ML052280415
| ML052280415 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/11/2005 |
| From: | Jesse Rollins Yankee Atomic Electric Co |
| To: | Document Control Desk, NRC/FSME |
| References | |
| BYR 2005-071 | |
| Download: ML052280415 (142) | |
Text
YANKEE ATOMIC ELECTRIC COMPANY Telephone (413)424-5261 49 Yankee Road, Rowe, Massachusetts 01367 August 11, 2005
/E BYR 2005-071 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
- 1. Licensee No. DPR-3 (Docket No. 50-29)
- 2. YAEC Submittal to USNRC, "2004 Annual Radiological Environmental Operating Report", dated April 26, 2005, BYR 2005-042
Subject:
2004 Annual Radiological Environmental Operating Report, Revision 1 Yankee Atomic Electric Company (YAEC) herewith submits the subject report as a revision to the Reference 2 initial report (see Enclosure). Shortly after the initial report was issued, an inadvertent omission was identified. The enclosed Revision 1 of the report corrects this omission. In the initial report, the results for the Decommissioning Air Particulate (DAP) samplers were missing for periods after 3/9/04. These DAP sampler results actually go beyond the scope of the program, as defined in the Off Site Dose Calculation Manual (ODCM); and the actual samplers were installed to confirm that no significant airborne releases occur as a result of decommissioning and demolition activities. When the laboratory performing the analyses recognized that these results were not part of the REMP program, they removed them from the database used for off site monitoring results and stored them in a separate file.
Since a large part of the report contains data and analytical results which are managed by computer programs that automatically generate the data tables every year, only the data stored for the period 2/12/04 (when the DAPs were placed in service) to 3/9/04 (when subsequent data were directed to a different file) were included in the original report. These data tables are spot checked for accuracy during the review of this report prior to issue; however, these omissions were missed. Once identified, the missing data that were stored in the separate computer file were transferred to the correct computer data file, and the report was updated with the new tables. These corrected tables start on page C-2 of Appendix C, "Summary of REMP Data. "
Should you have any questions regarding this revised report, please contact the undersigned at 413424-2300.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Jack D. Rollins.
Licensing and Regulatory Affairs Manager Enclosure J. Hickman, USNRC, Project Manager r
s 5 M. Miller, USNRC, Region 1
[P
.9 I.
I:-,§ C7 -'d i
- f ;
2m-mlz 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-SM1"3-01 Revision I
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE OF CONTENTS 1.0 EXECUTIVE
SUMMARY
1
2.0 INTRODUCTION
2 2.1 General Plant Site Information.......................
2 2.2 Program Design.2 2.3 Monitoring Zones
.3 2.4 Pathways Monitored
.3 2.5 Descriptions 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.36 4.4 Data Analysis by Media Type.36 4.4.1 Air Particulates.36 4.4.2 River Water.37 4.4.3 Ground Water.38 4.4.4 Storm Drain Water.39 4.4.5 Sediment.39 4.4.6 Fish.43 4.4.7 Food.44 4.4.8 Maple Syrup.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 ii
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.
1
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 IOCFR50 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.
2
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, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants; the NRC Branch Technical Position of November 1979 entitled, An Acceptable Radiological Environmental Monitoring Program; and NRC NUREG-0472, Radiological Effluent Technical Specifications for PWR's.
The environmental TLD program was designed and tested around NRC Regulatory Guide 4.13, Performance, Testing and Procedural Specilcationsfor Thermoluminescence Dosimetry: Environmental Applications. The quality assurance program was designed around the guidance given in NRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment.
The sampling requirements of the REMP are given in 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:
3
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
- Airborne Pathway Air Particulate Sampling
- Waterbome Pathways River Water Sampling Ground Water Sampling Storm Drain Water Sampling Sediment Sampling
- Ingestion Pathways Fish Sampling Food Product (fruits & vegetables, broad leaf vegetation)
Maple Syrup Sampling
- Direct Radiation Pathway TLD Monitoring Section 2.5.1 Section 2.5.2 Section 2.5.3 Section 2.5.4 Section 2.5.5 Section 2.5.6 Section 2.5.7 Section 2.5.8 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 22 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 NaHSO3 or HNO3 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 are 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.
5
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-80 I AS I and UD-814AS1 calcium sulfate dosimeters are used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-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
I r
I I
I f
I I '
I I
(
r I
rI I
I I
I 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 1
Composite at two Monthly Gross Beta Each Sample hour intervals-Gamma Isotopic Each Sample Downstream Tritium (H-3)
Quarterly Composite I
Grab -Upstream Monthly
- b. Ground Water 2
Grab Quarterly Gamma Isotopic Each Sample Tritium (H-3)
Each Sample
- 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
I r
I I
I I
I r
f I
I r
r X
I Yankee Nulcear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.1 (Continued)
Radiological Environmental Monitoring Program (Sample Types, Collection Frequency, Analysis Requirements)
(As required by ODCM Table 4.1)
Collection Analysis Exposure Pathway And/or 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
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.2 Radiological Environmental Monitoring Locations (non-TLD) in 2004 Yankee Nuclear Power Station Exnosure Pathway Station Code Distance From Plant Type Stack (krn)
Station Description Direction From Plant Stack
- 1.
Airborne AP-I I(DAP-4*)
AP-12 AP-13 AP-14 AP-21 AP-3 I
- DAP-l*
DAP-2*
DAP-3
- Observation Stand Monroe Bridge Rowe School Harriman Station Williamstown, MA YAEC Visitor's Center Gatehouse ISFSI north fence DEMCO Trailer I
0.5 I
1.1 1
4.2 1
3.2 C
22.2 I
0.8 DI 0.1 DI 0.1 DI 0.1 N
W SW W
SSE NE
- 2.
Waterborne
- a.
Surface WR-1I WR-21 WR-3 I *
- b.
Ground WG-1 I WG-12
- c.
Storm Drain WW-5 I
- WW-52*
- d.
- Bear Swamp Lower Harriman Reservoir Sherman Pond Plant Potable Sherman Spring East Storm Drain West Storm Drain No. 4 Station Harriman Reservoir Sherman Pond 1
6.3 C
10.1 I
0.1 I
On-site 1
0.2 I
On-site I
On-site 1
36.2 C
10.1 1
0.1 Down-river Up-river N
NW Down-river Up-river N
- 3.
Ingestion
- a.
Fish FH-I1 FH-21 Sherman Pond Harriman Reservoir 1
1.5 C
10.1 Near Discharge Up-river a
I=lndicator 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
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.2 (Continued)
Radiological Environmental Monitoring Locations (non-TLD) in 2004 Yankee Nuclear Power Station Distance Exposure Pathway Station Code From Plant TIYpW (km)
Direction From Plant Station Description
- b. Food Products TF-11 TF-13 TF-2 1 MS-33*
(Maple Syrup)
MS-45*
(Maple Syrup)
Monroe Bridge, MA Monroe, MA Williamstown, MA Rowe, MA Florida, MA 1
1.3 I
1.9 C
21.0 1
1.0 C
10.5 SW WNW WSW S
WSW a lndicator 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 Type a (km)'
From Plant GM-I YAEC Visitors' Center I
0.8 SW GM-2 Observation Stand 1
0.5 NW GM-3 Rowe School 1
4.2 SE GM-4 Harriman Station l
3.2 N
GM-5 Monroe Bridge I
1.1 SW GM-6 Readsboro Road Barrier 1
1.3 N
GM-7 Whitingham Line 1
3.5 NE GM-8 Monroe Hill Barrier 1
1.8 S
GM-9 Dunbar Brook l
3.2 SW GM-10 Cross Road 1
3.5 E
GM-I l Adams High Line l
2.1 WNW GM-12 Readsboro, VT l
5.5 NNW GM-13b Restricted Area Fence F
0.08 WSW GM-14b Restricted Area Fence F
0.11 WNW GM-1b Restricted Area Fence F
0.08 NNW GM-16b Restricted Area Fence F
0.13 NNE GM-17b Restricted Area Fence F
0.14 ENE GM-18 b Restricted Area Fence F
0.14 ESE GM-19 Restricted Area Fence F
0.16 SE GM-20b Restricted Area Fence F
0.16 SSE GM-21 Restricted Area Fence F
0.11 SSW GM-22 Heartwellville, VT C
12.6 NNW GM-23 Williamstown Substation C
22.2 W
GM-25 Whitingham, VT 0
7.7 NNE GM-27 Number 9 Road 0
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.
C GM station distances and direction are from the former 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 Power Station Distance From Direction Station Code Station Description Typea Plant/ISFSI From (km)
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
6.6c W
GM-38 West Hill Road 0
6.6 NW GM-40 Readsboro Road I
0.7c W
IF-C ISFSI Security Fence IF 0.02 d WNW IF-2 Observation Stand IF 0.56 d NW IF-3 e ISFSI Security Fence IF 0.02 d N
IF-4 e ISFSI Security Fence IF 0.03 d NE IF-5e ISFSI Security Fence IF 0.05 d E
IF-6 ISFSI Security Fence IF 0.02 d SE IF-7e ISFSI Security Fence IF 0.02 d S
IF-8 e ISFSI Security Fence IF 0.04 d SW IF-9 Restricted Area Fence IF 0.05 d SE IF-1 e Restricted Area Fence IF 0.05 d SSE IF-I1C Restricted Area Fence IF 0.14 d SW IF-12 Restricted Area Fence IF 0.21 d N
IF-18C YNPS CW Intake IF 0.24 d NNW IF-19 e ISFSI Security Fence Admin. Building IF 0.17 d W
IF-20 e ISFSI Security Fence Gatehouse IF 0.24 d WNW IF-40 e 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.
e These TLDs monitor the YNPS ISFSI and are not part of the REMP program.
12
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 2.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements from ODCM Table 4.3 Airborne Food Water Particulates Fish Product Sediment Analysis (pCi/Q) or Gases (pCi/m3)
(pCi/k-g)
(pCi/kg)
(pCifkg -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/rn3)
(pCi/kg)
(pCi/kg)
(pCiAl)*
(wet)
H-3 30000 Mn-54 1000 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 h.-
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 15
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 16
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.3 Radiological Environmental Sampling Locations Outside 12 Miles of Yankee Nuclear Power Station 17
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 19
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
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Figure 2.7 Environmental TLD Monitoring Locations For the ISFSI Facility at the Yankee Nuclear Power Station 21
Yankee 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: (1) 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, Ce-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: PCUcubic meter Indicator Stations Radionuclides' (No. Analyses)
Non-Routine Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected' Control Stations Mean Range No. Detected-GR-B (162)
(0)
Be-7 (24)
(0)
K-40 (24)
(0)
Co-58 (24)
(0)
Co-60 (24)
(0)
Cs-134 (24)
(0)
Cs-137 (24)
(0)
Th-232 (24)
(0) 0.01 2.OE -2
(
6.2 -
39.7)E -3 (135/ 135) 13 2.4E -2
(
1.5 - 4.0)E -2 (27/ 27) 9.2E -2
( 5.1 -
14.9)E -2 (20/ 20)
-2.7E -3 I -2.6 - 1.2)E -2 (0/
20)
-1.2E -4
( -1.0 - 0.8)t -3 (0/
20) 4.1E -5
( -1.0 - 0.8)E -3 (0/
20) 13 1.1E -1
(
6.2 -
14.9)E -2 (4/ 4) 31
- 1. 1E -3
( -8.6 - 8.5)E -3 (0/ 4) 14 2.9E -4 I -4.3 - 8.4)E -4 (0/ 4) 1.8E -2
(
1.2 - 3.3)E -2 (27/ 27) 9.4E -2
(
6.2 - 11.8)E -2 (4/ 4)
-2.4E -3
( -1.4 - 0.8)E -2 (0/
4)
-1.9E -4
( -7.0 - 6.1)E -4 (0/ 4)
-3.0E -4
( -7.2 - 1.9)E -4 (0/
4)
-3.7E -5
( -1.9 - 2.5)E -4 (0/ 4)
-1.3E -4
-1.3 -
1.1)E -3 (0/
4) 5.9E -4
( -4.0 -
13.0)E -4 (0/
4) 31 4.1E -4
(
2.2 - 7.9)E -4 (0/ 4) 0.05 2.OE -5 I -6.8 -
7.0)E -4 (0/ 20) 14 2.6E -4
(
0.0 - 5.9)E -4 (0/ 4) 0.06
-9.OE -5
( -1.3 - 0.8)E -3 (0/
20) 3.2E -4
( -2.5 - 2.1)E -3 (0/ 20) 13 3.6E -4
( -4.2 - 8.2)E -4 (0/ 4) 12 1.1E -3
( 1.0 - 200.0)E -5 (0/ 4) 23 The only radlonuclides 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 3 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 Enironmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Fish (FH)
UNITS: PCilkq Indicator Stations Station With Highest Mean Control Stations Radionudides' (No. Analyses)
Non-Routine Mean Required Range LLD No. Detected-Station Mean Range No. Detected-Mean Range No. Detected-K-40 (4)
(0)
Mn-54 (4)
(0)
Co-58 (4)
(0) 2.9E 3
(
2.3 - 3.4)E 3 (2/
2) 21 3.5E 3
( 3.5 -
3.6)1E 3 (2/
2) 130 130
-3.0E 0
( -1.6 -
1.0)E 1 (0/ 2) 1.5E 1
( 1.0 -
1.9)E 1 (0/
2)
-5.OE 0
( -2.2 - 1.2)E 1 (0/
2) 21 11 11 9.OE 0
( 1.0 -
17.0)E 0 (0/
2) 1.5E 1
(
1.0 -
1.9)E 1 (0/ 2)
-5.OE 0
( -2.2 -
1.2)E 1 (0/
2) 3.5E 3
( 3.5 - 3.6)E 3 (2/ 2) 9.0E 0
( 1.0 -
17.0)E 0 (0/ 2) 3.5E 0
(-1.6
- 2.3)E 1 (0/ 2)
-5.3E 1 t -1.3 - 0.3)E 2 (0/ 2)
Fe-59 (4)
(0)
Co-G0 (4) 130
-5.OE -1 21 (0)
( -1.1 - 1.0)E 1 (0/ 2) 6.0E 0
( -2.0 - 14.0)E 0 (0/
2) 6.0E 0
( -2.0 -
14.0)E 0 (0/
2)
Zn-65 (4) 260 (0) 1.2E 1
( 0.0 - 2.3)E 1 (0/
2) 11 1.2E 1
(
0.0 - 2.3)E 1 (0/
2)
-3.1E 1
( -3.7 - -2.5)E 1 (0/
2) 1.3E 0
( -2.0 -
4.5)1E 0 (0/
2)
Cs-134 (4)
(0) 130 4.9E 0
(
2.6 -
7.1)E 0 (0/
2) 11 4.8E 0
(
2.6 - 7.1)E 0 (0/
2)
Cs-137 (4)
(0) 150 3.7E 1
(
3.5 -
3.9)E 1 (0/
2) 11 3.7E 1
(
3.5 - 3.9)E 1 (0/
2) 7.5E 0 C -6.0 - 21.0)E 0 (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 3 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.
rThe action of sample analyses yielding detectable measurements (ie. >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: Maple Svrup (MS)
UNITS: pCI/kg Radionuclides' (No. Analyses)
Non-Routine-Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected*
Be-7 (2)
(0) 1.8E 1 33 1.8E 1 8.0E 0 (0/
1)
(0/ 1)
(0/
1)
K-40 (2)
(0)
Mn-54 (2)
(0)
Co-57 (2)
(0)
Co-58 (2)
(0)
Fe-59 (2)
(0)
Co-60 (2)
(0)
Zn-65 (2)
(0)
Zr-95 (2)
(0)
Ru-103 (2)
(0)
Ru-I06 (2)
(0)
Ag-110m (2)
(0) 1.9E 3 33 1.9E 3 1.5E 3 (1/
1)
(1/
1)
(1/ 1)
-9.oE -1 45 9.0E -1 9.0E -1 (0/
1)
(0/ 1)
(0/
1)
1)
(0/ 1)
(0/
1) 3.OE -1 45 2.2E 0 2.2E 0 (0/
1)
(0/
1)
(0/
1) 1.6E 1 33 1.6E 1 1.2E 1 (0/
1)
(0/
1)
(0/
1)
-1.0E 0 45 4.0E 0 4.0E 0 (0/
1)
(0/
1)
(0/
1)
-1.1E 1 45 8.3E 0 8.3E 0 (0/
1)
(0/ 1)
(0/
1) 6.0E -1 45 2.2E 0 2.2E 0 (0/
1)
(o/ 1)
(0/ 1)
-2.1E 0 33
-2.1E 0
-3.4E 0 (0/
1)
(0/
1)
(0/ 1) 2.5E 1 33 2.5E 1
-2.0E 0 (0/ 1)
(0/
1)
(0/ 1)
-4.5E 0 45 2.5E 0 2.5E 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 3 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: Maple SVru, (MS)
UNITS: PCikg Radionuciides-(No. Analyses)
Non-Routine" Indicator Stations Mean Required Range LLD No. Detected' Station With Highest Mean Station Mean Range No. Deteded*'
Control Stations Mean Range No. Detected-Sb-124 (2)
(0) 1431 (2)
(0) 2.3E 0 33 2.3E 0
-1.2E 0 (0/
1)
(0/
1)
(0/ 1)
-4.1E 0 45 5.6E 0 5.6E 0 (0/
1)
(0/
1)
(0/ 1)
Cs-134 (2)
(0)
Cs-I37 (2)
(0) 60
-B.OE -1 (0/
1) 80 2.OE 1 33
-8.0E -1
-2.7E 0 (0/
1)
(0/
1) 33 2.OE 1 1.4E 1 (1/
1)
(1/ 1)
(1/
1)
Ba-140 (2)
(0) 8.0E -1 33 8.0E -1
-4.0E -1 (0/ 1)
(0/
1)
(0/
1)
Ce-141 (2)
(0)
-3.6E 0 45
-2.7E 0
-2.7E 0 (0/ 1)
(0/
1)
(0/
1)
Ce-144 (2)
(0) 1.2E 1 33 1.2E 1 4.0E 0 (0/
1)
(0/ 1)
(0/
1)
Th-232 (2)
(0) 2.6E 0 45 3.6E 0 3.6E 0 (0/ 1)
(0/
1)
(0/ 1) 26
'The only radlonuclides 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 3 of this report for a discussion of other radionuclides that were analyzed.
-Non-Routlne refers to those radionucides that exceeded the Reporting Levels In ooCM 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: Sediment (SE)
UNITS: pCI/kg dry Indicator Stations Radionudides' (No. Analyses)
Non-Routine-Mean Required Range LLD No. Detected^
Station With Highest Mean Station Mean Range No. Detected---
Control Stations Mean Range No. Detected-Be-7 (18)
(0)
K-40 (18)
(0)
Co-58 (18)
(0)
Co-60 (18)
(0)
Cs-134 (18)
(0)
Cs-1137 (18)
(0) 8.BE 1
( -4.3 -
7.7)1E 2 (0/
12) 2.0E 4 I
9.7 -
26.4)E 3 (12/ 12)
-6.1E 0
( -7.2 -
4.1)E 1 (0/ 12)
-4.3E 0
( -5.4 -
4.3)E 1 (0/ 12) 91 3.OE 2 I -2.7 -
7.7)E 2 (0/ 6) 91 2.5E 4
(
2.3 -
2.6)E 4 (6/ 6) 91
-3.8E 0
( -5.9 - 4.1)E 1 (0/ 6) 21 1.2E 1
(
0.0 -
2.6)E 1 (0/
6)
-4.7E 1
-4.1 - 2.3)E 2 (0/
6) 1.5E 4 1.3 - 1.8)E 4 (6/ 6)
-1.21 1
-3.6 - 0.4)E 1 (0/
6) 1.2E 1 0.0 -
2.6)1E 1 (0/
6) 9.7E -1 I -2.5 - 5.2)E 1 (0/
6) 1.7E 2
(
6.3 - 27.8)E 1 (4/ 6) 6.0E 2 3.7 - 8.6)E 2 (6/
6) 150 180 3.5E 0
( -8.0 -
9.5)E 1 (0/
12) 6.1E 2
( -1.6 - 135.7)E 1 (9/
12) 1.4E 3
(
5.5 - 22.2)E 2 (12/ 12) 91 5.0E 0 I -8.0 -
9.5)E 1 (0/
6) 91 1.1E 3 9
8.4 - 13.6)1E 2 (6/ 6)
Th-232 (18)
(0) 91 2.0E 3
(
1.7 - 2.2)E 3 (6/ 6) 27 The only radionuclides reported In this table are those with ULD requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 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: Food Cron (TF)
UNITS: oCilkc Indicator Stations Station With Highest Mean Control Stations Radionuclides*
(No. Analyses)
Non-Routine Mean Required Range LLD No. Detected~
Station Mean Range No. Detected-Mean Range No. Detected-K-40 (3)
(0)
Co-58 (3)
(0)
Co-60 (3)
(0) 1431 (3)
(0)
Cs-134 (3)
(0) 3.3K 3
( 9.8 -
55.2)E 2 (2/ 2)
-1.OE -1
( -4.8 - 4.6)E 0 (0/ 2) 6.6E 0
( -1.3 - 2.6)E 1 (0/ 2) 4.5E 0 4 -1.5 - 2.4)E 1 (0/ 2) 60
-1.2E 1
(-1.5
-O.9)E 1 (0/ 2) 13 5.5E 3 1.9E 3 (1/
1)
(1/
1) 13 4.6E 0
-6.3E 0 (0/ 1)
(0/ 1) 13 2.6E 1 1.OE 1 (0/ 1)
(0/ 1) 11 2.4E 1 3.0E 0 (0/ 1)
(0/ 1) 21
-2.7E 0
-2.7E 0 (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 LL D requirements, those for which positive radioactivity was detected, or which were considered important due to past effluent history. See Section 3 of this report for a discussion of other rad lonuclides 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: Ground Water (WG)
UNITS: pCllliter Radionuciides (No. Analyses)
Non-Routine Indicator Stations Mean Required Range LLD No. Detected-Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected*
GR-B (26)
(0)
H-3 (26)
(0)
Mn-54 (26)
(0)
Co-58 (26)
(0)
Fe-59 (26)
(0)
Co-60 (26)
(0)
Zn-65 (26)
(0)
Zr-95 (26)
(0) 1-131 (26)
(0)
Cs-134 (26)
(0)
Cs-137 (26)
(0)
Ba-140 (26)
(0) 4 4.5E 0
(
1.5 -
9.0)E 0 (19/ 26) 12 5.7E 0
(
3.2 -
9.0)E 0 (12/ 13) 2000 1.2E 2
( -2.5 - 5.9)E 2 (4/ 26) 15
-1.9E -2
-3.6 - 3.2)E 0 (0/ 26) 15
-6.6E -1
-2.6 - 2.2)E 0 (0/ 26) 1.2E 0
-7.9 -
16.0)E 0 (0/ 26) 15 4.9E -1
-3.4 -
3.3)E 0 (0/ 26) 30
-2.1E 0
-1.3 - 1.1)E 1 (0/ 26) 15 3.2Z -1
-7.8 -
6.8)E 0 (0/ 26)
-1.5E 0
-1.2 -
1.4)E 1 (0/ 26) 15 2.4E -1
-2.0 -
2.6)E 0 (0/ 26) 18
-3.8E -1
-2.4 -
3.2)E 0 (0/ 26) 6.45 -1
-6.1 -
17.4)E 0 (0/ 26) 12 12 12 2.3E 2
( -1.0 - 59.0)E 1 (4/ 13) 4.5E -1
( -2.6 - 3.2)E 0 (0/ 13)
-4.6E -1
( -2.6 - 2.2)E 0 (0/ 13) 11 I1 11 I1 11 I1 12 2.15 0
-7.9 -
16.0)E 0 (0/ 13) 7.9E -1
-1.8 -
3.2)E 0 (0/ 13)
-1.25 0
-1.2
- 1.1)E 1 (0/ 13) 1.5E 0
-3.6 6.8)E 0 (0/ 13)
-3.6E -1
-6.4 2.8)E 0 (0/ 13) 2.5E -1
( -2.0 -
1.9)E 0 (0/ 13)
-3.8E -2
-2.1 -
3.2)E 0 (0/ 13)
NO DATA NO DATA.
NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 12 1.5E 0
( -3.1 -
17.4)E 0 (0/ 13) 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 3 of this report for a discussion of other red ionuclides that were analyzed.
Non-Routlne refers to those radionuclides that exceeded the Reporting Levels in DOCM Table 4.2.
The fraction of sample analyses yielding detectable measurements lie. >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: River Water iWR)
UNITS: nCi/liter Indicator Stations Radionuclides*
(No. Analyses)
Non-Routine Mean Required Range LiD No. Detected Station With Highest Mean Station Mean Range No. Detected-Control Stations Mean Range No. Detected-GR-B (38)
(0)
H-3 (50)
(0)
Mn-54 (38)
(0)
Co-58 (38)
(0)
Fe-59 (38)
(0)
Co-60 (38)
(0)
Zn-65 (38)
(0)
Zr-95 (38)
(0) 1-131 (38)
(0)
Cs-134 (38)
(0)
Cs-137 (38)
(0)
Ba-140 (38)
(0) 4 2.3Z 0
( 3.2 -
69.0)E -1 (5/
25) 2000
-4.2E 1
-1.0 -
0.8)E 3 (0/ 33) 15
-2.8E -1
-2.8 - 2.2)E 0 (0/ 25) 15
-8.6E -1
-5.4 -
2.1)E 0 (0/ 25)
-1.9E 0
-1.0 - 0.6)E 1 (0/ 25) 15 6.9E -1
-3.4 - 4.3)E 0 (0/ 25) 30
-1.3E 0
-1.5 - 1.0)E 1 (0/ 25) 15
-1.8E -1
-6.9 - 6.9)E 0 (0/ 25) 2.8E -1
-1.1 - 0.8)E 1 (0/ 25) 15 2.8E -1
-2.8 - 3.8)E 0 (0/ 25) 18
-3.3E -1
-3.6 - 2.8)E 0 (0/
25) 6.3E -1
-1.3 - 0.8)E 1 (0/ 25) 11 2.7E 0
( 8.9 -
69.0)E -1 (4/
13) 31
-1.6E 1
( -7.9 - 5.5)E 2 (0/
16) 31
-1.41E -1
( -2.2 - 1.7)E 0 (0/
12) 21
-2.21 -1
( -2.0 - 4.3)E 0 (0/
13)
-3.8E -1
( -1.0 - 0.6)E 1 (0/
12) 1.2E 0
( -3.4 - 4.3)E 0 (0/
12) 8.0E -1
( -8.1 - 7.9)E 0 (0/
13) 8.3E -1
( -2.9 -
6.9)E 0 (0/ 12) 2.4E 0
( -2.0 - 7.1)E 0 (0/ 12) 5.5E -1
( -3.0 - 3.7)E 0 (0/ 13) 1.71 -1
( -1.8 - 2.8)E 0 (0/
13) 1.3E 0
( -2.5 - 5.6)E 0 (0/
12) 1.6E 0 2.6 - 24.4)E -1 (0/
13)
-5.7E 1
-6.7 - 4.8)E 2 (0/ 17)
-9.4E -1
-5.0 - 1.2)E 0 (0/
13)
-2.2E -1
-2.0 - 4.3)E 0 (0/
13)
-1.8E 0
-7.9 - 5.6)E 0 (0/ 13) 8.51 -1
-1.5 -
3.1)E 0 (0/
13) 8.0E -1
-8.1 - 7.9)E 0 (0/
13) 3.41E -1
-9.6 - 8.7)E 0 (0/
13) 6.51E -1
-1.1 - 1.3)E 1 (0/ 13) 5.5E -1
-3.0 - 3.7)E 0 (0/ 13) 5.41E -2
-2.9 - 2.8)E 0 (0/ 13)
S.1E -1
-4.7 -
8.5)E 0 (0/ 13) 30
'The only radionucildes 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 3 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 fie. >3 standard deviations) is shown In parentheses.
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Table 3.1 iRadiolog Ical Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2004)
MEDIUM: Storm Drain Water (WW)
UNITS: oCi/liter Indicator Stations Station With Highest Mean Control Stations Radionudides' (No. Analyses)
Non-Routine-Mean Required Range LLD No. Detected-Station Mean Range No. Detected-Mean Range No. Detected*
GR-B (19)
(0) 4 9.7E 0
(
4.0 -
16.3)E 0 (19/ 19) 61 1.3E 1
(
8.9 - 15.3)E 0 (9/
9)
NO DATA H-3 (19)
(0) 2000 5.4E 1
( -6.6 - 16.3)E 2 (1/
19) 61 1.3E 2
( -6.6 -
16.3)E 2 (1/
9)
NO DATA Mn-54 (19)
(0)
Co-58 (19)
(0)
Fe-59 (19)
(0)
Co-C0 (19)
(0)
Zn-65 (19)
(0)
Zr-95 (19)
(0) 1-131 (19)
(0)
Cs-134 (19)
(0)
Cs-137 (19)
(0)
Ba-140 (19)
(0) 15
-9.4E -1
( -5.6 - 3.7)E 0 (0/
19) 15
-1.4E -1
( -4.9 -
2.4)E 0 (0/
19)
-1.1E -2
( -5.6 -
7.2)E 0 (0/
19) 15 2.1E -1
-2.7 -
6.1)E 0 (0/
19) 30
-2.7E 0
-8.5 -
7.9)E 0 (0/
19) 15 1.3E -1
-5.1 - 3.4)E 0 (0/
19) 9.5E -1
-9.2 - 8.0)E 0 (0/
19) 15
-6.4E -1
-3.3 - 2.9)E 0 (0/
19) 18 3.OE -1
-3.1 -
3.3)E 0 (0/
19) 7.1E -1
-7.2 - 6.9)E 0 (0/
19) 52 52 51 62 52 52 52 52 61
-5.0E -1 t -2.9 - 3.7)E 0 (0/
10)
-6.OE -2
( -4.9 -
2.3)E 0 (0/ 10) 7.8E -2
( -4.2 -
6.5)E 0 (0/
9) 8.2E -1
( -1.4 -
6.1)E 0 (0/
10)
-1.35 0
( -7.2 -
7.9)E 0 (0/
10) 5.0E -1
( -3.6 - 3.4)E 0 (0/
10) 2.4E 0
( -4.9 -
8.0)E 0 (0/
10)
-5.OE -1
-3.3 - 2.9)E 0 (0/
10) 8.9E -1
-2.5 -
3.3)E 0 (0/
9)
NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 52 7.4E -1
( -5.2 - 5.9)E 0 (0/
10) 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 3 of this report for a discussion of other rad lonuclides 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 3.2 ENVIRONMENTAL TLD DATA
SUMMARY
(JANUARY - DECEMBER 2004) piR/hr INDICATOR TLDs MEAN RANGE (NO. MEASI RFMENTS'9*
OUTER RING TLDs MEAN RANGE (NO.
MEASUREMENTS},*
FENCELINE TLDs**
MEAN RANGE (NO. MEASUREMENTS)*
CONTROL TLDS MEAN RANGE (NO. MEASUREMENTS)*
A.................
A...
A..
A..
6.7 +/- 0.4 5.0 8.2 (52) 6.6
+/- 0.4 4.6 10.3 (36) 12.9 +/-
0.7 5.9 34.7 (36) 7.4
- 5.9 -
(8) 0.5 8.4 OFFSITE STATION WITH HIGHEST MEAN STA.
NO.
GM-38 MEAN RANGE (NO. MEASUREMENTS)*
8.4
+
0.4 6.4 10.3 (4)
- Each 'measurement' is based on quarterly readings from five TLD elements. Measurement units are PiR/hr.
32
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE 3.3 2004 ENVIRONMENTAL TLD MEASUREMENTS*
(Micro-R per hour)
Annual 4th Quarter Average 1 st Quarter 2nd Quarter 3rd Quarter Sta.
No.
Descriotion Exoos.
+/-SD Expos.
+/-SD-Exoos.
+/-kSD-*
Exoos.
- SDm Expos.
GM01 YNPS Visitors Center GM02 Observation Stand GM03 Rowe School GM04 Harriman Station.
GM05 Monroe Bridge GM06 Readsboro Rd. Barrier GM07 Whitingham Line GM08 Monroe Hill Barrier GM09 Dunbar Brook GM10 Cross Road GM11 Adams High Line GM12 Readsboro, VT GM13 Indust. Area Fence^
GM14 Indust Area Fence^
GM15 Indust Area Fence GM16 Indust. Area Fence GM17 Indust. Area Fence GM18 Indust. Area Fence-GM19 Indust. Area Fence-GM20 Indust. Area Fence GM21 Indust. Area Fence GM22 Heartwellville, VT GM23 Williamstown.Subst.
GM25 Whitingham GM27 No.9 Road GM29 Route 8A GM31 Legate Road GM32 Rowe Road GM33 Zoar Road GM35 Whitcomb Subst.
GM36 Tilda Road GM38 West Hill Rd GM40 Readsboro Rd 5.00
- 0.23 6.99 0.77 6.36 6.02
- 0.27 7.34
- 0.85 7.04 4.99
+/-0.31 6.35
+/-0.70 5.66 5.51
- 0.35 6.58
+/-0.88 6.48 6.53
- 0.29 7.55
- 0.81 7.28 5.77
- 0.33 7.69
+/-0.59 7.81 6.24
- 0.43 7.76
+/-1.00 7.86 5.55
- 0.30 6.33
+/-0.67 6.35 5.63
- 0.29 7.07
+/-0.61 7.40 6.06
- 0.31 6.20
+/-0.88 7.04 5.37
+/-0.30 6.36
+/-0.55 7.04 7.05
+/-0.32 7.65
+/-0.88 7.80 7.52
+/-0.30 10.03
+/-0.63 9.88 6.31
- 0.35 7.56
+/-0.63 7.61 6.51
+/-0.30 7.30
+/-0.58 7.88 5.93
+/-0.36 6.12
+/-0.77 7.15 6.77
+/-0.34 7.66
- 0.68 8.59 16.32
+/-0.94 25.62
+/-1.25 25.83 33.86
+/-1.54 32.03
+/-1.97 32.44 12.24
+/-0.56 13.37
+/-0.79 14.18 6.44
+/-0.35 7.28
+/-0.61 7.85 5.88
+/-0.38 7.41
+/-0.69 7.61 7.29
+/-0.32 7.10
+/-0.65 7.91 4.56
+/-0.23 4.91
+/-0.52 6.05 4.83
+/-0.24 5.13
+/-0.61 6.54 4.91
+/-0.23 4.68
+/-0.54 5.83 5.50
+/-0.32 5.47
+/-0.52 6.45 5.80
+/-0.35 7.93
+/-0.63 6.98 6.26
+/-0.29 7.83
+/-0.81 7.35 6.61
+/-0.82 7.84
+/-0.62 7.76 5.93
+/-0.52 7.29
+/-0.87 7.53 6.43
+/-0.36 8.70
+/-0.67 8.25 5.24
+/-0.27 7.14
+/-0.64 7.47
+/-0.29 6.26
+/-0.38 6.83
+/-0.31 5.80
+/-0.27 6.52
+/-0.34 7.65
+/-0.30 7.64
+/-0.28 7.81
+/-0.31 6.54
+/-0.33 7.62
- 0.23 6.78
+/-0.37 6.50
+/-0.29 8.20
+/-0.36 10.17
+/-0.43 7.44
+/-0.37 8.25
+/-0.47 6.96
+/-0.56 8.72
+/-0.88 27.33
+/-1.23 34.68
+/-0.57 13.84
+/-0.32 8.44
- 0.31 7.74
+/-0.43 8.41
+/-0.41 5.81
+/-0.27 6.25
+/-0.32 5.76
+/-0.28 6.42
+/-0.33 7.00
+/-0.28 7.82
+/-0.32 7.88
+/-0.36 7.01
+/-0.35 10.27
+/-0.42 7.49
+/-0.36
- 0.42
- 0.33
+/-0.26
+/-0.24
+/-0.40
+/-0.26
+/-0.43
+/-0.26
+/-0.30
- 0.34
- 0.36
+/-0.49
- 0.39
+/-0.34
+/-0.30
+/-0.41
- 1.26
- 1.22
+/-0.55
+/-0.51
+/-0.34
+/-0.78
+/-0.22
+/-0.23
+/-0.26
+/-0.22
- 0.46
+/-0.30
+/-0.27
- 0.25
- 0.33
+/-0.38 6.2 6.8 5.7 6.3 7.3 7.2 7.4 6.2 6.9 6.5 6.3 7.7 9.4 7.2 7.5 6.5 7.9 23.8 33.3 13.4 7.5 7.2 7.7 5.3 5.7 5.3 6.0 6.9 7.3 7.5 6.9 8.4 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) 1 st Quarter 2nd Quarter 3rd Quarter Sta.
No.
Annual 4 tS Quarter Average Dos.
+/-SD-Expos.
Description Exoos.
+/-SD' Exoos.
+/-SD-Exoos.
tSD-Exi IF-i ISFSI Security Fence-IF-2 Observation Stand-IF-3 ISFSI Security Fence*
IF-4 ISFSI Security Fence*
IF-5 ISFSI Security Fence-IF-6 ISFSI Security Fence" IF-7 ISFSI Security Fence-IF-8 ISFSI Security Fenced IF-9 Restricted Area Fence*
IF-10 Restricted Area Fence-IF-i1 Restricted Area Fence' IF-12 Restricted Area Fence-IF-18 YNPS CW Intake- (a)
IF-19 ISFSI Security Fence Admin. Building-IF-20 ISFSI Security Fence Gatehouse-IF-40 Readsboro Roads 360.27 5.39
+/-29.29
+/-0.21 371.24 5.91
+/-23.15
+/-1.00 349.51 6.58
+/-34.19 329.34
+/-0.35 6.56
+/-26.38 352.6
+/-0.28 6.1
+/-20.45 435.5 460.94
+/-12.88 428.8
+/-17.09 423.26
+/-14.88 428.82 261.41
+/-7.83 350.18
+/-8.08 190.21
+/-21.29 28.6
+/-2.03 48.1
+/-1.51 22.1
+/-1.47 9.18
+/-0.42 6.3
+/-0.36 6.09
+/-0.23 7.62
+/-0.23 6.96
+/-0.23 5.27
+/-0.23 135.2 268.44 351.16 187.44 29.31 48.31 23.58 11.75 7.84 6.80 9.52 7.38 7.09
+/-5.74
+/-14.68
+/-28.76
+/-9.15
+/-1.58
+/-2.85
+/-1.45
+/-0.84
+/-0.89
+/-0.82
+/-0.78
+/-2.74
+/-0.67 136.54 247.15 321.14 176.9 27.93 47.26 22.02 11.21 7.64 7.59 9.13 7.74 7.23
+/-8.37 131.8
+/-8.63 271.5
+/-19.13 339.94
+/-6.43 181.92
+/-1.97 30.08
+/-2.17 51.63
+/-1.44 23.69
+/-0.49 12.08
+/-0.31 7.6
+/-0.42 8.4
+/-0.35 9.16
+/-0.29 8.05
+/-0.30 6.81
+/-10.42
+/-11.90
+/-12.23
+/-5.09
+/-1.68
+/-1.87
+/-0.68
+/-1.13
+/-0.37
+/-0.52
+/-0.43
+/-0.31
+/-0.44 134.5 262.1 340.6 184.1 29.0 48.8 22.8 11.1 7.3 7.2 8.9 7.5 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
Yankee 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 was one program deviation noted in the REMP during 2004.
On January 3, 2005 the December 2004 sample for Sherman Pond river water (WR-3 1) could not be obtained due to decommissioning activities.
Routine non-REMP sample collection had the following 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-5 1, respectively). On February 25, 2004 WW-51 was not sampled due to ice blockage. During November and December 2004 WW-51 and WW-52 could not be sampled because they were closed to accommodate decommissioning work.
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 posteriori or after the fact LLD (or minimum detectable concentration - MDC) calculated for that analysis was compared with the required a priori LLD. 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.
35
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 4.3 RESULTS COMPARED AGAINST REPORTING LEVELS ODCM Control 4.1.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 I. 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.
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 4-11.
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-1 1, -12, -13, -14, and -31 in the plant vicinity, and one is a control station, AP-3lin 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
-Indicators 0.04
- 0.04 0.03 --
0.03 0.02 0.02 0.01-0.01 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 36 c-O1
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.
Flaure 42 Yankee Rowe Bi-Weekly Air Particulate Gross Beta Analysis Results 0.05 -_
0 AP-1 I Observation Stand 0045 -
-- AP-12 Monroe Bridge AP-13 Rowe School
- AP-14 Harriman Station 0.04
-~-
e 0
- AP-21 Williamstown, MA AP-31 Furlon House 0.035- -
0.03 -
0.025 -~~N 0.02 --
p-I 1'
Lo~-
/___
0.01 0.005 Jan-3 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-11 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 (t
0
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-1 1 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 Gross-Beta Measurements of River Water (Semi-Annual Averages) 4 3
I 2
0
§
__________sas4§ i
I I
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-l 1 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.
Fflure 44 Tritium In Ground Water Station WG-12, Sherman Spring 1700
~700 200
'A fs A
.3001
- 5E g
sN
- Note that these samples are not required by the REMP program.
400 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-l l 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-Il 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-l l 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-Il 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-11 400.00 Month/Year 0 0-5 cm
- 5-10 cm 0 10-15 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
}
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 O 0-5 cm
- 5-10cm 0 10-15 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 location opposite the plant former discharge into Sherman Pond. It is believed that the higher Cs-137 levels at SE-91, whether 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.
41
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 on 2000 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 0 0-5 cm
- 5-10 cm 010-15cm 42
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 4.4.6 Fish (See Figure 4-8)
Semiannual samples of fish were collected from two locations during 2004, FH-lI, an indicator station in Sherman Pond, and FH-21, 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 K-40 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 are 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 be 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 are 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 -
40 30 h
I I
20 -
10 0
1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year
.FH-I I Sherman Pond l FH-21 Harriman Reservoir (control) 4.4.7 Food Three food samples were collected from indicator stations TF-I1 and TF-13 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 C
01
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 & 4-11)
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 1J 1j
-x-Indicators Control
£A-Outer Ring 10
- 0 a-I 15 10 5
0 raT
,}K,..
5 0
i i
I I
I I
I I
. I 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 45 J D'
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 0
GM-OI YAEC Visitores Center GM-02 Observation Stand
GM-03 Rowe School GM-04 Harriman Station NE GM-05 Monroe Bridge GM-06 Readsboro Road Barrier GM-07 Whitingham Line GM-08 Monroe Hill Barrier GM-09 Dunbar Brook GM-IO Cross Road GM-Il Adams High Lane GM-12 Readsboro, VT 10
-GM-40 Readsboro Road 10 10 -
5v 0
20 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 GM-13RestrictedAreaFence GM-14RestrictedAreaFence GM-15 Restricted Area Fence --
GM-16 Restricted Area Fence 35-W GM-17 Restricted Area Fence -O-GM-18 Restricted Area Fence 30
+
GM-19 Restricted Area Fence -
GM-20 Restricted Area Fence GM-21 Restricted Area Fence X
/
e 25 20 20 5
100 1996 1997 1998 1999 2000 2001 2002 2003 2004 47 A
L - By'
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 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 CFR190, is 25 mRem to the whole body, 75 mRem to the thyroid, and 25 mRem to any other organ. These standards are a fraction of the USA background radiation of 300 mRem per year given in NCRP 94 (Reference 3).
During 2004 there were no instances of plant-related 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 Be-7 in air particulate samples, and gross beta in water samples, K-40 and Cs-137 in fish, K-40 and Cs-137 and Ac-Th-228 in river sediment, and K40 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 1 kg of maple syrup at the average measured concentration of 17 pCi/kg of Cs-137 would be approximately 0.0056 mrem/yr (Child, Bone). Note that the source for Cs-137 is credited to weapons-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
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
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, Appendix 1, Rev. 1, October, 1977.
- 3.
Exposure of the Population in the United States and Canadafrom Natural Background Radiation. NCRP Report No.
- 94. National Council on Radiation Protection and Measurements, Bethesda, Maryland, 1994.
49
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 APPENDIX A - LAND USE CENSUS FOR 2004 A-l
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 re-evaluation 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. 1.
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)
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) 5 2.1(1.3) 2.8 (1.8) 3.2 (2.0)**
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
SUMMARY
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 are routinely submitted in triplicate to evaluate the bias and precision of a measurement process. Table B. I 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 3m" 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 pre-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 are taken. The FANPEL internal acceptance criteria are summarized at the end of Table B. 1.
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 (d20.1%) and precision (+/-12.8%). Third Party QC results are summarized below.
B-3
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Percentage of Individual Analyses that passed FANPEL Internal Criteria Dosimeter Type Number
% Passed Bias Criteria
% Passed Precision Tested Criteria Panasonic Environmental 90 100 100 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 11, high energy
-0.3 + 1.0 Q2/2004 11, high energy 2.8 + 1.4 Q3/2004 11, 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 1 5 0
0 0
0 0
0 III. 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
Iodine-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 7
Sum of Analyses 665 215 (1) Percent Bias Criteria by Bias Category Bias Category = I > 0%/o and < = 5%
Bias Category = 2 > 5% and < = 10%
Bias Category = 3 > 10% and < = 15%, or within 2 sigma of known Gross alphalbeta water, Sr 89/90 > 10% and < = 25%
Transuranics > 10%/ and <= 20%/c Bias Category = 4 Outside Criteria (2) Percent Precision Criteria by Precision Category Precision Category = 1 > 0% and < = 5%
Precision Category = 2 > 5% and < = 10%
Precision Category= 3 > 100/o and <= 15%/6, or within 2 sigma of mean Precision Category = 4 Outside Criteria B-5
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 TABLE B.2 FANPEL RESULTS IN THE ANALYTICS INC. CROSS CHECK PROGRAM Quarter 4, 2003 - Quarter 3, 2004 Sample Quarter/
Sample Reported Known Ratio: E-LABI 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-137 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 4th/2003 Milk gamma 91 90 1.01 Agreement 1-1 31 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 1 st12004 Water Gross Alpha 72.3 74.5 0.97 Agreement Gross Beta 286 301 0.95 Agreement E4058-162 1 st/2004 Water 1-131LL 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-134 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/Liter (Filters in pCi)
B-6
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 Quarterl Sample Reported Known Ratio E4LABI 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 I st/2004 Filter Gross Alpha 48.1 58.9 0.82 Agreement Gross Beta 231 218 1.06 Agreement E4061-162 1st12004 Milk 1-131 LL 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-1 34 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 1st12004 Milk Sr-89 86.2 103 0.84 Agreement Sr-90 12.7 12.1 1.05 Agreement E4059-162 1 st/2004 Water Sr-89 107.7 123 0.88 Agreement Sr-9o 14.85 14.5 1.02 Agreement E4182-162 2nd12004 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 2nd/2004 Filter Ce-141 86 88.3 0.97 Agreement Cr-51 127 128 0.99 Agreement Cs-134 54 56.9 0.94 Agreement Cs-137 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 2ndl2004 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 1-131LL 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 filter dissolution, sample re-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 Quarter/
Sample Reported Known Ratio E-LABI Number Year Media Nuclide Value Value Analytics Evaluation E4186-162 2nd/2004 Milk Cs-134 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 1-31 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 1-131LL 79.4 83.5 0.95 Agreement Ce-141 240 235 1.02 Agreement Cr-51 214 210 1.02 Agreement Cs-134 89.5 90.6 0.99 Agreement Cs-137 204 202 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 l
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 Annual Radiological Environmental Operating Report 2004 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 I
L7069-01 2/12/2004 AcTh-228
-5.70E-03 3.80E-03 2.OOE-02 AP-DAP I
L7069-01 2/12/2004 Be-7 2.40E-02 1.90E-02 6.30E-02 AP-DAP I
L7069-01 2/12/2004 Co-58
-4.20E-03 2.OOE-03 1.OOE-02 AP-DAP I
L7069-01 2/12/2004 Co-60
-6.OOE-04 1.40E-03 6.60E-03 AP-DAP I
L7069-01 2/12/2004 Cs-134 9.OOE-04 1.80E-03 6.90E-03 AP-DAP I
L7069-01 2/12/2004 Cs-137
-7.OOE-04 1.50E-03 6.20E-03 AP-DAP I
L7069-01 2/12/2004 K-40
-3.00E-02 2.OOE-02 9.50E-02 AP-DAP I
L7071-01 2/24/2004 AcTh-228
-5.70E-03 3.70E-03 1.80E-02 AP-DAP 1
L707 -01 2/24/2004 Be-7 4.20E-02 I.50E-02 4.40E-02 AP-DAP I
L7071-01 2/24/2004 Co-58 O.OOE+00 1.20E-03 5.20E-03 AP-DAP I
L707 1-01 2/24/2004 Co-60
-1.OOE-03 1.40E-03 6.40E-03 AP-DAP I
L7071-01 2/24/2004 Cs-134 2.90E-03 1.40E-03 4.30E-03 AP-DAP I
L7071-01 2/24/2004 Cs-137 1.50E-03 1.IOE-03 3.50E-03 AP-DAP I
L7071-01 2/24/2004 K-40
-4.OOE-03 1.40E-02
- 6. 1OE-02 AP-DAP I
L7054-01 3/9/2004 Acil-228 4.OOE-04 4.30E-03 1.80E-02 AP-DAP I
L7054-01 3/9/2004 Be-7
- 5. IOE-02 1.80E-02 5.OOE-02 AP-DAP I
L7054-01 3/9/2004 Co-58 O.OOE+00 1.90E-03 7.30E-03 AP-DAP I
L7054-01 3/9/2004 Co-60
-1.60E-03 1.20E-03 6.40E-03 AP-DAP I
L7054-01 3/9/2004 Cs-134
-4.OOE-04 I.OOE-03 4.70E-03 AP-DAP I
L7054-01 3/9/2004 Cs-137
-2.OOE-03 1.20E-03 5.70E-03 AP-DAP I
L7054-01 3/9/2004 K-40 I.OOE-03 1.50E-02 6.20E-02 AP-DAP I
L7121-01 3/25/2004 AcTh-228
-7.OOE-04 2.90E-03 1.20E-02 AP-DAP I
L7121-01 3/25/2004 Be-7 2.32E-02 9.70E-03 2.90E-02 AP-DAP I
L7121-01 3/25/2004 Co-58
-1.23E-03 7.OOE-04 3.60E-03 AP-DAP I
L7121-01 3/25/2004 Co-60
-9.OOE-04 I.OOE-03 4.60E-03 AP-DAP I
L7121-01 3/25/2004 Cs-134
-5.30E-04 6.40E-04 3.00E-03 AP-DAP I
L7121-01 3/25/2004 Cs-137 7.70E-04 8.40E-04 3.OOE-03 AP-DAP I
L7121-01 3/25/2004 K-40
-5.80E-03 7.90E-03 3.90E-02 AP-DAP I
L7191-01 3/31/2004 Aclh-228
-3.00E-03 I.IOE-02 4.50E-02 AP-DAP I
L7191-01 3/31/2004 Be-7 9.30E-02 4.20E-02 1.30E-OI AP-DAP I
L7191-01 3/31/2004 Co-58 3.20E-03 4.20E-03 I.SOE-02 AP-DAP I
L7191-01 3/31/2004 Co-60 8.40E-03 3.70E-03 9.50E-03 AP-DAP I
L7191-01 3/31/2004 Cs-134 4.00E-04 2.40E-03 9.90E-03 AP-DAP I
L7191-01 3/31/2004 Cs-137 3.60E-03 3.20E-03 I.IOE-02 AP-DAP I
L7191-01 3/31/2004 K-40 1.23E-01 5.40E-02 1.60E-0I AP-DAP I
L7218-01 4/12/2004 AcTh-228 5.80E-03 4.90E-03 1.70E-02 AP-DAP I
L7218-01 4/12/2004 Be-7 3.40E-02 2.20E-02 7.20E-02 AP-DAP I
L7218-01 4/12/2004 Co-58 3.30E-03 2.00E-03 6.1OE-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 Annual Radiological Environmental Operating Report 2004 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 I
L7218-01 4/12/2004 Co-60 1.OOE-03 2.1OE-03 8.30E-03 AP-DAP I
L7218-01 4/12/2004 Cs-134
-5.00E-04 1.80E-03 7.70E-03 AP-DAP I
L7218-01 4/12/2004 Cs-137
-1.96E-03 8.80E-04 5.40E-03 AP-DAP I
L7218-01 4/12/2004 K-40
-I.OOE-02 1.80E-02 8.60E-02 AP-DAP I
L7343-01 4/14/2004 Ac1h-228 1.60E-02 2.90E-02 1.20E-01 AP-DAP I
L7343-01 4/14/2004 Be-7 2.30E-02 9.60E-02 3.70E-01 AP-DAP I
L7343-01 4/14/2004 Co-58 1.40E-03 8.SOE-03 3.70E-02 AP-DAP I
L7343-01 4/14/2004 Co-60
-5.OOE-03 5.00E-03 3.50E-02 AP-DAP I
L7343-01 4/14/2004 Cs-134
-4.OOE-03 9.SOE-03 4.20E-02 AP-DAP I
L7343-01 4/14/2004 Cs-137 1.40E-02 1.lOE-02 3.80E-02 AP-DAP I
L7343-01 4/14/2004 K-40 2.00E-02 1.40E-01 5.70E-01 AP-DAP I
L7347-01 4/26/2004 AcTh-228 4.30E-03 5.60E-03 2.SOE-02 AP-DAP I
L7347-01 4/26/2004 Be-7 6.20E-02 2.40E-02 7.30E-02 AP-DAP I
L7347-01 4/26/2004 Co-58
-1.IOE-03 2.1OE-03 8.90E-03 AP-DAP I
L7347-01 4/26/2004 Co-60
-3.40E-03 1.80E-03 9.SOE-03 AP-DAP I
L7347-01 4/26/2004 Cs-134
-6.OOE-04 1.70E-03 7.10E-03 AP-DAP I
L7347-01 4/26/2004 Cs-137 2.1OE-03 1.SOE-03 4.90E-03 AP-DAP I
L7347-01 4/26/2004 K40 3.00E-03 l.90E-02 8.00E-02 AP-DAP I
L7418-01 5/10/2004 AcTh-228 3.90E-03 3.40E-03 1.20E-02 AP-DAP I
L7418-01 5/10/2004 Be-7 8.70E-02 2.30E-02 6.20E-02 AP-DAP I
L7418-01 5/10/2004 Co-58
-I.00E-04 1.60E-03 6.80E-03 AP-DAP I
L7418-01 5/10/2004 Co-60 6.OOE-04 1.20E-03 S.20E-03 AP-DAP I
L7418-01 5/10/2004 Cs-134 2.00E-04 1.IOE-03 4.80E-03 AP-DAP I
L7418-01 5/10/2004 Cs-137 1.60E-03 1.70E-03 6.20E-03 AP-DAP I
L7418-01 5/10/2004 K-40
-3.20E-02 2.00E-02 9.90E-02 AP-DAP I
L7469-01 5/24/2004 AcTh-228 9.OOE-04 4.00E-03 1.60E-02 AP-DAP I
L7469-01 5124/2004 Be-7 8.60E-02 2.00E-02 5.30E-02 AP-DAP I
L7469-01 5124/2004 Co-58
-1.I OE-03 1.30E-03 6.00E-03 AP-DAP I
L7469-01 5/24/2004 Co-60 9.00E-04 1.30E-03 5.20E-03 AP-DAP I
L7469-01 5/24/2004 Cs-134 1.40E-03 1.40E-03 5.OOE-03 AP-DAP I
L7469-01 5/24/2004 Cs-137 1.20E-03 1.30E-03 4.60E-03 AP-DAP I
L7469-01 5/24/2004 K40
-2.20E-02 1.70E-02 8.10E-02 AP-DAP I
L7558-01 6/7n2004 Ac1h-228
-1.IOE-03 5.90E-03 2.40E-02 AP-DAP I
L7558-01 6/7/2004 Be-7 3.30E-02 2.20E-02 7.20E-02 AP-DAP I
L7558-01 6/7/2004 Co-58 I.90E-03 1.60E-03 5.50E-03 AP-DAP I
L7558-01 6/7/2004 Co-60 l.lOE-03 1.50E-03 6.OOE-03 AP-DAP I
L7558-01 6/7/2004 Cs-134
-4.00E-04 1.80E-03 7.SOE-03 AP-DAP I
L7558-01 6/7/2004 Cs-137 I.90E-03 1.30E-03 4.10E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-3
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
NUCLIDE MDC (pCi/m3)
AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP I
L7558-01 L7610-01 I
L7610-01 I
L7610-01 L7610-01 I
L7610-01 I
L7610-01 L7610-01 I
L7672-01 I
L7672-01 I
L7672-01 I
L7672-01 I
L7672-01 I
L7672-01 I
L7672-01 I
L7752-01 I
L7752-01 L7752-01 I
L7752-01 I
L7752-01 I
L7752-01 I
L7752-01 I
L7839-01 I
L7839-01 I
L7839-01 I
L7839-01 I
L7839-01 I
L7839-01 L7839-01 I
L7905-01 I
L7905-01 I
L7905-01 I
L7905-01 I
L7905-01 I
L7905-01 I
L7905-01 L7982-01 L7982-01 6/7/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 8/9/2004 8/9/2004 8/9/2004 8/9/2004 8/9/2004 8/9/2004 8/9/2004 8/23/2004 8/23/2004 K-40 AcTh-228 Be-7 Co-58 CO-60 Cs-134 Cs-137 K-40 Ac'll-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7
-1.80E-02 3.00E-04 8.70E-02 0.00E+00 3.70E-04
-1.70E-03 O.OOE+00
-2.00E-03
-1.80E-03 9.50E-02 O.OOE+00
-1.90E-03 O.OOE+00
-2.40E-03 1.40E-02 6.00E-03 1.03E-OI 1.80E-03 O.OOE+00
-2.30E-03 4.00E-04
-9.OOE-03 5.20E-03 7.70E-02 2.00E-04 1.I OE-03 9.OOE-04 3.00E-04 4.00E-03
-1.80E-03 9.702-02
-1.00E-04 1.9023-03 7.00E-04
-. 00E-04 1.70E-02 5.70E-03 7.70E-02 1.20E-02 3.20E-03 1.80E-02
- 1. IOE-03 7.60E-04 1.302-03
- 1. IOE-03 1.40E-02 7.10E-03 2.50E-02 2.102-03 2.40E-03 2.00E-03 1.60E-03 2.60E-02 5.70E-03 2.10E-02 1.70E-03 9.10E-04 1.70E-03 1.20E-03
- 2. 10E-02 5.20E-03 1.802-02 1.20E-03 1.502-03 1.20E-03 1.20E-03 1.502-02 4.402-03 2.10E-02 1.40E-03 1.20E-03 1.30E-03 1.40E-03 2.30E-02 5.70E-03 2.20E-02 7.20E-02 1.40E-02 4.40E-02 4.50E-03 3.30E-03 5.80E-03 4.50E-03 5.90E-02 2.90E-02 6.80E-02 8.30E-03 1.IOE-02 8.202-03 7.70E-03 1.002-01 2.002-02 4.60E-02 5.90E-03 4.70E-03 8.00E-03 5.00E-03 9.30E-02 1.90E-02 4.20E-02 5.10E-03 5.80E-03 4.50E-03 4.60E-03 6.50E-02 1.90E-02 5.30E-02 5.60E-03 3.90E-03 4.90E-03 5.50E-03 8.40E-02 2.00E-02 6.10E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C4
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 I
L7982-01 8/23/2004 Co-58 4.00E-04 1.50E-03 5.90E-03 AP-DAP I
L7982-01 8/23/2004 Co-60
-2.00E-04 1.50E-03 6.30E-03 AP-DAP I
L7982-01 8/23t2004 Cs-134 1.90E-03 1.50E-03 5.20E-03 AP-DAP I
L7982-01 8/23/2004 Cs-137
-7.00E-04 1.30E-03 5.40E-03 AP-DAP I
L7982-01 8/23/2004 K-40 1.90E-02 1.80E-02 6.40E-02 AP-DAP I
L8045-01 9/712004 AcTh-22S 4.40E-03 3.70E-03 1.30E-02 AP-DAP I
L8045-01 9/7/2004 Be-7 9.30E-02 1.60E-02 3.60E-02 AP-DAP I
L8045-01 9/7/2004 Co-58 6.OOE-04 I.IOE-03 4.1OE-03 AP-DAP I
L8045-01 9/7/2004 Co-60 6.OOE-04 I.IOE-03 4.10E-03 AP-DAP I
L8045-01 9/72004 Cs-134 8.00E-04 1.30E-03 4.70E-03 AP-DAP I
L8045-01 9/7/2004 Cs-137
-1.20E-03 7.70E-04 3.80E-03 AP-DAP I
L8045-01 9/7/2004 K40 1.90E-02 1.40E-02 4.80E-02 AP-DAP I
L8120-01 9/21/2004 AcTh-228
-2.103E-03 3.20E-03 1.60E-02 AP-DAP I
L8120-01 9/21/2004 Be-7 6.50E-02 1.60E-02 4.10E-02 AP-DAP I
L8120-01 9/21/2004 Co-5S
-9.70E-04 6.90E-04 4.20E-03 AP-DAP I
L8120-01 9/21/2004 Co-60 5.00E-04 1.40E-03 5.70E-03 AP-DAP I
L8120-01 9/21/2004 Cs-134 7.00E-04 I.lOE-03 4.20E-03 AP-DAP I
L8120-01 9/21/2004 Cs-137
-1.03E-03 9.10E-04 4.50E-03 AP-DAP I
L8120-01 9/21/2004 K-40
-1.70E-02 1.50E-02 7.60E-02 AP-DAP I
L8150-01 9/29/2004 AcTh-228
-2.80E-03 8.1OE-03 3.30E-02 AP-DAP I
L8150-01 9/29/2004 Be-7 1.05E-01 2.90E-02 8.20E-02 AP-DAP I
L8150-01 9/29/2004 Co-58 2.30E-03 1.60E-03 5.30E-03 AP-DAP I
L8150-01 9/29/2004 Co-60 2.80E-03 1.80E-03 5.60E-03 AP-DAP I
L8150-01 9/29/2004 Cs-134
-I.OOE-03 2.20E-03 9.30E-03 AP-DAP I
L8150-01 9/29/2004 Cs-137 3.00E-04 2.20E-03 8.40E-03 AP-DAP I
L8150-01 9/29/2004 K-40 4.90E-02 3.60E-02 1.20E-01 AP-DAP I
L8296-01 10/14/2004 AcTh-228
-1.50E-03 3.00E-03 1.50E-02 AP-DAP I
L8296-01 10/14/2004 Be-7 8.80E-02 1.80E-02 3.80E-02 AP-DAP I
L8296-01 10/14/2004 Co-58
-1.40E-04 9.00E-04 4.20E-03 AP-DAP I
L8296-01 10/14/2004 Co-60
-7.00E-04 I.IOE-03 5.70E-03 AP-DAP I
L8296-01 10/14/2004 Cs-134 I.00E-03 1.30E-03 4.70E-03 AP-DAP I
L8296-01 10/14/2004 Cs-137 1.30E-03 I.OOE-03 3.50E-03 AP-DAP I
L8296-01 10/14/2004 K40
-2.00E-02 1.30E-02 7.00E-02 AP-DAP I
L8345-01 10/26/2004 Acll-228
-2.00E-03 2.90E-03 1.60E-02 AP-DAP 1
L8345-01 10/26/2004 Be-7 2.20E-02 1.40E-02 4.50E-02 AP-DAP I
L8345-01 10/26/2004 Co-58
-8.00E-04 1.40E-03 6.20E-03 AP-DAP I
L8345-01 10/26/2004 Co-60
-3.00E-04 2.1 OE-03 8.90E-03 AP-DAP I
L8345-01 10/26/2004 Cs-134 2.80E-03 1.40E-03 3.80E-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 Annual Radiological Environmental Operating Report 2004 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 I
L8345-01 10/26/2004 Cs-137
-3.90E-04 8.70E-04 4.20E-03 AP-DAP I
L8345-01 10/26/2004 K-40 1.20E-02 2.20E-02 8.40E-02 AP-DAP I
L8418-01 11/8/2004 AcTh-228
-2.OOE-03 6.10E-03 2.50E-02 AP-DAP I
L8418-01 11/8/2004 Be-7 3.60E-02 I.50E-02 4.40E-02 AP-DAP I
L8418-01 11/8/2004 Co-58 5.00E-04 1.60E-03 6.20E-03 AP-DAP I
L8418-01 11/8/2004 Co-60 1.16E-03 8.20E-04 1.60E-03 AP-DAP I
L8418-01 11/8/2004 Cs-134 2.20E-03 1.30E-03 4.1OE-03 AP-DAP I
L8418-01 11/8/2004 Cs-137 1.OOE-04 1.IOE-03 4.50E-03 AP-DAP I
L8418-01 11/8/2004 K-40
-5.00E-03 2.00E-02 8.40E-02 AP-DAP I
L8482-01 11/21/2004 Acll-228
-7.20E-03 5.50E-03 2.70E-02 AP-DAP I
L8482-01 11/21/2004 Be-7 4.70E-02 1.60E-02 4.40E-02 AP-DAP I
L8482-01 11/21/2004 Co-58 9.00E-04 1.IOE-03 4.1OE-03 AP-DAP I
L8482-01 11/21/2004 Co-60 6.00E-04 1.30E-03 5.80E-03 AP-DAP I
L8482-01 11/21/2004 Cs-134
-1.50E-03 1.80E-03 8.OOE-03 AP-DAP I
L8482-01 11/21/2004 Cs-137 8.00E-04 L.OOE-03 3.90E-03 AP-DAP I
L8482-01 11/21/2004 K-40
-1.40E-02 1.80E-02 8.80E-02 AP-DAP I
L8550-01 12/6/2004 AcTh-228 5.SOE-03 5.80E-03
- 2. IOE-02 AP-DAP I
L8550-01 12/6/2004 Be-7 9.OOE-02 1.90E-02 4.40E-02 AP-DAP I
L8550-01 1216/2004 Co-58 8.OOE-04 1.20E-03 4.90E-03 AP-DAP I
L8550-01 12/6/2004 Co-60 4.00E-04 1.90E-03 7.90E-03 AP-DAP I
L8550-01 12/6/2004 Cs-134
-2.00E-04 1.30E-03 5.60E-03 AP-DAP I
L8550-01 12/6/2004 Cs-137
-4.00E-04 I.OOE-03 4.70E-03 AP-DAP I
L8550-01 12/6/2004 K-40
-7.00E-03 1.80E-02 8.40E-02 AP-DAP I
L8603-01 12/21/2004 AcTh-228
-3.40E-03 4.20E-03 1.90E-02 AP-DAP I
L8603-01 12/21/2004 Be-7 4.90E-02 1.40E-02 3.80E-02 AP-DAP I
L8603-01 12/21/2004 Co-58 4.30E-04 7.30E-04 3.OOE-03 AP-DAP I
L8603-01 12/21/2004 Co-60 4.00E-04 1.IOE-03 4.80E-03 AP-DAP I
L8603-01 12/21/2004 Cs-134
-I.00E-03 1.30E-03 5.70E-03 AP-DAP I
L8603-01 12/21/2004 Cs-137
-3.00E-04 1.20E-03 4.70E-03 AP-DAP I
L8603-01 12/21/2004 K-40 L.OOE-02 1.80E-02 6.60E-02 AP-DAP 2
L7069-02 2/12/2004 Be-7
-1.40E-02 1.60E-02 7.20E-02 AP-DAP 2
L7069-02 2/12/2004 Co-58
-1.60E-03 2.OOE-03 9.20E-03 AP-DAP 2
L7069-02 2/12/2004 Co-60 1.40E-03 1.60E-03 6.00E-03 AP-DAP 2
L7069-02 2/12/2004 Cs-134 1.40E-03 1.80E-03 6.60E-03 AP-DAP 2
L7069-02 2/12/2004 Cs-137 1.20E-03 1.20E-03 4.40E-03 AP-DAP 2
L7069-02 2/12/2004 K-40
-2.50E-02 1.80E-02 9.70E-02 AP-DAP 2
L7069-02 2/12/2004 AcTh-228
-1.20E-03 4.20E-03 2.OOE-02 AP-DAP 2
L7071-02 2/24/2004 AcTh-228 2.80E-03 3.70E-03 1.40E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-6
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV.
MDC TYPE STATION LSN DATE NUCLIDE (pCi/m3)
(pCi/m3)
(pCim3)
AP-DAP 2
L7071-02 2/24/2004 Be-7 2.20E-02 1.50E-02 5.OOE-02 AP-DAP 2
L7071-02 2/24/2004 Co-58
-L.56E-03 7.80E-04 5.OOE-03 AP-DAP 2
L7071-02 2/24/2004 Co-60 2.1OE-03 1.30E-03 4.20E-03 AP-DAP 2
L7071-02 2/24/2004 Cs-134 2.OOE-04 1.1OE-03 4.60E-03 AP-DAP 2
L7071-02 2124/2004 Cs-137
-1.40E-03 1.40E-03 5.90E-03 AP-DAP 2
L7071-02 2/24/2004 K40 1.40E-02 2.10E-02 7.80E-02 AP-DAP 2
L7054-02 3//2004 Aclh-228 L.001E-02
- 1.
IOE-02 4.00E-02 AP-DAP 2
L7054-02 3/9/2004 Be-7 9.60E-02 3.50E-02 L.00E-0I AP-DAP 2
L7054-02 3/9/2004 Co-58 3.OOE-04
.80E-03 7.90E-03 AP-DAP 2
L7054-02 3/9/2004 Co-60 1.90.E-03 2.70E-03 L.IOE-02 AP-DAP 2
L7054-02 3/9/2004 Cs-134
-2.30E-03 2.40E-03 1.1OE-02 AP-DAP 2
L7054-02 3/9/2004 Cs-137 4.00E-04 2.80E-03 1.10E-02 AP-DAP 2
L7054-02 3/9/2004 K-40
-3.00E-03 3.70E-02 I.50E-01 AP-DAP 2
L7121-02 3/25/2004 AcTh-228
-1.10E-03 1.70E-03 7.90E-03 AP-DAP 2
L7121-02 3/25/2004 Be-7 4.48E-02 9.70E-03 2.30E1-02 AP-DAP 2
L7121-02 3/25/2004 Co-58
-1.02E-03 9.40E-04 4.00E-03 AP-DAP 2
L7121-02 3/25/2004 Co-60 1.32E-03 7.90E-04 2.50E-03 AP-DAP 2
L7121-02 3/25/2004 Cs-134
-3.90E-04 5.50E-04 2.60E-03 AP-DAP 2
L7121-02 3/25/2004 Cs-137 8.10E-04 7.OOE-04 2.40E-03 AP-DAP 2
L7121-02 3/25/2004 K-40
- 1. IOE-02 1.00E-02 3.60E-02 AP-DAP 2
L7191-02 3/31/2004 Aclb-228 7.40E-03 5.IOE-03 1.70E-02 AP-DAP 2
L7191-02 3/31/2004 Be-7 5.30E-02 2.30E-02 6.80E-02 AP-DAP 2
L7191-02 3/31/2004 Co-58
-1.90E-03 1.70E-03 8.90E-03 AP-DAP 2
L7191-02 3/31/2004 Co-60 7.00E-4 1.50E-03 6.40E-03 AP-DAP 2
L7191-02 3/31/2004 Cs-134
-2.00E-04 1.20E-03 5.80E-03 AP-DAP 2
L7191-02 3/31/2004 Cs-137
-2.70E-03 1.30E-03 6.soE-03 AP-DAP 2
L7191-02 3/31/2004 K-40 L.00E-03 2.20E-02 9.30E-02 AP-DAP 2
L7218-02 4/12/2004 AcTh-228 5.OOE-03 4.90E-03 1.80E-02 AP-DAP 2
L7218-02 4/12/2004 Be-7 1.1OE-02 1.20E-02 4.30E-02 AP-DAP 2
L7218-02 4/12/2004 Co-58
-4.40E-04 9.30E-04 5.OOE-03 AP-DAP 2
L7218-02 4/12/2004 Co-60
-9.00E-04 1.30E-03 6.70E-03 AP-DAP 2
L7218-02 4/12/2004 Cs-134 9.60E-04 6.80E-04 1.30E-03 AP-DAP 2
L7218-02 4/12/2004 Cs-137
-2.00E-04 L.00E-03 4.50E-03 AP-DAP 2
L7218-02 4/12/2004 K-40
-8.OOE-03 1.20E-02 6.40E-02 AP-DAP 2
L7343-02 4/14/2004 AcTh-228
-l.80E-02 l.80E-02 8.70E-02 AP-DAP 2
L7343-02 4/14/2004 Be-7
-6.70E-02 5.20E-02 2.30E-01 AP-DAP 2
L7343-02 4/14/2004 Co-58
-4.00E-04 3.40E-03 1.80E-02 AP-DAP 2
L7343-02 4/14/2004 Co-60
-6.70E-03 6.20E-03 3.20E-02
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCi/m3)
SAMPLE TYPE STD.DEV.
(pCi/m3)
MDC (pCi/m3)
AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP 2
L7343-02 4/14/2004 Cs-134 2
L7343-02 4/14/2004 Cs-137 2
L7343-02 2
L7347-02 2
L7347-02 2
L7347-02 2
L7347-02 2
L7347-02 2
L7347-02 2
L7347-02 2
L7418-02 2
L7418-02 2
L7418-02 2
L7418-02 2
L7418-02 2
L7418-02 2
L7418-02 2
L7469-02 2
L7469-02 2
L7469-02 2
L7469-02 2
L7469-02 2
L7469-02 2
L7469-02 2
L7558-02 2
L7558-02 2
L7558-02 2
L7558-02 2
L7558-02 2
L7558-02 2
L7558-02 2
L7610-02 2
L7610-02 2
L7610-02 2
L7610-02 2
L7610-02 4/14/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/24/2004 5/24/2004 5/24/2004 5/24/2004 5/24/2004 5/24/2004 5/24/2004 6n/2004 6n/2004 6/7/2004 6n/2004 6/7/2004 6/7/2004 6/7/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 6/22/2004 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AclFh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Bc-7 Co-58 Co-60 Cs-134
-5.20E-03
-1.60E-03
-2.50E-02
-1.70E-03 3.70E-02 6.00E-04
-8.OOE-04 4.50E-04 5.00E-04
-3.30E-02
-2.00E-03 6.50E-02
-2.20E-03
-1.30E-03
-5.30E-04 2.90E-04 9.00E-03
-1.70E-03 2.60E-02
-8.40E-04 4.00E-04
-7.00E-04 I.57E-03
- 1. IOE-02
-2.40E-03 I.47E-02 s.80E-04 7.90E-04
-1.40E-03 O.OOE+00
-8.00E-03 3.30E-03 5.40E-02
-6.OOE-04 0.00E+00
- 1. 14E-03
-7.00E-04 4.OOE-03 5.30E-03 2.60E-02 3.50E-03 1.70E-02 5.70E-02 2.80E-0O 5.20E-03 2.20E-02 1.40E-02 4.00E-02 I.OOE-03 4.10E-03 1.20E-03 6.30E-03 4.50E-04 1.20E-03 1.20E-03 4.80E-03 I.OOE-02 7.70E-02 3.IOE-03 1.50E-02 1.40E-02 3.30E-02 1.20E-03 6.00E-03 1.40E-03 6.70E-03 8.80E-04 4.20E-03 6.50E-04 2.70E-03 1.50E-02 5.70E-02
- 3. 1OE-03 1.40E-02 1.30E-02 4.20E-02 8.60E-04 4.30E-03
- 1. IOE-03 4.70E-03 1.IOE-03 4.80E-03 7.80E-04 2.1OE-03 1.40E-02 5.40E-02 2.30E-03 1.20E-02 8.70E-03 2.80E-02 9.10E-04 3.50E-03 5.60E-04
- 1. IOE-03 I.OOE-03 4.90E-03 8.70E-04 4.80E-03 2.80E-03 1.50E-02 9.80E-04 1.40E-03 9.30E-04 3.50E-03 3.80E-02 9.90E-03
- 4. 1OE-02 4.70E-03
- 6. 1OE-03 3.20E-03 2
L7610-02 6/22/2004 Cs-137 2
L7610-02 6/22/2004 K-40 I.00E-03 4.60E-03 1.40E-02 5.90E-02
- 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 Annual Radiological Environmental Operating Report 2004 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-DAP 2
L7672-02 6/30/2004 AcTh-228
-2.60E-03 4.50E-03 2.OOE-02 AP-DAP 2
L7672-02 6/30/2004 Be-?
5.1OE-02 1.70E-02 4.80E-02 AP-DAP 2
L7672-02 6/30/2004 Co-58
-3.OOE-04 1.30E-03 5.70E-03 AP-DAP 2
L7672-02 6/30/2004 Co-60 5.40E-04 9.40E-04 4.OOE-03 AP-DAP 2
L7672-02 6/30/2004 Cs-134
-1.40E-03 1.20E-03 5.80E-03 AP-DAP 2
L7672-02 6/30/2004 Cs-137 3.50E-04 9.20E-04 3.70E-03 AP-DAP 2
L7672-02 6/30/2004 K40
-6.OOE-03 1.40E-02 6.80E-02 AP-DAP 2
L7752-02 7/12/2004 AcTh-228
-4.101E-03 4.70E-03
- 2. 1OE-02 AP-DAP 2
L7752-02 7/12/2004 Be-7 4.80E-02 1.50E-02 4.1OE-02 AP-DAP 2
L7752-02 7/12/2004 Co-58 8.20E-04 8.60E-04 3.20E-03 AP-DAP 2
L7752-02 7/12/2004 Co-60 2.20E-03 1.40E-03 4.60E-03 AP-DAP 2
L7752-02 7/12/2004 Cs-134 I.OOE-05 9.80E-04 4.20E-03 AP-DAP 2
L7752-02 7/12/2004 Cs-137
-I.OOE-04 1.30E-03 5.OOE-03 AP-DAP 2
L7752-02 7/12/2004 K40 1.40E-02 1.60E-02 5.90E-02 AP-DAP 2
L7839-02 7/26/2004 AcTh-228 I.90E-03 3.OOE-03 1.20E-02 AP-DAP 2
L7839-02 7/26/2004 Be-7
- 5. 1OE-02 1.40E-02 3.90E-02 AP-DAP 2
L7839-02 7/26/2004 Co-58
-1.20E-04 8.60E-04 3.70E-03 AP-DAP 2
L7839-02 7/26/2004 Co-60
-I.OOE-04 8.20E-04 3.80E-03 AP-DAP 2
L7839-02 7/26/2004 Cs-134
-7.90E-04 9.30E-04 4.30E-03 AP-DAP 2
L7839-02 7/26/2004 Cs-137
-1.25E-03 7.90E-04 3.90E-03 AP-DAP 2
L7839-02 7/26/2004 K-40
-1.40E-02 1.30E-02 6.20E-02 AP-DAP 2
L7905-02 8/9/2004 AcTh-228
-1.90E-03 4.10E-03 1.80E-02 AP-DAP 2
L7905-02 8/9/2004 Be-7
-5.OOE-03 I.OOE-02 4.30E-02 AP-DAP 2
L7905-02 8/9/2004 Co-58
-2.90E-03 1.80E-03 8.30E-03 AP-DAP 2
L7905-02 8/9/2004 Co-60
-2.OOE-03 I.OOE-03 6.OOE-03 AP-DAP 2
L7905-02 8/9/2004 Cs-134 O.OOE+00 I.IOE-03 4.80E-03 AP-DAP 2
L7905-02 8/9/2004 Cs-137 3.20E-04 9.60E-04 3.80E-03 AP-DAP 2
L7905-02 8/9/2004 K-40
-2.90E-02 1.30E-02 7.80E-02 AP-DAP 2
L7982-02 8/23/2004 AcTh-228 7.OOE-04 3.1OE-03 1.30E-02 AP-DAP 2
L7982-02 8/23/2004 Be-7
- 6. 1OE-02 1.30E-02 2.80E-02 AP-DAP 2
L7982-02 8/23/2004 Co-58
-1.60E-04 8.70E-04 3.80E-03 AP-DAP 2
L7982-02 8/23/2004 Co-60 O.OOE+00 7.80E-04 3.60E-03 AP-DAP 2
L7982-02 8/23/2004 Cs-134 5.10E-04 7.90E-04 3.10E-03 AP-DAP 2
L7982-02 8/23/2004 Cs-137
-2.50E-04 6.60E-04 3.OOE-03 AP-DAP 2
L7982-02 8/23/2004 K-40 I.OOE-03 1.20E-02 5.10E-02 AP-DAP 2
L8045-02 97n2OO4 AcTh-228 5.80E-03 5.50E-03 I.90E-02 AP-DAP 2
L8045-02 9/7n2004 Be-7 4.80E-02 1.50E-02 4.40E-02 AP-DAP 2
L8045-02 9/7n2004 Co-58
-1.50E-03 1.20E-03 5.30E-03
- 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 Annual Radiological Environmental Operating Report 2004 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 2
L8045-02 9/712004 Co-60 2.00E-04 I.IOE-03 4.50E-03 AP-DAP 2
L8045-02 9/7/2004 Cs-134 6.OOE-04 I.IOE-03 3.90E-03 AP-DAP 2
L8045-02 9/7/2004 Cs-137 5.IOE-04 9.90E-04 3.70E-03 AP-DAP 2
L8045-02 9/712004 K-40 6.OOE-03 1.30E-02 4.90E-02 AP-DAP 2
L8120-02 9121/2004 AcTh-228 1.60E-03 4.60E-03 1.80E-02 AP-DAP 2
L8120-02 9/21/2004 Be-7 4.1OE-02 1.30E-02 3.70E-02 AP-DAP 2
L8120-02 9/21/2004 Co-58
-1.09E-03 8.60E-04 4.40E-03 AP-DAP 2
L8120-02 9/21/2004 Co-60
-1.20E-03 I.50E-03 6.50E-03 AP-DAP 2
L8120-02 9/21/2004 Cs-134
-4.70E-04 8.80E-04 4.1OE-03 AP-DAP 2
L8120-02 9/21/2004 Cs-137 9.00E-05 9.00E-04 3.60E-03 AP-DAP 2
1L8120-02 9121/2004 K-40 1.50E-02 1.40E-02 5.00E-02 AP-DAP 2
L88150-02 9/29/2004 AcTh-228
-3.90E-03 2.90E-03 1.60E-02 AP-DAP 2
L8150-02 9/29/2004 Be-7 7.1OE-02 I.SOE-02 3.80E-02 AP-DAP 2
L8150-02 9/29/2004 Co-58 1.20E-03 1.20E-03 4.30E-03 AP-DAP 2
L8150-02 9/29/2004 Co-60 6.00E-04 1.60E-03 6.30E-03 AP-DAP 2
L8150-02 9/29/2004 Cs-134 0.00E+00 1.20E-03 5.OOE-03 AP-DAP 2
L8150-02 9/29/2004 Cs-137 2.20E-03 1.80E-03 6.00E-03 AP-DAP 2
L8150-02 9/29/2004 K-40 2.40E-02 2.1OE-02 7.30E-02 AP-DAP 2
L8296-02 10/14/2004 Ac'll-228
-4.30E-03 3.50E-03 1.60E-02 AP-DAP 2
L8296-02 10/14/2004 Be-7 4.60E-02 1.40E-02
- 4. 1OE-02 AP-DAP 2
L8296-02 10/1412004 Co-58 6.40E-04 5.90E-04 2.10E-03 AP-DAP 2
L8296-02 10/14/2004 Co-60
-5.20E-04 7.90E-04 4.10E-03 AP-DAP 2
L8296-02 10114/2004 Cs-134
-6.20E-04 8.90E-04 4.00E-03 AP-DAP 2
L8296-02 10/14/2004 Cs-137 3.60E-04 7.1OE-04 2.80E-03 AP-DAP 2
L8296-02 10/14/2004 K-40 7.00E-04 9.50E-03 4.20E-02 AP-DAP 2
L8345-02 1012612004 AcTh-228
-3.00E-04 3.70E-03 1.60E-02 AP-DAP 2
L8345-02 10/2612004 Bc-7 4.70E-02 1.40E-02 3.90E-02 AP-DAP 2
L8345-02 10/26/2004 Co-58
-9.20E-04 7.40E-04 4.1OE-03 AP-DAP 2
L8345-02 10/26/2004 Co-60 1.60E-03 1.20E-03 4.20E-03 AP-DAP 2
L8345-02 10/26/2004 Cs-134
-1.90E-04 9.20E-04 4.20E-03 AP-DAP 2
L8345-02 10/2612004 Cs-137
-8.70E-04 9.60E-04 4.40E-03 AP-DAP 2
L8345-02 1026/2004 K-40
-1.OOE-02 1.20E-02
- 6. 1OE-02 AP-DAP 2
L8418-02 11/8/2004 Aclb-228
-1.IOE-03 2.90E-03 1.30E-02 AP-DAP 2
L8418-02 11/8/2004 Be-7 5.80E-02 1.20E-02 2.60E-02 AP-DAP 2
L8418-02 11/8/2004 Co-58
-2.00E-04 I.OOE-03 4.30E-03 AP-DAP 2
L8418-02 11/8/2004 Co-60
-7.OOE-04 1.40E-03 6.20E-03 AP-DAP 2
L8418-02 11/8/2004 Cs-134 8.00E-04 I.OOE-03 3.90E-03 AP-DAP 2
L8418-02 11/8f2004 Cs-137 2.70E-04 6.00E-04 2.SOE-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP 2
L8418-02 2
L8482-02 2
L8482-02 2
L8482-02 2
L8482-02 2
L8482-02 2
L8482-02 2
L8482-02 2
L8550-02 2
L8550-02 2
L8550-02 2
L8550-02 2
L8550-02 2
L8550-02 2
L8550-02 2
L8603-02 2
L8603-02 2
L8603-02 2
L8603-02 2
L8603-02 2
L8603-02 2
L8603-02 3
L7069-03 3
L7069-03 3
L7069-03 3
L7069-03 3
L7069-03 3
L7069-03 3
L7069-03 3
L7071-03 3
L7071-03 3
L7071-03 3
L7071-03 3
L7071-03 3
L7071-03 3
L7071-03 3
L7054-03 3
L7054-03 11/8/2004 1122/2004 11/22/2004 11/22/2004 11/22/2004 11/22/2004 11/22/2004 11/22/2004 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 2/12/2004 2/12/2004 2/12/2004 2/12/2004 2/12/2004 2/12/2004 2/12/2004 2/24/2004 2/24/2004 2/24/2004 2/24/2004 2/24/2004 2/24/2004 2/24/2004 3/9/2004 3/9/2004 K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-S8 Co-60 Cs-134 Cs-137 K40 Aclh-228 Be-7 Co-S8 Co-60 Cs-134 Cs-137 K40 AclIh-228 Be-7 Co-5S Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 8.00E-03 3.00E-03 4.50E-02 3.00E-04
-1.26E-03 5.30E-04 I.00E-04 4.00E-03
-3.50E-03 3.50E-02 1.61E-03 3.90E-04
-1.30E-03 6.30E-04 I.OOE-03
-4.80E-03 2.60E-02 3.60E-04 1.20E-03 3.00E-04
-4.50E-04
-1.24E-02
-2.20E-03 3.70E-02 I.00E-03 2.80E-03
-3.20E-03 I.00E-03 6.40E-02 4.70E-03 9.90E-02
-1.20E-03 2.00E-03 0.00E+O0 1.20E-03
-2.00E-03
-3.00E-04 5.40E-02 1.50E-02 3.40E-03 1.30E-02 1.30E-03 8.90E-04 9.80E-04 1.00E-03 1.30E-02 3.60E-03 1.30E-02 8.90E-04 8.00E-04 7.30E-04 8.00E-04 1.20E-02 3.1OE-03 l.OOE-02 9.20E-04 6.90E-04
- 1. IOE-03
- 7. 1OE-04 9.70E-03
- 7. 1OE-03 2.30E-02 1.80E-03
- 2. 1OE-03 1.80E-03 2.50E-03 3.20E-02
- 4. 1OE-03 1.90E-02 1.60E-03
.IOE-03 9.80E-04 1.20E-03 2.00E-02 3.20E-03 1.60E-02 5.90E-02 1.30E-02 3.50E-02
- 5. 1OE-03 5.60E-03 3.90E-03 4.20E-03 5.40E-02 1.60E-02 3.70E-02 2.70E-03 3.50E-03 4.00E-03 3.00E-03 5.00E-02 1.50E-02 3.00E-02 3.60E-03
- 1. IOE-03 4.30E-03 3.20E-03 5.10E-02 2.90E-02 7.40E-02
- 7. 1OE-03 7.OOE-03 8.50E-03 9.00E-03 I.00E-0I 1.40E-02 I.OOE-02 7.60E-03 1.80E-03 4.50E-03 4.30E-03 8.50E-02 1.40E-02 4.70E-02
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP 3
L7054-03 3
L7054-03 3
L7054-03 3
L7054-03 3
L7054-03 3
L7121-03 3
L7121-03 3
L7121-03 3
L7121-03 3
L7121-03 3
L7121-03 3
L7121-03 3
L7191-03 3
L7191-03 3
L7191-03 3
L7191-03 3
L7191-03 3
L7191-03 3
L7191-03 3
L7218-03 3
L7218-03 3
L7218-03 3
L7218-03 3
L7218-03 3
L7218-03 3
L7218-03 3
L7343-03 3
L7343-03 3
L7343-03 3
L7343-03 3
L7343-03 3
L7343-03 3
L7343-03 3
L7347-03 3
L7347-03 3
L7347-03 3
L7347-03 3
L7347-03 3/9/2004 3/9/2004 3/9/2004 3/9/2004 3/9/2004 3/25/2004 3/25/2004 3/25/2004 3/25/2004 3/25/2004 3/25/2004 3/25/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 4/12/2004 4/12/2004 4/12/2004 4/12/2004 4/12/2004 4/12/2004 4/12/2004 4/14/2004 4/14/2004 4/14/2004 4/14/2004 4/14/2004 4/14/2004 4/14/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 Co-S8 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Aclb-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-58 Co-60
- 1.
12E-03 8.00E-04 5.OOE-04
-4.00E-04
-8.00E-03 6.00E-04
- 8. IOE-02
-5.80E-04 I.OOE-04 1.65E-03 4.90E-04 1.20E-02 9.OOE-04 1.63E-01 2.40E-03 3.20E-03 O.OOE+00
-3.80E-03
-3.70E-02
-3.OOE-04 1.30E-0O
-3.00E-04
-4.OOE-04 2.70E-03 1.20E-03
- 2. 1OE-02 2.50E-02
-3.70E-02
-9.50E-03 I.12E-02 O.OOE+00
-5.20E-03
-8. IOE-02
-5.00E-04 1.21E-0I
-2.60E-03
-5.OOE-04
-2.00E-04 8.80E-04 1.40E-03 I.OOE-03 1.20E-03 1.20E-02 3.50E-03 1.60E-02
- 9. 1OE-04 I.OOE-03 9.50E-04 7.00E-04 1.40E-02
- 8. 1OE-03 4.1 OE-02 2.40E-03 2.00E-03 2.10E-03 2.30E-03 2.40E-02 6.40E-03 3.20E-02 2.00E-03 1.60E-03 2.20E-03 1.40E-03 2.20E-02 2.30E-02 6.20E-02 6.30E-03
- 8. 1OE-03 5.80E-03 4.90E-03 8.50E-02 6.50E-03 2.90E-02 1.80E-03 2.00E-03 1.40E-03 3.00E-03 5.30E-03 3.90E-03 4.60E-03 5.80E-02 1.40E-02 4.10E-02 4.10E-03 4.20E-03 3.00E-03 3.20E-03 5.lOE-02 3.20E-02
- 1. IOE-0I 8.60E-03 5.90E-03 8.SOE-03 1.OOE-02 1.20E-O1 2.80E-02 7.30E-02
- 9. 1OE-03 8.SOE-03 7.40E-03 5.50E-03 8.00E-02 7.90E-02 2.50E-0O 3.00E-02 2.70E-02 2.40E-02 2.20E-02 3.70E-01 2.80E-02
- 7. 1OE-02 9.30E-03 9.60E-03 6.60E-03 4/26/2004 Cs-134
- 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 Annual Radiological Environmental Operating Report 2004 Radiklogical 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 3
L7347-03 4/26/2004 Cs-137 O.OOE+00 l.50E-03 6.40E-03 AP-DAP 3
L7347-03 4/26/2004 K-40 5.OOE-03 2.20E-02 9.60E-02 AP-DAP 3
L7418-03 5/10/2004 AcTh-228 4.70E-03 4.50E-03 1.60E-02 AP-DAP 3
L7418-03 5/10/2004 Be-7 1.14E-01 2.40E-02 5.90E-02 AP-DAP 3
L7418-03 5/10/2004 Co-58
-7.90E-04 8.90E-04 4.90E-03 AP-DAP 3
L7418-03 5/10/2004 Co-60 1.38E-03 9.80E-04 I.90E-03 AP-DAP 3
L7418-03 5/10/2004 Cs-134 5.40E-04 8.OOE-04 3.30E-03 AP-DAP 3
L7418-03 5/10/2004 Cs-137 1.30E-03 1.40E-03 5.20E-03 AP-DAP 3
L7418-03 5/10/2004 K-40
-1I.OOE-03 I.90E-02 8.40E-02 AP-DAP 3
L7469-03 5/24/2004 AcTh-228
-3.70E-03 2.80E-03 1.40E-02 AP-DAP 3
L7469-03 5/24/2004 Be-7 I.19E-01 2.OOE-02 4.70E-02 AP-DAP 3
L7469-03 5/24/2004 Co-58 9.00E-04 I.10E-03 4.20E-03 AP-DAP 3
L7469-03 5/24/2004 Co-60
-1.60E-03 I.10E-03 6.00E-03 AP-DAP 3
L7469-03 5/24/2004 Cs-134
-1.50E-03 1.20E-03 5.40E-03 AP-DAP 3
L7469-03 5/24/2004 Cs-137
-2.00E-04 1.30E-03 5.00E-03 AP-DAP 3
L7469-03 5/24/2004 K-40
-5.00E-03 1.70E-02 7.1OE-02 AP-DAP 3
L7558-03 6/7/2004 AcTh-228
-7.80E-03 6.40E-03 2.80E-02 AP-DAP 3
L7558-03 6/7/2004 Be-7 I.OIE-0 2.40E-02 6.1OE-02 AP-DAP 3
L7558-03 6/7/2004 Co-58 8.00E-04 1.50E-03 5.90E-03 AP-DAP 3
L7558-03 6/7/2004 Co-60 5.OOE-04 I.IOE-03 4.60E-03 AP-DAP 3
L7558-03 6/7/2004 Cs-134
-1.80E-03 I.OOE-03 5.80E-03 AP-DAP 3
L7558-03 6/7/2004 Cs-137
-4.OOE-04 1.40E-03 5.90E-03 AP-DAP 3
L7558-03 6/7/2004 K-40
-2.00E-02 1.50E-02 8.OOE-02 AP-DAP 3
L7610-03 6/22/2004 AcTh-228 I.90E-03 3.50E-03 1.30E-02 AP-DAP 3
L7610-03 6/22/2004 Be-7 1.46E-01 1.70E-02 2.30E-02 AP-DAP 3
L7610-03 6/22/2004 Co-58 8.00E-04 I.OOE-03 3.60E-03 AP-DAP 3
L7610-03 6/22/2004 Co-60
-1.20E-03 7.70E-04 4.20E-03 AP-DAP 3
L7610-03 6/22/2004 Cs-134 8.50E-04 8.50E-04 3.OOE-03 AP-DAP 3
L7610-03 6/22/2004 Cs-137
-7.00E-04 1.OOE-03 4.30E-03 AP-DAP 3
L7610-03 6/22/2004 K-40 4.OOE-03 I.OOE-02 4.30E-02 AP-DAP 3
L7672-03 6/30/2004 AcTh-228 6.OOE-04 5.60E-03 2.30E-02 AP-DAP 3
L7672-03 6/30/2004 Be-7 5.90E-02 2.30E-02 7.1OE-02 AP-DAP 3
L7672-03 6/30/2004 Co-58
-1.70E-03 1.60E-03 7.40E-03 AP-DAP 3
L7672-03 6/30/2004 Co-60
-7.OOE-04 2.90E-03 1.1 OE-02 AP-DAP 3
L7672-03 6/30/2004 Cs-134
-8.00E-04 1.90E-03 7.90E-03 AP-DAP 3
L7672-03 6/30/2004 Cs-137
-7.OOE-04 2.1OE-03 8.30E-03 AP-DAP 3
L7672-03 6/30/2004 K-40
-I.OOE-03 1.40E-02 6.80E-02 AP-DAP 3
L7752-03 7/12/2004 AcTh-228
-2.70E-03 5.40E-03 2.40E-02
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END TYPE STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP 3
L7752-03 3
L7752-03 3
L7752-03 3
L7752-03 3
L7752-03 3
L7752-03 3
L7839-03 3
L7839-03 3
L7839-03 3
L7839-03 3
L7839-03 3
L7839-03 3
L7839-03 3
L7905-03 3
L7905-03 3
L7905-03 3
L7905-03 3
L7905-03 3
L7905-03 3
L7905-03 3
L7982-03 3
L7982-03 3
L7982-03 3
L7982-03 3
L7982-03 3
L7982-03 3
L7982-03 3
L8045-03 3
L8045-03 3
L8045-03 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/26/2004 7/26(2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 7/26/2004 8/16/2004 8/16/2004 8/16/2004 8/16/2004 8/16/2004 8/16/2004 8/16/2004 8/22/2004 8/22/2004 8/22/2004 8/22/2004 8/22/2004 8/22/2004 8/22/2004 9/7/2004 9/7/2004 9/7/2004 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Aclb-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Aclh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 1.08E-Ol 4.30E-04
-7.OOE-04 3.00E-04 1.30E-03 L.OOE-03
.801E-03 1.07E-0l
-5.20E-04 I.OOE-03 7.40E-04
-9.20E-04 LOOE-02 3.70E-03 6.00E-02 5.20E-04 1.46E-03 1.02E-03
-8.40E-04 4.00E-03 4.30E-03 1.16E-OI 3.00E-04 3.00E-04
-2.80E-04
-8.60E-04
-6.1OE-03 3.90E-03 8.70E-02
-4.00E-04
-8.00E-04
-6.00E-04
-3.40E-04
-4.00E-03 4.90E-03 5.50E-02 3.00E-04
-I.90E-03 2.10E-02 4.30E-02 9.50E-04 4.1OE-03 1.20E-03 6.20E-03 1.20E-03 5.30E-03 1.30E-03 4.60E-03 1.801E-02 7.90E-02 3.50E-03 1.30E-02 1.60E-02 3.40E-02 9.1OE-04 3.90E-03 1.20E-03 4.50E-03 9.40E-04 3.40E-03 9.40E-04 4.00E-03 1.40E-02 5.30E-02 4.90E-03 1.80E-02 1.60E-02 4.20E-02 9.40E-04 3.70E-03 8.40E-04 1.30E-03 8.40E-04 2.90E-03 8.60E-04 4.1OE-03 1.70E-02 6.80E-02 4.30E-03 1.60E-02 1.80E-02 2.60E-02 1.20E-03 4.90E-03 1.30E-03 5.40E-03 6.00E-04 3.20E-03 9.50E-04 4.40E-03 8.00E-03 4.80E-02 4.80E-03 1.80E-02 1.80E-02 3.80E-02 1.50E-03 6.30E-03 1.40E-03 6.40E-03 1.40E-03 6.10E-03 8.90E-04 4.00E-03 2.00E-02 8.50E-02 3.90E-03 1.30E-02 1.40E-02 4.OOE-02 1.20E-03 4.40E-03
- 1. I OE-03 5.20E-03 3
L8045-03 9/7/2004 Co-60 3
L8045-03 9/7/2004 Cs-134 3
L8045-03 3
L8045-03 3
L8120-03 3
L8120-03 3
L8120-03 3
L8120-03 9/7/2004 9/7/n04 9/21/2004 9/21/2004 9/21/2004 9/21/2004 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60
- 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 Annual Radiological Environmental Operating Report 2004 IRadiological 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 3
L8120-03 9/21/2004 Cs-134 I.00E-03 I.IOE-03 3.80E-03 AP-DAP 3
L8120-03 9/21/2004 Cs-137 1.51E-03 9.1OE-04 2.90E-03 AP-DAP 3
L8120-03 9/21/2004 K40 2.00E-03 1.40E-02 5.50E-02 AP-DAP 3
L8150-03 9/29/2004 AcTh-228 5.70E-03 6.40E-03 2.30E-02 AP-DAP 3
L8150-03 9/29/2004 Be-7 9.10E-02 2.OOE-02 4.80E-02 AP-DAP 3
L8150-03 9/29/2004 Co-58
-I.OOE-04 1.50E-03 6.50E-03 AP-DAP 3
L8150-03 9/29/2004 Co-60 3.40E-03 1.80E-03 5.IOE-03 AP-DAP 3
L8 150-03 9/29/2004 Cs-134
-1.60E-03 1.90E-03 8.30E-03 AP-DAP 3
L8150-03 9/29/2004 Cs-137 1.SOE-03 1.60E-03 5.90E-03 AP-DAP 3
L8150-03 9/29/2004 K40
-2.70E-02 2.20E-02 1.IOE-01 AP-DAP 3
L8296-03 10/14/2004 AcTh-228
-7.20E-03 4.40E-03 2.20E-02 AP-DAP 3
L8296-03 10/14/2004 Be-7 1.18E-01 1.70E-02 2.1OE-02 AP-DAP 3
L8296-03 10/14/2004 Co-58
-5.50E-04 8.00E-04 4.20E-03 AP-DAP 3
L8296-03 10/14/2004 Co-60
-2.00E-04 1.50E-03 6.60E-03 AP-DAP 3
L8296-03 10/14/2004 Cs-134 1.99E-03 8.90E-04 I.IOE-03 AP-DAP 3
L8296-03 10/14/2004 Cs-137 9.70E-04 7.20E-04 2.40E-03 AP-DAP 3
L8296-03 10/14/2004 K-40 1.30E-02 1.30E-02 4.90E-02 AP-DAP 3
L8345-03 10/26/2004 AcTh-228 1.70E-03 4.40E-03 1.80E-02 AP-DAP 3
L8345-03 10/26/2004 Be-7 5.50E-02 1.70E-02 4.60E-02 AP-DAP 3
L8345-03 10/26/2004 Co-58
-1.90E-03 1.60E-03 7.40E-03 AP-DAP 3
L8345-03 10/26/2004 Co-60
-1.60E-03 1.IOE-03 7.00E-03 AP-DAP 3
L8345-03 10/26/2004 Cs-134 8.OOE-04 1.30E-03 4.90E-03 AP-DAP 3
L8345-03 10/26/2004 Cs-137 2.40E-03 1.40E-03 4.30E-03 AP-DAP 3
L8345-03 10/26/2004 K40 7.00E-03
- 2. 1OE-02 8.60E-02 AP-DAP 3
L8418-03 11/8/2004 AcTh-228 I.00E-03 4.90E-03 I.90E-02 AP-DAP 3
L8418-03 11/8/2004 Be-7 4.30E-02 1.50E-02 4.30E-02 AP-DAP 3
L8418-03 11/8/2004 Co-58 5.20E-04 9.50E-04 3.80E-03 AP-DAP 3
L8418-03 11/8/2004 Co-60 5.OOE-04 I.00E-03 4.30E-03 AP-DAP 3
L8418-03 11/8/2004 Cs-134
-9.1OE-04 9.30E-04 4.60E-03 AP-DAP 3
L8418-03 11/8/2004 Cs-137 2.40E-03 1.IOE-03 3.20E-03 AP-DAP 3
L8418-03 11/8/2004 K40 O.OOE+00 I.OOE-02 4.80E-02 AP-DAP 3
L8482-03 11/22/2004 AcTh-228
-7.90E-03 2.80E-03 2.OOE-02 AP-DAP 3
L8482-03 11/22/2004 Be-7 8.40E-02 1.80E-02 3.90E-02 AP-DAP 3
L8482-03 11/22/2004 Co-58 9.00E-04 1.IOE-03 4.1OE-03 AP-DAP 3
L8482-03 11/22/2004 Co-60
-2.OOE-04 1.60E-03 7.40E-03 AP-DAP 3
L8482-03 11/22/2004 Cs-134 1.50E-03 1.20E-03
- 4. IOE-03 AP-DAP 3
L8482-03 11/22/2004 Cs-137 8.OOE-04 1.20E-03 4.50E-03 AP-DAP 3
L8482-03 11/22/2004 K-40
- 2. 1OE-02 1.70E-02 5.90E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-15
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological.Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pci/m3)
NUCLIDE AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP-DAP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 3
L8550-03 3
L8550-03 3
L8550-03 3
L8550-03 3
L8550-03 3
L8550-03 3
L8550-03 3
L8603-03 3
L8603-03 3
L8603-03 3
L8603-03 3
L8603-03 3
L8603 -03 3
L8603-03 I1 L6809-01 I1 L6911I-01 I1 L6944-01 I1 L6944-01 II L6944-01 1I L6944-01 II L6944-01 II L6944-01 11 L6944-01 I1 L6944-01 11 L7052-01 I1 L7052-01 I1 L7052-01 II L7052-01 II L7052-01 I1 L7052-01 II L7052-01 I1 L7052-01 I1 L7068-01 Ii L7068-01 II L7068-01 II L7068-01 II L7068-01 II L7068-01 12/6/2004 AcTh-228 12/6/2004 Be-7 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/6/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 1/15/2004 1/31/2004 2/11/2004 2/11/2004 2/11/2004 2/11/2004 2/11/2004 2/11/2004 2/11/2004 2/11/2004 3/10/2004 3/10/2004 3/10/2004 3/10/2004 3/10/2004 3/10/2004 3/10/2004 3/10/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 GROSS BETA GROSS BETA AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137
-4.80E-03 7.60E-02
-6.90E-04
-1.30E-03 2.30E-04 3.90E-04
-1.00E-02
- 3. 1OE-03 6.00E-03
-8.OOE-04 8.70E-04 4.80E-04 7.00E-04
-1.94E-02 2.39E-02 l.75E-02 3.80E-03
-1.40E-01
-2.60E-02 8.OOE-04
-I.00E-04 L.OOE-04 2.OSE-02 3.00E-03
-2.soE-03
- 9. 1OE-02 2.30E-04 3.00E-04 1.09E-03 5.40E-04 2.14E-02
-2.40E-03
- 2. 1OE-03 7.20E-02 1.15E-03 3.OOE-04 I.53E-03
-7.60E-04 3.00E-03 1.20E-02 8.90E-04 I.OOE-03 9.50E-04 7.20E-04 1.00E-02
- 4. 1OE-03 I.OOE-02 6.50E-04 9.60E-04
- 9. IOE-04 7.30E-04 7.90E-03 6.90E-04 6.40E-04
- 4. 1OE-03 2.20E-01 1.IOE-02 1.20E-03 1.20E-03 1.20E-03 8.40E-04 1.IOE-02 2.80E-03 1.40E-02 6.90E-04 8.90E-04 8.50E-04 7.50E-04 1.OOE-03 9.60E-03 4.60E-03 1.60E-02 9.00E-04 1.20E-03 7.80E-04 9.20E-04 1.40E-02 2.40E-02 3.80E-03 4.70E-03 3.70E-03 2.70E-03 4.70E-02 1.501E-02 3.60E-02 3.60E-03 3.60E-03 3.60E-03 2.70E-03 5.40E-02 1.1OE-03 1.20E-03 1.50E-02 8.80E-01 5.70E-02 4.60E-03 4.90E-03 4.70E-03 1.40E-03 4.SOE-02 1.20E-02 2.80E-02 2.80E-03 3.60E-03 2.90E-03 2.70E-03 1.50E-03 4.10E-02 1.70E-02 4.00E-02 3.1OE-03 4.90E-03 2.1 OE-03 4.00E-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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 11 L7068-01 11 L7068-01 11,7130-01 11 L7130-01 II L7130-01 11 L7130-01 II L7130-01 1, 7130-I 11 L7130-01 II L7130-01 11 L7190-01 11 L7190-01 II L7190-01 1, 7190-01 II L7190-01 II L7190-01 II L7190-01 II L7190-01 II L7217-01 11 L7217-01 II L7217-01 II L7217-01 II L7217-01 II L7217-01 II L7217-01 11 L7217-01 11 L7282-01 11 L7282-01 II L7282-01 II L7282-01 II L7282-01 11 L7282-01 11 L7282-01 II L7282-01 11 L7282-01 II L7282-01 II L7282-01 II L7282-01 2/25/2004 2/25/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 411/2004 4/1/2004 4/l/2004 4/1/2004 4/1/2004 4/1/2004 4/1/2004 4/1/2004 4/13/2004 4/13/2004 4/13/2004 4/13/2004 4/13/2004 4/13/2004 4/13/2004 4/13/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-22s Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-22s Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K40 AcTh-228 Ag-I lOIm Ba-140 Be-7 Ce-141 Ce-144 2.43E-02 1.70E-02
-3.60E-03 7.80E-02
-2.09E-03 I1.87E-03 I1.24E-03 2.60E-04 I1.75E-02
-1I.20E-03
-3.20E-03 1.34E-01 6.OOE-04
-1. I OE-03 8.OOE-04 3.90E-03 I1.77E-02
-4.OOE-03
-1.00E-03 1.1I9E-0 I 0.00E+00 3.001E-04 3.901E-04 3.80E3-04 I1.25E3-02
-4.0013-03 0.OOE3+00
-7.60E-04
-1.60E-02
- 9. I OE-02 L.0E-03
-3.OOE-03
-5.OOE-05 6.30E-04
-2.001E-04 5.OOE-05 3.OOE-05
-2.70E-03
- 1. IOE-03 I.20E-02 2.40E-03 1.50E-02 9.40E-04 9.30E-04 8.20E-04 6.90E-04 9.soE-04 9.40E-03 5.20E-03 2.60E-02 1.30E-03 1.60E-03 1.30E-03 1.60E-03 1.40E-03 1.80E-02 3.30E-03 1.70E-02
- 1. IOE-03 11.OOE-03 6.60E-04 7.70E-04
.OOE-03 1.IOE-02 I.OOE-03 4.30E-04 1.90E-02 1.30E-02 1.60E-03 1.40E-03 1.60E-04 6.60E-04 4.40E-04
- 3. 1OE-04 4.80E-04
- 2. 1OE-03 2.00E-03 4.10E-02 1.30E-02 2.80E-02 5.20E-03 1.30E-03 2.60E-03 2.80E-03 1.70E-03 4.50E-02 2.50E-02 s.50E-02 5.40E-03 8.60E-03 5.20E-03 3.90E-03 2.90E-03 8.50E-02 1.40E-02 3.40E-02 4.40E-03 4.40E-03 2.70E-03 3.00E-03 2.20E-03
- 5. IOE-02 4.20E-03 2.20E-03 9.40E-02 2.80E-02 5.60E-03 5.70E-03
- 6. 1OE-04 2.30E-03 1.90E-03 1.20E-03 1.80E-03 L OOE-02 3/24/2004 Co-57 3124/2004 Co-58 3/24/2004 Co-60 3/24/2004 Cs-134 3/24/2004 Cs-1 37 3/24/2004 Fe-59
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-17
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program-Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP L72820 L72820 L72820 1IL72820 1lL72820 1lL72820 1lL72820 1lL72820 1lL72820 L72820 L7342-01 L7342-01 L7342-01 L7342-01 L7342-01 L7342-01 L7342-01 L7342-01 L7401 -01 L7401-01 L7401-01 L7401-01 L7401 -01 L7401-01 L7401-01 L740 I-01 L7468-0 L7468-0 L7468-0 L7468-0 L7468-0 L7468-0 L7468-01 L7468-0 L7525-0 L7525-0 L7525-0 L7525-0 324/2004 324/2004 324/2004 324/2004 324/2004 324/2004 324/2004 324n2004 324/2004 3n24noo04 4/29/204 4nsnoo04 4nsnoo04 4nsnoo04 4nsnoo04 4nsnoo04 4/29/2004 4/29/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/10/2004 5/25/2004 5s25n204 5s25n204 5/25/204 5s25n204 5s25n204 5s25n204 5/5/200o4 6/7n2004 6/7/2004 6/7/2004 67/200o4 1-131 K40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 AcTh-22S Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K40 AcTh-22S Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K 40 AcTh-22S Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-22S Be-7 Co-58 Co-60
-6. IOE-02
-2.03E-02 Ls.8E-02
.OOoE-04 O.OOE+OO 5.OOE-04
- 5.
1OE-03 8.OOE-04 s5.20E-04 LOOE-04 4.SOE-03 9.90E-02 4.00E-04 O.OOE+OO
-I.IOE-03
-1.22E-03 1.71 E-02 7.00E-03 8.OOE-04 1.40E-OI
-3.10OE-04
-2.00E-04 6.00E-04
-7.00E-05 1.98E-02
-I.OOE-03
-4.30E-03 1.18E3-OI
-2.50E-04 9.90E3-04
-3.00E-05 1.06E-03 1.87E3-02 ILOOE-03 O.OOE+OO 9.30E-02 1.30E-03 1.74E-03 9.10OE-02 4.SOE-03 2.20E-02 2.80E-04 1.20E-03 1.30E-03 2.40E-03 I.SOE-03 6.40E-04 1.20E-03 3.40E-03 I1.SOE-02 S.80E-04 O.OOE+OO 7.60E-04 7.30E-04 9.20E-04 I.IIOE-02 3.00E-03 2.20E-02 9.40E-04 1.20E-03 I.I OE-03 8.30E-04 1.30E-03 1.30E-02 2.30E-03 1.50E-02 8.50E-04 7.90E-04 8.30E-04 8.60E-04 I.OOE-03 1.20E-02 2.60E-03 1.50E-02 I.IOE-03 8.70E-04 3.70E-OI 2.50E-02 I.I OE-O I 8.50E3-04 S. I OE-03 4.60E3-03 6.80E-03 6.30E-03
- 3. I OE-03 4.70E-03 I.IOE-02 3.20E-02 3.00E3-03 1.20E3-03 3.90E3-03 3.70E-03 1.70E3-03 4.30E-02 1.20E-02 S.20E-02 4.10OE-03 S.40E-03 4.20E-03 3.50E-03 2.50E-03 5.40E-02 1.20E3-02 2.50E-02 3.60E3-03 2.70E3-03 3.40E-03 2.90E3-03 1.70E3-03 5.00E-02 1.20E-02 3.00E3-02 3.90E-03 1.20E-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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END TYPE STATION LSN DATE CONC (pCi/m3)
STD.DEV.
MDC (pCi/m3)
(pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP II L7525-01 II L7525-01 II L7525-01 II L7525-01 11 L7609-01I II L7609-01 Ii L7609-01I Ii L7609-01 I1 L7609-01I I1 L7609-01I II L7609-01 II L7609-0 1 II L7671 -01 II L7671 -01 11 L7671 -O1 II L7671-01 II L7671 -01 Ii L7671 -O1 Ii L7671 -01 Il L767 I-Ol II L7704-01 Il L7704-01 11 L7704-01 11 L7704-01 11 L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 II L7704-01 11 L7704-01 II L7704-01 11 L7704-01 6/7t2004 67n2004 67n2004 6/7/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6n7/2004 617/2004 67/2004 67/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 6/7/2004 Cs-134 Cs-137 GROSS BETA K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Ag-1 10in Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103
- 1. 14E-03
-7.30E-04 1.43E-02 8.OOE-03
-3.OOE-04 1.35E-01 8.80E-04
-2.20E-04
-7.OOE-04 6.80E3-04 I1.941E-02 5.70E3-03
-6.OOE-04 I1.621E-01 3.301E-03
-3.80E-03
-6.OOE-04 3.80E-03 1.56E-02 6.30E-02 2.OOE-04
-7.60E-04 0.00E+00 I1.07E-01
-11.00E-03 I1.70E-03
-1.801E-04
-11.OOE-04 6.OOE-05 7.OOE-05 I.00E-04
-8.OOE-04
-2.40E-02 5.20E-03 0.OOE+00 2.70E-04 3.70E-03 8.OOE-04 7.50E-04 7.30E-04 9.70E-04 I1.201E-02 3.I1OE-03 I1.50E-02 7.001E-04 9.20E-04 6.OOE-04 6.50E-04 I.001E-03 9.90E-03 8.90E-03 3.20E-02 2.10OE-03 3.30E-03 2.50E-03 1.90E-03
- 2. 1 OE-03 3.401E-02 I.00E-03 4.90E-04 I1.80E-02 I1.60E3-02 1.90E-03 I1.70E3-03 I1.90E3-04 6.30E-04
- 4. 1 OE-04 3.30E-04 7.20E-04 2.30E-03 7.80E-02 4.60E-03
- 2. I OE-02 3.201E-04 I1.501E-03
- 1. I OE-03 2.401E-03 3.40E-03 I.80E-03 4.50E-02 I1.20E3-02 2.60E3-02 2.40E3-03 3.90E-03 3.00E-03 2.30E-03 1.90E-03 3.80E-02 3.70E-02 6.801E-02 6.70E-03 I1.501E-02 I. IOE-02 5.20E-03 5.60E-03 9.60E-02 4.30E-03 2.50E-03
- 8. 1OE-02 3.40E-02 7.OOE-03 6.001E-03 7.401E-04 2.701E-03 I1.70E-03 I1.40E-03 2.60E-03 9.90E-03
- 3. 101-0 I 1.60E-02 9.30E-02 I1.2013-03 4.20E-03
- 4. 1 OE-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-19
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 L7704-01 6/7/2004 Ru-106
-440E-03 3.70E-03 1.60E-02 AP II L7704-01 6/7/2004 Sb-124
-4.20E-03 2.50E-03 1.30E-02 AP 1 I L7704-01 6/7/2004 Zn-65
-1.57E-03 9.40E-04 4.70E-03 AP 1 I L7704-01 6/7/2004 Zr-95
-7.00E-04 1.40E-03 5.80E-03 AP II L7753-01 7/14/2004 AcTh-228
-2.70E-03 2.1OE-03 L.00E-02 AP II L7753-0l 7/14/2004 Be-7 5.89E-02 9.80E-03 2.00E-02 AP 11 L7753-O1 7/14/2004 Co-58 1.40E-04 5.00E-04 2.1OE-03 AP II L7753-01 7/14/2004 Co-60
-2.00E-05 6.50E-04 2.80E-03 AP I I L7753-01 7/14/2004 Cs-134 3.80E-04 4.30E-04 1.60E-03 AP 1 I L7753-01 7/14/2004 Cs-137 3.40E-04 4.80E-04' 1.80E-03 AP II L7753-01 7/14/2004 GROSS BETA 6.23E-03 6.30E-04 1.50E-03 AP 11 L7753-01 7/14/2004 K40 1.OOE-02 1.20E-02 4.50E-02 AP I
L7838-l 7/29/2004 AcTh-228 4.soE-03 3.20E-03 LOOE-02 AP II L7s38-01 7/29/2004 Be-7 8.40E-02
.501E-02 3.60E-02 AP II L7838-01 7/29/2004 Co-58 6.00E-04 6.20E-04 2.30E-03 AP 1 I L7838-01 7/29/2004 Co-60
-1.30E-04 8.90E-04 3.90E-03 AP II L7838-01 7/29/2004 Cs-134
-4.00E-04 LOOE-03 4.20E-03 AP 11 L7838-Ol 7/29/2004 Cs-137 5.90E-04 6.10E-04 2.20E-03 AP 11 L7838-0l 7/29/2004 GROSS BETA 1.58E-02 9.80E-04 1.90E-03 AP I I L7838-01 7/29/2004 K40
-1.70E-02 9.20E-03 5.20E-02 AP 1 I L7904-01 8/13/2004 AcTh-228 6.00E-04 3.60E-03 1.40E-02 AP 1 I L7904-Ol 8/13/2004 Be-7 7.20E-02 1.40E-02 3.30E-02 AP II L7904-01 8/13/2004 Co-58 4.50E-04 9.00E-04 3.50E-03 AP II L7904-01 8/13/2004 Co-60 2.30E-03 1.20E-03 3.70E-03 AP 1I L7904-01 8/13/2004 Cs-134 s.IOE-04 8.OOE-04 3.IOE-03 AP 11 L7904-01 8/13/2004 Cs-137 7.60E-04 7.60E-04 2.70E-03 AP 11 L7904-01 8/13/2004 GROSS BETA 2.09E-02 L.001E-03 1.50E-03 AP 11 L7904-01 8/13/2004 K-40
-2.40E-02 1.20E-02 6.50E-02 AP 1I L798I-0I 8/27/2004 AcTh-228
-1.80E-03 2.70E-03 1.IOE-02 AP II L7981 -0 8/27/2004 Be-7 LOOE-01 1.40E-02 3.1OE-02 AP 1 I L7981-01 8/27/2004 Co-58 1.26E-03 8.90E-04 3.00E-03 APl 1I L7981-01 8/27/2004 Co-60 4.60E-04 5.IOE-04 1.90E-03 AP 11 L798 -0l 8/27/2004 Cs-134 3.80E-04 4.1OE-04 1.60E-03 AP 1 I L7981-01 8/27/2004 Cs-137
-1.70E-04 6.OOE-04 2.50E-03 AP 11 L798 1-01 8/27/2004 GROSS BETA 2.22E-02 1.20E-03 2.20E-03 AP II L798 1 -0I 8/27/2004 K40 5.OOE-03 1
.OOE-02 3.90E-02 AP II L8044-01 9/8/2004 AcTh-228
-1.30E-03 3.40E-03 1.40E-02 AP I I L8044-01 9/8/2004 Be-7 9.50E-02 1.SOE-02 3.20E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-20
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
MDC (pCi/m3)
(pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP II L8044-01 II L8044-01 II L8044-01 II L8044-01 II L8044-01 11 L8044-01 I
L8 1 19-01 II L8119-01 11 L8119-01 Ii L8119-01 II L8119-01 1, 8119-01 11 L8119-01 1, 8119-01 11,8162-01 II L8162-01 11 L8162-01 II L8162-01 11 L8162-01 11 L8162-01 Ii L8 162-01 11 L8162-01 11 L8240-01 11 L8240-01 11 L8240-01 II L8240-01 II L8240-01 II L8240-O1 11 L8240-01 11 L8240-01 II L8266-01 II L8266-01 II L8266-01 II L8266-01 II L8266-01 II L8266-01 II L8266-01 II L8266-01 9/8t2004 9/8/2004 9/8/2004 9/8/2004 9/8/2004 9/8/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 10/13/2004 10/13/2004 10/13/2004 10/13/2004 10/13/2004 10/13/2004 10/13/2004 10/13/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Ag-l lOim Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58
-1.99E-03
-4.30E-04
-5. 1OE-04 2.0013-05 1.85E3-02 5.30E-03 2.001E-03
- 9. I OE-02 1.6013-04
-1. 13E-03
-1.77E-03 1.88E-03 1.43E-02
-9.0013-03 5.80E-03 I1.35E-01
-6.0013-04
-1.20E-03 8.OOE-04 0.OOE+00 2.52E-02 1.30E-02 I1.60E-03 8.90E-02
-1.04E-03
-1I.60E-03
-6.90E-04 4.70E-04 2.531E-02 2.OOE-02
-2.50E-03 3.5013-04 3.0013-03 9.60E-02 I1.40E-03
-8.OOE-04
-2.OOE-05 1.20E-04 8.60E-04 8.20E-04 6.80E-04 7.70E-04 1.20E-03 9.90E-03 2.80E-03 I.50E-02 7.60E-04 8.00E-04
- 8. 1OE-04 8.00E-04 9.50E-04 I.OOE-02 S.50E-03 2.80E-02 1.60E-03 1.80E-03 1.30E-03
- 2. IOE-03
- 2. 1OE-03 3.20E-02 2.90E-03 1.30E-02 7.20E-04 1.40E-03 9.50E-04 4.70E-04
- 1. IOE-03 1.30E-02 1.20E-03 4.70E-04 6.80E-03 1.30E-02
- 1. IOE-03 1.50E-03 1.80E-04 3.70E-04 4.30E-03 3.70E-03 3.20E-03 3.I1OE-03 2.I1OE-03 3.80E-02 I.00E3-02 3.60E-02 3.I1OE-03 4.201E-03 4.20E-03 2.20E-03 1.90E-03 4.90E-02 2.OOE-02 6.70E-02 7.30E-03 8.80E-03 5.30E-03 8.50E-03 4.40E-03 1.20E-01 1.1I OE-02 2.40E-02 3.70E-03 6.30E-03 4.20E-03 1.70E-03 1.70E-03 4.20E-02 5.70E-03 I1.801E-03 2.801E-02 2.70E-02 3.80E-03 5.60E-03 6.50E-04 I1.50E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-21
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCi/m3)
SAMPLE TYPE STD.DEV.
(pCi/m3)
MDC (pCi/m3)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L.8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11 L8266-01 11
.L8266-01 11 L8344-01 11
.L8344-01 11
.L8344-01 11
.L8344-01 11
.L8344-01 II L8344-01 11 L8344-01 11
.L8344-01 11 L8417-01 11
.L8417-01 11 L8417-01 11
.L8417-01 11
.L8417-01 11
.L8417-01 11
.L8417-01 I I L8417-01 11
.L8481-01 11 L8481-01 11 L8481-01 11 L8481-01 11 L8481-01 11 L8481-01 11 L8481-01 11
.L8481-01 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 11/9/2004 11/9/2004 11/9/2004 11/9/2004 11/9/2004 11/9/2004 11/9/2004 11/9/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 0.00E+00
-4.80E-04
-8.OOE-05
-l.IOE-03
-8.00E-03
-5.30E-03 3.50E-03 6.OOE-05
-5.00E-04 0.00E+00
-7.00E-04
-9.00E-04 0.00E+00
-2.00E-04
-4.80E-03 8.30E-02 1.13E-03 I1.30E-03
-5.40E-04
-1I.50E-03 1.38E-02 3.OOE-03
-6.40E-03 5.20E-02 1.60E-04 I1.90E-03 1.00E-04 5.50E-04 1.991E-02
-1
.60E-02 2.50E-03
- 1.
IOE-01
-3.90E-04 I1.301E-03
-7.OOE-04
-2.20E-04 2.37E-02 2.60E-02 3.50E-04 3.60E-04 5.20E-04 I1.80E-03
- 2. 1 OE-02 3.80E-03 7.80E-03
- 3.
1 OE-04
- 1.
I OE-03 6.901E-04 2.601E-03 I1.60E3-03 8.70E-04
- 1. I OE-03 2.601E-03 I1.30E-02 8.30E-04 I.001E-03 7.80E-04 I.00E3-03 9.501E-04 I.00E-02 3.OOE-03 I1.40E-02 9.30E-04 I1.20E-03
- 1.
IOE-03 6.70E-04 I. IOE-03 I1.50E-02 3.60E-03 I1.60E-02 9.10OE-04 L.0E-03 8.60E-04 8.90E-04
- 1. I OE-03 1.501E-02 I.50E-03 1.60E-03 1.90E-03 7.90E-03 8.40E-02 1.90E-02 3.20E-02 1.20E-03 4.50E-03 2.80E-03 1.I OE-02 7.80E-03 3.60E-03 4.60E-03 1.30E-02 2.70E-02 2.80E-03 3.60E-03 3.50E-03 4.40E-03 2.00E-03 4.20E-02 1.70E-02 4.OOE-02 3.90E-03 3.80E-03 4.40E-03 2.60E-03 2.20E-03
- 7. 1OE-02 1.40E-02 2.50E-02 4.00E-03 3.40E-03
- 4. 1OE-03 3.70E-03 2.00E-03 4.80E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-22
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCi/m3)
SAMPLE TYPE STD.DEV.
(pCi/m3)
MDC (pCi/m3)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 11 L8549-01 11 L8549-01 11 L8549-01 11 L8549-01 11 L8549-01 11 L8549-01 11
[L8549-01 11 L8549-01 11 L8604-01 11 L8604-01 11 L8604-01 11 L8604-01 11 L8604-01 11 L8604-01 11
.L8604-01 11
.L8604-01 11 L8665-01 11 L8665-01 11
.L8665-01 11
.L8665-01 11 L8665-01 11
[L8665-01 11
[L8665-01 11
[L8736-01 11
[L8736-01 11
[L8736-01 11
.L8736-01 11 L8736-01 11
.L8736-01 11
[L8736-01 11
[L8736-01 11 L8736-01 11
[L8736-01 11 L8736-01 11
[L8736-01 11
[L8736-01 11
[L8736-01 11
[L8736-01 12/8/2004 12/8/2004 12/8/2004 12/8/2004 12/8/2004 12/8/2004 12/8/2004 12/8/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 12/21/2004 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 AcTh-228 Be-7 Co-58 CO-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 GROSS BETA K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Ag-I 10m Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140
-1.IOE-03 6.60E-02 4.00E-04
-4.50E-04
-1.29E-03 1.44E-03 1.87E-02 I.OOE-03 O.OOE+00 4.90E-02 3.20E-04 9.40E-04 2.20E-04 2.70E-04 1.71E-02
-2.00E-03 1.20E-03 9.50E-02 2.30E-04 1.17E-03 0.00E+00 3.OOE-04
-I1.OIE-02
-4.90E-04 5.80E-04
-5.00E-03
- 5. 1OE-02 1.20E-03
-1.20E-03 3.00E-05
-7.90E-04 2.80E-04
- 2. 1OE-04 4.00E-04
-1.20E-03
-1.1OE-01 3.60E-03
-6.00E-03 2.70E-03
- 1. IOE-02 7.80E-04 6.80E-04 6.30E-04 5.50E-04 9.80E-04 9.70E-03 3.90E-03 I1.30E-02 3.20E3-04 6.70E-04 7.801E-04 8.OOE-04 9.801E-04 I1.50E-02 2.70E-03 1.40E-02 7.70E-04 7.70E3-04 7.70E-04 5.80E-04 9.OOE-03 9.20E-04
- 4. 1 OE-04 1.IOE-02
- 1. IOE-02 I1.4013-03 1.40E-03 I1.70E-04 5.50E-04 3.90E-04 3.30E-04 5.80E-04 I1.401E-03 5.401E-02 3.90E-03 1.301E-02 1.20E-02 2.401E-02 3.OOE-03 3.60E-03 3.5013-03 5.60E-04 I1.60E3-03 4.10OE-02 1.60E-02 3.40E-02 8.70E-04 1.30E-03 3.3013-03 3.20E-03 I1.60E-03 6.40E-02 I.00E-02 3.OOE-02 3.001E-03 2.40E-03
- 3. 1 OE-03 2.201E-03 4.20E-02 4.00E3-03 1.40E-03 5.40E-02 2.901E-02 5.001E-03 5.30E-03 6.001E-04 2.60E-03 I1.50E-03 I1.20E-03 2.OOE-03 7.OOE-03 2.30E-01 1.40E-02 6.20E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-23
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 1I L8736-01 II L8736-01 II L8736-01 II L8736-01 II L8736-01 II L8736-01 II L8736-0l 12 L6809-02 12 L6911-02 12 L6944-02 12 L7052-02 12 L7068-02 12 L7130-02 12 L7190-02 12 L7217-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7282-02 12 L7342-02 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/15/2004 1/31/2004 2/11/2004 3/10/2004 2/25/2004 3/24/2004 4/1/2004 4/13/2004 3/24(2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 4/29/2004 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcIl-228 Ag-1 10m Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA
-1.02E-03
-9.OOE-04 2.30E-03
-2.00E-03 2.90E-03 O.OOE+00 I.00E-03 2.20E-02 1.49E-02 1.94E-02 1.581E-02 2.24E-02 1.34E-02 1.751E-02 1.19E-02 LOOE-05
-2.20E-04 O.OOE+00
- 9. IOE-02
-1.50E-03
-I.00E-03
-7.00E-05
-1.02E-03 3.90E-04
-7.00E-0S
-2.00E-05
-1.40E-03 1.37E-01
-2.03E-02 O.OOE+00 1.70E-04
-2.00E-03
-2.00E-04
-7.00E-04
-2.80E-03
-3.00E-04 8.OOE-04 1.63E-02 3.30E-04 1.20E-03 I.00E-03
- 3. 1OE-03 1.80E-03 6.70E-04 1.20E-03 6.60E-04 6.00E-04 8.1OE-04 9.30E-04 I. IOE-03 8.90E-04 I.SOE-03 I OOE-03 9.40E-04 3.90E-04 1.90E-02 1.30E-02 I.SOE-03 I.50E-03 1.80E-04 4.60E-04 3.90E-04 3.50E-04 5.60E-04
- 2. 1OE-03 8.80E-02 2.80E-03 2.20E-02 3.80E-04 I.00E-03 1.20E-03 2.60E-03 2.OOE-03 I OOE-03 1.20E-03 9.30E-04 1.70E-03 5.20E-03 3.00E-03 1.30E-02 5.60E-03 2.90E-03 4.SOE-03 I. IOE-03 1.20E-03 1.40E-03 I.SOE-03 2.00E-03 1.70E-03 3.00E-03 2.40E-03 3.90E-03 1.80E-03 8.40E-02 2.60E-02 5.70E-03 5.50E-03 6.70E-04 2.60E-03 1.40E-03 I.50E-03 2.1 OE-03 9.50E-03 2.90E-01 2.20E-02 9.70E-02 1.40E-03 5.50E-03 4.60E-03 1.1 OE-02 I.00E-02
- 4. IOE-03 4.30E-03 1.70E-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
MDC (pCi/m3)
(pCilm3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 12 L7401-02 12 L7468-02 12 L7525-02 12 L7609-02 12 L7671-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7704-02 12 L7753-02 12 L7838-02 12 L7904-02 12 L7981-02 12 L8044-02 12 L8119-02 12 L8162-02 12 L8240-02 12 L8266-02 12 L8266-02 12 L8266-02 5/10/2004 5/25/2004 6/2no04 6/23/2004 6/28/2004 6/28/2004 6/2812004 6/28/2004 6128/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6128/2004 6128/2004 6/28/2004 6/28/2004 6128/2004 6/28/2004 6/28/2004 6128/2004 6/28/2004 6/28/2004 6128/2004 6/28/2004 7/14/2004 7/29/2004 8/13/2004 8/27/2004 9/8/2004 9/22/2004 9/29/2004 10/13/2004 9/29/2004 9/29/2004 9/29/2004 GROSSBETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-110m Ba-140 Be-7 Ce-141 Cc-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSSBETA GROSSBETA GROSSBETA GROSSBETA GROSSBETA GROSSBETA GROSSBETA GROSS BETA AcTh-228 Ag-11 Om Ba-140 1.72E-02 1.96E-02 1.16E-02 1.28E-02 2.06E-02 2.00E-03
-3.20E-04 2.50E-03 1.19E-0I
-I.OOE-03 1.OOE-03
-1.00E-04 3.90E-04
-4.OOE-04
-3.60E-04
-1.70E-04 1.OOE-03 I.00E-02 6.60E-03 2.80E-03 5.00E-05
-7. 1OE-04
-5.20E-04 4.90E-03 2.60E-03
-9.80E-04 9.00E-04 1.31E-02 1.52E-02 1.95E-02 2.18E-02 2.01 E-02 1.37E-02 2.92E-02 2.61E-02 1.30E-03 1.OOE-04 2.80E-03 1.20E-03 1.IOE-03 9.00E-04 8.80E-04 2.20E-03 1.30E-03 4.30E-04 5.50E-03 1.20E-02 I.00E-03 1.50E-03 1.60E-04 4.70E-04 4.00E-04 3.40E-04 5.80E-04 1.40E-03 1.40E-02
- 4. IOE-03 6.30E-03 2.80E-04 8.80E-04
- 7. 10E-04 2.90E-03 1.60E-03 6.90E-04 1.IOE-03 8.70E-04 9.70E-04 I.OOE-03 1.20E-03 1.20E-03 9.30E-04 1.90E-03 1.20E-03 I. IOE-03
- 5. IOE-04 4.90E-03 2.50E-03 1.80E-03 1.80E-03 1.90E-03 5.50E-03 4.40E-03 I.90E-03 2.30E-02 2.00E-02 3.90E-03
- 5. IOE-03 6.1 OE-04 1.70E-03 1.80E-03 1.50E-03 2.1 OE-03 5.30E-03 4.90E-02 1.30E-02 2.60E-02
- 1. IOE-03 3.90E-03 3.00E-03 1.30E-02 5.00E-03 3.50E-03 3.80E-03 1.80E-03 2.00E-03 1.50E-03 2.20E-03 2.20E-03 1.90E-03 3.30E-03 1.80E-03 3.80E-03 2.00E-03 2.101E-02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-25
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8266-02 12 L8344-02 12 L8417-02 12 L8481-02 12 L8549-02 12 L8604-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 9/29/2004 912912004 912912004 912912004 9s29/2004 9/29s2004 9/29/2004 9/2912004 9/29/2004 9/29/2004 9/29/2004 9/2912004 9s29/2004 9/29/2004 9/29/2004 9/29/2004 9/29s2004 9/29/2004 9/29/2004 10/2712004 11/912004 11123/2004 12/8/2004 1212112004 1/3/2005 1/3/2005 1n312005 1/312005 1/3n2005 1/3n2005 1/312005 1/3n2005 1/312005 1/3n2005 1/312005 1/3n2005 1/312005 1/3/2005 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-lOrn Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K40 6.90E-02 1.72E-03 6.00E-04
-5.OOE-05 LOOE-04
-1. IOE-04
-6.80E-04
-1.07E-03
-5.OOE-04 1.IOE-02
-1.50E-03 3.30E-03 5.OOE-05 O.OOE+00
-9.20E-04 2.20E-03
-2.00E-04 O.OOE+00 4.60E-04 1.41E-02 1.93E-02 2.32E-02 1.75E-02 1.73E-02 1.20E-03
-9.30E-04
-.OOE-02 6.80E-02 1.70E-03 I. IOE-03
-4.00E-05 6.00E-05
-1.90E-04 1.80E-04 2.70E-04 1.20E-03
-2.60E-02
-9.OOE-04 1.20E-02 9.60E-04 1.30E-03 1.60E-04 4.40E-04 3.80E-04 3.40E-04 5.50E-04 1.60E-03 1.50E-02 4.40E-03 5.60E-03 2.90E-04 1.20E-03 7.60E-04 2.60E-03 1.80E-03 8.80E-04 9.1OE-04 9.60E-04 I. IOE-03
- 1. IOE-03 9.40E-04 9.80E-04 1.IOE-03 4.60E-04 7.00E-03 1.IOE-02 1.40E-03 1.30E-03 1.70E-04 5.60E-04 2.80E-04
- 4. 1OE-04 5.60E-04 1.40E-03 4.90E-02 4.50E-03 2.90E-02 3.10E-03 4.70E-03 6.00E-04 1.80E-03 1.60E-03 1.70E-03 2.20E-03 6.90E-03 5.40E-02 I.90E-02 2.40E-02 1.20E-03 4.70E-03 3.30E-03 9.50E-03 7.80E-03 3.60E-03 4.00E-03 2.00E-03
- 2. 1OE-03 2.00E-03 1.60E-03 1.60E-03 3.80E-03 2.30E-03 4.60E-02
- 2. 1OE-02 4.90E-03 4.50E-03 6.30E-04 2.30E-03 1.40E-03 1.50E-03 2.00E-03 5.40E-03 1.90E-01 1.80E-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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCim3)
STD.DEV.
(pCim3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 12 L8736-02 13 L6809-03 13 L6911-03 13 L6944-03 13 L7052-03 13 L7068-03 13 L7130-03 13 L7190-03 13 L7217-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 13 L7282-03 1/312005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/15/2004 1/31/2004 2/11/2004 3/10/2004 2/25/2004 3/24/2004 4/1/2004 4/13/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-110m Ba-140 Be-7 Ce-141 Ce-144 Co-57 CO-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95
-1.15E-02
-1.20E-04
-9.OOE-04
-8.30E-04 3.40E-03 7.30E-04
-2.40E-04 3.00E-04 3.09E-02 2.04E-02 2.27E-02 2.44E-02 3.3 I E-02 2.41 E-02 2.15E-02 1.70E-02 1.70E-03 7.50E-04 1.IOE-02 LOOE-01
-6.OOE-04 LOOE-03 1.IOE-04
-1.60E-04 3.80E-04
-5.20E-04 8.20E-04
-3.70E-03 1.80E-01
-2.64E-02 1.20E-02
-1.90E-04
-1.20E-03 1.40E-03
-5.00E-03
-1.00E-04
-1.40E-03 3.OOE-03
- 8. 1OE-03 2.90E-04 1.20E-03 9.30E-04 3.20E-03 7.30E-04 9.90E-04 1.30E-03 9.30E-04 8.30E-04
- 1. IOE-03 1.30E-03 1.50E-03 1.40E-03 1.90E-03 1.40E-03 1.IOE-03 8.00E-04 2.90E-02 1.80E-02 2.20E-03 2.00E-03 2.20E-04 8.40E-04 5.60E-04 4.80E-04 7.OOE-04 2.30E-03 1.40E-01 4.90E-03 3.30E-02 4.00E-04 1.90E-03 1.40E-03 4.40E-03 1.70E-03 I. IOE-03 1.90E-03 5.30E-02 1.20E-03 5.20E-03 3.90E-03 1.IOE-02 2.00E-03 4.00E-03 5.00E-03 I.50E-03 1.60E-03 2.00E-03 2.1 OE-03 2.70E-03 2.40E-03 4.20E-03
- 3. 1OE-03 3.70E-03 2.90E-03 1.20E-01 4.20E-02 8.IOE-03 7.20E-03 8.00E-04 3.50E-03 2.1 OE-03 2.20E-03 2.40E-03 1.20E-02 4.70E-0O 3.20E-02 1.30E-0O 1.80E-03 8.20E-03 4.80E-03 I.90E-02 8.80E-03 5.40E-03 5.90E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-27
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 13 L7342-03 13 L7401-03 13 L7468-03 13 L7525-03 13 L7609-03 13 L7671-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7704-03 13 L7753-03 13 L7838-03 13 L7904-03 13 L7981-03 13 L8044-03 13 L8119-03 13 L8162-03 13 L8240-03 13 L8266-03 13 L8266-03 4/29/2004 5/10/2004 5/25/2004 6/7/2004 6/23/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 7/14/2004 7/29/2004 8/13/2004 8/27/2004 9/8/2004 9/22/2004 9/27/2004 10/13/2004 GROSS BETA GROSS BETA GROSSBETA GROSS BETA GROSS BETA GROSSBETA AcTh-228 Ag-110m Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSSBETA GROSS BETA GROSS BETA GROSS BETA GROSSBETA 2.32E-02 2.64E-02 2.53E-02 1.53E-02 2.46E-02 2.49E-02 6.00E-04
-8.00E-04
- 3. 1OE-03 1.32E-01 6.00E-04 6.00E-04
-1.IOE-04
-5. 1OE-04 6.00E-05
-2. 10E-04 4.70E-04
-4.00E-03
-2.00E-03 7.50E-03 3.60E-03 2.90E-04 9.60E-04
-4.70E-04
-2.90E-03 2.60E-03 O.OOE+00
-1.50E-03 1.75E-02 1.95E-02 2.56E-02 2.77E-02 2.50E-02 2.07E-02 3.97E-02 3.52E-02 O.OOE+00
-8.70E-04 1.30E-03 1.90E-03 1.40E-03 1.30E-03 1.40E-03 2.40E-03 1.50E-03 5.80E-04 8.20E-03 1.60E-02 1.30E-03 1.70E-03 2.20E-04 5.40E-04 3.90E-04
- 4. 1OE-04 8.20E-04 1.60E-03 1.50E-02 6.40E-03 9.50E-03 3.40E-04 9.60E-04 9.30E-04 5.OOE-03 2.OOE-03 1.30E-03 1.40E-03 1.30E-03 1.40E-03 1.40E-03 1.60E-03 1.70E-03 1.40E-03 3.30E-03 1.50E-03 1.80E-03 7.90E-04 2.40E-03 3.90E-03 2.40E-03 2.60E-03 2.70E-03 5.80E-03 5.70E-03 2.80E-03 3.30E-02 3.30E-02 4.80E-03
- 6. 1OE-03 8.30E-04 2.60E-03 1.70E-03 1.801E-03 2.90E-03 9.50E-03
- 6. 1OE-02 2.20E-02 3.80E-02 1.30E-03 3.50E-03 3.90E-03 2.00E-02 6.90E-03 5.30E-03 6.30E-03 2.90E-03 2.90E-03 2.20E-03 3.20E-03 3.20E-03 2.80E-03 6.80E-03 2.30E-03 7.20E-03 3.50E-03 9/27/2004 AcTh-228 9/27/2004 Ag-llOm
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8266-03 13 L8344-03 13 L8417-03 13 L8481-03 13 L8549-03 13 L8604-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 912712004 9s27/2004 9/27/2004 9/27/2004 9/27/2004 9/27f2004 9127/2004 9/2712004 9/27/2004 9/27/2004 9127/2004 9/2712004 9s27n2004 9s27n2004 10/27/2004 11/9/2004 11/23/2004 12/8/2004 1212112004 1/3n2005 1/312005 1/312005 1/312005 1/3n2005 1/312005 1/312005 1/3/2005 1/3/2005 1/3n2005 1/3/2005 Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-I lOm Ba-140 Be-7 Cc-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 4.60E-03 1.49E-01
-2.20E-03
-5.00E-04
-4.00E-05
-5.90E-04 4.00E-05 7.00E-04 5.70E-04 1.60E-03
-2.00E-03 3.40E-03 5.30E-03 2.90E-04
-3.30E-03
-8.00E-04 5.50E-03
-1.30E-03 4.00E-04 6.00E-04 1.59E-02 2.39E-02 2.85E-02 2.39E-02 1.83E-02 1.40E-03 8.OOE-05
-7.30E-03 6.20E-02
-2.00E-04
-3. 1OE-03 1.70E-04
-3.80E-04
-1.02E-03 5.OOE-05
-4.20E-04 4.20E-03
-1.20E-02 8.00E-03 1.80E-02 1.70E-03 2.202-03 2.40E-04 6.30E-04 6.60E-04 4.50E-04 9.00E-04 2.00E-03 2.90E-02 6.50-03
- 9. 1OE-03 6.30E-04 1.302-03 1.30E-03 3.60E-03 2.50E-03 1.30E-03 1.40E-03 1.30E-03 1.70E-03 1.50-03 1.30E-03 1.20E-03 1.50E-03 5.20E-04 7.30E-03 1.50E-02 2.00E-03 2.00E-03 2.50E-04 7.50E-04 5.80E-04 4.50E-04 6.70E-04 2.20E-03 7.20E-02 3.40E-02 2.802-02 6.80E-03 8.10E-03
- 9. 1OE-04 3.10E-03 2.70E-03 1.50E-03 3.20E-03 7.40E-03
- 1. 10-01 2.50E-02 3.90E-02 2.30E-03 6.80E-03 5.50E-03 1.20E-02 1.20E-02 5.10E-03 5.50E-03 2.90E-03 3.602-03 2.80E-03 2.30E-03 2.30E-03 5.50E-03 2.20E-03 5.40E-02 3.90E-02 7.30E-03 8.00E-03 8.90E-04 3.30E-03 2.802-03 1.802-03 2.60E-03 6.20E-03 2.80E-01 1/3f2005 Fe-59 1/3f2005 1-131
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-29
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 13 L8736-03 14 L6809-04 14 L6911-04 14 L6944-04 14 L7052-04 14 L7068-04 14 1L7130-04 14 L7190-04 14 L7217-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14 L7282-04 14
.L7282-04 14 L7282-04 14 L7282-04 1/3n2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/15/2004 1/31/2004 2/11/2004 3/10/2004 2/25/2004 3/24/2004 4/2/2004 4/13/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 K40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSSBETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-110n Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 1.191-02
-8.40E-03
-4.90E-04 6.00E-04 1.20E-03 1.07E-02 L.00E-03
-I.70E-03
- I. IOE-03 2.40E-02 1.792-02 2.05E-02 1.87E-02 2.69E-02 I1.501-02 1.3 1E-02 1.23E-02
-6.00E-04 1.901E-04 8.002-03 7.30E-02
-8.00E-04 8.00E-04 3.40E-04 4.OOE-05 1.30E-04 1.50E-04
-1.30E-03 1.30E-03
-7.00E-02
-1.49E-02 9.00E-03
-3.10E-04
-2. 1OE-03 1.20E-03 2.10E-03
-1.70E-03 2.50E-04 7.70E-03 8.40E-03 5.20E-04 1.70E-03 1.40E-03 4.50E-03 1.90E-03 1.30E-03 1.IOE-03 6.80E-04 6.40E-04 8.10E-04 9.60E-04 1.IOE-03 9.20E-04 1.20E-03 I.00E-03 1.20E-03 3.60E-04 1.70E-02 1.20E-02 1.40E-03 1.30E-03 1.50E-04 6.70E-04 3.40E-04 2.80E-04 5.20E-04 1.90E-03 7.30E-02 4.00E-03 2.00E-02 2.70E-04 1.50E-03 9.30E-04 2.50E-03 1.20E-03 8.40E-04 2.50E-02 6.20E-02 2.30E-03 6.60E-03
- 5. IOE-03 1.30E-02 8.10E-03 6.00E-03 5.50E-03 I.OOE-03 1.20E-03 1.40E-03 I.50E-03 1.90E-03 1.70E-03 2.40E-03 2.30E-03 4.90E-03 1.40E-03
- 7. IOE-02 2.30E-02 5.40E-03 4.60E-03 4.60E-04 2.70E-03 1.40E-03
- 1. IOE-03 2.20E-03 7.10E-03 3.20E-01 2.20E-02 8.10E-02 1.30E-03 6.80E-03 3.10E-03 9.30E-03 7.80E-03 3.30E-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 14 L7282-04 14 L7342-04 14 L7401-04 14 L7468-04 14 L7525-04 14 L7609-04 14 L7671-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14
[L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14
[L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7704-04 14 L7753-04 14 L7838-04 14 L7904-04 14 L7981-04 14
.L8044-04 14 L[8119-04 14 LS[162-04 1 4 L8240-04 1
4 1,8266-04 3/24/2004 4/29/2004 5/10/2004 5/25/2004 6/712004 612312004 6/28/2004 6/28/2004 612812004 6/28/2004 6128/2004 6/28/2004 6128/2004 6/28/2004 6128/2004 6128/2004 6/28/2004 6/28/2004 6/28/2004 6/282004 6/282004 6128/2004 6/28/2004 612812004 6128/2004 6/28/2004 612812004 6/2812004 612812004 7/14/2004 712912004 8/13/2004 8/27/2004 9/8/2004 9/22/2004 9/29/2004 10/1312004 9129/2004 Zr-95 GROSSBETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-1 [Om Ba-140 Be-7 Cc-141 Ce-144 Co-57 CO-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSSBETA GROSS BETA GROSS BETA GROSS BETA GROSSBETA GROSS BETA AcTh-228 4.00E-04 1.61E-02 1.86E-02 2.07E-02 1.14E-02
.78E-02
.97E-02 7.00E-04
-1.70E-04 O.OOE+00 1.IOE-01 1.60E-03
-2.40E-03 I.50E-04
-4.30E-04
-3.70E-04 O.OOE+00
- 4. 1OE-04 2.30E-03 2.00E-03 3.90E-03 O.OOE+00
-2.70E-04 3.90E-04
-6.40E-04 6.00E-04
-8.00E-04 O.OOE+00
-4.1 OE-04 1.20E-02 1.43E-02 1.90E-02 1.81E-02 1.78E-02 1.29E-02 2.60E-02 2.52E-02
-5.90E-04 1.20E-03 8.90E-04 1.20E-03 I.00E-03 8.70E-04 9.40E-04 2.10E-03 I.IOE-03 4.20E-04 4.60E-03 1.20E-02 I. IOE-03 1.30E-03 1.60E-04 5.90E-04 3.70E-04 3.80E-04 5.40E-04 1.50E-03 1.40E-02 3.50E-03 5.30E-03 2.70E-04
- 7.
1OE-04 7.50E-04 2.30E-03 1.40E-03 5.60E-04 8.00E-04 8.10E-04 9.10E-04 9.50E-04 1.IOE-03 1.IOE-03 8.80E-04 1.70E-03 I.
IOE-03 8.40E-04 4.60E-03 1.60E-03 2.40E-03 1.60E-03 1.70E-03 1.80E-03 5.20E-03
- 4. 1OE-03 1.80E-03 2.IOE-02 2.20E-02 3.50E-03 5.20E-03 5.40E-04 2.50E-03 1.70E-03 1.50E-03 1.90E-03 5.OOE-03 5.30E-02 1.20E-02 2.40E-02 1.30E-03 2.80E-03 3.1OE-03
- 9.
1OE-03 6.90E-03 2.40E-03 3.50E-03 1.70E-03 1.90E-03 1.40E-03
- 2. 1OE-03 2.00E-03 1.80E-03 2.90E-03 1.80E-03 3.90E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-31
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV.
MDC TYPE STATION LSN DATE NUCLIDE (pCim3)
(pCi/m3)
(pCim3)
AP 14 L8266-04 9/29/2004 Ag-10m 5.80E-04 4.1OE-04 1.40E-03 AP 14 L8266-04 9/29/2004 Ba-140
-5.30E-03 6.50E-03 3.20E-02 AP 14 L8266-04 9/2912004 Be-7 9.10E-02 1.20E-02 2.30E-02 AP 14 L8266-04 9/2912004 Ce-141 I.90E-03 1.OOE-03 3.30E-03 AP 14 L8266-04 9/29/2004 Ce-144
-1.OOE-04 I.IOE-03 4.20E-03 AP 14 L8266-04 9/29/2004 Co-57 0.OOE+00 1.50E-04 5.60E-04 AP 14 L8266-04 9/29/2004 Co-58 8.40E-04 4.70E-04 1.40E-03 AP 14 L8266-04 9/29/2004 Co-60
-2.30E-04 3.30E-04 I.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 Fe-59 0.00E+00 1.40E-03 5.90E-03 AP 14 L8266-04 9/29/2004 1-131
-2.50E-02 1.30E-02 6.20E-02 AP 14 L8266-04 9/29/2004 K-40
-3.80E-03 3.80E-03 1.80E-02 AP 14 L8266-04 9/29/2004 La-140
-6.1OE-03 7.40E-03 3.60E-02 AP 14 L8266-04 9/29/2004 Mn-54
-1.IOE-04 3.1OE-04 1.30E-03 AP 14 L8266-04 9/29/2004 Nb-95
-I1.OOE-03 9.30E-04 4.20E-03 AP 14 L8266-04 9/29/2004 Ru-103
-6.90E-04
-3.40E-03 2.60E-03 1.20E-02 AP 14 L8266-04 9/29/2004 Sb-124
-7.00E-04 7.00E-04 5.OOE-03 AP 14 L8266-04 9/29/2004 Zn-65
-1.19E-03 7.90E-04 3.80E-03 AP 14 L8266-04 9/29/2004 Zr-95 6.90E-04 8.30E-04 3.00E-03 AP 14 L8344-04 10/27/2004 GROSS BETA 1.22E-02 8.70E-04 1.90E-03 AP 14 L8417-04 11/9/2004 GROSS BETA 1.85E-02 I.00E-03 2.OOE-03 AP 14 L8481-04 11/23/2004 GROSS BETA 2.23E-02 1.lOE-03 1.90E-03 AP 14 L8549-04 12/8/2004 GROSS BETA 1.73E-02 9.20E-04 I.50E-03 AP 14 L8604-04 12/21/2004 GROSS BETA 1.65E-02 9.30E-04 I.SOE-03 AP 14 L8736-04 1w4/2005 AcTh-228 8.80E-04 9.10E-04 3.30E-03 AP 14 L8736-04 1/4/2005 Ag-llOm 1.04E-03 4.30E-04 I.IOE-03 AP 14 L8736-04 1/4/2005 Ba-140 8.90E-03 8.90E-03 3.30E-02 AP 14 L8736-04 1/4/2005 Be-7 7.1OE-02 I.IOE-02 2.20E-02 AP 14 L8736-04 1/4/2005 Ce-141
-6.00E-04 1.20E-03 4.60E-03 AP 14 L8736-04 1/4/2005 Ce-144
-1.00E-04 1.40E-03 5.00E-03 AP 14 L8736-04 1/4/2005 Co-57 2.20E-04 1.SOE-04 5.OOE-04 AP 14 L8736-04 1/412005 Co-SB 6.80E-04 5.60E-04 I.90E-03 AP 14 L8736-04 1/4/2005 Co-60 3.50E-04 2.90E-04 I.00E-03 AP 14 L8736-04 1/4/2005 Cs-134 3.OOE-04 2.70E-04 9.60E-04 AP 14 L8736-04 1/4/2005 Cs-137 3.80E-04 6.00E-04 2.1OE-03 AP 14 L8736-04 1/4/2005 Fe-59 O.OOE+00 I.SOE-03 6.SOE-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-32
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
MDC (pCi/m3)
(pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 14 L8736-04 21 L6809-05 21 L6911-05 21 L6944-05 21 L7052-05 21 L7068-05 21 L7130-05 21 L7190-05 21 L7217-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-O5 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 21 L7282-05 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/15/2004 1/31/2004 2/11/2004 3/10/2004 2/25/2004 3/24/2004 3/31/2004 4/13/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 3/24/2004 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-I lOmn Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 1.90E-02
-7.30E-03 1.OOE-02
-2.00E-05 I.OOE-03
-1. 16E-03
-6.00E-04
-8.OOE-04
-2.20E-04 7.20E-04 1.73E-02 I.59E-02 1.26E-02 1.66E-02 2.05E-02 I.28E-02 L.68E-02 1.44E-02
-4.OOE-04 2.00E-04
-2.90E-02 1.00E-01 7.00E-04 1.50E-03 O.OOE+00
-5.80E-04
-7.20E-04
-7.00E-05 1.06E-03
-8.00E-04
-6.40E-02
-1.43E-02
-3.30E-02
-7.00E-05 3.70E-03
-3.00E-04
-7.20E-03
-2.00E-04 3.60E-02 3.90E-03 I.00E-02 2.80E-04 I. IOE-03 8.70E-04 2.70E-03 1.60E-03 5.90E-04 8.60E-04 8.30E-04 7.60E-04 7.30E-04 I.00E-03 1.IOE-03 9.40E-04 1.30E-03 1.20E-03 1.IOE-03 3.00E-04 1.70E-02 1.50E-02 1.70E-03 1.40E-03 2.00E-04 6.80E-04 3.60E-04 4.00E-04 7.20E-04 1.40E-03 9.60E-02 5.70E-03 1.90E-02 3.00E-04 1.70E-03 1.30E-03 3.80E-03 2.1OE-03 1.30E-01 1.90E-02 3.80E-02 1.20E-03 3.80E-03 3.80E-03 1.IOE-02 7.70E-03 2.70E-03 3.20E-03 1.70E-03 1.60E-03 1.50E-03 1.80E-03 2.20E-03 1.90E-03 2.50E-03 2.70E-03 4.80E-03 1.30E-03 I.OOE-0I 3.00E-02 6.30E-03 4.70E-03 7.50E-04
- 3. 1OE-03 2.OOE-03 1.70E-03 2.40E-03 7.70E-03 4.10E-0I 2.80E-02 1.20E-0I 1.30E-03 4.70E-03 5.30E-03 1.70E-02 9.90E-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
MDC (pCi/m3)
(pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 21 L7282-05 21 L7282-05 21 L7342-05 21 L7401-05 21 L7468-05 21 L7525-05 21 L7609-05 21 L7671-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7704-05 21 L7753-05 21 L7838-05 21 L7904-05 21 L7981-05 21 L8044-05 21 L8119-05 21 L8162-05 3/24/2004 3/24/2004 4/29/2004 5/10/2004 5/25/2004 6/7/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/14/2004 7/29/2004 8/13/2004 8/27/2004 9/8/2004 9/22/2004 9/27/2004 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-110m Ba-140 Be-7 Cc-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA
-1.60E-03 6.00E-04 1.76E-02 2.05E-02
.78E-02 I.21E-02 1.98E-02 1.43E-02 I.06E-03
-7. 1OE-04
-9.90E-03 9.70E-02 5.OOE-04
-2. 10E-03
-2.50E-04
-9.ooE-05
-2.80E-04
-1.90E-04 2.90E-04
-I.50E-03
-2.80E-02 5.OOE-04
-1.14E-02 2.40E-04
-7.20E-04 1.70E-04
-2.80E-03
-2.20E-03 2.50E-04
-2.00E-04 1.33E-02 1.65E-02 1.91E-02 2.12E-02 2.08E-02 1.37E-02 3.32E-02 2.30E-02 9.60E-04 1.40E-03 9.60E-04 1.30E-03 I.00E-03 9.20E-04 I.00E-03 2.00E-03 9.90E-04 4.50E-04 7.00E-03 1.20E-02 I.IOE-03 1.30E-03 1.60E-04
- 5. 1OE-04 4.20E-04 3.90E-04 5.60E-04 1.70E-03 1.50E-02 4.00E-03 8.00E-03 3.30E-04 8.90E-04 6.80E-04 3.00E-03 1.60E-03 6.50E-04 I.OOE-03 8.90E-04 I.OOE-03 I1.OOE-03 I. IOE-03 1.20E-03 9.40E-04 2.40E-03 4.80E-03 5.30E-03 1.80E-03 2.60E-03 1.80E-03 1.80E-03 1.90E-03 5.50E-03 3.50E-03 2.20E-03 3.50E-02 2.40E-02 3.80E-03 S.40E-03 6.50E-04
- 2. 1OE-03 1.80E-03 1.60E-03 2.00E-03 7.50E-03 6.50E-02 1.60E-02 4.00E-02 1.20E-03 4.00E-03 2.60E-03 1.30E-02 8.40E-03 2.70E-03 4.1OE-03 1.80E-03 2.00E-03 1.60E-03 2.20E-03 2.20E-03 1.90E-03 4.50E-03 21 L8240-05 10/13/2004 GROSS BETA I.00E-03 1.70E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-34
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8266-05 21 L8344-05 21 L8417-05 21 L8481-05 21 L8549-05 21 L8604-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 9/27/2004 10/27/2004 11/9/2004 11/23/2004 12/8/2004 12/21/2004 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 AcTh-228 Ag-110m Ba-140 Be-7 Ce-141 Ce-144 Co-57 CO-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-I ]Om Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 I1.30E3-03
-4.001E-05
-6.40E-03 I. I 8E-0 I
-2.70E-03 4.OOE-04 2.OOE-05
-7.001E-04
-3.70E-04 2.501E-04
-1.281E-03 6.001E-04
-2.OOE-03 7.601E-03
-7.40E-03
-5.OOE-04 I.OOE3-04 3.90E-04 5.301E-03
-9.001E-04
-8.00E3-04
-1. 12E-03 1.29E-02 1.87E-02 2.20E-02 I1.941E-02 I1.63E-02 4.001E-04 7.OOE-05 5.OOE-03 6.201E-02 9.OOE-04 7.OOE-04
-1.70E-04
- 6. 1OE-04 1.901E-04
- I1.40E-04
-5.70E-04 1.30E-03 5.10E-04 7.90E-03 1.40E-02 1.30E-03 1.40E-03 1.50E-04 7.30E-04 3.90E-04 3.50E-04 5.60E-04 2.20E-03 2.00E-02 5.50E-03 9.OOE-03 3.20E-04 I.IOE-03 8.30E-04 2.90E-03 1.70E-03 7.00E-04 9.70E-04 9.20E-04 I.IOE-03 1.20E-03 I.OOE-03 9.70E-04 1.40E-03 4.20E-04 1.30E-02 1.20E-02 1.60E-03 1.40E-03 1.80E-04 5.50E-04 4.30E-04 2.60E-04 5.20E-04 4.60E-03
- 2. 1OE-03 3.90E-02 2.70E-02 5.20E-03 5.20E-03 5.40E-04
- 3. 1OE-03 1.80E-03 1.30E-03 2.30E-03 8.30E-03 7.70E-02 1.80E-02 4.40E-02 1.50E-03 4.50E-03 3.1OE-03 9.00E-03 8.20E-03 3.50E-03 4.50E-03 2.00E-03 2.20E-03 2.40E-03 1.70E-03 1.60E-03 5.20E-03 1.70E-03 5.40E-02 2.90E-02 5.70E-03 5.1OE-03 6.80E-04 1.90E-03 1.60E-03 1.20E-03 2.00E-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE TYPE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP I
STATION LSN D
21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 21 L8736-05 31 L6809-06 31 L6911-06 31 L6944-06 31 L7052-06 31 L7068-06 31 L7130-06 31 L7190-06 31 L7217-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 31 L7282-06 1/
I/
2I 3I 2I 3/
4/
3/
3/
3/
3/
3/:
3/:
3/:
3/
3/
3/
3/
3,:
3/:
3,:
Summary of 2004 Data END ATE NUCLIDE 11412005 Fe-59 1/4/2005 1-131 1/4w2005 K40 11412005 La-140 1n4o2005 Mn-54 1/4n2005 Nb-95 11412005 Ru-103 1w4o2005 Ru-106 1/4n2005 Sb-124 1/4n2005 Zn-65 1/4n2005 Zr-95
'15/2004 GROSS BETA 3112004 GROSS BETA
' 112004 GROSS BETA 110/2004 GROSS BETA 2512004 GROSS BETA 2412004 GROSS BETA 1/1/2004 GROSS BETA 1312004 GROSS BETA 24/2004 AcTh-228 2412004 Ag-i lOm 2412004 Ba-140 2412004 Be-7 2412004 Ce-141 2412004 Ce-144 2412004 Co-57 2412004 Co-58 24/2004 Co-60 2412004 Cs-134 24/2004 Cs-137 24/2004 Fe-59 24/2004 1-131 2412004 K40 2412004 La-140 2412004 Mn-54 24/2004 Nb-95 2412004 Ru-103 2412004 Ru-106 CONC (pCi/m3) 3.OOE-03
-2.30E-02
-3.30E-03 6.00E-03 3.30E-04 1.00E-04 8.70E-04
-7.00E-04
-I.90E-03
-L.49E-03 3.00E-04 2.76E-02
.68E-02 2.06E-02 2.03E-02 2.90E-02 1.93E-02 2.26E-02 1.59E-02
-2.00E-03
-1.30E-04
-2.00E-02 8.OOE-02
-1.40E-03
-4.00E-04
-2.00E-04 6.OOE-05 7.90E-04
-6.00E-05 1.901E-04 9.OOE-04
-9.00E-02
-8.60E-03
-2.30E-02 1.801E-04 4.00E-04 0.00E+00
-I.90E-03 STD.DEV.
(pCi/m3) 1.60E-03
- 5. IOE-02 3.70E-03
.50E-02 3.40E-04 1.30E-03 9.70E-04 2.30E-03 2.50E-03 8.60E-04 1.30E-03 8.50E-04 6.20E-04 s.90E-04 1.20E-03 2.00E-03 1.20E-03 1.80E-03 1.30E-03 1.50E-03 3.90E-04 2.80E-02 1.50E-02 2.20E-03
- 2. 1OE-03 2.1 OE-04 8.80E-04 4.50E-04 3.70E-04 7.70E-04 2.90E-03 1.30E-01 5.90E-03 3.20E-02 3.90E-04 1.80E-03 9.90E-04 3.90E-03 MDC (pCi/m3) 4.40E-03 2.00E-01 1.70E-02 6.20E-02 1.20E-03
- 5. 1OE-03 3.40E-03 9.80E-03
- 1. IOE-02 4.1OE-03 5.00E-03 1.40E-03 1.20E-03 1.60E-03
- 2. 1OE-03 4.30E-03 2.20E-03 3.70E-03 2.90E-03 6.70E-03 1.90E-03 1.30E-0O 3.30E-02 8.40E-03 7.60E-03 8.30E-04 3.50E-03 1.40E-03 1.60E-03 2.80E-03 1.1 OE-02 5.20E-01 2.70E-02 I.SOE-0I 1.50E-03 7.00E-03 4.1 OE-03 1.60E-02
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END DATE CONC (pCim3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
STATION LSN NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 31 L7282-06 31 L7282-06 31 L7282-06 31 L7342-06 31 L7401-06 31 L7468-06 31 L7525-06 31 L7609-06 31 L7671-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7704-06 31 L7753-06 31 L7838-06 31 L7904-06 31 L7981-06 31 L8044-06 31 L8119-06 31 L8162-06 3/24/2004 3/24/2004 3/24/2004 4/29/2004 5/10/2004 5/25/2004 6/72004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/14/2004 7/29/2004 8/13/2004 8/27/2004 9/8/2004 9/22/2004 9/29/2004 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-1 10m Ba-140 Be-7 Cc-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA 3.20E-03
-3.30E-04 2.50E-03 1.96E-02 2.22E-02 2.12E-02 1.70E-02 2.36E-02 I.91E-02
- 2.
-3.80E-04
-1.25E-02 1.18E-10
-1.00E-04 9.00E-04
-1.00E-05
-7.60E-04 2.20E-04 3.30E-04 2.40E-04 6.00E-04 2.90E-02 5.30E-03
-1.43E-02 6.1 OE-04 I.00E-03
-2.20E-04 1.80E-03
-1.00E-04 3.1OE-04
-1.OOE-03 1.33E-02 1.80E-02 2.18E-02 2.36E-02 2.28E-02 1.65E-02 3.53E-02 1.80E-03 8.80E-04 1.20E-03
- 1. IOE-03 1.60E-03 1.30E-03 1.20E-03 1.20E-03 2.70E-03 1.40E-03 5.90E-04 7.60E-03 1.40E-02 1.40E-03 1.80E-03 1.70E-04 7.30E-04 4.40E-04 3.30E-04 7.90E-04 1.70E-03 2.OOE-02 6.40E-03 8.80E-03 3.70E-04 I.50E-03 8.50E-04 2.80E-03 1.20E-03 8.20E-04 1.30E-03 9.50E-04 I.IOE-03 1.20E-03 1.30E-03 1.40E-03 1.IOE-03 2.20E-03 2.90E-03 4.00E-03 3.30E-03 2.20E-03 3.30E-03 2.20E-03 2.40E-03 2.40E-03 7.20E-03 4.40E-03 2.60E-03
- 4. 1OE-02 2.60E-02 5.IOE-03 6.20E-03 6.SOE-04 3.20E-03 1.70E-03 1.20E-03 2.80E-03 6.80E-03 6.70E-02 2.30E-02 4.70E-02 1.20E-03 5.30E-03 3.50E-03 I. IOE-02 6.40E-03 3.30E-03 5.50E-03 2.00E-03 2.30E-03 1.80E-03 2.60E-03 2.SOE-03 2.20E-03 3.70E-03
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/m3)
STD.DEV.
(pCi/m3)
MDC (pCi/m3)
NUCLIDE AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 31 L8240-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8266-06 31 L8344-06 31 L8417-06 31 L8481-06 31 L8549-06 31 L8604-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 31 L8736-06 10/13/2004 9/29/2004 9/29/2004 9129/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9(29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 10/27/2004 11/9/2004 11/23/2004 12/8/2004 12/21/2004 1/5/2005 1/5/2005 1/5/2005 1/5/2005 1/5/2oo5 1/5/2005 1/5/2005 1/5/2005 115/2005 1/5/2005 GROSS BETA AcTh-228 Ag-110m Ba-140 Be-7 Ce-141 Cc-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 GROSS BETA GROSS BETA GROSS BETA GROSS BETA GROSS BETA AcTh-228 Ag-110n Ba-140 Be-7 Ce-141 Ce-144 Co-S57 Co-58 Co-60 Cs-134 2.83E-02 4.00E-04 1.20E-04 6.60E-03 1.03E-01 4.OOE-04
-8.00E-04 2.00E-04
-4.80E-04 2.90E-04 4.00E-05
-7.70E-04 1.80E-03 1.70E-02 8.soE-03 8.OOE-03 1.02E-03 2.soE-03
-1.28E-03 0.00E+00 7.00E-04
-8.90E-04 2.90E-03 1.34E-02 1.99E-02 2.14E-02 1.74E-02 2.11 E-02 I.00E-04 3.50E-04 5.00E-03 6.30E-02 1.20E-03
-I.00E-04 3.00E-05
-4.00E-05 3.50E-04 I. IOE-04 1.30E-03 I.IOE-03 5.90E-04 9.30E-03 1.40E-02 1.20E-03 1.80E-03 2.00E-04 5.50E-04 4.20E-04 3.90E-04 7.60E-04 1.80E-03 2.40E-02 6.40E-03 1.lIOE-02 4.20E-04 1.IOE-03 8.00E-04 3.40E-03 1.40E-03 8.90E-04 1.IOE-03 I.00E-03 1.20E-03 1.20E-03 1.00E-03 1.IOE-03 1.20E-03
- 4. 1OE-04 1.20E-02 I.00E-02 1.60E-03 1.70E-03 1.90E-04 3.80E-04 5.40E-04 4.20E-04
- 2. 1OE-03 4.40E-03 2.30E-03 3.60E-02 3.00E-02 4.50E-03 6.80E-03 7.00E-04 2.60E-03 1.60E-03 1.60E-03 2.90E-03 6.60E-03 8.50E-02 2.20E-02 4.10E-02
- 1. IOE-03 3.20E-03 3.70E-03 1.30E-02 6.20E-03 4.20E-03 2.60E-03 2.30E-03 2.50E-03 2.30E-03 1.80E-03 1.80E-03 4.80E-03 1.50E-03 4.80E-02 2.00E-02 5.60E-03
- 6. 1OE-03 7.00E-04 1.80E-03 2.00E-03 1.60E-03
- Radioactivity detected in sampic (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-38
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 L8736-06 1/5/2005 Cs-137
-1.12E-03 5.SOE-04 2.30E-03 AP 31 L8736-06 1/5/2005 Fe-59 0.OOE+00 2.OOE-03 8.40E-03 AP 31 L8736-06 1/5/2005 1-131 3.20E-02 4.40E-02 1.60E-01 AP 31 L8736-06 1/5/2005 K40
-1.OOE-03 4.30E-03 1.80E-02 AP 31 L8736-06 1/5/2005 La-140 6.00E-03 1.30E-02 5.50E-02 AP 31 L8736-06 1/5/2005 Mn-54 7.OOE-05 3.SOE-04 1.40E-03 AP 31 L8736-06 1/5/2005 Nb-95
-5.OOE-04 L.OOE-03 4.SOE-03 AP 31 L8736-06 1/5/2005 Ru-103
-2.00E-04 1.20E-03 4.60E-03 AP 31 L8736-06 1/5/2005 Ru-106
-3.80E-03 3.30E-03 1.40E-02 AP 31 L8736-06 1/5/2005 Sb-124 6.00E-04 2.20E-03 9.10E-03 AP 31 L8736-06 1/5/2005 Zn-65
-8.OOE-04 l.OOE-03 4.SOE-03 AP 31 L8736-06 1/5/2005 Zr-95 2.24E-03 9.90E-04 2.50E-03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-39
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/kg)
STD.DEV.
(pCi/kg)
MDC (pCi/kg)
NUCLIDE FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH FH L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L7398-01 L8337-01 L8337-01 II L8337-01 I11 L8337-01 L833701 L8337-01 L8337-01 L8337-01 L8337-01 L8337-01 18337-01 L8337-01 L8337-01 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 4/22/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 10/19/2004 Ag-l Orm Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-S Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 Ag-I lOm Ba-140 Be-7 Cc-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 0.00E+00 1.20E+01
-6.20E3+01 4.90E+01 0.0013+00 1.001E+02
-2.70E+01 2.30E+01
-1.30E3+01 4.6013+01
-9.80E+00 5.901E+00 1.00E+01 1.IOE3+01
-I.10E+01 1.OO1E+01 2.60E+00 8.801-'-00 3.9013+01 1.40E+01
-2.20E+01 4.50E+01
-5.0013+01 1.30E+02 3.40E+03 3.30E+02
-7.20E+0 I 5.70E3+01 I.00E+01 1.20E3+01
-1.50E3+01 1.601E+01 1.40E3+01 1.40E+01
-5.70E+01 9.40E+01 9.40E+00 9.40E+00 0.00E+00 2.2013+01 5.IOE1+01 2.10OE+01
-7.OOE+00
- 1. IOE+01 0.0013+00 2.80E+01 1.70E3+01 8.90E+01I
-9.OOE+00 I1.70E+01
- 1. 16E+02 5.0013+01
-2.3013+00 6.80E+00 1.91 E+0 1 9.I1OE+00 l.OOE+01 1.30E+01
- 7. 1OE1+00 9.40E+00 3.5013+01 1.40E+01 1.201E+01 3.801E+01
-1.47E+02 5.40E+01 2.28E+03 3.20E+02 0.OOE+00 3.20E+01
-1.59E+01 9.90E+00 2.30E+01 l.1OE+01
-2.30E+01 1.30E+01 4.80E+01 2.30E+02 3.80E3+02 8.70E+01 I1.7013+02 2.30E+01 3.90E+01 4.60E+01 3.40E3+01 4.20E3+01 I1.80E+02 5.0013+02 5.0013+02 2.70E+02 4.OOE-i01 6.50E3+01 5.OOE+01 3.70E+02 2.60E+01 8.60E+01 5.90E+01 5.001E+01 I1.201-i-02 3.40E3+02 6.30E+01 1.60E+02 2.50OE+01 2.60E3+01 4.80E+01 3.40E+01 4.1013+0 I 1.5013+02 2.30E3+02 6.40E3+02 1.40E+02 4.40E+0 1 3.30E+01 5.40E+0 I I I L8337-01 10/19/2004 La-140 11 L8337-01 10/19/2004 Mn-54 11 L8337-01 I I L8337-01 10/19/2004 Nb-95 10/19/2004 Ru-103
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-40
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 Il L8337-01 10/19/2004 Ru-106
-5.70E+01 9.90E+01 3.90E+02 FH 11 L8337-01 10/19/2004 Sb-124 O.OOE+00 2.OOE+01 9.10E+01 FH II L8337-01 10/19/2004 Zn-65 2.30E+01 2.80E+01 9.90E+01 FH 11 L8337-01 10/19/2004 Zr-95 3.90E+01 I.90E+01 5.90E+0I FH 21 L7398-02 4/22/2004 Ag-l lOm
-7.00E+00 1.70E+01 6.90E+01 FH 21 L7398-02 4/22/2004 Ba-140
-1.21E+02 5.70E+01 3.OOE+02 FH 21 L7398-02 4/22/2004 Be-7 5.90E+01 7.70E+01 2.80E+02 FH 21 L7398-02 4/22/2004 Ce-141
-4.00E+00 2.20E+01 7.80E+OI FH 21 L7398-02 4/22/2004 Ce-144
-3.40E+01 5.10E+01 1.90E+02 FH 21 L7398-02 4/22/2004 Co-57
-3.90E+00 6.SOE+00 2.40E+01 FH 21 L7398-02 4/22/2004 Co-58
-1.60E+01 1.30E+OI 5.50E+O1 FH 21 L7398-02 4/22/2004 Co-60
-2.00E+00 I.00E+01 4.40E+O1 FH 21 L7398-02 4/22/2004 Cs-134 4.50E+00 8.80E+00 3.40E+0O FH 21 L7398-02 4/22/2004 Cs-137
-6.00E+O0 1.IOE+01 4.40E+01 FH 21 L7398-02 4/22/2004 Fe-59
-1.33E+02 5.90E+01 2.70E+02 FH 21 L7398-02 4/22/2004 1-131
-2.1OE+02 1.30E+02 5.30E+02 FH 21 L7398-02 4/22/2004 K-40 3.52E+03 3.70E+02 5.20E+02 FH 21 L7398-02 4/22/2004 La-140
-1.39E+02 6.SOE+01 3.50E+02 FH 21 L7398-02 4/22/2004 Mn-54 I.00E+00 I.00E+OI 4.00E+01 FH 21 L7398-02 4/22/2004 Nb-95 2.20E+01 2.00E+01 6.90E1+O0I FH 21 L7398-02 4/22/2004 Ru-103
-6.OOE+00 1.60E+01 6.1OE+OI FH 21 L7398-02 4/22/2004 Ru-106
-1.00E+02 I.00E+02
- 4. 10E+02 FH 21 L7398-02 4/22/2004 Sb-124
-1.20E+01 3.20E+0 1.50E+02 FH 21 L7398-02 4/22/2004 Zn-65
-2.50E+01 3.20E+01 1.30E+02 FH 21 L7398-02 4/22/2004 Zr-95
-6.40E+01 2.50E+01 1.20E+02 FH 21 L8337-02 10/1/2004 Ag-l lOm 0.00E+00 1.50E+01 6.00E+OI FH 21 L8337-02 10/1/2004 Ba-140
-1.OOE+02 1.00E+02 4.70E+02 FH 21 L8337-02 10/1/2004 Be-7 1.30E+02 1.30E+02 4.60E+02 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 Ce-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 1.40E+01 1.50E+01 S.20E+01 FH 21 L8337-02 10/1/2004 Cs-134
-2.OOE+00 1.20E+01 4.90E+01 FH 21 L8337-02 10/1/2004 Cs-137 2.1OE+OI 1.50E+O1 4.90E+O1 FH 21 L8337-02 10/l/2004 Fe-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 K-40 3.56E+03 4.00E+02 5.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-41
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
- Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/kg)
STD.DEV.
(pCi/kg)
MDC (pCi/kg)
NUCLIDE FH FH FH FH FH FH FH FH 21 L8337-02 21 L8337-02 21 L8337-02 21 L8337-02 21 L8337-02 21 L8337-02 21 L8337-02 21 L8337-02 10/12004 10/1/2004 10/1/2004 10/1/2004 10/1/2004 10/1/2004 10/1/2004 10/1/2004 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95
-1.20E+02 1.20E+02 5.40E+02 1.70E+0O I.IOE+01 3.70E+0O
-2.30E+01 2.1OE+O1 9.30E+0I
-7.00E+00 1.60E+01 6.40E+0O
-2.60E+01 9.1OE+01 3.70E+02 3.1OE+01 3.10E+0 1..IOE+02
-3.70E+01 3.40E3+01 I.50E+02 5.00E+01 2.60E+01 8.00E+01
- 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 Annual Radiological Environmental Operating Report 2004 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 2.90E3+01 MS 33 L7204-01 3/31/2004 Ag-lOnm
-4.50E+00 2.60E+O0 1.IOE+OI MS 33 L7204-01 3/31/2004 Ba-140 8.00E-01 2.90E+O0 I.I0E+0I MS 33 L7204-01 3/3112004 Be-7 1.80E+01 1.40E+01 4.80E+0O MS 33 L7204-01 3/31/2004 Ce-141
-3.60E+00 3.30E+00 1.20E+0I MS 33 L7204-01 3/31/2004 Ce-144 1.20E+01 1.30E+01 4.20E+01 MS 33 L7204-01 3(31/2004 Co-57
-1.30E+00 1.50E+00 5.50E+00 MS 33 L7204-01 3/31/2004 Co-58 3.00E-0 I.90E+00 7.00E+O0 MS 33 L7204-01 3/31/2004 Co-60
-I.OOE+O0 2.00E+00 7.80E+00 MS 33 L7204-01 3/31(2004 Cs-134
-8.OOE-01 1.70E+00 6.80E+00 MS 33 L7204-01 3/31/2004 Cs-137 1.96E+01 3.10E+00 7.50E+00 MS 33 L7204-01 3/31/2004 Fe-59 1.63E+01 6.30E+00 1.90E+0O MS 33 L7204-01 3/31/2004 1-131
-4.1OE+00 4.40E+00 1.70E+01 MS 33 L7204-01 3/31/2004 K-40 1.89E+03 8.90E+01 7.70E+01 MS 33 L7204-01 3/31/2004 La-140 9.00E-01 3.30E+00 1.30E+0O MS 33 L7204-01 3/31/2004 Mn-54
-9.00E-01 I.90E+00 7.10E+00 MS 33 L7204-01 3/31/2004 Nb-95
-9.OOE-01 2.20E+00 8.20E+00 MS 33 L7204-01 3/31/2004 Ru-103
-2. 10E+00 1.60E+00 6.60E+0O MS 33 L7204-01 3/31/2004 Ru-106 2.50E+01 1.60E+0 5.IOE+01 MS 33 L7204-01 3/31/2004 Sb-124 2.30E+00 2.80E+O0 1.OOE+0O MS 33 L7204-01 3/31/2004 Zn-65
-1.06E+01 4.70E+00 2.OOE+OI MS 33 L7204-01 3/31/2004 Zr-95 6.00E-01 3.40E+00 1.30E+0O 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-llOm 2.SOE+00 2.20E+00 7.60E+O0 MS 45 L7204-02 3/31/2004 Ba-140
-4.OOE-01 2.80E+00 1.20E+0O MS 45 L7204-02 3/31/2004 Be-7 8.00E+00 1.40E+01 5.10E+O1 MS 45 L7204-02 3/31/2004 Ce-141
-2.70E+00 3.10E+00 l.lOE+01 MS 45 L7204-02 3/31/2004 Ce-144 4.00E+00 I.00E+0 3.60E+0 MS 45 L7204-02 3/31/2004 Co-57 O.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+00 6.60E+O0 MS 45 L7204-02 3/31/2004 Cs-134
-2.70E+00 1.70E+00 7.30E+00 MS 45 L7204-02 3/31/2004 Cs-137 1.39E+01 2.90E+00 7.80E+00 MS 45 L7204-02 3/31/2004 Fe-59 1.17E+O1 6.00E+00 1.90E+01 MS 45 L7204-02 3/31/2004 1-131 5.60E+00 3.SOE+00 1.20E+01 MS 45 L7204-02 3/31/2004 K-40 1.49E+03 8.30E+01 7.70E+01 MS 45 L7204-02 3/31/2004 La-140
-4.00E-01 3.20E+00 1.30E+0O MS 45 L7204-02 3/31/2004 Mn-54 9.00E-01 1.70E+00 6.20E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-43
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Mdnitoring Program Summary of 2004 Data SAMPLE TYPE MS MS MS MS MS MS END STATION LSN DATE 45 L7204-02 3/31/2004 45 L7204-02 3/31/2004 45 L7204-02 3/31/2004 45 L7204-02 3/31/2004 45 L7204-02 3/31/2004 45 L7204-02 3/31/2004 NUCLIDE Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 CONC (pCi/kg) 3.30E+00
-3.40E+00
-2.00E+00
-1.20E+00 8.30E+00 2.20E+00 STD.DEV.
(pCi/kg) 2.40E+00 2.00E+00 1.40E+01 3.70E+00 4.80E+00 3.20E+00 MDC (pCi/kg) 7.90E+00 8.10E+00 5.20E+01 1.60E+01 1.60E+01
- 1. IOE+OI
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-44
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC TYPE STATION LSN DATE NUCLIDE (pCi/kg)
STD.DEV.
(pCi/kg)
MDC (pCi/kg)
SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SE1 SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI SEI 11 L7263-01 11 L7263-01 1
L7263-01 I I L7263-01 11 L7263-01 11 L7263-01 11 L7263-01 11 L8342-01 11 L8342-01 11 L8342-01 II L8342-01 11 L8342-01 1
L8342-01 1
L8342-01 21 L7263-04 21 L7263-04 21 L7263-04 21 L7263-04 21 L7263-04 21 L7263-04 21 L7263-04 21 L8342-04 21 L8342-04 21 L8342-04 21 L8342-04 21 L8342-04 21 L8342-04 21 L8342-04 91 L7263-07 91 L7263-07 91 L7263-07 91 L7263-07 91 L7263-07 91 L7263-07 91 L7263-07 91 L8342-07 91 L8342-07 91 L8342-07 4/19/2004 4/ 9/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/21/2004 4/21/2004 4/21/2004 4/2112004 4/21/2004 4/21/2004 4/21/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 10/26/2004 10/26/2004 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 1.30E+03
-3.40E+02 3.40E+01
-!.00E+00
-1.80E+01 2.65E+02 2.19E+04 7.23E+02 3.80E+0O
-7.30E+00 2.OOE+00 1.70E+00 2.50E+01 1.07E+04 8.27E+02 3.00E+01
-3.60E+0O 1.40E+0O 5.20E+0O 2.25E+02 1.79E+04 5.69E+02 2.30E+02
-1.40E+0O 4.00E+00 I.00E+0O 2.33E+02 1.54E+04 2.22E+03 6.50E+02
- 4. 1OE+OI S.OOE+00 9.50E+01 8.36E+02 2.42E+04 2.18E+03
-7.00E+01
-5.00E+00 I. I OE+02 2.60E+02 2.90E+01 2.20E+01 2.40E+01 4.20E+01 1.00E+03 4.70E+0O 9.30E+0O 9.70E+00 l.OOE+0O 9.20E+00 1.30E+0O 4.20E+02 7.30E+01 1.60E+02 1.80E+0O 1.70E+0O l.90E+01 2.70E+0O 6.60E+02 4.90E+01
- l. IOE+02 1.30E+01 I.lOE+01 4.101E+01
- 2. 10E+01 4.80E+02 1.60E1+02 3.50E+02 4.00E+01 3.90E+01 4.20E+01 7.20E+01 1.20E+03 1.SOE+02 3.00E+02 3.30E+0O 4.00E+02 9.80E+02 I.00E+02 8.70E+0O 8.80E+0O l.lOE+02 I.00E+03 I.50E+02 3.20E+02 3.60E+01 3.80E+01 3.20E+0I 4.40E+0O 3.90E+02 2.40E+02 5.60E+02 7.10E+0I S.90E+01 6.00E+01 6.50E+01 4.50E+02 1.50E+02 3.60E+02 4.70E+01 4.OOE+01 1.40E+02 4.80E+0I 4.30E+02 5.40E+02 1.1 OE+03 1.40E+02 1.40E+02 1.30E+02 1.60E+02 1.40E+03 S.OOE+02
- 1. IOE+03 1.20E+02 10/26/2004 Co-58
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-45
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004
- Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE SEI SEI SEI SEI END STATION LSN DATE 91 L8342-07 91 L8342-07 91 L8342-07 91 L8342-07 10/26/2004 10/26/2004 10/26/2004 10/26/2004 NUCLIDE Co-60 Cs-134 Cs-137 K40 CONC (pCi/kg)
-1.20E+01
-8.00E+0I 1.36E+03 2.64E+04 STD.DEV.
(pCi/kg) 3.30E+01 3.50E+01 7.80E+0O 1.20E+03 MDC (pCi/kg) 1.30E+02 1.30E+02 1.40E+02 1.30E+03 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 II L7263-02 11 L7263-02 11 L7263-02 11 L7263-02 11 L7263-02 II L7263-02 11 L7263-02 11 L8342-02 II L8342-02 11 L8342-02 11 L8342-02 11 L8342-02 11 L8342-02 II L8342-02 21 L7263-05 21 L7263-05 21 L7263-05 21 L7263-05 21 L7263-05 21 L7263-05 21 L7263-05 21 L8342-05 21 L8342-05 21 L8342-05 21 L8342-05 21 L8342-05 21 L8342-05 21 L8342-05 91 L7263-08 91 L7263-08 91 L7263-08 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/21/2004 4/21/2004 4/21/2004 4/2l/2004 4/21/2004 4/21/2004 4/21/2004 10/26/2004 10/26n2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/21/2004 4/21/2004 4/21/2004 AcTh-228 Be-7 CO-5S Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Acib-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 CO-58 CO-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 CO-58 8.92E+02
-4.30E+02
-7.20E+01
-1.40E+01 2.OOE+00 I1.95E+02 1.811E+04 5.50E+02 6.001E+01
-8.OOE3-01
-1.30E+01 2.40E+01 1.90E+01 1.09E+04 5.32E+02
-1.90E+02
-5.00OE+00 1.70E+01
-2.50E+01 8.30E+01 I1.69E+04 4.21 E+02 I.50E+01
-1.58E+01 I1.27E+01
-3.60E+00 2.78E+02 1.33E+04 2.051E+03 4.40E+02
-5.90E+01I 9.00E+01 2.00E+02 2.80E+01 I1.901E+01 I1.601E+01 3.50E+01 9.OOE+02 5.I1OE+01I 1.00E+02 9.70E+00 1.301E+01 1.00E+01 1.20E+01 4.90E+02 7.70E+01 I1.60E+02 I1.901E+01 1.80E+01 1.50E+01 2.80E+01 7.80E+02 2.001E+01 4.20E+01 5.50E+00 5.40E+00 4.80E+00 I. IOE+01 2.30E1e-02 1.60E+02 3.40E+02 3.40E+0 I 3.50E+02 7.90E+02 1.20E+02 8.00E+01 5.90E+01 9.20E3+01 6.90E+02 1.80E-+02 3.50E+02 3.70E+01 5.10E+01
- 3. 1OE+OI 4.00E+01 3.80E+02 3.OOE+02 6.30E+02 7.30E+01 6.30E+0O 5.90E+01 8.40E+01 6.20E+02 7.20E+0I 1.40E+02 2.00E+0I 1.70E+01 1.70E+01 2.OOE+01 1.70E+02 5.40E+02 1.IOE+03 1.30E+02
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC LSN DATE NUCLIDE (pCi/kg)
SAMPLE TYPE STATION STD.DEV.
(pCi/kg)
MDC (pCi/kg)
SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE2 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 SE3 91 L7263-08 4/21/2004 Co-60 91 L7263-08 4/21/2004 Cs-134 91 L7263-08 91 L7263-08 91 L8342-08 91 L8342-08 91 L8342-08 91 L8342-08 91 L8342-08 91 L8342-08 91 L8342-08 11 L7263-03 11 L7263-03 11 L7263-03 11 L7263-03 II L7263-03 11 L7263-03 II L7263-03 11 L8342-03 11 L8342-03 11 L8342-03 11 L8342-03 11 L8342-03 11 L8342-03 11 L8342-03 21 L7263-06 21 L7263-06 21 L7263-06 21 L7263-06 21 L7263-06 21 L7263-06 21 L7263-06 21 L8342-06 21 L8342-06 4/21/2004 4/21/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 4/19/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 10/26/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 4/21/2004 10/26/2004 10/26/2004 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 AcTh-228 Be-7 Co-58 Co-60 Cs-134 Cs-137 K40 AcTh-228 Be-7
-5.40E+01 4.00E+01 1.03E+03 2.48E+04 2.03E+03
-2.70E+02
- 2. 1OE+OI
-1.40E+01
-1.60E+01
- 1. IOE+03 2.33E+04 9.20E+02 I.OOE+02
-1.90E+01 9.00E+00 2.SOE+01 2.58E+02 1.74E+04 S.67E+02
-1.50E+02 1.50E+01
-2.00E+00
-2.31 E+OI
-1.60E+01 9.67E+03 8.57E+02
-4. 10E+02 4.00E+00 0.OOE+00
-1.90E+01 6.30E+01 1.60E+04 3.72E+02 4.60E+0I 2.80E+01 1.20E+02 3.80E+01 1.30E+02 7.40E+01 I.50E+02 1.20E+03 1.30E+03 1.20E+02 3.50E+02 3.00E+02 I.IOE+03 2.80E+01 9.70E+01 2.80E+01 1.IOE+02 2.80E+01 I.00E+02 6.40E+01 1.20E+02 I.00E+03 1.30E+03 1.00E+02 2.10E+02 2.30E+01 2.1OE+OI 2.50E+0O 3.90E+01
- 9. 1OE+02 5.30E+0I 1.1 OE+02 1.20E+01 1.20E+01 9.80E+00 1.20E+01 4.60E+02 8.60E+0O 1.80E+02 2.00E+01 1.90E+01 1.20E+01 3.1OE+OI 8.60E+02 4.80E+01 9.50E+01 3.OOE+02 7.30E+02
- 9. 1O1+01I 7.70E+01 8.401E+01 9.601E+01 8.40E+02 I1.60E+02 4.00E3+02 4.IOE1+01I 4.601E+01 4.001E+01 4.70E+01 4.50E3+02 3.001E+02 7.401E+02 7.50E+01 7.501E+01 5.201E+01 9.90E+01 7.701E+02 1.90E+02 3.30E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C47
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 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 21 L8342-06 10/26/2004 Co-58
-6.OOE+00 1.20E+01 4.40E+01 SE3 21 L8342-06 10/26/2004 Co-60 2.60E+01 I.OOE+01 3.OOE+01 SE3 21 L8342-06 10/2612004 Cs-134
-8.60E+00 9.60E+00 3.60E+01 SE3 21 L8342-06 10/26/2004 Cs-137 1.26E+02 I.90E+01 4.90E+01 SE3 21 L8342-06 10/26/2004 K40 1.35E+04 5.10E+02 4.40E+02 SE3 91 L7263-09 4/21/2004 AcTh-228 1.65E+03 1.60E+02 4.20E+02 SE3 91 L7263-09 4/21/2004 Bc-7 2.60E+02 3.60E+02 1.30E+03 SE3 91 L7263-09 4/2112004 Co-58 6.00E+00 3.70E+01 1.40E+02 SE3 91 L7263-09 4/21/2004 Co-60 O.OOE+00 3.30E+01 1.30E+02 SE3 91 L7263-09 4/21/2004 Cs-134 1.30E+01 2.90E+01 I.00E+02 SE3 91 L7263-09 4121/2004 Cs-137 9.80E+02 8.00E+01 1.40E+02 SE3 91 L7263-09 4/21/2004 K-40 2.47E+04 1.40E+03 1.501E+03 SE3 91 L8342-09 10/26/2004 Ac1h-228 1.72E+03 1.IOE+02 4.00E+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 I.00E+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
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-48
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCi/kg)
STD.DEV.
(pCi/kg)
MDC (pCi/kg)
TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF II L8057-01 11 L8057-01 II L8057-01 II L8057-01 II L8057-01 11 L8057-01 II L8057-01 11 L8057-01 II L8057-01 11 L8057-01 11 L8057-01 II L8057-01 11 L8057-01 II L8057-01 11 L8057-01 11 L8057-01 II L8057-01 11 L8057-01 II L8057-01 II L8057-01 11 L8057-01 11 L8057-01 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 13 L8057-02 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/1412004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/1412004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 9/14/2004 AcTh-228 Ag-I lOm Ba-140 Be-7 Ce-141 Cc-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Ru-103 Ru-106 Sb-124 Zn-65 Zr-95 AcTh-228 Ag-i lOm Ba-140 Be-7 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59
-2.40E+01 O.OOE+00
-9.OOE+O0
-7.40E+01
-3.00E+00 7.00E+00 3.80E+00
-4.80E+00
-1.28E+0O
-1.48E+0O
-1.77E+01 L.40E+01 2.40E+0O 9.80E+02
-1.00E+01
-3.70E+00 7.90E+00 7.20E+00 1.62E+02 5.00E+00
-4.OOE+01 2.OOE+OO l.00E+01
-8.00E+00
-3.00E+00 1.43E+02
-2.33E+0O 1.70E+01
-2.30E+00 4.60E+00 2.60E+0O
-9. 1OE+00
-2.60E1+O0
-I.00E+0I
-1.50E+0O 5.52E+03 3.10E+01 1.20E+02
- 1. IOE+OI 4.00E+01 l.lOE+0O 4.80E+01 6.20E+01 2.40E+02 I.00E+0 3.70E+01 3.80E+01 1.30E+02 4.90E+00 1.70E+0O 6.50E+00 2.60E+01 8.80E1+00 3.70E+0O 7.80E+00 3.30E+01 8.00E+00 3.30E+01 2.00E+01 7.30E+I0 1.30E+01 4.10E+01 1.60E+02 3.40E+02 1.30E+01 5.50E+01 7.70E+00 3.00E+01 8.80E+00 3.10E+0O 7.40E+00 2.50E+01 6.40E+01 I.90E+02 1.70E+01 6.80E+0O 2.20E+01 9.1OE+OI 1.40E+01 5.20E+01 3.1 OE+O I I.IOE+02 I.OOE+0I 4.10E+01 l.OOE+0 4.50E+0 7.90E+01 2.60E+02
- 9. IOE+O0 3.60E+0O 3.30E+01 1.IOE+02 3.80E+00 1.40E+0I
- 8. 10E+00 2.90E+01 1.20E+01 3.50E+0O 9.50E+00 3.80E+0O 7.90E+00 3.00E+01 3.1OE+01 1.20E+02 I. IOE+OI 4.30E+0I 3.70E+02 5.40E+02 13 L8057-02 9/14/2004 1-131 13 L8057-02 9/14/2004 K-40 13 L8057-02 9/14/2004 La-140 13 L8057-02 9/14/2004 Mn-54
-4.00E+00 1.20E+01 5.20E+0I 1.08E+01 7.40E+00 2.50E+01
- 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 Annual Radiological Environmental Operating Report 2004 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 13 L8057-02 9/14/2004 Nb-95
-3.BOE+01 1.IOE+OI 4.90E+0I TF 13 L8057-02 9/14/2004 Ru-103 3.40E+00 8.20E+00 2.90E+01 TF 13 L8057-02 9/14/2004 Ru-106 I.IOE+01 6.30E+01 2.30E+02 TF 13 L8057-02 9/14/2004 Sb-124 O.OOE+O0 1.80E+01 7.70E+OI TF 13 L8057-02 9/14/2004 Zn-65 1.20E+01 4.60E+01 1.60E+02 TF 13 L8057-02 9/14/2004 Zr-95
-2.40E+01 2.OOE+01 7.60E+0I TF 21 L8057-03 9/14/2004 Aclh-22S
-3.90E+01 3.OOE+01 1.20E+02 TF 21 L8057-03 9/14/2004 Ag-blOm 7.60E+00 9.30E+00 3.30E+01 TF 21 L8057-03 9/14/2004 Ba-140
-2.23E+01 9.50E+00 5.00E+01 TF 21 L8057-03 9/14/2004 Bc-7
-4.20E+01 6.00E+01 2.30E+02 TF 21 L8057-03 9/14/2004 Ce-141 1.90E+00 8.80E+00 3.10E+01 TF 21 L8057-03 9/14/2004 Ce-144 2.70E+01 3.40E+01 1.20E+02 TF 21 L8057-03 9/14/2004 Co-57
-5.90E+00 3.80E+00 1.50E+01 TF 21 L8057-03 9/14/2004 Co-58
-6.30E+00 7.00E+00 2.90E+01 TF 21 L8057-03 9/14/2004 Co-60 1.00E+01 9.50E+00 3.30E+O1 TF 21 L8057-03 9/14/2004 Cs-134
-2.70E+00 7.40E+00 2.90E+01 TF 21 L8057-03 9/14/2004 Cs-137
-8.80E+00 7.90E+00 3.10E+0O TF 21 L8057-03 9/14/2004 Fe-59 1.00E+00 1.90E+01 7.50E+01 TF 21 L8057-03 9/14/2004 1-131 3.00E+00 1.IOE+OI 4.00E+O1 TF 21 L8057-03 9/14/2004 K-40 1.89E+03 2.20E+02 4.30E+02 TF 21 L8057-03 9/14/2004 La-140
-2.60E+01 1.IOE+01 5.80E+01 TF 21 L8057-03 9/14/2004 Mn-54
-1.21E+01 6.80E+00 2.90E+01 TF 21 L8057-03 9/14/2004 Nb-95
-2.00E-01 8.60E+00 3.20E+01 TF 21 L8057-03 9/14/2004 Ru-103 2.10E+00 7.00E+00 2.50E+OI TF 21 L8057-03 9/14/2004 Ru-106 1.20E+02 7.00E+01 2.30E+02 TF 21 L8057-03 9/14/2004 Sb-124 5.OOE+00 2.1OE+01 8.00E+OI TF 21 L8057-03 9/14/2004 Zn-65
-3.00E+01 I.90E+01 7.90E+01 TF 21 L8057-03 9/14/2004 Zr-95 0.00E+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-50
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCitL)
SAMPLE TYPE STD.DEV.
(pCi/L)
MDC (pCi/L)
WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG I l L6910-05 I I L6910-05 It L6910-05 I I L6910-05 I I L6910-05 I I L6910-05 1 I L6910-05 L6910-05 L6910-05 L6910-05 I I L6910-05 I I L6910-05 I I L6992-04 1 1 L6992-04 1 1 L6992-04 I
[ L6992-04 L6992-04 1
[ L6992-04 I I L6992-04 I I
[L6992-04 I I
[L6992-04 t I L6992-04 I I
[L6992-04 L6992-04 L7175-04 L7175-04 I
[ L7175-04 I I L7175-04 I I
[L7175-04 I I
[L7175-04 t I L7175-04 L7175-04 L7175-04 L7175-04 L7175-04 I
I L7175-04 11 L7341-04 I I
[L7341-04 1/30/2004 1/30/2004 1130/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 4/26/2004 4/26/2004 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 1.90E+00
-3.1 OE-01 9.20E-01 7.70E-01
- 1.
14E+00
-7.90E+00 3.68E+00
- 2.
14E+02
-6.40E+00 6.OOE-01
-3.OOE-01 I1.40E+00 3.30E+00 2.OOE+00
-3.OOE-01 I1.50E+00
-7.OOE-0 I
-6.20E+00 3.44E+00 7.90E+01
-3.OOE4-00
-1. IOE+00 1.04E+01 2.20E+00
-5.20E+00
-9.OOE-01
-1.20E+00
-1.60E+00
-2.30E+00 2.OOE-0 I 2.80E+00 0.00E+00 2.80E+00
-6.OOE-01
-2. I OE+00 3.70E+00
-6. I OE+00 I.00E+00 2.40E+00 9.60E-01 s.10E-01 9.40E-01 9.90E-01 2.80E+00 9.90E-01 8.70E+01 3.soE+00 t.OOE+00
- 3. 1OE+00 1.70E+00 6.70E+00 1.30E+00 1.40E+00 1.40E+00 L.60E+00
- 4. 1OE+00 9.70E-01 9.10E+01 1.30E+01 1.SOE+00 6.30E+00
- 3. 10E+00 4.50E+00 2.40E+00 2.40E+00 2.OOE+00 1.80E+00 6.70E+00 1.OOE+00
- 1. IOE+02 4.80E+00 1.90E+00 5.1OE+00 3.70E+00 4.80E+00 2.00E+00 8.50E+00 3.70E-I00 2.80E+00 3.30E+00 3.40E+00 I1.30E+01 2.80E+00 2.70E+02 1.50E+01 3.7013+00
- 1. IOE+01 5.90E+00 2.50E+01 4.40E+00 5.90E+00 4.80E+00 6.OOE+00 2.00E+01 2.80E+00 2.90E+02 4.70E+01 5.90E+00 2.101E+01I
- 1.
I OE+0lI 2.10E+01 9.30E+00 1.OOE3+01 8.30E+00 7.80E+00 2.60E+01
- 3. 1 OE+00 3.50E+02 I1.70E+01 7.50E+00 2.OOE+01 I1.30E+01 2.30E+01 7.60E+00
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCUL)
SAMPLE TYPE STD.DEV.
(pCiIL)
MDC (pCi/L)
WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WiG L7341-04 L7341-04 L7341-04 11 L7341-04 ll L7341-04 L7341-04 L7341-04 L7341-04 L7341-04 L7341-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7471-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 L7611-04 II L7611-04 11 L7611-04 L7643-04 L7643-04 L7643-04 11 L7643-04 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26(2004 4/26/2004 4/26/2004 4/26/2004 4126/2004 4/26/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23(2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 3.OOE-01
-6.00E-O0
-1.20E+O0 4.80E+O0 1.52E+O0
-7.00E+01
-1.90E+00 2.30E+O0
-7.20E+O0 1.60E+O0
-3.40E+O0
-2.20E+O0 5.OOE-01
-8.00E-01
-3.00E-01 1.02E+01 1.52E+O0
-3.00E+01 2.1OE+O0 2.00E+O0 4.00E+00
-1.I OE+O0 3.30E+00 9.00E-01 1.30E+O0 6.00E-OI
-3.00E-0O
- 4. 10E+O0 2.36E+00 2.68E+02 2.00E+O0
-3.00E-0O O.OOE+O0 6.80E+00
-2.70E+O0
-6.00E-OI 3.20E+00
-2.00E+00 2.20E+00 1.70E+O0
- 2. 1OE+O0 6.60E+O0 9.40E-01 1.lIOE+02
- 5.
10E+00 1.90E+O0 3.80E+O0 3.10E+00 5.80E+O0 1.90E+00 2.10E+00 1.501E+O0 2.40E+O0 5.60E+00 9.20E-0O 1.30E+02 6.60E+O0 1.90E+O0 4.80E+O0 3.20E+O0 3.70E+00 1.90E+O0 1.80E+O0 1.80E+00 l.50E+O0 6.00E+00 9.80E-01 9.90E+OI 4.20E+O0 1.80E+O0 2.40E+O0 3.50E+o0 2.90E+O0 l.SOE+O0 2.20E+00 2.20E+00 8.80E+00 7.30E+O0 8.70E+00 2.50E+0O 3.10E+O0 3.30E+02 2.00E+OI 6.60E+O0 1.90E+I0 1.20E+0I 2.50E+OI 8.80E+O0 8.60E+O0 7.OOE+0O 9.50E+O0 1.60E+OI 3.00E+00 4.00E+02 2.40E+0I 6.80E+00 2.10E+OI 1.40E+0O 1.30E+OI 6.80E+00 6.60E+O0 6.70E+O0 5.80E+00 2.20E+OI 3.00E+00 3.00E+02 1.50E+0O 6.80E+O0 l.OOE+OI l.l1OE+01 1.20E+OI 6.00E+00 7.30E+O0 8.80E+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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (Pci/L)
STD.DEV.
MDC (pCi/L)
(pCi/L)
NUCLIDE WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG 11 L7643-04 II L7643-04 11 L7643-04 II L7643-04 II L7643-04 II L7643-04 II L7643-04 II L7643-04 II L7840-04 II L7840-04 II L7840-04 II L7840-04 II L7840-04 II L7840-04 II L7840-04 11 L7840-04 11 L7840-04 II L7840-04 11 L7840-04 11 L7840-04 11 L7980-04 11 L7980-04 11 L7980-04 II L7980-04 II L7980-04 11 L7980-04 11 L7980-04 11 L7980-04 11 L7980-04 II L7980-04 II L7980-04 II L7980-04 II L812 I-01 I
L8 12 1-Ol Ii L812 I-01 II L812 I-OI II L812 I-01 II L812 I-01 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59
-I1.70E+00 1.60E3+01 2.1 IE+O0 3.OOE+01
-3.00E-01 2.40E+00
-6.90E+00 1.60E+00
-1.30E+00 1.001E-01 1.80E+O0 6.001E-01
-1.30E+00 I1.25E+01 3.20E3+00
-2.50E+02 I1.40E+O0
-3.60E+00
-2.30E+00
-3.60E+00
-2.80E-01
-1.64E+00 9.20E-01 2.401E-01
-3.90E-01
-1.30E+00 4.90E3+00
-3.0013+01
-1.00E-01
-5.90E-01 4.OOE+00
-4.40E-01 I1.30E+00
-2.20E+O0
-1.80E3+00 1.40E+00 0.OOE3+00
-2.60E+00 2.10E+O0 5.50E+00 9.90E-0 I l.00E+02 3.50E+00 1.701E+00 4.401E+00 3.203+O00 3.8013+00 1.80E+00 2.50E+00 1.90E3+00 I1.70E+O0 6.40E+00 l.00E+00 I1.30E+02 3.20E+00
- 2. IOE+00 3.301E+O0 3.30E+O00 9.001E-01 5.10E-01 4.60E-01 5.10E-01 7.50E-01 1.30E+00
- l. IOE+00 I. I OE+02 I1.401E+00 4.4013-01 2.30E+00 8.30E-01 4.30E+O0
- 2. 1 OE+O0 I1.90E+O0 2.30E+00 1.80E+00 5.OOE+00 8.00E+00 1.50E+01 3.20E+00 3.20E+02 1.30E+01 5.60E+00 1.80E+01 1.10E+01 1.70E+01
- 7. 1OE+00 9.00E+00 7.30E+00 7.20E+00 1.90E+01 3.1OE+00 3.90E+02 1.20E+01 9.20E+00 1.50E+01 1.50E+01
- 3. 1OE+00 1.90E+00 1.50E+00 1.70E+00 2.50E+00 4.80E+00 2.90E+00 3.30E+02 4.60E+00 1.60E+00 7.40E+00 2.90E+00 1.70E+01 8.90E+00 8.80E+00 8.30E1+00
- 7. 10E+00 2.30E+01 I Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-53
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCitL)
STD.DEV.
(pCi/L)
MDC (pCitL)
WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG I1
[L8121-01 L8121-01 1 L8121-01 11 L8121-01 II L121-01 11 L8121-01 I I L8352-04 I I L8352-04 I I L8352-04 L8352-04 L8352-04 L8352-04 L8352-04 L8352-04 L8352-04 L8352-04 18352-04 1 8352-04 18484-04 1,8484-04 L8484-04 L8484-04 L8484-04 L8484-04 L8484-04 L8484-04 1484-04 18484-04 18484-04 L1484-04 L8663-04 L8663-04 L8663-04 L8663-04 L8663-04 L8663-04 11
[L8663-04 L8663-04 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 1 1/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-S5 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 3.10E+00
-3.00E+01 4.00E-01
-4.00E-01
-4.60E+00
-3.00E-01
-1.30E+00
-2.50E+00 2.90E+00 1.80E+00
-2.00E+00 4.00E-01
- 3. IOE+00 4.00E+01
-8.00E-01
-3.40E+00
- 1. IOE+01 3.70E+00
-1. IOE+00
-2.40E+00 1.80E+00
-5.OOE-01
-2.40E+00 0.00E+00 4.60E+00
-3.00E+01 3.00E-01
-1.40E+00
-1.17E+01 2.50E+00 8.40E+00
-2.50E+00
-1.003E-0 L.90E+00 2.00E+00
-3.30E+00 5.90E+00
-2.70E+0 I
- 1. I1E+00 1.00E+02 4.40E+00 2.30E+00 4.80E+00 3.70E+00 2.30E+00
.50E+00 1.70E+00 1.60E+00
.50E+00 3.60E+00 1.00E+00 I.00E+02 3.10E+00 1.60E+00 7.90E+00 3.30E+00 4.40E+00 3.00E+00 3.60E+00 2.20E+00 2.20E+00 8.50E+00 1.20E+00
.00E+02 4.90E+00 1.30E+00 6.50E+00 3.80E+00 3.30E+00 1.40E+00 1.70E+00 1.50E+00 1.90E+00 4.60E+00
. I OE+00 9.90E+01 3.20E+00 3.30E+02 I.60E+01
- 9. IOE+00
- 2. IOE+OI 1.50E+01
- 9. IOE+00 6.10E+00 5.50E+00 5.30E+00 5.80E+00 1.40E+01
- 3. 1OE+00 3.30E+02 1.I10E+01 6.40E+00 2.60E+01 1.I0E+0I 2.00E+01 1.20E+01 1.30E+01
- 9. IOE+00 9.50E+00 3.40E+01 3.30E+00 3.30E+02 1.90E+01 6.80E+00 2.90E+01 1.40E+01
- 9. IOE+00 6.00E+00 6.soE+00 4.90E+00 6.40E+00 1.90E+01 2.70E+00 3.20E+02 a
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
NUCLIDE WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG 1 I L8663-04 I
L8663-04 1I
[8663-04 I I L8663-04 12 L6910-06 12
[,6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6910-06 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L6992-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-05 12 L7175-OS 1/3/2005 1n3o2005 1/3n2005 1/3n2005 1/3012004 1/30/2004 1/30n2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/3012004 1/30/2004 1/30/2004 2125/2004 2/25n2004 2125/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/2512004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3n29/2004 3/29/2004 3/29/2004 3129/2004 1-131 Mn-54 Zn-65 Zr-95 Ba-140 CO-s8 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Z,-95 Ba-140 CO-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54
-1.20E+00
-2.20E+00
-2.10E+00 1.90E+00
-2.
1OE+00 1.00E-01
-1.80E+00
-9.OOE-01
-2.101E+00 4.70E+00 5.OOE+00 1.46E+02
-8.OOE-01
-7.00E-01 1.40E+00
-1.60E+00 1.74E+01
-2.60E+00
-4.00E-0I 1.50E+00
-1.20E+00
-4.soE+00 4.30E+00 2.24E+02
-8.00E+00
-8.00E-0O
-I.06E+01
-2.
1OE+00 1.30E+00 1.30E+00
-3.40E+00
-1.90E+00 4.OOE-0I 7.40E+00 5.00E+00 O.OOE+00
-1.22E+01 1.20E+00
- 4. 1OE+00 1.40E+00 7.10E+00 2.60E+00 4.10E+00 1.70E+00 1.90E+00 1.60E+00 1.40E+00 4.70E+00 1.20E+00 8.70E+01 4.70E+00 1.30E+00 3.00E+00 2.80E+00 7.50E+00 1.80E+00 1.90E+00 1.90E+00 1.40E+00 6.00E+00 1.20E+00 9.20E+01 1.20E+01 1.90E+00 4.40E+00 3.60E+00 4.20E+00 1.70E+00 2.10E+00 1.90E+00 1.40E+00 S.50E+00 1.20E+00 1.l OE+02 4.70E+00 1.60E+00 1.50E+01 6.00E+00 2.SOE+01 9.30E+00 1.70E+01 6.30E+O0 7.80E+00 6.40E+00 6.OOE+00 1.60E+0O 3.30E+00 2.70E+02 1.80E+01 5.20E+00
- 1. IOE+0I 1.l OE+0I 2.10E+01 7.70E+00 7.60E+00 6.70E+00 5.70E+00 2.60E+01 3.30E+00 2.90E+02 4.70E+01 7.40E+00 2.00E+01 1.40E+01 1.70E+01 6.00E+00 9.80E+00 8.20E+00 5.40E+00 1.80E+01 3.20E+00 3.50E+02 2.10E+0I 5.90E+00
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCUL)
NUCLIDE WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG 12 L7175-05 12 L7175-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-05 12 L7341-0s 12 L7341-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-0s 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7471-05 12 L7611-05 12 L7611-05 12 L761l-05 12 L7611-05 12 L7611-05 12 L7611-05 12 L7611-OS 12 L7611-05 3/29/2004 3/29/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 412612004 4/26/2004 4(26/2004 4/26/2004 4/26/2004 4/26/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6n23/2004 6/23/2004 6/23/2004 6/23n2004 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fc-59 GROSS BETA H-3 3.00E+00 6.00E-01
-1.40E+00 3.00E-01
-3.10E+00 2.60E+00 2.30E+00
-5.OOE+O0 4.20E+00
-1.OOE+01
-8.60E+00 2.40E+00 1.60E+O0
- 3. 10E+O0 3.40E+O0
-2. 1 OE+O0 3.30E+O0
-6.00E-01
-8.OOE-0l 4.90E+00 6.60E+00 2.60E+02
-9.70E+00
-3.00E-O0
-1.34E+O0 O.OOE+O0
-1.40E+00 2.20E+O0 L.90E+O0
-4.00E-OI 1.20E+00 5.30E+O0 6.00E+O0 1.48E+02 3.00E+00 2.40E+0O 4.20E+00 1.90E+00 2.20E+00 1.70E+00 2.00E+O0 5.00E+00 1.IOE+0O 1.lOE+02 6.70E+O0 1.60E+00 4.20E+00 3.20E+O0 4.80E+00 2.OOE+00 2.70E+00 2.00E+00 1.60E+0O 4.90E+0O 1.30E+00 1.30E+02 5.30E+00 2.00E+00 5.40E+00 3.00E+00 3.00E+0O 1.70E+OO 2.10E+00 1.90E+00 1.80E+00 7.50E+0O 1.20E+00 9.80E+01 l.lOE+O1 9.80E+O0 2.00E+OI 7.90E+O0 1.20E+O1 5.40E+O0 7.00E+O0 2.70E+O1 3.20E+O0 3.30E+02 2.80E+O1 4.90E+O0 1.70E+01 1.20E+01 I.80E+OI 8.SOE+O0 9.10E+O0 8.00E+O0 6.60E+O0 1.80E+O1 3.40E+O0 4.00E+02 2.20E+01 7.80E+o0 2.40E+0l 1.20E+0O 1.50E+OI 5.70E+O0 7.70E+00 7.70E+00 6.40E+O0 2.70E+0O 3.1OE+O0 3.00E+02 12 L7611-05 6/23/2004 1-131 12 L7611-05 6/23/2004 Mn-54 12 L7611-05 6/23(2004 Zn-65 12 L7611-05 6/23/2004 Zr-95
-2.70E+00 5.60E+00
- 2. 1OE+OI
-1.30E+00 1.70E+00 7.20E+O0
-7.50E+00 3.90E+OO l.90E+OI
-6.00E-01 3.20E+00 1.30E+OI
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7643-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7840-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 12 L7980-05 6/28/2004 6/28/2004 6/28/2004 6n8no2004 6/2n82004 6n8no2004 6/8/o2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 87/2004 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54
-3.IOE01+00 2.IOE01+00
-1.20E+00 1.50E+00
-3.OOE-01 1.30E3+00 1.80E+00 1.30E+00
-1.OOE+00 1.20E+00
-6.60E+00 4.20E+00 3.20E+00 I. I OE+00 1.20E+02 1.00E3+02 I1.20E3+00 2.401E+00 9.001E-01 I. IOE1+00 7.OOE-01 3.101E-i00
-3.I1OE+00 2.80E+00 8.00E-01 3.OOE+00
-2.1I0E+00 I1.50E+00 2.40E+00 I1.50E+00 2.OOE+00 1.90E+O0
-1.50E+00 1.60E+00
-4.60E+00 4.80E+00
- 5. 1OE+00 1.20E1e-00 4.001E+01 1.30E3+02 9.OOE-01 3.90E3+00 3.20E+-00 1.60E+00
- 2. 10E+00 2.80E+00 1.701E+00 2.90E+00 4.50E+00 3.OOE-i00
-1.90E+00 2.001E+00 1.901E+00 2.20E+00 3.OOE-01 1.50E3+00
-1.IOE+00 1.90E+00 2.30E+00 5.I1OE+00
- 6. 10E+00 1.30E+00 4.20E+02 1.I010E+02 2.40E+00 2.80E-i00
-2.60E+00 I1.40E3+00 2.201E+00 3.IOE01+00
-7.80E+00 2.90E-I00 0.001E+00 2.80E+00
-7.OOE-01 1.70E+00 9.80E+00 6.10OE+00 5.401E+00 4.20E3+00
- 5. IOE1+00 I1.90E3+01 3.30E3+00 3.201E+02 8.601E+00
- 4. 1O01+00 I1.201E+01 IOE01+01 I1.201E+01 6.301E+00 4.70E3+00 6.401E+00 6.30E+00 2.OOE+01 3.301E+00 3.901E+02 I1.40E3+01 5.00OE+00 l.00E3+01
- 1. IOE1+01I 9.70E-I00 8.30E3+00 8.OOE3+00 6.001E+00 7.80E-.-00 2.00E3+0l 3.40E3+00 3.30E+02 9.801E+00 7.001E+00 1.20E3+01 I.SOE+01 I1.20E+01 7.OOE+00 12 L7980-05 8/27/2004 Zn-65 12 L7980-05 8/27/2004 Zr-95 12 L8121-05 9/22/2004 Ba-140 12 L8121-05 9/22/2004 Co-58
- Radidactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-57
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG WG 12 LS121-05 12 Ls121-05 12 Ls121-05 12 Ls121-05 12 Ls121-05 12 Ls121-05 12 L8121-05 12 Ls121-05 12 L8121-05 12 L8121-05 12 L8352-05 1 2 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8352-05 12 L8484-05 1 2 L8484-05 1 2 L8484-05 1 2 L8484-05 12 L8484-05 12 L8484-0s 12 L8484-05 12 L8484-05 12 18484-05 12 L8484-05 12 L8484-05 12 L8484-05 12 L8663-05 12 L8663-05 12 L8663-05 1 2 L8663-05 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 1/3/2005 1/3/2005 1/3/2005 1/3/2005 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-1 34 I1.301E+00
-2.OOE+00 3.201E+00
-5.50E+00 9.OOE+00 3.OOE+02 I1.41E+01 I1.30E+00
-6.90E+00
-1.501E+00 3.00E+00 2.00E3-01 3.20E+00
-1.30E+O0
-8.OOE-01
-3. I OE+00 7.801E+00 5.90E+02
-1.40E+00 2.OOE+00
-4.80E+00 0.OOE3+00
-1.60E+00
-1l.OOE-01I
-2.70E+00
-1.00E-01 2.50E+00
-8.001E-01 6.90E+O0 4.30E+02
-1. IOE+01 7.OOE-01
-1.08E+01 2.OOE+O0
-1.00E+00 6.001E-01 1.OOE3-01 2.OOE+00 1.801E+00 1.70E+00 1.40E+00 4.40E+00 1.40E+O0 1.IOE+02 4.80E+00 1.801E+00 3.30E+00 2.40E+00 1.50E+00 1.I OE+O0 1.40E+00
.IOE+O0
- 1. IOE+00
- 3. 10E+00 1.30E+00 1.OE+02 2.20E+O0 1.20E+00 2.70E+00 2.10E+00 4.30E+00 1.90E+00 2.90E+00 1.90E+00 2.30E+00 5.50E+00 1.30E+00 1.lOE+02 5.20E+00 1.30E+00 3.80E+00 3.90E+00 2.50E+00 1.20E+00 1.50E+00 1.70E+00 6.50E+00 7.50E+00 3.80E+00
- 2. 1 OE+01I 3.30E+00 3.30E+02 I1.40E3+01 6.5013+00 1.60E3+01 1.IOE3+01 4.501E+00 4.OOE+00 4.20E3+00 4.70E+00 4.50E+00 I1.30E+01 3.20E+00 3.30E+02 8.30E+00 3.80E3+00 I. IOE+01 8.OOE3+00 2.OOE+01 8.00E+O00 1.30E+01 7.7013+00 7.80E+00 2.401E+01 3.30E+00 3.301E+02 2.30E+01 5.301E+00 2.10OE+01 1.50E+01 l.IOE3+01 4.60E+00
- 6. 101E+00 5.60E+00
- 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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (KUiL)
STD.DEV.
(pCi/L)
MDC (Pci/L)
WG 12 WG 12 WG 12 WG 12 WG 12 WG 12 WG 12 WG 12 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 WG SP. DUPL. 32 L8663-05 L8663-05 L8663-05 L8663-05 L8663-05 L8663-05 L8663-05 L8663-05 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 L7980-06 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1n3o2005 1/3/2005 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 87/2004 8/27(2004 8/27/2004 8/27/2004 8/27/2004 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fc-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95
-1.60E+00 8.60E+O0 5.OOE+O0 3.20E+02 6.0013-01
-2.OOE-01 4.20E3+00
-2.30E+00
-1.20E+O0
-5.001E-01 0.OOE3+00 8.OOE-01 0.00E+00
-5.20E+00 7.201E+00 2.001E+02 7.001E-01
-I1.
I OE+00
-5.80E+O0
-8.001E-01 1.30E+00 4.80E+00 1.20E+00 I.OOE+02
- 3. 1OE+00 1.40E+00 3.00E+00 2.90E+00 2.70E+00 2.00E+00
- 2. IOE+00 2.40E+00
- 2. 1OE+00 5.50E+00 1.40E+00
- 1. IOE+02 2.70E+00 I.90E+00 5.OOE+00 3.50E+00 5.40E+00 I1.50E+01 3.20E+00 3.20E+02
- 1. IOE+01 5.30E+00 9.90E+00 I1.20E+01 1.30E+01 8.501E+00 9.OOE+00 9.30E+00 8.30E+00 2.701E+01 3.80E+00 3.4013+02 I
.OOE+01 8.30E+00 2.30E1i-O1 1.501E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-59
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
NUCLIDE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 11 L6910-01 11 L6910-01 11 L6910-01 11 L6910-01 II L6910-01 11 L6910-01 11 L6910-01 11 L6910-01 11 L6910-01 11 L6910-01 11 L6910-01 II L6910-01 11 L6992-01 II L6992-01 II L6992-01 II L6992-01 II L6992-01 11 L6992-01 11 L6992-01 II L6992-01 11 L6992-01 11 L6992-01 II L6992-01 11 L6992-01 II L7175-01 11 L7175-01 11 L7175-01 II L7175-01 11 L7175-01 11 L7175-01 II L7175-01 11 L7175-01 11 L7175-01 11 L7175-01 11,7175-01 1, 7175-01 II L7297-01 II L7341 -01 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 4/26/2004 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 CO-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140
-3.50E+00
-1.60E+00 2.30E+00 5.OOE-0l O.OOE+00
- 2. IOE+00 8.90E-01
-4.00E+01
- 3. IOE+00 6.OOE-01 O.OOE+00 0.OOE+00
-1.30E+01
-.IOE+00 2.00E+00
-9.OOE-01 2.80E+00
-3.10E+00 1.56E+00
-2.90E+02
-9.OOE+00
-9.00E-01
-3.20E+00
-6.90E+00 1.60E+00
-1.10E+00
-1. 10E+00
-6.OOE-01 2.20E+00
-5.OOE+00 3.00E+00
-3.70E+02 1.60E+00
-5.10E-01 5.20E+00
-1.40E+00 4.00E+02
-3.80E+00 2.90E+00 1.10E+00 1.20E+00 1.20E+00 I.20E+00 4.20E+00
- 8. OE-01 4.00E+02 4.60E+00 1.IOE+00 2.30E+00 2.30E+00 6.70E+00 1.801E+00
.SOE+00
.SOE+00 1.20E+00 6.40E+00 8.60E-01 2.30E+02 1.40E+01 1.70E+00 3.SOE+00 3.20E+00 3.00E+00 1.40E+00 1.40E+00
- l. lOE+00 1.30E+00 3.SOE+00 l.OOE+00 3.20E+02 3.30E+00 9.30E-0O 2.70E+00 2.SOE+00 3.20E+02 3.30E+00 1.30E+01 4.80E+00 3.80E+00 4.50E+00 4.50E+00 1.50E+01 2.80E+00 I1.20E+03 1.60E+01 3.90E+O0 8.70E+00 8.60E+00 3.20E+01 7.40E+00 5.OOE+00 6.20E+00 3.40E+00 2.601E+01 2.80E+00 6.70E+02 5,30E3+01 6.70E3+00 I1.50E+0I 1.51E+01 1.IOE+01 5.60E+00 5.90E+00 4.70E+00 4.40E+00 1.60E+01
- 3. 1 0E+00
- 1. IOE1+03 I1.20E+01 4.00E+00 8.50E+00 l.00E+01 l.001E+03 1.40E+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 Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCiIL)
SAMPLE TYPE STD.DEV.
(pCUL)
MDC (pCUL)
WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7341-01 L7471-01 L7471-01 L7471-01 L7471-01 L7471-01 L7471-01 L7471-01 L7471-0I L7471-01 L7471-01 L7471-01 II L7471-01 ll L7611-01 11 L7611-0I 1l L7611-01 L7611-01 L761I-01 L7611-01 L7611-01 L7611-01 L7611-01 L7611-01 L7611-01 L7611-01 II L7643-01 II L7643-01 II L7643-01 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/20n4 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/2612004 4/26/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSSBETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSSBETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSSBETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60
-1.40E+00 1.00E+00
-6.00E-01 2.00E-01
-2.80E+00 3.20E+00
-5.60E+02 7.60E+00
-2.80E+00
-9.50E+00
-2.90E+O0 7.60E+00
-8.00E-01
-2. 1OE+00 3.00E-01 O.OOE+00 0.00E+00 4.40E+00
-5.40E+02
-2. 1OE+00 2.20E+00
-2.80E+00 I. IOE+00 5.40E+00 4.00E-01 1.30E+00 0.OOE+00 6.00E-01
-9.40E+O0 6.90E+00 3.90E+02
-4.80E+00 1.50E+00 6.00E+00
-6.60E+00 2.20E+O0
-3.00E+00
-3.00E-01 1.60E+00 1.50E+00 1.40E+00 1.40E+00 3.70E+00 1.OOE+00 4.30E+02 4.00E+00 1.40E+00 3.60E+00 2.60E+00 3.90E+00 1.40E+00 1.80E+00 1.60E+00 1.70E+00 4.60E+00
- 1.
IOE+00 3.50E+02
- 5. IOE+00 1.30E+00 7.60E+00 2.70E+00 4.50E+O0 l.SOE+00 1.70E+00 2.00E+00 1.501E+00 4.80E+00 1.20E+00 4.60E+02 4.40E+00 1.70E+00
- 7. IOE+00 3.30E+00 2.20E+00 I.50E+00 1.70E+00 6.30E+00 5.40E+00 5.60E+00 5.20E+O0 1.60E+O1 3.1OE+O0 1.30E+03 1.30E+01 6.1 OE+00 1.60E+0O
- l. lOE+01 1.20E+01 5.80E+00 7.70E+00 5.90E+00 6.30E+00 I.80E+01
- 3. 1OE+00 1.20E+03 1.80E+01 4.20E+00 2.70E+01 1.OOE+01 1.50E+01 5.70E+00 6.10E+00 7.60E+00 5.70E+00 2.30E+01 2.90E+00 1.40E+03 1.70E+0O 6.20E+00 2.40E+01 1.40E+01 7.70E+O0 6.20E+00 6.20E+00
- 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 Annual Radiological Environmental Operating Report 2004
- Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
NUCLIDE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR L7643-01 L7643-01 L7643-01 L7643-01 L7643-01 L7643-01 L7643-01 L7643-01 L7643-01 L7743-01 L7840-01 L7840-0i L7840-01 L7840-01 L7840-01 L7840-01 L7840-01 L7840-01 L7840-01 1
L7840-01 I I L7840-01 L7840-01 L7980-01 L7980-01 L7980-01 L7980-01 L7980-01 I I L7980-01 L7980-01 L7980-01 L7980-01 L7980-01 L7980-01 L7980-0l I l L8121-04 L,8121-04 L8121-04 L8121-04 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140 Co-S8 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134
-5.OOE-01
-I.IOE+00
-4.40E+00 I.53E+00 3.1OE+02 3.20E+00 O.OOE+00
-2.50E+00
-1.70E+00
-5.70E+02 2.30E+00 O.OOE+00 2.50E+00 1.60E+O0
-1.80E+00
-3.20E+00 4.80E+00
-1.30E+02
-I.50E+00 4.OOE-OI 5.20E+00 4.20E+O0
-3.50E+O0 2.00E-O1 S.OOE-OI
-1.40E+O0
-3.00E-O1
-1.OOE+O0 1.60E+O0 8.30E+02
-3.30E+00
-2.00E+O0 9.80E+O0
-9.OOE-0I 3.40E+00
-I.OOE+00 6.00E-0I 3.80E+00 1.40E+00 1.60E+00 4.30E+00 9.20E-0I 3.80E+02
- 3. 1OE+00 1.60E+00 8.50E+00 2.70E+00 5.30E+02 2.70E+00 1.60E+00 1.80E+O0 1.70E+00 1.30E+00 4.40E+00
- 1. IOE+00 S.40E+02 2.90E+00 1.40E+00 6.00E+00 2.90E+00 2.30E+00 1.60E+00 1.90E+00 1.40E+00 1.80E+00 4.80E+00 8.50E-0O 4.90E+02 3.00E+00 1.80E+00 7.60E+00 2.60E+00 3.40E+00
- 2. 1OE+00 2.1 OE+00 1.60E+00 5.40E+O0 5.90E+O0 1.70E+O1 3.00E+O0 1.20E+03 I. IOE+OI 5.90E+00 3.00E+0I l.OOE+0O 1.80E+03 I.00OE+OI 6.10E+00 6.00E+00 5.90E+00 5.SOE+00 1.90E+0O 3.00E+00 1.70E+03
- 1. IOE+OI 5.10E+00 2.00E+01 9.70E+O0 l.IOE+O1 6.OOE+00 7.10E+O0 6.30E+O0 6.80E+00 L.90E+0O 2.70E+00 1.50E+03 1.20E+0I 7.40E+00 2.50E+0I l.00E+01 1.20E+0I
- 8. IOE+00 7.90E+00 4.60E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-62
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE TYPE I
STATION LSN D
WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 11 L8121-04 II L8121-04 II L8121-04 11 L8121-04 11 L8121-04 11 L8121-04 11 L8121-04 11 L8121-04 11 L8315-01 II L8352-01 II L8352-01 11 L8352-01 II L8352-01 11 L8352-01 II L8352-01 11 L8352-01 11 L8352-01 II L8352-01 11 L8352-01 11 L8352-01 11 L8352-01 11 L8484-01 11 L8484-01 11 L8484-01 II L8484-01 11 L8484-01 11 L8484-01 II L8484-01 II L8484-01 11 L8484-01 11 L8484-01 11 L8484-01 11 L8484-01 II L8663-01 II L8663-01 Ii L8663-01 II L8663-01 II L8663-01 9'
9, 9j 9,
9, 9,
9, 9,
9, 10, 10, 10, 10, 10, 10) 10) 10) 10) 11) 11) 11) 11)
Ill II/
Il/
11 li ii Summary of 2004 Data
'ND
'ATE NUCLIDE t22/2004 Cs-137
/22/2004 Fe-59 122/2004 GROSS BETA
'22/2004 H-3
/22/2004 1-131 122/2004 Mn-54 122/2004 Zn-65
/22/2004 Zr-95
'22/2004 H-3
'27/2004 Ba-140 27/2004 Co-58 27/2004 Co-60 27/2004 Cs-134 27/2004 Cs-137
/27/2004 Fe-59 27/2004 GROSS BETA
/27/2004 H-3
/27/2004 1-131 27/2004 Mn-54 27/2004 Zn-65 27/2004 Zr-95 23/2004 Ba-140 23/2004 Co-58 23/2004 Co-60 23/2004 Cs-134 23/2004 Cs-137 23/2004 Fe-59 23/2004 GROSS BETA 23/2004 H-3 23/2004 1-131 23/2004 Mn-54 23/2004 Zn-65 23/2004 Zr-95 1/3/2005 Ba-140 1/3/2005 Co-58
/3/2005 Co-60 1/3/2005 Cs-134
/3/2005 Cs-137 CONG (pCi/L)
-1.40E+00
-1.001E+01 2.25E3+00
-4.40E+02
-1.05E3+01
-2.20E+00
-1.27E+01 0.001E+00
-5.00E3+01 0.00E3+00
-8.201E-01
-1.60E+00 1.90E3+00 7.001E-01 I1.40E3+00 2.17E+00 5.1 oE+02 l.001E+00
-5.00OE-01
-7.001E-01 5.001E-01 9.OOE-01
-1.60E+00
-2.20E+00 I.001E-01
-3.001E-01
-7.20E+00 1.82E+00
-1.04E+03
-1.60E+00
-6.OOE-01
-3. 1 OE+00
-7.001E-01 0.OOE+00
-1.OOE+00 6.OOE-01 I.00E3-01 6.001E-0 I STD.DEV.
(PUiL) 2.10OE+00 4.60E+00 9.10E-01 4.60E+02 5.501E+00 2.201E+00 5.50E3+00 3.80E3+00 3.30E+02 2.00E3+00 9.80E-01 1.701E+00 1.401E+00 1.30E3+00 3.60E3+00 9.101E-01 3.30E3+02 2.40E+00 1.30E3+00 2.20E+00 1.80E+00 5.6013+00 2.90E+00 2.301E+00 2.40E3+00 2.001E+00 5.401E+00 8.60E3-01 4.701E+02
- 5. 1 OE+00 2.30E+00 4.80E+00 3.40E+00 1.90E3+00 1.20E+00 I. I OE+00 1.201E+00 I1.20E+00 MDC (pCiAL) 8.0O1E+00 2.20E+01 2.80E+00 I1.40E+03 2.101E+01 8.40E3+00 2.301E+01 1.40E3+01 1.IOE+03 8.20E3+00 4.40E+00 7.30E3+00 4.70E+00 4.601E+00 I1.401E+01 2.80E3+00 1.00E+03 8.601E+00 5.301E+00 9.50E+00 7.201E+00 2.30E3+01 1.20E+01 L.IOE+01 9.60E+00 8.20E+00 2.90E+01 2.701E+00 I1.50E+03 2.OOE+01 9.40E+00 2.20E+01 1.50E+01 7.70E3+00 4.70E+00
- 4. 1 01+00 4.60E+00 4.301E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-63
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END CONC STD.DEV.
MDC TYPE STATION LSN DATE NUCLIDE (pCUL)
(pCi/L)
(pCiIL)
WR 11 L8663-01 1/3/2005 Fe-59
-1.40E+00 3.00E+00 1.20E+01 WR 11 L8663-01 1/3/2005 GROSS BETA 1.58E+00 9.30E-01 3.OOE+00 WR 11 L8663-01 1/3/2005 H-3 5.40E+02 4.30E+02 1.30E+03 WR I1 L8663-01 1/3/2005 1-131
-4.80E+00 3.00E+00 I.IOE+01 WR 11 L8663-01 1/3/2005 Mn-54
-4.OOE-0
- 1. IOE+00 4.40E+00 WR 11 L8663-01 1/3/2005 Zn-65
-9.OOE-01 2.50E+00 9.80E+00 WR 11 L8663-01 1/3/2005 Zr-95 8.00E-01 2.00E+00 7.20E+00 WR 11 L8748-01 1/3/2005 H-3
-8.00E+01 3 10E+02 I.00E+03 WR 21 L6910-02 1/30/2004 Ba-140
-I.00E+00 2.60E+00 1.20E+01 WR 21 L6910-02 1/30/2004 Co-58 7.00E-01 1.50E+00 5.SOE+00 WR 21 L6910-02 1/30/2004 Co-60
-2.00E-0O
- 1. IOE+00 4.70E+00 WR 21 L6910-02 1/30/2004 Cs-134 7.00E-0 I.50E+00 5.50E+00 WR 21 L6910-02 1/30/2004 Cs-137
-2.90E+00 1.IOE+00 5.30E+00 WR 21 L6910-02 1/30/2004 Fe-59
-7.90E+00 4.70E+00 2.10E+01 WR 21 L6910-02 1/30/2004 GROSS BETA 1.70E+00 8.60E-01 2.70E+00 WR 21 L6910-02 1/30/2004 H-3 4.30E+02 4.1OE+02 1.20E+03 WR 21 L6910-02 1/30/2004 1-131 2.70E+00 4.80E+00 1.70E+01 WR 21 L6910-02 1/30/2004 Mn-54
-2.60E+00 1.60E+00 6.60E+00 WR 21 L6910-02 1/30/2004 Zn-65
-3.30E+00 2.70E+00 1.20E+01 WR 21 L6910-02 1/30/2004 Zr-95
-1.70E+00 2.80E+00 1.IOE+0O WR 21 L6992-02 2/25/2004 Ba-140
-4.70E+00 4.50E+00 2.00E+0O WR 21 L6992-02 2/25/2004 Co-58
-1.40E+00 1.50E+00 6.20E+00 WR 21 L6992-02 2/25/2004 Co-60
-1.50E+00 1.20E+00 5.30E+00 WR 21 L6992-02 2/25/2004 Cs-134
-3.00E-01 1.20E+00 4.60E+00 WR 21 L6992-02 2/25/2004 Cs-137 2.80E+00 1.30E+00 4.1OE+00 WR 21 L6992-02 2/25/2004 Fe-59 2.00E+00 5.20E+00 I.90E+0I WR 21 L6992-02 2/25/2004 GROSS BETA 1.49E+00 8.10E-01 2.60E+00 WR 21 L6992-02 2/25/2004 H-3 7.00E+01 2.30E+02 6.70E+02 WR 21 L6992-02 2/25/2004 1-131 1.30E+01 1.20E+01 4.20E+01 WR 21 L6992-02 2/25/2004 Mn-54 1.IOE+00 1.IOE+00 3.80E+00 WR 21 L6992-02 2/25/2004 Zn-65 3.40E+00 2.80E+00 9.60E+00 WR 21 L6992-02 2/25/2004 Zr-95 1.50E+00 2.30E+00 8.40E+00 WR 21 L7175-02 3/29/2004 Ba-140
-4.00E+00 2.70E+00 1.30E+01 WR 21 L7175-02 3/29/2004 Co-58
-7.00E-01 1.20E+00 4.90E+00 WR 21 L7175-02 3/29/2004 Co-60 5.00E-01 1.40E+00 5.50E+00 WR 21 L7175-02 3/29/2004 Cs-134 3.1OE+00 1.50E+00 4.50E+00 WR 21 L7175-02 3/29/2004 Cs-137
-2.00E-01 1.50E+00 5.60E+00 WR 21 L7175-02 3/29/2004 Fe-59 3.50E+00 3.60E+00 1.30E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-64
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE TYPE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR S
STATION LSN D
21 L7175-02 21 L7175-02 21 L7175-02 21 L7175-02 21 L7175-02 21 L7175-02 21 L7297-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7341-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7471-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 3,
3, 3,
3, 3,
3, 3,
4, 4,
4, 4,
4, 4,
4, 4,
4, 4,
4, 4,
4i 5,
4, 4,
5, 5,
5, 4,
Si 5,
5s 5,
6/
65 6/
6/
6/
6) 6)
Summary of 2004 Data END ATE NUCLIDE
'29/2004 GROSS BETA
/29/2004 H-3
'2912004 1-131
/29/2004 Mn-54 29/2004 Zn-65 29/2004 Zr-95 129/2004 H-3 126/2004 Ba-140
'26/2004 Co-58 26/2004 Co-60
'26/2004 Cs-134
'26/2004 Cs-137
/26/2004 Fe-59
'26/2004 GROSS BETA
'26/2004 H-3
'26/2004 1-131 26/2004 Mn-54
'26/2004 Zn-65 26/2004 Zr-95 25/2004 Ba-140 25/2004 Co-58 25/2004 Co-60 25/2004 Cs-134 25/2004 Cs-137 25/2004 Fe-59 25/2004 GROSS BETA 25/2004 H-3 25/2004 1-131 2512004 Mn-54
/25/2004 Zn-65 25/2004 Zr-95 23/2004 Ba-140 23/2004 Co-58 23/2004 Co-60 23/2004 Cs-134 23/2004 Cs-137 23/2004 Fe-59 23/2004 GROSS BETA CONC (pCi/L)
L.99E+00 1.00E+01
-8.20E+00
-1.30E+00
-s.90E+O0 8.OOE-01 4.20E+02 O.OOE+00
-1.20E+00 1.40E+00 1.OOE+00 1.OOE+00
-7.00E+00 1.27E+00
-3.20E+02 6.90E+00 O.OOE+00 0.OOE+00 9.00E-01
-1.80E+00
-5.OOE-01 3.00E-01
-2.1 OE+00
-7.00E-01
-1.SOE+00 2.41E+00
-5.OOE+02 8.10E+00
-1.OOE+00 3.70E+00 4.20E+00 1.30E+O0
-2.00E+00
- 3. IOE+00 3.00E-01
-1.80E+00
-7.60E+00 2.60E-01 STD.DEV.
(pCi/L) 8.80E-01 3.30E+02 4.1 OE+00 1.20E+00 2.80E+00 2.30E+00 3.20E+02 3.20E+00 1.40E+O0 1.60E+00 1.90E+00 1.50E+00 5.00E+00 8.40E-01 4.20E+02 5.20E+O0 1.70E+00 2.60E+00 2.90E+00
- 3. 1OE+00 1.70E+00 1.90E+00
- 2. 1OE+00 1.30E+00 4.80E+00 9.40E-01 3.50E+02
- 4. 1OE+00 1.70E+00 3.90E+00 2.90E+00 3.90E+00 1.80E+00 1.50E+00 1.30E+00 1.80E+00 5.00E+00 8.1OE-0I MDC (pCiUL) 2.80E+00
- 1. IOE+03 1.70E+01 4.90E+00 1.20E+01 8.SOE+00 1.OOE+03 1.40E+01 6.20E+00 5.90E+00 7.1 OE+00 5.40E+00 2.30E+01 2.80E+00 1.30E+03 1.70E+01 6.70E+00
- 1. lOE+01 1.lOE+01 1.40E+01 6.90E+00 7.60E+00 8.70E+00 5.60E+00 2.00E+01 2.90E+00 1.20E+03 1.30E+01 6.90E+00 1.40E+0 I 9.70E+O0 1.50E+01 8.00E+00 4.OOE+00 5.50E+00 7.50E+00 2.40E+01 2.80E+00
- Radioactivity detected in sample (i.e., concentration >3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-65
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC Wpi/ll)
STD.DEV.
(pCUL)
MDC (pCUL)
WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7611-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7643-02 21 L7743-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7840-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/2812004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 CO-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 4.80E+02
-1.13E+01 O.OOE+00
-2.00E+00 4.10E+00 8.soE+00 1.OOE-01 2.70E+00 2.OOE-01 1.20E+00 5.50E+00 1.85E+00 2.70E+02 6.OOE-01
-2.50E+00 7.90E+00
-1.60E+00
-5.70E+02 4.70E+00 1.70E+00 2.20E+00
- 2. 1OE+00 8.00E-01
-1.20E+00 1.39E+00
-6.00E+02
-2.80E+O0
-1.40E+00 6.50E+00 1.40E+00
-9.OOE-01
-1.40E+00 5.00E-0O O.OOE+00 8.00E-0 I 5.60E+O0 1.82E+O0 3.1OE+02 4.70E+02 6.OOE+00 I1.80E+00 4.30E+00 3.60E+00 3.70E+00 1.90E+00 2.50E+00 1.90E+00 I.80E+O0 4.40E+00 8.70E-01 3.80E+02 2.80E+00 2.50E+00 4.10OE+00 2.70E+00 5.40E+02 2.901E+00 2.201E+00 2.20E+00 2.50E+O0 2.001E+00 6.OOE+00 8.20E-01 5.30E+02 3.80E+00 I1.80E+00 7.40E+00 3.50E+00 2.OOE+O0 1.80E+00 1.60E+O0 1.801E+00 I1.901E+00 4.40E+00 8.40E-01 4.701E+02 1.40E+03 2.40E+01 7.10E+00 1.80E+0O 1.20E+01 9.00E+00 7.80E+00 8.90E+O0 7.70E+O0 6.80E+O0 1.50E+0O 2.80E+00 1.20E+03 I. IOE+01 I.OOE+01 1.20E+01 1.20E+0O 1.80E+03 8.60E+00 8.OOE+00 7.80E+00 8.70E+00 7.30E+O0 2.50E+01 2.70E+00 1.80E+03 I.50E+01 7.50E+00 2.60E+0O 1.30E+0O 9.50E+00 7.SOE+00 6.60E+00 7.20E+00 7.00E+00 1.50E+01 2.70E+00 1.40E+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-66
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC KU~iL)
STD.DEV.
MDC (pCi/L)
(pCi/L)
NUCLIDE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 21 L7980-02 21 L7980-02 21 L7980-02 21 L7980-02 21 L8121-02 21 L8121-02 21 LS121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8121-02 21 L8315-02 2 1 L8352-02 2 1 L8352-02 2 1 L8352-02 21 L8352-02 2 1 L8352-02 21 L8352-02 21 L8352-02 21 L8352-02 21 L8352-02 2 1 L8352-02 2 1 L8352-02 2 1 L8352-02 2 1 L8484-02 21 L8484-02 2 1 L[844-02 2 1 L8484-02 2 1 L8484-02 2 I L8484-02 2 1 L8484-02 2 1 L8484-02 21 L8484-02 8/27/2004 827/2004 8/27/2004 8/27/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 CO-60 Cs-134 Cs-137 Fc-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-1 34 Cs-137 Fe-59 GROSS BETA H-3 1-131 1.70E+OO I.OOE-01 2.10E+00
-5.00E+00
-2. IOE+00
-2.00E+00 11.OOE+O0 2.30E+00
-1.40E+00
-5.40E+00 1.03E+O0
-4.00E+01
-3.70E+00 l.00E+00
-8. 1OE+00
-9.60E+00
-3. 1OE+02 4.30E+00
-1.20E+00 8.00E-01
-3.00E+O0
-1.00E+00
-2.00E+00 2.44E+00
-.60E+02 3.20E+O0 I.20E+00 0.OOE+00 8.70E+00 3.60E+00 4.30E+00 1.20E+00 3.70E+00 l.IOE+00
-5.90E+00 1.43E+00
-6.70E+02
-6.00E-0 I 2.401E+00 I1.5013+00 4.40E+00 3.40E+00 3.90E+O0 1.70E+00 1.90E+00 1.60E+00 I1.80E+O0 5.001E+00 8.30E-01 4.70E+02 3.70E+O0 1.40E+00 3.50E+00 3.00E+00 3.50E+02 3.30E+00 I1.50E+O0 I1.70E+00 I1.60E+O0 1.70E+00 3.80E+00 8.70E-01 3.20E+02 2.70E+00 1.40E+O0 3.40E+00 3.20E+00 5.20E+O0 2.20E+00
- 3. IOE1+00 2.20E+00 I1.80E+O0 6.20E+00 8.50E-01 4.80E+02
- 4. I OE+00 8.70E+O0 6.00E+00 1.70E+01 1.50E+01 1.60E+O1 7.40E+00 7.00E+00 5.20E+00 7.30E+00 2.30E+01 2.70E+00 1.40E+03 1.50E+01 5.OOE+O0 1.70E+01 1.50E+0O 1.20E+03
- 1. IOE+O1 6.30E+00 6.80E+00 7.50E+00 6.80E+O0 1.70E+01 2.60E+O0 1.00E+03
- 9. IOE+O0 5.20E+00 1.40E+0O 8.60E+00 2.OOE+OI 6.50E+00 1.20E+01 6.70E+00 6.80E+00 3.00E+01 2.70E+00 1.50E+03 1.70E+0I
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-67
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCIL)
STD.DEV.
MDC (pCi/L)
(pCi/L)
NUCLIDE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 21 L8484-02 21 L8484-02 21 L8484-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 '
L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8663-02 21 L8748-02 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6910-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 11/23/2004 11/23/2004 11/23/2004 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/4/2005 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 1/30/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140 Co-5S Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3
-5.00E3+00 1.50E+00 2.60E+00
-1.30E+00 7.00E-01
-1.00OE+00
-9.OOE-0O l.OOE+00
-1.70E+00 1.29E+00 3.40E+02
-I.IOE+00
-1.80E+00 6.00E-01
-1.90E+00
-1.30E+02
-9.00E-01
-3.00E-01 2.40E+00 7.00E-01
-2.30E+00
-3.00E+00 9.80E-01 5.40E+02 7.00E-01 1.IOE+00
-4.SOE+00 7.00E-01 1.60E+00 O.OOE+00 1.90E+00
-6.00E-0I 2.20E+00
-4.00E-0O 2.29E+00
-2.90E+02
- 2. 10E+00 4.50E+00 3.90E+00 2.70E+00 1.40E+00 1.20E+00 1.60E+00 1.60E+00 3.40E+00 8.40E-01 4.30E+02 2.70E+00 1.30E+00 2.80E+00 2.40E+00
- 3. 1OE+02 3.70E+00 1.40E+00 1.30E+00 1.30E+00 1.30E+00 3.90E+00 8.00E-01
- 4. 1OE+02 5.SOE+00 1.20E+00 3.70E+00 2.80E+00 6.50E+00 1.70E+00 1.70E+00 1.60E+00 1.30E+00 4.30E+00 9.1OE-0I 2.30E+02 l.00E+01 I.80E+01 I1.50E+01
- 1. IOE-e01 5.0O1E+00 5.5013+00 6.3013+00 5.60E3+00 I1.50E+01 2.70E3+00 I1.30E3+03 1.00E+01 5.50E+00 1.IOE+01 9.60E+00 l.00E+03 1.50E+01 5.60E+00 4.20E+00 4.90E+00 5.60E+00 I1.70E-e-01 2.7013+00 1.20E+03 2.OOE+01 4.20E+00 1.50E+01 1.00E+01 2.50E+01 6.50E+00 6.OOE+00 6.301E+00 4.20E+00 I1.80E+01 2.80E3+00 6.70E+02
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-68
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE TYPE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR I
STATION LSN D
31 L6992-03 31 L6992-03 31 L6992-03 31 L6992-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7175-03 31 L7297-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7341-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 2j 2i 2i 2j 3,
3, 3,
3, 3,
3, 3) 3)
4) 4, 4,
4, 4,
4, 4,
4, 4,
4, 4,
4/
5/
5' 5/
5/
5/
5/
Summary of 2004 Data
'ND ATE NUCLIDE 25/2004 1-131 25/2004 Mn-54 25/2004 Zn-65 25/2004 Zr-95 29/2004 Ba-140 29/2004 Co-58 29/2004 Co-60 29/2004 Cs-134 29/2004 Cs-137 29/2004 Fe-59 29/2004 GROSS BETA 29/2004 H-3 29/2004 1-131 29/2004 Mn-54 29/2004 Zn-65 29/2004 Zr-95 29/2004 H-3
/26/2004 Ba-140 26/2004 Co-58
/26/2004 Co-60 26/2004 Cs-134 26/2004 Cs-137
'26/2004 Fe-59 2612004 GROSS BETA 26/2004 H-3 26/2004 1-131 26/2004 Mn-54 26/2004 Zn-65 26/2004 Zr-95 25/2004 Ba-140 25/2004 Co-58 25/2004 Co-60 25/2004 Cs-134 25/2004 Cs-137 25/2004 Fe-59 25/2004 GROSS BETA CONC (pCi/L)
-2.OOE+00 1.20E+00
-2.20E+00
-1.80E+00
-1.OOE+00
-S.OOE-01
-1.20E+O0 3.40E+00
-2.90E+00 O.OOE+00 1.62E+00 O.OOE+00 4.20E+00
-4.00E-01
-4.20E+00 1.60E+00 5.OOE+02
-1.60E+00
-4.00E-01
-1.90E+00
-2.80E+00
-1.40E+00 2.40E+00 2.01E+00 5.OOE+01 2.60E+00
-2.20E+O0 3.70E+00
-8.OOE-0I 3.40E+00 1.20E+00 4.30E+00
-1.70E+00
-1.80E+00
-1.04E+0O 2.40E+00 STD.DEV.
(pCi/L) 1.20E+01 1.40E+O0 3.OOE+00 3.20E+00 3.40E+O0 1.40E+00 1.60E+00 1.501E+00 1.20E+O0 4.50E+O0 8.70E-01 3.30E+02 3.90E+00 1.30E+00 3.30E+00 2.20E+00 3.20E+02 4.10E+00 1.60E+O0 2.40E+00 1.90E+00 1.90E+00 7.70E+00 9.70E-O1 4.30E+02 4.20E+00 2.10E+00 4.80E+00 3.20E+00 3.40E+00 2.40E+00 2.70E+O0 1.80E+00 1.20E+00 7.30E+O0
- 1. IOE+00 MDC (pCi/L) 4.50E+01 5.00E+O0 1.30E+01 1.30E+01 1.40E+01 5.60E+O0 6.90E+00 4.40E+00 5.70E+00 1.80E+O1 2.80E+00
- 1.
IOE+03 1.30E+01 5.10E+O0 1.40E+01 8.1OE+00 1.OOE+03 1.90E+O1 7.OOE+00 1.lOE+01 8.90E+00 8.00E+00 2.90E+01 3.00E+OO 1.30E+03 l.50E+01 9.00E+00 1.70E+01 1.30E+01 1.30E+O1 9.00E+00 8.80E+00 8.50E+o0 6.40E+00 3.40E+0 I 3.60E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-69
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE I
TYPE STATION LSN D
WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7471-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7611-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7643-03 31 L7743-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 5,
5, 5,
6i 6,
6/
6i 6/
6/
6/
6/
6/
6) 6/
6/
6/
6/
6/
6/
6/
6/
6/
7/:
7/:
7/:
Summary of 2004 Data END
'ATE NUCLIDE
- 25/2004 H-3 (25/2004 1-131
- 25/2004 Mn-54
- 2512004 Zn-65
/25/2004 Zr-95
'23/2004 Ba-140
'23/2004 Co-58
'23/2004 Co-6o 23/2004 Cs-134 23/2004 Cs-137 23/2004 Fe-59
'23/2004 GROSS BETA 23/2004 H-3 23/2004 1-131 123/2004 Mn-54 23/2004 Zn-65 123/2004 Zr-95 28/2004 Ba-140 28/2004 Co-58 28/2004 Co-6o 28/2004 Cs-134 28/2004 Cs-137 28/2004 Fe-59 28/2004 GROSS BETA 28/2004 H-3 28/2004 1-131 28/2004 Mn-54 28/2004 Zn-65 28/2004 Zr-95 28/2004 H-3 29/2004 Ba-140 29/2004 Co-58 29/2004 Co-6o 29/2004 Cs-134 29/2004 Cs-137 29/2004 Fe-59 CONC (Pci/L)
-2.90E+02
- 7. 1 0E+00
-4.001E-01
-1.301E+00 6.901E+00 3.401E+00
-2.70E+00 3.801E+00
-1. IOE1+00 1L00E-01 5.50E+00 I1.86E+00 0.00E+00 6.401E+00 8.00E-01
-2.70E+00 9.001E-01 3.6013+00
-5.40E+00
-1.00E+00
- 2. IO0E+00
-3.60E+00
- 3. 1 OE+00 I1.49E+O00 3.601E+02 I1.90E3+00 8.001E-01 1.30E+00
-3.OOE-01
-6.40E+02 4.60E+00
-3.40E+O0 1.40E+00 I1.20E+00 1.30E3+00
-2.60E+00 STD.DEV.
(pCi/L) 3.50E+02 5.90E+00 1.60E+00 4.00E+00 3.10E+00 5.80E+o0 2.00E+00 2.40E+00 2.10E+00 1.80E+00 6.60E+00 8.SOE-01 4.50E+02 4.80E+00 L.50E+00 4.60E+00 3.50E+O0 3.20E+00 2.20E+O0 1.90E+00 2.10E+00 L.80E+00 5.60E+00 8.70E-01 4.10E+02 3.30E+00 1.60E+O0 4.30E+00 2.60E+00 5.40E+02 3.60E+00 1.40E+O0 1.70E+00 l.50E+o0
- 2. 1 OE+00 5.IOE+00 MDC (pUiL)
I1.20E+03 2.001E+01 7.00E3+00 I1.80E+01 8.OOE3+00 2.20E+01 9.201E+00 7.801E+00 8.901E+00 7.201E+00 2.40E-i01 2.70E+00 I1.40E+03 1.60E+01 5.90E+00 2.001E+01 I1.40E+01
- 1. IOE+01 I.00E+01 8.601E+00 7.50E+00 8.60E3+00 2.20E3+01 2.801E+00 1.301E+03 1.201E+01 6.20E+00 I1.70E+01
- 1. IOE+01 I1.8013+03 1.20E+01 7.40E+00 6.20E+O00 5.601E+00 7.601E+00 2.30E3+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-70
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004. Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
NUCLIDE WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7840-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L7980-03 31 L8121-03 31 L812i-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8121-03 31 L8315-03 31 L8352-03 3 1 L8352-03 3 1 L8352-03 3 1 L8352-03 3 1 L8352-03 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27n2004 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3 Ba-140 Co-58 Co-60 Cs-1 34 Cs-137 2.05E+00
-6.OOE+02 7.OOE-01
-1.50E+00 2.10E+00
-2.90E+O0 5.60E+00 2.10E+00
-3.40E+00
-4.OOE-01
-1.OOE-01 1.00E+00
- 2. 1 SE+O0
- 4. 10E+02 5.OOE+00
-1.90E+00
-6.70E+00
-5.OOE-01 2.20E+00 1.00E+00 2.OOE+O0 9.OOE-01
- 1. I OE+00
-6.OOE-01 2.76E+00 5.50E+02 3.401E+00 8.001E-01 3.90E+00
- 2. IOE1+00
-1.60E3+02
-2.501E+00 8.00E3-01 2.901E+00 6.OOE-01
-5.OOE-01 9.30E-01 5.30E+02 3.70E+00 I.60E+00 4.50E+00 2.70E+00 3.00E+00 1.60E+00 1.90E+00 1.90E+00 I.90E+00 4.50E+00
- 9. IOE-01 4.80E+02 3.30E+00 I.80E+00 4.50E+00 3.30E+00
- 3. IOE+O0 1.30E+00 1.40E+00 1.60E+00 I.80E+O0 3.90E+00 9.00E-01 4.70E+02 3.90E+00 I.60E+00 3.60E+00 3.00E+00 3.50E+02 2.20E+00 1.60E+00 2.00E+00 1.80E+00 1.50E+00 2.90E+00 I1.70E+03 I1.40E+01 7.OOE+00 1.70E+01 1.20E+01 8.70E+00 5.50E+00 9.40E+00 7.60E+00 7.50E+00 I1.80E+01 2.80E+00 1.50E+03 1.1I OE+01I 8.001E+00 2.001E+01 I1.30E+01 1.20E1e-01 4.90E3+00 4.6013+00 6.201E+00 6.40E+O00 1.70E+01 2.60E+00 I1.401E+03 1.30E+01 6.OOE+00 1.30E+01
- 1. I OE+0 I 1.20E+03 I. IOE+01 6.O0E-e-00 6.701E+00 6.701E+00 6.001E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-71
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END STATION LSN DATE NUCLIDE SAMPLE TYPE CONC (pCi/L)
STD.DEV.
(pCi/L)
MDC (pCi/L)
WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR WR 31 L8352-03 10/27/2004 Fe-59 31 L8352-03 10/27/2004 GROSSBETA 31 L8352-03 31 L8352-03 31 L8352-03 31 18352-03 31 L8352-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8484-03 31 L8748-03 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 11/23/2004 H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 H-3
-2.soE+00 1.04E+00
-1.60E+02
-1.80E+00 1.70E+00 2.70E+00 1.50E+00
-2.30E+00
-1.20E+00 2.60E+00 3.00E-01
-2.SOE+00 2.90E+00 3.20E-0I
-7.90E+02 O.OOE+00
-1.70E+00
-1.48E+01 2.60E+00 2.70E+02 5.IOE+00 2.1OE+O I 8.30E-01 2.70E3+00 3.20E+02 1.001E+03 2.80E+00 1.IOE+OI 1.40E+00 4.70E+00 3.50E+00 1.30E+01 2.80E+00 1.00E+01 2.80E+00 1.20E+01 1.70E+00 6.80E+00 1.40E+00 4.50E+00 1.60E+00 5.80E+00 1.50E+00 6.20E+00 4.20E+00 1.50E+01 7.10E-01 2.50E+00 4.70E+02 L.501E+03 4.10E+00 1.50E+01 1.20E+00 S.40E+00 4.00E+00 1.90E+01 2.90E+00 1.00E+01 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-72
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program SAMPLE TYPE S
STATION LSN D
WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW WW 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 L7175-07 51 1,7175-07 51 L7175-07 51 L7175-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7341-07 51 L7471-06 51 L7471-06 51 L7471-06 51 L7471-06 51 L7471-06 51 L7471-06 5I L7471-06 51 L7471-06 51 L7471-06 51 L7471-06 5I L7471-06 5I L7471-06 51 L7611-07 51 L7611-07 3,
3, 3,
3, 3,
3, 3,
3, 3,
3, 3,
3, 4'
4, 4'
4' 4'
4' 4/
4/
4/
4/
4' 5'
5, 5f, St 5f, 54 V.
St 54 5f St Summary of 2004 Data
,ND ATE NUCLIDE
/29/2004 Ba-140
/29/2004 Co-58 29/2004 Co-60 29/2004 Cs-134 29/2004 Cs-137 29/2004 Fe-59 29/2004 GROSS BETA 29/2004 H-3 29/2004 1-131 29/2004 Mn-54 29/2004 Zn-65 29/2004 Zr-95 26/2004 Ba-140 26/2004 Co-58 26/2004 Co-60 26/2004 Cs-134 26/2004 Cs-137 26/2004 Fe-59 26/2004 GROSS BETA 26/2004 H-3 26/2004 1-131 26/2004 Mn-54 26/2004 Zn-65 26/2004 Zr-95 25/2004 Ba-140 25/2004 Co-58 25/2004 Co-60 25/2004 Cs-134 25/2004 Cs-137 25/2004 Fe-59 25/2004 GROSS BETA 25/2004 H-3 25/2004 1-131 25/2004 Mn-54 25/2004 Zn-65 25/2004 Zr-95 23/2004 Ba-140 23/2004 Co-58 CONC (pCi/L)
-2. 10E+00 1.60E+00 O.OOE+00
-4.00E-0I 3.20E+00
-2.00E-01 1.49E+01
- 1. lOE+02 3.70E+00
-7.00E-0I
-2.20E+00 3.30E+00 6.90E+00 1.80E+00
-2.20E+00
-5.OOE-01 1.50E+00
-4.20E+00 1.22E+01
-6.60E+02
-2.90E+00
-5.60E+00 3.90E+00 2.OOE-01 0.OOE+00
-1.40E+00
-3.00E-01
-2.40E+00 3.30E+00
-7.00E-0O 1.27E+0O 1.40E+02 3.80E+00
-1.40E+00
-8. 10E+00
-5.
10E+00
-7.20E+00 2.OOE-0O STD.DEV.
(pCi/L) 2.80E+00 1.20E+00 1.30E+00 1.40E+00 1.30E+00 4.20E+00 1.90E+00 3.30E+02 4.00E+00
- 1. lOE+00 2.20E+00 1.80E+00 4.00E+00 2.20E+00 3.00E+00 2.00E+00 1.30E+00
- 5. 1OE+00 1.40E+00 4.20E+02 5.20E+00
- 2. 10E+00 2.30E+00 3.50E+00 3.90E+00 1.60E+00 1.70E+00 1.90E+00 1.90E+00 4.30E+00 1.60E+00 1.30E+02 5.20E+00 1.80E+00 3.90E+00 3.40E+00 4.40E+00 2.60E+00 MDC (pCi/L) 1.20E+01 4.10OE+00 5.OOE+00 5.30E+00 3.80E+00 1.60E+01 4.20E+00 l.IOE+03 1.40E+01 4.50E+00 9.50E+00 5.70E+00 1.20E+01
- 8.
10E+O0 1.30E+01 8.20E+00 4.50E+00 2.50E+01 3.10E+00 I1.30E+03 2.10OE+01 I.OOE+01 3.60E+00 1.40E+01 1.60E+01 6.80E-I00 7.20E+00 8.OOE+O0 6.OOE+00 1.80E+01 3.40E+00 3.90E+02 1.80E+01 7.30E+00 I1.80E+01 I1.501E+01 2.40E-i01 l.OOE+01
+
k.-
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-73
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE CONC (pCi/L)
STD.DEV.
MDC (pCi/L)
(pCi/L)
NUCLIDE ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww 51 L7611-07 Sl L7611-07 5
L7611-07 51 L7611-07 51 L7611-07 51 L7611-07 51 L7611-07 51 L7611-07 51 L7611-07 51 L7611-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 51 L7643-07 Sl L7643-07 51 L7840-07 51 L7840-07 51 L7840-07 51 L7840-07 51 L7840-07 51 L7840-07 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/2812004 6/28/2004 6/28/2004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 CO-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 CO-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 5.OOE-0O 4.00E-0O 1.50E+O0 6.50E+00 1
.42E+Ol 1.63E+03 2.00E+00 1.90E+O0 2.40E+00 5.20E+O0 1.50E+00
- 4. 1OE+02
-9.20E+00 6.50E+O0
-3.80E+00 1.80E+00
-8.50E+00 4.50E+00
-3.30E+00
- 3. 10E+O0 6.00E-01 2.40E+00
-2.60E+00 1.40E+00
-1.IOE+00 1.50E+00
-3.OOE-0I I.SOE+O0
-1.30E+00 1.30E+00
-3.OOE+00 3.40E+O0 1.12E+01 1.40E+00
-1.SOE+02 3.90E+02 1.IOE+OO 2.60E+00 8.00E-01 1.70E+00
-8.OOE-01 3.OOE+00 O.OOE+00 2.20E+00 3.50E+00 4.50E+O0
-3.70E+00 2.30E+00 5.OOE-01 1.40E+O0
-1.20E+00 2.10E+00
-8.00E-01 2.OOE+00
-3.20E+00 2.30E+00 8.90E+00 1.30E+00
-3.1OE+02 5.30E+02 8.40E+00 7.60E+00 8.80E+00 1.80E+01 3.10E+O0 1.20E+03 2.70E+0O 9.10E+00 2.30E+OI 1.50E+01 9.40E+00 6.30E+00 6.20E+00 5.90E+O0 5.50E+00 I.50E+0I 3.00E+O0 1.30E+03 9.30E+O0
- 6. 1OE+O0 1.20E+0O 8.70E+00 1.60E+01 9.90E+O0 5.90E+00 8.50E+00 7.90E+00 l.50E+0O 3.20E+00 1.70E+03 1.30E+0O 6.OOE+O0 2.10E+0O 1.20E+0I
- l.
IOE+0I 7.60E+O0 l.00E+0O 8.30E+00 51 L7840-07 7/29/2004 GROSS BETA 51 L7840-07 7/29/2004 H-3 51 L7840-07 51 L7840-07 51 L7840-07 51 L7840-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 7/29/2004 7/29/2004 7/29/2004 7/29/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 2.80E+00 1.30E+00
-4.20E+00
-1.50E+00 I.20E+00 4.OOE-01
-2.70E+00
- 1. IOE+00 3.80E1+00 I.70E+00 5.00E+00 2.80E+00 2.70E+00 1.90E+00 2.20E+00 2.20E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-74
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCi/L)
STD.DEV.
(pCUL)
MDC (pCi/L) ww ww ww ww ww b-ww ww ww h-ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L7980-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8121-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 51 L8352-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 8/7/2004 8/27/2004 8n7/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 8/27/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/22/2004 9/2212004 9/22/2004 9/22/2004 9/22s2004 9/22/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 10/27/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59
-2.50E+00
-L.00E+O0 1.53E+0l 1.60E+02
-2.40E+00
-1.30E+00
-7.10E+00 8.OOE-01 6.00E-01
-7.00E-01
-1.60E+00
-2.40E+00 4.00E-01 4.90E+00
- 1. 16E+01 3.40E+02
-5.OOE-01
-1.50E+00
-7.30E+00 1.901E+00 2.60E+00 2.40E+00 2.60E+00
-l.40E+00 2.70E+00 1.60E+00 1.25E+01
-L.IOE+02
-1.80E+00
-6.00E-01
-4.20E+00 l.IOE+00 5.90E+00 2.10E+00 L.50E+O0
-4.OOE-O0
-6.OOE-01 4.30E+00 2.30E+00
- 6. IOE+O0 I.80E+00 4.70E+02 3.20E+00 1.60E+00 5.soE+O0 3.30E+00 3.60E+00 2.OOE+00 1.90E+O0 1.60E+00 1.20E+00 5.80E+00 1.60E+00 4.60E+02 3.80E+00 1.90E+00
- 4. 1 OE+00 3.80E+O0 2.80E+00 I.60E+00 2.40E+00 1.70E+00 1.90E+00 4.80E+00 1.50E+00 3.20E+02 4.20E+00 1.90E+00 3.90E+O0 3.70E+00 4.80E+00 1.30E+00 1.30E+00 1.20E+00 1.20E+00 3.60E+00 I.00E+0O 2.60E+01 3.90E+00 1.40E+03 1.30E+OI 7.40E+00 2.50E+0O L.30E+I01 1.50E+01 8.20E+O0 8.60E+00 7.60E+00 4.70E+00
- 2. 1OE+OI 3.60E+00 1.40E+03 1.40E+01 8.OOE+00 L.90E+0O 1.40E+01 1.IOE+OI 5.20E+O0 8.40E+00 7.50E+00 6.40E+00 1.90E+01 3.00E+00 l.00E+03 1.60E+01 7.60E+00 1.70E+01 1.40E+0O 1.60E+01 4.20E+00 4.30E+00 4.70E+00 4.60E+00 1.60E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-75
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data END CONC STATION LSN DATE NUCLIDE (pCi/L)
SAMPLE TYPE STD.DEV.
(pCi/L)
MDC (pCi/L) ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L6992-07 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7175-08 52 L7341-08 52 L7341-08 52 L734 I -08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7341-08 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 2t25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 3/2912004 3/29/2004 3/29/2004 3/29/2004 3/29/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 4/26/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 5/25/2004 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 CO-5s Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-5s Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1.63E+01
-.50E+02 8.OOE+00 4.00E-01
-2.90E+O0
-1.60E+O0
-1.20E+O0 2.101E+00 3.00E-01 S.00E-01 4.00E-01 3.30E+O0 8.20E+00
-4.00E+01 5.40E+00
-2.20E+00
-3.00E+00 3.30E+00
-2.20E+00 L.90E+00
-5.OOE-01
-1.70E+00 3.10E+00 2.20E+00 4.20E+00 3.00E+02 4.90E+00
-2.00E+00
-5.60E+O0 3.40E+00
-6.00E-01
-1.70E+O0 8.00E-0l
-3.30E+O0 2.20E+00 1.90E+00 4.80E+00
-4.70E+02 1.90E+00 2.30E+02 L.00E+01
. IOE+00 2.80E+O0 2.soE+O0 2.80E+O0 1.30E+00 L IOE+00 I. IOE-0-00 I. IOE+O0 3.30E+O0 1.40E+O0 3.30E+02 4.10E+00 L IOE+00 2.80E+00 2.1 OE+00 2.50E+00 1.30E+00 1.80E+00 1.70E+00 1.40E+00 4.20E+00 L.IOE+00 4.40E+02 4.20E+00 1.80E+00 3.60E+00 2.80E+00 4.70E+00 2.10E+00 1.70E+00 2.30E+00
- 2. 1OE+00 6.70E+00 1.20E+00 3.50E+02 3.90E+00 6.70E+02 3.50E+0O 4.20E+00 1.lIOE+0I 9.90E+00 I.lOE+0O 4.10E+O0 4.40E+O0 4.20E+00 4.00E+00 1.20E+0O 3.40E+00
- l. IOE+03 1.40E+0O 5.OOE+00 l.lOE+0O 6.90E+00 1.20E+01 4.40E+00 7.20E+00 7.00E+00 4.30E+00 1.60E+01 2.90E+00 1.30E+03 1.60E+01 7.20E+00 I.SOE+0O 9.60E+00 2.00E+0O 8.80E+00 7.00E+00 1.00E+01 7.20E+00 2.60E+0O 3.20E+O00 1.20E+03
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-76
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE END TYPE STATION LSN DATE CONC (pCi/L)
STD.DEV.
MDC (pCi/L)
(pCi/L)
NUCLIDE ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww 52 L7471-07 52 L7471-07 52 L7471-07 52 L7471-07 52 L7611-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L761 I-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L7611-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7643-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 52 L7840-08 5/25/2004 5/25/2004 5/25/2004 5/25/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/23/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 6/28/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 7/29/2004 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 CD-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 7.soE+00
-2.90E+00 O.OOE+00
-I.OOE-01 1.80E+00
-2. IOE+00
-7.00E-01
-2.70E+00
-1.OOE+00
-5.60E+00 4.00E+00 O.OOE+00 1
.soE000 1.80E+00 4.90E+00
-3.00E-0I
-5.20E+00 1.90E+00
-1.40E+00 2.90E+00
-3. IOE+00
-2.00E+00 5.40E+00
-2. 10E+02 4.70E+00
-2.70E+00
-7.00E+00 2.00E-01 4.60E+00
-4.90E+00
-2.00E-01
-1.30E+00
-3.OOE-01
-6.00E-01 7.80E+00
-1 30E+02 1.60E+00
-5.OOE-01 4.90E+00 I.70E+00 3.30E+00 3.60E+00 3.60E+00 I.SOE+00 1.80E+00 1.60E+00
.40E+00 4.60E+00 I.20E+00 4.60E+02 3.70E+00 L.SOE+00 3.SOE+00 2.60E+00 3.70E+00 2.10E+00 2.OOE+00 2.20E+00 2.40E+00 4.60E+00 1.20E+00 4.00E+02 3.40E+00 1.SOE+00 4.20E+00 3.50E+00 2.70E+00 1.50E+00 1.60E+00 1.60E+00 1.70E+00 5.OOE+00 1.30E+00 5.SOE+02 3.20E+00 1.30E+00 1.60E+0I 8.IOE+00 1.40E+0I 1.40E+0O 1.40E+01 6.30E+00 7.OOE+00 7.00E+00 5.70E+00 2.00E+01 3.60E+00 1.40E+03 1.30E+0I
- 5.
IOE+00 1.20E+0O l.OOE+0I 1.80E+01 7.SOE+00 9.SOE+00 7.SOE+00 l.00E+01 2.20E+0O 3.20E+00 1.30E+03
- 1. IOE+01 7.90E+00 2.10E+0I 1.40E+0I 8.SOE+00 7.00E+00 6.30E+00 6.40E+00 6.20E+00 1.90E+0I 3.1OE+00 1.80E+03 I. IOE+OI 5.20E+00
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-77
Yankee Nuclear Power Station Annual Radiological Environmental Operating Report 2004 Radiological Environmental Monitoring Program Summary of 2004 Data SAMPLE TYPE END STATION LSN DATE NUCLIDE CONC (pCiIL)
STD.DEV.
(pCi/L)
MDC (pCi/L) ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww ww 52 L7840-08 7/29/2004 52 L7840-08 7/29/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 8/27/2004 52 L7980-08 827/2004 52 L7980-08 8/27/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9(22/2004 52 L8 121-08 9(22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8121-08 9/22/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 52 L8352-08 10/27/2004 Zn-65 Zr-95 Ba-140 Co-58 CobO Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GROSS BETA H-3 1-131 Mn-54 Zn-65 Zr-95 7.90E+00 2.80E+00
-2.30E+00
-9.OOE-01 6.00E-O1 1.20E+O0
-1.00E+00 7.20E+00 6.50E+00 1.80E+02 2.60E+O0
-9.OOE-01
-7.20E+00
-8.OOE-01 4.60E+0o
-1.30E+00
- 6. 1OE+00 1.40E+00
-2.60E+00 1.80E+00 7.40E+00 3.40E+02
-2.20E+00 3.OOE-O1 4.70E+00
-3.60E+O0 2.00E+O0 2.30E+00 1.70E+00
-1.60E+00 6.OOE-0I
-4.80E+o0 7.00E+00 5.00E+01
-7.00E-01 3.70E+00
-4.70E+00 1.70E+O0 6.SOE+00 2.70E+O0 2.00E+00 I.501E+00 1.70E+00 1.SOE+00 1.70E+00 4.60E+00 1.20E+O0 4.70E+02 2.90E+00 1.60E+00 4.00E+0O 2.90E+0O 4.40E+00 2.40E+00 2.30E+00 2.50E+00 1.70E+00 4.80E+00 1.20E+00 4.60E+02 4.60E+00
- 2. 1OE+00 4.70E+00 3.20E+00 3.OOE+00 2.20E+00 1.80E+00 2.90E+O0 2.20E3+00 4.80E+00 1.20E+0O 3.30E+02 4.70E+0O 1.50E+00 4.1OE+00 3.40E+00 2.20E+01 9.20E+00 9.90E3+00 6.40E+00 6.60E+0O 5.50E+00 6.90E+0O 1.SOE+Ol 3.10E+0O 1.40E+03 1.00E+01 6.40E+0O 1.80E+01 1.20E+Ol L.SOE+O1 9.60E+00 5.60E+00 9.00E+00 7.90E+00 2.00E+01 3.00E+00 1.40E+03 1.80E+01 8.101E+00 1.70E+01 1.40E+01 1.30E+01 7.80E+00 7.00E+00 1.20E+01 8.70E+00 2.60E1+O1 2.80E+00 1.00E+03 1.80E+01 1.70E+00 2.00E+01 1.30E+01
- Radioactivity detected in sample (i.e., concentration > 3 X standard deviation)
+ Minimum Detectable Concentration > Lower Limit of Detection Requirement C-78