIGURE 4-5 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-I1 400.00 350.00 300.00 l 250.00 -n
~'200.00
~o150.00 C.100.00 50.00 0.00 I I
-50.00 I
-100.00 Month/Year 0 0-5 cm
- 5-1Ocm 010-15 cm Results for sediment samples from the upstream (SE-21) control location are slightly elevated (Figure 4-6), but are bounded by levels previously reported at that location for recent years. At both the indicator and the control location, the character of the sediment is highly dependent on the specific location sampled, and it also can depend on the water level in Harriman Reservoir or on the Deerfield River shoreline at the time of sampling. The diverse character of the sediment at either location, and the fact that Cs-137 tends to bind more to finer-grained sediment containing organic matter than to sandy and rocky sediment, leads to a wide range of Cs-137 concentrations, as shown in Figures 4-5 through 4-7.
40 clO
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 FIGURE 4-6 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-21 1100 900 700 500 300 100
-100 05/97 10/97 05/98 10/98 05/99 10/99 05/00 10/00 05/01 10/01 05/02 10/02 04/03 10/03 04/04 10/04 Month/Year a 0-5 cm
- 5-10 cm 1110-15 cm Table 3.1 and Figure 4-7 show the levels of Cs-137 at station SE-91. These samples were collected from a deep water Iwhether location opposite the plant former discharge into Sherman Pond. It is believed that the higher Cs-137 levels at SE-91, due to fallout or plant effluents, are also related to the character of the sediment (a rich organic benthic layer) at the bottom of Sherman Pond at this location as described earlier.
I .
3 41 CA
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 FIGURE 4-7 CESIUM-137 IN RIVER SEDIMENT STATION SE-91 4000 3500 3000 2500 no 2000 Q
1500 1000 500 0
05/97 10/97 05/98 10/98 05/99 10/99 05/00 10/00 05/01 10/01 05/02 10/02 04/03 10/03 04/04 10/04 Month/Year I0-5cm E5-lOcml 0~l10-15 cml 42
Yankee Nuclear P ower Station Annual Radiological Environmcntal Operating Report 2004 4.4.6 Fish (See Figure 4-8)
Semiannual samples of fish were collected from two locations during 2004, F-I -I , an indicator station in Sherman Pond, and FH-2 1, a control station in Harriman Reservoir. The edible portions of each of these samples were analyzed for gamma-emitting radionuclides. As expected in aquatic animals, naturally-occurring K40 was detected in all samples from both locations. No plant-related gamma emitting radionuclides were detected in 2004 fish samples. The average 2004 Cs-137 concentrations shown in Figure 4-8 arc not considered detectable or "positive" measurements, but include the results of counting statistics on sample measurements, even when the analysis counts did not exceed the criteria for a
,positive" determination. The wide variation in relative Cs-137 activity illustrated in Figure 4-8 over past years is suspected to bc due to the different species of fish and their specific eating habits. Fish that are bottom feeders tend to accumulate more of the Cs- 137 activity from aquatic sediment. However, the makeup of any individual catch (fish sample) could be dominated by a single species available at the time. No attempt is made to differentiate sample analysis by fish species, such as those who primarily feed on the bottom and arc closer to any radioactivity deposited in bottom sediments, from those species that feed higher in the water column and away from one potential source of Cs-137 in the environment.
43
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 FIGURE 4-8 CESIUM-137 IN FISH ANNUAL AVERAGE CONCENTRATIONS 60 50 40 1 30 20 10 0
1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year l*FH- 11 Sherman Pond a FH-21 Harriman Reservoir (control) 4.4.7 Food Three food samples were collected from indicator stations TF-1 1 and TF-1 3 in Monroe Bridge and Monroe, MA, respectively, and from a control station, TF-21 in Williamstown, MA during 2004. Samples were analyzed for gamma-emitting radionuclides. K-40 (naturally occurring) was detected in all three samples. No plant-related gamma emitting radionuclides were detected in 2004 food samples.
4.4.8 Maple Syrup Processed maple syrup samples were collected from an indicator and control location at the end of March 2004. The indicator station is MS-33 in Rowe, MA, and the control station, MS-45, is in the town of Florida, MA. These samples represent concentrated media, relative to the original tree sap, produced by boiling (see Section 2.5.8). Naturally-occurring K-40, and Cs-137 from global nuclear weapons testing fallout, were detected in both samples. The detected 44
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 concentrations of Cs-137 in 2004 samples, at 20 and 14 pCi/kg respectively for MS-33 and MS-45, are consistent with that detected in both indicator and control samples in previous years.
4.4.9 Direct Radiation (See Figures 4-9, 4-10 & 4-1 1)
Direct radiation is continuously measured at 33 locations surrounding YNPS with the use of thermoluminescent dosimeters (TLDs). These are collected every calendar quarter for readout at the E-LAB.
As shown in Figure 4-9, there is a distinct annual cycle at both indicator and control locations. The lowest point of the cycle occurs 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 radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another.
Figure 4-9 Exposure Rate at Indicator, Outer Ring and Control TLDs 15 15
-x- Indicators
--- Control A Outer Ring 10 10 I- C- )"
5 5 0 0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 45 M
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Based on the data in Table 3.2 and 3.3 and illustrated in Figure 4.9, it is evident that the mean exposure rates for the Indicator, Outer Ring, and Control categories were not significantly different in 2004. This indicates that there was no significant overall increase in direct radiation exposure rates in the plant vicinity beyond the industrial area of the plant.
As shown in Figures 4-10 and 4-11, the levels at offsite locations in 2004 are consistent with or bounded by levels in previous years.
Figure 4-10 Exposure Rate at Indicator TLDs 15 -15 GM-01 YAEC Visitor's Center
-U- GM-02 Observation Stand A- GM-03 Rowe School X GM-04 Harriman Station X GM-05 Monroe Bridge GM-06 Readsboro Road Barrer
+ GM-07 Whitingham Line
. GM-08 Monroe Hill Barrier GM-09 Dunbar Brook GM-10 Cross Road GM-I I Adams High Lane GM-12 Readsboro, VT 10 GM-40 Readsboro Road 10
- 4 A I A
0 - 0 1996 1997 1998 1999 2000 2001 2002 2003 2004 46
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Results from the Fenceline TLDs are shown in Figure 4-11 and summarized in Tables 3.2 and 3.3. These TLDs are located on the fence surrounding the Radiation Control Area within the YNPS property bounds, and are influenced by the ISFSI. Specifically, the elevated exposure rates at TLD locations GM- 18, -19, and -20 since 2002 are due to fuel and GTCC transfer activities to the ISFSI, completed during 2003, and storage of spent fuel at the ISFSI and other decommissioning activities that move and temporarily place potentially radioactive materials at various locations across the site.
Figure 4-11 Exposure Rate at Fenceline TLDs 40 - 40
-O-GM-13 Restricted Area Fence -- GM-14 Restricted Area Fence 35 - GM-15 Restricted Area Fence X GM-16 Restricted Area Fence X GM-17 Restricted Area Fence -- GM-1 8 Restricted Area Fence 30 + GM-19 Restricted Area Fence -GM-20 Restricted Area Fence
-- GM-21 Restricted Area Fence 25 20 20 15 10 5
1996 1997 1998 1999 2000 2001 2002 2003 2004 47
Yankee Nuclear Power Station Annual Radiological Environmental Operating Rcport 2004 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS The purpose of this section is to evaluate off-site dose consequences (dose equivalent commitments) associated with detectable plant related radioactivity in environmental media. The method utilizes Regulatory Guide 1.109 (Reference 2)
ODCM models and actual measurements of the concentrations of radioactivity in various environmental media (e.g., air, sediment, ground water) to compute the dose consequences resulting from the inhalation or ingestion of such material.
These evaluations can be used to provide assurance that the station's radioactive liquid and airborne effluent dose models are unlikely to underestimate actual impacts.
The standards for the maximum dose to an individual of the general public taken from 40 CFR 190, is 25 mRcm to the whole body, 75 mRcm to the thyroid, and 25 mRem to any other organ. These standards arc a fraction of the USA background radiation of 300 mRcm per year given in NCRP 94 (Reference 3).
During 2004 there were no instances of plant-rclated radioactivity observed in environmental media with the exception of low H-3 in three Sherman Spring samples and in one on-site storm water sample, and Cs- 137 in sediment and maple syrup.
Detected levels of radioactivity attributable to natural processes or fallout include gross beta and Bc-7 in air particulate samples, and gross beta in water samples, K-40 and Cs-137 in fish, K40 and Cs-137 and Ac-Th-228 in river sediment, and K-40 and Cs-137 in maple syrup.
For past years, the potential dose from detected level of Cs-137 in fish samples has been evaluated on a conservative basis.
There was positive measurement of Cs-137 in 2004.
In 2004 the potential dose for the postulated ingestion of I kg of maple syrup at the average measured concentration of 17 pCi/kg of Cs-137 would be approximately 0.0056 mremlyr (Child, Bone). Note that the source for Cs-137 is credited to wcapons-testing fallout based on location and low level of plant discharge.
Since the REMP for 2004 did not indicate plant related radioactivity in off-site media associated directly with human inhalation or ingestion, there is no indication that the plant's effluent dose models underestimate the dose impact to members of the public.
48
6.0 REFERENCES
- 1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2. Regulatory Guide 1.109, Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appcndix I, Rev. 1, October, 1977.
- 3. Exposure of uihe Populationin the United States and CanadafromNaturalBackgroundRadiation.NCRP Report No.
- 94. National Council on Radiation Protection and Measurements, Bcthcsda, Maryland, 1994.
49
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 APPENDIX A - LAND USE CENSUS FOR 2004 A-l
APPENDIX A - LAND USE CENSUS FOR 2004 A Land Use Census is conducted annually between the dates of June I and October I to identify the locations of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles of the plant.
Immediately following the collection of field data, in compliance with ODCM Control 4.2, 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 conservative Method I dose calculations found in the ODCM (i.e. the dose calculations done in compliance with ODCM Surveillance Requirement 3.4). If a Census location has a 20% greater potential dose than that of the Critical Receptor, this fact must be announced in the Semiannual Effluent Release Report for that period. A reevaluation of which location to use as a Critical Receptor would also be done at that time. For the 2004 Census, no such location was identified.
Pursuant to ODCM Control 4.2, a dosimetric analysis is then performed, using site specific meteorological data, to determine which food product census locations would provide the optimal sampling locations. If any location has a 20% greater potential dose commitment than at a currently-sampled location, the new location is added to the routine environmental sampling program in replacement of the location with the lowest calculated dose (which is later eliminated from the program). For the 2004 Census, no such garden location was identified, and consequently no changes were mandated for the food product sampling program. Also, there were no milk animal locations that could provide milk samples for the REMP identified in the 2004 census.
The Land Use Census was carried out and completed between the dates of June I and October 1, as required. The results of the 2004 Land Use Census are included in that report in compliance with ODCM Surveillance Requirement 4.2. The locations identified during the Census may be found in Table A.l.
A-2
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE A.1 2004 LAND USE CENSUS LOCATIONS SECTOR NEAREST NEAREST NEAREST MILK ANIMAL RESIDENCE GARDEN Km (Mi)
Km (Mi) Km (Mi)
N 5.2 (3.2) 6.0(3.7)
NNE 4.3 (2.7) 4.8 (3.0)
NE 3.4 (2.1) 3.5 (2.2)
ENE 3.7 (2.3) 5.8 (3.6)
E 2.8 (1.8) 3.4 (2.3) l ESE 3.4 (2.1) 3.4 (2.1)
SE 2.0(1.3) 3.3 (2.1)
SSE 1.9 (1.2) 1.9(1.2)
S 2.1 (1.3) 2.8 (1.8) 3.2 (2.0)**
SSW * *
- SW 1.3 (0.8) 7.2 (4.5)
- WSW 1.3 (0.8) 1.9 (1.2)
- W 2.0(1.3) 2.9 (1.8)
- WNW 2.0(1.3) 2.0 (1.3)
NW 2.4 (1.5) 2.8 (2.0)
- NNW 2.9 (1.8) 3.7 (2.3)
- No location was identified within 5 miles of the plant.
- Few goats only. Insufficient availability for routine sampling.
A-3
APPENDIX B - QUALITY ASSURANCE PROGRAM
SUMMARY
B-I
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 APPENDIX B - QUALITY ASSURANCE PROGRAM SUMMIARY The quality assurance program at the AREVA Framatome ANP Environmental Laboratory (FANPEL) 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 FANPEL 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 a staff training program. Monitoring programs include the Intralaboratory Quality Control Program administered 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.
This summary reports all intralaboratory and third party results received by FANPEL on or before December 31, 2004.
Intralaboratory Quality Control Program The FANPEL QA Officer administers an extensive intralaboratory quality control program in which process check samples are submitted for analysis. These samples are "spiked" with a known amount of radioactive material and arc routinely submitted in triplicate to evaluate the bias and precision of a measurement process. Table B. 1 provides the summary of the process check results for January to December 2004. Of the 665 analyses, 99.4% passed the bias criteria and 99.1% of the 215 results evaluated for precision were acceptable. The FANPEL internal acceptance criteria are summarized at the end of Table B. 1.
Third Party Cross Check Program The FANPEL participates in a third party cross check program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical Specification/ODCM. The FANPEL Analytics program was originally used to augment the EPA Intercomparison Program that it now replaces. The current program is designed to be comparable to the pre-1996 EPA PE Program in terms of the number of samples, matrices and nuclides. The results for the 4th quarter 2003 through the 3Y quarter 2004 are summarized in Table B.2. Each sample is normally analyzed in triplicate and the results are evaluated against the internal acceptance criteria described in the FANPEL Manual 100-Laboratory Quality Assurance Plan. This acceptance protocol is used for all interlaboratory programs with no prc-set acceptance criteria.
When results fall outside of the acceptance criteria, an investigation is initiated to determine the cause of the problem and if appropriate, corrective measures arc taken. The FANPEL internal acceptance criteria are summarized at the end of Table B.l.
B-2
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Blind Duplicate Program.
Under the Blind Duplicate Quality Assurance Program, samples are split from homogeneous environmental media by the client and sent to the FANPEL for analysis. They are "blind" in that the identification of the matching sample is not identified to the Laboratory.
Participating clients submitted a total of 23 paired samples in 2004. The measurements evaluated include twenty-six gamma emitting radionuclides, H-3, Sr-89/90, and gross beta. All measurements are evaluated, whether the results are statistically positive or not, and whether the net concentration is positive or negative.
The samples submitted as part of this program are listed in Table B.3. For the 2004 program, 99.8% (486/487) of the measurements met the FANPEL internal acceptance criteria.
Environmental TLD Quality Assurance Program Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the FANPEL 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 performance tests were conducted in 2004 by FANPEL and the third party tester. These tests were made on 15 separate sets of 6 dosimeters. All of the 15 TLD test sets passed the mean bias criteria of +/-20.1%. Of the ninety individual measurements, 100% of the dosimeter evaluations met the FANPEL Internal Acceptance Criteria for bias
(+20.1%) and precision (+/-12.8%). Third Party QC results are summarized below.
B-3
Yankcc Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Percentage of Individual Analyses that passed FANPEL Internal Criteria Summary of Third Party Testing Dosimeter Type Exposure Period ANSI Category % (Bias +/- SD)
Panasonic Environmental Q4/2003 II, high energy 4.2 +/- 0.8
.. Q1/2004 II, high energy -0.3 +/- 1.0
.. Q2/2004 II, high energy 2.8 + 1.4 Q3/2004 II, high energy 1.6 +/-0.3
- 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 N13.29-1995 (Draft) Category 11, High energy photons (Cs-137 or Co-60).
B4
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE B.1 FANPEL RESULTS IN THE INTRALABORATORY PROCESS CONTROL PROGRAM January - December 2004 Media Bias Criteria (1) Precision Criteria (2)
Analysis 1 2 3 4 1 2 3 4 I. Air Charcoal Gamma-Quantitative 6 2 0 0 0 0 0 0 Gamma-Screening 83 31 18 0 0 0 0 0
- 11. Air Filter Beta 243 15 0 0 0 0 0 0 Ill. Milk Gamma 6 0 0 0 9 0 0 0 IV. Water Gross Alpha 13 13 28 0 2 0 28 0 Gross Beta 22 13 24 4 10 8 12 0 Gamma 53 7 0 0 0 2 56 2 lodine-LL 9 3 1 0 9 3 1 0 Sr-90 11 6 14 0 0 0 34 0 Tritium 31 5 4 0 11 6 22 0 Total Number in Range 477 95 89 4 41 19 153 2 Percentage of Total 71.7 14.3 13.4 0.6 19.1 8.8 71.2 0.9 Processed Sum of Analyses 665 215 (1) Percent Bias Criteria by Bias Category (2) Percent Precision Criteria by Precision Category Bias Category = I > 0% and < = 5% Precision Category = I > 0% and < = 5%
BiasCategory =2>5%and<= 10% Precision Category = 2 > 5% and < = 10%
BiasCategory=3> 10%and<= 15%. or Precision Category = 3 > 10% and < = 15%, or within 2 sigma of known within 2 sigma of mean Gross alpha/beta water, Sr 89/90 > 10% and < = 25% Precision Category = 4 Outside Criteria Transuranics > 10% and < = 20%
Bias Category = 4 Outside Criteria B-5
Yankee Nuclear Power Station Annual Radiological Environmcntal Operating Report 2004 TABLE B.2 FANPEL RESULTS IN TIlE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2003 - Quarter 3, 2004 Sample Quarter - Sample . Reported Known Ratio: E-LAB/
Number Year'. Media Nuclide ;.Value Value Analytics Evaluation E3937-162 4th/2003 Water H-3 2307 2290 1.01 Agreement E3938-162 4th/2003 Water Sr-89 99 100 0.99 Agreement Sr-90 11 10 1.10 Agreement E3939-162 4th/2003 Filter Gross Alpha 15 16 0.94 Agreement Gross Beta 50 47 1.06 Agreement E3940-162 4th/2003 Filter Ce-141 110 100 1.10 Agreement Cr-51 171 153 1.12 Agreement Cs-134 75 74 1.01 Agreement Cs-i 37 75 71 1.06 Agreement Co-58 64 61 1.05 Agreement Mn-54 103 95 1.08 Agreement Fe-59 64 56 1.14 Agreement Zn-65 117 108 1.08 Agreement Co-60 82 85 0.96 Agreement E3941-162 4th/2003 Filter Sr-89 103 109 0.94 Agreement Sr-90 11 11 1.00 Agreement 1-131 LL by beta-E3942-162 4th12003 Milk gamma 91 90 1.01 Agreement 1-131 LL by prop.
counter 89 90 0.99 Agreement 1-131 84 90 0.93 Agreement Ce-141 191 202 0.95 Agreement Cr-51 275 280 0.98 Agreement Cs-134 135 135 1.00 Agreement Cs-137 126 129 0.98 Agreement Co-58 107 111 0.96 Agreement Mn-54 173 173 1.00 Agreement Fe-59 106 102 1.04 Agreement Zn-65 203 197 1.03 Agreement Co-60 148 155 0.95 Agreement E4057-162 1st2004 Water Gross Alpha 72.3 74.5 0.97 Agreement Gross Beta 286 301 0.95 Agreement E4058-162 1st12004 Water 1-131 LL 88.7 90.2 0.98 Agreement 1-131 94 90.2 1.04 Agreement Ce-141 87.5 85 1.03 Agreement Cr-51 335 326 1.03 Agreement Cs-i 34 86 89.7 0.96 Agreement Cs-137 186 185 1.00 Agreement Co-58 113 112 1.01 Agreement Mn-54 112 114 0.99 Agreement
- pCi/Litcr (Filters in pCi)
B-6
Yankecc Nuclcar Power Station Annual Radiological Environmental Operating Report 2004 TABLE B.2 (cont'd)
FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2003 - Quarter 3, 2004 Sample Quarterl Sample Reported Known Ratio E-LABI
-Number --. Year, Media: Nuclide . Value Value Analytics., Evaluation E4058-162 1st12004 Water Fe-59 60.8 56.7 1.07 Agreement Zn-65 149.1 143 1.04 Agreement Co-60 151.4 153 0.99 Agreement E4060-162 1st12004 Filter Gross Alpha 48.1 58.9 0.82 Agreement Gross Beta 231 218 1.06 Agreement E4061-162 1st12004 Milk 1-131LL 83.6 77.7 1.08 Agreement 1-131 77.7 77.7 1.00 Agreement Ce-141 92 85.2 1.08 Agreement Cr-51 314 327 0.96 Agreement Cs-134 88.7 90 0.99 Agreement Cs-137 188.6 185 1.02 Agreement Co-58 115 112 1.03 Agreement Mn-54 114.7 114 1.01 Agreement Fe-59 59.7 56.8 1.05 Agreement Zn-65 145.5 143 1.02 Agreement Co-60 154.8 153 1.01 Agreement E4062-162 1st2004 Milk Sr-89 86.2 103 0.84 Agreement Sr-90 12.7 12.1 1.05 Agreement E4059-162 st/2004 Water Sr-89 107.7 123 0.88 Agreement Sr-90 14.85 14.5 1.02 Agreement E4182-162 2nd/2004 Water H-3 11680 11900 0.98 Agreement E4183-162 2nd/2004 Filter Gross Alpha 46.8 48.8 0.96 Agreement Gross Beta 156 160 0.98 Agreement E4184A-162 2nd12004 Filter Ce-141 86 88.3 0.97 Agreement Cr-51 127 128 0.99 Agreement Cs-1 34 54 56.9 0.94 Agreement Cs-1 37 90 87.8 1.03 Agreement Co-58 27 26 1.03 Agreement Mn-54 42 39.7 1.06 Agreement Fe-59 27 25.1 1.09 Agreement Zn-65 62 56 1.11 Agreement Co-60 92 96.8 0.95 Agreement E4185-162 2nd/2004 Filter Sr-89 Sr-90 MAPEP RdF12 May 2004 Filter Sr-90 20.3 22.4 0.91 Agreement E4186-162 2nd/2004 Milk 1-131 55 58.2 0.95 Agreement 1-131 LL 59 58.2 1.01 Agreement Ce-141 165 157 1.06 Agreement Cr-51 241 228 1.06 Agreement
- pCi/Liter (Filters in pCi)
- Problems encountered in filher dissolution, samplc rc-ordered. MAPEP filter used as replacement.
B-7
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE B.2 (cont'd)
FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2003 - Quarter 3, 2004 Sample Ouarter/ Sample - ! Reported Known Ratio E-LAB/
Number Year Media Nucilde Value. Value Analytics Evaluation E4186-162 2nd/2004 Milk Cs-1 34 99 101 0.98 Agreement Cs-137 157 156 1.01 Agreement Co-58 46 46.2 1.00 Agreement Mn-54 73 70.5 1.04 Agreement Fe-59 48 44.5 1.08 Agreement Zn-65 100 99.3 1.01 Agreement Co-60 175 172 1.02 Agreement E4269-162 3rd/2004 Water Gross Alpha 41.3 42.7 0.97 Agreement Gross Beta 214 225 0.95 Agreement E4270-162 3rd/2004 Water 1-131 70.5 70.8 1.00 Agreement 1-131 LL 67.8 70.8 0.96 Agreement Ce-141 258 250 1.03 Agreement Cr-51 230 223 1.03 Agreement Cs-134 93.4 96.4 0.97 Agreement Cs-137 217 215 1.01 Agreement Co-58 93.4 94.6 0.99 Agreement Mn-54 181 181 1.00 Agreement Fe-59 95.2 91.6 1.04 Agreement Zn-65 180 178 1.01 Agreement Co-60 126 125 1.01 Agreement E4271 -162 3rd/2004 Filter Gross Alpha 38.3 36.8 1.04 Agreement Gross Beta 191 194 0.98 Agreement E4272-162 3rd/2004 Milk 1-131 81.1 83.5 0.97 Agreement 1-131 LL 79.4 83.5 0.95 Agreement Ce-141 240 235 1.02 Agreement Cr-51 214 210 1.02 Agreement Cs-1 34 89.5 90.6 0.99 Agreement Cs-1 37 204 202 1.01 Agreement Co-58 90.9 89 1.02 Agreement Mn-54 173 171 1.01 Agreement Fe-59 91.3 86.1 1.06 Agreement Zn-65 169 167 1.01 Agreement Co-60 116 118 0.98 Agreement E4273-162 3rd/2004 Milk Sr-89 99.2 102 0.97 Agreement Sr-90 23.4 24.5 0.96 Agreement E4340-162 3rd/2004 Filter Sr-89 151 152 1.00 Agreement Sr-90 53.5 58.8 0.91 Agreement
- pCi/Liter (Filters in pCi)
Bias and Precision Acceptance Criteria as described above.
B-8
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE B.3
SUMMARY
OF BLIND DUPLICATE SAMPLES January - December 2004 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Ground Water 2 Surface Water 17 Algae 2 Mussels 2 TOTAL 23 B-9
APPENDIX C -
SUMMARY
OF 2004 REMP DATA C-l
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP-DAP L7054-01 3/912004 Acnh-228 4.00E-04 4.30E-03 1.802-02 AP-DAP L7054-01 3/9/2004 Be-7 5.1 OE-02 1.80E-02 5.00E-02 AP-DAP L7054-01 3/912004 Co-58 O.OOE+00 1.90E-03 7.30E-03 AP-DAP L7054-01 3/9/2004 CO-60 -1.60E-03 1.20E-03 6.40E-03 AP-DAP L7054-01 3/9J2004 Cs-134 -4.00E-04 I .00E-03 4.70E-03 AP-DAP L7054-01 3/9/2004 Cs-137 -2.00E-03 1.20E-03 5.70E-03 AP-DAP L7054-01 319/2004 K-40 I .00E-03 1.50E-02 6.20E-02 AP-DAP L7069-01 2/12/2004 AcTh-228 -5.70E-03 3.80E-03 2.00E-02 AP-DAP L7069-01 2/12/2004 Be-7 2.40E-02 1.902-02 6.30E-02 AP-DAP L7069-01 2/12/2004 Co-58 -4.20E-03 2.00E-03 1.002-02 AP-DAP L7069-01 2/12/2004 Co-60 -6.00E-04 1.40E-03 6.60E-03 AP-DAP L7069-01 2/12V2004 Cs-134 9.00E-04 1.802-03 6.90E-03 AP-DAP L7069-01 2/12/2004 Cs-137 -7.00E-04 1.50E-03 6.20E-03 AP-DAP L7069-01 2V12V2004 K-40 -3.00E-02 2.00E-02 9.502-02 AP-DAP L7071-01 2/24/2004 AcM-228 -5.70E-03 3.70E-03 1.802-02 AP-DAP L7071-01 2/24/2004 Be-7 4.20E-02 1.502-02 4.40E-02 AP-DAP L7071-01 2/24/2004 Co-58 0.00E+00 1.202-03 5.20E-03 AP-DAP L707 1-01 2/24/2004 Co-60 -I .00E-03 1.40E-03 6.40E-03 AP-DAP L707 I-01 2/24/2004 Cs- 134 2.90E-03 1.40E-03 4.30E-03 AP-DAP L707 I-01 2/24/2004 Cs-137 1.50E-03 1. 1OE-03 3.50E-03 AP-DAP L7071-01 2/24/2004 K-40 -4.00E-03 1.402-02 6.10E-02 AP-DAP L7054-02 3/912004 Ac'lh-228 I .00E-02 1. 1OE-02 4.00E-02 AP-DAP L7054-02 3/9/2004 Be-7 9.60E-02 3.50E-02 1.002-01 AP-DAP L7054-02 3/9/2004 CO-58 3.002-04 1.80E-03 7.90E-03 AP-DAP L7054-02 3/9/2004 Co-60 1.90E-03 2.70E-03 1.I OE-02 AP-DAP L7054-02 3/912004 Cs-134 -2.30E-03 2.40E-03 1.I OE-02 AP-DAP L7054-02 3/9/2004 Cs-137 4.00E-04 2.80E-03 1.I OE-02 AP-DAP L7054-02 3/9/2004 K-40 -3.00E-03 3.70E-02 1.502-01 AP-DAP L7069-02 2/12/2004 Ac'Fh-228 -1.20E-03 4.20E-03 2.002-02 AP-DAP L7069-02 2/12/2004 Be-7 - 1.40E-02 1.602-02 7.20E-02 AP-DAP L7069-02 2/12/2004 Co-58 -1.60E-03 2.002-03 9.20E-03 AP-DAP L7069-02 2/12/2004 Co-60 1.40E-03 1.602-03 6.002-03 AP-DAP L7069-02 2V12V2004 Cs-134 1.40E-03 1.802-03 6.60E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-2
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCilm3) (pCi/m3) (pCilm3)
AP-DAP L7069-02 2/12/2004 Cs-137 1.20E-03 1.20E-03 4.40E-03 AP-DAP L7069-02 2/12/2004 K-40 -2.50E-02 1.80E-02 9.70E-02 AP-DAP L7071-02 2V24/2004 AcTh-228 2.80E-03 3.70E-03 1.40E-02 AP-DAP L7071-02 2V24/2004 Be-7 2.20E-02 1.50E-02 5.00E-02 AP-DAP L7071-02 2V24/2004 Co-58 -1.56E-03 7.80E-04 5.OOE-03 AP-DAP L7071-02 2V24/2004 Co-60 2.1OE-03 1.30E-03 4.20E-03 AP-DAP L7071-02 2V24/2004 Cs-134 2.OOE-04 1.1 OE-03 4.60E-03 AP-DAP L7071-02 2V24/2004 Cs-137 -1.40E-03 1.40E-03 5.90E-03 AP-DAP L7071-02 2V24/2004 K-40 1.40E-02 2. 1OE-02 7.80E-02 AP-DAP L7054-03 3/9/2004 AcMh-228 -3.00E-04 3.20E-03 1.40E-02 AP-DAP L7054-03 3/9/2004 Be-7 5.40E-02 1.60E-02 4.70E-02 AP-DAP L7054-03 3/9/2004 Co-58 1.12E-03 8.80E-04 3.00E-03 AP-DAP L7054-03 3/9/2004 Co-60 8.OOE-04 1.40E-03 5.30E-03 AP-DAP L7054-03 3/9/2004 Cs-134 5.OOE-04 I .00E-03 3.90E-03 AP-DAP L7054-03 3/9/2004 Cs-137 4.00E-0.4 1.20E-03 4.60E-03 AP-DAP L7054-03 3/9/2004 K-40 -8.00E-03 1.20E-02 5.80E-02 AP-DAP L7069-03 211212004 AcTh-228 -2.20E-03 7.1 OE-03 2.90E-02 AP-DAP L7069-03 211212004 Be-7 3.70E-02 2.30E-02 7.40E-02 AP-DAP L7069-03 2V12/2004 Co-58 I .OOE-03 1.80E-03 7.10E-03 AP-DAP L7069-03 211212004 Co-60 2.80E-03 2.10E-03 7.OOE-03 AP-DAP L7069-03 2V12/2004 Cs-134 -3.20E-03 1.80E-03 8.50E-03 AP-DAP L7069-03 2V12V2004 Cs-137 1.OOE-03 2.50E-03 9.OOE-03 AP-DAP L7069-03 2V12V2004 K-40 6.40E-02 3.20E-02 l.OOE0-O AP-DAP L7071-03 2/24/2004 AcTh-228 4.70E-03 4.1OE-03 1.40E-02 AP-DAP L7071-03 2V24/2004 Be-7 9.90E-02 1.90E-02 I .OOE-02 AP-DAP L7071-03 2V24/2004 Co-58 -1.20E-03 1.60E-03 7.60E-03 AP-DAP L7071-03 2124/2004 Co-60 2.OOE-03 1. IOE-03 1.80E-03 AP-DAP L7071-03 2V24/2004 Cs-134 O.OOE+OO 9.80E-04 4.50E-03 AP-DAP L7071-03 2V24/2004 Cs-137 1.20E-03 1.20E-03 4.30E-03 AP-DAP L7071-03 2V24/2004 K-40 -2.00E-03 2.00E-02 8.50E-02 AP L6809-01 1115/2004 GROSS BETA 2.39E-02 6.90E-04 1.IOE-03 AP L691 1-01 1/31/2004 GROSS BETA 1.75E-02 6.40E-04 1.20E-03 AP L6944-01 2V11/2004 AcTh-228 3.802-03 4.10E-03 I.SOE-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-3
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 11 [L6944-01 2/11/2004 Be-7 -1.40E-01 2.20E-01 8.802-01 AP 11 [L6944-01 2/11/2004 Co-58 -2.60E-02 1.IOE-02 5.70E-02 AP 11 L6944-01 2/11/2004 Co-60 8.OOE-04 1.20E-03 4.60E-03 AP II L6944-01 2/11/2004 Cs-134 -1.00E-04 1.20E-03 4.901-03 AP 11 L6944-01 2/11/2004 Cs-137 L.OOE-04 1.20E-03 4.70E-03 AP 11 L6944-01 2111/2004 GROSS BETA 2.08E-02 8.40E-04 I.40E-03 AP 11 L6944-01 2/1112004 K-40 3.00E-03 1.10E-02 4.501-02 AP 11 L7052-01 3/10/2004 AcTh-228 -2.80E-03 2.80E-03 1.20E-02 AP 11 L7052-01 3/10/2004 Be-7 9.1OE-02 IlAOE-02 2.80E-02 AP 11 L7052-01 3/10/2004 Co-58 2.30E-04 6.902-04 2.80E-03 AP 11 L7052-01 3/10/2004 Co:60 3.OE-04 8.9012-04 3.602-03 AP 11 L7052-01 3/10/2004 Cs-134 1.091E-03 8.502-04 2.902-03 AP 11 L7052-01 3/10/2004 Cs-137 5.40E-04 7.SOE-04 2.70E-03 AP 11 L7052-01 3/10/2004 GROSS BETA 2.14E-02 1.OOE-03 1.50E-03 AP 11 L7052-01 3/10/2004 K-40 -2.40E-03 9.60E-03 4.10E-02 AP 11 L7068-01 2/25/2004 Acah-228 2.10E-03 4.60E-03 1.702-02 AP 11 L7068-01 2/25/2004 Be-7 7.20E-02 1.60E-02 4.00E-02 AP 11 L7068-01 2/25/2004 Co-58 1.152-03 9.OOE-04 3.10E-03 AP 11 L7068-01 2/25/2004 Co-60 3.002-04 1.202-03 4.902-03 AP 11 L7068-01 2/25/2004 Cs-134 1.532-03 7.80E-04 2.10E-03 AP 11 L7068-01 2/25/2004 Cs-137 -7.60E-04 9.202-04 4.002-03 AP 11 L7068-01 2/25/2004 GROSS BETA 2.43E2-02 1.102-03 2.00E-03 AP 11 L7068-01 2/25/2004 K40 1.70E-02 1.202-02 4.102-02 AP 11 L7130-01 3/24/2004 AcTh-228 -3.60E-03 2.402-03 1.302-02 AP 11 L7130-01 3/24/2004 Be-7 7.80E-02 1.502-02 2.802-02 AP 11 L7130-01 3/24/2004 Co-58 -2.092-03 9.402-04 5.202-03 AP 11 L7130-01 3/24/2004 Co-60 1.87E-03 9.302-04 1.302-03 AP 11 L7130-01 3/24/2004 Cs-134 1.24E-03 8.202-04 2.602-03 AP 11 L7130-01 3/24/2004 Cs-137 2.60E-04 6.90E-04 2.802-03 AP 11 L7130-01 3/24/2004 GROSS BETA 1.75E-02 9.802-04 1.70E-03 AP 11 L7130-01 3/24/2004 K40 -1.20E-03 9.40E-03 4.502-02 AP II L7190-01 4/l/2004 AcTh-228 -3.20E-03 5.202-03 2.502-02 AP 11 L7190-01 4/1/2004 Be-7 1.342-01 2.602-02 5.5023-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-4
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCiWm3) (pCi/m3) (pCi/m3)
AP 11 L7190-O1 4/1/2004 Co-58 6.00E-04 1.30E-03 5.40E-03 AP 11 L7190-Ol 4/1/2004 Co-60 -l.1OE-03 1.60E-03 8.60E-03 AP 11 L7190-01 4/1/2004 Cs-134 8.OOE-04 1.30E-03 5.20E-03 AP 11 L7190-O1 4/1/2004 Cs-137 3.90E-03 1.6012-03 3.90E-03 AP II L7190-0l 4/1/2004 GROSS BETA 1.77E-02 1.40E-03 2.901-03 AP 11 L7190-0l 4/1/2004 K40 -4.00E-03 1.80E-02 8.502-02 AP II L7217-01 4/13/2004 Acnh-228 -L.OOE-03 3.30E-03 1.40E-02 AP 11 L7217-01 4/13/2004 Be-7 1.192-01 1.70E-02 3.40E-02 AP 11 L7217-01 4/13/2004 Co-58 O.OOE+00 1.IOE-03 4.40E-03 AP 11 L7217-01 4/13/2004 Co-60 3.00E-04 LOOE-03 4.40E-03 AP 11 L7217-01 4/13/2004 Cs-134 3.90E-04 6.60E-04 2.70E-03 AP 11 L7217-01 4/13/2004 Cs-137 3.80E-04 7.702-04 3.00E-03 AP 11 L7217-01 4/13/2004 GROSS BETA 1.253-02 1.00-03 2.202-03 AP 11 L7217-01 4/13/2004 K40 -4.002-03 1.IOE-02 5.1OE-02 AP 11 L7282-0 1 3/24/2004 AcM-228 O.OOE+00 1.002-03 4.20E-03 AP 11 L7282-0l 3/24/2004 Be-7 9.10E-02 1.30E-02 2.802-02 AP 11 L7282-01 3/24/2004 Co-58 6.30E-04 6.60E-04 2.30E-03 AP 11 L7282-0 1 3/24/2004 Co-60 -2.00E-04 4.40E-04 1.90E-03 AP 11 L7282-0l 3/24/2004 Cs-134 5.OOE-05 3.10E-04 1.20E-03 AP 11 L7282-01 3/24/2004 Cs-137 3.002-05 4.80E-04 1.80E-03 AP 11 L7282-01 3/24/2004 K40 -2.032-02 4.502-03 2.502-02 AP 11 L7342-01 4/29/2004 Aclb-228 4.502-03 3.40E-03 1.102-02 AP 11 L7342-01 4/29/2004 Be-7 9.902-02 1.50E-02 3.202-02 AP 11 L7342-01 4/29/2004 Co-58 -4.002-04 5.802-04 3.00E-03 AP 11 L7342-01 4/29/2004 Co-60 O.OOE+00 O.OOE+00 1.20E-03 AP 11 L7342-01 4/29/2004 Cs-134 -1.10E-03 7.60E-04 3.902-03 AP 11 L7342-01 4/29/2004 Cs-137 -1.22E-03 7.30E-04 3.702-03 AP 11 L7342-01 4/29/2004 GROSS BETA 1.71E-02 9.20E-04 1.702-03 AP 11 L7342-01 4/29/2004 K40 7.002-03 1.IOE-02 4.30E-02 AP II L7401-01 5/10/2004 AcTh-228 8.OOE-04 3.002-03 1.20E-02 AP II L7401-01 5/10/2004 Bc-7 1.40E-01 2.202-02 5.20E-02 AP II L7401-01 5/10/2004 Co-58 -3.10E-04 9.40E-04 4.10E-03 AP II L7401-01 5/10/2004 Co-60 -2.00E-04 1.20E-03 5.40E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-5
Yankee Nuclear Power Station Radiological Environmental Monitoring Program
'Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 11 L7401-01 5/10/2004 Cs-134 6.001-04 1.10-03 4.20E-03 AP 11 L7401-01 5/10/2004 Cs-137 -7.001-05 8.302-04 3.50E-03 AP II L7401 -01 5/10/2004 GROSS BETA 1.981E-02 1.30E-03 2.50E-03 AP 11 L7401-01 5/10/2004 K-40 -1.00E-03 1.30E-02 5.40E-02 AP 11 L7468-Ol 5/25/2004 AcTh-228 -4.30E-03 2.30E-03 1.20E-02 AP 11 L7468-01 5/25/2004 Be-7 1.182-01 1.501-02 2.50E-02 AP 11 L7468-O1 5/25/2004 Co-58 -2.50E-04 8.soE-04 3.60E-03 AP 11 L7468-0l 5/25/2004 Co-60 9.90E-04 7.90E-04 2.70E-03 AP 11 L7468-01 5/25/2004 Cs-134 -3.OOE-05 8.30E-04 3.40E-03 AP 11 L7468-01 5/25/2004 Cs-137 1.06E-03 8.603-04 2.90E-03 AP 11 L7468-01 5/25/2004 GROSS BETA 1.87E-02 1.002-03 1.70E-03 AP II L7468-01 5/25/2004 K-40 L.OOE-03 1.20E-02 5.OOE-02 AP 11 L7525-01 6/7/2004 AcTh-228 0.002+00 2.602-03 1.20E-02 AP 11 L7525-01 6/7/2004 Be-7 9.30E-02 1.502-02 3.00E-02 AP 11 L7525-01 6/7/2004 Co-58 1.30E-03 1.1OE-03 3.901-03 AP 11 L7525-0 1 6n/2004 Co-60 1.74E-03 8.70E-04 1.20E-03 AP 11 L7525-01 6n72004 Cs-134 1.142-03 7.501-04 2.40E-03 AP 11 L7525-01 6n/2004 Cs-137 -7.30E-04 7.30E-04 3.40E-03 AP 11 L7525-01 6n/2004 GROSS BETA 1.43E-02 9.70E-04 1.80E-03 AP 11 L7525-01 6n/2004 K40 8.002-03 1.20E-02 4.50E-02 AP 11 L7609-01 6/23/2004 AcTh-228 -3.002-04 3.10E-03 1.20E-02 AP 11 L7609-01 6/23/2004 Be-7 1.35E-01 1.50E-02 2.60E-02 AP 11 L7609-01 6/23/2004 Co-58 8.80E-04 7.00E-04 2.402-03 AP 11 L7609-01 6/23/2004 Co-60 -2.202-04 9.202-04 3.902-03 AP 11 L7609-01 6/23/2004 Cs-134 -7.00E-04 6.002-04 3.002-03 AP 11 L7609-01 6/23/2004 Cs-137 6.80E-04 6.50E-04 2.30E-03 AP 11 L7609-01 6/23/2004 GROSS BETA 1.94E-02 1.002-03 1.902-03 AP 11 L7609-01 6/23/2004 K40 5.701-03 9.902-03 3.802-02 AP 11 L7671 -01 6/28/2004 Aclh-228 -6.002-04 8.902-03 3.702-02 AP II L767 1-01 6/28/2004 Be-7 1.622-01 3.202-02 6. 802-02 AP 11 L767 1-01 6/28/2004 Co-58 3.30E-03 2.10E-03 6.702-03 AP II L7671-01 6/28/2004 Co-60 -3.80E-03 3.302-03 1.501-02 AP 11 L7671-01 6/28/2004 Cs-134 -6.002-04 2.502-03 1.1OE-02
- Radioactivity defected in sample (i.e., concentration >3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-6
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCilm3) (pCi/m3) (pCi/m3)
AP II L7671-01 6/2812004 Cs-137 3.80E-03 l.90E-03 5.20E-03 AP II L7671-01 6128/2004 GROSS BETA l.56E-02 2.1OE-03 5.60E-03 AP 11 L7671 -01 6/28/2004 K-40 6.30E-02 3.40E-02 9.60E-02 AP II L7704-01 6n/2004 Acnh-228 2.00E-04 L.OOE-03 4.30E-03 AP 11 L7704-01 6n/2004 Be-7 1.07E-01 1.60E-02 3.40E-02 AP 11 L7704-01 6/7/2004 Co-58 -l.OOE-04 6.30E-04 2.70E-03 AP II L7704-01 6no2004 Co-60 6.OOE-05 4.10E-04 1.70E-03 AP 11 L7704-01 6n72004 Cs-134 7.OOE-05 3.30E-04 1.40E-03 AP . 11 L7704-01 6n72004 Cs-137 L.OOE-04 7.20E-04 2.60E-03 AP II L7704-01 6n72004 K-40 5.20E-03 4.60E-03 1.60E-02 AP II L7753-01 7/14/2004 Acah-228 -2.70E-03 2.1OE-03 L.OOE-02 AP II L7753-01 7/14/2004 Be-7 5.89E-02 9.80E-03 2.00E-02 AP 11 L7753-0l 7/14/2004 Co-58 1.40E-04 5.OOE-04 2.1OE-03 AP 11 L7753-0l 7/14/2004 Co-60 -2.OOE-05 6.50E-04 2.80E-03 AP 11 L7753-0l 7/14/2004 Cs-134 3.80E-04 4.30E-04 1.60E-03 AP 11 L7753-0l 7/14/2004 Cs-137 3.40E-04 4.80E-04 1.80E-03 AP II L7753-0l 7/14/2004 GROSS BETA 6.23E-03 6.30E-04 L.50E-03 AP II L7753-01 7/14/2004 K-40 .OOE-02 1.20E-02 4.50E-02 AP 11 L7838-0l 7/29/2004 Ach-228 4.50E-03 3.20E-03 L.OOE-02 AP II L7838-01 7/29/2004 Be-7 8.40E-02 1.50E-02 3.60E-02 AP 11 L7838-01 7/29/2004 Co-58 6.00E-04 6.20E-04 2.30E-03 AP 11 L7838-01 7/29/2004 Co-60 -1.30E-04 8.90E-04 3.90E-03 AP 11 L7838-0l 7/29/2004 Cs-134 -4.00E-04 L.OOE-03 4.20E-03 AP 11 L7838-01 7/29/2004 Cs-137 5.90E-04 6.1OE-04 2.20E-03 AP II L7838-0l 7/29/2004 GROSS BETA 1.58E-02 9.80E-04 1.9013E-03 AP II L7838-0l 729/2004 K-40 -1.70E-02 9.20E-03 5.20E-02 AP 11 L7904-01 8/13/2004 AcTh-228 6.00E-04 3.60E-03 1.40E-02 AP 11 L7904-01 8/13/2004 Be-7 7.20E-02 1.40E-02 3.30E-02 AP 11 L7904-01 8/13/2004 Co-58 4.50E-04 9.OOE-04 3.50E-03 AP 11 L7904-01 8/13/2004 Co-60 2.30E-03 1.20E-03 3.70E-03 AP 11 L7904-01 8/13/2004 Cs-134 5.IOE-04 8.OOE-04 3.1OE-03 AP 11 L7904-01 8/13/2004 Cs-137 7.60E-04 7.60E-04 2.70E-03 AP 11 L7904-01 8/3/2004 GROSS BETA 2.09E-02 I.1OOE-03 .501E-303
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-7
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 11 L7904-01 8/13/2004 K-40 -2.40E-02 1.202-02 6.50E-02 AP 11 L7981-01 8/27/2004 AcTh-228 -1.80E-03 2.70E-03 1.1OE-02
-AP II L7981-01 8/27/2004 Be-7 1.OOE-OI 1.40E-02 3.1OE-02 AP 11 L7981-01 8/27/2004 Co-58 1.26E-03 8.90E-04 3.00E-03 AP 11 L7981-01 8/2712004 Co-60 4.60E-04 5.10O-04 1.902-03 AP II L7981-01 8/27/2004 Cs-134 3.80E-04 4.10E-04 1.60E-03 AP 11 L7981-01 8127/2004 Cs-137 -1.70E-04 6.OOE-04 2.50E-03 AP 11 L798 1-01 8/27/2004 GROSSBETA 2.22E-02 1.20E-03 2.20E-03 AP 11 L7981-01 8/27/2004 K-40 5.00E-03 1.00E-02 3.90E-02 AP 11 L8044-01 918/2004 AcMh-228 -1.30E-03 3.40E-03 1.40E-02 AP 11 L8044-01 9/8/2004 Be-7 9.50E-02 1.50E-02 3.20E-02 AP 11 L8044-01 9/8/2004 Co-58 -1.99E-03 8.602-04 4.302-03 AP 11 L8044-01 9/8/2004 Co-60 -4.30E-04 8.20E-04 3.70E-03 AP 11 L8044-01 9/8/2004 Cs-134 -5.IOE-04 6.80E-04 3.202-03 AP 11 L8044-01 9/8/2004 Cs-137 2.00E-05 7.70E-04 3.10E-03 AP 11 L8044-01 9/8/2004 GROSS BETA 1.85E-02 1.20E-03 2.10E-03 AP 11 L8044-01 9/8/2004 K-40 5.302-03 9.902-03 3.80E-02 AP 11 L8119-01 9/22/2004 Acib-228 2.002E03 2.80E-03 1.00E-02 AP 11 L8119-01 9122/2004 Be-7 9.1 OE-02 1.50E-02 3.602-02 AP 11 L8119-01 9/2212004 Co-58 1.60E-04 7.602-04 3.10E-03 AP II L8119-01 9/22/2004 Co-60 -1.13E-03 8.002-04 4.20E-03 AP 11 L8119-01 9/22/2004 Cs-134 -1.772-03 8.1 OE-04 4.202-03 AP 11 L8119-01 9/22/2004 Cs-137 1.882-03 8.00E-04 2.20E-03 AP 11 L8119-01 9/22/2004 GROSS BETA 1.43E-02 9.50E-04 1.90E-03 AP 11 L8119-01 9/22/2004 K-40 -9.00E-03 1.002-02 4.90E-02 AP 11 L8162-01 9/27/2004 AcTh-228 5.80E-03 5.50E-03 2.002-02 AP 11 L8162-01 9/27/2004 Be-7 1.35E-01 2.80E-02 6.70E-02 AP 11 L8162-01 9/27/2004 Co-58 -6.00E-04 1.602-03 7.30E-03 AP 11 L8162-01 9/27/2004 Co-60 -1.20E-03 1.802-03 8.802-03 AP 11 L8 162-01 9/2712004 Cs-134 8.00E-04 1.30E-03 5.30E-03 AP 11 L8162-01 9/27/2004 Cs-137 O.OOE+00 2.10E-03 8.50E-03 AP II L8162-01 9/27/2004 GROSS BETA 2.52E-02 2.10E-03 4.40E-03 AP 11 L8162-01 9/27/2004 K-40 1.30E-02 3.20E-02 1.20E-01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-8
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP L8240-01 10/13/2004 AcTh-228 I .60E-03 2.90E-03 1.IOE-02 AP L8240-01 10/13/2004 Be-7 8.90E-02 I .30E-02 2.40E-02 AP L8240-01 10/13/2004 Co-58 -1 .04E-03 7.20E-04 3.70E-03 AP L8240-01 10/13/2004 Co-60 -1 .60E-03 I .40E-03 6.30E-03 AP L8240-01 10/13/2004 Cs-134 -6.90E-04 9.50E-04 4.20E-03 AP L8240-01 10/13/2004 Cs-137 4.70E-04 4.70E-04 1.70E-03 AP L8240-01 10/13/2004 GROSS BETA 2.53E-02 1.I OE-03 1.70E-03 AP L8240-01 10/13/2004 K-40 2.00E-02 I .30E-02 4.20E-02 AP L8266-01 9/27/2004 AcTh-228 -2.50E-03 1.20E-03 5.70E-03 AP L8266-01 9/27/2004 Be-7 9.60E-02 I.30E-02 2.70E-02 AP L8266-01 9/27/2004 Co-58 I .20E-04 3.70E-04 1.50E-03 AP L8266-01 9/27/2004 Co-60 0.00E+00 3.50E-04 1.50E-03 AP L8266-01 9/27/2004 Cs-134 -4.80E-04 3.60E-04 1.60E-03 AP L8266-01 9/27/2004 Cs-137 -8.00E-05 5.20E-04 1.902-03 AP L8266-01 9/27/2004 K-40 -5.30E-03 3.80E-03 1.90E-02 AP L8344-01 10/27/2004 AcTh-228 -4.80E-03 2.60E-03 1.30E-02 AP L8344-01 10/27/2004 Be-7 8.30E-02 1.30E-02 2.70E-02 AP L8344-01 10/27/2004 Co-58 1.13E-03 8.30E-04 2.80E-03 AP L8344-01 10/27/2004 Co-60 I .30E-03 l .00-03 3.60E-03 AP L8344-01 10/27/2004 Cs-134 -5.40E-04 7.80E-04 3.50E-03 AP L8344-01 10/27/2004 Cs-137 -1.50E-03 l .00-03 4.40E-03 AP L8344-01 10/27/2004 GROSS BETA I.38E-02 9.50E-04 2.00E-03 AP L8344-01 10/27/2004 K40 3.00E-03 I .OOE-02 4.20E-02 AP L8417-01 11/9/2004 AcTh-228 -6.40E-03 3.00E-03 1.702-02 AP L8417-01 11/9/2004 Be-7 5.20E-02 1.40E-02 4.00E-02 AP L8417-01 11/9/2004 Co-58 I .60E-04 9.30E-04 3.90E-03 AP L8417-01 11/9/2004 Co-60 I .90E-03 1.20E-03 3.80E-03
-AP L8417-01 11/9/2004 Cs-134 1.00E-04 [.I OE-03 4.40E-03 AP L8417-01 11/9/2004 Cs-137 5.50E-04 6.70E-04 2.60E-03 AP L8417-01 11/9/2004 GROSS BETA I .99E-02 1.1 OE-03 2.20E-03 AP .8417-01 11/9/2004 K-40 -I .60E-02 1.50E-02 7.10E-02 AP L8481-01 11/23/2004 AcTh-228 2.50E-03 3.60E-03 1.40E-02 AP L848 1-01 11/23/2004 Be-7 1.I 0E-01 1.60E-02 2.50E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-9
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 11 L8481-01 11/23/2004 Co-58 -3.90E-04 9.10E-04 4.00E-03 AP II L8481-01 11123/2004 Co-60 1.30E-03 I.OOE-03 3.40E-03 AP 11 L8481-01 11/23/2004 Cs-134 -7.00E-04 8.60E-04 4.10E-03 AP 11 L8481-01 1112312004 Cs-137 -2.20E-04 8.90E-04 3.70E-03 AP II L8481-01 11/23/2004 GROSS BETA 2.37E-02 1.IOE-03 2.00E-03 AP II L848 1-01 11/23/2004 K-40 2.60E-02 I.50E-02 4.80E-02 AP I L8549-01 1218/2004 AcTh-228 -1.10E-03 2.70E-03 1.20E-02 AP 11 L8549-01 12/8/2004 Be-7 6.60E-02 1.1OE-02 2.40E-02 AP 11 L8549-01 12/8/2004 Co-58 4.00E-04 7.80E-04 3.OOE-03 AP 11 L8549-01 12/812004 Co-60 -4.50E-04 6.80E-04 3.60E-03 AP 11 L8549-01 12/8/2004 Cs-134 -1.29E-03 6.30E-04 3.50E-03 AP 11 L8549-01 1218/2004 Cs-137 1.44E-03 5.50E-04 5.60E-04 AP 11 L8549-01 12/8/2004 GROSS BETA 1.87E-02 9.80E-04 1.60E-03 AP 11 L8549-01 12/8/2004 K-40 1.OOE-03 9.70E-03 4.10E-02 AP 11 L8604-01 12/21/2004 AcTh-228 0.00E+00 3.90E-03 1.60E-02 AP 11 L8604-01 12/21/2004 Be-7 4.90E-02 1.30E-02 3.40E-02 AP II L8604-01 12/21/2004 Co-58 3.20E-04 3.20E-04 8.70E-04 AP 11 L8604-01 12/21/2004 Co-60 9.40E-04 6.70E-04 1.30E-03 AP 11 L8604-01 12/21/2004 Cs-134 2.20E-04 7.80E-04 3.30E-03 AP 11 1,8604-01 12/21/2004 Cs-137 2.70E-04 8.00E-04 3.20E-03 AP 11 L8604-01 12/21/2004 GROSS BETA 1.71E-02 9.80E-04 1.60E-03 AP 11 L8604-01 12/21/2004 K40 -2.00E-03 1.50E-02 6.40E-02 AP 11 L8665-01 1/3/2005 AcTh-228 1.20E-03 2.70E-03 I1.OOE-02 AP II L8665-01 1/3/2005 Be-7 9.50E-02 1.40E-02 3.00E-02 AP 11 L8665-01 1/3/2005 Co-58 2.30E-04 7.70E-04 3.00E-03 AP 11 L8665-01 1/3/2005 Co-60 1.17E-03 7.70E-04 2.40E-03 AP II L8665-01 113/2005 Cs-134 0.OOE+00 7.70E-04 3.10E-03 AP 11 L8665-01 1/3/2005 Cs-137 3.OOE-04 5.80E-04 2.20E-03 AP II L8665-01 1/3/2005 K-40 -1.0I E-02 9.00E-03 4.20E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-10
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCilm3)
AP 12 L6809-02 1/15/2004 GROSS BETA 2.20E-02 6.60E-04 l.lOE-03
- AP 12 L6911-02 1/31/2004 GROSS BETA 1.49E-02 6.00E-04 1.20E-03
- AP 12 L6944-02 2/11/2004 GROSS BETA 1.94E-02 8.101E-04 1.40E-03
- AP 12 L7052-02 3/10/2004 GROSS BETA 1.58E-02 9.30E-04 1.50E-03
- AP 12 L7068-02 2/25/2004 GROSS BETA 2.24E-02 1.10-03 2.OOE-03
- AP 12 L7130-02 3/24/2004 GROSS BETA 1.34E-02 8.90E-04 1.70E-03
- AP 12 L7190-02 4/1/2004 GROSS BETA 1.75E-02 1.502-03 3.00E-03
- AP 12 L7217-02 4/13/2004 GROSS BETA 1.19E-02 11.OOE-03 2.40E-03
- AP 12 L7282-02 3/24/2004 AcTh-228 1.00E-05 9.40E-04 3.90E-03 AP 12 L7282-02 3/24/2004 Be-7 9.10E-02 1.30E-02 2.60E-02
- AP 12 L7282-02 3/24/2004 Co-58 -1.02E-03 4.60E-04 2.60E-03 AP 12 L7282-02 312412004 Co-60 3.90E-04 3.90E-04 1.40E-03 AP 12 L7282-02 312412004 Cs-134 -7.00E-05 3.50E-04 1.50E-03 AP 12 L7282-02 312412004 Cs-137 -2.00E-05 5.60E-04 2.1OE-03 AP 12 L7282-02 3/24/2004 K-40 -2.032-02 2.80E-03 2.20E-02 AP 12 L7342-02 4129/2004 GROSS BETA 1.63E-02 9.30E-04 1.70E-03
- AP 12 L7401-02 5/10/2004 GROSS BETA 1.72E-02 1.202-03 2.50E-03
- AP 12 L7468-02 5/25/2004 GROSS BETA 1.96E-02 I.IOE-03 1.80E-03
- AP 12 L7609-02 6/23/2004 GROSS BETA 1.282-02 8.80E-04 1.902-03
- AP 12 L7671-02 6/28/2004 GROSS BETA 2.062-02 2.20E-03 5.50E-03
- AP 12 L7704-02 6128/2004 Aclb-228 2.002-03 1.30E-03 4.40E-03 AP 12 L7704-02 6/28/2004 Be-7 1.192-01 1.20E-02 2.002-02
- AP 12 L7704-02 6/28/2004 Co-58 3.90E-04 4.70E-04 1.70E-03 AP 12 L7704-02 612812004 Co-60 4.00E-04 4.OOE-04 1.80E-03 AP 12 L7704-02 6/28/2004 Cs-134 -3.602-04 3.402-04 1.50E-03 AP 12 L7704-02 6128/2004 Cs-137 -1.70E-04 5.802-04 2.10E-03 AP 12 L7704-02 6128/2004 K-40 6.602-03 4.1 OE-03 1.302-02 AP 12 L7753-02 7/14/2004 GROSS BETA 1.31E-02 8.70E-04 1.802-03 AP 12 L7838-02 7/29/2004 GROSS BETA 1.52E-02 9.702-04 2.002-03
- Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-Il
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 12 L7904-02 8/13/2004 GROSS BETA I .95E-02 I .OOE-03 I .50E-03 AP 12 L7981-02 8/n72004 GROSS BETA 2.18E-02 I .20E-03 2.20E-03 AP 12 L8044-02 9/8/2004 GROSS BETA 2.01E-02 1.20E-03 2.20E-03 AP 12 L8119-02 9/22/2004 GROSS BETA 1.37E-02 9.30E-04 1.90E-03 AP 12 L8 162-02 9/29/2004 GROSS BETA 2.92E-02 l.90E-03 3.30E-03 AP 12 L8240-02 10/13/2004 GROSS BETA 2.61E-02 1.20E-03 1.80E-03 AP 12 L8266-02 9/29/2004 AcTh-228 1.30E-03 1.1 OE-03 3.80E-03 AP 12 L8266-02 9/29/2004 Be-7 6.90E-02 I .20E-02 2.90E-02 AP 12 L8266-02 9/29/2004 Co-58 1.OOE-04 4.40E-04 1.80E-03 AP 12 L8266-02 9/29/2004 Co-60 -1.IOE-04 3.80E-04 1.60E-03 AP 12 L8266-02 9/29/2004 Cs-134 -6.80E-04 3.40E-04 1.70E-03 AP 12 L8266-02 9129/2004 Cs-137 -1.07E-03 5.50E-04 2.20E-03 AP 12 L8266-02 9/29/2004 K-40 -1.50E-03 4.40E-03 1.90E-02 AP 12 L8344-02 10/27/2004 GROSS BETA 1.41E-02 9.60E-04 2.00E-03 AP 12 L8417-02 11/9/2004 GROSS BETA 1.93E-02 1.IOE-03 2. 1OE-03 AP 12 L8481-02 11/23/2004 GROSS BETA 2.32E-02 1.IOE-03 2.OOE-03 AP 12 L8549-02 12/8/2004 GROSS BETA I .75E-02 9.40E-04 1.60E-03 AP 12 L8604-02 12/21/2004 GROSS BETA 1.73E-02 9.80E-04 1.60E-03 AP 13 L6809-03 1/15/2004 GROSS BETA 3.09E-02 9.30E-04 I .50E-03 AP 13 L6911-03 1/31/2004 GROSS BETA 2.04E-02 8.30E-04 1.60E-03 AP 13 L6944-03 2/11/2004 GROSS BETA 2.27E-02 1.10E-03 2.OOE-03 AP 13 L7052-03 3/10/2004 GROSS BETA 2.44E-02 1.30E-03 2.1 OE-03 AP 13 L7068-03 2/25/2004 GROSS BETA 3.31 E-02 I .50E-03 2.70E-03 AP 13 L7130-03 3/2412004 GROSS BETA 2.4 1E-02 1.40E-03 2.40E-03 AP 13 L7190-03 4/1/2004 GROSS BETA 2.15E-02 1.90E-03 4.20E-03 AP 13 L7217-03 4113/2004 GROSS BETA I .70E-02 1.40E-03 3.1OE-03 AP 13 L7282-03 3124/2004 AcTh-228 I .70E-03 1.IOE-03 3.70E-03 AP 13 L7282-03 3/24/2004 Be-7 I .OOE-01 1.80E-02 4.20E-02 AP 13 L7282-03 3124/2004 Co-58 -1.60E-04 8.40E-04 3.50E-03 AP 13 L7282.03 3/24/2004 Co-60 3.80E-04 5.60E-04 2.10E-03 AP 13 L7282-03 3/24/2004 Cs-134 -5.20E-04 4.80E-04 2.20E-03 AP 13 L7282-03 3/24/2004 Cs-137 8.20E-04 7.OOE-04 2.40E-03 AP 13 L7282-03 3/24/2004 K-40 -2.64E-02 4.90E-03 3.20E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-12
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 13 L7342-03 4/29/2004 GROSS BETA 2.32E-02 1.30E-03 2.40E-03
- AP 13 L7401-03 5/10/2004 GROSS BETA 2.64E-02 1.902-03 3.90E-03
- AP 13 L7468-03 5/25/2004 GROSS BETA 2.53E-02 1.40E-03 2.40E-03
- AP 13 L7525-03 6/7/2004 GROSS BETA 1.53E-02 1.30E-03 2.60E-03
- AP 13 L7609-03 6/23/2004 GROSS BETA 2.46E-02 1.40E-03 2.70E-03
- AP 13 L7671-03 6/30/2004 GROSS BETA 2.492-02 2.40E-03 5.80E-03
- AP 13 L7704-03 6/30/2004 AcTh-228 6.00E-04 1.502-03 5.70E-03 AP 13 L7704-03 6/30/2004 Be-7 1,32E-01 1.60E-02 3.30E-02
- AP 13 L7704-03 6/30/2004 Co-58 -5.1 OE-04 5.40E-04 2.60E-03 AP 13 L7704-03 6/30/2004 Co-60 6.002-05 3.90E-04 1.70E-03 AP 13 L7704-03 6/30/2004 Cs-134 -2.102-04 4.102-04 1.802-03 AP 13 L7704-03 6/30/2004 Cs-137 4.70E-04 8.202-04 2.90E-03 AP 13 L7704-03 6/30/2004 K-40 7.502-03 6.40E-03 2.20E-02 AP 13 L7753-03 7/14/2004 GROSS BETA 1.752-02 1.302-03 2.90E-03
- AP 13 L7838-03 7/29/2004 GROSS BETA .951E-02 1.40E-03 2.90E-03
- AP 13 L7904-03 8/13/2004 GROSS BETA 2.56E-02 1.40E-03 2.20E-03
- AP 13 L7981-03 8/27/2004 GROSS BETA 2.772-02 1.60E-03 3.20E-03
- AP 13 L8044-03 9/8/2004 GROSS BETA 2.502-02 1.702-03 3.202-03
- AP 13 L8 119-03 9/22/2004 GROSS BETA 2.072-02 1.402-03 2.80E-03
- AP 13 L8 162-03 9/27/2004 GROSS BETA 3.972-02 3.302-03 6.802-03
- AP 13 L8240-03 10/13/2004 GROSS BETA 3.522-02 1.502-03 2.30E-03
- AP 13 L8266-03 9/27/2004 AcTh-228 0.002+00 1.802-03 7.202-03 AP 13 L8266-03 9/27/2004 Be-7 1.492-01 1.802-02 2.802-02
- AP 13 L8266-03 9/27/2004 Co-58 -5.90E-04 6.302-04 3.102-03 AP 13 L8266-03 9/27/2004 Co-60 4.002-05 6.602-04 2.70E-03 AP 13 L8266-03 9/27/2004 Cs-134 7.002-04 4.50E-04 1.502-03 AP 13 L8266-03 9/27/2004 Cs-137 5.70E-04 9.002-04 3.202-03 AP 13 L8266-03 9/27/2004 K-40 3.40E-03 6.502-03 2.502-02 AP 13 L8344-03 10/27/2004 GROSS BETA 1.592-02 1.30E-03 2.902-03
- AP 13 L8417-03 11/9/2004 GROSS BETA 2.392-02 1.70E-03 3.602-03
- AP 13 L8481-03 11/23/2004 GROSS BETA 2.852-02 1.502-03 2.802-03
- AP 13 L8549-03 12/8/2004 GROSS BETA 2.392-02 1.302-03 2.302-03
- AP 13 L8604-03 12/21/2004 GROSS BETA 1.832-02 1.202-03 2.30E-03 *
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-13
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pci/m3) (pCi/m3) (pCi/m3)
AP L6809-04 I/15/2004 GROSS BETA 2.40E-02 6.80E-04 1.00I2-03 AP L69 11-04 1/31/2004 GROSS BETA 1.792-02 6.40E-04 1.20E-03 AP L6944-04 2/11/2004 GROSS BETA 2.05E-02 8.1 OE-04 1.40E-03 AP L7052-04 3/10/2004 GROSS BETA 1.87E-02 9.60E-04 1.50-03 AP L7068-04 2/25/2004 GROSS BETA 2.691-02 1.I OE-03 1.902-03 AP L7 130-04 3/24/2004 GROSS BETA 1.50E-02 9.20E-04 1.70E-03 AP L7 190-04 4/2/2004 GROSS BETA 1.31 E-02 I .20E-03 2.40E-03 AP L7217-04 4/13/2004 GROSS BETA 1.23E-02 I .OOE-03 2.30E-03 AP L7282-04 3/24n2004 AcTh-228 -6.00E-04 1.20E-03 4.90E-03 AP L7282-04 3/24/2004 Be-7 7.30E-02 1.20E-02 2.30E-02 AP L7282-04 3/24/2004 Co-58 4.00E-05 6.70E-04 2.70E-03 AP L7282-04 3/24/2004 Co-60 1.30E-04 3.40E-04 1.40E-03 AP L7282-04 3/24/2004 Cs-134 1.50-04 2.80E-04 1.1 OE-03 AP L7282-04 3/24/2004 Cs-137 -1.30E-03 5.20E-04 2.20E-03 AP L7282-04 3/24/2004 K40 -. A91-02 4.00E-03 2.20E-02 AP L7342-0-4 4/29/2004 GROSS BETA 1.61 E-02 8.90E-04 1.602-03 AP L7401-04 5/10/2004 GROSS BETA 1.86E-02 1.20E-03 2.40E-03 AP L7468-0.4 5/25/2004 GROSS BETA 2.07E-02 I .OOE-03 1.60E-03 AP L7525-04 6n/2004 GROSS BETA 1.14E-02 8.70E-04 1.70E-03 AP L7609-04 6/23/2004 GROSSBETA 1.78E-02 9.40E-04 1.80E-03 AP L7671-04 6/28/2004 GROSSBETA 1.97E-02 2.1 OE-03 5.20E-03 AP L7704-0-4 6/28/2004 AcTh-228 7.00E-04 1.I OE-03 4.10E-03 AP L7704-04 6/28/2004 Be-7 I.IOE-0I 1.202-02 2.20E-02 AP L7704-04 6/28/2004 Co-58 -4.30E-04 5.90E-04 2.50E-03 AP L7704-04 6/28/2004 CD-60 -3.70E-04 3.70E-04 1.70E-03 AP L7704-04 6/28/2004 Cs-134 0.00+00 3.80E-04 1.502-03 AP L7704-04 6128/2004 Cs-137 4.10E-04 5.40E-04 1.90E-03 AP L7704-04 6128/2004 K40 3.90E-03 3.50E-03 1.202-02 AP L7753-04 7/14/2004 GROSSBETA I .20E-02 8. 1OE-04 1.702-03 AP L7838-04 7/29/2004 GROSS BETA 1.43E-02 9.IOE-04 1.90E-03 AP L7904-04 8/13/2004 GROSS BETA 1.90E-02 9.50E-04 1.40E-03 AP L7981-04 8/27/2004 GROSS BETA 1.81E-02 1.I OE-03 2.10E-03 AP L8044-04 9/8/2004 GROSSBETA 1.78E-02 1.IOE-03 2.00E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-14
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCift3) (pCi/m3) (pCi/m3)
AP 14 L8119-04 9122/2004 GROSS BETA 1.29E-02 8.80E-04 1.80E-03 AP 14 L8162-04 9/29/2004 GROSS BETA 2.60E-02 1.70E-03 2.90E-03 AP 14 L8240-04 10/13/2004 GROSS BETA 2.52E-02 1.1OE-03 1.80E-03 AP 14 L8266-04 9/29/2004 AcTh-228 -5.90E-04 8.40E-04 3.902-03 AP 14 L8266-04 9/29/2004 Be-7 9.1 OE-02 1.20E-02 2.30E-02 AP 14 L8266-04 9/29/2004 Co-58 8.40E-04 4.70E-04 1.402-03 AP 14 L8266-04 9129/2004 Co-60 -2.30E-04 3.30E-04 1.50E-03 AP 14 L8266-04 9/29/2004 Cs-134 5.90E-04 3.60E-04 1.20E-03 AP 14 L8266-04 9/29/2004 Cs-137 -7.40E-04 4.80E-04 1.90E-03 AP 14 L8266-04 9/29/2004 K-40 -3.80E-03 3.80E-03 1.80E-02 AP 14 L8344-04 10/27/2004 GROSS BETA 1.22E-02 8.70E-04 l.90E-03 AP 14 L8417-04 11/9/2004 GROSS BE1A 1.85E-02 I.OOE-03 2.00E-03 AP 14 L8481-04 11/23/2004 GROSS BETA 2.23E-02 1.1 OE-03 1.90E-03 AP 14 L8549-04 12/8/2004 GROSS BETA 1.73E-02 9.202-04 1.501E-03 AP 14 L8604-04 12/21/2004 GROSS BETA 1.652-02 9.302-04 1.50E-03 AP 21 L6809-05 1/15/2004 GROSS BETA 1.73E-02 8.302-04W 1.70E-03 AP 21 L6911-05 1/31/2004 GROSS BETA 1.592-02 7.602-04 1.60E-03 AP 21 L6944-05 2/11/2004 GROSS BETA 1.262-02 7.30E-04 1.50E-03 AP 21 L7052-05 3/10/2004 GROSS BETA 1.662-02 1.002-03 1.80E-03 AP 21 L7068-05 2/25/2004 GROSS BETA 2.052-02 1.1 OE-03 2.20E-03 AP 21 L7130-05 3/24/2004 GROSS BETA 1.282-02 9.40E-04 1.90E-03 AP 21 L7190-05 3131/2004 GROSS BETA 1.68E-02 1.30E-03 2.50E-03 AP 21 L7217-05 4/13/2004 GROSS BETA 1.442-02 1.20E-03 2.70E-03 AP 21 L7282-05 3/24/2004 Acrh-228 -4.OOE-04 1.1OE-03 4.80E-03 AP 21 L7282-05 3/24/2004 Be-7 l .OOE-01 1.50E-02 3.00E-02 AP 21 L7282-05 3/24/2004 Co-S8 -5.80E-04 6.80E-04 3.10E-03 AP 21 L7282-05 3/24/2004 Co-60 -7.20E-04 3.60E-04 2.002-03 AP 21 L7282-05 3/24/2004 Cs-134 -7.00E-05 4.00E-04 1.70E-03 AP 21 L7282-05 3/24/2004 Cs-137 1.06E-03 7.20E-04 2.402-03 AP 21 L7282-05 3/24/2004 K-40 -1.43E-02 5.70E-03 2.80E-02 AP 21 L7342-05 4/29/2004 GROSS BETA 1.76E-02 9.60E-04 1.80E-03 AP 21 L7401-05 5/10/2004 GROSS BETA 2.05E-02 1.30E-03 2.602-03 AP 21 L7468-05 5/25/2004 GROSS BETA 1.78E-02 1.00-03 1.80E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > ILower Limit or Detection Requirement C-15
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP L7525-05 6nno/4 GROSS BETA 1.211E-02 9.201-04 1.803-03 AP L7609-05 6/23/2004 GROSS BETA 1.98E-02 I .OOE-03 1.9023-03 AP L7671-05 612812004 GROSS BETA 1.43E-02 2.00E-03 5.502-03 AP L7704-05 6/28/2004 AcTh-228 1.06E-03 9.90E-04 3.502-03 AP L7704-05 6/28/2004 Be-7 9.70E-02 1.20E-02 2.402-02 AP L7704-05 6/28/2004 CO-58 -9.002-05 5.1OE-04 2.10E-03 AP L7704-05 6/28/2004 Co-60 -2.80E-04 4.20E-04 1.80E-03 AP L7704-05 6/28/2004 Cs-134 -1.90E-04 3.901-04 1.60E-03 AP L7704-05 6/28/2004 Cs-137 2.90E-04 5.60E-04 2.00E-03 AP L7704-05 6/28/2004 K-40 5.OOE-04 4.00E-03 1.60E-02 AP L7753-05 7/14/2004 GROSS BETA 1.33E-02 8.90E-04 1.8023-03 AP L7838-05 7/29/2004 GROSS BETA 1.65E-02 .OOE-03 2.002-03 AP L7904-05 8/13/2004 GROSS BETA 1.9 1E-02 11.OOE-03 1.602-03 AP L7981-05 8/27/2004 GROSS BETA 2.12E-02 1.IOE-03 2.20E-03 AP L8044-05 9/8/2004 GROSS BETA 2.082-02 1.20E-03 2.202-03 AP L8119-05 9/22/2004 GROSS BETA 1.37E-02 9.40E-04 1.90E-03 AP L8162-05 9/27/2004 GROSSBETA 3.32E-02 2.40E-03 4.50E-03 AP L8240-05 10/13/2004 GROSS BETA 2.30E-02 1.0012-03 1.702-03 AP L8266-05 9/27/2004 AcTh-228 1.30E-03 1.30E-03 4.60E-03 AP L8266-05 9/27/2004 Be-7 1.18E-01 1.40E-02 2.702-02 AP L8266-05 9/27/2004 Co-58 -7.00E-04 7.30E-04 3.1OE-03 AP L8266-05 9/27/2004 Co-60 -3.70E-04 3.90E-04 1.802-03 AP L8266-05 9/27/2004 Cs-134 2.50E-04 3.50E-04 1.30E-03 AP 1.266-05 9/27/2004 Cs-137 -1.281-03 5.602-04 2.302-03 AP L8266-05 9/27/2004 K-40 7.60E-03 5.50E-03 1.80E-02 AP L.8344-05 10/27/2004 GROSS BETA 1.29E-02 9.20E-04 2.00E-03 AP L8417-05 11/9/2004 GROSS BETA 1.87E-02 1.IOE-03 2.202-03 AP 1.8481-05 11/23/2004 GROSS BETA 2.20E-02 1.20E-03 2.402-03 AP L8549-05 12/8/2004 GROSS BETA 1.94E-02 1.002-03 1.70E-03 AP L8604-05 12/21/2004 GROSS BETA 1.632-02 9.701-04 1.60E-03 AP L6809-06 1/15/2004 GROSS BETA 2.76E-02 8.502-04 1.40E-03 AP L69 11-06 1/31/2004 GROSS BETA I.68E-02 6.20E-04 1.202-03 AP 1.6944-06 2/11/2004 GROSS BETA 2.06E-02 8.902-04 1.602-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-16
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 31 L7052-06 3/10/2004 GROSS BETA 2.03E-02 1.20E-03 2.10E-03
- AP 31 L7068-06 2/25/2004 GROSS BETA 2.90E-02 2.OOE-03 4.30E-03
- AP 31 L7130-06 3/24/2004 GROSS BETA 1.93E-02 1.20E-03 2.20E-03
- AP 31 L7190-06 4/l/2004 GROSS BETA 2.26E-02 1.80E-03 3.70E-03
- AP 31 L7217-06 4/13/2004 GROSS BETA 1.59E-02 1.30E-03 2.90E-03
- AP 31 L7282-06 3/24/2004 AcTh-228 -2.00E-03 I.50E-03 6.70E-03 AP 31 L7282-06 3124/2004 Be-7 8.00E-02 1.50E-02 3.30E-02 AP 31 L7282-06 3/24/2004 Co-58 6.00E-05 8.80E-04 3.50E-03 AP 31 L7282-06 3/24/2004 Co-60 7.90E-04 4.50E-04 1.40E-03 AP 31 L7282-06 3/24/2004 Cs-134 -6.00E-05 3.70E-04 1.60E-03 AP 31 L7282-06 3/24/2004 Cs-137 I.90E-04 7.70E-04 2.80E-03 AP 31 L7282-06 3/24/2004 K40 -8.60E-03 5.90E-03 2.70E-02 AP 31 L7342-06 4/29/2004 GROSS BETA 1.96E-02 1.I OE-03 2.20E-03
- AP 31 L7401-06 5/10/2004 GROSS BETA 2.22E-02 1.60E-03 3.30E-03
- AP 31 L7468-06 512512004 GROSS BETA 2.12E-02 1.30E-03 2.20E-03
- AP 31 L7525-06 6/72004 GROSS BETA 1.70E-02 1.20E-03 2.40E-03
- AP 31 L7609-06 6/23/2004 GROSS BETA 2.36E-02 1.20E-03 2.40E-03
- AP 31 L7671-06 6/28/2004 GROSS BETA 1.91 E-02 2.70E-03 7.20E-03
- AP 31 L7704-06 6/28/2004 AcTh-228 2.1 OE-03 1.40E-03 4.40E-03 AP 31 L7704-06 6/28/2004 Be-7 1.18E-01 1.40E-02 2.60E-02
- AP 31 L7704-06 6/28/2004 Co-58 -7.60E-04 7.30E-04 3.20E-03 AP 31 L7704-06 6/28/2004 Co-60 2.20E-04 4.40E-04 1.70E-03 AP 31 L7704-06 6/28/2004 Cs-134 3.30E-04 3.30E-04 1.20E-03 AP 31 L7704-06 6/28/2004 Cs-137 2.40E-04 7.90E-04 2.80E-03 AP 31 L7704-06 6/28/2004 K40 5.30E-03 6.40E-03 2.30E-02 AP 31 L7753-06 7/14/2004 GROSS BETA 1.33E-02 9.50E-04 2.00E-03
- AP 31 L7838-06 7/29/2004 GROSS BETA 1.80E-02 I.IOE-03 2.30E-03
- AP 31 L7904-06 8/13/2004 GROSS BETA 2.18E-02 1.20E-03 1.80E-03
- AP 31 L7981-06 8/27/2004 GROSS BETA 2.36E-02 1.30E-03 2.60E-03
- AP 31 L8044-06 9/8/2004 GROSS BETA 2.281E-02 1.40E-03 2.5013-03
- AP 31 L8119-06 9/22/2004 GROSS BETA 1.6513-02 1.IOE-03 2.2013-03
- AP 31 L8162-06 9/29/2004 GROSS BETA 3.53E-02 2.20E-03 3.70E-03
- AP 31 L8240-06 10/13/2004 GROSS BETA 2.8313-02 1.30E-03 2.10OE-03 *
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit orDetection Requirement C-17
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3) (pCi/m3) (pCi/m3)
AP 31 L8266-06 9/29/2004 AcTh-228 4.00E-04 1.IOE-03 4.40E-03 AP 31 L8266-06 9/29/2004 Be-7 I .03E-01 1.40E-02 3.002-02 AP 31 L8266-06 9/29/2004 Co-58 -4.80E-04 5.50E-04 2.60E-03 AP 31 L8266-06 9/29/2004 Co-60 2.90E-04 4.20E-04 I .60E-03 AP 31 L8266-06 9/29/2004 Cs-134 4.00E-05 3.90E-04 I.60E-03 AP 31 L8266-06 9/29/2004 Cs-137 -7.70E-04 7.60E-04 2.90E-03 AP 31 L8266-06 9/29/2004 K-40 8.50E-03 6.40E-03 2.20E-02 AP 31 L8344-06 10/27/2004 GROSSBETA 1.34E-02 I OOE-03 2.30E-03 AP 31 L8417-06 11/9/2004 GROSS BETA 1.99E-02 1.20E-03 2.50E-03 AP 31 L8481-06 11/23/2004 GROSS BETA 2.14E-02 1.20E-03 2.30E-03 AP 31 L8549-06 12/8/2004 GROSS BETA 1.74E-02 1.OOE-03 I.80E-03 AP 31. L8604-06 12/21/2004 GROSS BETA 2.11E-02 1.11OE-03 1.80E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-18
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary ot 2004 Data SAMPLE IEND CONC STD.DEV. MDC TYPE STATION LSN D))ATE NUCLIDE (pCi/kg) (pci/kg) (pCi/kg)
FH L7398-01 4/22/2004 Ag- lOim 0.002+00 1.202+01 4.802+01 FH L7398-01 4/22/2004 Ba-140 -6.20E+01 4.90E+01 2.30E+02 FH L7398-01 4/22/2004 Be-7 O.OOE+00 l .00E+02 3.80E+02 FH L7398-01 4/22/2004 Ce-141 -2.70E+01 2.30E+0O 8.70E+01 FH-I L7398-01 4/22/2004 Ce-144 -1.30E+01 4.60E+01 1.702+02 FH1 L7398-01 4122/2004 Co-57 -9.80E+00 5.902+00 2.30E+01 FH L7398-01 4/22t2004 Co-58 l.OOE+01 1.10+01 3.90E+01 FH L7398-01 4/22/2004 Co-60 -1.1OE+01 1.00E+01 4.60E+01 FH L7398-01 4/22/2004 Cs-134 2.60E+00 8.80E+00 3.40E+01 FH L7398-01 4/22/2004 Cs-137 3.90E+01 1.40E+01 4.20E+01 FH L7398-01 4/22/2004 Fe-59 -2.20E+01 4.50E+01 1.80E+02 FH L7398-01 4/22/2004 1-131 -5.00E+01 1.30E+02 5.00E+02 3.40E+03 3.30E+02 5.00E+02 #
FH L7398-01 4t22/2004 K40 FH L7398-01 4/22/2004 La-140 -7.20E+01 5.70E+01 2.70E+02 FH L7398-01 4/22/2004 Mn-54 1.00+01 1.202+01 4.00E+01 FH L7398-01 4/22/2004 Nb-95 -1.50E+01 1.60E+01 6.502+01 FH L7398-01 4/22/2004 Ru-103 1.402+01 1.402+01 5.002+01 FH L7398-01 4/22/2004 Ru-106 -5.70E+01 9.40E+01 3.70E+02 FH L7398-01 4/22/2004 Sb-124 9.40E+00 9.40E+00 2.60E+01 FH L7398-01 4/22/2004 Zn-65 O.OOE+00 2.20E+01 8.60E+01 FH L7398-01 4/22/2004 Zr-95 5.10E+01 2.10E+OI 5.90E+01 FH L8337-01 10/19/2004 Ag-I Orm -7.00E+00 1.10+01I 5.00E+01 FH L8337-01 10/19/2004 Ba-140 O.OOE+00 2.80E+01 1.20E+02 FH L8337-01 10/19/2004 Be-7 1.70E+01 8.90E+01 3.40E+02 FH L8337-01 10/19/2004 Ce-141 -9.OOE+00 1.70E+01 6.30E+01 FH L8337-01 10/19/2004 Cc-144 1.16E+02 5.00E+01 1.602+02 Fl1 L8337-01 10/19/2004 Co-57 -2.30E+00 6.80E+00 2.50E+01 FH L8337-01 10/19/2004 Co-58 1.91 E+OI 9.10E+00 2.602+01 FH L8337-01 10/19/2004 Co-60 1.00E+01 1.30E+01 4.80E+01 FH L8337-01 10/19/2004 Cs-134 7.1 0E+00 9.40E+00 3.40E+01 FH L8337-01 10/19/2004 Cs-137 3.50E+01 1.40E+01 4. 10E+OI FH I1 L8337-01 10/19/2004 Fe-59 1.20E+01 3.802+01 1.50E+02 FH I1 L8337-01 10/19/2004 1-131 -1.47E+02 5.40E+01 2.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-I9
Yankce Nuclear Power Station Radiological Environmcntal Monitoring Program Summary of 2004 Data-SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
Fll L8337-01 10/19/2004 K-40 2.28E+03 3.20E+02 6.40E+02 Fl L8337-01 10/19/2004 La-140 0.OOE+00 3.20E+0O 1.40E+02 FH L8337-01 10/19/2004 Mn-54 -1.59E+01 9.90E+00 4.40E+01 FH L8337-01 10/19/2004 Nb-95 2.30E+01 1.IOE+0O 3.30E+0O FH L8337-01 10/19/2004 Ru-103 -2.30E+01 1.30E+0O 5.40E+01 FH L8337-01 10/19/2004 Ru-106 -5.70E+01 9.90E+0O 3.90E+02 FH L8337-01 10o19/2004 Sb-124 0.OOE+O0 2.00E+0O 9.10E+OI FH L8337-01 10/1912004 Zn-65 2.30E+01 2.80E+0O 9.90E+O1 FH L8337-01 10/1912004 Zr-95 3.90E+01 1.90E+0O 5.90E+01 FH L7398-02 4/22/2004 Ag-l lOm -7.00E+00 1.70E+OI 6.90E+01 FH L7398-02 4/22/2004 Ba-140 -1.21E+02 5.70E+0I 3.OOE+02 Fl1 L7398-02 4/22/2004 Be-7 5.90E+01 7.70E+0I 2.80E+02 FH L7398-02 4/22/2004 Ce-141 -4.00E+00 2.20E+01 7.80E+01 FH L7398-02 4/22/2004 Cc-144 -3.40E+01 5.10E+0I 1.90E+02 FH L7398-02 4/22/2004 Co-57 -3.90E+00 6.50E+00 2.40E+01 FH L7398-02 4/22/2004 Co-58 -1.60E+01 1.30E+01 5.50E+01 FH L7398-02 4122/2004 Co-60 -2.00E+00 1.OOE+0O 4.40E+01 FH L7398-02 4/22/2004 Cs-134 4.50E+00 8.80E+00 3.40E+01 FH L7398-02 4/22/2004 Cs-137 -6.OOE+00 1.IOE+OI 4.40E+01 FH L7398-02 4/22/2004 Fe-59 -1.33E+02 5.90E+0O 2.70E+02 FH L7398-02 4/22/2004 I-131 -2.1 OE+02 1.30E+02 5.30E+02 FH L7398-02 4/22/2004 K-40 3.52E+03 3.70E+02 5.20E+02 FH L7398-02 4/22/2004 La-140 -1.39E+02 6.50E+0O 3.50E+02 FH L7398-02 4122/2004 Mn-54 1.OOE+00 1.OOE+0O 4.00E+OI FH L7398-02 4/22/2004 Nb-95 2.20E+01 2.00E+0O 6.90E+0O FH L7398-02 4/22/2004 Ru-103 -6.00E+00 1.60E+0O 6. 10E+OI FH L7398-02 4/22/2004 Ru-106 -1.OOE+02 1.OOE+02 4.101E+02 FH L7398-02 4/22/2004 Sb-124 -1.20E+01 3.20E+0O I .50E+02 FH L7398-02 4/22/2004 Zn-65 -2.50E+01 3.20E+01 1.30E+02 FPl L7398-02 4/22/2004 Zr-95 -6.40E+01 2.50E+0O 1.20E+02 FH L8337-02 1011/2004 Ag-I Orm 0.OOE+00 I.50E+0 6.00E+0O FH 21 L8337-02 10/1/2004 Ba-140 -I.OOE+02 1.OOE+02 4.70E+02 FH 21 L8337-02 10/1/2004 Be-7 1.30E+02 1.30E+02 4.60E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-20
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
FH 21 L8337-02 10/1/2004 Ce-141 1.00E+01 2.60E+01 9.30E+01 FH 21 L8337-02 10/1/2004 Cc-144 1.90E+01 5.80E+01 2.00E+02 FH 21 L8337-02 10/1/2004 Co-57 8.00E-01 6.70E+00 2.40E+01 FH 21 L8337-02 10/1/2004 Co-58 2.30E+01 1.60E+01 5.50E+01 FH 21 L8337-02 10/1/2004 Co-60 1.402+01 1.50E+01 5.202+01 FH 21 L8337-02 10/1/2004 Cs-134 -2.00E+00 1.20E+01 4.90E+01 FH 21 L8337-02 10/112004 Cs-137 2.10E+01 1.50E+01 4.90E+01 FH 21 L8337-02 10/112004 Fc-59 2.80E+01 4.10E+01 1.60E+02 FH 21 L8337-02 10/1/2004 1-131 -1.30E+02 2.40E+02 9.40E+02 FH 21 L8337-02 10/1/2004 K40 3.56E+03 4.OOE+02 5.30E+02 FH 21 L8337-02 10/1/2004 La-140 -1.20E+02 1.202+02 5.40E+02 FH 21 L8337-02 10/1/2004 Mn-54 1.70E+01 1.IOE+01 3.70E+01 FH 21 L8337-02 10/1/2004 Nb-95 -2.30E+01 2.102+01 9.30E+01 FH 21 L8337-02 10/1/2004 Ru-103 -7.00E+00 1.60E+01 6.40E+01 FH 21 L8337-02 10/1/2004 Ru-106 -2.60E+01 9.10E+01 3.70E+02 FH 21 L8337-02 10/1/2004 Sb-124 3.10E+01 3.10E+01 1.10+02 FH 21 L8337-02 10/1/2004 Zn-65 -3.70E+01 3.402+01 1.50E+02 FHl 21 18337-02 10/1/2004 Zr-95 5.00E+01 2.60E+01 8.00E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > LoNver Limit (if Detection Requirement C-21
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
MS 33 L7204-01 3/31/2004 AcTh-228 2.60E+00 8.30E+00 2.90E+0I MS 33 L7204-01 3/31/2004 Ag-I Orm -4.50E+00 2.60E+00 1.lIOE+OI MS 33 L7204-01 3/3112004 Ba-140 S.OOE-0I 2.90E1+O0 1.1 OE+O1 MS 33 L7204-01 3/31/2004 Be-7 1.801E+0O 1.40E+01 4.80E+OI MS 33 L7204-O1 3/31/2004 Cc-141 -3.60E+00 3.30E+00 1.20E+OI MS 33 L7204-01 3/31/2004 Ce-144 1.20E+O1 1.30E+0I 4.20E+O1 MS 33 L7204-01 313112004 Co-57 -1.30E+00 1.50E+00 5.50E+O0 MS 33 L7204-01 3/31/2004 Co-58 3.00E-0I l.90E+O0 7.00E+00 MS 33 L7204-01 3/31/2004 Co-60 -I1.OOE+O0 2.00E+O0 7.80E+00 MS 33 L7204-01 3/31/2004 Cs-134 -8.00E-0O 1.70E+O0 6.80E+00 MS 33 L7204-01 3/31/2004 Cs-137 1.96E+01 3.1OE+00 7.50E+00 MS 33 L7204-01 3/31/2004 Fe-59 1.63E+01 6.30E+00 1.90E+OI MS 33 L7204-01 3/31/2004 1-131 -4. 1OE+00 4.40E+00 1.70E+0I MS 33 L7204-01 3/31/2004 K-40 1.89E+03 8.90E+OI 7.70E+0I MS 33 L7204-01 3/31/2004 La-140 9.00E-0I 3.30E+00 1.30E+01 MS 33 L7204-01 3/31/2004 Mn-54 -9.OOE-0I 1.90E+O0 7.10E+0O MS 33 L7204-0O 3/31/2004 Nb-95 -9.OOE-0I 2.20E+00 8.20E+O0 MS 33 L7204-01 3/31/2004 Ru-103 -2.1OE+00 1.60E+00 6.60E+00 MS 33 L7204-01 3/3112004 Ru-106 2.50E+01 1.60E+01 5.1OE+01 MS 33 L7204-01 3/3112004 Sb-124 2.30E+00 2.80E+00 I.OOE+01 MS 33 L7204-01 3/31/2004 Zn-65 -1.06E+OI 4.70E+00 2.00E+0I MS 33 L7204-01 3/31/2004 Zr-95 6.00E-0I 3.40E+00 1.30E+0I MS 45 L7204-02 3/31/2004 AcTh-228 3.60E+00 6.40E+00 2.30E+01 MS 45 L7204-02 3/31/2004 Ag-I Orm 2.50E+00 2.20E+00 7.60E+00 MS 45 L7204-02 3/31/2004 Ba-140 -4.00E-0O 2.80E+00 1.20E+01 MS 45 L7204-02 3/31/2004 Be-7 8.00E+00 1.40E+0I 5.1 0E+0I MS 45 L7204-02 3/31/2004 Ce-141 -2.70E+00 3.10E+00 1.1OE+01 MS 45 L7204-02 3/31/2004 Ce-144 4.00E-+O0 l.OOE+0O 3.60E+01 MS 45 L7204-02 3/31/2004 Co-57 0.OOE+00 1.30E+00 4.60E+00 MS 45 L7204-02 3/31/2004 Co-58 2.20E+00 2.OOE+00 6.90E+00 MS 45 L7204-02 3/31/2004 Co-60 4.00E+00 2.10E+0O 6.60E+00 MS 45 L7204-02 3/31/2004 Cs-134 -2.70E1+O0 1.70E+00 7.30E+00 MS 45 L7204-02 3/31/2004 Cs-137 1.39E+0I 2.90E+O0 7.80E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-22
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
MS 45 L7204-02 3/31/2004 Fe-59 1.17E+01 6.OOE+00 1.90E+01 MS 45 L7204-02 3/31/2004 1-131 5.60E+00 3.50E+00 1.20E+01 MS 45 L7204-02 3/31/2004 K-40 1.49E+03 8.30E+01 7.70E1+OI
- MS 45 L7204-02 3/31/2004 La-140 -4.00E-0O 3.20E+00 1.30E+01 MS 45 L7204-02 3/31/2004 Mn-54 9.00E-0O 1.70E+00 6.20E+00 MS 45 L7204-02 3/31/2004 Nb-95 3.30E+00 2.40E+00 7.90E+00 MS 45 L7204-02 3/31/2004 Ru-103 -3.40E+00 2.OOE+00 8.1OE+00 MS 45 L7204-02 3/31/2004 Ru-106 -2.00EOOE0 1.40E+0O 5.20E+01 MS 45 L7204-02 3/31/2004 Sb-124 -1.20E+00 3.70E+00 1.60E+01 MS 45 L7204-02 3/31/2004 Zn-65 8.30E+O0 4.80E+00 1.60E+0O MS 45 L7204-02 3/31/2004 Zr-95 2.20E+00 3.20E+00 l.lOE+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Mlinimum Detectable Concentration > Lower Limit of Detection Requirement C-23
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE I"ND CONC STD.DEV. MDC TYPE STATION LSN D'ATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
SEI L7263-01 4j/19/2004 AcTh-228 1.30E+03 1.101O+02 4.00E+02 SEI L7263-01 4, /19/2004 Be-7 -3.40E+02 2.60E+02 9.80E+02 SEI L7263-01 4,'19/2004 Co-58 3.40E+01 2.902+01 1.00E+02 SEI L7263-01 4,19/2004 Co-60 -1.00E+00 2.20E+01 8.70E+01 SEI L7263-01 4d '19/2004 Cs-134 - 1.80E+01 2.40E+01 8.80E+01 SEI L7263-01 4d'19/2004 Cs-137 2.65E+02 4.20E+01 1.E10+02 SEI L7263-01 4d '19/2004 K40 2.19E+04 1.002+03 1.00E+03 SEI L8342-01 10, 26/2004 AcTb-228 7.23E+02 4.702+01 1.50E+02 SEI L8342-01 I 0,'26/2004 Be-7 3.80E+01 9.30E+01 3.20E+02 SEI L8342-01 10,/26/2004 Co-58 -7.30E+00 9.70E+00 3.60E+01 SEI L8342-01 10,n6/2004 Co-60 2.00E+00 1.002+01 3.80E+01 SEI L8342-01 10,'26/2004 Cs-134 1.70E+00 9.20E+00 3.20E+01 SEI L8342-01 I Oi'26/2004 Cs-137 2.50E+0O 1.302+01 4.40E+01 SEI L8342-01 10,/26/2004 K-40 1.07E+04 4.20E+02 3.90E+02 SEI L7263-04 4~ /21/2004 AcTh-228 8.27E+02 7.30E+01 2.40E+02 SEI L7263-04 4~ /21/2004 Be-7 3.002+01 1.60E+02 5.60E+02 SEI L7263-04 4, /21/2004 Co-58 -3.60+01I 1.80E+01 7.10E+0I SEI L7263-04 4)'21/2004 Co-60 1.40E+01 1.702+01 5.90E+01 SEI L7263-04 4j'21/2004 Cs-134 5.20E+01 1.902+01 6.002+01 SEI L7263-04 4j '21/2004 Cs-137 2.25E+02 2.70E+01 6.50E+01 SEI L7263-04 4j'21/2004 K40 1.792+04 6.602+02 4.50E+02 SEI L8342-04 I Oi'6/2004 AcTh-228 5.69E+02 4.90E+01 1.50+02 SEI L8342-04 I Oi'26/2004 Be-7 2.30E+02 1.102+02 3.60E+02 SEI L8342-04 l0i'26/2004 Co-58 -1.40E+01 1.302+01 4.70E+01 SEI L8342-04 IOi'6/2004 Co-60 4.00E+00 1.102+01 4.00E+01 SEI L8342-04 IOi26/2004 Cs-134 l .00+01 4.102+01 1.402+02 SEI L8342-04 l0)'26/2004 Cs-137 2.33E+02 2.102+01 4.80E+01 SEI L8342-04 IOd 26/2004 K40 1.54E+04 4.80E+02 4.30E+02 SEI L7263-07 4, 21/2004 AcTh-228 2.22E+03 1.60E+02 5.40E+02 SEI L7263-07 4,/21/2004 Be-7 6.50E+02 3.50E+02 1.I 0.+03 SEI L7263-07 4)/21/2004 Co-58 4.102+0I 4.00E+01 1.40E+02 SEI L7263-07 4, 21/2004 Co-60 5.00E+00 3.90E+01 1.40E+02 SEI L7263-07 4,/21/2004 Cs-134 9.50E+01 4.20E+01 1.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-24
Yankee Nuclear Power Station Radiological Environmental Monitoring Program
-Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
SEI 91 L7263-07 4/21/2004 Cs-137 8.36E+02 7.20E+01 1.60E+02
- SEI 91 L7263-07 4/21/2004 K40 2.42E+04 1.20E+03 1.40E+03
- SEI 91 L8342-07 10/26/2004 AcTh-228 2.1 8E+03 1.50E+02 5.OOE+02
- SEI 91 L8342-07 10/26/2004 Be-7 -7.OOE+OI 3.OOE+02 1.IOE+03 SEI 91 L8342-07 10/26/2004 Co-58 -5.OOE+O0 3.30E+01 1.20E+02 SEI 91 L8342-07 10/26/2004 Co-60 -1.20E+O1 3.30E+01 1.30E+02 SEI 91 L8342-07 10/26/2004 Cs-134 -8.00E+01 3.50E+01 1.30E+02 SEI 91 L8342-07 10/26/2004 Cs-137 1.36E+03 7.80E+01 1.40E+02
- SEI 91 L8342-07 10/26/2004 K40 2.64E+04 1.20E+03 1.30E+03 *
- Radioactivily detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-25
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
SE2 L7263-02 4119/2004 AcTh-228 8.92E+02 9.00E+01 3.50E+02 SE2 L7263-02 4/19/2004 Be-7 -4.30E+02 2.00E+02 7.90E+02 SE2 L7263-02 4119/2004 Co-58 -7.20E+01 2.80E+01 1.20E+02 SE2 L7263-02 4119/2004 Co-60 -1.40E+01 1.90E+01 8.00E+01 SE2 L7263-02 4119/2004 Cs-134 2.00E+00 1.60E+01 5.90E+01 SE2 L7263-02 4/19/2004 Cs-137 1.95E+02 3.50E+01 9.20E+01 SE2 L7263-02 4/19/2004 K-40 1.81E+04 9.002+02 6.90E+02 SE2 L8342-02 10/26/2004 Ac~h-228 S.50E+02 5.102+0I 1.802+02 SE2 L8342-02 10o2612004 Be-7 6.00E+01 1.002+02 3.50E+02 SE2 L8342-02 10/26/2004 Co-58 -8.002-01 9.70E+00 3.70E+01 SE2 L8342-02 10/26/2004 Co-60 -1.30E+01 1.30E+01 5.10E+01 SE2 L8342-02 10/26/2004 Cs-134 2.40E+01 1.002+01 3.10E+01 SE2 L8342-02 10/26/2004 Cs-137 1.90E+01 1.202+01 4.00E+01 SE2 L8342-02 10/26/2004 K-40 1.09E+04 4.90E+02 3.80E+02 SE2 L7263-05 4/21/2004 AcTh-228 5.32E+02 7.70E+01 3.00E+02 SE2 L7263-05 4/21/2004 Be-7 -1.90E+02 1.60E+02 6.30E+02 SE2 L7263-05 4/21/2004 Co-58 -5.00E+00 1.902+01 7.30E+01 SE2 L7263-05 4/21/2004 Co-60 1.70E+01 1.802+01 6.30E+01 SE2 L7263-05 4/21/2004 Cs-134 -2.50E+01 1.502+01 5.90E+01 SE2 L7263-05 4/21/2004 Cs-137 8.30E+01 2.80E+01 8.40E+01 SE2 L7263-05 4/21/2004 K-40 1.69E+04 7.80E+02 6.20E+02 SE2 L8342-05 10/26/2004 AcTb-228 4.21E+02 2.00E+01 7.20E+01 SE2 L8342-05 10/26/2004 Be-7 1.50+01 4.20E+01 1.402+02 SE2 L8342-05 10/26/2004 Co-58 -1.58E+01 5.50E+00 2.00E+01 SE2 L8342-05 10/26/2004 Co-60 1.27E+01 5.40E+00 1.70E+01 SE2 L8342-05 10/26/2004 Cs-134 -3.60E+00 4.80E+00 1.702+01 SE2 L8342-05 10/26/2004 Cs-137 2.78E+02 1.10+01 2.00E+01 SE2 L8342-05 10/26/2004 K-40 1.33E+04 2.30E+02 1.70E+02 SE2 L7263-08 4/21/2004 AcTh-228 2.05E+03 1.60E+02 5.402+02 SE2 L7263-08 4/21/2004 Be-7 4.40E+02 3.40E+02 1.I0.+03 SE2 L7263-08 4/21/2004 Co-5 8 -5.90E+01 3.40E+01 1.302+02 SE2 L7263-08 4/21/2004 Co-60 -5.40E+01 2.80E+01 1.20E+02 SE2 L7263-08 4/21/2004 Cs-134 4.00E+01 3.80E+01 1.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-26
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
SE2 91 L7263-08 4121/2004 Cs-137 1.03E+03 7.40E1+01 1.50E+02
- SE2 91 L7263-08 4/21/2004 K40 2.48E+04 1.2013+03 1.3013+03
- SE2 91 L8342-08 10/26/2004 AcTh-228 2.03E+03 1.20E+02 3.50E+02
- SE2 91 L8342-08 10126/2004 Be-7 -2.70E+02 3.00E+02 I.lOE+03 SE2 91 L8342-08 10/26/2004 Co-58 2.1OE+0O 2.8013+01 9.7013+01 SE2 91 L8342-08 10/26/2004 Co-60 -1.40E+01 2.80E+01 1.1013+02 SE2 91 L8342-08 10/26/2004 Cs-134 -1.60E+0O 2.8013+01 I.0013+02 SE2 91 L8342-08 10/26/2004 Cs-137 1.lOE+03 6.4013+01 1.2013+02
- SE2 91 L8342-08 10/26/2004 K.40 2.33E+04 l.0013+03 1.3013+03 *
- Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)
+ Minimum Dctectable Concentration > Lower Lnimit of Detection Requirement C-27
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCilkg) (pCilkg) (pCi/kg)
SE3 L7263-03 4/19/2004 AcTh-228 9.20E+02 I.00E+02 3.00E+02 SE3 L7263-03 4/19/2004 Be-7 I.00E+02 2.10E+02 7.30E+02 SE3 L7263-03 4119/2004 Co-58 -1.90E+01 2.30E+01 9.1 0E+0I SE3 L7263-03 4/19/2004 Co-60 9.00E+00 2.10E+01 7.70E+01 SE3 L7263-03 4119/2004 Cs-134 2.50E+01 2.50E+01 8.40E+01 SE3 L7263-03 4/19/2004 Cs-137 2.58E+02 3.90E+01 9.60E+0I SE3 L7263-03 4119/2004 K-40 1.74E+04 9. 10E+02 8.40E+02 SE3 L8342-03 10o26/2004 AcTh-228 5.67E+02 5.30E+01 1.60E+02 SE3 L8342-03 10/26/2004 Be-7 -1.50E+02 1.lOE+02 4.00E+02 SE3 L8342-03 10/26/2004 Co-58 1.50E+01 1.20E+01 4.10E+0I SE3 L8342-03 10/26n2004 Co-60 -2.00E+00 1.20E+01 4.60E+0I SE3 L8342-03 10o26/2004 Cs-134 -2.3 1E+OI 9.80E+00 4.00E+01 SE3 L8342-03 10/26/2004 Cs-137 -1.60E+01 1.20E+01 4.70E+01 SE3 L8342-03 10/26/2004 K-40 9.67E+03 4.60E+02 4.50E+02 SE3 L7263-06 4121/2004 AcTh-228 8.57E+02 8.60E+01 3.00E+02 SE3 L7263-06 4121/2004 Be-7 -4.1OE+02 1.80E+02 7.40E+02 SE3 L7263-06 4121/2004 Co-58 4.00E+00 2.00E+01 7.50E+01 SE3 L7263-06 4/21/2004 Co-60 0.00E+00 I.90E+01 7.50E+01 SE3 L7263-06 4/21/2004 Cs-134 -1.90E+01 1.20E+01 5.20E+01 SE3 L7263-06 4/21/2004 Cs-137 6.30E+01 3.10E+01 9.90E+01 SE3 L7263-06 4/21/2004 K-40 1.60E+04 8.60E+02 7.70E+02 SE3 L8342-06 10/26/2004 AcTh-228 3.72E+02 4.80E+01 1.90E+02 SE3 L8342-06 10/26/2004 Be-7 4.60E+01 9.50E+0I 3.30E+02 SE3 L8342-06 10/26/2004 CO-58 -6.00E+00 1.20E+01 4.40E+01 SE3 L8342-06 10/26/2004 Co-60 2.60E+01 l.00OE+01 3.00E+0O SE3 L8342-06 10/26/2004 Cs-134 -8.60E+00 9.60E+00 3.60E+01 SE3 L8342-06 10/26/2004 Cs-137 1.26E+02 1.90E+01 4.90E1+0I SE3 L8342-06 10/26/2004 K-40 1.35E+04 5.10E+02 4.40E+02 SE3 L7263-09 4/21/2004 AcTh-228 1.65E+03 1.60E+02 4.20E+02 SE3 L7263-09 4/21/2004 Be-7 2.60E+02 3.60E+02 1.30E+03 SE3 L7263-09 4/21/2004 Co-58 6.00E+00 3.70E+01 1.40E+02 SE3 L7263-09 4/21/2004 Co-60 O.OOE+00 3.30E+01 1.30E+02 SE3 L7263-09 4/21/2004 Cs-134 1.30E+01 2.90E3+01 1.OOE+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-28
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
SE3 91 L7263-09 4121/2004 Cs-137 9.80E+02 8.OOE+01 1.40E+02
- SE3 91 L7263-09 4/21/2004 K-40 2.47E+04 1.40E+03 I.50E+03
- SE3 91 L8342-09 10/26/2004 AcTh-228 1.72E+03 I.IOE+02 4.OOE+02
- SE3 91 L8342-09 10/26/2004 Be-7 7.70E+02 2.70E+02 8.40E+02 SE3 91 L8342-09 10/26/2004 Co-58 -2.70E+01 2.70E+01 9.90E+01 SE3 91 L8342-09 10/26/2004 Co-60 4.30E+01 3.10E+01 1.OOE+02 SE3 91 L8342-09 10/26/2004 Cs-134 -2.20E+01 2.50E+01 8.90E+01 SE3 91 L8342-09 10/26/2004 Cs-137 1.31E+03 6.60E+01 1.20E+02 SE3 91 L8342-09 10/26/2004 K-40 2.50E+04 9.70E+02 1.20E+03 C-29
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
TF L8057-01 9/14/2004 AcTh-228 -2.40E+01 3.10E+0I 1.20E+02 TF L8057-01 9/14/2004 Be-7 -7.40E+01 6.20E+01 2.40E+02 TF L8057-01 9/14/2004 Co-58 -4.80E+00 6.50E+00 2.602+01 TF L8057-01 9/14/2004 Co-60 -1.28E+01 8.80E+00 3.70E+01 TF L8057-01 9/14/2004 Cs-134 -1.48E+01 7.80E+00 3.302+01 TF L8057-01 9/1412004 Cs-137 -1.77E+01 8.00E+00 3.30E+01 TF L8057-01 9/14/2004 K-40 9.80E+02 1.60E+02 3.40E+02 TF L8057-02 9/14/2004 AcTh-228 l.00E+01 3. 10E+0I 1. 1OE+02 TF L8057-02 9/14/2004 Ag-I lOm -8.00E+00 1.00+01 4.102+01 TF L8057-02 9/14/2004 Ba-140 -3.00E+00 1.002+01 4.50E+01 TF L8057-02 9114/2004 Be-7 1.43E+02 7.90E+01 2.60E+02 TF L8057-02 9/14/2004 Ce-141 -2.33E+01 9. 102+00 3.60E+01 TF L8057-02 9/14/2004 Ce- 144 1.70E+01 3.30E+01 1.102+02 TF L8057-02 9/14/2004 Co-57 -2.30E+00 3.80E+00 1.402+01 TF L8057-02 9/14/2004 Co-58 4.60E+00 8.102+00 2.90E+01 TF L8057-02 9/14/2004 Co-60 2.60E+01 1.202+01 3.502+01 TF L8057-02 9/14/2004 Cs-134 -9.1 OE+00 9.50E+00 3.80E+01 TF L8057-02 9/14/2004 Cs-137 -2.60E+00 7.90E+00 3.00E+01 TF L8057-02 9/14/2004 Fe-59 -1.OOE+01 3. 102+0I 1.202+02 TF L8057-02 9/14/2004 1-131 -1.50E+01 1. 10+01I 4.302+01 1F L8057-02 9/14/2004 K-40 5.52E+03 3.70E+02 5.40E+02 TF L8057-02 9/14/2004 La-140 -4.OOE+00 1.20E+01 5.20E+01 TF L8057-02 9/14/2004 Mrn-54 1.08E+01 7.40E+00 2.50E+01 TF L8057-02 9/14/2004 Nb-95 -3.80E+01 1.102+01 4.90E+01
'IT L8057-02 9/14/2004 Ru-103 3.40E+00 8.202+00 2.90E+01 TF L8057-02 9/14/2004 Ru-106 1.lOE+01 6.30E+01 2.30E+02 TF L8057-02 9/14/2004 Sb-124 O.OOE+00 1.80E+01 7.70E+01 TF L8057-02 9/14/2004 Zn-65 1.20E+01 4.60E+01 1.602+02 TF L8057-02 9/14/2004 Zr-95 -2.40E+OI 2.00E+01 7.602+01 TF L8057-03 9/14/2004 AcTh-228 -3.90E+01 3.00E+01 1.20E+02 TF L8057-03 9114/2004 Ag-l Orm 7.60E+00 9.302+00 3.30E+01 TF L8057-03 9114/2004 Ba-140 -2.23E+01 9.502+00 5.OOE+01 TF L8057-03 9/14/2004 Be-7 -4.20E+01 6.00E+01 2.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-30
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
TF 21 L8057-03 9114/2004 Ce-141 1.90E+00 8.80E+00 3.1013+0I TF 21 L8057-03 9/14/2004 Cc-144 2.7013+01 3.4013+01 1.20E+02 TF 21 L8057-03 9/1412004 Co-57 -5.90E+00 3.80E+00 1.50E+01 TF 21 L8057-03 9/14/2004 Co-58 -6.30E+00 7.0013+00 2.90E+0O TF 21 L8057-03 9/14/2004 Co-6 1.0013+01 9.50E+00 3.3013+01 TF 21 L8057-03 9/14/2004 Cs-134 -2.70E+00 7.40E+00 2.9013+01 TF 21 L8057-03 9/14/2004 Cs-137 -8.80E+00 7.90E+00 3.10E+01 TF 21 L8057-03 9/14/2004 Fe-59 1.00E+00 1.9013+01 7.50E+01 TF 21 L8057-03 9/14/2004 1-131 3.00E+00 l.l1OE+01 4.00E+01 9/14/2004 K-40 1.8913+03 2.20E+02
- TF 21 L8057-03 4.30E+02 TF 21 L8057-03 9/14/2004 La-140 -2.6013+01 1.13OE+0I 5.80E+01 TF 21 L8057-03 9/14/2004 Mn-54 -1.21 E+OI 6.80E+00 2.9013+01 TF 21 L8057-03 9/14/2004 Nb-95 -2.00E-01 8.60E+00 3.2013+01 21 L8057-03 9/14/2004 Ru-1 03 2.1OE+00 7.0013+00 2.50E+01 TF 21 L8057-03 9/14/2004 Ru-106 1.20E+02 7.00E+0O 2.30E+02 TF 21 L8057-03 9/14/2004 Sb-124 5.0013+00 2.10E+0O 8.00E+01 TF 21 L8057-03 9/14/2004 Zn-65 -3.00E+0O 1.90E+01 7.9013+01 TF 21 L8057-03 9/14/2004 Zr-95 0.00E+00 1.20E+01 4.7013+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-31
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/lkg)
WG 11 L6910-05 1/30/2004 Ba-140 1.90E+00 2.40E+00 8.502+00 WG 11 L6910-05 1/30/2004 Co-58 -3.10E-01 9.602-01 3.70E+00 WG 11 L6910-05 1/30/2004 Co-60 9.20E-01 8.10E-01 2.80E+00 WG II L6910-05 1/30/2004 Cs-134 7.70E-01 9.40E-01 3.30E+00 WG 11 L6910-05 1/30/2004 Cs-137 1.14E+00 9.90E-01 3.40E+00 WG 11 L6910-05 1/30/2004 Fe-59 -7.90E+00 2.80E+00 1.302+01 WG II L6910-05 1/30/2004 GROSS BETA 3.682+00 9.902-01 2.80E+00 WG 11 L6910-05 1/30/2004 H-3 2.14E+02 8.70E+01 2.70E+02 WG 11 L6910-05 1/30/2004 1-131 -6.40E+00 3.80E+O0 1.50E+01 WG 11 L6910-05 1/30/2004 Mn-54 6.OE-01 1.0OOE+O0 3.702+00 WG II L6910-05 1/30/2004 Zn-65 -3.00E-01 3.10E+00 1.102+01 WG 11 L6910-05 1/30/2004 Zr-95 1.40E+00 1.70E+00 5.902+00 WG 11 L6992-04 2/25/2004 Ba-140 3.30E+00 6.70E+00 2.50E+01 WG 11 L6992-04 2/25/2004 Co-58 2.00E+00 1 30E+00 4.40E+00 WG 11 L6992-04 2/25/2004 Co-60 -3.002-01 1.40E+00 5.90E+00 WG 11 L6992-04 2125/2004 Cs-134 1.50E+00 1.40E+00 4.80E+00 WG 11 L6992-04 2/25/2004 Cs-137 -7.002-01 1.60E+00 6.00E+O0 WG 11 L6992-04 2/25/2004 Fe-59 -6.20E+00 4.10E+00 2.002+01 WG 11 L6992-04 2/25/2004 GROSS BETA 3.44E+00 9.702-01 2.80E+00 WG 11 L6992-04 2/25/2004 H-3 7.90E+01 9.1 0E+01 2.90E+02 WG 11 L6992-04 2/25/2004 1-131 -3.00E+00 1.302+01 4.70E+01 WG 11 L6992-04 2/25/2004 Mn-54 -L.10E+00 1.50E+00 5.90E+00 WG 11 L6992-04 2/25/2004 Zn-65 1.042+01 6.30E+00 2.10E+01 WG 11 L6992-04 2/25/2004 Zr-95 2.20E+00 3.IE+00 1.10EE+01 WG II L7175-04 3/29/2004 Ba-140 -5.201+00 4.50E+00 2.10E+01 WG 11 L7175-04 3/29/2004 Co-58 -9.001-01 2.40E+00 9.30E+00 WG 11 L7175-04 3/29/2004 Co-60 -1.20E+00 2.40E+00 1.OOE+01 WG 11 L7175-04 3/29/2004 Cs-134 -1.60E+00 2.00E+00 8.30E+00 WG 11 L7175-04 3/29/2004 Cs-137 -2.30E+00 1.80E+00 7.80E+00 WG 11 L7175-04 3/29/2004 Fe-59 2.00E-01 6.702+00 2.60E+01 WG 11 L7175-04 3/29/2004 GROSS BETA 2.80E+00 1.002+00 3.10E+00 WG 11 L7175-04 3/29/2004 H-3 0.00E+00 1.I1OE+02 3.502+02 WG 11 L7175-04 3/29/2004 1-131 2.80E+00 4.802+00 1.70E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-32
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG II L7175-04 3/2912004 Mn-54 -6.00E-Ol 1.902+00 7.50E+00 WG II L7175-04 3/29/2004 Zn-65 -2.10E+00 5.lOE+O0 2.00E+01 WG 11 L7175-04 3/2912004 Zr-95 3.70E+00 3.70E+00 1.30E+01 WG II L7341-04 4/26/2004 Ba-140 -6.10E+00 4.80E+O0 2.30E+01 WG II L7341-04 412612004 Co-58 1.OOE+00 2.00E+00 7.60E+00 WG II L7341-04 4/26/2004 Co-60 3.002-01 2.202+00 8.80E+00 WG 11 L7341-04 4/26/2004 Cs-134 -6.00E-01 1.70E+00 7.30E+00 WG II L7341-04 4/26/2004 Cs-137 -1.20E+00 2.10E+00 8.70E+00 WG 11 L7341-04 4/26/2004 Fe-59 4.801+00 6.60E+00 2.50E+01 WG II L7341-04 4/26/2004 GROSS BETA 1.522+00 9.40E-01 3.10E+00 WG 11 L7341-04 4/26/2004 H-3 -7.00E+01 L.IOE+02 3.30E+02 WG II L7341-04 4/26/2004 1-131 -L.90E+00 5.IOE+00 2.001+01 WG 11 L7341-04 4/26/2004 Mn-54 2.30E+00 1.902+00 6.60E+00 WG 11 L7341-04 4/26/2004 Zn-65 -7.20E+00 3.80E+00 1.90E+01 WG II L7341-04 4/26/2004 Zr-95 1.60E+00 3.10E+00 1.20E+O1 WG 11 L7471-04 5/25/2004 Ba.140 -3.40E+00 5.802+00 2.502+01 WG 11 L7471-04 5/25/2004 Co-58 -2.20E+00 1.903E+00 8.80E+00 WG II L7471-04 5/25/2004 Co-60 5.002-01 2.10E+00 8.601+00 WG 11 L7471-04 5/25/2004 Cs-134 -8.001-01 1.50L+00 7.00E+00 WG II L7471-04 5/25/2004 Cs-137 -3.00E-01 2.40E+00 9.50E+00 WG II L7471-04 5/25/2004 Fe-59 1.02E+0I 5.60E+00 1.60E+01 WG 11 L7471-04 5/25/2004 GROSS BETA 1.52E+00 9.201-01 3.00E+00 WG II L7471-04 5/25/2004 H-3 -3.002+01 1.30E+02 4.00E+02 WG II L7471-04 5/25/2004 1-131 2.10E+00 6.60E+00 2.40E+01 WG 11 L7471-04 5/25/2004 Mn-54 2.OOE+00 1.90E+00 6.801+00 WG 11 L7471-04 5/25/2004 Zn-65 -4.00E+00 4.801+00 2.10E+01 WG II L7471-04 5/25/2004 Zr-95 -1.10+00 3.202+00 1.40E+01 WG 11 L7611-04 6/23/2004 Ba-140 3.30E+00 3.70E+00 1.302+01 WG 11 L7611-04 6/23/2004 Co-58 9.001-01 1.901E+00 6.801+00 WG II L7611-04 6/23/2004 Co-60 1.30E+00 L.80E+00 6.60E+00 WG II L7611-04 6/23/2004 Cs-134 6.002-01 1.80E+00 6.70E+00 WG II L7611-04 6/23/2004 Cs-137 -3.002-01 1.503+00 5.80E+00 WG II L7611-04 6/23/2004 Fe-59 4.10E+00 6.00E+00 2.20E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-33
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG 11 L7611-04 6/23/2004 GROSS BETA 2.36E+00 9.80E-01 3.00E+00 WG 11 L7611-04 6/23/2004 H-3 2.68E+02 9.90E+01 3.00E+02 WG 11 L7611-04 6/23/2004 1-131 2.00E+00 4.20E+00 1.50E+01 WG 11 L7611-04 6/23/2004 Mn-54 -3.00E-01 1.80E+00 6.80E+00 WG 11 L7611-04 6/23/2004 Zn-65 0.OOE+00 2.40E+00 1.00E+01 WG 11 L7611-04 6/23/2004 Zr-95 6.80E+00 3.50E+00 1.I1E+01 WG 11 L7643-04 6/28/2004 Ba-140 -2.70E+00 2.90E+00 1.20E+01 WG II L7643-04 6/28/2004 Co-58 -6.00E-01 1.50E+00 6.00E+00 WG 11 L7643-04 6/28/2004 Co-60 3.20E+00 2.20E+00 7.30E+00 WG 11 L7643-04 6/28/2004 Cs-134 -2.00E-+00 2.20E+00 8.80E+00 WG 11 L7643-04 6/28/2004 Cs-137 -1.70E+00 2.10E+00 8.00E+00 WG 11 L7643-04 6/28/2004 Fe-59 1.60E+01 5.50E+00 1.50E+01 WG 11 L7643-04 6/28/2004 GROSS BETA 2.11 E+00 9.90E-01 3.20E+00 WG 11 L7643-04 6/28/2004 H-3 3.00E+01 1.001E+02 3.20E1+02 WG 11 L7643-04 6/28/2004 1-131 -3.00E-01 3.50E+00 1.30E+01 WG 11 L7643-04 6/28/2004 Mn-54 2.40E+00 1.70E+00 5.60E+00 WG 11 L7643-04 6/28/2004 Zn-65 -6.90E+00 4.40E+00 1.80E+01 WG 11 L7643-04 6/28/2004 Zr-95 1.60E+00 3.20E+00 1.10E+01 WG II L7840-04 7/29/2004 Ba-140 -1.30E+00 3.80E+00 1.70E+01 WG II L7840-04 7/29/2004 Co-58 1.001E-01 1.80E+00 7.10E+00 WG II L7840-04 7/29/2004 Co-60 1.80E+00 2.50E+00 9.00E+00 WG 11 L7840-04 7/29/2004 Cs-134 6.00E-01 1.90E+00 7.30E+00 WG II L7840-04 7/29/2004 Cs-137 -1.30E+00 1.70E+00 7.20E+00 WG 11 L7840-04 7/29/2004 Fe-59 1.25E+01 6.40E+00 1.90E+01 WG 11 L7840-04 7/29/2004 GROSS BETA 3.20E+00 1.00E+00 3.10E+00 t WG 11 L7840-04 7/29/2004 H-3 -2.50E+02 1.30E+02 3.90E+02 WG 11 L7840-04 7/29/2004 1-131 1.40E+00 3.20E+00 1.20E+01 WG 11 L7840-04 7n29/2004 Mn-54 -3.60E+00 2.10E+00 9.20E+00 WG 11 L7840-04 7/29/2004 Zn-65 -2.30E+00 3.30E+00 1.501E+01 WG 11 L7840-04 7/29/2004 Zr-95 -3.60E+00 3.30E+00 1.50E+01 WG II L7980-04 8/27/2004 Ba-140 -2.80E-01 9.00E-01 3.10E+00 WG 11 L7980-04 8/27/2004 Co-58 -1.64E+00 5.10E-01 1.90E+00 WG 11 L7980-04 8/27/2004 Co-60 9.20E-01 4.60E-01 1.50E+00
- Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)
+ Nlinimum Detectable Concentration > Lower Limit of Detection Requirement C-34
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG L7980-04 8/27/2004 Cs-134 2.40E-01 5.102-01 1.70E+00 WG L7980-04 8/27/2004 Cs-137 -3.90E-01 7.501-01 2.50E+00 WG L7980-04 8/27/2004 Fc-59 -1.30E+00 1.302+00 4.80E+00 WG L7980-04 8/27/2004 GROSS BETA 4.90E+00 1.102+00 2.90E+00 WG L7980-04 8/27/2004 H-3 -3.00E+01 1.102+02 3.30E+02 WG L7980-04 8/27/2004 1-131 -1.00E-01 1.40E+00 4.60E+00 WG L7980-04 8/27/2004 Mn-54 -5.902-01 4.402-01 1.60E+00 WG L7980-04 8/27/2004 Zn-65 4.00E+00 2.302+00 7.40E+00 WG L7980-04 8/27/2004 Zr-95 -4.401-01 8.302-01 2.90E+00 WG L8121 -01 9/2212004 Ba-140 1.30E+00 4.30E+00 1.70E+01 WG L8121-01 9/22s2004 Co-58 -2.20E+00 2. 1OE+00 8.90E+00 WG L8121 -01 9/22/2004 Co-60 -1.80+00 1.902+00 8.80E+00 WG L8121 -01 9/2212004 Cs-134 1.40E+00 2.30E+00 8.30E+00 WG L8121-01 9/22/2004 Cs-137 0.00+00 1.802+00 7.10E+00 WG L8121 -01 9/22/2004 Fc-59 -2.60E+00 5.002+00 2.30E+01 WG L18121-01 9/22/2004 GROSS BETA 3. IOE+00 1.1 OE+00 3.202+00 WG L8121 -01 9/22/2004 H-3 -3.002+01 1.002+02 3.30E+02 WG L8121 -01 9/22/2004 1-131 4.002-01 4.402+00 1.60E+01 WG L8121 -01 9/22/2004 Mn-54 -4.002-01 2.30E+00 9.10E+00 WG L8121 -01 9/22/2004 Zn-65 -4.60E+00 4.80E+00 2. 10E+OI WG L8121 -01 9/22/2004 Zr-95 -3.002-01 3.702+00 1.50E+01 WG L8352-04 10/27/2004 Ba-140 -1.30E+00 2.30E+00 9.10E+00 WG L8352-04 10/27/2004 Co-58 -2.50E+00 1.50+00 6.10E+00 WG L8352-04 10/27/2004 Co-60 2.901+00 1.70E+00 5.502+00 WG L8352-04 10/27/2004 Cs-134 1.80E+00 1.602+00 5.30E+00 WG L8352-04 10/27/2004 Cs-137 -2.00E+00 1.502+00 5.80E+00 WG L8352-04 10/27/2004 Fe-59 4.002-01 3.60E+00 1.40E+01 WG L8352-04 10/27/2004 GROSS BETA 3. 10E+00 1.00E+00 3.10E+00 WG L8352-04 10/27/2004 H1-3 4.002+01 1.00E+02 3.30E+02 WG L8352-04 10/27/2004 1-131 -8.003-01 3.1 OE+00 1.I02+0I WG L8352-04 10/27/2004 Mn-54 -3.40E+00 1.602+00 6.40E+00 WG L8352-04 10/27/2004 Zn-65 1.1012+01 7.90E+00 2.60E+01 WG L8352-04 10/27/2004 Zr-95 3.70E+00 3.30E+00 1.1 0E+0 I
- Radioactivity detected in sample (i.e, concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-35
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG 11 L8484-04 11/23/2004 Ba-140 -1.1OE+00 4.40E+00 2.00E+01 WG 11 L8484-04 11/23/2004 Co-58 -2.40E+00 3.00E+00 1.20E+01 WG 11 L8484-04 11/23/2004 Co-60 1.80E+00 3.60E+00 1.30E+01 WG 11 L8484-04 11/23/2004 Cs-134 -5.00E-01 2.20E+00 9.10E+00 WG 11 L8484-04 11/23/2004 Cs-137 -2.40E+00 2.20E+00 9.50E+00 WG 11 L8484-04 11/23/2004 Fe-59 0.00E+00 8.50E+00 3.40E+01 WG 11 L8484-04 11/23/2004 GROSS BETA 4.60E+00 1.20E+00 3.30E+00 WG 11 L8484-04 11/23/2004 H-3 -3.002+01 1.00E+02 3.30E+02 WG 11 L8484-04 11/23/2004 1-131 3.002-01 4.90E+00 1.90E+01 WG 11 L8484-04 11/23/2004 Mn-54 -1.40E+00 1.30E+00 6.80E+00 WG II L8484-04 11/23/2004 Zn-65 -1.17E+01 6.50E+00 2.90E+01 WG II L8484-04 11/23/2004 Zr-95 2.50E+00 3.80E+00 1.40E+01 WG 12 L6910-06 1/30/2004 Ba-140 -2.10E+00 4.102+00 1.70E+01 WG 12 L6910-06 1/30/2004 Co-58 1.002-01 1.70E+00 6.30E+00 WG 12 L6910-06 1/3012004 Co-60 -1.80E+00 1.90E+00 7.80E+00 WG 12 L6910-06 1/30/2004 Cs-134 -9.00E-01 1.60E+00 6.40E+00 WG 12 L6910-06 1/30/2004 Cs-137 -2.10E+00 1.40E+00 6.00E+00 WG 12 L6910-06 1/30/2004 Fe-59 4.702+00 4.70E+00 1.60E+01 WG 12 L6910-06 1/30/2004 GROSS BETA 5.00E+00 1.20E+00 3.30E+00 WG 12 L6910-06 1/30/2004 H-3 1.46E+02 8.70E+01 2.70E+02 WG 12 L6910-06 1/30/2004 1-131 -8.00E-01 4.70E+00 1.802+01 WG 12 L6910-06 1/30/2004 Mn-54 -7.00E-01 1.302+00 5.202+00 WG 12 L6910-06 1/30/2004 Zn-65 1.40E+00 3.00E+00 1.10E+01 WG 12 L6910-06 1/30/2004 Zr-95 -1.60E+00 2.80E+00 1.102+01 WG 12 L6992-05 2/25/2004 Ba-140 1.74E+01 7.50E+00 2.10E+01 WG 12 L6992-05 2/25/2004 Co-58 -2.60E+00 1.80E+00 7.70E+00 WG 12 L6992-05 2/25/2004 Co-60 -4.00E-01 1.90E+00 7.60E+00 WG 12 L6992-05 2/25/2004 Cs-134 1.50E+00 1.90E+00 6.70E+00 WG 12 L6992-05 2/25/2004 Cs-137 -1.20E+00 1.40E+00 5.70E+00 WG 12 L6992-05 2/25/2004 Fe-59 -4.50E+00 6.00E+00 2.602+01 WG 12 L6992-05 2/25/2004 GROSS BETA 4.30E+00 1.20E+00 3.30E+00 WG 12 L6992-05 2/25/2004 H-3 2.24E+02 9.20E+01 2.90E+02 WG 12 L6992-05 2/25/2004 1-131 -8.00E+00 1.20E+01 4.70E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-36
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG 12 L6992-05 2125/2004 Mn-54 -8.OOE-0 1.90E+00 7.40E+00 WG 12 L6992-05 2n25/2004 Zn-65 -1.06E+01 4.40E+00 2.OOE+0O WG 12 L6992-05 2/25/2004 Zr-95 -2.1 OE+00 3.60E+00 IAOE+0O WG 12 L7175-05 3/29/2004 Ba-140 1.30E+00 4.20E+00 1.70E+0O WG 12 L7175-05 3/29/2004 Co-58 1.30E+00 1.70E+00 6.00E+00 WG 12 L7175-05 3/29/2004 Co-60 -3.40E+00 2.10E+00 9.80E+00 WG 12 L7175-05 3/29/2004 Cs-134 -1.90E+00 I.90E+00 8.20E+00 WG 12 L7175-05 3/29/2004 Cs-137 4.OOE-01 1.40E+00 5.40E+00 WG 12 L7175-05 3/29/2004 Fe-59 7.40E+00 5.50E+00 1.80E1+0I WG 12 L7175-05 3/29/2004 GROSS BETA 5.00E+00 1.20E+00 3.20E+00 WG 12 L7175-05 3/29/2004 H-3 0.OOE+00 1.1OE+02 3.50E+02 WG 12 L7175-05 3/29/2004 1-131 -1.22E+01 4.70E+00 2.IOE+01 WG 12 L7 175-05 3/29/2004 Mn-54 1.20E+00 1.60E+00 5.903E+00 WG 12 L7175-05 3/29/2004 Zn-65 3.00E+00 3.00E+00 I.10E1+0I WG 12 L7175-05 3/29/2004 Zr-95 6.OOE-01 2.40E+00 9.80E+00 WG 12 L7341-05 4/26/2004 Ba-140 -1.40E+00 4.20E+00 2.00E+0O WG 12 L7341-05 4/26/2004 Co-58 3.OOE-01 I.90E+00 7.90E+00 WG 12 L7341-05 4126/2004 Co-60 -3.1 0E+00 2.20E+00 1.20E+01 WG 12 L7341-05 4/26/2004 Cs-134 2.60E+00 1.70E+00 5.40E+00 WG 12 L7341-05 4/26/2004 Cs-137 2.30E+00 2.OOE+00 7.00E+00 WG 12 L7341-05 4/26/2004 Fe-59 -5.OOE+00 5.0OE+00 2.70E2+01 WG 12 L7341-05 4/26/2004 GROSS BETA 4.20E+00 l.lOE+00 3.20E+00 WG 12 L7341-05 4/26/2004 H-3 -1.OOE+0 1.IOE11+02 3.30E+02 WG 12 L7341-05 4/26/2004 1-131 -8.60E+00 6.70E+00 2.80E+I01 WG 12 L7341-05 4/26/2004 Mn-54 2.40E+00 1.60E+00 4.90E+00 WG 12 L7341-05 4/26/2004 Zn-65 1.60E+00 4.20E+00 1.70E+01 WG 12 L7341-05 4/26/2004 Zr-95 3.102+00 3.20E+00 1.20E+01 WG 12 L7471-05 5/25/2004 Ba-140 3.40E+00 4.802+00 1.80E+01 WG 12 L7471-05 5/25/2004 Co-58 -2.1 OE+00 2.00E+00 8.50E+00 WG 12 L7471-05 5/25/2004 Co-60 3.30E+00 2.70E+00 9. 1OE+00 WG 12 L7471-05 5/25/2004 Cs-134 -6.00E-01 2.00E-+00 8.00E+00 WG 12 L7471-05 5/25/2004 Cs-137 -8.00E-01 1.60E+00 6.60E3+00 WG 12 L7471-05 5/25/2004 Fe-59 4.90E+00 4.90E+00 1.80E+0O
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-37
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG L7471-05 5/25/2004 GROSS BETA 6.60E+00 1.30E+00 3.40E+00
- WG L7471-05 n512o004 H-3 2.60E+02 1.30E+02 4.00E+02 WG L7471-05 5/25/2004 1-131 -9.70E+00 5.30E+00 2.20E+01 WG L7471-05 5/25/2004 Mn-54 -3.OOE-01 2.00E+00 7.80E3+00 WG L7471-05 5/25/2004 Zn-65 -1.34E+01 5.40E+00 2.40E+01 WG L7471 -OS 5/25/2004 Zr-95 O.OOE+00 3.00E+00 1.20E+01 WG L761 1-05 6/23/2004 Ba-140 -1.40E+00 3.00E+00 1.50E+01 WG L7611-05 6/23/2004 Co-58 2.20E+00 1.70E+00 5.70E+00 WG L761 1-05 6/23/2004 Co-60 1.90E+00 2.1OE+00 7.70E+00 WG L761 1-05 6/23/2004 Cs-134 -4.OOE-01 1.90E+00 7.70E+00 WG L7611-05 6/23/2004 Cs-137 1.20E+00 1.80E+00 6.40E+00 WG L761 1-05 6/23/2004 Fe-59 5.30E+00 7.50E+00 2.70E+01 WG L7611-05 6/23/2004 GROSS BETA 6.OOE+00 1.20E+00 3.10E+00 t WG L761 1-05 6/23/2004 H-3 1.48E+02 9.80E+01 3.00E+02 WG L7611-05 6/23/2004 1-131 -2.70E+00 5.60E+00 2.10E+0I WG L7611-05 6/23/2004 Mn-54 -1 .30E+00 1.70E+00 7.20E+00 WG L7611-05 6/23/2004 Zn-65 -7.50E+00 3.90E+00 1.90E+0I WG L761 1-05 6/23/2004 Zr-95 -6.OOE-01 3.20E+00 1.30E+0I WG L7643-05 6/28/2004 Ba-140 -3.1OE+00 2.1OE+00 9.80E+00 WG L7643-05 6/28/2004 Co-58 -1.20E+00 1.50E+00 6.1OE+00 WG L7643-05 6/28/2004 Co-60 -3.00E-0l 1.30E+00 5.40E+00 WG L7643-05 6/28/2004 Cs-134 .80E+00 1.30E+00 4.20E+00 WG L7643-05 6/28/2004 Cs-137 -L.OOE+00 1.20E+00 5.1 OE+00 WG L7643-05 6/28/2004 Fe-59 -6.60E+00 4.20E+00 1.90E+0I WG L7643-05 6/28/2004 GROSS BETA 3.20E+00 l .IOE+00 3.30E+00 WG L7643-05 6/28/2004 H-3 1.20E+02 11.OOE+02 3.20E+02 WG L7643-05 6/28/2004 1-131 1.20E+00 2.40E+00 8.60E+00 WG L7643-05 6/28/2004 Mn-54 9.OOE-01 1.IOE+O0 4.1 OE+00 WG L7643-05 6/28/2004 Zn-65 7.00E-0l 3.1OE+00 1.20E+01 WG L7643-05 6/28/2004 Zr-95 -3.1 OE+00 2.80E+00 1. IOE+0 I WG L7840-05 7/29/2004 Ba-140 8.OOE-01 3.00E+00 1.20E+01 WG L7840-05 7/29/2004 Co-58 -2.1 OE+00 1.50E+00 6.30E+00 WG L7840-05 7/29/2004 Co-60 2.40E+00 1.50E+00 4.70E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-38
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data' SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG 12 L7840-05 7/29/2004 Cs-134 2.00E+00 1.902+00 6.40E+00 WG 12 L7840-05 7/29/2004 Cs-137 -1.50+00 1.60E+00 6.30E+00 WG 12 L7840-05 7/2912004 Fe-59 -4.60E+00 4.80E+00 2.002+01 WG 12 L7840-05 7/29/2004 GROSS BETA 5.1 0E+00 1.20E+00 3.30E+00 WG 12 L7840-05 7/29/2004 H-3 4.00E+01 1.302+02 3.902+02 WG 12 L7840-05 7/29/2004 1-131 9.00E-01 3.902+00 1.40E+O1 WG 12 L7840-05 7/29/2004 Mn-54 3.20E+00 1.60E+00 5.00E+00 WG 12 L7840-05 7/29/2004 Zn-65 2.10E+00 2.802+00 1.002+01 WG 12 L7840-05 7/29/2004 Zr-95 1.702+00 2.902+00 1.102+01 WG 12 L7980-05 8/27/2004 Ba-140 4.502+00 3.002+00 9.702+00 WG 12 L7980-05 8/27/2004 Co-58 -1.90E+00 2.002+00 8.302+00 WG 12 L7980-05 8/27/2004 Co-60 1.902+00 2.202+00 8.002+00 WG 12 L7980-05 8/27/2004 Cs-134 3.002-01 1.50+00 6.002+00 WG 12 L7980-05 8/27/2004 Cs-137 -1.IO0+00 1.902+00 7.802+00 WG 12 L7980-05 8/27/2004 Fe-59 2.30E+00 5.I10+00 2.002+01 WG 12 L7980-05 8/27/2004 GROSS BETA 6.10E+00 1.30E+00 3.40E+00 WG 12 L7980-05 8/27/2004 H-3 4.20E+02 1.1 02+02 3.30E+02 WG 12 L7980-05 8/27/2004 1-131 2.402+00 2.802+00 9.802+00 WG 12 L7980-05 8/27/2004 Mn-54 -2.60E+00 1.402+00 7.002+00 WG 12 L7980-05 8/27/2004 Zn-65 2.20E+00 3.10E+00 1.202+01 WG 12 L7980-05 8/27/2004 Zr-95 -7.80E+00 2.90E+00 1.502+01 WG 12 L8121-05 9/22/2004 Ba-140 0.00+00 2.80E+00 1.202+01 WG 12 L8121-05 9/22/2004 Co-58 -7.002-01 1.702+00 7.002+00 WG 12 L8121-05 9/22/2004 Co-60 1.302+00 1.80E+00 6.50E+00 WG 12 L8121-05 9/22/2004 Cs-134 -2.00E+00 1.70E+00 7.50E+00 WG 12 L8121-05 9/22/2004 Cs-137 3.202+00 1.40E+00 3.80E+00 WG 12 L8121-05 9/22/2004 Fe-59 -5.50E+00 4.402+00 2.1OE+01 WG 12 L8121-05 9/22/2004 GROSS BETA 9.002+00 1.402+00 3.302+00 WG 12 L8121-05 9/22/2004 H-3 3.002+02 1.IOE+02 3.30E+02 WG 12 L8121-05 9/22/2004 1-131 1.41E+01 4.80E+00 1.402+01 WG 12 L8121-05 9/22/2004 Mn-54 1.30E+00 1.80E+00 .6.502+00 WG 12 L8121-05 9/22/2004 Zn-65 -6.90E+00 3.302+00 1.602+01 WG 12 L8121-05 9/22/2004 Zr-95 -1.SOE+00 2.402+00 1.10E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit orDetection Requirement C-39
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCilkg) (pCi/kg)
WG 12 L8352-05 10/27/2004 Ba-140 3.001+00 1.50E+00 4.50E+00 WG 12 L8352-05 10/27/2004 Co-58 2.00E-O1 1.IOE+O0 4.OOE+00 WG 12 L8352-05 10/27/2004 Co-60 3.20E+00 1.40E+00 4.20E+00 WG 12 L8352-05 10/27/2004 Cs-134 -1.30E+O00 L.IOE+00 4.70E+00 WG 12 L8352-05 10/27/2004 Cs-137 -8.OOE-0 L.10E+00 4.50E+00 WG 12 L8352-05 10/27/2004 Fe-59 -3.1OE+00 3.10E+00 1.30E+01 WG 12 L8352-05 10/27/2004 GROSS BETA 7.80E+00 1.30E+00 3.20E+00 WG 12 L8352-05 10/27/2004 H-3 5.90E+02 L.10E+02 3.30E+02 WG 12 L8352-05 10/27/2004 1-131 -1.40E+00 2.20E+00 8.30E+00 WG 12 L8352-05 10/27/2004 Mn-54 2.00E+00 1.20E+00 3.80E+00 WG 12 L8352-05 10/27/2004 Zn-65 -4.80E+00 2.70E+00 1.10E+01 WG 12 L8352-05 10/27/2004 Zr-95 O.OOE+00 2.1OE+00 8.OOE+00 WG 12 L8484-05 11/2312004 Ba-140 -1.60E+00 4.30E+00 2.00E+01 WG 12 L8484-05 11123/2004 Co-58 -1.OOE-01 L.90E+00 8.OOE+00 WG 12 L8484-05 11/23/2004 Co-60 -2.70E+00 2.90E+00 1.30E+01 WG 12 L8484o05 11/23/2004 Cs-134 -1.00E-01 L.90E+00 7.70E+00 WG 12 L8484-05 11/23/2004 Cs-137 2.50E+00 2.30E+00 7.80E+00 WG 12 L8484-05 11/23/2004 Fe-59 -8.OOE-0l 5.50E+00 2.40E+01 WG 12 L8484-05 11/23/2004 GROSS BETA 6.90E+00 1.30E+00 3.30E+00 WG 12 L8484-05 11/23/2004 H-3 4.30E+02 L.IOE+02 3.30E+02 WG 12 L8484-05 11/23/2004 1-131 -1.IOE+01 5.20E+00 2.30E+01 WG 12 L8484-05 11/23/2004 Mn-54 7.00E-01 1.30E+00 5.30E+00 WG 12 L8484-05 11/23/2004 Zn-65 -1.08E+0l 3.80E+00 2.10E+01 WG 12 L8484-05 11/23/2004 Zr-95 2.00E+00 3.90E+00 1.50E+01 WG 32 L7980-06 8127/2004 Ba-140 -1.20E+00 2.70E+00 1.30E+01 WG 32 L7980-06 8/27/2004 Co-58 -5.00E-01 2.00E+00 8.50E+00 WG 32 L7980-06 8/27/2004 Co-60 O.OOE+00 2.10E+00 9.OOE+00 WG 32 L7980-06 8/27/2004 Cs-134 8.00E-01 2.40E+00 9.30E+00 WG 32 L7980-06 8/27/2004 Cs-137 O.OOE+00 2.10E+00 8.30E+00 WG 32 L7980-06 8/27/2004 Fe-59 -5.20E+00 5.50E+00 2.70E+01 WG 32 L7980-06 8/27/2004 GROSS BETA 7.20E+00 1.40E+00 3.80E+00 WG 32 L7980-06 8/27/2004 H-3 2.00E+02 1I.OE+02 3.40E+02 WG 32 L7980-06 8/27/2004 1-131 7.00E-01 2.70E+00 1.OOE+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-40
Yankec Nuclcar Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE SEND CONC STD.DEV. MDC TYPE STATION LSN D'ATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WG 32 L7980-06 8j,27/2004 Mn-54 -1.102O+00 1.90E+00 8.30E+00 WG 32 L7980-06 ,27/2004 Zn-65 -5.80E+00 5.OOE+00 2.30E+01 WG 32 L7980-06 81,27/2004 Zr-95 -8.00E-01 3.50E+00 1.50E+01 WG 51 L7471-06 '25/2004 Ba-140 0.00+00 3.90E+00 1.60E+01 5,
WG 51 L7471-06 /25/2004 Co-58 -1.402+00 1.60E+00 6.80E+00 5,
WG 51 L7471-06 /25/2004 Co-60 -3.00E-0O 1.70E+00 7.20E+00 5,
WG 51 L7471-06 '25/2004 Cs-134 -2.40E+00 1.902+00 8.00E+00 WG 51 L7471-06 /25/2004 Cs-137 3.30E+00 1.902+00 6.00E+00 5,
WG 51 L7471-06 /25/2004 Fe-59 -7.OOE-01 4.30E+00 1.80E+01 54 WG 51 L7471-06 /25/2004 GROSS BETA 1.27E+01 1.60E+00 3.40E+00
- 5j WG 51 L7471 -06 125/2004 H-3 1.402+02 1.30E+02 3.90E+02 54 WG 51 L7471-06 /25/2004 1-131 3.80E+00 5.20E+00 1.80E+01 54 WG 51 L7471-06 /25/2004 Mn-54 -1.40E+00 1.80E+00 7.30E+00 5,
WG 51 L7471-06 /25/2004 Zn-65 -8.1 OE+00 3.90E+00 1.80E+01 5j WG 51 L7471-06 /25/2004 Zr-95 -5.10+00 3.40E+00 1.50E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Iower Limit or Detection Requirement CI41
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR II L6864-01 12/29/2003 H-3 -1.20E+02 3.OOE+02 1.OOE+03 WR 11 L6910-01 1/3012004 Ba-140 -3.50E+00 2.90E+00 1.30E+O1 WR 11 L6910-01 1/30/2004 Co-58 -1.60E+00 LIOE+00 4.80E+00 WR 11 L6910-01 1/30/2004 Co-60 2.30E+00 1.20E1+00 3.80E+00 WR 11 L6910-01 1/30/2004 Cs-134 5.OOE-01 1.20E+00 4.50E+00 WR 11 L6910-01 1/3012004 Cs-137 O.OOE+00 1.20E+00 4.50E+00 WR 11 L6910-01 1/3012004 Fe-59 2.10E+00 4.20E+00 1.50E+01 WR 11 L6910-01 1/30/2004 GROSS BETA 8.90E-01 8.10E-01 2.80E+00 WR 11 L6910-01 1/30/2004 11-3 -4.00E+01 4.OOE+02 1.20E+03 WR 11 L6910-01 1/30/2004 1-131 3.10E+00 4.60E+00 1.60E+01 WR 11 1L6910-01 1/30/2004 Mn-54 6.OOE-01 1.IOE+00 3.90E+00 WR 11 1L6910-01 1/30/2004 Zn-65 O.OOE+00 2.30E+00 8.70E+00 R 11 L6910-01 1/3012004 Zr-95 O.OOE+00 2.30E+00 8.60E+00 WR 11 L6992-01 2/25/2004 Ba-140 -130E+01 6.70E+00 3.20E+01 WR 11 L.6992-01 2/25/2004 Co-58 -1IOE+00 1.80E+00 7.40E+00 WR 11 L6992-01 2/25/2004 Co-60 2.OOE+00 1.50E+00 5.00E+00 NR 11 L.6992-01 2/2512004 Cs-134 -9.OOE0-0 1.501E+00 6.20E+00 R 11 .L6992-01 2/2512004 Cs-137 2.80E+00 1.20E+00 3.40E+00 WR 11 .L6992-01 2/25/2004 Fc-59 -3.1OE+00 6.40E+00 2.60E+01 WR 11 L6992-01 2/25/2004 GROSS BETA 1.56E+00 8.60E-0I 2.80E+00 WR 11 .L6992-01 2/25/2004 11-3 -2.90E+02 2.30E+02 6.70E+02 WR 11 .L6992-01 2/25/2004 1-131 -9.OOE+00 1.40E+01 5.30E+01 WR 11 L6992-01 . 2/2512004 Mn-54 -9.OOE-01 1.70E+00 6.70E+00 WR 11 L6992-01 2/25/2004 Zn-65 -3.20E+00 3.50E+00 1.50E+01 WR 11 1L6992-01 2/25/2004 Zr-95 -6.90E+00 3.20E+00 1.50E+01 WR 11 L7175-01 312912004 Ba-140 1.60E+00 3.00E+00 1.IOE+0I WR II L7175-01 3/29/2004 Co-58 -LIOE+00 1.40E+00 5.60E+00 WVR 11 L7175-01 3129/2004 Co-60 -1.1OE+00 1.40E+00 5.90E+00 WR 11 .L7175-01 3/29/2004 Cs-134 -6.OE-01 1.IOE+00 4.70E+00 WR 11 .L7175-01 3/29/2004 Cs-137 2.20E+00 1.30E+00 4.40E+00 WR 11 .L7175-01 3129/2004 Fe-59 -5.OOE+00 3.50E+00 1.60E+01 WR II L7175-01 3/29/2004 GROSS BETA 3.00E+00 LOOE+00 3.10E+00 WR 11 L7175-01 3/29/2004 H-3 -3.70E+02 3.20E+02 1.I1OE+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-42
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/k-g) (pCi/kg) (pCi/kg)
WR 11 L7175-01 3129/2004 1-131 1.60E1+00 3.30E+00 1.20E+01 WR II L7175-01 3/29/2004 Mn-54 -5.10E-01 9.30E-01 4.00E+00 WR 11 L7175-01 3/29/2004 Zn-65 5.20E+00 2.70E+00 8.50E+00 WR 11 L7175-01 3/29/2004 Zr-95 -1.40E+00 2.50E+00 1.OOE+01 WR II L7297-01 3/29/2004 H-3 4.OOE+02 3.20E+02 1.OOE+03 WR 11 L7341-01 4/26/2004 Ba-140 -3.80E+00 3.30E+00 1.40E+01 WR 11 L7341-01 4/26/2004 Co-58 -1.40E+00 1.60E+00 6.30E+00 WR 11 L7341-01 4/26/2004 Co-60 L.OOE+00 1.SOE+00 5.40E+00 WR 11 L7341-01 4/26/2004 Cs-134 -6.00E-01 1.40E+00 5.60E+00 WR II L7341-01 4/26n2004 Cs-137 2.00E-01 1.40E+00 5.20E+-00 WR II L7341-01 4/26/2004 Fc-59 -2.80E+00 3.70E+00 1.601i+01 WR 1I L7341-01 4/26/2004 GROSS BETA 3.20E+00 L.OOE+00 3.10E+00 WR 11 L734 1-01 4/26/2004 H-3 -5.60E+02 4.30E+02 1.30E+03 WR 11 L7341-01 4/26/2004 1-131 7.60E+00 4.00E+00 1.30E+0I WR II L7341-01 4/26/2004 Mn-54 -2.80E+00 1.40E+00 6.103E+00 NVR 11 L7341-01 4/26/2004 Zn-65 -9.50E+00 3.60E+00 1.60E1+01 WVR 1I L7341 -01 4/26/2004 Zr-95 -2.90E+00 2.60E+00 1.11OE+01 NVR 1I L7471-01 5/25/2004 Ba-140 7.60E+00 3.90E+00 1.20E+01 WR 1I L7471-01 5/25/2004 Co-58 -8.00E-01 1.40E+00 5.soE+00 WR 1I L747 1-01 5/25/2004 Co-60 -2.103E+00 I.SOE+00 7.70E+00 WR 11 L7471-01 5/25/2004 Cs-134 3.00E-01 1.60E+00 5.90E3+00 WR 11 L7471-01 5/25/2004 Cs-137 0.OOE+00 1.70E+00 6.30E+00 WR 11 L7471-01 5/25/2004 Fc-59 0.OOE+00 4.60E+00 L.80E+0l WVR 11 L7471-01 5/25/2004 GROSS BETA 4.40E+00 1.IOE+00 3.1OE+00 WR 11 L7471-01 5/25/2004 H-3 -5.40E+02 3.50E+02 1.20E+03 WVR 11 L7471-01 5/25/2004 1-131 -2.10E+00 5.IOE+00 L.80E+0l WR 11 L7471-01 5/25/2004 Mn-54 2.20E+00 1.30E+00 4.20E+00 WR II L7471-01 5/25/2004 Zn-65 -2.80E+00 7.60E+00 2.70E+01 WR 11 L7471-01 5/25/2004 Zr-95 1.IOE+00 2.70E+00 I.OOE+01 WR 11 L761 1-01 6/23/2004 Ba-140 5.40E+00 4.50E+00 .503E+01 WR 11 L761 1-01 6/23/2004 Co-58 4.00E-01 1.50E+00 5.70E+00 WR 11 L761 1-01 6/23/2004 Co-60 1.30E+00 1.70E+00 6.1OE+00 WR 11 L761 1-01 6/23/2004 Cs-134 0.OOE+00 2.00E+00 7.60E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C43
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCilkg)
WR L761 1-01 6123/2004 Cs-137 6.OOE-01 1.502+00 5.70E+00 WR L761 1-01 6/23/2004 Fe-59 -9.40E+00 4.801+00 2.30E+01 WR L761 1-01 6123/2004 GROSS BETA 6.90E+00 1.202+00 2.90E+00 WR L761 1-01 6/23/2004 H-3 3.90E+02 4.60E+02 1.40E+03 WR L761 1-01 6/23/2004 1-131 -4.80E+00 4.40E+00 1.702+01 WR L761 1-01 6/23/2004 Mn-54 L.501+00 1.70E+00 6.202+00 WVR L761 1-01 6/23/2004 Zn-65 6.OOE+00 7. 1OE+00 2.40E+01 WR L761 1-01 6/23/2004 Zr-95 -6.60E+00 3.30E+00 1.40E+01 WR L7643-01 6/28/2004 Ba-140 2.20E+00 2.20E+00 7.70E+00 WR L7643-01 6/28/2004 Co-S8 -3.OOE+00 1.50E+00 6.20E+00 WR L7643-01 6/28/2004 Co-60 -3.002-01 1.702+00 6.202+00 WVR L7643-01 6/28/2004 Cs-134 -5.OOE-01 1.402+00 5.40E+00 WVR L7643-01 6/28/2004 Cs-137 -1.I02+00 1.60E+00 5.90E+00 WVR L7643-01 6/28/2004 Fe-59 -4.40E+00 4.30E+00 1.70E+01 WVR L7643-01 6/28/2004 GROSS BETA .53E+00 9.20E-01 3.00E+00 WVR L7643-01 6/28/2004 H-3 3.1 0E+02 3.80E+02 1.20E+03 WR L7643-01 6/28/2004 1-131 3.20E+00 3.10E+00 1.I0E+01 WR L7643-01 6/28/2004 Mn-54 O.OOE+00 1.602+00 5.90E+00 WR L7643-01 6/28/2004 Zn-65 -2.50E+00 8.50E+00 3.00E+01 WR L7643-01 6/28/2004 Zr-95 -1.70E+00 2.70E+00 1.00+01 WR L7743-01 6/28/2004 H-3 -5.70E+02 5.30E+02 1.80E+03 WR L7840-01 7/29/2004 Ba-140 2.30E+00 2.70E+00 1.00E+01 WR L7840-01 7/29/2004 Co-58 O.OOE+00 1.60E+00 6.10E+00 WR L7840-01 7/29/2004 Co-60 2.50E+00 1.80E+00 6.00E+00 WR L7840-01 7/29/2004 Cs-134 1.60E+00 1.70E+00 5.902+00 WR L7840-01 7/29/2004 Cs-137 -1.80E+00 1.30E+00 5.502+00 WR L7840-01 7/29/2004 Fe-59 -3.20E+00 4.40E+00 1.90E+01 WR L7840-01 7/29/2004 GROSS BETA 4.80E+00 1.1 OE+00 3.00E+00 WR L7840-01 7/29/2004 H-3 -1.30E+02 5.40E+02 1.70E+03 WR L7840-01 7/29/2004 1-131 -1.50E+00 2.90E+00 1.I0.+0I WR L7840-01 7/29/2004 Mn-54 4.002-01 1.40E+00 5.10E+00 WR L7840-01 7/29/2004 Zn-65 5.201+00 6.002+00 2.00E+01 WR L7840-01 7/29/2004 Zr-95 4.20E+00 2.90E+00 9.70E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-44
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L7980-01 8/27/2004 Ba-140 -3.50E+00 2.30E+00 1.1 0E+01 WVR L7980-01 8/27/2004 Co-58 2.00E-01 1.602+00 6.002+00 WR L7980-01 8/27/2004 Co-60 5.00E-01 1.90E+00 7.10E+00 WR L7980-01 8/27/2004 Cs-134 -1.402+00 1.40E+00 6.30E+00 WR L7980-01 8127/2004 Cs-137 -3.00E-01 1.80E+00 6.80E+00 WR L7980-01 8/27/2004 Fe-59 -1.00+00 4.80E+00 1.90E+01 WR L7980-01 8/27/2004 GROSS BETA 1.60E+00 8.50E-01 2.70E+00 WVR L7980-01 8/27/2004 H-3 8.30E+02 4.90E+02 1.502+03 WVR L7980-01 8/27/2004 1-131 -3.30E+00 3.00E+00 1.202+01 WR L7980-01 8/27/2004 Mn-54 -2.00E+00 1.802+00 7.402+00 WR L7980-01 8/27/2004 Zn-65 9.80E+00 7.60E+00 2.50E+01 WR L7980-01 8/27/2004 Zr-95 -9.OOE-01 2.60E+00 1.00+01 WR L8121-04 9/22/2004 Ba-140 3.402+00 3.40E+00 1.20E+01 WR L8121-04 9/2212004 Co-58 -l.002+00 2.10E+00 8.102O+00 WR L8121-04 9/22/2004 Co-60 6.00E-01 2.102+00 7.90E+00 WR L8121-04 9/2212004 Cs-134 3.80E+00 1.60E+00 4.60E+00 WVR 1.8121-04 9/22/2004 Cs-137 -1.40E+00 2.1 0E+00 8.00E+00 WR L.8121-04 9/22/2004 Fe-59 -1.002+01 4.60E+00 2.202+01 WR L8121-04 9/22/2004 GROSS BETA 2.25E+00 9.10E-01 2.80E+00 WR L8 121-04 9/22/2004 H-3 -4.40E+02 4.60E+02 1.40E+03 WR 18121-04 9/22/2004 1-131 -1.05E+01 5.50E+00 2.101O+01 WR L8121-04 9/22/2004 Mn-54 -2.20E+00 2.20E+00 8.40E+00 WR L8121-04 9/22/2004 Zn-65 -1.27E+01 5.50E+00 2.30E+01 WR L8121-04 9/22/2004 Zr-95 0.00+00 3.80E+00 1.40E+01
%VR L8315-01 9/22/2004 H-3 -5.002+01 3.30E+02 1.IOE+03 WR L8352-01 10/27/2004 Ba-140 0.002+00 2.00E+00 8.202+00 WR L8352-01 10/27/2004 Co-58 -8.20E-01 9.80E-01 4.40E+00 WR L8352-01 10/27/2004 Co-60 -1.60E+00 1.70E+00 7.30E+00 WR L8352-01 10/27/2004 Cs-134 1.90E+00 1.402+00 4.70E+00 WR L8352-01 1027/200n4 Cs-137 7.002-01 1.302+00 4.60E+00 WR L8352-01 10/27/2004 Fe-59 1.40E+00 3.602+00 1.40E+01 WR L8352-01 10/27/2004 GROSS BETA 2.172+00 9.10E-01 2.80E+00 WR L8352-01 10/27/2004 H-3 5.1 02+02 3.30E+02 1.00+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-45
Yankec Nuclear Power Station Radiological Environmental Monitoring Program Summary of2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L8352-01 10/27/2004 1-131 L.OOE+00 2.40E+00 8.60E+00 WVR 18352-01 n0/27/2004 Mn-54 -5.00E-01 1.30E+00 5.30E+00 WR L8352-01 10o27/2004 Zn-65 -7.002-01 2.20E+00 9.50E+00 NVR L8352-01 10/27/2004 Zr-95 5.OOE-01 1.80E+00 7.20E+00 WR L8484-01 11/23/2004 Ba-140 9.00E-01 5.60E+00 2.30E+01 WR L8484-01 11/23n2004 Co-58 -1.60E+00 2.90E+00 1.20E+01 WR Ls484-01 11/23/2004 Co-60 -2.20E+00 2.30E+00 1.10E+01 WR L8484-01 11/23/2004 Cs-134 1.OOE-01 2.40E+00 9.60E+00 WR L8484-01 11/23/2004 Cs-137 -3.00E-01 2.00E+00 8.20E+00 WVR 18484-01 11/23/2004 Fe-59 -7.20E+00 5.40E+00 2.90E+01 WR L8484-01 11/23/2004 GROSS BETA 1.82E+00 8.60E-01 2.70E+00 WR L8484-01 11/23/2004 H-3 -1.04E+03 4.70E+02 1.50E+03 WR L8484-01 11/23/2004 1-131 -1.60E+00 5.10E+00 2.00E+01 WR L8484-01 11/23/2004 Mn-54 -6.00E-01 2.30E+00 9.40E+00 WR L8484-01 11/23/2004 Zn-65 -3.10E+00 4.80E+00 2.20E+01 WR L8484-01 11/23/2004 Zr-95 -7.00E-01 3.40E+00 1.50E+01 WVR L6864-02 12/29/2003 H-3 -3.002+01 2.90E+02 9.50E+02 WR L6910-02 1130/2004 Ba-140 -1.00L+00 2.60E+00 1.20E+01 WR L6910-02 1/30/2004 Co-58 7.00E-01 1.50E+00 5.502+00 WR L6910-02 1/30/2004 Co-60 -2.002-01 1.102+00 4.70E+00 WR L6910-02 1/30/2004 Cs-134 7.002-01 1.50E+00 5.502+00 WR L6910-02 1/30/2004 Cs-137 -2.90E+00 1.l10+00 5.30E+00 WVR L6910-02 1/30/2004 Fe-59 -7.90E+00 4.70E+00 2.10E+01
%VR L6910-02 1/30/2004 GROSS BETA 1.70E+00 8.60E-01 2.70E+00 WR L6910-02 113012004 H-3 4.30E+02 4.102+02 1.20E+03 WR L6910-02 1/30/2004 1-131 2.70E+00 4.80E+00 1.70E+01 WR L6910-02 1/30/2004 Mn-54 -2.60E+00 1.60E+00 6.60E+00 WR L6910-02 1/30/2004 Zn-65 -3.30E+00 2.70E+00 1.20E+01 WR L6910-02 1/30/2004 Zr-95 -1.70E+00 2.80E+00 1.10E+01 WR L6992-02 2/25/2004 Ba-140 -4.70E+00 4.50E+00 2.00E+01 NVR L6992-02 2/25/2004 Co-58 -1.40E+00 1.50E+00 6.202+00 WVR L6992-02 2/25/2004 Co-60 -1.50E+00 1.20E+00 5.30E+00 WVR L6992-02 2125/2004 Cs-134 -3.00E-01 1.20E+00 4.60E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-46
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L6992-02 2/25/2004 Cs-137 2.80E+00 1.30E+00 4.102+00 WR L6992-02 2/25/2004 Fe-59 2.00E+00 5.20E+00 1.90E+01 WR L6992-02 2/25/2004 GROSS BETA 1.49E+00 8.10E-0I 2.602+00 WR L6992-02 2/25/2004 H-3 7.00E+01 2.30E+02 6.70E+02 WVR L6992-02 2125/2004 1-131 1.30E+01 1.20E+01 4.202+01 WVR L6992-02 2/25/2004 Mn-54 1.OE+00 I.1OE+00 3.80E+00 WR L6992.02 2/2512004 Zn-65 3.40E+00 2.80E+00 9.603+00 WR L6992-02 2/25/2004 Zr-95 1.SOE+00 2.30E+00 8.40E+00 WR L7175-02 312912004 Ba-140 -4.002+00 2.70E+00 1.302+01 WR L7175-02 312912004 Co-58 -7.00E-01 1.20E+00 4.901+00 WR L7 175-02 3/29/2004 Co-60 5.OOE-01 1.40E+00 5.50E+00 WR L7175-02 3/29/2004 Cs-134 3.1 OE+00 1.SOE+00 4.50E+00
- VR L7175-02 3/29/2004 Cs-137 -2.00E-01 1.50E+00 5.602+00 WR L7175-02 3/29/2004 Fe-59 3.50E+00 3.60E+00 1.30E+01 NVR L7175-02 3/29/2004 GROSS BETA 1.991E+0O 8.80E-01 2.80E+00 WR
- VR L7175-02 3/29/2004 H-3 I.OOE+01 3.30E+02 1.10+03
- VR L7175-02 3129/2004 1-131 -8.20E+00 4. 10+00 1.70E+01 WR L7175.02 3/29/2004 Mn-54 -1.30E+00 1.20E+00 4.90E+00 WR L7175-02 312912004 Zn-65 -1.90E+00 2.802+00 1.20E+01 WR L7175-02 312912004 Zr-95 8.00E-01 2.30E+00 8.502+00 WR L7297-02 3/2912004 H-3 4.20E+02 3.20E+02 1.00E+03 WR L7341-02 4126/2004 Ba-140 O.OOE+00 3.20E+00 1.40E+01 WR L7341-02 4126/2oo4 Co-58 -1.20E+00 1AOE+00 6.20E+00 WR L7341-02 4/2612004 Co-60 1.40E+00 1.60E+00 5.90E+00
- VR L7341-02 4/2612004 Cs-134 1.00+00 1.90E+00 7.102+00 WR L7341 -02 4/26/2004 Cs-137 1.00+00 1.50E+00 5.40E+00
- VR L7341-02 4/26/2004 Fe-59 -7.OOE+00 5.OOE+00 2.30E+01 WR L7341-02 4/26/2004 GROSS BETA 1.27E+00 8.40E-01 2.80E+00 WR L7341-02 4/26/2004 H-3 -3.20E+02 4.20E+02 1.302+03 WR L7341-02 4126/2004 1-131 6.90E+00 5.203+00 1.702+01 WR L7341-02 4126/2004 Mn-54 0.OOE+00 1.70E+00 6.702+00 WR L7341-02 412612004 Zn-65 0.OOE+00 2.602+00 1.10E+01 WR L7341-02 412612004 Zr-95 9.OOE-01 2.90E+00 1.10E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-47
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN E)ATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR 21 L7471-02 5/25/2004 Ba-140 -1.80E+00 3.1OE+00 1.40E+01 WR .21 L7471-02 5/25/2004 Co-58 -5.00E-01 1.70E+00 6.90E+00 WVR 21 L7471-02 5/25/2004 Co-60 3.00E-01 1.90E+00 7.60E+00 WR 21 L7471-02 5/25/2004 Cs-134 -2.10OE+00 2.10E+00 8.70E+00 WR 21 L7471-02 5/25/2004 Cs-137 -7.00E-01 1.30E+00 5.60E+00 WR 21 L7471-02 5/25/2004 Fe-59 -1.502+00 4.80E+00 2.00E+01 WR 21 L7471-02 5/25/2004 GROSS BETA 2.41E+00 9.40E-01 2.90E+00 WR 21 L7471-02 5/25/2004 H-3 -5.00E+02 3.50E+02 1.20E+03 WVR 21 L7471-02 5/25/2004 1-131 8.1OE+00 4.10E+00 1.30E+01 WVR 21 L7471-02 5/25/2004 Mn-.54 -1.OOE+00 1.70E+00 6.90E+00 WR 21 L7471-02 5/25/2004 Zn-65 3.70E+00 3.90E+00 1.40E+01 WR 21 L7471-02 5/25/2004 Zr-95 4.20E+00 2.90E+00 9.70E+00 WR 21 L7611-02 6/23/2004 Ba-140 1.30E+00 3.90E+00 l .SOE+01 WR 21 L7611-02 6/23/2004 Co-58 -2.00E+00 1.80E+00 8.00E+00 WR 21 L7611-02 6/23/2004 co-6o 3. 10E+00 1.50E+00 4.00E+00 WVR 21 L7611-02 6/23/2004 Cs-134 3.00E-01 1.30E+00 5.50E+00 WVR 21 L7611-02 6/2312004 Cs-137 -1.80E+00 1.80E+00 7.50E+00 WVR 21 L7611-02 6/23/2004 Fc-59 -7.60E+00 5.00E+00 2.40E+01 WR 21 L7611-02 6/23/2004 GROSS BETA 2.60E-01 8.10E-01 2.80E+00 WR 21 L7611-02 6/23/2004 H-3 4.80E+02 4.70E+02 1.40E+03 WR 21 L7611-02 6/23/2004 1-131 -1.13E+01 6.OOE+00 2.40E+01 WR 21 L7611-02 6/23/2004 Mn-54 0.OOE+00 1.80E+00 7.10E+00 WR 21 L7611-02 6/23/2004 Zn-65 -2.00E1+0O 4.30E+00 1.80E+01 WVR 21 L7611-02 6 123/2004 Zr-95 4.1OE+00 3.60E+00 1.202+01 WVR 21 L7643-02 6/28/2004 Ba-140 8.50E+00 3.70E+00 9.00E+00 WVR 21 L7643-02 6/28/2004 Co-58 1.00-01 1.90E+00 7.80E+00 WVR 21 L7643-02 6/28/2004 Co-60 2.70E+00 2.50E+00 8.90E+00 WR 21 L7643-02 6/28/2004 Cs-134 2.00E-01 1.90E+00 7.70E+00 WR 21 L7643-02 6128/2004 Cs-137 1.20E+00 1.80E+00 6.80E+00 WR 21 L7643-02 6/28/2004 Fe-59 5.50E+00 4.40E+00 1.50E+01 WR 21 L7643-02 6/28/2004 GROSS BETA 1.85E+00 8.70E-01 2.802+00 WR 21 L7643-02 6/2812004 H-3 2.70E+02 3.80E+02 1.20E+03 WR 21 L7643-02 6r28/2004 1.131 6.00E-01 2.80E+00 1.10+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C48
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCitkg) (pCi/kg) (pCi/kg)
WVR 21 L7643-02 6/28/2004 Mn-54 -2.50E+00 2.50E+00 I.OOE+01 WR 21 L7643-02 6/28/2004 Zn-65 7.90E+00 4.10E+00 1.20E+01 WR 21 L7643-02 6128/2004 Zr-95 -1.60E+00 2.70E+00 1.20E+01 WR 21 L7743-02 6/28/2004 H-3 -5.70E+02 5.40E+02 1.80E+03 WR 21 L7840-02 7/2912004 Ba-140 4.70E+00 2.90E+00 8.60E+00 WR 21 L7840-02 7129/2004 Co-58 1.70E+00 2.20E+00 8.OOE+00 NVR 21 L7840-02 7/29/2004 Co-60 2.20E+00 2.20E+00 7.80E+00 NWR 21 L7840-02 7/29/2004 Cs-134 2.10E+00 2.50E1+00 8.70E+00 NWR 21 L7840-02 7/29/2004 Cs-137 8.OOE-01 2.OOE+00 7.30E+00 WR 21 L7840-02 7/29/2004 Fe-59 -1.20E+00 6.OOE+00 2.50E+01 WR 21 L7840-02 7/29/2004 GROSS BETA 1.39E+00 8.20E-01 2.70E+00 WR 21 L7840-02 7/29/2004 H-3 -6.OOE+02 5.30E+02 1.80E+03 WR 21 L7840-02 7/29/2004 1-131 -2.80E+00 3.80E+00 1.50E+0I WR 21 L7840-02 7/29/2004 Mn-54 -1.40E+00 1.80E+00 7.50E+00 NWR 21 L7840-02 7/29/2004 Zn-65 6.50E+00 7.40E+00 2.60E+01 NWR 21 L7840-02 7/29/2004 Zr-95 1.40E+00 3.50E+00 1.30E+0O NVR 21 L7980-02 8/27/2004 Ba-140 -9.00E-01 2.OOE+00 9.50E+00 WVR 21 L7980-02 8/27/2004 Co-58 -1.40E+00 1.80E+00 7.50E+00 WR 21 L7980-02 8/27/2004 Co-60 5.00E-01 1.60E+00 6.60E+00 WR 21 L7980-02 8/27/2004 Cs-134 O.OOE+00 1.80E+00 7.20E+00 WR 21 L7980-02 8127/2004 Cs-137 8.00E-01 1.90E+00 7.00E+00 WR 21 L7980-02 8/27/2004 Fe-59 5.60E+00 4.40E+00 1.50E+O1 WR 21 L7980-02 8/27/2004 GROSS BETA 1.82E+00 8.40E-01 2.70E+00 WR 21 L7980-02 8/27/2004 H-3 3.10E+02 4.70E+02 1.40E+03 NWR 21 L7980-02 8/27/2004 1-131 1.70E+00 2.40E+00 8.70E+O0 WR 21 L7980-02 8/27/2004 Mn-54 I.00E-01 1.50E+00 6.00E+00 WVR 21 L7980-02 8/27/2004 Zn-65 2. 1OE+00 4.40E+00 1.70E+0I NVR 21 L7980-02 8/27/2004 Zr-95 -5.00E+00 3.40E+00 1.50E+01 WR 21 L8121-02 9/22/2004 Ba-140 -2.1OE+00 3.90E+00 1.60E+0I WR 21 L8 121-02 9/22t2004 Co-58 -2.00E+00 1.70E+00 7.40E-+O0 WR 21 L8121-02 9/22t2004 Co-60 1.00E+00 1.90E+00 7.00E+O0 WR 21 L8121-02 9/22t2004 Cs-134 2.30E+00 1.60E+00 5.20E+00 WR 21 L8121-02 9/22t2004 Cs-137 -1.40E+00 1.80E+00 7.30E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-49
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summa ry of 2004 Data SAMPLE SEND CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR 21 L8121-02 9/22/2004 Fe-59 -5.40E+00 5.00E+00 2.30E+01 WR 21 L8121-02 9/22/2004 GROSS BETA 1.03E+00 8.30E-0O 2.70E+00 WR 21 L8121-02 9/22/2004 IH-3 -4.00E+01 4.70E+02 1.40E+03 WR 21 L8121-02 9/22/2004 I-131 -3.70E+00 3.70E+00 1.50E+01 WR 21 L8121-02 9/22/2004 Mn-54 1.00E+00 1.40E+00 5.00E+00 WR 21 L8121-02 9/22/2004 Zn-65 -8. 10E+00 3.50E+00 1.70E+0O WR 21 L8121-02 9/22s2004 Zr-95 -9.60E+00 3.00E+00 1.50E+01 WR 21 L8315-02 9/22/2004 1H-3 -3. 10E+02 3.50E+02 1.20E1+03 WR 21 L8352-02 10/27/2004 Ba-140 4.30E+00 3.30E+00 1.1OE+01 WVR 21 L8352-02 10/27/2004 Co-58 -1.20E+00 1.50E+00 6.30E+00 WR 21 L8352-02 10/27/2004 Co-60 8.00E-01 1.70E+00 6.80E+00 WR 21 L8352-02 10/27/2004 Cs-134 -3.00E+00 1.60E+00 7.50E+00 WR L8352-02 10/27/2004 Cs-137 -1.OOE+00 1.70E+00 6.80E+00 WR L8352-02 10/27/2004 Fe-59 -2.00E+00 3.80E+00 1.70E+01 WR LU352-02 10/27/2004 GROSS BETA 2.44E+00 8.70E-0O 2.60E+00 L8352-02 10/27/2004 H-3 -1.60E+02 3.20E+02 l .00E+03 WVR L8352-02 10/27/2004 1-131 3.20E+00 2.70E+00 9.1 OE+00 WR L8352-02 10/27/2004 Wn-54 1.20E+00 1.40E+00 5.20E+00 WR L8352-02 10/27/2004 Zn-65 O.OOE+00 3.40E+00 1.40E+01 WR L8352-02 10/27/2004 Zr-95 8.70E+00 3.20E+00 8.60E+00 WR L8484-02 11/23/2004 Ba-140 3.60E+00 5.20E+00 2.00E+01 WR L8484-02 11/23/2004 Co-58 4.30E+00 2.20E+00 6.50E+00 WR L8484-02 11/23/2004 Co-60 1.20E3+00 3.1OE+00 1.20E+01 WVR L8484-02 11/23/2004 Cs-134 3.70E+00 2.20E+00 6.70E+00 WR L8484-02 11/23/2004 Cs-137 1.l OE+00 1.801E+00 6.80E+00 WR L8484-02 11/23/2004 Fe-59 -5.90E+00 6.20E+00 3.00E-+0I WR L8484-02 11/23/2004 GROSS BETA 1.43E+00 8.50E-01 2.70E+O00 WR L8484-02 11/23/2004 ,H-3 -6.70E+02 4.80E+02 1.50E+03 WR L8484-02 11/23/2004 1-131 -6.00E-01 4.10E+00 1.70E+01 WR L8484-02 11/23/2004 Mn-54 -5.00E+00 2.10E+00 l .00E+0I WR L8484-02 11/23/2004 Zn-65 1.50E+00 4.50E+00 1.80E+01 WR L8484-02 11/23/2004 Zr-95 2.60E+00 3.90E+00 1.50E+01 WVR L6864-03 12n29/2003 iH-3 5.00E+01 3.1 OE+02 1.00E+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-50
Yankee Nuclear Power Station Radiological Environmental Monitoring Program
- Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L6910-03 1/30/2004 Ba-140 -9.002-01 3.70E+00 1.50E+01 WR L6910-03 1/30/2004 Co-58 -3.00E-01 1.40E+00 5.60E+00 WR L6910-03 1/30/2004 Co-60 2.40E+00 1.30E+00 4.20E+00 WR L6910-03 1/30/2004 Cs-134 7.00E-01 1.30E+00 4.90E+00 WR L6910-03 1/30/2004 Cs-137 -2.30E+00 1.30E+00 5.60E+00 WR L6910-03 1/30/2004 Fe-59 -3.00E+00 3.90E+00 1.70E+01 WVR L6910-03 1/30/2004 GROSS BETA 9.802-01 8.002-01 2.70E+00 WR L6910-03 1/30/2004 H-3 5.402+02 4.10E+02 1.20E+03 WR L6910-03 1/30/2004 1-131 7.00E-01 5.50E+00 2.00E+01 WR L6910-03 1/30/2004 Mn-54 l.lOE+00 1.20E+00 4.20E+00 WR L6910-03 1/30/2004 Zn-65 -4.50E+00 3.70E+00 1.502+01 WR L6910-03 1/30/2004 Zr-95 7.002-01 2.80E+00 1.00+01 WR L6992-03 2/25/2004 Ba-140 1.60E+00 6.50E+00 2.50E+01 WR L6992-03 2/25/2004 CO-58 0.00+00 1.70E+00 6.502+00 WR L6992-03 2/25/2004 Co-60 1.90E+00 1.70E+00 6.00E+00 WVR L6992-03 2/25/2004 Cs-134 -6.00E-01 1.60E+00 6.30E+00 WR L6992-03 2/25/2004 Cs-137 2.20E+00 1.30E+00 4.20E+00 WR L6992-03 2/25/2004 Fe-59 -4.00E-01 4.30E+00 1.80E+01 WR L6992-03 2/25/2004 GROSS BETA 2.29E+00 9.102-01 2.80E+00 WR L6992-03 2/25/2004 11-3 -2.90E+02 2.30E+02 6.70E+02 WR L6992-03 2/25/2004 1-131 -2.00E+00 1.20E+01 4.50+01 WR L6992-03 2/25/2004 Mn-54 1.20E+00 1.40E+00 5.00+00 WR L6992-03 2/25/2004 Zn-65 -2.20E+00 3.00E+00 1.30E+01 WR L6992-03 2/25/2004 Zr-95 -1.802+00 3.20E+00 1.30E+01 WR L7175-03 3/29/2004 Ba-140 -1.002+00 3.40E+00 1.40E+01 WR L7175-03 3/29/2004 Co-58 -5.00-01 1.40E+00 5.60E+00 WR L7175-03 3/29/2004 Co-60 -1.20E+00 1.60E+00 6.90E+00 WR L7175-03 3/29/2004 Cs-134 3AOE+00 1.50+00 4.40E+00 WVR L7175-03 3/29/2004 Cs-137 -2.90E+00 1.202+00 5.702+00 WR L7175-03 3/29/2004 Fe-59 0.002+00 4.50+00 1.80E+01 WVR L7175-03 3/29/2004 GROSS BETA 1.62E+00 8.70E-01 2.80E+00 NVR L7175-03 3/29/2004 11-3 0.00+00 3.30E+02 1.102+03 WVR L7175-03 3/29/2004 1-131 4.20E+00 3.902+00 1.30E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-51
Yankee Nuclear Power Station Radiological Environmental Monitoring Program
- Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L7175-03 3/2912004 Mn-54 -4.002-01 1.30E+00 5.1 OE+00 WR L7175-03 3/29/2004 Zn-65 -4.20E+00 3.30E+00 1.40E+0O WR L7175-03 3/29/2004 Zr-95 1.60E+00 2.20E+00 8.1 0E+00 WR L7297-03 3/29/2004 H-3 5.OOE+02 3.20E+02 1.OOE+03 WR L7341-03 4/26/2004 Ba-140 -1.60E+00 4. 1OE+00 1.90E+0O WR L7341-03 4/26/2004 Co-58 -4.00E-01 1.60E+00 7.OOE+00 WVR L7341-03 4/26/2004 Co-60 -L.90E3+00 2.40E+00 1.1OE+01 WR L7341-03 4/2612004 Cs-134 -2.80E+00 1.901E+00 8.90E+00 WR L7341 -03 4/26/2004 Cs-137 - 1.40E+00 L.90E+00 8.00E+00 WR L7341-03 4/26/2004 Fe-59 2.40E+00 7.70E+00 2.90E+01 WR L7341-03 4/26/2004 GROSS BETA 2.01E+00 9.701-01 3.OOE+00 WR L7341-03 4/26/2004 H-3 5.002+01 4.30E+02 1.302+03 WR L7341-03 4/26/2004 1-131 2.60E+00 4.20E+00 1.50+01 WR L7341-03 4/26/2004 Mn-54 -2.20E+00 2.101E+00 9.00E+00 WR L7341-03 4/26/2004 Zn-65 3.70E+00 4.80E+00 1.70E+0O WR L7341-03 4/26/2004 Zr-95 -8.OOE-01 3.20E+00 1.30E+01 WR L7471-03 5/25/2004 Ba-140 3.40E+00 3.40E+00 1.30E+01 WR L7471-03 5s25/2004 Co-58 1.20E+00 2.40E+00 9.00E+00 WR L7471-03 5/25/2004 Co-60 4.30E+00 2.70E+00 8.80E+00 WR L7471-03 5/25/2004 Cs-134 -1.702+00 1.80E+00 8.50E+00 WR L7471-03 5/25/2004 Cs-137 -L.80E+00 1.20E+00 6.40E+00 WR L7471.03 5/25/2004 Fe-59 -1.04E+01 7.30E+00 3.40E+01 WVR L7471-03 5/25/2004 GROSS BETA 2.40E+00 l.lOE+00 3.60E+00 WVR L7471-03 5/25/2004 H-3 -2.90E+02 3.50E+02 1.20E+03 WR L7471-03 5/25/2004 1-131 7.10E+00 5.90E+00 2.00E+0O WR L7471-03 5/25/2004 Mn-54 -4.002-01 1.60E+00 7.002+00 WR L7471-03 5/25/2004 Zn-65 -1 .30E+00 4.00E+00 1.80E+01 WR L7471-03 5/25/2004 Zr-95 6.90E+00 3.1 OE+00 8.00E+00 WR L7611-03 6/23/2004 Ba-140 3.40E+00 5.80E+00 2.20E+0O WVR L7611-03 6/23/2004 Co-58 -2.70E+00 2.00E+00 9.20E+00 WVR L7611-03 6/23/2004 Co-60 3.80E+00 2.40E+00 7.802+00 WVR L7611-03 6/23/2004 Cs-134 -L - I OE+00 2.10E+00 8.90E+00 WVR L7611-03 6/23/2004 Cs-137 L.OOE-01 1.80E+00 7.20E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-52
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WR L7611-03 6/23/2004 Fe-59 5.50E+00 6.60E+00 2.40E+0I WR L7611-03 6/23/2004 GROSS BETA 1.86E+00 8.50E-01 2.70E+00 WR L7611-03 612312004 H-3 0.00E+00 4.50E+02 1.40E+03 WR L76 11-03 6/23/2004 1-131 6.40E+00 4.80E+00 1.60E+OI WR L7611-03 6/23/2004 Mn-54 8.00E-01 1.50E+00 5.90E+00 WVR L7611-03 6/23/2004 Zn-65 -2.70E+00 4.60E+00 2.00E+01 WR L7611-03 6/23/2004 Zr-95 9.00E-0I 3.50E+00 I AOE+0I WR L7643-03 6n28/2004 Ba-140 3.60E+00 3.20E+00 1.1OE+01 WR L7643-03 6/28/2004 Co-58 -5.40E+00 2.20E+00 1.00E+01 WR L7643-03 6/28/2004 Co-60 -1.00E+00 1.90E+00 8.60E+00 WR L7643-03 6/28/2004 Cs-134 2.10E+00 2.1 OE+00 7.50E+00 WVR L7643-03 6/28/2004 Cs-137 -3.60E3+00 1.80E+00 8.60E+00 WR L7643-03 6/2812004 Fe-59 3.1 0E+00 5.60E+00 2.20E+01 WR L7643-03 6/28/2004 GROSS BETA 1.49E+00 8.70E-01 2.80E+00 WR L7643-03 6128/2004 H-3 3.60E+02 4.1 0E+02 1.30E+03 WR L7643-03 6/28/2004 1-131 1.90E+00 3.30E+00 1.20E+01 WR L7643-03 6/28/2004 Mn-54 8.00E-01 1.60E+OO 6.20E+00 WR L7643-03 6/28/2004 Zn-65 1.30E+00 4.30E+00 1.70E+0I WR L7643-03 6/28/2004 Zr-95 -3.00E-01 2.60E+00 1.1 OE+0I WR L7743-03 6/28/2004 H-3 -6.40E+02 5.40E+02 1.80E1+03 WVR L7840-03 7/29/2004 Ba-140 4.60E+00 3.60E+00 1.20E+OI WR L7840-03 7/29/2004 Co-58 -3.40E+O00 1.40E+00 7.40E+00 WR L7840-03 7/29/2004 Co-60 1.40E+00 1.70E+00 6.20E+00 WR L7840-03 7/29/2004 Cs-134 1.20E+00 1.50E+00 5.60E+00 WR L7840-03 7/29/2004 Cs-137 1.30E+00 2.10E+00 7.60E+00 WR L7840-03 7/29/2004 Fe-59 -2.60E+00 5.10E+00 2.30E+0I WR L7840-03 7/29/2004 GROSS BETA 2.05E+00 9.30E-01 2.90E+00 WR L7840-03 7/29/2004 H-3 -6.00E+02 5.30E+02 1.70E+03 WR L7840-03 7/29/2004 1-131 7.00E-01 3.70E+00 1.40E+0I WR L7840-03 7/29/2004 Mn-54 -1.501E+00 1.60E+00 7.00E+00 WR L7840-03 7/29/2004 Zn-65 2.1 OE+00 4.50E+00 1.70E+0I WR L7840-03 7/29/2004 Zr-95 -2.90E+00 2.70E+00 1.20E+01 WvR L7980-03 8/27/2004 Ba-140 5.60E+00 3.00E+00 8.70E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ AMinimum Detectable Concentration > Lower Limit or Detection Requirement C-53
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/lkg)
WR 31 L7980-03 812712004 Co-58 2.101E+00 1.60E+00 5.50E+00 WR 31 L7980-03 8/27/2004 Co-60 -3.40E+00 1.90E+00 9.40E+00 WR 31 L7980-03 8/27/2004 Cs-134 -4.00E-01 1.90E+00 7.60E+00 WR 31 L7980-03 8/27/2004 Cs-137 -1.OOE-0O 1.902+00 7.50E+00 WR 31 L7980-03 8/27/2004 Fe-59 1.001E+00 4.50E+00 1.80E+0O WR 31 L7980-03 8/27/2004 GROSS BETA 2.15E+00 9.10E-01 2.802+00 WR 31 L7980-03 8/27/2004 H-3 4.1OE+02 4.80E+02 1.502+03 WR 31 L7980-03 8/27/2004 1-131 5.OOE+00 3.30E+00 1.IOE+O1 WR 31 L7980-03 8/27/2004 Mn-54 -1.90E+00 1.80E+00 8.00E+00 WVR 31 L7980-03 8/27/2004 Zn-65 -6.70E+00 4.soE+00 2.00E+01 WR 31 L7980-03 8/27/2004 Zr-95 -5.002-01 3.30E+00 1.302+01 WR 31 L8121-03 9/22/2004 Ba-140 2.20E+00 3.10E+00 1.20E+0O WR 31 L8121-03 9/22/2004 Co-58 1.00E+00 1.30E+00 4.902+00 WR 31 L8121-03 9/22/2004 Co-60 2.00E+00 1.40E+00 4.60E+00 WR 31 L8121-03 9/22/2004 Cs-134 9.00E-01 1.60E+00 6.20E+00 WR 31 L8121-03 9/22/2004 Cs-137 1.I1E+00 1.80E+00 6.40E+00 WR 31 L8121-03 9/22/2004 Fe-59 -6.00E-01 3.90E+00 1.70E+O1 WR 31 L8121-03 9/22/2004 GROSS BETA 2.76E+00 9.00E-01 2.60E+00 WR 31 L8 121-03 9/22/2004 H-3 S.50E+02 4.70E+02 1.40E+03 WR 31 1L8121-03 9/22/2004 1-131 3.40E+00 3.90E+00 1.302+01 WR 31 L8121-03 9/22/2004 Mn-54 8.00E-01 1.60E+00 6.00E+00 WR 31 L8121-03 9/22/2004 Zn-65 3.90E+00 3.60E+00 1.302+01 WR 31 L8121-03 9/22/2004 Zr-95 2.10E+00 3.00E+00 1.1E0+01 WR 31 L8315-03 9/22/2004 H-3 -1.60E+02 3.50E+02 1.20E+03 WR 31 L8352-03 10/27/2004 Ba-140 -2.50E+00 2.20E+00 1.10+01 WVR 31 L8352-03 10/27/2004 Co-58 8.00E-01 1.60E+00 6.00E+00 WR 31 L8352-03 10/27/2004 Co-60 2.902+00 2.002+00 6.70E+00 WR 31 L8352-03 10/27/2004 Cs-134 6.002-01 1.80E+00 6.702+00 WR 31 L8352-03 10/27/2004 Cs-137 -5.00E-01 1.50E+00 6.00E+00 WR 31 L8352-03 10/27/2004 Fe-59 -2.50E+00 5.10E+00 2.10E+01 WR 31 L8352-03 10/27/2004 GROSS BETA 1.04E+00 8.30E-01 2.70E+00 WVR 31 L8352-03 10/27/2004 11-3 -1.60E+02 3.20E+02 1.00E+03 WR 31 L8352-03 10/27/2004 1-131 -1.80E+00 2.802+00 1.I0E+0I
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-54
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pci/kg) (pCi/kg) (pCi/kg)
WR 31 L8352-03 10/27/2004 Mn-54 1.70E+00 I.40E+00 4.70E+00 WR 31 L8352-03 10/27/2004 Zn-65 2.70E+00 3.50E+00 1.30E+01 WR 31 L8352-03 10/27/2004 Zr-95 1.50E+00 2.80E+00 l .00E+01 WR 31 L8484-03 11/23/2004 Ba-140 -2.30E+00 2.80E+00 1.20E+OI WVR 31 L8484-03 11/23/2004 Co-58 - 1.20E+00 1.70E+00 6.80E+00 NVR 31 L8484-03 11/23/2004 Co-60 2.60E+00 1.40E+00 4.50E+00 WR 31 L8484-03 11/23/2004 Cs-134 3.00E-01 1.60E+O0 5.80E+O0 WR 31 L8484-03 11/23/2004 Cs-137 -2.50E+O0 1.50E+O0 6.20E+00 WR 31 L8484-03 11/23/2004 Fc-59 2.90E+00 4.20E+00 1.50E+01 WR 31 L8484-03 11/23/2004 GROSS BETA 3.20E-01 7.10E-01 2.50E+00 WR 31 L8484-03 11/23/2004 H-3 -7.90E+02 4.70E+02 1.50E+03 WR 31 L8484-03 11/23/2004 1-131 0.00E+00 4.10E+00 I.50E+01 WR 31 L8484-03 11/23/2004 Mn-54 -1.70E+00 1.20E+00 5.40E+00 WR 31 L8484-03 11/23/2004 Zn-65 -1.48E+OI 4.00E+00 l.90E+01 WR 31 L8484-03 11/23/2004 Zr-95 2.60E+00 2.90E3+00 l.00E-+0I WVR 31 L8748-03 11/23/2004 H-3 2.70E+02 3.30E+02 1.00E+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower limit of Detection Requirement C-55
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg) wVwV L7175-07 3/29/2004 Ba-140 -2.10E+00 2.801+00 1.20E+01 wW L7175-07 3/29/2004 Co-58 1.60E+00 1.20E+00 4.10E+00 ww L7175-07 3/29/2004 Co-60 0.OOE+00 1.30E+00 5.00E+00 ww L7175-07 3/29/2004 Cs-134 4.00E-01 1.40E+00 5.30E+00 ww L7175-07 3/29/2004 Cs-137 3.20E+00 1.302+00 3.80E+00 ww L71 75-07 3/29/2004 FR-59 -2.00E-01 4.20E+00 1.60E+01 WW L7 175-07 3/29/2004 GROSS BETA .49E+01 1.90L+00 4.202+00 WV L7 175-07 3/29/2004 H-3 1.10E+02 3.30E+02 1.102+03 WV L7175-07 3/29/2004 1-131 3.70E+00 4.OOE+00 I1AOE+01 ww L7175-07 3/29/2004 Mn-54 -7.00E-01 1.1 OE+00 4.502+00 ww L7175-07 3/29/2004 Zn-65 -2.20E+00 2.20E+00 9.50E+00 ww L7175-07 3/29/2004 Zr-95 3.30E+00 1.802+00 5.70E+00 ww L7341 -07 4/26/2004 Ba-140 6.90E+00 4.00E+00 1.20E+01 WW L7341-07 4/26/2004 Co-58 1.80E+00 2.20E+00 8.10E+00 NV"V L7341-07 4/26/2004 Co-60 -2.20E+00 3.00E+00 1.302+01 WNV L7341-07 4/26/2004 Cs-134 -5.OOE-01 2.00E+00 8.20E+00 ww L7341-07 4/26/2004 Cs-137 L.SOE+00 .1.302+00 4.50E+00 ww L7341-07 4/26/2004 Fe-59 -4.202+00 5.102+00 2.50E+01 ww L7341 -07 4/26/2004 GROSS BETA 1.222+01 1.40E+00 3.10+E+0 ww L7341-07 4/26/2004 H-3 -6.60E+02 4.20E+02 1.302+03 NVW L7341-07 4/2612004 1-131 -2.90E+00 5.20E+00 2.10E+01 NVW L7341 -07 4/26/2004 Mn-54 -5.60E+00 2.101+00 1.00+01 WW L7341-07 4/26/2004 Zn-65 3.90E+00 2.30E+00 3.60E+00 WW L7341-07 4/26/2004 Zr-95 2.00E-01 3.502+00 1.40E+01 WwV L7611-07 6/23/2004 Ba- 140 -7.20E+00 4.40E+00 2.40E+01 ww L7611-07 6/23/2004 Co-58 2.00E-01 2.60E+00 1.00+01 WW L7611-07 6/2312004 Co-60 5.OOE-01 2.00E+00 8.40E+00 WW L7611-07 6/23/2004 Cs-134 4.00E-01 1.90E+00 7.60E+00 WW L7611-07 6/23/2004 Cs-137 L.50E+00 2.402+00 8.802+00 wW L7611-07 6/23/2004 Fe-59 6.50E+00 5.20E+00 1.80E+01 NVwV L7611-07 6/23/2004 GROSS BETA 1.42E+0l 1.502+00 3.10E+00 NVW L7611-07 6/23/2004 H-3 1.632+03 4.1012+02 1.202+03 W'V L7611-07 6/23/2004 1-131 -9.20E+00 6.50E+00 2.70E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-56
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WW L7611-07 6/23/2004 Mn-54 -3.80E+00 1.80E+00 9.1 OE+00 WW L7611-07 6123/2004 Zn-65 -8.50E+00 4.50E+00 2.30E+01 WW L7611-07 6/23/2004 Zr-95 -3.30E+00 3.10E+00 1.50E+01 WW L7643-07 6/28/2004 Ba-140 6.002-01 2.40E+00 9.40E+00 wVw L7643-07 6/28/2004 Co-58 -2.60E+00 1.40E+00 6.30E+00 WW L7643-07 6/2812004 Co-60 -. IOE+00 .50E+00 6.20E+00 WW L7643-07 6/28/2004 Cs-134 -3.00E-01 1.50E+00 5.90E+00 NvW L7643-07 6/28/2004 Cs-137 -1,30E+00 1.30E+00 5.50E+00 WW L7643-07 6/28/2004 Fe-59 -3.002+00 3.40E+00 1.50E+01 V~rW L7643-07 6/28/2004 GROSS BETA 1.12E+0I 1.40E+00 3.00E+00 WW L7643-07 6/28/2004 H-3 -1.50E+02 3.90E+02 1.30E+03 WW L7643-07 6/28/2004 1-131 1.I OE+00 2.60E+00 9.30E+00 WW L7643-07 6/28/2004 Mn-54 8.00E-01 1.70E+00 6.10E+00 NYW L7643-07 6/28/2004 Zn-65 -8.002-01 3.00E+00 1.20E+01 NYW L7643-07 6/28/2004 Zr-95 O.OOE+00 2.202+00 8.70E+00
'VwV L7840-07 7/29/2004 Ba-140 3.50E+00 4.50E+00 1.60E+01 WW L7840-07 7/2912004 Co-58 -3.70E+00 2.30E+00 9.90E+00 W'V L7840-07 7/29/2004 Co-60 5.00E-01 1.402+00 5.90E+00 WW L7840-07 7/29/2004 Cs-134 -1.20E+00 2.10E+00 8.50E+00 WW L7840-07 7/29/2004 Cs-137 -8.00E-01 2.00E+00 7.90E+00 WW L7840-07 7/29/2004 Fe-59 -3.20E+00 2.30E+00 1.50E+01 WW L7840-07 7/29/2004 GROSS BETA 8.90E+00 1.30E+00 3.20E+00 WW L7840-07 7/29/2004 H-3 -3.1 0E+02 5.30E+02 1.70E+03 wwNY L7840-07 7/29/2004 1-131 2.80E+00 3.80E+00 1.30E+01 WW L7840-07 7/29/2004 Mn-54 1.30E+00 1.70E+00 6.00E+00 WW L7840-07 7/29/2004 Zn-65 -4.20E+00 5.00E+00 2.10E+01 WW L7840-07 7/29/2004 Zr-95 -L.50E+00 2.80E+00 1.20E+01 WW L7980-07 8/27/2004 Ba-140 1.20E+00 2.70E+00 1.10E+01 WW L7980-07 8s27/2004 CO-58 4.00E-01 1.90E+00 7.602+00
%VW L7980-07 8/27/2004 Co-60 -2.70E+00 2.20E+00 1.00+01 WW L7980-07 8/27/2004 Cs-134 L.IOE+00 2.202+00 8.30E+00 NM1V L7980-07 8/27/2004 Cs-137 -2.50E+00 2.30E+00 1.00E+01 WW L7980-07 8/27/2004 Fe-59 -L.00E+00 6.10E+00 2.60E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit or Detection Requirement C-57
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WW 51 L7980-07 8/2712004 GROSS BETA 1.53E+01 1.80E+00 3.90E+00 WW 51 L7980-07 8/27/2004 H-3 1.60E+02 4.70E+02 1.40E+03 WW 51 L7980-07 8/2712004 1-131 -2.40E+00 3.20E+00 1.30E+01 51 L7980-07 8/27/2004 Mn-54 -1.30E+00 1.60E+00 7.40E+00 NVNV 51 L7980-07 8/27/2004 Zn-65 -7.101E+00 5.50E+00 2.50E+01 NVY 51 L7980-07 8/27/2004 Zr-95 8.00E-01 3.30E+00 1.30E+01 51 L8121-07 9122/2004 Ba-140 6.00E-01 3.60E+00 1.50E+0O WW 51 L8121-07 9/22/2004 Co-58 -7.00E-01 2.00EE00 8.20E+00 WW 51 L8121-07 9/22/2004 Co-60 -1.60E+00 1.90E+00 8.60E+00 WW 51 L8121-07 9/2212004 Cs-134 -2.40E+00 1.60E+00 7.60E+00 WW 51 L8121-07 9/22/2004 Cs-137 4.00E-01 1.20E+00 4.70E+00 WW 51 L8121-07 9/22/2004 Fe-59 4.90E+00 5.80E+00 2.10E+01 WW 51 L8121-07 9/22/2004 GROSS BETA 1.16E+01 1.60E+00 3.60E+00 51 L8121-07 9122/2004 H-3 3.40E+02 4.60E+02 1.40E+03 NVWY 51 L8121-07 9/2212004 1-131 -5.OOE-01 3.80E+00 1.40E+01 VW 51 L8121-07 9/22/2004 Mn-54 -1.50E+00 1.90E3+00 8.00E+O00 WW 51 L8121-07 9/22/2004 Zn-65 -7.30E+00 4.10E+00 1.90E+01 WW WW 3.80E3+00 51 L8121-07 9/22/2004 Z7-95 1.90E+00 1.40E+0O WW 51 L8352-07 10/27/2004 Ba-140 2.60E+00 2.80E1+00 l .1OE+01 WW 51 L8352-07 10/27/2004 Co-58 2.40E+00 1.60E+00 5.20E+00 WW 51 L8352-07 10/27/2004 Co-60 2.60E+00 2.40E3+00 8.40E+00 WW 51 L8352-07 10/27/2004 Cs-134 -1.40E+00 1.70E+00 7.50E+00 WW 51 L8352-07 10/27/2004 Cs-137 2.70E1+O0 1.90E+00 6.40E+00 WW 51 L8352-07 10/27/2004 Fc-59 1.60E3+00 4.80E3+00 1.90E+01 51 L8352-07 10/27/2004 GROSS BETA 1.25E+01 1.501E+00 3.00EOOE0 NVWY 51 L8352-07 10/27/2004 H-3 -1.IOE+02 3.20E+02 l .OOE+03 WW 51 L.8352-07 10/27/2004 1-131 -1.80E+00 4.20E+00 1.60E+01 51 L8352-07 10/27/2004 Mn-54 -6.00E-01 1.90E+00 7.60E+00 WW 51 L8352-07 10/2712004 Zn-65 -4.20E+00 3.90E+00 1.70E+01
~WW 1.I1OE+00 3.70E+O00 1.40E+01 51 L8352-07 10/27/2004 Zr-95 WW 52 L6992-07 2/25/2004 Ba-140 5.90E+00 4.80E+00 1.60E+01 WW 52 L6992-07 2/25/2004 Co-58 2.1OE+00 1.30E+00 4.20E+00 WW 52 L6992-07 2/2512004 Co-60 1.501E+00 1.30E+O00 4.30E+O0
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-58
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WW L6992-07 2/25/2004 Cs-134 -4.00E-01 1.20E+00 4.70E+00 L6992-07 2/2512004 Cs-137 -6.00E-01 1.20E+00 4.60E+00
'vwY L6992-07 2/25/2004 Fe-59 -4.30E+00 3.60E+00 1.60E+01 L6992-07 2/25/2004 GROSS BETA 1.63E+01 1.90E+00 3.90E+00 WWV L6992-07 2125/2004 H-3 -1.50E+02 2.30E+02 6.70E+02 WW L6992-07 2/25/2004 1-131 8.00E+00 1.00+01 3.50E+01 L WW L6992-07 2/25/2004 Mn-54 4.00E-01 l.1OE+00 4.20E+00 L6992-07 2/25/2004 Zn-65 -2.90E+00 2.80E+00 1.1 0E+0 I VWW L6992-07 2125/2004 Zr-95 -1.60E+00 2.50E+00 9.90E+00 WY L7175-08 3/29/2004 Ba-140 -1.20E+00 2.802+00 1.10E+01 WNVN L7175-08 3129/2004 Co-S8 2.10E+00 1.30E+00 4.10E+00 NWW L7175-08 3/29/2004 Co-60 3.00E-01 1.10+00 4.40E+00 L7175-08 3/2912004 Cs-134 5.00-01 1.lOE+00 4.20E+00 WW L7175-08 3/29/2004 Cs-137 4.00E-0O 1.10E+00 4.00E+00 WW L7175-08 3n29/2004 Fe-59 3.30E+00 3.30E+00 1.202+01 WW L7175-08 3/29/2004 GROSS BEIA 8.20E+00 1.40E+00 3.40E+00 L7175-08 3/29/2004 H-3 -4.00E+01 3.30E+02 1.101O+03 WW w'v L7175-08 3/29/2004 1-131 5.40E+00 4. 1OE+00 1.40E+01 ww L7175-08 3/29/2004 Mn-54 -2.20E+00 1.IOE+00 5.00E+00 L7175-08 3/29/2004 Zn-65 -3.00E+00 2.80E+00 1.102O+01 WW L7175-08 312912004 Zr-95 3.30E+00 2.10E+00 6.90E+00 WW L7341-08 4/26/2004 Ba-140 -2.20E+00 2.50E+00 1.20E+01 WW L7341-08 4/26/2004 Co-58 1.90E+00 1.30E+00 4.40E+00 WW L7341-08 4/26/2004 Co-60 -5.00E-01 1.80E+00 7.20E+00 WW L7341-08 4126/2004 Cs-134 -1.70E+00 1.70E+00 7.002+00 W Y L7341-08 4/26/2004 Cs-137 3.10E+00 1.40E+00 4.302+00 WW L7341-08 4/26/2004 Fc-59 2.20E+00 4.20E+00 1.60E+01 WW L7341 -08 4/26/2004 GROSS BETA 4.20E+00 1.102+00 2.902+00 L7341-08 4/26/2004 H-3 3.00E+02 4.40E+02 1.30E+03 WW L7341-08 4/26/2004 1-131 -4.90E+00 4.20E+00 1.60E+01 WW L7341-08 4/26/2004 Mn-54 -2.00E+00 1.80E+00 7.20E+00 WW L7341-08 4/26/2004 Zn-65 -5.60E+00 3.60E+00 1.50+01 L7341-08 4/26/2004 Zr-95 3.40E+00 2.80E+00 9.60E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Mlinimum Detectable Concentration > Lower Limit or Detection Requirement C-59
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WVW 52 L7471-07 5/25/2004 Ba-140 -6.OOE-01 4.70E+00 2.OOE+OI WNV 52 L7471-07 5/25/2004 Co-58 -1.70E+00 2.10E+00 8.80E+00 WNV 52 L7471-07 5/25/2004 Co-60 8.00E-01 1.70E+00 7.00E+00 WWV 52 L7471-07 5/25/2004 Cs-134 -3.30E+00 2.30E+00 1.OOE+0O WW 52 L7471-07 5/25/2004 Cs-137 2.20E+00 2.10E+00 7.20E+00 WW 52 L7471-07 5/25/2004 Fe-59 I.90E+00 6.70E+00 2.60E+01 WW 52 L7471-07 5/2512004 GROSS BETA 4.80E+00 1.20E+00 3.20E+00 WW 52 L7471-07 5/25/2004 H-3 -4.70E+02 3.50E+02 1.20E+03 WW 52 L7471-07 5/25/2004 1-131 7.50E+00 4.90E+00 1.60E+01 NVNV 52 L7471-07 5/25/2004 Mn-54 -2.90E+00 1.702+00 8.10E+00 WVW 52 L7471-07 5/25/2004 Zn-65 0.OOE+00 3.30E+00 IAOE+01 WNV 52 L7471-07 5/25/2004 Zr-95 -1.OOE-01 3.60E+00 1.40E+01 WNV 52 L7611-08 6/23/2004 Ba-140 1.80E+00 3.60E+00 1.40E+01 WW 52 L7611-08 6/23/2004 Co-58 -2.10E+00 1.50E+00 6.30E+00 WW 52 L761 1-08 6/23/2004 Co-60 -7.00E-01 1.80E+00 7.00E+00 WW 52 L7611-08 6/23/2004 Cs-134 -2.70E+00 1.60E+00 7.00E+00 WW 52 L7611-08 6/23/2004 Cs-137 -1.00E+00 1.40E+00 5.70E+00 WW 52 L7611-08 6/23/2004 Fe-59 -5.60E+00 4.60E+00 2.00E+01 WW 52 L7611-08 6/23/2004 GROSS BETA 4.002+00 1.20E+00 3.60E+00 WW 52 L761 1-08 6/23/2004 H-3 0.00+00 4.60E+02 1.40E+03 WW 52 L7611-08 6/23/2004 1-131 1.50E+00 3.70E+00 1.302+01 WW 52 L7611-08 6/23/2004 Mn-54 1.80E+00 1.50E+00 5.10E+00 WW 52 L7611-08 6/23/2004 Zn-65 4.90E+00 3.50E+00 1.20E+01 WW 52 L7611-08 6/23/2004 Zr-95 -3.00E-01 2.60E+00 1.00E+01 WW 52 L7643-08 6/28/2004 Ba-140 -5.20E+00 3.70E+00 1.80E+01 WNV 52 L7643-08 6/28/2004 Co-58 1.90E+00 2.102+00 7.502+00 WWV 52 L7643-08 6/28/2004 Co-60 -1.40E+00 2.00E+00 9.50E+00 WVW 52 L7643-08 6/28/2004 Cs-134 2.902+00 2.20E+00 7.502+00 WVW 52 L7643-08 6/28/2004 Cs-137 -3.10E+00 2.40E+00 1.00E+01 WVW 52 L7643-08 6/28/2004 Fe-59 -2.00E+00 4.602+00 2.20E+01 WW 52 L7643-08 6/28/2004 GROSS BETA 5.40E+00 1.20E+00 3.20E+00 WW 52 L7643-08 6/28/2004 H-3 -2.10E+02 4.00E+02 1.30E+03 WW 52 L7643-08 6/28/2004 1-131 4.70E+00 3.402+00 1.102+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-60
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WW 52 L7643-08 6/28/2004 Mn-54 -2.70E+00 1.SOE+00 7.90E+00 WW 52 L7643-08 6/28/2004 Zn-65 -7.00E+00 4.20E+00 2.10E+01 WW 52 L7643-08 6/28/2004 Zr-95 2.00E-01 3.50E+00 1.402+01 WVW 52 L7840-08 7/29/2004 Ba-140 4.60E+O0 2.70E+00 8.50E+00 NVV 52 L7840-08 7/29/2004 Co-58 -4.90E+00 1.50E+00 7.00E+00 NVW 52 L7840-08 7/29/2004 Co-60 -2.00E-01 1.60E+00 6.30E+00 NVW 52 L7840-08 7/29/2004 Cs-134 -1.302+00 1.60E+00 6.40E+00
%VNV 52 L7840-08 7/29/2004 Cs-137 -3.00E-01 1.70E+00 6.20E+00 WW 52 L7840-08 7/29/2004 Fe-59 -6.00E-01 5.00E+O0 1.902+01 NVNV 52 L7840-08 7/29/2004 GROSS BETA 7.80E+00 1.30E+00 3.102+00
- NV'V 52 L7840-08 7/29/2004 H-3 -l .30E+02 5.SOE+02 1.80E+03 NVNV 52 L7840-08 7/29/2004 1-131 I.60E+00 3.20E+00 1.102+01 WVNV 52 L7840-08 7/29/2004 Mn-54 ..5.0(01..01 1.30E+00 5.20E+00 "VW 52 L7840-08 7/29/2004 Zn-65 7.9012+00 6.50E+00 2.20E+01 WVW 52 L7840-08 7/29/2004 Zr-95 2.8012+00 2.70E+00 9.202+00 WNV 52 L7980-08 8/27/2004 Ba-140 -2.30E+00 2.00E+00 9.90E+00 VNV 52 L7980-08 8/27/2004 Co-58 -9.OOE0120 1.SOE+00 6.40E+00 WVWV 52 L7980-08 8/27/2004 Co-60 6.OOE-0l 1.70E+00 6.60E+00 W'V 52 L7980-08 8/27/2004 Cs-134 1.20E+00 1.50O+00 5.50+00 WVW' 52 L7980-08 8/27/2004 Cs-137 -1.0023+00 1.70E+O0 6.90E+00 W'V 52 L7980-08 8/27/2004 Fe-59 7.20E+00 4.60E+O0 1.502+01 6.00E+00
- WW 52 L7980-08 8/27/2004 GROSS BETA 1.20E+00 3.102+00 WW 52 L7980-08 8/27/2004 H-3 1.80E+02 4.70E+02 1.40E+03 WV. 52 L7980-08 8/27/2004 1-131 2.60E3+00 2.90E+00 1.OOE+01 W'V 52 L7980-08 8/27/2004 Mn-54 -9.OOE-01 1.60E+00 6.40E+00 W'V 52 L7980-08 8/27/2004 Zn-65 -7.20E+00 4.00E+00 1.80E+01 W'V 52 L7980-08 8/27/2004 Zr-95 68.00E-01 2.90E+00 1.202+01 WVA 52 L8121-08 9/22/2004 Ba-140 4.601E+00 4.40E+00 1.502+01 NVW 52 L8121 -08 9/22/2004 Co-58 -1.30E+00 2.40E+00 9.602+00 WW 52 LS 121-08 9/22/2004 Co-60 6.IOE01+00 2.30E+00 5.60E+00 NVM 52 LS 121-08 9/22/2004 Cs-134 1.40E.+00 2.50E+00 9.002+00 WW 52 LS 121-08 9/22/2004 Cs-137 -2.60E+00 1.70E+00 7.90E+00 WW 52 L 121-08 9/22/2004 Fe-59 4.80E+00 4.80E+00 2.00E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-61
Yankee Nuclear Power Station Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV. MDC TYPE STATION LSN DATE NUCLIDE (pCi/kg) (pCi/kg) (pCi/kg)
WW 52 L8121-08 9/22/2004 GROSS BETA 7.40E+00 1.20E+00 3.00E+00 WW 52 L8121-08 9/22/2004 H-3 3.40E+02 4.60E+02 1.40E+03 WW 52 L8121-08 9/22/2004 1-131 -2.20E1+00 4.60E+00 1.80E+01 WW 52 L8121 -08 9/22/2004 Mn-54 3.00E-01 2.10E+00 8.10E+00 NYVN 52 L8121-08 9/22/2004 Zn-65 4.70E+00 4.70E+00 1.70E+01 NWWY 52 [8121-08 9/22/2004 Zr-95 -3.60E+00 3.20E+00 1.40E+01 WW 52 L8352-08 10/27/2004 Ba-140 2.00E+00 3.00E+00 1.30E+01 WW 52 L8352-08 10/27/2004 Co-S8 2.30E+00 2.20E+00 7.80E+00 WW 52 L8352-08 10/27/2004 Co-60 1.70E+00 1.80E+00 7.OOE+00 WW 52 L8352-08 10/27/2004 Cs-134 -1.60E+00 2.90E+00 1.20E+01 WW 52 L8352-08 10/27/2004 Cs-137 6.00E-01 2.20E+00 8.70E+00 WYW 52 L8352-08 10/27/2004 Fe-59 -4.80E+00 4.80E+00 2.60E+01 WW 52 L8352-08 10/27/2004 GROSS BETA 7.00E+00 1.20E+00 2.80E+00 WWY 52 L8352-08 10/27/2004 H-3 5.00E+01 3.30E+02 1.00E+03 NYNY 52 L8352-08 10/27/2004 1-131 -7.00E-01 4.70E+00 1.80E+01 NVNW 52 L8352-08 10/27/2004 Mn-54 3.70E+00 1.50E+00 1.70E+00 NVWV 52 L8352-08 10/27/2004 Zn-65 -4.70E+00 4.10E+00 2.00E+01 WWY 52 L8352-08 10/27/2004 Zr-95 1.70E+00 3.40E+00 1.30E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Mlinimum Detectable Concentration > Lower Limit of Detection Requirement C-62