ML021280290
| ML021280290 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/23/2002 |
| From: | Kay J Yankee Atomic Electric Co |
| To: | Document Control Desk, NRC/FSME |
| References | |
| -RFPFR, BYR 2002-026 | |
| Download: ML021280290 (109) | |
Text
YANKEE A TOMIC ELECTRIC COMPANY Suite 200, 19 Midstate Drive, Auburn, Massachusetts 01501 CeANKIEE April 23, 2002 BYR 2002-026 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
Subject:
(a)
License No. DPR-3 (Docket No. 50-29) 2001 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the 2001 Annual Radiological Environmental Operating Report. This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Yankee Atomic Electric Company (YAEC) in the vicinity of the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts. This information is submitted in accordance with YNPS Defueled Technical Specification 6.8.2.a.
We trust this information is satisfactory; however, if you have any questions, please contact me at (978) 568-2302.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY James A. Kay Manager of Regulatory affairs Enclosure c:
J. Hickman, USNRC, Project Manager R. B. Bellamy, USNRC, Region I (192<;
Telephone (508) 721-7736 Facsimile (508) 721-7743
YANKEE A TOMIC ELECTRIC COMPANY Suite 200, 19 Midstate Drive, Auburn, Massachusetts 01501 AkaK-EE April 23, 2002 BYR 2002-026 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
Subject:
(a)
License No. DPR-3 (Docket No. 50-29) 2001 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the 2001 Annual Radiological Environmental Operating Report. This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Yankee Atomic Electric Company (YAEC) in the vicinity of the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts. This information is submitted in accordance with YNPS Defueled Technical Specification 6.8.2.a.
We trust this information is satisfactory; however, if you have any questions, please contact me at (978) 568-2302.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY James
. Kay Manager of Regulatory affairs Enclosure c:
J. Hickman, USNRC, Project Manager R. B. Bellamy, USNRC, Region I Telephone (508) 721-7736 Facsimile (508) 721-7743
YANKEE A TOMIC ELECTRIC COMPANY CeANKEE)
Suite 200, 19 Midstate Drive, Auburn, Massachusetts 01501 April 23, 2002 BYR 2002-026 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
Subject:
(a)
License No. DPR-3 (Docket No. 50-29) 2001 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the 2001 Annual Radiological Environmental Operating Report. This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Yankee Atomic Electric Company (YAEC) in the vicinity of the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts. This information is submitted in accordance with YNPS Defueled Technical Specification 6.8.2.a.
We trust this information is satisfactory; however, if you have any questions, please contact me at (978) 568-2302.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY James A. Kayý Manager of Regulatory affairs Enclosure c:
J. Hickman, USNRC, Project Manager R. B. Bellamy, USNRC, Region I Telephone (508) 721-7736 Facsimile (508) 721-7743
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT YANKEE ROWE STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1, 2001 - DECEMBER 31, 2001 DOCKET NO. 50-29 LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts
TABLE OF CONTENTS 1.0 EXECUTIVE SUM M AR Y..........................................................................................................................
1 2.0 IN TROD UCTION.......................................................................................................................................
2 2.1 G eneral Plant Site Inform ation..........................................................................................
2 2.2 Program D esign.......................................................................................................................
2 2.3 M onitoring Zones....................................................................................................................
3 2.4 Pathw ays M onitored.......................................................................................................
3 2.5 Descriptions of Monitoring Programs..............................................................................
4 2.5.1 Air Sam pling..................................................................................................................................
4 2.5.2 River W ater Sam pling....................................................................................................................
4 2.5.3 Ground W ater Sam pling.........................................................................................................
4 2.5.4 Storm Drain W ater Sam pling....................................................................................................
5 2.5.5 Sedim ent Sam pling........................................................................................................................
5 2.5.6 M ilk Sam pling...............................................................................................................................
5 2.5.7 Fish Sampling................................................................................................................................
5 2.5.8 Food Product Sampling.........................................................................................................
5 2.5.9 M aple Syrup Sam pling..................................................................................................................
6 2.5.10 TLD M onitoring............................................................................................................................
6 3.0 RADIOLOGICAL DATA
SUMMARY
TABLES...................................................................................
21 4.0 ANALYSIS OF ENVIRONMENTAL RESULTS................................................................................
34 4.1 Sam pling Program D eviations.........................................................................................
34 4.2 Comparison of Achieved LLDs with Requirements.....................................................
34 4.3 Results Compared Against Reporting Levels................................................................
34 4.4 D ata A nalysis by M edia Type.........................................................................................
34 4.4.1 Air Particulates.............................................................................................................................
35 4.4.2 River W ater..................................................................................................................................
36 4.4.3 Ground W ater..............................................................................................................................
37 4.4.4 Storm Drain W ater.......................................................................................................................
38 4.4.5 Sedim ent......................................................................................................................................
39 4.4.6 M ilk.............................................................................................................................................
41 4.4.7 Fish...............................................................................................................................................
41 4.4.8 Food.............................................................................................................................................
42 4.4.9 M aple Syrup................................................................................................................................
42 4.4.10 Direct Radiation...........................................................................................................................
43 5.0 OFF-SITE DOSE EQUIVALENT COMMITMENTS.......................................................................
46
- 6. 0 REFEREN CES.........................................................................................................................................
47 APPENDIX A - LAND USE CENSUS FOR 2001..........................................................................................
A-I APPENDIX B - QUALITY CONTROL PROGRAM...................................................................................
B-i APPENDIX C -
SUMMARY
OF 2001 REMP DATA..................................................................................
C-i ii
Annual Radiological Environmental Operating Report 2001 1.0 EXECUTIVE
SUMMARY
The radiological environmental monitoring program for the Yankee Rowe Nuclear Power Station was continued for the period January through December 2001, in compliance with the Technical Specifications and the Off-Site Dose Calculation Manual (ODCM). This annual report was prepared for the Yankee Atomic Electric Company (YAEC) by the Radiological Engineering Group of Duke Engineering and Services (DE&S). Sample collection and preparation was performed by Normandeau Associates. Gamma exposure rate measurements and laboratory analyses were performed by Duke Engineering and Services Environmental Laboratory (DESEL).
Thermoluminescent dosimeters (TLDs) were used to measure direct gamma exposure in the vicinity of the station and as far away as 22.2 miles. Radiochemical and radiological analyses of samples were performed to detect the presence of any station-related radioactivity. Samples collected include air-particulate filters, milk, broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, and fish. In evaluating the results of these analyses it is necessary to consider the variability of natural and man-made sources of radioactivity, distribution in the environment and uptake in environmental media. This variability is dependent on many factors including station release rates, past spatial variability of radioactive fallout from nuclear weapons tests and on-going redistribution of the fallout, contribution from cosmically produced radioactivity, 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 Rowe was permanently shutdown in 1991. Primary activities at the Yankee Rowe station are now focused on fuel storage, site decontamination and facility decommissioning. Even though the station is no longer generating power, decommissioning activities include processing and discharging of liquids containing radioactivity and monitoring for any release of airborne radioactivity. However, the levels of radioactivity released are significantly lower than releases during plant operation. The radiological monitoring of the environment through this program will continue to assure the health and safety of the public and workers are maintained at all times.
The predominant radioactivity detected by the monitoring program was that from outside sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As typical of previous years, station-related radioactivity was observed at some of the monitoring locations. The specific observations of station effects were tritium in ground water and Cobalt-60 in two bottom sediment samples. Air sample results demonstrated that no plan related airborne particulate activity was found.
As usual, Strontium-90 was measured in milk. This was measured at the control location in Williamstown, MA, 21 krn from the plant. The levels are a result of nuclear weapons testing in the 1960s and not the result of station decommissioning operations. This can be concluded because an insufficient quantity of this isotope has been released by the station to account for the measured concentrations. Higher levels of Strontium-90 were detected prior to initial plant operation and have been declining since the ban on nuclear weapons testing in the 1960s.
During 2001, there were no changes made to the radiological environmental monitoring program. The ODCM was revised to reflect the abandonment of the meteorological tower and the move to use 5-year meteorological averages.
1 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001
2.0 INTRODUCTION
2.1 General Plant Site Information The Yankee Nuclear Power Station (YNPS) is located on a 2200-acre site in a predominantly rural area of northwestern Massachusetts, three-quarters of a mile south of the Vermont border. The plant 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, has 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 Administration.
The radiological environmental monitoring program for YNPS continued during 2001 and will continue throughout the decommissioning period until its 10CFR50 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 station effluent controls and monitoring systems.
"* To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
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 due to the relatively low quantities of radioactive material now on the site, some of the objectives have a different degree of importance than in the past.
2 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 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 Specifications for 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 the direct radiation, airborne, waterborne, and ingestion pathways. Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:
Airborne Pathway Air Particulate Sampling Waterbome Pathways River Water Sampling 3
Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Ground Water Sampling Storm Drain Water Sampling Sediment Sampling Ingestion Pathways Milk Sampling Fish Sampling Food Product (fruits & vegetables, broad leaf vegetation) and Maple Syrup Sampling Direct Radiation Pathway TLD Monitoring 2.5 Descriptions of Monitoring Programs Sample types and frequency of analysis are given in Table 2.1. The sample locations are listed in Table 2.2 and Table 2.3 and shown in Figures 2.1 - 2.6. 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:
2.5.1 Air 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.
Airbome 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 DESEL before being analyzed for gross-beta radioactivity (indicated as GR-B in the data tables). The biweekly filters are composited by location at the DESEL for a quarterly gamma spectroscopy analysis.
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. Grab samples are collected monthly at Sherman Pond and at one upstream location. All river water samples are preserved with HC1 and NaHSO3, or HNO3, to prevent the plate out of potentially present radionuclides on the container walls. Each sample is analyzed for gross-beta and gamma-emitting radionuclides. The monthly samples are composited quarterly by location at the DESEL 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 4
Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 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 from the East and West Storm Drain. 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. Neither storm drain network is directly connected to any plant operation. 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 DESEL. At the DESEL, 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 Milk Sampling Milk samples are collected monthly from one control location. Immediately after collection, the milk sample is preserved with an appropriate amount of formaldehyde. The sample is analyzed for gamma-emitting radionuclides.
Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on quarterly composite samples.
2.5.7 Fish Sampling Fish samples are collected semiannually at two locations (upstream of the plant and in Sherman Pond). A gill net is set ovemight 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. The fish samples are frozen and delivered to the DESEL where the edible portions are analyzed for gamma-emitting radionuclides.
2.5.8 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, based on 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 DESEL for gamma-emitting radionuclides.
5 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 2.5.9 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 or three 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. 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 DESEL 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.
2.5.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs).
Specifically, Panasonic UD-801AS1 and UD-814AS1 calcium sulfate dosimeters are used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-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 DESEL processes them.
6 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 TABLE 2.1 Radiological Environmental Monitoring Program (as required by ODCM Table 4.1)
Does not include General Site Area and Owner Controlled Area fence locations.
7 i~~~~
I
I I
I I
I I
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 TABLE 2.1 (Continued)
Radiological Environmental Monitoring Program (As required by ODCM Table 4.1)
- 4. Ingestion
- a. Milk
- b. Fish
- c. Food Products Tuberous or above ground vegetables, or fruit I.
2 3
Grab Grab Grab Monthly Semiannually (or seasonal if appropriate)
At harvest Gamma Isotopic Gamma Isotopic on edible portions Gamma Isotopic on edible portion See Table 4.1 in ODCM.
8 Each sample Each sample Each sample
Annual Radiological Environmental Operating Report 2001 TABLE 2.2 Radiological Environmental Monitoring Locations (non-TLD) in 2001 Yankee Nuclear Power Station Station Description Observation Stand Monroe Bridge Rowe School Harriman Station Williamstown, MA YAEC Visitor's Center Distance From Plant Type (km)
I I
I I
C I
0.5 1.1 4.2 3.2 22.2 0.8
- 2.
Waterborne
- a.
- b.
Ground WG-11 WG-12
- c.
Storm Drain WW-51 WW-52
- d.
Sediment SE-11 SE-21 SE-91 Bear Swamp Lower Harriman Reservoir Sherman Pond Plant Potable Sherman Spring East Storm Drain West Storm Drain No. 4 Station Harriman Reservoir Sherman Pond I
C I
I I
I I
I C
I 6.3 10.1 0.1 On-site 0.2 On-site On-site 36.2 10.1 0.1
- 3.
Ingestion
- a.
Milk
- b.
Fish a
b TM-2 Ib FH-11 FH-21 Williamstown, MA Sherman Pond Harriman Reservoir C
21 I
1.5 C
10.1 I=Indicator Station, C=Control Station.
No sampling location is available within five miles.
9 Exposure Pathway
W SW Down-river Up-river N
NW Down-river Up-river N
WSW Near Discharge Up-river Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE 2.2 (Continued)
Radiological Environmental Monitoring Locations (non-TLD) in 2001 Yankee Nuclear Power Station Exposure Pathway Station Code Food Products TF-1I TF-13 TF-21 MS-33 (Maple Syrup)
MS-45 (Maple Syrup)
Station Description Monroe Bridge, MA Monroe, MA Williamstown, MA Rowe, MA Florida, MA Distance From Plant T
(kmrn)
C I
1.3 1.9 21.0 1.0 C
10.5 a
I=Indicator Station, C=Control Station.
10 Direction From Plant SW WNW WSW S
WSW Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE 2.3 Radiological Environmental Monitoring Locations (TLD) in 2001 Yankee Nuclear Power Station GM-I YAEC Visitors' Center 1
0.8 SW GM-2 Observation Stand 1
0.5 NW GM-3 Rowe School 1
4.2 SE GM-4 Harriman Station I
3.2 N
GM-5 Monroe Bridge I
1.1 SW GM-6 Readsboro Road Barrier I
1.3 N
GM-7 Whitingham Line 1
3.5 NE GM-8 Monroe Hill Barrier 1
1.8 S
GM-9 Dunbar Brook I
3.2 SW GM-10 Cross Road I
3.5 E
GM-I l Adams High Line I
2.1 WNW GM-12 Readsboro, VT I
5.5 NNW GM-13b Restricted Area Fence F
0.08 WSW GM-14b Restricted Area Fence F
0.11 WNW GM-15b 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-I 8b Restricted Area Fence F
0.14 ESE GM-1 9 b Restricted Area Fence F
0.16 SE GM-20b Restricted Area Fence F
0.16 SSE GM-21b 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 = Fenceline TLD.
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.
11 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE 2.3 (Continued)
Radiological Environmental Monitoring Locations (TLD) in 2001 Yankee Nuclear Power Station (iM-31 GM-32 GM-33 GM-35 GM-36 GM-38 GM-40 Legate HIll Road Rowe Road Zoar Road Whitcomb Summit Tilda Road West Hill Road Readsboro Road U
0 0
0 0
0 I
7.6 7.9 6.9 8.6 6.6 6.6 0.5 a
I = Indicator TLD; C = Control TLD; 0 = Outer Ring TLD; F = Fenceline TLD.
12 S
SSW WSW W
NW W
Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE 2.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements from ODCM Table 4.3 GrossBeta 4
H-3 2000 Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Additional explanatory footnotes are given in ODCM Table 4.3.
13 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 TABLE 2.5 Reporting Levels for Radioactivity Concentrations In Environmental Samples from ODCM Table 4.2 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 60 1000 Cs-137 50 20 2000 70 2000 Reporting Level for non-drinking water pathways.
14
Annual Radiological Environmental Operating Report 2001 Figure 2.1 Radiological Environmental Sampling Locations Within 1 Mile of Yankee Rowe Nuclear Power Station Nt Vermont
.......... r. o.?...
Massachusetts Sherman Pond/
AP-';
YNPS WW-51
&52AWG-11 TF-11 AP-31 Derfield River Meters S0 200 15 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Figure 2.2 Radiological Environmental Sampling Locations Within 12 Miles of Yankee Rowe Nuclear Power Station 16 e
Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 3
Figure 2.3 Radiological Environmental Sampling Locations Outside 12 Miles of Yankee Rowe Nuclear Power Station UN n rima n Reservoir xVermont II A
Meterst MEE:: 500 lo 17I0 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 I
Figure 2.4 Environmental TLD Monitoring Locations Within 1 Mile of Yankee Rowe Nuclear Power Station I
"I N
-- J N
NN NNE "NW NE
- Vermont, GM 6
'....Massachuseits.......
WNW
/ENE III
.h
, G M -
.J..
U" "ESE Deerfleld -,iver SW$
SSW A GM-8 22 Meters 0
200 18
Annual Radiological Environmental Operating Report 2001 Figure 2.5 Environmental TLD Monitoring Locations Within 12 Miles of Yankee Rowe Nuclear Power Station 4NNW N
NNE NW A
NE arrima eserv*jr "GM-25 VGM-I WNW xA GM-4:!'
ENE "A"
GM8 "A
SEE ENIERGEM T
IN F*bURP.2.5
""-7 11
.GM GM-..
Jr-Vermont M-------------*-.-.....Gn M
assachusetts S.....4I-
.i NNPGMlO-10:
Bear aLower r
WS
'33
- "" /GM-3*
MohawkfTrail SW iSS E
0 2o 0.0b 400 Yankee Rowe Station 19
Annual Radiological Environmental Operating Report 2001 Figure 2.6 Environmental TLD Monitoring Locations Outside of 12 Miles from Yankee Rowe Nuclear Power Station 20 e
Yankee Rowe Station C-W
Annual Radiological Environmental Operating Report 2001 3.0 RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples that were collected during 2001. 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. The units for each media type are also given. 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 2001, 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" measurements. 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 2001 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: 1) 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 DESEL in a gamma spectroscopy analysis are: Th 232, Ag-I l0m, Ba-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, 1-131, 1-133, K-40, Mn-54, Mo-99, Np-239, Ru-103, Ru-106, Sb-124, Se-75, TeI-132, Zn-65 and Zr-95. In no case did a 21 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 radionuclide not shown in Table 3.1 appear as a "detectable measurement" during 2001.
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.
22
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Air Particulates (AP)
UNITS: pCi/cubic meter Indicator Stations Radionuclides*
(No. Analyses)
(Non-Routine**)
Mean Required (Range)
LLD (No. Detected***1 Station With Highest Mean Sta. Mean (Range)
(No. Detected*-)
Control Stations Mean (Range)
(No. Detected-)
GR-B (174)
(0)
Be-7 (24)
(0)
Co-58 (24)
(0)
Co-60 (24)
(0)
Cs-134 (24)
(0)
Cs-1 37 (24)
(0) 0.01 0.05 0.06 2.5E -2
(
9.2 -
51.6)E -3 (145/ 145) 8.0E -2
(
3.6 -
13.8)E -2 (20/
- 20) 2.2E -5
( -2.0 - 1.4)E -3 (0/ 20) 2.OE -4
( -1.4 -
1.0)E -3 (0/ 20) 6.7E -5
( -6.7 - 8.2)E -4 (0/ 20) 5.9E -5
( -9.0
- 9.1)E -4 (0/ 20) 12 3.2E -2
(
1.6 - 5.2)E -2 (29/
- 29) 12 1.1E -1
(
8.6 -
13.8)E -2 (4/
- 4) 11 3.5E -4
(
7.0 -
71.2)E -5 (0/
- 4) 13 8.8E -4 8.3 -
9.6)E -4 (0/
- 4) 31 2.1E -4
( -1.8 6.4)E -4 (0/ 4) 13 6.2E -4
(
1.5 -
9.1)E -4 (0/
4) 2.4E -2
(
1.3 -
3.4)E -2 (29/ 29) 8.3E -2
(
5.1 -
11.1)E -2 (4/
- 4)
-2.2E -4
( -6.0 -
3.6)E -4 (0/
- 4)
-6.1E -5
( -1.9 -
1.5)E -4 (0/
- 4) 0.0E 0
( -4.1 - 2.6)E -4 (0/
- 4) 2.4E -5
( -3.2 -
3.5)E -4 (0/
4)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
23 LLD (No. Detected-)
Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: River Water (WR)
UNITS: pCilkg Indicator Stations Radionuclides*
(No. Analyses)
(Non-Routine**)
Mean Required (Range)
LLD (No. Detected-)
Station With Highest Mean Sta. Mean (Range)
(No. Detected-*)
Control Stations Mean (Range)
(No. Detected*-)
4 1.5E 0
(
2.4 - 34.0)E -1 (10/
25) 2000 3.OE 2
-5.7 -
11.4)E 2 (0/
9)
GR-B (37)
(0)
H-3 (13)
(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-1 34 (38)
(0)
Cs-1 37 (38)
(0)
Ba-140 (38)
(0) 11 1.6E 0
(
2.4 -
34.0)E -1 (5/
- 13) 11 4.3E 2
( 2.0 -
6.7)E 2 (0/
- 4) 91 5.8E -1 (0/
- 1) 91 2.OE 0 (0/ 1) 21 1.6E 0
( -5.5 -
10.2)E 0 (0/
- 12) 91 2.1E 0 (0/
- 1) 21
-1.4E 0
( -6.4 -
9.4)E 0 (0/
- 12) 91 1.1E 0 (0/
1) 91 3.OE 0 15
-1.1E -1
( -2.8 -
2.4)E 0 (0/
- 26) 15
-6.2E -1
( -4.9 -
2.0)E 0 (0/
- 26) 1.1E -1
( -9.0 -
6.9)E 0 (0/
- 26) 15
-1.9E -2
( -2.7 - 3.4)E 0 (0/
- 26) 30
-2.4E 0
( -7.1 -
10.9)E 0 (0/ 26) 15
-4.4E -1
( -8.1 - 2.6)E 0 (0/ 26)
-7.6E -1
( -7.7 - 3.0)E 0 (0/ 26) 15
-1.7E -1
( -2.9 - 2.8)E 0 (0/
- 26) 18
-8.8E -1
( -5.7 - 2.8)E 0 (0/
- 26)
-5.5E -1
( -1.0 - 0.4)E 1 (0/
26)
(0/
1) 1.5E 0
(
5.1 -
23.5)E -1 (5/
- 12) 1.4E 2
( -2.1 - 5.6)E 2 (0/
- 4) 8.8E -3
( -1.3 - 1.3)E 0 (0/
- 12)
-4.4E -1
( -2.2 - 1.3)E 0 (0/
- 12) 1.6E 0
( -5.5 -
10.2)E 0 (0/
- 12)
-2.0E -1
( -1.9 -
3.8)E 0 (0/ 12)
-1.4E 0
( -6.4 -
9.4)E 0 (0/
- 12)
-9.7E -1
( -5.7 - 3.7)E 0 (0/
- 12)
-1.4E 0
( -5.9 - 3.5)E 0 (0/
- 12) 7.5E -1
-8.1 -
23.6)E -1 (0/
- 12)
-1.1E 0
-4.2 -
1.4)E 0 (0/
- 12)
-9.3E -2
-2.4 - 2.6)E 0 (0/
12)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
24 (0/
- 1) 21 7.5E -1
-8.1 -
23.6)E -1 (0/
- 12) 91 4.3E -1 (0/
- 1) 91 3.5E 0 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Ground Water (WG)
UNITS: oCilka Indicator Stations Radionuclides*
(No. Analyses)
(Non-Routine**
Mean Required (Range)
LLD (No. Detected-)
Station With Highest Mean Sta. Mean (Range)
(No. Detected~***
Control Stations Mean (Range) 4 2000 3.9E 0
(
1.8 -
6.9)E 0 (22/ 24) 5.2E 1
-1.3 - 3.7)E 2 (2/ 24)
GR-B (24)
(0)
H-3 (24)
(0)
Mn-54 (24)
(0)
Co-58 (24)
(0)
Fe-59 (24)
(0)
Co-60 (24)
(0)
Zn-65 (24)
(0)
Zr-95 (24)
(0) 1-131 (24)
(0)
Cs-1 34 (24)
(0)
Cs-1 37 (24)
(0)
Ba-140 (24)
(0) 12 4.7E 0
(
2.4 -
6.9)E 0 (11/ 12) 12 1.4E 2
( -6.9 -
37.4)E 1 (2/
- 12) 11
-6.4E -2
( -2.5 -
2.0)E 0 (0/
- 12) 12
-1.1E -1
( -1.8 - 2.0)E 0 (0/
- 12) 12 7.7E -1
( -3.2 - 7.8)E 0 (0/
- 12) 12 4.OE -1
( -2.7 -
2.6)E 0 (0/
- 12) 12 2.OE -1
( -6.4 - 7.4)E 0 (0/
- 12) 12 6.OE -1
( -3.4 - 4.8)E 0 (0/
- 12) 11 9.1E -1
( -2.0 -
4.2)E 0 (0/
- 12) 12
-9.2E -2
( -4.3 - 2.5)E 0 (0/
- 12) 12
-9.9E -1
( -3.9 - 1.0)E 0 (0/
- 12) 12 8.1E -1
( -2.8 - 6.3)E 0 (0/
12)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
25 15
-2.5E
-1
-2.5 - 2.0)E 0 (0/
- 24) 15
-1.1E 0
-5.1 -
2.0)E 0 (0/ 24) 4.7E -2
( -6.7 - 7.8)E 0 (0/
- 24) 15 2.8E -1
( -2.7 - 2.6)E 0 (0/
- 24) 30
-8.7E -1
( -6.4 -
7.4)E 0 (0/
- 24) 15 5.1E -2
( -4.9 -
4.8)E 0 (0/
- 24) 6.1E -1
-1.6 - 0.9)E 1 (0/ 24) 15
-2.9E -1
( -4.3 - 2.5)E 0 (0/
- 24) 18
-1.1E 0
( -4.7 -
2.3)E 0 (0/ 24) 4.4E -1
( -3.2 -
6.3)E 0 (0/ 24)
NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA (No. Detected-I iNo Detected-'
Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Storm Drain Water (WWV)
UNITS: oCilka Indicator Stations Radionuclides*
(No. Analyses)
(Non-Routine*)
Mean Required (Range)
LLD (No. Detected**)
Station With Highest Mean Sta. Mean (Range)
(No. Detected***
Control Stations Mean (Range)
(Non D~t.t*.d 4
7.7E 0
(
2.2 -
14.5)E 0 (22/ 24)
GR-B (24)
(0)
H-3 (24)
(0)
Mn-54 (24)
(0)
Co-58 (24)
(0)
Fe-59 (24)
(0)
Co-60 (24)
(0)
Zn-65 (24)
(0)
Zr-95 (24)
(0) 1-131 (24)
(0)
Cs-134 (24)
(0)
Cs-137 (24)
(0)
Ba-140 (24)
(0) 51 7.8E 0
(
2.2 -
14.5)E 0 (11/ 13) 52
-2.3E 2
-1.3 - 0.5)E 3 (0/
- 11) 52
-4.3E
-1
-1.3 -
0.9)E 0 (0/
- 11) 51
-7.0E -1
-3.1 -
0.8)E 0 (0/ 13) 52 1.1E 0
-5.3 -
8.5)E 0 (0/
- 11) 52 3.0E -1
-1.4 -
2.6)E 0 (0/
- 11) 52 7.4E -1
-5.6 -
15.6)E 0 (0/ 11) 52 1.0Z 0
-4.5 -
6.4)E 0 (0/ 11) 51 3.6E 0
-9.7 -
29.4)E 0 (0/
- 13) 52 2.0E -1
-2.1 - 2.9)E 0 (0/ 11) 52
-5.1E -1
-1.9 - 0.8)E 0 (0/ 11) 51 8.4E -1
-2.0 -
7.2)E 0 (0/
13)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
"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.
26 2000
-2.5E 2
-1.3 -
0.5)E 3 (0/
- 24) 15
-5.0E -1
-2.3 -
2.2)E 0 (0/
- 24) 15
-8.8E
-1
-3.1 - 0.8)E 0 (0/
- 24) 2.6E -1
-5.3 -
9.8)E 0 (0/
- 24) 15 8.7E -2
-3.4 -
2.6)E 0 (0/
- 24) 30 4.2E -1
-9.8 - 15.6)E 0 (0/
- 24) 15 5.7E -1
-4.5 - 6.4)E 0 (0/
- 24) 9.9E -1
-1.0 -
2.9)E 1 (0/
- 24) 15
-1.1E -1
-2.6 -
2.9)E 0 (0/
- 24) 18
-6.1E -1
-3.7 - 2.2)E 0 (0/
- 24) 7.9E -2
( -5.2 - 7.2)E 0 (0/
24)
NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA (N
Dee te (N
i I....
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIIJM: Sepdimc~nt (SE)
UNITS:
nCi/ka dry Radionuclides*
(No. Analyses)
(Non-Routine**)
Indicator Stations Mean Required (Range)
LLD (No. Detected*-)
Station With Highest Mean Sta. Mean (Range)
(No. Detected***
Control Stations Mean (Range)
(No
,etected I
,.(No D.t.
t.. d-.
9.7E 0
-1.8 -
2.3)E 2 (0/
- 12) 1.9E 4
(
1.2 - 2.6)E 4 (12/
- 12)
-1.OE 1
-5.1 - 1.4)E 1 (0/
- 12) 1.8E 1
-1.2 -
6.3)E 1 (2/ 12) 9.3E -1
-3.2 - 4.3)E 1 (0/
- 12) 8.3E 2
( 7.4 - 199.2)E 1 (9/
- 12) 1.5E 3
(
6.9 - 22.7)E 2 (12/
12) 11 1.2E 2
(
0.0 -
2.3)E 2 (0/
- 6) 91 2.5E 4
(
2.3 -
2.6)E 4 (6/
- 6) 11
-4.2E 0
( -3.5 -
1.4)E 1 (0/
- 6) 91 1.9E 1
( -5.8 -
53.2)E 0 (2/
- 6) 11 3.7E 0
( -3.2 -
4.3)E 1 (0/
- 6) 91 1.5E 3
(
1.1 - 2.0)E 3 (6/
- 6) 91 2.OE 3
(
1.8 - 2.3)E 3 (6/
6)
-3.9E 1
-1.4 -
0.9)E 2 (0/
- 6) 1.5E 4
(
1.3 -
1.8)E 4 (6/
- 6)
-6.2E 0
( -2.4 - 1.2)E 1 (0/
- 6) 1.6E 0
( -2.8 -
2.2)E 1 (0/
- 6) 9.1E -1
( -1.2 -
1.0)E 1 (0/
- 6)
-2.1E 0
( -6.3 - 3.8)E 1 (0/
- 6) 2.8E 2
( -3.2
- 4.7)E 2 (5/
6)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
27 Be-7 (18)
(0)
K-40 (18)
(0)
Co-58 (18)
(0)
Co-60 (18)
(0)
Cs-1 34 (18)
(0)
Cs-1 37 (18)
(0)
Th-232 (18)
(0) 150 180 (SE)
UNITS: oCi/ka drv MEDIUM: Sediment Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Milk (TM)
UNITS: pCi/kg Indicator Stations Radionuclides*
(No. Analyses) t*IrnI.rn.
,tjna=**\\
Mean Required (Range)
LLD (No. Detected***)
Station With Highest Mean Sta. Mean (Range)
(Non D*.t*.dd****
Control Stations Mean (Range)
NO DATA NO DATA NO DATA NO DATA 15 NO DATA 18 NO DATA NO DATA K-40 (12)
(0)
Sr-89 (4)
(0)
Sr-90 (4)
(0) 1-131 (12)
(0)
Cs-134 (12)
(0)
Cs-137 (12)
(0)
Ba-140 (12)
(0)
Th-232 (12)
(0) 21 1.4E 3
(
1.3 - 1.4)E 3 (12/ 12) 21 1.8E -1
( -5.0 -
6.8)E 0 (0/
- 4) 21 1.4E 0
(
6.6 - 28.9)E -1 (1/ 4) 21
-4.4E -2
( -5.4 - 4.0)E 0 (0/
- 12) 21 1.4E -1
( -1.5 - 2.2)E 0 (0/
- 12) 21 9.0E -1
( -1.5 -
6.4)E 0 (0/
- 12) 21 2.1E -1
( -3.7 - 2.7)E 0 (0/ 12) 21 3.3E 0
( -1.6 -
1.5)E 1 (0/
12) 1.4E 3
(
1.3 - 1.4)E 3 (12/ 12) 1.8E -1
( -5.0 - 6.8)E 0 (0/
- 4) 1.4E 0
(
6.6 -
28.9)E -1 (1/
- 4)
-4.4E -2
( -5.4 -
4.0)E 0 (0/
- 12) 1.4E -1
( -1.5 -
2.2)E 0 (0/
- 12) 9.OE -1
( -1.5 -
6.4)E 0 (0/
- 12) 2.1E -1
( -3.7 - 2.7)E 0 (0/
- 12) 3.3E 0
( -1.6 -
1.5)E 1 (0/
12)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
28 NO DATA LLD (No Detected* I INo Detected-'
I I IUI I--1%*ULlll*
J Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Fish (FH)
UNITS: oCilka Indicator Stations Radionuclides*
(No. Analyses)
(Non-Routine**)
K-40 (4)
(0)
Mn-54 (4)
(0)
Co-58 (4)
(0)
Fe-59 (4)
(0)
Co-60 (4)
(0)
Zn-65 (4)
(0)
Cs-1 34 (4)
(0)
Cs-137 (4)
(0)
Mean Required (Range)
LLD (No. Detected**)
2.9E 3
(
2.2 -
3.5)E 3 (2/
- 2) 130
-3.9E 0
( -9.6 -
1.7)E 0 (0/
- 2) 130 1.1E 1
(
7.4 - 15.6)E 0 (0/
- 2)
-2.2E 1
( -2.3 - -2.2)E 1 (0/
2) 130 260 130 8.3E 0 4.4 -
12.2)E 0 (0/
- 2)
-3.6E 1
-5.1 -
-2.1)E 1 (0/
- 2) 4.2E 0
( -1.1 -
9.5)E 0 (0/
2) 150 3.5E 1
(
3.1 -
3.9)E 1 (0/
2)
Station With Highest Mean Sta. Mean (Range)
(No. Detected**'
21 3.0OE 3
(
2.7 - 3.3)E 3 (2/
- 2) 21
-2.8E 0
( -1.4 - 0.8)E 1 (0/ 2) 11 1.1E 1
(
7.4 -
15.6)E 0 (0/
- 2) 21 2.6E 1
-2.2 - 7.5)E 1 (0/
- 2) 11 8.3E 0 4.4 - 12.2)E 0 (0/
- 2) 21
-1.1E 1
( -1.4 -
-0.8)E 1 (0/
- 2) 11 4.2E 0
( -1.1 - 9.5)E 0 (0/
- 2) 11 3.5E 1
(
3.1 -
3.9)E 1 (0/
2)
Control Stations Mean (Range)
(No. Detected**)
- 3. CE 3
(
2.7 -
3.3)E 3 (2/
- 2)
-2.8E 0
-1.4 - 0.8)E 1 (0/
- 2) 5.9E -2
-4.4 - 4.6)E 0 (0/
- 2) 2.6E 1
-2.2 - 7.5)E 1 (0/
- 2)
-2.9E -1
-1.5 - 1.4)E 1 (0/
- 2)
-1.1IE 1
-1.4 - -0.8)E 1 (0/
- 2)
-7.2E 0
-1.2 -
-0.3)E 1 (0/
- 2) 5.5E 0
-9.1 - 20.1)E 0 (0/ 2)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
29 (FH)
UNITS: pCi/k
- ~~N Detected-)....
Annual Radiological Environmental Operating Report 2001 Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Food Crop (TF)
UNITS: pCilkg Radionuclides*
(No. Analyses)
(Non-Routine**)
K-40 (3)
(0)
Co-58 (3)
(0)
Co-60 (3)
(0) 1-131 (3)
(0)
Cs-1 34 (3)
(0)
Cs-137 (3)
(0)
Indicator Stations Mean Required (Range)
LLD (No. Detected-)
4.9E 3
(
8.1 -
89.7)E 2 (2/
2)
-1.6E 1
( -2.4 -
-0.8)E 1 (0/
- 2)
-2.4E 1
( -2.6 - -2.2)E 1 (0/
- 2) 1.6E 0
-1.1 -
1.5)E 1 (0/
- 2) 60 1.7E 1 0.0 - 3.5)E 1 (0/
- 2) 80 1.1E 1 6.3 - 16.3)E 0 (0/
2)
Station With Highest Mean Sta. Mean (Range)
(No. Detected-)
11 9.OE 3 21
-1.4E 0 21
-5.1E 0 13 1.5E 1 11 3.5E 1 13 1.6E 1 (1/
- 1)
(0/
- 1)
(0/
- 1)
(0/ 1)
(0/ 1)
(0/ 1)
Control Stations Mean (Range)
INo. Detected-)
1.9E 3
-1.4E 0
-5. 1E 0 3.8E 0
-7.2E 0
3.0E 0 (U/ 1)
(0/ 1)
(0/ 1)
(0/ 1)
(0/ 1)
(0/ 1)
The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
30 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 Radionuclides*
(No. Analyses)
(Non-Routine*)
K-40 (2)
(0)
Co-58 (2)
(0)
Co-60 (2)
(0) 1-131 (2)
(0)
Cs-1 34 (2)
(0)
Cs-137 (2)
(0)
Table 3.1 Radiological Environmental Program Summary Yankee Nuclear Power Station, Rowe, MA (January - December 2001)
MEDIUM: Maple Syrup (MS)
UNITS: pCilkg Indicator Stations Station With Highest Mean Mean Sta. Mean Required (Range)
(Range)
LLD (No. Detected-)
(No. Detected-)
1.8E 3 33 1.8E 3 (U/ 1)
(U/ 1) 6.4E -2 45 3.6E -1 (0/ 1)
(0/ 1)
-2.9E 0 45
-1.4E 0 (0/ 1)
(0/
- 1) 2.1E 0 33 2.1E 0 (0/
- 1)
(0/ 1) 60 8.6E -1 45 1.1E 0 (0/ 1)
(0/ 1) 80 1.8E 1 33 1.8E 1 (1/ 1)
(U/ 1)
Control Stations Mean (Range)
(No. Detected*-*)
1.5E 3 3.6E -1 (0/
1
-1. 4E 0 (0/ 1
-4.9E 0 (0/ 1 1.1E 0 (0/ 1 1.4E 1 (1/
1 The radionuclides reported in this table are those with LLD requirements, those for which positive radioactivity was detected, or those that were of specific interest for any other reason.
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.
31
Annual Radiological Environmental Operating Report 2001 TABLE 3.2 ENVIRONMENTAL TLD DATA SUMMAR Y*
(JANUARY-DECEMBER 2001)
INDICATOR TLDs MEAN RANGE (NO. MEASUREMENTS)*
6.4 0.9 4.1 8.3 (51)
OUTER RING TLDs MEAN RANGE (NO. MEASUREMENTS)*
6.2
+/-
1.1 4.3 8.5 (36)
FENCELINE TLDs**
MEAN RANGE (NO. MEASUREMENTS)*
7.2
+
1.1 5.3 9.1 (36)
CONTROL TLDS MEAN RANGE (NO. MEASUREMENTS)*
7.0
- 0.8 5.2 7.7 (8)
OFFSITE STATION WITH HIGHEST MEAN STA.
NO.
MEAN RANGE (NO. MEASUREMENIrS)*
GM-38 7.5
+/-
1.3 5.9 8.5 (4)
- Each "measurement" is based on quarterly readings from five TLD elements. Measurement units are 11R/hr.
- Not part of REMP Program.
32 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 TABLE 3.3 2001 ENVIRONMENTAL TLD MEASUREMENTS*
(Micro-R per hour)
ANNUAL Sta.
I ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER AVE.
No.
Descrition EX..
SJD EXM.
MD E.
E EXP S
EXM_.
GM-01 YNPS Visitor's Center 5.6
+ 0.2 6.9
+/- 0.2 6.8
+/- 0.3 6.7
+/- 0.3 6.5 GM-02 Observation Stand 5.0 +/- 0.4 5.9
+/- 0.3 6.4
+/- 0.3 6.1
+ 0.3 5.8 GM-03 Rowe School 4.1
+ 0.2 5.6
+/- 0.3 5.3
+/- 0.2 5.3 0.3 5.1 GM-04 Harriman Station 4.9
+/- 0.3 5.8
+/- 0.2 5.5
+/- 0.3 5.7 4 0.3 5.5 GM-05 Monroe Bridge 6.6
+/- 0.2 7.3
+ 0.3 7.1
+/- 0.3 7.0
- 0.3 7.0 GM-06 Readsboro Rd. Barrier 5.3 4 0.3 6.9
+/-
0.4 7.3
- 0.4 7.3
+ 0.3 6.7 GM-07 Whitingham Line 5.8
+ 0.7 6.4
+/- 0.2 7.7 0.3 7.4
+ 0.3 6.8 GM-08 Monroe Hill Barrier 5.1
+/-
0.2 5.8 0.4 6.3
+ 0.3 6.2
+/- 0.3 5.8 GM-09 Dunbar Brook 5.3
+/- 0.3 6.9 0.3 7.3 0.4 7.1 0.3 6.7 GM-10 Cross Rd.
4.8
+/- 0.3 6.2 0.2 6.9
+/- 0.3 6.5 0.3 6.1 GM-Il Adams High Line 5.1 E 0.4 6.8 0.2 6.5 0.2 7.1 0.3 6.4 GM-12 Readsboro, VT 7.2
+/- 0.4 7.9
- E 0.3 8.3 4 0.5 7.8 0.5 7.8 GM-13 Indust. Area Fence 6.1
+/- 0.3 7.7
+/- 0.4 8.5 A
0.4 8.3 0.5 7.7 GM-14 Indust. Area Fence 5.6
+/- 0.4 7.1
+ 0.3 7.4 0.4 7.1
+ 0.3 6.8 GM-15 Indust. Area Fence 5.8
+/- 0.4 6.9
+/- 0.2 7.5 +/- 0.5 7.1
+ 0.3 6.8 GM-16 Indust. Area Fence 5.7
+/-
0.3 6.7
+/-
0.3 7.1
+/- 0.3 7.1
+/- 0.3 6.6 GM-17 Indust. Area Fence 5.7
+/- 0.7 6.9
+/- 0.4 7.7 0.4 7.6
+/- 0.3 7.0 GM-18 Indust. Area Fence 6.8
- E 0.4 8.1
+/- 0.3 8.9
+/- 0.3 9.0
+/- 0.3 8.2 GM-19 Indust. Area Fence 6.0
- E 0.2 7.3
+/- 0.2 8.8
+/- 0.3 9.1
+/- 0.3 7.8 GM-20 Indust. Area Fence 5.7
- h 0.3 7.4
+/- 0.2 8.7
+/- 0.3 8.7
+/- 0.4 7.6 GM-21 Indust. Area Fence 5.3
+/-
0.3 6.5
+/-
0.3 7.1
+/- 0.4 7.4
+/- 0.3 6.6 GM-22 Heartwellville, VT 5.2
- h 0.3 7.2
+/- 0.4 7.4 +/- 0.3 7.7
+- 0.4 6.9 GM-23 Williamstown Subst.
6.8
+/- 0.3 7.3
+/- 0.2 7.2
+/- 0.7 7.7
+/- 0.4 7.2 GM-25 Whitingham, VT 4.8
+ 0.3 5.8 4
0.3 6.5
+/- 0.3 5.9
+/- 0.4 5.8 GM-27 Number 9 Rd.
4.6
+/- 0.2 5.9 4 0.3 6.3
+/- 0.4 6.0
+/- 0.3 5.7 GM-29 Route 8A 4.3
- h 0.5 4.8 0.3 5.0
+/- 0.3 4.8
+/- 0.2 4.7 GM-31 Legate Hill Rd.
5.0
+/- 0.3 6.2
+/-
0.3 6.2
+/- 0.3 6.8
+/- 0.3 6.1 GM-32 Rowe Rd.
5.1
+/- 0.2 6.6 0.3 7.0 -
0.2 6.5 +/- 0.4 6.3 GM-33 Zoar Rd.
5.6
- h 0.2 6.3
- L 0.2 7.4
+/- 0.3 6.8
+/- 0.3 6.5 GM-35 Whitcomb Summit 5A
+/-
0.5 6.7
+/- 0.3 7.7 0.3 7.9 +/- 0.4 6.9 GM-36 Tilda Rd.
5.3
+/-
0.2 6.5
+/- 0.3 6.7 0.2 7.8
+/- 0.9 6.6 GM-38 West Hill Rd.
5.9
+ 0.3 7.1
+/- 0.3 8.4 0.5 8.5
+/- 0.5 7.5 GM-40 Readsboro Rd.
5.0
+/- 0.2 6.8 +/- 0.3 7.0
- 0.4 6.9
+/- 0.3 6.5
- Each "measurement" is based on quarterly readings from five TLD elements.
33
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 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 only one program deviation noted in the REMP during 2001:
April change-out of the first quarter TLD at station GM-05 (Monroe Bridge) indicated that the TLD reported as missing for the fourth quarter 2000 had actually been left out in the field for a six-month exposure period.
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 DESEL, 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 calculated for that analysis was compared with the required LLD. Of the more than 670 analyses performed with a specified LLD requirement, 99.7% met the requirements of Table 4.3 of the ODCM in 2001. Two storm drain samples for station 51 did not meet the required LLD. However, these samples are not a required part of the REMP as it is not a location specified in the ODCM.
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 2001, no Reporting Levels were exceeded.
4.4 Data Analysis by Media Type The 2001 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."
34
Yankee Rowe Station Annual Radiologioal Environmental Operating Report 2001 4.4.1 Air Particulates The biweekly air particulate filters from each of the six operating sampling sites were 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.
Mgme4-1 Qvw-Bd htlicannumts w Air ageiiate Filtes (Qiartery Avrgses) 0.05 004 i
a.002 0.0; 0.05 0.04 0.03 0.02 0.01 0
191 1Q19 196 1997
¶9 1599 200
")I As shown in Figure 4-1, there has been no significaut differeace 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 an air particulate filters fluctuate significantly over the course of a year. This is due principally to seasonal variations and the related effects on naturally occurrng tenestiril radionuclide emissions. The measements from ontrol 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 contral locations, further supporting this conclusion.
d-07 e
Annual Radiological Environmental Operating Report 2001 Figure 4-2 Bi-Weeldy Air Particulate Gross Beta Analysis Results 0.06 005 a 0.04 C
'4.
S0.03 0
- g 0.02 0.01 0
Jan-01 F4-01 Mar-l Apr.01 May-01 Jun-01 Jul-01 Aug-01 Sep-01 Oct-01 Nov-01 Dec-01 4.4.2 River Water Aliquots of river water were automatically collected every two hours from the Deerfield River downstream from the plant.
These composited samples were collected monthly and sent to the DESEL for analysis. Monthly grab samples were also collected at the Harriman Reservoir control location and at Sherman Pond near the discharge area.
Table 3.1 shows that gross-beta measureents were positive in fifteen of the thirty-seven samples collected, as would 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 dnring the last half of 1992 and 1998-1999 when the levels at WR-11 were slightly elevated relative to the control. This was attributed to naturally-occurring radioactivity and is discussed in the 1992, 1993, 1998, and 1999 Arnual Radiological Environmental Operating Reports.
36 Yankee Rowe Station
Annual Radiologieal Environmental Operating Report 2001 GýmaBeta Measuremnt of Ibwr Water (Ses-Anmnd Average) 6 3
2 1
0 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 200 2001 2002 No ganma-eminag radionuclides attributable to actvies at YNPS were detected in any of the samples. For each sampling site, the monthly samples were composited into quarterly samples for 14-3 analyses. No H-3 was detected in river water samples during 2001.
Beginning in July 1994, a split-sampling program was undertaken in cooperation with the Massachusetts Radiation Control Program (MCRP). Water samples are collected at the discharge point and then split with the MCRP, at their discretion.
During 2001, one sample was split and analyzed by the DESEL and the MCRP laboratory. A gamma spectroscopy and H-3 analysis was performed on the sample. No radioactivity was detected in the 2001 samples, as analyzed at the DESEL. In Figure 2.1 and Table 2.2, this sample location is in the same vicinity as WR-31. In the data collected in Table 3.1, this location is labeled as WR-91 to distinguish it from routine REMP samples collected from WR-3 1.
4.4.3 Ground Water Monthly ground water samples were collected from two on-site locations during 2001. (Only quarterly samples am requtred by ODCM Table 4.1.) Table 3.1 shows that gross-beta measurements were positive in most of the samples This is due to naturally-occurring radionuclides in the water.
37 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 Tritium was also detected in two of the samples from WG-12 (Sherman Springs). A steadily decreasing concentration of H-3 has been detected in previous years in Sherman Spring samples, as shown in Figure 4-4. The water from Sherman Spring leaves the ground on YNPS property and flows into the Deerfield River. Neither the Deerfield River nor Sherman Spring are used for drinking water.
No gamma-emitting radionuclides were detected in any of the ground water samples.
Figure 4-4 Tritium in Ground Water Station WG-12, Sherman Spring 1700 1200 700 200
-300
-800 1995 1996 1997 1998 1999 2000 2001 4.4.4 Storm Drain Water Monthly grab samples were collected from the East and West Storm Drains (WW-51 and 52) when available during 2001.
Each sample was analyzed for gross-beta and gamma-emitting radionuclides and H-3. Gross-beta measurements were positive in twenty-two of the twenty-four samples taken, as would be expected. The levels are consistent with those from previous years. No gamma-emitting radionuclides or H-3 were detected in any of the samples.
38 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 4.4.5 Sediment Semiannual sediment core samples were collected from three locations during 2001. Each set of samples was segmented by depth (0-5, 5-10,10-15 cm) and anabzed for gamma-emitfing radionuclides. As would be expected, naturally-occ uning K-40 and Th-232 were detected in most of the samples.
In addition to the naturally-occuringradionuclides, Cs-137 was detected in half of the segments. Theresiiltstromthe 0-5 cm depth segment from downstream location SE-l are consistent with what has been measured in previous years (see Figure 4-5) and is attributed to nuolearweapons testingfallout. The Cs-137 inthe 5-10 cm and 10-15 m depth segments at SE-Il are bounded by levels previously reported at the control location (SE-21). The levels andthe distribution of the Cs-137 in the core segments indicate nuclear weapons testing fallout as the origin. At both the indicator and the control location, the character of the sediment is highly dependent on the specific location sampled, which in tun is dependent on FIGURE 4-5 aESiurTWi IN SHOUIJNE SEDIMFENT SFTION.IWA 1 35i00 250.00 20.0O 100&.O 0.00
-50.00 05/97 10/97 05/98 1(98 05/99 10/99 05103 10/00 05/01 10JO1 NInthrlYer 130-5.a 05-10.a
[ 10-15orn c-10 39 e
Yankee RoweStation
Annual Radiological Environmental Operating Report 2001 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 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.
FIGURE 4-6 CESIUM-137 It SHORELINE S FDIMEhT STTJAON SE-21 500 400 300 200 100 0
6
-100 05/97 10197 05/98 10/98 05/99 10/99 05/00 10/00 05/01 10/01 Month!Ya 30-5 cm
- 5-10 cm 13 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 near the plant discharge in Sherman Pond. Although much of the Cs-137 in this sediment is due to global nuclear weapons testing fallout, some of the Cs-137 in these samples is likely due to effluents released from monitored plant discharges. It is believed that the higher Cs-137 levels at SE-91, whether due to fallout or plant effluents, are related to the physical make-up of the sediment (rich organic benthic layer) at the bottom of Sherman Pond.
Co-60 has also becn detected in the deep water sediment at SE-91. With respect to 2001 samples, the 0-5 om segment from the core taken in May 2001 at SB-91 showed a concentration of 53 + 10 pCi/kg-dry and the 10-15 cm segment showed a concentration of 48 + 14 pCi/kg-di3. This sample, as all others at SE-91, were collected in deep water, well away from the shoreline and is attributed to licensed plant discharges in past years. None of this radioactivily is involved in any significant pathway to exposure to man.
CAi 40 e
Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 FIGURE 4-7 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-91 4000 3500 3000 2500 e2000 1500 1000 500 0
10/97 05/98 10/98 05/99 10/99 05/00 10/00 05/01 10/01 Month/Year
[O*5 em
- 15.10 cr1 0 1 0-15 em 4.4.6 Milk Milk samples fiom cows at one control farm were collected montly (when available) during the year. The indicator farm sold its milking cows in August 1998, making indicator milk samples unavailable since this time. Each sample was analyzed for gamma-emitting radionuclides. Quarterly composites, by location, were analyzed for Sr-89 and Sr-90.
As expeoted, naturally-occurring K-40 was deteoted in all samples. Sr-90 was detected in one of the four composite samples.
The Sr-90 levels are consistent with those detected in previous years near YNPS and is indicative of the residual levels due to weapons testing fallout.
4.4.7 Fish Semiannual samples of fish were collected from two locations dming2001. The edible portions of each of these were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally-oacuring K-40 was detected in all samples.
No other gamma emitting radionuclides were detected in 2001 fish samples. The average Cs-137 concentrations shown in Figure 4-8 are not considered detectable or "positive" measurements. The wide variation in Cs-137 activity is primarily due to the different speieis of fish and the specific eating habits of the fish. Fish that are bottom feeders would tend to pick up more of the Cs-137 activity located in the water sediment.
41
Annual Radiological Environmental Operating Report 2001 FIGURE 4-8 CESIUM-137 IN FISH ANNUAL AVERAGE CONCENTRATIONS 60 50 40 20 10 0
191 1992 193 194 195 1996 1997 1998 1999 2000 2001 Year 4.4.8 Food Three food samples w=e collected during 2001 and analyzed for gamnma-emntting radionuclides, K-40 was detected in all three samples. No other gamma emitting radionuclides were detected in 2001 food samples.
4.4.9 Maple Syrup Processed maple syrup samples were collected from an indicator and control location during the month of April. These samples had been concentrated, relative to the original tree sap, by boiling (see Section 2.5.9). Naturally-occuning K-40 and Cs-137 were detected in both samples. The concentrations of Cs-137 in 2001 samples are consistent with that detected in both indicator and control samples in previous years, and is attributed to global nuclear weapons testing fallout.
C-42 e~
Yankee Rowe Station
Yankee Rowe Station Annual Radiological Envirnmental Operating Report 2001 4.4.10 Direct Radiation Direct radiation is continuously measured at 33 locations surromunding YNPS with the use of thernolumimescnt dosimeters (TLDs). These are collected every calendar quarter for readout at the DESEL.
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 toe winter months. This is duo primarily to the attenuating effect of the snow cover on radon emissions and on direct iradiation by naturally-occurring radionuclides m the soil. Differing amounts of these radionuclides in the underlying soil, rook or nearby building materials result in different radiation levels between one field site and another.
From Table 3.2 and 3.3, it can be seen that the mean exposure rates for the Indicator, Outer Ring, and Control categories Figure 4-9 10 5
0 1996 Exposure Rate at Indicator, Outer Ring and Control TLDs 1997 1998 1999 2000 2001 15 10 5
-0 2002 were not significantly different in 2001. This indicates that there was no significant overall increase in direct radiation exposure rates in the plant vicinity. As shown in Figures 4-10 through. 4-11, the levels in 2001 are consistent with or bounded by levels in previous years.
43 t
1 Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 U
The Fenceline TLDs shown in Figures 4-11 and summarized in Tables 3.2 and 3.3 are located on the fence surrounding the Radiation Control Area within the YNPS properly bounds, and are influenced by licensed plant activities. The Fencelme exposure rates have shown a declining trend as the decommissioning of the site has progressed.
Figure 4-10 1 i5 Exposwe Rate at Indicator TLDs, GM-01-GM-12 GM-- 1 yABC Vkisi C.t1
_GM_2002 en'aton Stnd G C-03 ROWb Scho ol 505 MoX/o B5idge
""M6)6 R9adsbom" Road 200 200 O--+- l
- iigam tine
- OM*08 MomoelHll BonierI GU-
¶(0os 10a I
I I
I I
- 1 44
Yankee Rowe Station C
Annual Radiologioal Environmental Operating Report 2001 Figure 4-11 Exposure Rate at Fenceine TLDs 0
1 1996 1997 199 45 2m0 "2I1 2M)2 0 _f&
e
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 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. This assessment utilizes actual measurements of the concentration of radioactivity in various environmental media (e.g., air, milk, fish) 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.
During 2001, there were a few instances where plant-related radioactivity was observed in environmental media. Station related tritium activity was observed in on-site well water. On-site well water is used for station processes and services, and is available for limited on-site human consumption. Comparing the maximum H-3 concentration observed (374 pCi/kg) to the EPA standard for tritium in drinking water of 4 mrem/year per 20,000 pCi/L (Reference 7) results in a predicted whole body dose of 0.075 mrem/year to an on-site individual (plant staff). In addition, Cesium-137 and Cobalt-60 were identified in bottom sediment samples. Although these concentrations maybe attributable to plant related discharges in past years, these samples were taken from deep water sediment in Sherman Pond where there is no direct exposure pathway to man.
Since the REMP for 2001 did not indicate plant related radioactivity in off-site media associated directly with human inhalation or ingestion pathways, there is no indication that the plant's effluent dose models underestimate the dose impacts to members of the public.
46
Annual Radiological Environmental Operating Report 2001
6.0 REFERENCES
- 1.
USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2.
NCRP Report No. 94, Exposure of the Population in the United States and Canada from Natural Background Radiation, National Council on Radiation Protection and Measurements, 1987.
- 3.
Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.
- 4.
Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, Harwood Academic Publishers, New York, 1984.
- 5.
Letter, "Issuance of Amendment No. 146 to Facility Possession Only License No. DPR-3-Yankee Nuclear Power Station," M. Fairtile, NRC to J. Grant, Yankee Atomic Electric Company, dated November 5, 1992.
- 6.
Subject:
Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989.
- 7.
USEPA, 40 CFR 141, National Primary Drinking Water Regulations.
47 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 APPENDIX A - LAND USE CENSUS FOR 2001 A-1 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 A Land Use Census is conducted annually between the dates of June 1 and October 1 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 2001 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 milk and 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 2001 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 2001 census.
The Land Use Census was carried out and completed between the dates of June 1 and October 1, as required. The results of the 2001 Land Use Census are included in this 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 Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE A. 1 2001 LAND USE CENSUS LOCATIONS 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 (2.1)**
ENE 3.7(2.3) 5.8(3.6)
E 2.8(1.8) 3.7 (2.3)**
ESE 3.4(2.1) 3.4(2.1)
SE 2.0(1.3) 3.4(2.1)
SSE 1.9(1.2) 3.0(1.9)
S 2.1(1.3) 2.8(1.8)
WSW 1.3(0.8) 1.9(1.2)
W 2.1(1.3) 2.9(1.8)
WNW 2.1 (1.3) 2.1 (1.3)
NW 2.4(1.5) 2.4(1.5)
NNW 2.9(1.8) 3.7(2.3)
No location was identified within 5 miles of the plant.
- New location in 2001 A-3 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 APPENDIX B - QUALITY CONTROL PROGRAM B-I Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 QUALITY ASSURANCE PROGRAM The quality assurance program at the Duke Engineering & Services Environmental Laboratory (DESEL) 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 DESEL 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 the Laboratory Quality Control Audit Committee administers a blind duplicate program conducted through client environmental monitoring programs.
This summary reports all intralaboratory and third party results received by DESEL on or before December 31, 2001.
Intralaboratory Quality Control Program The DESEL QA Officer administers an extensive intralaboratory quality control program in which process check samples are submitted for analysis. These samples are submitted either in duplicate to evaluate the precision of a measurement process or are "spiked" with a known amount of radioactive material to assess the bias in the measurement. Table B. I provides the summary of the process check results for January to December 2001. Of the 290 analyses, 97.9% passed the bias criteria and 100% of the results evaluated for precision were acceptable.
For 2001, the individual gross alpha and beta failures may not initiate an investigation unless the mean of three consecutive results is outside the DESEL performance criteria. During 2001, a spiked alpha or beta sample was run with each set of client samples. Samples were reprocessed if the individual spike sample was outside the +/- 25%
criteria.
Third Party Cross Check Program The DESEL participates in a third party cross check program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical Specification/ODCM. The DESEL 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 4'h quarter 2000 through the 3 rd quarter 2001 are summarized in Table B.2. Each sample is analyzed in triplicate and B-2 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 the results are evaluated against the internal acceptance criteria described in the DESEL 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 DESEL internal acceptance criteria are summarized at the end of Table B.2.
Investigations were initiated for the Analytics results that fell within the 'non-agreement' category.
"* Sr-89 on filter - Low Sr89:Sr9O ratio. Evaluation pending as of 12/31/2001.
"* Np-237 in water - Non-agreement due to contaminated glassware. Glassware will be disposed following processing of spiked samples. Investigation closed as of 12/31/01.
"* Sr-89 in milk - Evaluation ongoing.
Blind Duplicate Program The Laboratory Quality Control Audit Committee (LQCAC) is comprised of representatives from several New England DESEL clients. Two of the primary functions of the LQCAC have been to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate Quality Assurance Program, samples are split from homogeneous environmental media by the client and sent to the DESEL 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 31 paired samples in 2001. The measurements evaluated include twenty five gamma emitting radionuclides, H-3, Sr-89, Sr-90, 1-131 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 TableB.3. For the 2001 program, 99.4% of the measurements met the DESEL internal acceptance criteria.
Environmental TLD Quality Assurance Program Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the DESEL is provided by the dosimetry quality assurance testing program. This program includes the National Voluntary Laboratory Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer.
Under these programs, dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Group 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 doses are known to the processor.
Eighty-four performance tests were conducted in 2001 by DESEL and the third party tester. Of these, 100% of the dosimeter evaluations met the DESEL Internal Acceptance Criteria for bias (+/- 20.1%) and precision (+12.8%). In B-3 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 addition 14 TLD test sets passed the control limits set by the LQCAC in 1998 to evaluate the sum of the bias and precision values. A tolerance limit of +/- 30% applies to environmental dosimeters. Third Party QC results are summarized below.
Percentage of Individual Analyses which passed DESEL Internal Criteria Summary of Third Party Testing Dosimeter Type Exposure Period NVLAP Category Shallow (7mg/cm 2 )
% (Bias +/- SD)
IBI + S*
Panasonic Environmental Q4/2000 IV, high energy
-1.7 + 0.8 0.025
""t Q1/2001 IV, high energy 8.8+/- 1.2 0.100
""t Q2/2001 IV, high energy
-2.9 + 1.3 0.042
""t Q3/2001 IV, high energy 6.4 - 1.3 0.079 Note: Results are expressed as the delivered exposure for environmental TLD. NVLAP Category IV, High energy photons (Cs 137 or Co-60).
- American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semi-Annual QA Status Report.
B-4 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE B.1 DESEL RESULTS IN THE INTRALABORA TOR YPROCESS CONTROL PROGRAM January - December 2001 (1) Percent Bias Criteria by Bias Category Bias Category = 1 > 0% and < = 5%
Bias Category = 2 > 5% and < = 10%
Bias Category = 3 > 10% and < = 15%, or within 2 sigma of known Gross alpha and beta, Sr 89/90 > 10% and < = 25%
Transuranics > 10% and <= 20%
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 > 10% and < = 15%, or within 2 sigma of mean Precision Category = 4 Outside Criteria B-5 Media Bias Criteria (1)
Precision Criteria (2)
Analysis 1
2 3
4 1
2 3
4 I. Air Charcoal Gamma 36 5
0 0
0 0
0 0
II. Air Filter Alpha Beta 100 2
0 0
0 0
0 0
Gamma III. Milk Gamma Iodine-LL 7
3 0
0 15 0
0 0
Strontium-89 0
1 9
0 8
2 0
0 Strontium-90 6
3 1
0 7
3 0
0 IV. Water Gross Alpha 7
12 17 3
4 1
0 0
Gross Beta 25 5
10 3
5 0
0 0
Gamma 0
0 0
0 6
4 6
0 Iodine-LL Radium 226 11 7
2 0
15 4
1 0
Radium-228 3
I 2
0 3
0 2
0 Tritium 4
1 0
0 0
0 0
0 V. Sediment/Soil Gamma Radium-226 VI. Vegetation Gamma Total Number in Range 199 40 45 6
63 14 9
0 Sum of Analyses 290 86 Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE B.2 DESEL RESULTS IN THE ANAL YTICS INC. CROSS CHECK PROGRAM Quarter 4, 2000 - Quarter 3, 2001 Sample Quarter Sample Nuclide Reported Known Ratio Evaluation Year Media Value*
Value
- DESEL" Analytics E2477-162 4mn00 Filter Sr-89 60 85 0.70 Non-agreement Sr-90 42 41 1.03 Agreement E2478-162 4th/ 0 0 Filter Gross Alpha 20 21 0.97 Agreement Gross Beta 136 114 1.19 Agreement E2479-162 4th/ 0 0 Water H-3 9657 10082 0.96 Agreement E2480-162 4th/ 0 0 Milk 1-131LL 89 85 1.05 Agreement 1-131 86 85 1.01 Agreement Ce-141 362 356 1.02 Agreement Cr-51 521 503 1.04 Agreement Cs-134 84 85 0.99 Agreement Cs-137 204 199 1.02 Agreement Co-58 79 76 1.04 Agreement Mn-54 162 152 1.06 Agreement Fe-59 93 82 1.13 Agreement Zn-65 148 148 1.00 Agreement Co-60 185 184 1.00 Agreement E2592-162 ISt/01 Water 1-131 88 90 0.98 Agreement 1-131LL 89 90 0.99 Agreement Ce-141 100 94 1.06 Agreement Cr-51 236 242 0.98 Agreement Cs-134 120 129 0.93 Agreement Cs-137 97 102 0.95 Agreement Co-58 48 48 1.00 Agreement Mn-54 103 101 1.02 Agreement Fe-59 88 84 1.05 Agreement Zn-65 187 186 1.01 Agreement Co-60 144 147 0.98 Agreement E2593-162 ISt/01 Water Gross Alpha 40 39 1.03 Agreement Gross Beta 300 268 1.12 Agreement E2598A-162 I st/01 Filter Gross Alpha 30 30 1.00 Agreement Gross Beta 229 211 1.18 Agreement E2594-162 I st/01 Water Ra-226 51 50 1.02 Agreement Ra-228 63 63 1.00 Agreement
- pCi/Liter (Filters in pCi)
B-6 Yankee Rowe Station
Yankee Rowe Station Annual Radiological Environmental Operating Report 2001 TABLE B.2 (continued)
DESEL RESULTS IN THE ANAL YTICS INC. CROSS CHECK PROGRAM Quarter 4, 2000 - Quarter 3, 2001 Sample Quarter Sample Nuclide Reported Known Ratio Evaluation Year Media Value Value*
DESEL/
I I_
Analytics E2595-162 Ist/O1 Milk 1-131 78 77 1.01 Agreement 1-131LL 74 77 0.96 Agreement Ce-141 166 162 1.02 Agreement Cr-51 455 418 1.09 Agreement Cs-134 217 223 0.97 Agreement Cs-137 173 176 0.98 Agreement Co-58 86 82 1.05 Agreement Mn-54 185 175 1.06 Agreement Fe-59 151 146 1.03 Agreement Zn-65 328 322 1.02 Agreement Co-60 252 254 0.99 Agreement E2597-162 1 st/0 1 Water Am-241 5.6 6.0 0.93 Agreement Pu-238 7.2 7.5 0.96 Agreement Pu-239 5.5 5.5 1.00 Agreement Np-237 9.6 7.9 1.22 Non-Agreement Cm-244 5.6 6.3 0.89 Agreement E2670-162 2nd/01 Milk 1-131 63 69 0.91 Agreement I-131LL 66 69 0.96 Agreement Ce-141 165 163 1.01 Agreement Cr-51 228 224 1.02 Agreement Cs-134 131 134 0.98 Agreement Cs-137 128 121 1.06 Agreement Co-58 97 96 1.01 Agreement Mn-54 154 150 1.03 Agreement Fe-59 91 88 1.03 Agreement Zn-65 180 182 0.99 Agreement Co-60 138 135 1.03 Agreement E2666-162 2nd/o1 Filter Ce-141 91 96 0.95 Agreement Cr-51 130 132 0.98 Agreement Cs-134 74 79 0.94 Agreement Cs-137 77 71 1.08 Agreement Co-58 57 57 1.00 Agreement Mn-54 99 88 1.13 Agreement Fe-59 58 51 1.14 Agreement Zn-65 118 107 1.10 Agreement Co-60 77 79 0.97 Agreement
- Units in pCi/Liter (filter in pCi)
B-7
Annual Radiological Environmental Operating Report 2001 TABLE B.2 (continued)
DESEL RESULTS IN THE ANAL YTICS INC. CROSS CHECK PROGRAM Quarter 4, 2000 - Quarter 3, 2001 E2669-162 2nf/01 Water H-3 7007 7494 0.94 Agreement E2667-162 2nd/01 Filter Sr-89 89 84 1.06 Agreement Sr-90 75 64 1.17 Agreement E2806-162 3rd/OI Water 1-131 63 60 1.05 Agreement I-13ILL 62 60 1.04 Agreement Ce-141 96 88 1.09 Agreement Cr-51 275 265 1.04 Agreement Cs-134 113 116 0.97 Agreement Cs-137 234 232 1.01 Agreement Co-58 132 128 1.03 Agreement Mn-54 153 149 1.03 Agreement Fe-59 66 62 1.06 Agreement Zn-65 184 184 1.00 Agreement Co-60 195 193 1.01 Agreement E2805-162 3rd/01 Water Gross Alpha 84 78 1.08 Agreement Gross Beta 175 205 0.85 Agreement E2808-162 3rd/01 Filter Gross Alpha 51 50 1.02 Agreement Gross Beta 136 133 1.02 Agreement E2809-162 3rd/O1 Milk 1-131 90 91 0.99 Agreement I-131LL 91 91 1.00 Agreement Ce-141 131 121 1.08 Agreement Cr-51 374 366 1.02 Agreement Cs-134 157 160 0.98 Agreement Cs-137 323 319 1.01 Agreement Co-58 182 177 1.03 Agreement Mn-54 211 205 1.03 Agreement Fe-59 87 86 1.01 Agreement Zn-65 261 254 1.03 Agreement Co-60 274 266 1.03 Agreement E2807-162 3rd/ 0 1 Water Sr-89 87 85 1.02 Agreement Sr-90 61 59 1.03 Agreement E2810-162 3 rd/01 Milk Sr-89 121 75 1.61 Non-Agreement Sr-90 49 50 0.98 Agreement
- Units in pCi/Liter (filters in pCi)
Bias Acceptance Criteria +/- 15%, or as noted below:
Precision Acceptance Criteria + 15%, or as noted below:
Gross alpha and beta, Sr 89/90 +/- 25%
Gross alpha and beta, Sr 89/90 - 25%
Transuranics and Radium +/- 20% or, Transuranics and Radium +/- 20%
If known value falls within 2 sigma range acceptance criteria is met B-8 Sample Quarter Sample Nuclide Reported Known J Ratio Evaluation Year Media Value Value
- DESEL Ii Analytics j Yankee Rowe Station
Annual Radiological Environmental Operating Report 2001 TABLE B.3
SUMMARY
OF BLIND DUPLICATE SAMPLES January - December 2001 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Milk 8
Ground Water 2
Surface Water 14 Algae 2
Mussels 4
Food Product 1
TOTAL 31 B-9 Yankee Rowe Station
APPENDIX C -
SUMMARY
OF 2001 REMP DATA C-I
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE NUCLIDE AIR PARTICULATES
- 7. 60E-02 4.22E-04
-4.26E-05
- 1. 75E-04
-5. 40E-04
- 8. 30E-02
- 7. 12E-04
- 6. 99E-05
-9. 58E-05
- 0. OOE+00
- 0. 10E+00 6.99E-05
- 2. 71E-04 1.48E-04
-2. 75E-04
- 6. 50E-02 1.94E-04
- 1. 59E-04 4.16E-04
-1. 08E-04
- 1. 14E-02
- 5. 44E-04
- 2. 96E-04
- 1. 60E-04
- 2. 40E-04
- 1. 09E-02
- 3. 96E-04
- 2. 19E-04
- 1. 82E-04
- 2. 1OE-04
- 9. 89E-03
- 3. 33E-04
- 2. 17E-04
- 1. 35E-04
- 1. 75E-04
- 6. 64E-03 2.44E-04
- 1. 90E-04 1.76E-04
- 1. 85E-04 2.52E-02
- 2. OOE-03 1.31E-03
- 5. 71E-04
- 1. 17E-03 2.22E-02 *
- 1. 18E-03
- 9. 23E-04
- 8. 45E-04
- 8. 37E-04 1.65E-02
- 1. 36E-03
- 7. 36E-04
- 4. 83E-04
- 8. 54E-04 1.21E-02 *
- 8. 98E-04 6.99E-04
- 4. 88E-04
- 7. 34E-04 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-2 CONC (Pcilcu.m)
STD DEV.
(pCi/cu.m)
MDC (pCi/cu.m)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 11 11 11 II i1 11 11 11 11 11 11 11 11 1i 11 11 11 11 11 Ii 59634 59634 59634 59634 59634 61235 61235 61235 61235 61235 62401 62401 62401 62401 62401 63644 63644 63644 63644 63644 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 06/27/01 06/27/01 06/27/01 06/27/01 06/27/01 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137
MEDIA STA Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC LSN END DATE NUCLIDE (pCi/cu.m)
- 8. 80E-02
-1. 39E-04
- 5. 15E-04 8.23E-04 8.70E-04
- 0. 12E+00
-2. 04E-03
- 2. 30E-04 1.70E-04
-8.
- 0. 14E+00 4.77E-04 6.68E-04
-1. 19E-04
- 8. 32E-04
- 8. 58E-02
-1. 31E-04
-1. 38E-03
-1. 56E-04
-6. 17E-04
- 2. 06E-02
- 1. 04E-03
- 5. 67E-04
- 4. 79E-04
- 5. 03E-04 2.38E-02 1.47E-03 7.20E-04
- 6. 31E-04 6.50E-04
- 2. 1OE-02
- 8. 13E-04
- 4. 72E-04
- 5. 85E-04
- 6. 43E-04
- 1. 76E-02
- 9. 75E-04
- 9. 01E-04
- 3. 30E-04 4.77E-04 5.25E-02
- 4. 50E-03
- 2. 14E-03
- 1. 38E-03
- 1. 55E-03 5.26E-02
- 6.89E-03
- 3. 03E-03
- 2. 57E-03
- 2. 95E-03 3.69E-02
- 3. 31E-03
- 9. 04E-04
- 2. 65E-03 2.18E-03 4.03E-02 4.23E-03
- 4. 41E-03
- 1. 80E-03
- 2. 32E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-3 STD DEV.
(pCi/cu.m)
MDC (pCi/cu.m)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 06/27/01 06/27/01 06/27/01 06/27/01 06/27/01 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 59635 59635 59635 59635 59635 61236 61236 61236 61236 61236 62402 62402 62402 62402 62402 63645 63645 63645 63645 63645 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 01 01 01 01 01
/02/02
/02/02
/02/02
/02/02
/02/02
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 6.77E-02
- 2. 15E-04 9.60E-04
- 6. OOE-04
- 5. 02E-04 6.34E-02
- 1. 36E-03
- 8. 50E-04
- 1. 08E-04
- 9. 08E-04
- 8. 31E-02
- 2. 31E-04
- 8. 78E-04
-5. 45E-04 1.50E-04 6.33E-02
-5. 45E-04
- 8. 32E-04
-5. OOE-04 9.07E-04
- 1. 93E-02
- 1. 02E-03
- 6. 20E-04 4.72E-04 4.78E-04
- 2. OOE-02 1.07E-03
- 6. 79E-04
- 5. 72E-04
- 5. 97E-04
- 1. 97E-02
- 1. 1OE-03
- 8. 76E-04
- 6. 09E-04
- 4. 80E-04 4.03E-04 4.50E-04 5.34E-02 *
- 4. 16E-03
- 1. 93E-03
- 1. 60E-03
- 1. 69E-03 5.54E-02
- 3. 64E-03
- 2. 31E-03 2.40E-03
- 1. 94E-03 5.06E-02 4.48E-03
- 3. 16E-03 2.79E-03
- 2. 97E-03 3.64E-02
- 3.36E-03 7. 50E-04 2.23E-03 1.23E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-4 NUCLIDE CONC (Pci/cu.m)
STD DEV.
(pCi/cu.m) 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 MDC (pCi/cu.m)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 06/27 06/27 06/27 06/27 06/27
/01
/01
/01
/01
/01 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 59636 59636 59636 59636 59636 61237 61237 61237 61237 61237 62403 62403 62403 62403 62403 63646 63646 63646 63646 63646 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137
- 4. 76E-02
-1. 16E-04
-1.74E-05
- 1. 37E-04 2.81E-04
- 7. 26E-02
-2.80E-04
- 1. 05E-04
-2. 77E-04
-7. 83E-04
- 9. 20E-02
-2.25E-05
-3. 79E-04
-6. 72E-04
- 8. 83E-05
- 7. 79E-02 4.91E-04
-1. 31E-04
- 2. 91E-04
-3. 80E-04 1.01E-02 3.85E-04
- 2. 09E-04
- 2. 51E-04 2.26E-04
- 1. 31E-02
- 5. 32E-04
- 3. 29E-04
- 2. 91E-04
- 3. 20E-04
- 1. 27E-02
- 6. 06E-04
- 4. 03E-04
- 2. 99E-04
- 3. 55E-04
- 1. 08E-02
- 3. 14E-04 2.42E-02 1.86E-03 1.08E-03 9.99E-04
- 7. 74E-04 2.99E-02
- 2. 47E-03
- 1. 39E-03
- 1. 39E-03
- 1. 95E-03
- 1. 64E-03
- 1. 37E-03 2.01E-02
- 1. 97E-03
- 1. 22E-03
- 9. O1E-04
- 1. 38E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-5 NUCLIDE CONC (pCi/cu.m)
STD DEV.
(pCi/cu.m)
MDC (pCi/cu.m)
AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 59637 59637 59637 59637 59637 61238 61238 61238 61238 61238 62404 62404 62404 62404 62404 63647 63647 63647 63647 63647 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 06/27/01 06/27/01 06/27/01 06/27/01 06/27/01 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (Pcilcu.m)
(Pci/cu.m)
(Pci/cu.m) 5.09E-02
-5. 98E-04
-1. 85E-04 1.47E-04
-6. 88E-05 9.82E-02
-5. 17E-04
- 1. 47E-04 4.18E-05
- 1. 35E-04
- 0. 11E+00
-1. 09E-04
-1.
- 2. 58E-04
-3.25E-04
- 7. 15E-02
- 3. 58E-04
-1.
-4. 12E-04
- 3. 52E-04
- 1. 06E-02
- 6. 34E-04
- 2. 77E-04
- 2. 69E-04
- 2. 84E-04
- 1. 54E-02
- 4. 17E-04
- 1. 47E-04 1.81E-04
- 2. 1OE-04
- 1. 27E-02
- 3. 62E-04 2.87E-04
- 2. 94E-04
- 2. 51E-04
- 1. 05E-02
- 3. 74E-04
- 1. 98E-04
- 1. 84E-04
- 1. 98E-04 2.43E-02
- 2. 92E-03
- 1. 46E-03
- 1. 07E-03
- 1. 19E-03 3.53E-02
- 2.30E-03 3.99E-04 8.40E-04 8. 20E-04
- 2. 16E-02
- 1.75E-03 1.51E-03
- 1. 09E-03
- 1. 22E-03 2.14E-02
- 1. 38E-03
- 1. 03E-03
- 1. 14E-03
- 5. 78E-04 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-6 STD DEV.
MDC AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 59638 59638 59638 59638 59638 61239 61239 61239 61239 61239 62405 62405 62405 62405 62405 63648 63648 63648 63648 63648 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 06/27/01 06/27/01 06/27/01 06/27/01 06/27/01 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (Pcilcu.m)
(Pcilcu.m)
(pCifcu.m)
- 1. 19E-02
- 4. 95E-04
- 4. 06E-04
- 2. OOE-04
- 2. 54E-04
- 1. 66E-02
- 7. 73E-04
- 5. 33E-04 4.42E-04
- 3. 04E-04
- 1. 39E-02
- 6. 82E-04
- 4. 91E-04
- 3. 70E-04
- 3. 75E-04
- 1. 04E-02
- 4. 03E-04
- 4. 92E-04
- 3. 32E-04
- 2. 29E-04 3.47E-02
- 2.49E-03 1.46E-03
- 1. 1OE-03 1.23E-03 2.49E-02
- 3.24E-03 2.36E-03 1.81E-03
- 1. 34E-03 2.86E-02 *
- 3. 23E-03
- 1. 67E-03
- 1. 07E-03 1.22E-03 2.44E-02 *
- 1. 44E-03
- 2. 40E-03
- 1. 23E-03
- 9. 66E-04 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-7 STD DEV.
MDC AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 59639 59639 59639 59639 59639 61240 61240 61240 61240 61240 62406 62406 62406 62406 62406 63649 63649 63649 63649 63649 03/27/01 03/27/01 03/27/01 03/27/01 03/27/01 06/27/01 06/27/01 06/27/01 06/27/01 06/27/01 09/25/01 09/25/01 09/25/01 09/25/01 09/25/01 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137 Be-7 Co-58 Co-60 Cs-134 Cs-137
- 3. 64E-02
-4.87E-04
- 4. 07E-04
-1. 79E-04
-3. 28E-04
- 0. 11E+00
- 1. 45E-04
-7. 67E-05
- 9. 31E-05
-5. 71E-05
- 8. 19E-02
-5. 57E-04
- 6. 16E-04
- 6. 35E-04
- 5. 61E-04 4.75E-02 4.42E-04
-6. 18E-04
- 2. 92E-04
- 6. 37E-05
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA AP AP AP AP AP 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 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 Ii LSN END DATE 57892 58547 58310 58566 58695 59000 59218 59380 59532 59774 59937 60339 60518 60795 60884 61035 61334 61476 61748 61925 62024 62198 62591 62678 62858 63045 63260 63496 63570 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 04/04/01 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 07/03/01 07/17/01 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/02/02 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-8 NUCLIDE GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B CONC (pCi/cu.m)
- 1. 78E-02 4.91E-02 4.37E-02
- 1. 98E-02
- 2. 23E-02
- 2. OOE-02
- 1. 4 1E-02 9.17E-03
- 1. 71E-02
- 2. 44E-02
- 2. 31E-02
- 1. 15E-02
- 1. 29E-02
- 2. 02E-02
- 2. 03E-02
- 1. 23E-02
- 1. 94E-02
- 2. 32E-02
- 2. 25E-02
- 2. 25E-02 2.44E-02 2.28E-02
- 2. 18E-02
- 3. 02E-02
- 3. 32E-02
(pCi/cu.m)
- 1. 11E-03
- 1. 32E-03 1.75E-03
- 8. 06E-04
- 9. 50E-04
- 6. 27E-04
- 6. 1OE-04
- 6. 93E-04
- 1. 04E-03
- 1. 01E-03
- 1. 02E-03 7.75E-04 6.01E-04
- 9. 30E-04
- 1. 15E-03
- 6. 36E-04 6.52E-04
- 6. 93E-04
- 9. 94E-04
- 6. 68E-04 1.06E-03 7.26E-04
- 8. 48E-04 1.21E-03
- 5. 68E-04
- 2. 59E-03
- 1. 82E-03
- 2. 82E-03
- 1. 67E-03
- 1. 53E-03
- 9. 74E-04
- 1. 24E-03
- 1. 67E-03
- 2. 36E-03
- 1. 73E-03
- 1. 63E-03
- 1. 56E-03
- 1. 28E-03
- 1. 51E-03 2.39E-03 1.40E-03
- 1. 08E-03
- 1. 17E-03
- 1. 58E-03
- 1. 84E-03
- 9. 48E-04
- 1. 76E-03
- 1. 23E-03
- 1. 16E-03
- 1. 70E-03
- 9. 94E-04
- 2. 16E-03
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA AP AP AP AP AP 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 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 LSN END DATE NUCLIDE (pCi/cu.m)
(pCi/cu.m)
(pCi/cu.m) 57893 58548 58311 58567 58696 59001 59219 59381 59533 59775 59938 60340 60519 60796 60885 61036 61335 61477 61749 61926 62025 62199 62592 62679 62859 63046 63261 63497 63571 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 04/04/01 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 07/03/01 07/17/01 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/02/02 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B
- 2. 71E-02
- 3. 66E-02
- 3. 14E-02
- 2. 64E-02
- 2. 99E-02
- 2. 52E-02
- 1. 94E-02
- 2. 22E-02
- 2. 53E-02 3.24E-02 3.56E-02 1.59E-02
- 2. 07E-02
- 2. 96E-02
- 3. 45E-02
- 2. 08E-02
- 3. 34E-02
- 4. 82E-02
- 3. 29E-02
- 3. 16E-02
- 3. 71E-02
- 3. 65E-02
- 4. 01E-02 3.71E-02
- 3. 19E-02 4.31E-02
- 5. 16E-02
- 3. 07E-02
- 3. 78E-02
- 2. 35E-03
- 1. 62E-03
- 2. 15E-03 1.86E-03 2.06E-03 1.36E-03 1.48E-03
- 2. 41E-03
- 1. 70E-03 2.26E-03
- 2. 36E-03
- 1. 87E-03
- 1. 55E-03 2.21E-03
- 3. 00E-03 1.71E-03
- 1. 72E-03 2.20E-03
- 1. 56E-03
- 1. 97E-03
- 2. 22E-03 2.58E-03
- 1. 64E-03 2.70E-03 1.78E-03
- 2. 03E-03 2.85E-03 1.56E-03
- 2. 87E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-9 STD DEV.
MDC 6.05E-03
- 2. 93E-03 4.54E-03
- 4. 67E-03
- 4. 34E-03
- 2. 78E-03
- 3. 57E-03
- 6. 51E-03
- 4. 11E-03
- 5. 05E-03 4.70E-03
- 4. 68E-03
- 3. 89E-03
- 4. 72E-03
- 7. 04E-03 4.27E-03
- 3. 39E-03
- 4. 54E-03
- 2. 89E-03 4.57E-03
- 5. 07E-03
- 5. 88E-03
- 2. 93E-03 5.51E-03
- 3. 83E-03
- 3. 79E-03
- 5. 16E-03
- 3. 29E-03
- 6. 98E-03
MEDIA STA Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC LSN END DATE NUCLIDE (pCi/cu.m) 13 13 13 13 13 13 13 57894 58549 58312 58568 58697 59002 59220 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 GR-B GR-B GR-B GR-B GR-B GR-B GR-B 13 59382 04/04/01 GR-B AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP AP 59534 59776 59939 60341 60520 60797 60886 61037 61336 61478 61750 61927 62026 62200 62593 62680 62860 63047 63262 63498 63572 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 07/03/01 07/17/01 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/02/02 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B
- 1. 98E-02 3.28E-02
- 2. 38E-02
- 2. 36E-02
- 2. 22E-03 1.53E-03
- 1. 98E-03 1.84E-03 2.08E-03
- 1. 33E-03
- 1. 73E-03 2.02E-02 2.40E-03 6.42E-03 *
- 1. 88E-02 1.29E-02
- 2. 82E-02
- 1. 37E-02
- 1. 97E-02 2.72E-02
- 3. 42E-02
- 1. 98E-02
- 2. 4 1E-02
- 3. 89E-02
- 3. 17E-02
- 2. 80E-02
- 3. 15E-02
- 2. 88E-02
- 3. 22E-02 3.03E-02
- 4. 38E-02
- 2. 81E-02
- 3. 49E-02
- 1. 63E-03
- 1. 70E-03 2.25E-03
- 1. 81E-03 1.54E-03 2.09E-03
- 3. 06E-03
- 1. 66E-03
- 1. 51E-03
- 2. 01E-03
- 1. 50E-03
- 1. 86E-03
- 2. 04E-03
- 2. 35E-03
- 1. 53E-03
- 2. 44E-03
- 1. 73E-03
- 1. 93E-03
- 2. 62E-03
- 1. 47E-03 2.71E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-10 STD DEV.
(pCi/cu.m)
MDC (pCi/cu.m)
- 5. 86E-03
- 4. 66E-03 4.29E-03
- 2. 77E-03 4.29E-03
- A 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13
- 4. 09E-03 4.54E-03 4.81E-03
- 4. 63E-03
- 3. 87E-03
- 4. 56E-03
- 7. 15E-03
- 4. 11E-03
- 3. 27E-03 4.34E-03
- 2. 80E-03 4.41E-03 4.80E-03
- 5. 55E-03
- 2. 85E-03 5.34E-03 3.74E-03 3.62E-03
- 4. 95E-03
- 3. 14E-03
- 6. 65E-03
MEDIA STA AP AP AP AP AP 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 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC LSN END DATE NUCLIDE (pCi/cu.m) 57895 58550 58313 58569 58698 59003 59221 59383 59535 59777 59940 60342 60521 60798 60887 61038 61337 61479 61751 61928 62027 62201 62594 62681 62861 63048 63263 63499 63573 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 04/04/01 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 07/03/01 07/17/01 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/03/02 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B 1.89E-02
- 2. 31E-02
- 1. 98E-02
- 2. 35E-02
- 2. 71E-02
- 2. 06E-02
- 1. 60E-02 1.28E-02
- 1. 94E-02
- 2. 91E-02 2.58E-02 1.24E-02
- 1. 15E-02 3.06E-02
- 2. 82E-02
- 1. 36E-02
- 2. 21E-02
- 3. 58E-02
- 2. 16E-02
- 2. 46E-02
- 2. 60E-02
- 2. 37E-02
- 2. 1OE-02
- 3. 45E-02 2.23E-02
- 2. 64E-02 STD DEV.
MDC (pCi/cu.m)
(Pcilcu.m)
- 1. 36E-03 7.81E-04
- 1. 03E-03
- 1. 17E-03
- 1. 33E-03
- 8. 37E-04 8.71E-04
- 1. 16E-03 9.85E-04 1.41E-03 1.42E-03
- 1. 05E-03 6.83E-04
- 1. 82E-03
- 1. 82E-03 9.25E-04
- 9. 50E-04 1.26E-03
- 9. 40E-04
- 1. 1OE-03
- 1. 20E-03
- 1. 42E-03
- 9. 18E-04
- 1. 52E-03
- 1. 04E-03 9.78E-04
- 1. 63E-03
- 8. 92E-04 1.48E-03
- 3. 28E-03
- 1. 24E-03
- 1. 92E-03
- 2. 60E-03
- 2. 36E-03
- 1. 52E-03
- 1. 94E-03
- 2. 97E-03 2.21E-03
- 2. 68E-03
- 2. 57E-03
- 2. 37E-03
- 1. 57E-03
- 3. 49E-03
- 3. 91E-03
- 2. 19E-03 1.74E-03 2.29E-03 1.51E-03
- 2. 34E-03
- 2. 57E-03
- 3. 03E-03
- 1. 4 9E-03
- 2. 89E-03
- 2. O1E-03
- 1. 84E-03
- 2. 77E-03
- 1. 70E-03
- 3. 25E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-Il
-k
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE NUCLIDE CONC STD DEV.
MDC (pCi/cu.m)
(pCi/cu.m)
(pCi/cu.m) 57896 58551 58314 58570 58699 59004 59222 59384 59536 59778 59941 60343 60522 60799 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 04/04/01 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B AP AP AP AP AP 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 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/03/02 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B
- 1. 57E-02
- 2. 74E-02
- 2. 37E-02 2.33E-02 2.54E-02 1.77E-02
- 1. 80E-02
- 1. 45E-02 1.88E-02
- 2. 86E-02
- 2. 78E-02
- 1. 32E-02
- 1. 30E-02 2.29E-02
- 1. 27E-03 9.68E-04
- 1. 30E-03
- 1. 15E-03
- 1. 24E-03
- 1. 36E-03
- 1. 37E-03
- 1. 02E-03 7.81E-04
- 1. 18E-03
- 3. 14E-03
- 1. 61E-03
- 2. 49E-03
- 2. 56E-03
- 2. 20E-03
- 1. 42E-03 2.08E-03
- 3. 19E-03
- 2. OOE-03
- 2. 55E-03
- 2. 33E-03
- 2. 24E-03 1.84E-03
- 2. 13E-03 2.84E-02 1.69E-03 3.57E-03 1.41E-02 8.44E-04 1.96E-03
- 2. 14E-02 3.45E-02
- 2. 75E-02
- 2. 63E-02 2.77E-02
- 2. 37E-02
- 2. 85E-02
- 2. 40E-02 2.49E-02
- 3. 45E-02
- 3. 26E-02
- 2. 35E-02
- 2. 99E-02
- 8. 63E-04
- 1. 13E-03
- 8. 61E-04
- 1. 05E-03
- 1. 36E-03
- 9. 65E-04
- 1. 13E-03
- 1. 44E-03
- 8. 46E-04
- 1. 39E-03
- 1. 55E-03
- 2. 04E-03
- 1. 33E-03
- 2. 05E-03
- 2. 28E-03
- 2. 65E-03
- 1. 32E-03
- 2. 54E-03 1.75E-03 1.75E-03
- 2. 34E-03
- 1. 51E-03
- 2. 88E-03 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-12 60888 07/03/01 GR-B 61039 07/17/01 GR-B 61338 61480 61752 61929 62028 62202 62595 62682 62862 63049 63264 63500 63574
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA AP AP AP AP AP 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 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 LSN END DATE NUCLIDE (pCi/cu.m)
(pCi/cu.m)
(pCi/cu.m) 57897 58552 58315 58571 58700 59005 59223 59385 59537 59779 59942 60344 60523 60800 60889 61040 61339 61481 61753 61930 62029 62203 62596 62683 62863 63050 63265 63501 63575 01/03/01 01/17/01 01/30/01 02/13/01 02/27/01 03/13/01 03/27/01 04/04/01 04/17/01 05/02/01 05/15/01 05/29/01 06/12/01 06/27/01 07/03/01 07/17/01 08/01/01 08/14/01 08/30/01 09/12/01 09/25/01 10/03/01 10/19/01 10/31/01 11/13/01 11/28/01 12/11/01 12/26/01 01/02/02 GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B GR-B 1.21E-02
- 1. 98E-02
- 1. 77E-02
- 1. 93E-02
- 1. 39E-02
- 1. 88E-02 1.80E-02 2.56E-02
- 2. 82E-02
- 1. 32E-02 1.48E-02 2.26E-02
- 1. 87E-02
- 1. 39E-02 2.24E-02
- 3. 51E-02
- 2. 33E-02 2.24E-02
- 2. 60E-02
- 2. 71E-02
- 3. 02E-02
- 2. 14E-02
- 2. 36E-02
- 3. 52E-02 3.13E-02
- 1. 31E-02
- 3. 18E-02 1.45E-03
- 8. 34E-04
- 1. 09E-03
- 9. 53E-04
- 1. OOE-03
- 1. 84E-03
- 1. 17E-03
- 1. 63E-03
- 1. 68E-03
- 1. 31E-03
- 1. 05E-03
- 1. 50E-03
- 1. 85E-03
- 1. 12E-03
- 1. 11E-03
- 1. 47E-03 1.07E-03
- 1. 33E-03 1.44E-03 1.72E-03
- 1. 45E-03
CONC > 3 STD.
DEV.)
C-13 STD DEV.
- 3. 86E-03 1.44E-03
- 2. 24E-03
- 3. 18E-03
- 2. 96E-03 1.88E-03
- 2. 42E-03
- 4. 74E-03
- 2. 82E-03
- 3. 50E-03 3.21E-03
- 3. 05E-03
- 2. 57E-03
- 3. 04E-03
- 4. 55E-03
- 2. 77E-03
- 2. 19E-03
- 2. 94E-03
- 1. 89E-03
- 2. 99E-03
- 3. 20E-03
- 3. 77E-03
- 1. 95E-03
- 3. 65E-03
- 2. 56E-03
- 2. 50E-03 3.39E-03
- 1. 24E-03 4.61E-03
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 05/16/01 05/16/01 05/16/01 05/16/01 05/16/01 05/16/01 05/16/01 05/16/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 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 21 21 21 21 21 21 21 21 21 21 21 21 21 11 11 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 59983 59983 59983 59983 59983 59983 59983 59983 62446 62446 62446 62446 62446 62446 62446 62446 59984 59984 59984 59984 59984 59984 59984 59984 62447 62447 62447 62447 62447 62447 62447 62447 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-14 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
FISH MDC (pCi/kg)
Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 Mn-54 Zn-65 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 Mn-54 Zn-65 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 Mn-54 Zn-65 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 Mn-54 Zn-65 1.56E+01 4.44E+00
- 9. 45E+00
- 3. 91E+01
-2. 18E+01
- 2. 19E+03 1.71E+00
-2. 06E+01
- 7. 35E+00
- 1. 22E+01
-1. 06E+00
- 3. 08E+01
-2. 30E+01
- 3. 51E+03
-9. 55E+00
-5. 12E+01
- 4. 56E+00
- 1. 44E+01
-2. 85E+00
- 2. O1E+01
-2. 25E+01
- 2. 70E+03
- 7. 98E+00
-7. 90E+00
-4.44E+00
-1.50E+01
-1. 15E+01
-9. 14E+00
- 7. 48E+01 3.32E+03
-1.35E+01
-1.39E+01
- 1. 10E+01
- 9. 71E+00
- 9. 45E+00
- 1. 54E+01 2.4 6E+01
- 2. 66E+02
- 8. 91E+00
- 2. 35E+01
- 9. 22E+00 1.41E+01 1.29E+01
- 1. 62E+01
- 4. 76E+01
- 4. 06E+02 9.06E+00
- 3. 50E+01
- 8. 59E+00
- 8. 09E+00
- 7. 12E+00
- 1. 11E+01
- 3. 19E+01 2. 64E+02 8. 92E+00
- 1. 58E+01 1.26E+01 1.30E+01
- 1. 46E+01 1.51E+01 4.19E+01
- 3. 96E+02
- 1. 05E+01 2.79E+01
- 3. 66E+01
- 3. 64E+01
- 3. 29E+01 4.78E+01
- 1. 10E+02 5.24E+02 *
- 3. 34E+01
- 9. 47E+01
- 3. 40E+01 5.09E+01
- 5. 04E+01
- 5. 18E+01
- 1. 92E+02 7.37E+02
- 4.08E+01 1.47E+02
- 3. 16E+01
- 2. 51E+01
- 2. 93E+01
- 3. 57E+01
- 1. 30E+02 4.OOE+02
- 3. 12E+01
- 6. 58E+01
- 5. 13E+01
- 6. 07E+01
- 5. 96E+01 5.89E+01 1.30E+02 5.98E+02 4.70E+01
- 1. 16E+02 05/15 05/15 05/15 05/15 05/15 05/15 05/15 05/15
/01
/01
/01
/01
/01
/01
/01
/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01 10/10/01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg) 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE
- 1. 08E+03 9.73E+01 1.05E+02
- 8. 61E+01 1.21E+02 9.94E+02
- 3. 55E+02 9.48E+02
- 1. 19E+02 8.48E+01
- 1. 41E+02 1.29E+02 1.25E+03 2.83E+02
- 5. 52E+02 8.47E+01
- 6. 15E+01
- 5. 89E+01 7.83E+01
- 6. 54E+02
- 2. 54E+02
+
11 11 11 11 11 11 11 11 11 11 11 11 11 11 ii 11 1i 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 1i ii 11 11 11 11 11 11 1i 60034 60034 60034 60034 60034 60034 60034 60035 60035 60035 60035 60035 60035 60035 60036 60036 60036 60036 60036 60036 60036 62448 62448 62448 62448 62448 62448 62448 62449 62449 62449 62449 62449 62449 62449 62450 62450 62450 62450 62450 62450 62450 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-15 SEDIMENT STD DEV.
(pCi/kg)
MDC (pCi/kg)
- 0. OOE+00
- 1. 43E+01
-1. 24E+01
-1.78E+01 1.70E+02
- 1. 53E+04
- 1. 14E+03
- 0. OOE+00
-5. 16E+00 6.26E+01
-3.20E+01 7.44E+01
- 1. 33E+04 8.33E+02
- 2. 35E+02
-0. 51E+00
- 2. 13E+01
- 4. 93E+00 1 OOE+02
- 1. 25E+04
- 6. 92E+02
- 1. 90E+02
- 2. 94E+00
- 1. 41E+00 4. 32E+01 8.45E+01
- 1. 54E+04
- 1. 19E+03 2.22E+02
-1.86E+00
- 8. 53E+00
- 3. 69E+00
- 8. 09E+01 1.28E+04
- 1. 04E+03
- 1. 04E+02
-3. 48E+01
- 2. 16E+01
- 2. 01E+01
- 1. 95E+02
- 1. 42E+04
- 7. 93E+02 05/08 05/08 05/08 05/08 05/08 05/08 05/08
/01
/01
/01
/01
/01
/01
/01
- 2. 98E+02
- 2. 66E+01
- 2. 57E+01 2.23E+01 4.22E+01
- 9. 77E+02
- 1. 19E+02
- 2. 56E+02 3.07E+01
- 2. 88E+01
- 3. 73E+01
- 3. 98E+01
- 9. 91E+02
- 1. 05E+02 1.66E+02
- 2. 30E+01
- 1. 80E+01
- 1. 66E+01
- 2. 67E+01
- 6. 68E+02 7.54E+01 2.28E+02 2.21E+01
- 2. 15E+01
- 3. 40E+01 3.56E+01
- 9. 77E+02
- 1. 16E+02
- 2. 12E+02
- 2. 27E+01
- 2. 26E+01
- 2. 10E+01
- 3. 77E+01
- 9. 19E+02
- 1. 12E+02
- 2. 10E+02
- 2. 75E+01
- 2. 79E+01
- 2. 52E+01
- 4. 08E+01
- 9. 99E+02
- 1. 10E+02
- 7. 90E+02 8.42E+01
- 8. 52E+01
- 1. 06E+02
- 1. 12E+02 1.12E+03
- 3.68E+02 *
- 7. 28E+02
- 8. 87E+01
- 8. 73E+01
- 7. 67E+01
- 1. 20E+02 8.52E+02 3.60E+02 *
- 7. 57E+02
- 1. 16E+02
- 1. 01E+02 8.77E+01
- 1. 07E+02 8.77E+02
- 4. 86E+02 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE SE 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 60037 60037 60037 60037 60037 60037 60037 60038 60038 60038 60038 60038 60038 60038 60039 60039 60039 60039 60039 60039 60039 62451 62451 62451 62451 62451 62451 62451 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 05/08/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 10/09/01 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232 Be-7 Co-58 Co-60 Cs-134 Cs-137 K-40 Th-232
-1. 43E+02 1.24E+01
- 1. 85E+01
- 3. 42E+00
-1. 30E+01
- 1. 59E+04
- 3. 32E+02
-1.26E+02
-7. 33E+00
-4.21E+00 6.65E+00 3.82E+01
- 1. 81E+04
- 4. 04E+02
- 6. 36E+01
-2. 40E+01
-2. 81E+01
- 1. 01E+01
-6. 25E+01
- 1. 74E+04
- 4. 68E+02
-1.59E+01
-4. 55E+00
- 2. 62E+00
-4.32E+00
- 1. O1E+01 1.26E+04
-3. 19E+02 SE 21 62452 10/09/01 Be-7 8.86E+01 SE 21 62452 10/09/01 Co-58 3.19E+00 SE 21 62452 10/09/01 Co-60
-0.62E+00 SE 21 62452 10/09/01 Cs-134
-1.21E+01 SE 21 62452 10/09/01 Cs-137 1.37E+01 SE 21 62452 10/09/01 K-40 1.35E+04 SE 21 62452 10/09/01 Th-232 4.07E+02 SE 21 62453 10/09/01 Be-7
-1.03E+02 SE 21 62453 10/09/01 Co-58
-1.69E+01 SE 21 62453 10/09/01 Co-60 2.15E+01 SE 21 62453 10/09/01 Cs-134 1.68E+00 SE 21 62453 10/09/01 Cs-137 1.22E+00 SE 21 62453 10/09/01 K-40 1.27E+04 SE 21 62453 10/09/01 Th-232 3.89E+02 Radioactivity detected in sample (i.e.,
CONC > 3 STD
- 1. 67E+02 1.70E+01
- 1. 35E+01
- 1. 39E+01 1.77E+01 6.94E+02
- 6. 04E+01
- 2. 31E+02
- 2. 45E+01
- 1. 92E+01
- 1. 69E+01
- 1. 66E+01
- 9. 62E+02
- 9. 24E+01
- 1. 96E+02 2.21E+01 2.32E+01 1.72E+01
- 2. 08E+01
- 9. 78E+02
- 8. 25E+01
- 1. 24E+02
- 1. 33E+01
- 1. 12E+01
- 1. 13E+01
- 1. 40E+01
- 5. 92E+02 9.89E+01
- 1. 14E+02 1.25E+01
- 1. 20E+01
- 1. 10E+01 1.25E+01
- 5. 86E+02
- 5. 66E+01
- 1. 35E+02
- 1. 60E+01
- 1. 92E+01
- 1. 41E+01
- 1. 78E+01
- 6. 93E+02
- 7. 09E+01 6.33E+02
- 5. 99E+01 4.50E+01 4.97E+01
- 6. 61E+01 4.81E+02 2.20E+02
- 8. 73E+02
- 9. 51E+01 7.78E+01
- 6. 11E+01
- 4. 94E+01 8.97E+02
- 3.23E+02
- 7. 14E+02
- 9. 37E+01
- 1. 01E+02
- 6. 13E+01
- 9. 22E+01
- 5. 98E+02 2.43E+02
- 4. 54E+02
- 5. 11E+01 4.28E+01 4.23E+01 4.88E+01 5.65E+02
- 4.13E+02
- 3. 97E+02 4.59E+01
- 4. 64E+01
- 4. 25E+01 4.25E+01 4.40E+02 1.65E+02
- 5. 25E+02
- 6. 62E+01 6.58E+01
- 5. 13E+01
- 6. 48E+01 5.03E+02
- 2. 03E+02 DEV.)
C-16 STD DEV.
(pCi/kg)
MDC (pCi/kg)
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC STD DEV.
MDC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
(pCi/kg)
(pCi/kg)
SE 91 60040 05/08/01 Be-7
-7.84E+01 1.88E+02 6.42E+02 SE 91 60040 05/08/01 Co-58
-5.06E+01 1.77E+01 6.54E+01 SE 91 60040 05/08/01 Co-60 5.32E+01 1.04E+01 4.16E+01
- SE 91 60040 05/08/01 Cs-134 0.58E+00 1.54E+01 5.23E+01 SE 91 60040 05/08/01 Cs-137 1.07E+03 3.45E+01 7.14E+01
- SE 91 60041 05/08/01 Be-7
-1.76E+02 1.91E+02 6.58E+02 SE 91 60041 05/08/01 Co-58
-2.54E+01 2.19E+01 7.68E+01 SE 91 60041 05/08/01 Co-60 4.81E+01 1.38E+01 4.83E+01
- SE 91 60041 05/08/01 Cs-134 1.03E+01 1.53E+01 5.19E+01 SE 91 60041 05/08/01 Cs-137 1.39E+03 3.79E+01 7.16E+01
- SE 91 60042 05/08/01 Be-7
-9.02E+01 1.71E+02 5.85E+02 SE 91 60042 05/08/01 Co-58
-3.34E+00 1.77E+01 6.09E+01 SE 91 60042 05/08/01 Co-60 1.30E+01 1.46E+01 4.93E+01 SE 91 60042 05/08/01 Cs-134
-1.99E+01 1.77E+01 6.06E+01 SE 91 60042 05/08/01 Cs-137 1.99E+03 4.02E+01 6.47E+01
-8.77E+00 1.31E+01 4.54E+01 SE 91 62454 10/09/01 Co-60
-3.49E+00 1.39E+01 4.78E+01 SE 91 62454 10/09/01 Cs-134 4.41E+00 1.35E+01 4.52E+01 SE 91 62454 10/09/01 Cs-137 1.29E+03 3.11E+01 6.10E+01
- SE 91 62455 10/09/01 Be-7
-1.77E+02 2.36E+02 8.45E+02 SE 91 62455 10/09/01 Co-58 3.11E+00 2.50E+01 8.90E+01 SE 91 62455 10/09/01 Co-60 7.77E+00 2.56E+01 9.18E+01 SE 91 62455 10/09/01 Cs-134
-9.10E+00 2.15E+01 7.67E+01 SE 91 62455 10/09/01 Cs-137 1.51E+03 6.47E+01 1.07E+02
- SE 91 62456 10/09/01 Be-7
-1.16E+02 1.85E+02 6.52E+02 SE 91 62456 10/09/01 Co-58
-9.87E+00 1.79E+01 6.50E+01 SE 91 62456 10/09/01 Co-60
-5.83E+00 1.67E+01 6.12E+01 SE 91 62456 10/09/01 Cs-134 2.70E+00 1.58E+01 5.48E+01 SE 91 62456 10/09/01 Cs-137 1.97E+03 5.70E+01 8.36E+01
- Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-17
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE FOOD CROP
-8.
38E+00
-2. 58E+01
- 3. 47E+01
- 6. 34E+00
-1. 14E+01
- 8. 97E+03
-2. 43E+01
-2. 16E+01
- 0. OOE+00
- 1. 63E+01 1.46E+01
- 8. 12E+02
-1.42E+00
-5.06E+00
-7. 18E+00
- 3. 03E+00
- 3. 77E+00
- 1. 92E+03 1.71E+01 1.56E+01
- 1. 87E+01 1.43E+01
- 3. 96E+01 6.50E+02 1.33E+01 8.77E+00
- 1. 16E+01 1.40E+01
- 3. 67E+01 2.38E+02 7.48E+00
- 1. 05E+01
- 9. 72E+00
- 9. 74E+00 2.47E+01 2. 37E+02
- 6. 73E+01
- 7. 36E+01
- 5. 96E+01
- 5. 23E+01
- 1. 48E+02 7.04E+02
- 5. 71E+01 4.76E+01 4.4 6E+01
- 4. 75E+01
- 1. 31E+02 6.72E+02
- 3. 03E+01 4.28E+01
- 3. 94E+01 3.57E+01
- 9. 06E+01 4.OOE+02 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-18 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 08/14/01 08/14/01 08/14/01 08/14/01 08/14/01 08/14/01 TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF TF 13 13 13 11 13 13 13 13 13 13 13 13 21 21 21 21 21 21 61468 61468 61468 61468 61468 61468 61469 61469 61469 61469 61469 61469 61470 61470 61470 61470 61470 61470 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 08/14 08/14 08/14 08/14 08/14 08/14 08/14 08/14 08/14 08/14 08/14 08/14
/01
/01
/01
/01
/01
/01
/01
/01
/01
/01
/01
/01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE NUCLIDE MAPLE SYRUP
- 6. 38E-02
-2. 87E+00
- 0. 86E+00 1.78E+01
- 2. 05E+00 1.85E+03
- 0. 36E+00
-1.41E+00
- 1. 07E+00 1.42E+01
-4.88E+00
- 1. 53E+03 1.29E+00
- 1. 55E+00
- 1. 32E+00
- 2. 28E+00 4.81E+00
- 6. 47E+01 1.39E+00
- 1. 60E+00 1.43E+00 2.43E+00
- 8. 62E+00
- 6. 82E+01 4.70E+00
- 6. 29E+00
- 4. 62E+00 5.73E+00
- 1. 66E+01 5.91E+01 *
- 5. 12E+00
- 6. 46E+00
- 5. 04E+00 6.40E+00 *
- 3. 13E+01 5.86E+01
- Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-19 CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
MS MS MS MS MS MS MS MS MS MS MS MS 04/24/01 04/24/01 04/24/01 04/24/01 04/24/01 04/24/01 33 33 33 33 33 33 45 45 45 45 45 45 59772 59772 59772 59772 59772 59772 59773 59773 59773 59773 59773 59773 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 Co-58 Co-60 Cs-134 Cs-137 1-131 K-40 04 04 04 04 04 04
/19/01
/19/01
/19/01
/19/01
/19/01
/19/01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg) 57924 57924 57924 57924 01/03/01 01/03/01 01/03/01 01/03/01 Th-232 Ba-140 Cs-134 Cs-137 57924 01/03/01 1-131 57924 01/03/01 K-40 58317 58317 58317 58317 58317 58317 58712 58712 58712 58712 58712 58712 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 59693 02/27/01 59693 02/27/01 59343 59343 59343 59343 59343 59343 59753 59753 59753 59753 59753 59753 60346 60346 60346 60346 60346 60346 04 04 04 04 04 04
/04/01
/04/01
/04/01
/04/01
/04/01
/04/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Sr-89 Sr-90 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 61186 05/29/01 Sr-89 61186 05/29/01 Sr-90 8.21E+00
- 1. 89E+00
-1.
47E+00
- 8. 01E-02
-1. 37E+00
- 1. 31E+03
- 1. 22E+01 2.70E+00
-1. 21E+00
-1.4 6E+00 0.80E+00
- 1. 31E+03
-4.24E+00
- 1. 95E+00 0.55E+00
- 6. 43E+00
-3. 85E+00
- 1. 42E+03
- 7. 67E+00 2.44E+00 1.86E+00 1.53E+00
- 2. 61E+01
- 8. 87E+00
- 7. 24E+00
- 5. 68E+00 3.25E+00 1.19E+01 7.23E+01 7.71E+01 *
- 6. 87E+00
- 1. 95E+00
- 1. 60E+00
- 1. 80E+00
- 2. 37E+00
- 7. 33E+01
- 5. 81E+00
- 2. 61E+00
- 1. 70E+00 2 77E+00
- 3. 54E+00
- 6. 01E+01 2.22E+01 6.4 9E+00 6.38E+00
- 6. 90E+00
- 8. 37E+00 8.53E+01 *
- 2. 16E+01
- 9. 15E+00 6.02E+00
- 8. 89E+00
- 1. 28E+01 6.73E+01 6.84E+00 2.35E+00 6.94E+00 0.66E+00 0.43E+00 1.40E+00
-1.
63E+01
-3. 74E+00
-0. 61E+00
- 1. 34E+00
-5. 40E+00 1.29E+03
-0. 17E+00
- 0. 66E+00
-0. 93E+00
- 1. 82E+00
- 1. 42E+00
- 1. 34E+03
-2. 94E+00
-1. 16E+00
- 0. 92E+00
- 2. 05E+00
-0. 45E+00
- 1. 31E+03 6.70E+00
- 3. 09E+00
- 1. 70E+00
- 1. 60E+00
- 3. 71E+00
- 7. 31E+01
- 7. 98E+00 3.15E+00
- 1. 75E+00
- 1. 80E+00
- 3. 10E+00 7.48E+01
- 5. 90E+00 2.79E+00 1.54E+00
- 1. 69E+00 4.73E+00
- 6. 29E+01 2.83E+01 1.36E+01 6.53E+00
- 5. 59E+00 1.45E+01 8.67E+01
- 2. 90E+01
- 1. 19E+01
- 6. 81E+00
- 6. 18E+00
- 1. 09E+01 7.53E+01
- 2. 20E+01
- 1. 14E+01
- 5. 43E+00
- 5. 68E+00
- 1. 69E+01 7.20E+01 4.78E-02 2.82E+00 8.74E+00 2.89E+00 0.56E+00 1.75E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
C-20 MILK STD DEV.
(pCi/kg)
MDC (pCi/kg) 02 02 02 02 02 02
/27/01
/27/01
/27/01
/27/01
/27/01
/27/01 DEV.)
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg) 60832 60832 60832 60832 60832 60832 61276 61276 61276 61276 61276 61276 61717 61717 61717 61717 61717 61717 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM TM 62231 62231 62231 62231 62231 62231 62731 62731 62731 62731 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 Th-232 Ba-140 Cs-134 Cs-137 62731 10/31/01 1-131 62731 10/31/01 K-40 63052 63052 63052 63052 63052 63052 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Th-232 Ba-140 Cs-134 Cs-137 1-131 K-40 63661 11/28/01 Sr-89 63661 11/28/01 Sr-90 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21
- 7. 85E+00
- 3. 12E+00
- 1. 83E+00 1.76E+00
- 5. 94E+00
- 7. 39E+01
- 4. 34E+00 1.26E+00
- 1. 15E+00
- 1. 16E+00
- 1. 82E+00 5.20E+01
- 2. 95E+00
- 1. 18E+00
- 0. 75E+00
- 0. 78E+00
- 1. 87E+00 3.57E+01
- 2. 61E+01
- 1. 37E+01 6.34E+00
- 6. 68E+00
- 2. 12E+01
- 8. 18E+01
- 1. 11E+01
-2. 60E+00
- 1. 62E+00
-1. 16E+00
-0. 57E+00
- 1. 36E+03 3.54E+00
-1. 07E+00
- 0. 64E+00
-0. 60E+00
- 2. 46E+00
- 1. 39E+03
- 3. 08E+00 1.55E+00
-0. 23E+00
-0. 10E+00
- 0. 50E+00 1. 37E+03
-5. 04E+00
- 1. 22E+00
- 1. 4 9E+01
-0. 54E+00
- 2. 20E+00
- 1. 74E+00
- 3. 99E+00
- 1. 36E+03
- 5. 32E+00
- 1. 62E+00
-7.
OOE-02
- 1. 72E+00
-1. 61E+00 1.42E+03
- 5. 48E+00
- 1. 32E+00 0.26E+00
-1.
11E+00
- 3. 55E+00 1.40E+03
-1. 13E+00
- 0. 92E+00 3.16E+00 9.01E+00 0.57E+00 1.87E+00
- 6. 97E+00
- 1. 61E+00 1.57E+00
- 1. 72E+00
- 2. 30E+00
- 7. 33E+01
- 7. 85E+00 2.22E+00
- 1. 68E+00
- 2. 16E+00
- 2. 19E+01
- 7. 04E+00
- 5. 24E+00
- 5. 91E+00
- 7. 49E+00 7.02E+01 2.73E+01
- 8. 08E+00
- 6. 29E+00
- 7. 42E+00 2.78E+00 1.01E+01 7.53E+01 8.05E+01
- 4. 94E+00
- 1. 65E+00
- 1. 37E+00
- 1. 48E+00
- 1. 94E+00
- 5. 44E+01
- 1. 67E+01
- 5. 79E+00
- 4. 90E+00
- 5. 42E+00 6.30E+00
- 5. 95E+01 2.62E+00 9.15E+00 0.48E+00 1.55E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-21 STD DEV.
(pCi/kg)
MDC (pCi/kg) 1.49E+01
- 5. 23E+00
- 4. 04E+00
- 4. 26E+00
- 6. 06E+00 5.56E+01
- 9. 95E+00
- 3. 95E+00
- 2. 68E+00
- 2. 75E+00
- 6. 43E+00 3.70E+01
- 21 62523 08/30/01 Sr-89 21 62523 08/30/01 Sr-90 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC STD DEV.
MDC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
(pCi/kg)
(pCi/kg)
S...............................................................................................................................................
GROUND WATER WG 11 57929 01/03/01 Ba-140
-3.22E+00 2.65E+00 1.17E+01 WG 11 57929 01/03/01 Co-58
-1.40E+00 1.21E+00 5.19E+00 WG 11 57929 01/03/01 Co-60
-1.08E+00 1.39E+00 6.05E+00 WG 11 57929 01/03/01 Cs-134 0.72E+00 1.36E+00 5.00E+00 WG 11 57929 01/03/01 Cs-137
-0.49E+00 1.32E+00 5.15E+00 WG 11 57929 01/03/01 Fe-59 0.OOE+00 3.56E+00 1.35E+01 WG 11 57929 01/03/01 GR-B 2.84E+00 0.70E+00 2.18E+00 WG 11 57929 01/03/01 H-3
-1.02E+02 1.12E+02 3.78E+02 WG 11 57929 01/03/01 1-131
-1.05E+00 3.15E+00 1.15E+01 WG 11 57929 01/03/01 Mn-54 0.52E+00 1.37E+00 5.06E+00 WG 11 57929 01/03/01 Zn-65
-3.26E+00 4.61E+00 1.84E+01 WG 11 57929 01/03/01 Zr-95
-1.70E+00 2.46E+00 9.87E+00 WG 11 58322 01/30/01 Ba-140
-1.14E+00 2.78E+00 1.11E+01 WG 11 58322 01/30/01 Co-58
-3.13E+00 1.72E+00 7.10E+00 WG 11 58322 01/30/01 Co-60 0.55E+00 2.03E+00 7.49E+00 WG 11 58322 01/30/01 Cs-134
-0.96E+00 1.58E+00 6.26E+00 WG 11 58322 01/30/01 Cs-137
-1.14E+00 1.74E+00 6.64E+00 WG 11 58322 01/30/01 Fe-59 2.66E+00 4.57E+00 1.66E+01 WG 11 58322 01/30/01 GR-B 1.80E+00 1.01E+00 3.29E+00 WG 11 58322 01/30/01 H-3 0.OOE+00 1.12E+02 3.74E+02 WG 11 58322 01/30/01 1-131 3.18E+00 3.04E+00 1.03E+01 WG 11 58322 01/30/01 Mn-54
-2.55E+00 1.94E+00 7.60E+00 WG 11 58322 01/30/01 Zn-65
-3.19E+00 3.67E+00 1.47E+01 WG 11 58322 01/30/01 Zr-95 0.79E+00 2.78E+00 1.01E+01 WG 11 58726 02/26/01 Ba-140 0.OOE+00 2.50E+00 9.85E+00 WG 11 58726 02/26/01 Co-58
-5.06E+00 1.40E+00 6.59E+00 WG 11 58726 02/26/01 Co-60
-0.67E+00 2.02E+00 7.73E+00 WG 11 58726 02/26/01 Cs-134
-1.41E+00 1.35E+00 5.59E+00 WG 11 58726 02/26/01 Cs-137
-2.39E+00 1.49E+00 6.07E+00 WG 11 58726 02/26/01 Fe-59 0.88E+00 3.96E+00 1.51E+01 WG 11 58726 02/26/01 GR-B 2.99E+00 0.54E+00 1.65E+00 WG 11 58726 02/26/01 H-3
-1.08E+02 1.19E+02 4.01E+02 WG 11 58726 02/26/01 1-131
-1.80E+00 3.43E+00 1.26E+01 WG 11 58726 02/26/01 Mn-54
-0.27E+00 1.15E+00 4.51E+00 WG 11 58726 02/26/01 Zn-65
-5.90E+00 2.77E+00 1.26E+01 WG 11 58726 02/26/01 Zr-95
-2.82E+00 2.22E+00 9.34E+00 WG 11 59339 04/03/01 Ba-140
-0.86E+00 2.35E+00 9.15E+00 WG 11 59339 04/03/01 Co-58
-0.97E+00 0.97E+00 3.85E+00 WG 11 59339 04/03/01 Co-60 0.60E+00 1.12E+00 4.01E+00 WG 11 59339 04/03/01 Cs-134
-0.30E+00 0.93E+00 3.55E+00 WG 11 59339 04/03/01 Cs-137 0.77E+00 1.10E+00 3.83E+00 WG 11 59339 04/03/01 Fe-59
-4.43E+00 2.85E+00 1.21E+01 WG 11 59339 04/03/01 GR-B 4.23E+00 0.54E+00 1.58E+00 WG 11 59339 04/03/01 H-3
-1.07E+02 1.05E+02 3.53E+02 WG 11 59339 04/03/01 1-131
-2.04E+00 3.54E+00 1.29E+01 WG 11 59339 04/03/01 Mn-54 0.58E+00 0.94E+00 3.31E+00 WG 11 59339 04/03/01 Zn-65 3.38E+00 4.78E+00 1.62E+01 WG 11 59339 04/03/01 Zr-95 2.20E+00 1.84E+00 6.23E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-22
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
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 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 1i WG 11 61272 08/01/01 Ba-140 1.45E+00 WG 11 61272 08/01/01 Co-58
-1.54E+00 WG 11 61272 08/01/01 Co-60
-0.12E+00 WG 11 61272 08/01/01 Cs-134 0.16E+00 WG 11 61272 08/01/01 Cs-137
-1.76E+00 WG 11 61272 08/01/01 Fe-59
-4.71E+00 WG 11 61272 08/01/01 GR-B 3.23E+00 WG 11 61272 08/01/01 H-3
-1.31E+02 WG 11 61272 08/01/01 1-131 2.32E+00 WG 11 61272 08/01/01 Mn-54 0.14E+00 WG 11 61272 08/01/01 Zn-65 0.46E+00 WG 11 61272 08/01/01 Zr-95
-0.48E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
59758 59758 59758 59758 59758 59758 59758 59758 59758 59758 59758 59758 60350 60350 60350 60350 60350 60350 60350 60350 60350 60350 60350 60350 60849 60849 60849 60849 60849 60849 60849 60849 60849 60849 60849 60849
- 1. 30E+01
- 6. 12E+00 7.76E+00
- 6. 52E+00
- 8. 52E+00 2.23E+01 1.62E+00 *
- 3. 51E+02
- 1. 21E+01
- 7. 72E+00
- 1. 54E+01
- 9. 42E+00 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
- 0. OOE+00
-1. 37E+00
- 1. 61E+00
-3. 56E-02
-4.
71E+00
-6. 72E+00
- 2. 92E+00 4.40E+01 4.19E+00
-2. 04E+00
-5. 13E+00
- 1. 49E+00 0.45E+00
-0. 30E+00
- 0. 64E+00
-1.76E+00
-3. 88E+00
-0. 90E+00
- 2. 38E+00
-7. 11E+01
- 1. 45E+00
- 0. OOE+00
-3. 18E+00
- 1. 89E+00
- 0. OOE+00
-2. 96E+00
-0. 69E+00
-1.
65E+00
-2. 60E+00
-2.
10E+00
- 2. 49E+00
- 0. OOE+00
- 1. 74E+00
- 0. 26E+00
-5. 88E+00
-4. 87E+00 DEV.)
C-23 STD DEV.
(pCi/kg)
MDC (pCi/kg)
- 3. 44E+00
- 1. 53E+00 2.20E+00 1.74E+00
- 2. 13E+00
- 5. 4 6E+00
- 0. 53E+00
- 1. 06E+02
- 3. 60E+00
- 2. O1E+00
- 3. 74E+00
- 2. 62E+00
- 2. 68E+00 1 O1E+00
- 1. 18E+00
- 1. 07E+00
- 1. 19E+00
- 3. 02E+00
- 0. 64E+00
- 1. 14E+02
- 3. 50E+00
- 0. 97E+00
- 2. 53E+00
- 1. 84E+00
- 3. 52E+00
- 1. 40E+00
- 1. 43E+00
- 1. 40E+00
- 1. 63E+00 4.34E+00 0.55E+00
- 8. 34E+01 4.75E+00
- 1. 53E+00
- 3. 87E+00
- 2. 75E+00
- 1. 57E+00
- 1. 05E+00
- 1. 08E+00
- 1. 02E+00
- 1. 19E+00
- 2. 27E+00
- 0. 54E+00
- 1. 06E+02
- 2. 12E+00
- 1. 10E+00
- 6. 18E+00
- 1. 85E+00
- 3. 57E+00
- 9. 97E+00
- 6. 30E+00
- 1. 40E+01
- 6. 29E+00
- 5. 98E+00
- 5. 89E+i00
- 6. 64E+00 1.79E+01
- 1. 72E+00
- 2. 79E+02
- 1. 68E+01
- 5. 68E+00
- 1. 60E+01
- 1. 17E+01
- 5. 47E+00 4.21E+00 4. 10E+00
- 3. 75E+00 4.62E+00
- 1. 03E+01
- 1. 64E+00
- 3. 55E+02
- 7. 11E+00
- 3. 97E+00
- 2. 12E+01
- 6. 90E+00
- 9. 92E+00
- 3. 83E+00 4.25E+00
- 4. 36E+00 4.99E+00
- 1. 17E+01
- 2. OOE+00
- 3. 82E+02
- 1. 23E+01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC STD DEV.
MDC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
(pCi/kg)
(pCi/kg)
WG 11 61714 08/30/01 Ba-140 3.80E+00 2.60E+00 8.59E+00 WG 11 61714 08/30/01 Co-58
-2.10E+00 1.14E+00 4.91E+00 WG 11 61714 08/30/01 Co-60 0.17E+00 1.43E+00 5.38E+00 WG 11 61714 08/30/01 Cs-134
-1.05E+00 1.14E+00 4.65E+00 WG 11 61714 08/30/01 Cs-137 2.30E+00 1.35E+00 4.40E+00 WG 11 61714 08/30/01 Fe-59
-3.26E+00 3.49E+00 1.46E+01 WG 11 61714 08/30/01 GR-B 2.81E+00 0.63E+00 1.97E+00 WG 11 61714 08/30/01 H-3 6.12E+01 9.03E+01 2.83E+02 WG 11 61714 08/30/01 1-131 0.35E+00 3.25E+00 1.16E+01 WG 11 61714 08/30/01 Mn-54
-0.12E+00 1.08E+00 4.11E+00 WG 11 61714 08/30/01 Zn-65
-1.06E+00 6.68E+00 2.34E+01 WG 11 61714 08/30/01 Zr-95 0.72E+00 2.33E+00 8.46E+00 WG 11 62236 10/03/01 Ba-140
-2.11E+00 1.94E+00 8.13E+00 WG 11 62236 10/03/01 Co-58
-4.34E+00 1.34E+00 5.88E+00 WG 11 62236 10/03/01 Co-60 0.14E+00 1.48E+00 5.58E+00 WG 11 62236 10/03/01 Cs-134
-1.77E+00 1.46E+00 5.79E+00 WG 11 62236 10/03/01 Cs-137 0.78E+00 1.47E+00 5.18E+00 WG 11 62236 10/03/01 Fe-59 0.76E+00 4.13E+00 1.52E+01 WG 11 62236 10/03/01 GR-B 3.73E+00 0.43E+00 1.04E+00 WG 11 62236 10/03/01 H-3 9.94E+01 8.93E+01 2.80E+02 WG 11 62236 10/03/01 1-131
-0.83E+00 1.97E+00 7.20E+00 WG 11 62236 10/03/01 Mn-54 0.55E+00 1.23E+00 4.41E+00 WG 11 62236 10/03/01 Zn-65 3.85E+00 8.11E+00 2.76E+01 WG 11 62236 10/03/01 Zr-95 8.49E-02 2.23E+00 8.22E+00 WG 11 62735 10/31/01 Ba-140
-0.59E+00 1.77E+00 6.76E+00 WG 11 62735 10/31/01 Co-58
-1.38E+00 1.21E+00 4.66E+00 WG 11 62735 10/31/01 Co-60 1.56E+00 1.33E+00 4.49E+00 WG 11 62735 10/31/01 Cs-134 0.44E+00 1.16E+00 4.14E+00 WG 11 62735 10/31/01 Cs-137
-1.86E+00 1.38E+00 5.22E+00 WG 11 62735 10/31/01 Fe-59 7.38E+00 2.87E+00 8.41E+00 WG 11 62735 10/31/01 GR-B 3.22E+00 0.45E+00 1.15E+00 WG 11 62735 10/31/01 H-3
-7.60E+01 1.04E+02 3.34E+02 WG 11 62735 10/31/01 1-131 1.09E+00 2.09E+00 7.20E+00 WG 11 62735 10/31/01 Mn-54 0.14E+00 1.OOE+00 3.65E+00 WG 11 62735 10/31/01 Zn-65
-5.15E+00 6.03E+00 2.13E+01 WG 11 62735 10/31/01 Zr-95 0.61E+00 1.99E+00 7.11E+00 WG 11 63056 11/28/01 Ba-140 2.94E+00 1.71E+00 5.53E+00 WG 11 63056 11/28/01 Co-58
-0.52E+00 0.97E+00 3.74E+00 WG 11 63056 11/28/01 Co-60
-0.76E+00 1.40E+00 5.31E+00 WG 11 63056 11/28/01 Cs-134 1.68E+00 1.20E+00 3.98E+00 WG 11 63056 11/28/01 Cs-137
-0.26E+00 1.20E+00 4.38E+00 WG 11 63056 11/28/01 Fe-59 2.34E+00 2.64E+00 9.27E+00 WG 11 63056 11/28/01 GR-B 3.10E+00 0.35E+00 0.91E+00 WG 11 63056 11/28/01 H-3
-5.48E+01 1.12E+02 3.50E+02 WG 11 63056 11/28/01 1-131 2.35E+00 2.16E+00 7.26E+00 WG 11 63056 11/28/01 Mn-54 2.02E+00 1.27E+00 4.18E+00 WG 11 63056 11/28/01 Zn-65 1.86E+00 6.63E+00 2.26E+01 WG 11 63056 11/28/01 Zr-95
-3.91E+00 1.81E+00 7.49E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-24
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WG WG WG WG WG WG WG WG WG WG
- 6. 79E+00
- 3. 74E+00 3.33E+00
- 3. 54E+00 4 49E+00
- 7. 79E+00
- 2. 28E+00
- 3. 81E+02
- 7. 82E+00 4 11E+00
- 1. 96E+01
- 6. 4 6E+00
- 5. 32E+00
- 3. 54E+00
- 4. 24E+00
- 3. 61E+00
- 4. 07E+00
- 9. 98E+00
- 3. 69E+00 3.73E+02 5.73E+00 3.21E+00 8.48E+00
- 6. 32E+00 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 57930 57930 57930 57930 57930 57930 57930 57930 57930 57930 57930 57930 58323 58323 58323 58323 58323 58323 58323 58323 58323 58323 58323 58323 58727 58727 58727 58727 58727 58727 58727 58727 58727 58727 58727 58727 59340 59340 59340 59340 59340 59340 59340 59340 59340 59340 59340 59340 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-25 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
- 1. 64E+00
-0. 40E+00
- 2. 15E+00 1.23E+00
-0. 31E+00
- 0. 69E+00
- 3. 44E+00
-6.
85E+01
-0. 22E+00
-0.29E+00 4.68E+00
- 1. 68E+00
- 1. 47E+00
-0.43E+00
-1. 12E+00
-4. 02E-02
-1. 58E+00
-1.72E+00 2.42E+00
- 1. 02E+02 2.71E+00
-0. 14E+00
-4.49E+00
-0. 67E+00
- 1. 61E+00
-1.80E+00
-1. 94E+00
-4. 29E+00
-1. 61E+00
-1. 31E+00
- 3. 38E+00
- 3. 59E+01
- 9. 03E+00
- 0. 62E+00
- 2. 33E+00
-3. 37E+00
- 2. 69E+00
-1. 06E+00 0.79E+00
-0. 94E+00
-6. 21E-02
- 7. 83E+00
- 3. 66E+00 2' 15E+02
-1. 61E+01
-0. 64E+00
-2. 51E+00
- 0. 14E+00
- 1. 94E+00
- 0. 98E+00
- 1. 07E+00
- 1. 04E+00
- 1. 23E+00
- 2. 14E+00
- 0. 75E+00
- 1. 13E+02 2.19E+00
- 1. 11E+00 5.80E+00
- 1. 87E+00
- 1. 52E+00
- 0. 92E+00
- 1. 03E+00
- 0. 96E+00
- 1. 02E+00 2.47E+00
- 1. 14E+00
- 1. 13E+02
- 1. 74E+00
- 0. 85E+00
- 1. 93E+00
- 1. 66E+00 4. 11E+00
- 2. 08E+00
- 2. 08E+00
- 1. 98E+00
- 2. 02E+00
- 5. 27E+00
- 0. 55E+00
- 1. 20E+02
- 4. 74E+00
- 1. 85E+00
- 5. 03E+00
- 3. 24E+00 3.14E+00
- 1. 30E+00 1.36E+00 1.28E+00
- 1. 32E+00 4.23E+00 0.54E+00 1.08E+02 4.67E+00
- 1. 33E+00 7.21E+00
- 2. 11E+00
- 1. 52E+01
- 8. 18E+00
- 8. 69E+00
- 8. 57E+00 7.82E+00
- 2. 10E+01
- 1. 65E+00
- 3. 99E+02 1.53E+01
- 6. 75E+00
- 1. 74E+01
- 1. 31E+01
- 1. 11E+01
- 5. 16E+00
- 4. 94E+00
- 5. 06E+00
- 4. 87E+00
- 1. 34E+01
- 1. 62E+00 3.55E+02
- 1. 90E+01
- 5. 07E+00
- 2. 53E+01
- 7. 91E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE WG 12 59759 05/02/01 Ba-140
-2.83E+00 WG 12 59759 05/02/01 Co-58
-0.32E+00 WG 12 59759 05/02/01 Co-60 0.78E+00 WG 12 59759 05/02/01 Cs-134
-0.10E+00 WG 12 59759 05/02/01 Cs-137 0.80E+00 WG 12 59759 05/02/01 Fe-59 0.75E+00 WG 12 59759 05/02/01 GR-B
- 4. 13E+00 WG 12 59759 05/02/01 H-3 3.74E+02 WG 12 59759 05/02/01 1-131 0.OOE+00 WG 12 59759 05/02/01 Mn-54 0.57E+00 WG 12 59759 05/02/01 Zn-65 0.OOE+00 WG 12 59759 05/02/01 Zr-95 4.79E+00 WG 12 60351 05/29/01 Ba-140 6.33E+00 WG 12 60351 05/29/01 Co-58 2.04E+00 WG 12 60351 05/29/01 Co-60 1.13E+00 WG 12 60351 05/29/01 Cs-134 1.08E+00 WG 12 60351 05/29/01 Cs-137
-2.37E+00 WG 12 60351 05/29/01 Fe-59
-3.23E+00 WG 12 60351 05/29/01 GR-B 3.54E+00 WG 12 60351 05/29/01 H-3 7.08E+01 WG 12 60351 05/29/01 1-131 3.01E+00 WG 12 60351 05/29/01 Mn-54
-1.33E+00 WG 12 60351 05/29/01 Zn-65 7.36E+00 WG 12 60351 05/29/01 Zr-95
-3.04E+00 WG 12 60850 07/03/01 Ba-140 0.21E+00 WG 12 60850 07/03/01 Co-58
-0.77E+00 WG 12 60850 07/03/01 Co-60
-0.53E+00 WG 12 60850 07/03/01 Cs-134
-0.68E+00 WG 12 60850 07/03/01 Cs-137
-1.03E+00 WG 12 60850 07/03/01 Fe-59 2.16E+00 WG 12 60850 07/03/01 GR-B 4.49E+00 WG 12 60850 07/03/01 H-3 2.55E+02 WG 12 60850 07/03/01 1-131 0.99E+00 WG 12 60850 07/03/01 Mn-54
-0.51E+00 WG 12 60850 07/03/01 Zn-65 3.12E+00 WG 12 60850 07/03/01 Zr-95
-1.22E+00 WG 12 61273 08/01/01 Ba-140
-1.82E+00 WG 12 61273 08/01/01 Co-58 0.OOE+00 WG 12 61273 08/01/01 Co-60 2.62E+00 WG 12 61273 08/01/01 Cs-134 0.78E+00 WG 12 61273 08/01/01 Cs-137
-3.90E+00 WG 12 61273 08/01/01 Fe-59 2.47E+00 WG 12 61273 08/01/01 GR-B 6.25E+00 WG 12 61273 08/01/01 H-3 9.59E+01 WG 12 61273 08/01/01 1-131 2.16E+00 WG 12 61273 08/01/01 Mn-54 0.42E+00 WG 12 61273 08/01/01 Zn-65 1.91E+00 WG 12 61273 08/01/01 Zr-95 0.85E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD
- 1. 57E+00
- 1. 05E+00 1.27E+00 0.89E+00
- 1. 19E+00
- 2. 75E+00
- 0. 58E+00
- 1. 09E+02 1.76E+00
- 1. 09E+00 1.84E+00
- 1. 83E+00
- 2. 63E+00 1.84E+00
- 1. 14E+00
- 1. 06E+00 1. 34E+00
- 3. 86E+00
- 0. 71E+00
- 1. 15E+02
- 4. 32E+00 1.23E+00
- 6. 96E+00
- 2. 17E+00
- 1. 68E+00 0.77E+00
- 0. 61E+00
- 0. 65E+00
- 0. 65E+00
- 1. 92E+00
- 0. 64E+00
- 8. 55E+01
- 3. 38E+00
- 0. 63E+00
- 3. 19E+00
- 1. 15E+00
- 1. 77E+00 1.40E+00
- 1. 28E+00
- 1. 28E+00
- 1. 37E+00
- 2. 36E+00
- 0. 66E+00 1.08E+02
- 2. 28E+00 1.20E+00 6.8 6E+00
- 1. 97E+00 DEV.)
C-26 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 6.87E+00
- 3. 94E+00 4.50E+00
- 3. 39E+00
- 4. 15E+00
- 1. 02E+01 1.72E+00 3.53E+02
- 6. 32E+00 3.86E+00 6.98E+00
- 5. 49E+00
- 7. 94E+00
- 6. 17E+00
- 3. 94E+00
- 3. 62E+00
- 5. 12E+00
- 1. 48E+01 2.17E+00 *
- 3. 81E+02
- 1. 47E+01
- 4. 65E+00 2.32E+01 8.42E+00
- 6. 05E+00 2.79E+00
- 2. 30E+00 2.39E+00
- 2. 40E+00
- 6. 48E+00
- 1. 90E+00
- 2. 78E+02
- 1. 16E+01
- 2. 28E+00
- 1. 06E+01
- 4. 22E+00
- 7. 12E+00
- 5. OOE+00
- 4. 04E+00 4 46E+00
- 5. 48E+00
- 8. 21E+00
- 1. 89E+00
- 3. 57E+02
- 7. 71E+00 4.26E+00
- 2. 33E+01 6.97E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 12 12 12 12 12 12 12 12 12 12 12 12 61715 61715 61715 61715 61715 61715 61715 61715 61715 61715 61715 61715 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 WG WG WG WG WG WG WG WG WG WG 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 62736 62736 62736 62736 62736 62736 62736 62736 62736 62736 62736 62736 63057 63057 63057 63057 63057 63057 63057 63057 63057 63057 63057 63057 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 2.26E+00
- 0. 60E+00
-2. 66E+00
- 2. 53E+00
-0. 45E+00
-2. 28E+00 5.80E+00
- 1. 99E+02
- 1. 35E+00
-1. 57E+00
-5. 90E+00
- 1. 69E+00
- 0. OOE+00
- 1. 59E+00 1.26E+00
-0. 72E+00
-1. 60E+00 0.81E+00 6.87E+00
- 2. 98E+02
- 1. 61E+00
-0.77E+00
-6. 45E+00 1.81E+00
-1. 13E+00
-1.
73E+00
- 1. 99E+00
- 0. 16E+00
-0. 73E+00
- 2. 94E+00 6.30E+00
- 0. 00E+00
-1. 41E+00
-0. 55E+00
- 2. 68E+00 1.40E+00
-0. 65E+00
- 0. 94E+00 0.29E+00
-0.
11E+00 1.OOE+00
- 0. 11E+00 6.73E+00
- 1. 11E+02 0.50E+00
-1. 16E+00
-0. 32E+00
- 3. 16E+00
- 2. 50E+00
- 1. 54E+00
- 1. 42E+00
- 1. 63E+00
- 1. 85E+00 4.71E+00
- 0. 72E+00
- 9. 09E+01
- 4. 11E+00 1.28E+00
- 3. 28E+00
- 2. 32E+00
- 2. 17E+00
- 1. 16E+00
- 1. 4 6E+00
- 1. 58E+00
- 1. 38E+00
- 4. 36E+00
- 0. 60E+00
- 9. 09E+01
- 1. 90E+00
- 1. 48E+00 3.53E+00 2.49E+00
- 1. 39E+00
- 1. 04E+00
- 1. 16E+00 1.20E+00 1.06E+00 2.45E+00
- 0. 62E+00 1.25E+02 1.80E+00
- 0. 96E+00
- 5. 02E+00
- 1. 58E+00
- 1. 35E+00
- 0. 92E+00
- 0. 95E+00
- 0. 96E+00
- 0. 99E+00
- 2. 64E+00 0.4 9E+00
- 1. 15E+02 1.59E+00 0.77E+00
- 2. 75E+00 1.74E+00
- 9. 04E+00
- 5. 63E+00
- 6. 71E+00 5.34E+00 6.86E+00
- 1. 90E+01
- 2. 13E+00
- 2. 82E+02 1.45E+01
- 5. 41E+00
- 1. 44E+01
- 8. 35E+00
- 8. 62E+00
- 3. 87E+00
- 5. 25E+00
- 6. 20E+00
- 5. 67E+00
- 1. 66E+01
- 1. 37E+00
- 2. 79E+02
- 6. 58E+00
- 5. 78E+00
- 1. 52E+01
- 8. 84E+00
- 5. 70E+00
- 4. 18E+00 3.75E+00
- 4. 32E+00
- 4. 02E+00
- 8. 36E+00 1.43E+00 3.86E+02 6.63E+00
- 3. 66E+00
- 1. 71E+01 5.48E+00
- 5. 39E+00
- 3. 15E+00
- 3. 54E+00
- 3. 59E+00
- 3. 40E+00 9.88E+00 1.11E+00 *
- 3. 54E+02
- 5. 60E+00
- 3. 20E+00
- 1. OOE+01
- 5. 60E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-27 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237 12 62237
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE RIVER WATER 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 WR WR WR WR WR WR WR 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-28 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 57926 57926 57926 57926 57926 57926 57926 57926 57926 57926 57926 58318 58318 58318 58318 58318 58318 58318 58318 58318 58318 58318 58723 58723 58723 58723 58723 58723 58723 59631 58723 58723 58723 58723 59336 59336 59336 59336 59336 59336 59336 59336 59336 59336 59336 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95
-1.
85E+00
-4.
94E+00
- 1. 88E+00
- 0. 58E+00
-5.73E+00
-1.29E+00
- 1. 42E+00
-4.59E+00
-0. 52E+00
-3. 27E+00
-8.
12E+00
-0.54E+00
-2. OOE+00
-1. 94E+00
-0. 47E+00
- 0. 14E+00
- 1. 96E+00 2.22E+00
-2.76E+00
-1.
38E+00
- 1. 66E+00
-1.
88E+00
-1.24E+00
-1. 66E+00
-2. 14E+00
- 0. 82E+00
-0. 17E+00
-0. 93E+00 0.24E+00
- 3. 89E+02
-4.
50E+00
- 0. OOE+00
-2.09E+00
- 2. 35E+00
-2. 64E+00
-7. 14E-02 3.42E+00
-1.32E+00
-2.28E+00
-2.23E+00 1.39E+00
-1. 16E+00
- 0. 52E+00
-6. 54E+00 0.68E+00
- 3. 09E+00
- 2. 09E+00
- 2. 48E+00
- 2. 15E+00
- 2. 47E+00 4. 08E+00
- 0. 63E+00
- 4. 35E+00
- 2. 24E+00
- 4. 09E+00
- 3. 07E+00
- 1. 42E+00
- 1. 19E+00
- 1. 13E+00
- 1. 23E+00
- 1. 07E+00
- 3. 02E+00
- 0. 95E+00
- 1. 93E+00 1.09E+00
- 6. 24E+00
- 1. 74E+00
- 1. 90E+00
- 1. OlE+00
- 1. 31E+00
- 1. 32E+00
- 1. 31E+00
- 3. 22E+00
- 0. 45E+00
- 3. 67E+02
- 2. 70E+00
- 1. 04E+00
- 2. 33E+00
- 1. 98E+00
- 3. 41E+00
- 1. 36E+00
- 1. 80E+00
- 1. 48E+00
- 1. 57E+00
- 4. 62E+00
- 0. 46E+00
- 4. 57E+00
- 1. 32E+00
- 4. 13E+00
- 2. 17E+00
- 1. 24E+01
- 8. 61E+00
- 8. 68E+00
- 7. 71E+00
- 9. 70E+00
- 1. 55E+01
- 2. 02E+00
- 1. 58E+01
- 8. 19E+00
- 1. 61E+01
- 1. 32E+01
- 5. 57E+00
- 4. 69E+00
- 4. 71E+00 4. 58E+00
- 3. 88E+00
- 1. 07E+01
- 3. 05E+00 7 16E+00
- 4. 23E+00
- 2. 13E+01
- 6. 81E+00 7 81E+00
- 4. 30E+00
- 5. 54E+00
- 4. 68E+00
- 4. 80E+00 1.26E+01
- 1. 51E+00 1.22E+03
- 1. 04E+01
- 3. 88E+00
- 9. 39E+00
- 6. 72E+00
- 1. 47E+01
- 5. 28E+00
- 5. 61E+00
- 6. 03E+00
- 6. 36E+00
- 1. 89E+01 1.45E+00 *
- 1. 69E+01 4.88E+00
- 1. 70E+01
- 8. 22E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC STD DEV.
MDC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
(pCi/kg)
(pCi/kg)
WR 11 59754 05/02/01 Ba-140
-0.86E+00 1.69E+00 6.58E+00 WR 11 59754 05/02/01 Co-58
-0.14E+00 1.15E+00 4.19E+00 WR 11 59754 05/02/01 Co-60
-1.66E+00 1.01E+00 4.31E+00 WR 11 59754 05/02/01 Cs-134
-0.47E+00 1.07E+00 4.04E+00 WR 11 59754 05/02/01 Cs-137
-1.30E+00 1.18E+00 4.48E+00 WR 11 59754 05/02/01 Fe-59
-2.05E+00 2.37E+00 9.73E+00 WR 11 59754 05/02/01 GR-B 1.06E+00 0.46E+00 1.49E+00 WR 11 59754 05/02/01 1-131 0.36E+00 1.90E+00 6.67E+00 WR 11 59754 05/02/01 Mn-54
-0.55E+00 0.98E+00 3.73E+00 WR 11 59754 05/02/01 Zn-65
-1.51E+00 6.74E+00 2.32E+01 WR 11 59754 05/02/01 Zr-95 0.65E+00 1.77E+00 6.34E+00 WR 11 60347 05/29/01 Ba-140 3.56E+00 3.78E+00 1.34E+01 WR 11 60347 05/29/01 Co-58 0.11E+00 1.24E+00 4.82E+00 WR 11 60347 05/29/01 Co-60 0.89E+00 1.42E+00 5.27E+00 WR 11 60347 05/29/01 Cs-134
-0.51E+00 1.11E+00 4.65E+00 WR 11 60347 05/29/01 Cs-137 1.03E+00 1.40E+00 4.95E+00 WR 11 60347 05/29/01 Fe-59
-9.02E+00 4.77E+00 2.16E+01 WR 11 60347 05/29/01 GR-B 0.76E+00 0.59E+00 1.93E+00 WR 11 61092 05/29/01 H-3 6.68E+02 4.54E+02 1.50E+03 WR 11 60347 05/29/01 1-131
-7.65E+00 4.82E+00 1.89E+01 WR 11 60347 05/29/01 Mn-54 2.36E+00 1.46E+00 4.76E+00 WR 11 60347 05/29/01 Zn-65
-0.66E+00 3.17E+00 1.25E+01 WR 11 60347 05/29/01 Zr-95
-3.56E+00 2.76E+00 1.14E+01 WR 11 60846 07/03/01 Ba-140
-1.03E+01 3.86E+00 1.88E+01 WR 11 60846 07/03/01 Co-58
-0.95E+00 1.30E+00 5.39E+00 WR 11 60846 07/03/01 Co-60 0.75E+00 1.72E+00 6.40E+00 WR 11 60846 07/03/01 Cs-134 2.79E+00 1.23E+00 3.52E+00 WR 11 60846 07/03/01 Cs-137
-0.21E+00 1.60E+00 6.OOE+00 WR 11 60846 07/03/01 Fe-59 2.56E+00 4.08E+00 1.52E+01 WR 11 60846 07/03/01 GR-B 1.19E+00 0.50E+00 1.61E+00 WR 11 60846 07/03/01 1-131
-1.92E+00 5.15E+00 1.91E+01 WR 11 60846 07/03/01 Mn-54
-1.84E+00 1.47E+00 6.05E+00 WR 11 60846 07/03/01 Zn-65
-2.65E+00 3.25E+00 1.41E+01 WR 11 60846 07/03/01 Zr-95
-3.59E+00 2.79E+00 1.16E+01 WR 11 61269 08/01/01 Ba-140
-1.87E+00 1.91E+00 8.06E+00 WR 11 61269 08/01/01 Co-58
-2.50E+00 1.16E+00 5.OOE+00 WR 11 61269 08/01/01 Co-60 0.69E+00 1.53E+00 5.58E+00 WR 11 61269 08/01/01 Cs-134
-1.85E+00 1.13E+00 4.83E+00 WR 11 61269 08/01/01 Cs-137
-0.31E+00 1.16E+00 4.40E+00 WR 11 61269 08/01/01 Fe-59 5.50E+00 3.58E+00 1.18E+01 WR 11 61269 08/01/01 GR-B 1.34E+00 0.46E+00 1.46E+00 WR 11 61269 08/01/01 1-131
-1.79E+00 2.12E+00 7.89E+00 WR 11 61269 08/01/01 Mn-54 1.21E+00 1.15E+00 3.97E+00 WR 11 61269 08/01/01 Zn-65 1.09E+01 6.66E+00 2.19E+01 WR 11 61269 08/01/01 Zr-95 0.21E+00 2.03E+00 7.55E+00 Radioactivity detected in sample (i.e., CONC > 3 STD.
DEV.)
C-29
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
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 WR WR WR WR WR WR WR 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 ii 61711 61711 61711 61711 61711 61711 61711 62534 61711 61711 61711 61711 62233 62233 62233 62233 62233 62233 62233 62233 62233 62233 62233 62732 62732 62732 62732 62732 62732 62732 62732 62732 62732 62732 63053 63053 63053 63053 63053 63053 63053 63053 63053 63053 63053
- 8. 22E+00 3.4 1E+00
- 3. 51E+00
- 2. 79E+00
- 3. 77E+00
- 9. 84E+00 1.72E+00
- 8. 77E+02
- 7. 97E+00
- 3. 95E+00
- 9. 86E+00
- 5. 91E+00 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-30 STD DEV.
(pCi/kg)
MDC (pCi/kg)
Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95
-4.
03E+00
-1. 14E+00
-0.41E+00 2.34E+00
-0. 64E+00 0.39E+00
- 1. 03E+00
- 2. OOE+02
- 2. 31E+00
-0. 87E+00
-7.
OOE+00 0.71E+00
- 0. 55E+00
-0.31E+00
-0. 37E+00
-1. 16E+00
-0. 61E+00 2. 54E+00
- 2. 15E+00
-0. 66E+00
-1.29E+00
-4.
48E+00
- 0. 38E+00
-1. 60E+00
-0. 63E+00
-0. 62E+00 1.74E+00
-3. 17E+00
-2. 42E+00
- 2. 38E+00
- 2. 52E+00
-0. 82E+00
-6. 71E+00
- 1. 98E+00
- 3. 47E+00
-1. OOE+00
- 0. 55E+00
-1.28E+00
-1.
68E+00
-3. 45E+00 1.83E+00
- 0. 90E+00
- 0. 27E+00
-3. 59E+00
- 1. 03E+00
- 1. 83E+00 0.81E+00 0.86E+00
- 0. 94E+00
- 0. 98E+00
- 2. 60E+00
- 0. 53E+00
- 2. 76E+02
- 2. 34E+00
- 1. 02E+00 2.21E+00
- 1. 64E+00 1.4 1E+00
- 0. 88E+00
- 1. 14E+00
- 0. 86E+00
- 0. 96E+00
- 3. 01E+00 0.36E+00
- 1. 62E+00
- 0. 87E+00
- 2. 04E+00
- 1. 49E+00
- 1. 73E+00
- 1. 18E+00 1.28E+00
- 1. 35E+00
- 1. 43E+00
- 3. 47E+00
- 0. 41E+00
- 2. 09E+00
- 1. 09E+00
- 2. 95E+00 1.84E+00
- 2. 07E+00
- 1. 11E+00
- 1. 10E+00
- 1. 44E+00 1.43E+00 3.45E+00
- 0. 30E+00
- 2. 36E+00
- 1. 39E+00
- 2. 84E+00 1.78E+00
- 5. 21E+00
- 3. 38E+00 4.37E+00
- 3. 61E+00
- 3. 68E+00
- 1. 05E+01 1.02E+00
- 5. 87E+00
- 3. 57E+00 8.79E+00
- 5. 48E+00
- 7. 43E+00 4.59E+00
- 5. 16E+00
- 4. 53E+00
- 5. 84E+00 1.40E+01 1.09E+00
- 7.01E+00
- 4. 34E+00 1.27E+01
- 6. 35E+00
- 6. 67E+00 4.49E+00 4.12E+00
- 5. 63E+00 5.56E+00
- 1. 43E+01 0.85E+00
- 8.22E+00
- 5. 02E+00
- 1. 16E+01 6.4 6E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE NUCLIDE 11 63603 11 63603 11 63603 11 63603 11 63603 11 63603 11 63603 11 63674 11 63603 11 63603 11 63603 11 63603 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 01/02/02 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
-0.83E+00
-1. 30E+00
-1.
68E+00
-2.87E+00
- 0. 95E+00
- 1. 54E+00
- 3. 40E+00 4.77E+02
-2.55E+00
- 1. 60E+00
-1.49E+00
- 2. 61E+00
- 3. 28E+00
- 1. 37E+00
- 1. 64E+00
- 1. 32E+00
- 1. 33E+00
- 3. 78E+00 0.58E+00 3.8 9E+02
- 3. 91E+00 1.36E+00
- 3. 65E+00
- 2. 56E+00 1.26E+01
- 5. 41E+00 6.60E+00
- 5. 68E+00
- 4. 67E+00
- 1. 40E+01 1.62E+00
- 1.29E+03 1.43E+01 4.60E+00
- 1. 40E+01
- 8. 78E+00 Radioactivity detected in sample (i.e., CONC > 3 STD.
DEV.)
C-31 CONC (pCi/kg)
STD DEV.
(pCi/kg)
WR WR WR WR WR WR WR WR WR WR WR WR MDC (pCi/kg)
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WR WR WR WR WR WR WR Radioactivity detected in sample (i.e.,
CONC > 3 STD.
21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 57927 57927 57927 57927 57927 57927 57927 57927 57927 57927 57927 58319 58319 58319 58319 58319 58319 58319 58319 58319 58319 58319 58724 58724 58724 58724 58724 58724 58724 59632 58724 58724 58724 58724 59337 59337 59337 59337 59337 59337 59337 59337 59337 59337 59337 DEV.)
NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95
-2. 44E+00
-2.21E+00
-0. 51E+00
-0. 50E+00
-2. 74E+00 1.02E+01 0.51E+00
-3. 54E+00
- 1. 28E+00
-1. 93E+00
-3. 33E+00
-1.81E+00
-0. 94E+00
- 0. 32E+00
- 1. 54E+00
-0. 48E+00
-8. 54E-02
- 0. 84E+00 1.23E+00
-0.
13E+00
-4.
69E+00
-3. 92E-02
-0. 77E+00
-1. 70E+00
-1.85E+00
- 0. 92E+00
-0. 94E+00
-5.27E+00
- 1. 03E+00
- 1. 61E+02
-2.34E+00
-1.26E+00
- 3. 89E+00
-5. 66E+00
-2.27E+00
-0.81E+00
-1.
93E+00
-0.81E+00
-1. 13E+00
- 5. 57E+00 1.81E+00
- 1. 09E+00 0.29E+00
-1.
77E+00
- 1. 02E+00 2.28E+00 1.72E+00
- 1. 85E+00
- 1. 83E+00
- 2. 01E+00
- 3. 92E+00
- 0. 60E+00 4.06E+00 2.01E+00 4.13E+00
- 2. 98E+00
- 1. 35E+00
- 0. 94E+00
- 0. 91E+00
- 0. 96E+00
- 1. 07E+00
- 2. 58E+00
- 0. 90E+00
- 1. 61E+00
- 0. 82E+00 5.08E+00
- 1. 87E+00 1.73E+00
- 1. 11E+00
- 0. 98E+00 1.03E+00
- 1. 16E+00
- 3. 06E+00 0.4 6E+00
- 3. 63E+02
- 2. 46E+00
- 0. 92E+00
- 3. 20E+00
- 1. 96E+00
- 1. 98E+00
- 0. 94E+00 1.OOE+00
- 0. 95E+00
- 1. 16E+00
- 3. 01E+00
- 0. 46E+00
- 3. 39E+00 1.05E+00
- 2. 09E+00
- 1. 73E+00
- 1. 02E+01
- 6. 92E+00 7.26E+00
- 6. 92E+00
- 7. 80E+00
- 1. 15E+01
- 1. 97E+00 1.47E+01
- 7. 02E+00
- 1. 58E+01
- 1. 19E+01
- 5. 68E+00 3.67E+00
- 3. 39E+00
- 3. 13E+00
- 3. 96E+00
- 9. 71E+00
- 3. 01E+00
- 5. 52E+00
- 3. 08E+00
- 1. 80E+01
- 6. 78E+00
- 7. OOE+00 4. 52E+00 4.42E+00
- 3. 60E+00
- 4. 44E+00
- 1. 31E+01 1.51E+00
- 1. 23E+03
- 9. 18E+00
- 3. 81E+00
- 9. 91E+00
- 8. 52E+00 8.56E+00
- 3. 76E+00 4.38E+00
- 3. 78E+00
- 4. 43E+00
- 9. 52E+00 1.45E+00 *
- 1. 19E+01
- 3. 79E+00
- 8. 32E+00
- 6. 18E+00 C-32
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WR WR WR WR WR WR WR 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 59755 59755 59755 59755 59755 59755 59755 59755 59755 59755 59755 60348 60348 60348 60348 60348 60348 60348 61093 60348 60348 60348 60348 60847 60847 60847 60847 60847 60847 60847 60847 60847 60847 60847 61270 61270 61270 61270 61270 61270 61270 61270 61270 61270 61270 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-33 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 0.28E+00
-3.44E-02
-0. 16E+00
- 1. 52E+00
-2.32E+00
- 5. 42E+00
- 2. 27E+00
-4.
24E+00
-0.20E+00
-2. 88E+00
-1.
43E+00
- 2. 64E+00
- 1. 32E+00
-0. 69E+00
- 2. 36E+00
-0. 65E+00
-3. 54E+00
- 1. 07E+00
-2. 06E+02
- 3. 49E+O0
-0. 26E+00
-3. 92E+00
-2. 16E+00
-0. 20E+00
- 1. 16E+00
-1.79E+00
- 9. 19E-02
-9. 32E-02
-5. 47E+00
- 1. 37E+00
-5. 93E+00
- 0. 22E+00
-6. 37E+00
-2. 44E+00
- 0. OOE+00
- 0. 40E+00
- 3. 78E+00
- 1. 29E+00
-1. 28E+00
- 5. 85E+00
- 1. 78E+00
-1.4 6E+00 0.26E+00
-5. 17E+00
- 2. 68E+00
- 1. 48E+00
- 0. 82E+00
- 1. 07E+00
- 0. 94E+00
- 1. 09E+00
- 2. 64E+00
- 1. 02E+00
- 1. 74E+00
- 0. 88E+00
- 2. 27E+00 1.76E+00
- 4. 41E+00
- 1. 4 6E+00
- 1. 43E+00
- 1. 42E+00
- 1. 50E+00
- 5. 02E+00
- 0. 58E+00
- 4. 23E+02
- 5. 07E+00
- 1. 62E+00
- 3. 33E+00
- 2. 03E+00
- 2. 23E+00
- 1. 31E+00
- 1. 30E+00
- 1. 31E+00
- 1. 14E+00
- 4. 37E+00 0 49E+00
- 4. 11E+00
- 1. 06E+00
- 2. 98E+00
- 2. 35E+00
- 1. 81E+00
- 1. 23E+00
- 1. 93E+00
- 1. 42E+00
- 1. 62E+00 4.24E+00 0.46E+00
- 2. 49E+00
- 1. 29E+00
- 3. 42E+00
- 2. 52E+00
- 5. 54E+00
- 3. 10E+00 4.05E+00
- 3. 06E+00
- 4. 38E+00
- 8. 21E+00
- 3. 30E+00
- 6. 82E+00
- 3. 31E+00
- 9. 56E+00
- 6. 74E+00
- 1. 60E+01
- 5. 11E+00
- 5. 98E+00
- 4. 59E+00
- 5. 76E+00
- 2. 05E+01
- 1. 88E+00
- 1. 48E+03 1.76E+01 6.10E+00
- 1. 39E+01 8.82E+00
- 9. 18E+00
- 4. 57E+00
- 5. 59E+00 4.87E+00 4.28E+00
- 1. 80E+01
- 1. 58E+00
- 1. 58E+01
- 3. 95E+00
- 1. 27E+01
- 9. 37E+00
- 7. 51E+00
- 4. 62E+00 6.03E+00
- 4. 98E+00 6.29E+00
- 1. 42E+01 1.46E+00 9.27E+00
- 4. 85E+00
- 1. 45E+O1
- 8. 69E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WR WR WR WR WR WR WR WR 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 7.10E+00 4.71E+00 4.13E+00 4.20E+00
- 3. 65E+00
- 9. 50E+00 1.71E+00 8.75E+02
- 9. 70E+00 3.82E+00
- 1. 94E+01 7.19E+00 4.85E+00
- 3. 96E+00 4.03E+00
- 3. 96E+00
- 5. 17E+00 9.54E+00
- 0. 97E+00
- 6. 20E+00 3.72E+00 2.06E+01
- 6. 53E+00 61712 61712 61712 61712 61712 61712 61712 62535 61712 61712 61712 61712 62234 62234 62234 62234 62234 62234 62234 62234 62234 62234 62234 62733 62733 62733 62733 62733 62733 62733 62733 62733 62733 62733 63054 63054 63054 63054 63054 63054 63054 63675 63054 63054 63054 63054 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-34 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 2.12E+00 0.15E+00
-0. 19E+00 2.03E+00 1.03E+00 1.21E+00 1.31E+00 4.79E+01
- 0. 50E+00 0.42E+00
- 0. 10E+00
-2.761E+00 1.34E+00
-0.57E+00
-1. 15E+00 0.31E+00
-2. 26E+00
- 2. 19E+00 2.35E+00
-0.32E+00 0.001E+00
- 9. 42E+00
-2. 71E+00 0.OOE+00
- 0. 17E+00 2.38E+00
-0.29E+00
-4.20E+00
-3. 40E+00
- 1. 97E+00
-3.56E+00
- 0. OOE+00 0.65E+00 1.4 9E+00
- 0. OOE+00
-2.24E+00
-0. 65E+00
- 0. 54E+00 1.36E+00 6.78E+00 1.45E+00 5.61E+02
-1. 17E+00
-0.52E+00
-4.53E+00 3.71E+100 2.06E+00 1.32E+00 1.09E+00 1.28E+00 1.07E+00 2.59E+00
- 0. 53E+00
- 2. 72E+02
- 2. 77E+00
- 1. 07E+00
- 5. 63E+00 1.78E+00 1.39E+00
- 1. 05E+00
- 0. 97E+00
- 1. 10E+00
- 1. 35E+00 2.71E+00 0.36E+00 1.74E+00 1.02E+00
- 6. 25E+00 1.59E+00 2.011E+00 1.25E+00
- 1. 60E+00
- 1. 00E+00
- 1. 63E+00
- 4. 92E+00
- 0. 37E+00 2.411E+00 1.32E+00 4.39E+00 2.03E+00 2.43E+00
- 1. 36E+00 1.32E+00 1.48E+00 1.31E+00
- 4. 35E+00 0.32E+00
- 3. 91E+02 2.27E+00 1.37E+00 2.82E+00
- 2. 19E+00 8.17E+00 4.799E+00
- 5. 25E+00 4.21E+00 6.99E+00
- 1. 98E+01 1.03E+00
- 9.43E+00 5.03E+00 1.59E+01 7.34E+00
- 9. 56E+00 5.88E+00
- 5. 66E+00 5.47E+00 4.54E+00 1.42E+01 0.95E+00
- 1.29E+03 8.49E+00 5.35E+00 1.26E+01
- 7. 01E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WR WR WR WR WR WR WR 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 57928 57928 57928 57928 57928 57928 57928 57928 57928 57928 57928 58320 58320 58320 58320 58320 58320 58320 58320 58320 58320 58320 58725 58725 58725 58725 58725 58725 58725 59633 58725 58725 58725 58725 59338 59338 59338 59338 59338 59338 59338 59338 59338 59338 59338 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-35 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95
- 0. OOE+00
-0. 48E+00
-1.
59E+00
-2. 77E+00
-2. 63E+00
-1.30E+00 1.06E+00
- 0. 70E+00
-1. 04E+00
- 1. 30E+00
-2. 05E+00
-0. 42E+00
-1.
93E+00 0.4 1E+00
- 0. 15E+00
-0. 25E+00
-3. 36E+00
- 0. 73E+00 0.23E+00
-0.75E+00
- 3. 24E+00
-2. 92E+00
-0.40E+00
-0.89E+00
- 0. 50E+00
- 0. 19E+00
-0.49E+00
- 3. 52E+00
- 2. 07E+00
- 5. 72E+02
- 0. 82E+00 0. 67E+00
-2. 31E+00
-1. 23E+00 2.24E+00
- 0. 64E+00
-0. 52E+00
-2. 08E+00 1.77E+00
-1.48E+00 1.26E+00
-1.80E+00 0.OOE+00
-1. 48E+00
- 1. 04E+00
- 2. 72E+00 1.44E+00
- 1. 66E+00 1.34E+00
- 1. 66E+00 3.4 3E+00
- 0. 61E+00
- 2. 80E+00
- 1. 47E+00 2.76E+00 2.56E+00
- 1. 68E+00
- 1. 18E+00 1.51E+00 1.11E+00
- 1. 31E+00
- 3. 84E+00 0.88E+00 2.23E+00
- 1. 37E+00
- 7. 50E+00
- 2. 10E+00 1.74E+00
- 1. 30E+00
- 1. 08E+00
- 1. 36E+00 1.25E+00
- 2. 75E+00 0.48E+00
- 3. 74E+02 2.89E+00
- 1. 16E+00
- 6. 03E+00
- 1. 84E+00
- 2. 05E+00
- 1. 25E+00
- 1. 17E+00
- 1. 14E+00
- 1. 11E+00
- 2. 42E+00
- 0. 46E+00
- 3. 66E+00
- 1. 08E+00
- 2. 65E+00
- 1. 75E+00
- 1. 07E+01
- 5. 61E+00
- 7. O1E+00 6.08E+00 6.72E+00
- 1. 34E+01
- 1. 98E+00
- 1. OOE+01
- 5. 82E+00
- 1. 03E+01
- 1. 03E+01
- 6. 84E+00 4.92E+00
- 5. 58E+00 4.20E+00
- 4. 86E+00 1.55E+01
- 2. 97E+00
- 7. 92E+00
- 5. 19E+00
- 2. 56E+01
- 8. 59E+00
- 6. 97E+00
- 4. 94E+00
- 3. 98E+00
- 4. 95E+00 4.65E+00
- 9. 31E+00 1.49E+00
- 1. 23E+03
- 1. 01E+01
- 4. 11E+00
- 2. 12E+01 7.21E+00
- 7. 10E+00
- 4. 42E+00 4.4 9E+00
- 4. 64E+00
- 3. 64E+00
- 9. 99E+00 1.47E+00
- 1. 33E+01
- 3. 93E+00
- 9. 99E+00 6.23E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data CONC STD DEV.
MDC MEDIA STA LSN END DATE NUCLIDE (pCi/kg)
(pCi/kg)
(pCi/kg)
WR 31 59756 05/02/01 Ba-140 2.52E+00 1.79E+00 5.95E+00 WR 31 59756 05/02/01 Co-58 1.72E+00 1.08E+00 3.51E+00 WR 31 59756 05/02/01 Co-60 0.17E+00 1.42E+00 5.37E+00 WR 31 59756 05/02/01 Cs-134
-0.77E+00 1.23E+00 4.84E+00 WR 31 59756 05/02/01 Cs-137
-1.99E+00 1.45E+00 5.66E+00 WR 31 59756 05/02/01 Fe-59
-2.72E+00 3.98E+00 1.58E+01 WR 31 59756 05/02/01 GR-B 1.68E+00 0.48E+00 1.52E+00
- WR 31 59756 05/02/01 1-131 2.28E+00 2.54E+00 8.66E+00 WR 31 59756 05/02/01 Mn-54 1.96E+00 1.19E+00 3.89E+00 WR 31 59756 05/02/01 Zn-65
-5.29E+00 2.84E+00 1.20E+01 WR 31 59756 05/02/01 Zr-95 0.70E+00 2.24E+00 8.13E+00 WR 31 60349 05/29/01 Ba-140
-0.44E+00 2.18E+00 8.51E+00 WR 31 60349 05/29/01 Co-58
-0.31E+00 1.08E+00 4.05E+00 WR 31 60349 05/29/01 Co-60 1.19E+00 1.01E+00 3.44E+00 WR 31 60349 05/29/01 Cs-134 1.25E+00 1.13E+00 3.84E+00 WR 31 60349 05/29/01 Cs-137
-1.73E+00 1.17E+00 4.55E+00 WR 31 60349 05/29/01 Fe-59 4.30E+00 2.69E+00 8.76E+00 WR 31 60349 05/29/01 GR-B 0.98E+00 0.57E+00 1.87E+00 WR 31 61094 05/29/01 H-3
-3.69E+02 4.31E+02 1.52E+03 WR 31 60349 05/29/01 1-131
-1.41E+00 3.48E+00 1.26E+01 WR 31 60349 05/29/01 Mn-54
-0.28E+00 1.OOE+00 3.73E+00 WR 31 60349 05/29/01 Zn-65
-5.47E+00 2.66E+00 1.08E+01 WR 31 60349 05/29/01 Zr-95
-1.05E+00 1.65E+00 6.45E+00 WR 31 60848 07/03/01 Ba-140 0.OOE+00 3.56E+00 1.41E+01 WR 31 60848 07/03/01 Co-58
-2.53E+00 1.68E+00 7.OOE+00 WR 31 60848 07/03/01 Co-60
-4.68E-02 1.73E+00 6.72E+00 WR 31 60848 07/03/01 Cs-134 0.65E+00 1.63E+00 5.97E+00 WR 31 60848 07/03/01 Cs-137
-2.02E+00 1.83E+00 7.13E+00 WR 31 60848 07/03/01 Fe-59
-2.52E+00 5.19E+00 2.08E+01 WR 31 60848 07/03/01 GR-B 0.66E+00 0.49E+00 1.59E+00 WR 31 60848 07/03/01 1-131 0.59E+00 5.10E+00 1.83E+01 WR 31 60848 07/03/01 Mn-54 0.53E+00 1.39E+00 5.12E+00 WR 31 60848 07/03/01 Zn-65 0.OOE+00 3.37E+00 1.29E+01 WR 31 60848 07/03/01 Zr-95 0.12E+00 2.72E+00 1.03E+01 WR 31 61271 08/01/01 Ba-140
-2.83E+00 2.59E+00 1.10E+01 WR 31 61271 08/01/01 Co-58
-0.33E+00 1.23E+00 4.87E+00 WR 31 61271 08/01/01 Co-60 0.64E+00 1.87E+00 6.93E+00 WR 31 61271 08/01/01 Cs-134
-3.55E-02 1.41E+00 5.41E+00 WR 31 61271 08/01/01 Cs-137
-3.57E+00 1.56E+00 6.64E+00 WR 31 61271 08/01/01 Fe-59 3.58E+00 4.66E+00 1.66E+01 WR 31 61271 08/01/01 GR-B 0.90E+00 0.45E+00 1.48E+00 WR 31 61271 08/01/01 1-131
-5.48E-07 2.26E+00 8.21E+00 WR 31 61271 08/01/01 Mn-54
-0.25E+00 1.37E+00 5.28E+00 WR 31 61271 08/01/01 Zn-65
-3.83E+00 3.26E+00 1.36E+01 WR 31 61271 08/01/01 Zr-95
-2.42E+00 2.43E+00 9.93E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-36
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WR WR WR WR WR WR WR WR 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 61713 61713 61713 61713 61713 61713 61713 62536 61713 61713 61713 61713 62235 62235 62235 62235 62235 62235 62235 62235 62235 62235 62235 62734 62734 62734 62734 62734 62734 62734 62734 62734 62734 62734 63055 63055 63055 63055 63055 63055 63055 63676 63055 63055 63055 63055 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-37 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 31 31 31 31 31 31 31 31 31 31 31 31
-1. 70E+00
- 0. 55E+00
-0. 81E+00
-0.39E+00
- 1. 24E+00 3.4 6E+00
- 1. 34E+00
- 2. OOE+02
- 0. 95E+00
-1.30E+00 0.32E+00
- 2. 44E+00 0.26E+00
-0. 58E+00 0.27E+00
-0.
93E+00
-1.
67E+00
-0. 17E+00
- 2. 21E+00
-1. 81E+00 0.20E+00
-5. 11E+00
-1.21E+00
-1. 70E+00
- 0. 82E+00
- 0. 51E+00 1.53E+00 2.76E+00
- 0. 58E+00
- 1. 92E+00 0.58E+00
- 1. 02E+00
-7. 03E+00
- 1. 98E+00
- 2. 82E+00 1.71E+00
-2. 67E+00 0.71E+00
-0. 85E+00 6.93E+00 1.28E+00
- 1. 14E+03
-2.29E+00
-2. 80E+00
-2. 55E+00
-1.
35E+00
- 1. 77E+00
- 0. 76E+00
- 0. 89E+00
- 0. 96E+00 1.03E+00
- 2. 37E+00
- 0. 54E+00
- 2. 76E+02
- 2. 37E+00
- 0. 91E+00
- 2. 55E+00
- 1. 62E+00
- 1. 06E+00
- 0. 59E+00
- 0. 99E+00 0.81E+00 0.88E+00
- 2. 28E+00
- 0. 37E+00
- 1. 54E+00 0.77E+00 1.81E+00
- 1. 54E+00
- 2. 48E+00
- 1. 47E+00
- 1. 35E+00
- 1. 38E+00
- 1. 47E+00 4.80E+00
- 0. 39E+00
- 2. 42E+00 1.30E+00
- 2. 93E+00
- 2. 69E+00
- 2. 19E+00
- 1. 35E+00 1.50E+00
- 1. 34E+00
- 1. 43E+00
- 3. 81E+00 0.29E+00 4.05E+02
- 2. 53E+00
- 1. 4 6E+00
- 3. 38E+00
- 2. 17E+00
- 7. 24E+00
- 2. 72E+00
- 3. 68E+00 3.67E+00
- 3. 48E+00 7.84E+00
- 1. 72E+00
- 8. 78E+02 8.28E+00
- 3. 64E+00
- 9. 13E+00
- 5. 35E+00
- 4. 06E+00
- 2. 51E+00
- 3. 67E+00
- 3. 33E+00
- 3. 62E+00 8.7 6E+00 0.99E+00 *
- 5. 76E+00
- 2. 84E+00 8.14E+00
- 5. 98E+00
- 1. 03E+01
- 5. 30E+00
- 5. 19E+00 4.74E+00
- 4. 69E+00
- 1. 81E+01 1.10E+00
- 8. 63E+00
- 4. 62E+00
- 1. 36E+01
- 9. 51E+00 7.40E+00
- 4. 56E+00 6.93E+00
- 4. 92E+00
- 5. 60E+00
- 1. 19E+01 0.85E+00 *
- 1. 30E+03
- 9. 50E+00
- 6. 25E+00
- 1. 36E+01
- 8. 82E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA WR WR WR WR WR WR WR WR WR WR WR 91 91 91 91 91 91 91 91 91 91 91 LSN END DATE NUCLIDE 62270 62270 62270 62270 62270 62270 62270 62270 62270 62270 62270 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 09/14/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 H-3 1-131 Mn-54 Zn-65 Zr-95 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-38 CONC (pCi/kg)
- 3. 53E+00
- 2. 04E+00
- 2. 08E+00
-0. 32E+00
- 0. 43E+00
-1. 11E+00
-5. 71E+02
- 3. 02E+00 0.58E+00
-7.
14E+00
- 1. 12E+00 STD DEV.
(pCi/kg) 3.24E+00
- 1. 15E+00
- 1. OOE+00 1.05E+00
- 1. 07E+00
- 2. 67E+00
- 2. 96E+02 7.25E+00
- 0. 93E+00
- 2. 79E+00
- 1. 55E+00 MDC (pCi/kg)
- 1. 12E+01 3.72E+00
- 3. 09E+00
- 3. 95E+00
- 3. 81E+00
- 1. 09E+01
- 9. 94E+02
- 2. 54E+01
- 3. 31E+00
- 1. 15E+01
- 5. 52E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE STORM DRAIN 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 WW WW WW WW WW WW WW WW ww wW 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 57931 57931 57931 57931 57931 57931 57931 57931 57931 57931 57931 57931 58324 58324 58324 58324 58324 58324 58324 58324 58324 58324 58324 58324 58729 58729 58729 58729 58729 58729 58729 58729 58729 58729 58729 58729 59341 59341 59341 59341 59341 59341 59341 59341 59341 59341 59341 59341 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-39 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
-1.26E+00 0.73E+00
-0. 51E+00
-0. 16E+00
-1. 92E+00
- 0. 75E+00
- 2. 19E+00
-4.78E+02
- 1. 68E+00
- 0. 97E+00 0.86E+00 0.70E+00
-1. 13E+00
-2.31E+00
-0. 58E+00
- 0. 62E+00
-1.03E+00
-3. 4 1E+00 2.84E+00
- 2. 38E+02 1.23E+00
-0. 69E+00
-0. 67E+00
-1.59E+00
-1.63E+00
-1.03E+00 0.22E+00
-0.74E+00
-0. 89E+00
-0. 15E+00
- 9. 58E+00
-2. 10E+02 1.06E+01
-2. 18E+00
- 2. 35E+00 0.21E+00
- 7. 17E+00
-0. 98E+00 1.54E+00
-1.88E+00
-0.45E+00 9.84E+00 7.59E+00
-2. 12E+02
- 3. 57E+00
-1.58E+00
-0. 66E+00
-1.25E+00
- 2. 10E+00
- 0. 99E+00 0.83E+00 1.09E+00 1.31E+00 2.48E+00 0.70E+00 3.43E+02 2.28E+00 1.17E+00
- 6. 12E+00 1.83E+00
- 1. 13E+00
- 1. 12E+00
- 1. 02E+00
- 1. 12E+00
- 0. 92E+00
- 3. 02E+00
- 3. 54E+00
- 3. 41E+02 1.85E+00
- 0. 93E+00 3.82E+00
- 1. 60E+00 2.83E+00 1.53E+00 1.42E+00
- 1. 64E+00
- 1. 93E+00 5.45E+00 3.80E+00
- 3. 61E+02 3.77E+00 1.90E+00
- 3. 99E+00 2.44E+00
- 3. 80E+00 1.61E+00 1.71E+00
- 1. 82E+00 1.85E+00 5.17E+00 0.72E+00 3.59E+02 4.76E+00 1.97E+00
- 3. 38E+00
- 2. 75E+00 8.06E+00 3.46E+00 3.43E+00 4.05E+00 5.01E+00
- 8. 91E+00 2.23E+00 1.23E+03 7.81E+00
- 4. 04E+00 2.10E+01
- 6. 56E+00
- 4. 92E+00 4.52E+00 4.04E+00
- 3. 97E+00
- 3. 65E+00 1.21E+01 1.17E+01
- 1. 15E+03 6.37E+00
- 3. 60E+00
- 1. 37E+01
- 6. 32E+00 1.23E+01 6.29E+00 5.77E+00
- 6. 59E+00 7.38E+00 2.12E+01 1.22E+01 1.25E+03 1.13E+01 7.64E+00 1.36E+01
- 9. 47E+00 1.18E+01 6.37E+00
- 6. 05E+00 7.25E+00 6.86E+00 1.61E+01 2.07E+00
- 1.24E+03 1.65E+01 7.51E+00 1.33E+01
- 1. 08E+01
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 WW WW WW WW WW WW WW WW WW WW WW WW 59760 59760 59760 59760 59760 59760 59760 59760 59760 59760 59760 59760 60352 60352 60352 60352 60352 60352 60352 60352 60352 60352 60352 60352 60851 60851 60851 60851 60851 60851 60851 60851 60851 60851 60851 60851 61274 61274 61274 61274 61274 61274 61274 61274 61274 61274 61274 61274 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Radioactivity detected in sample (i.e.,
- 0. 30E+00 0.58E+00
-0. 17E+00
-0. 31E+00
-3. 72E+00
-9. 67E-02 8.80E+00
-6. 65E+01
- 1. 37E+00
-1.
39E+00 4.03E+00
- 0. 50E+00
- 1. 33E+00 0.OOE+00
- 0. 54E+00
- 0. 99E+00
-2. OOE+00 2.29E+00 1.45E+01
-7. 04E+01
- 3. 96E+00 0.84E+00
- 3. 28E+00
- 1. 31E+00
-1.
96E+00
- 0. 18E+00
-3. 38E+00
-2. 58E+00
- 0. 12E+00
-2. 30E+00 8.80E+00
- 3. 23E+01
-9.
66E+00
-1. 30E+00
-5.
92E+00
- 0. 44E+00
-0. 87E+00
-3. 06E+00
-1. 11E+00
-1.
67E+00 1.28E+00
-2. 15E+00 6.23E+00
-1. 15E+03
-0. 37E+00
-1. 51E+00 1.46E+01
- 1. 16E+00 CONC > 3 STD.
- 1. 57E+00
- 1. 09E+00
- 1. 11E+00
- 1. 17E+00 1.11E+00
- 2. 67E+00
- 0. 95E+00
- 3. 43E+02
- 2. 08E+00
- 1. 06E+00
- 5. 51E+00
- 1. 62E+00 2.21E+00
- 1. 09E+00
- 0. 85E+00
- 0. 96E+00
- 1. 06E+00
- 3. 11E+00 1.31E+00
- 3. 56E+02
- 3. 62E+00
- 0. 94E+00 3.28E+00
- 1. 55E+00 4.39E+00
- 1. 36E+00
- 2. 08E+00
- 1. 58E+00
- 1. 51E+00 4.77E+00
- 0. 87E+00
- 3. 74E+02
- 6. 47E+00 1.25E+00
- 3. 83E+00
- 2. 54E+00
- 1. 77E+00
- 1. 27E+00
- 1. 32E+00
- 1. 19E+00
- 2. 25E+00
- 3. 13E+00
- 0. 67E+00
- 4. 62E+02
- 2. 70E+00
- 1. 15E+00
- 6. 93E+00
- 1. 98E+00
- 5. 90E+00
- 3. 85E+00
- 4. 22E+00
- 4. 32E+00 4.72E+00
- 1. O1E+01 2.69E+00
- 1. 18E+03
- 7. 17E+00
- 4. 15E+00 1.86E+01
- 5. 89E+00
- 8. 02E+00
- 3. 98E+00
- 3. 10E+00
- 3. 29E+00 4.21E+00
- 1. 10E+01 3.63E+00 *
- 1. 24E+03 1.22E+01
- 3. 26E+00
- 1. 06E+01
- 5. 44E+00 1.78E+01
- 5. 21E+00
- 8. 76E+00 6.70E+00
- 5. 60E+00
- 1. 94E+01 2.44E+00 1.27E+03
- 2. 48E+01
- 5. 24E+00
- 1. 74E+01 9.58E+00 6.85E+00
- 5. 07E+00 5.09E+00
- 4. 65E+00
- 7. 62E+00 1.21E+01
- 1. 92E+00
- 1. 69E+03
- 9. 42E+00
- 4. 43E+00 2.25E+01 6.94E+00 DEV.)
C-40 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WW WW WW WW WW WW WW WW WW WW 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 61716 61716 61716 61716 61716 61716 61716 61716 61716 61716 61716 61716 62269 62269 62269 62269 62269 62269 62269 62269 62269 62269 62269 62269 62238 62238 62238 62238 62238 62238 62238 62238 62238 62238 62238 62238 62737 62737 62737 62737 62737 62737 62737 62737 62737 62737 62737 62737 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-41 NUCLIDE CONC (pCiikg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 08/30/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 09/04/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 51 51 51 51 51 51 51 51 51 51 51 51
- 3. O1E+00 0.21E+00
- 1. 12E+00
- 0. 69E+00
-0.78E+00
-0. 38E+00 8.44E+00
-2.49E+01 4.49E+00
-2.34E+00
-9. 83E+00
- 0. 12E+00
- 6. 30E+00
-1.
84E+00
-1. 38E+00
-0. 51E+00
- 0. 94E+00
-1.49E+00
- 4. 57E+00
-3.50E+02
- 2. 94E+01
- 0. 15E+00
-4.48E+00
- 0. 17E+00
-0. 54E+00
-0. 78E+00
- 4. 61E-02
- 0. 82E+00
- 2. 23E+00
-4.90E+00
- 1. 42E+01
-4.
04E+02
-0 53E+00
- 1. 02E+00
- 3. 19E+00
- 3. 24E+00
- 0. 81E+00 0.80E+00 0.81E+00
-1. 64E+00
-2. 16E+00
- 0. 62E+00
- 9. 89E+00
-7. 94E+02
-2.
OOE+00
- 2. 20E+00
-0. 98E+00
-0.80E+00
- 3. O1E+00
- 1. 36E+00 1.76E+00
- 1. 67E+00
- 1. 65E+00
- 5. 15E+00
- 0. 99E+00
- 2. 91E+02 3.54E+00 1.30E+00 3.53E+00
- 2. 63E+00
- 5. 78E+00
- 1. 17E+00
- 1. 10E+00
- 0. 97E+00
- 1. 07E+00 4.49E+00
- 0. 53E+00
- 2. 94E+02
- 1. 84E+01 1. 02E+00
- 2. 64E+00 1. 98E+00 1. 94E+00 1.26E+00
- 1. 51E+00
- 1. 49E+00
- 1. 48E+00 4.17E+00
- 1. 03E+00
- 2. 90E+02
- 1. 87E+00
- 1. 25E+00
- 2. 78E+00 2 17E+00 1.77E+00
- 1. 10E+00
- 1. 38E+00 1.21E+00
- 1. 40E+00
- 3. 38E+00
- 0. 88E+00 3.4 1E+02
- 2. 50E+00
- 1. 23E+00
- 2. 50E+00
- 2. 06E+00 1.06E+01
- 5. 18E+00
- 6. 38E+00
- 6. 08E+00
- 6. 29E+00
- 1. 98E+01 2.89E+00
- 9. 51E+02
- 1. 19E+01
- 5. 70E+00
- 1. 61E+01 9.92E+00 2.00E+01
- 4. 84E+00
- 4. 54E+00
- 3. 77E+00
- 3. 69E+00 1.72E+01 1.36E+00
- 9. 96E+02
- 6. 04E+01
- 3. 73E+00
- 1. 07E+01 7.41E+00
- 8. 07E+00
- 5. 11E+00
- 5. 96E+00
- 5. 40E+00
- 4. 89E+00
- 1. 78E+01
- 2. 08E+00
- 9. 84E+02
- 7. 00E+00 4.43E+00
- 9. 57E+00
- 7. 16E+00 6.69E+00 3.92E+00
- 5. 03E+00 5.03E+00 5.59E+00 1.28E+01 1.91E+00
- 1. 15E+03
- 9. 23E+00
- 3. 96E+00
- 9. 85E+00
- 7. 95E+00
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE
-0. 58E+00
-1. 61E+00 1.59E+00
- 1. 56E+00
-0.79E+00
-4.
94E+00
- 4. 05E+00
-8.
32E+01
- 2. 65E+00
-1.56E+00
-3. 90E+00
-1.
84E+00
- 2. 64E+00 1.21E+00
- 1. 62E+00 1.40E+00
- 1. 35E+00
- 4. 06E+00
- 0. 61E+00
- 3. 55E+02
- 2. 18E+00
- 1. 37E+00
- 3. 19E+00
- 2. 17E+00
- 1. 05E+01
- 5. 25E+00
- 5. 69E+00
- 4. 83E+00
- 5. 35E+00
- 1. 77E+01 1.82E+00
- 1. 13E+03
- 7. 35E+00
- 5. 68E+00
- 1. 35E+01
- 8. 99E+00 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-42 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
WW WW WW WW WW WW WW WW WW WW WW WW MDC (pCi/kg) 51 51 51 51 51 51 51 51 51 51 51 51 63058 63058 63058 63058 63058 63058 63058 63058 63058 63058 63058 63058 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 57932 57932 57932 57932 57932 57932 57932 57932 57932 57932 57932 57932 58325 58325 58325 58325 58325 58325 58325 58325 58325 58325 58325 58325 58730 58730 58730 58730 58730 58730 58730 58730 58730 58730 58730 58730 59342 59342 59342 59342 59342 59342 59342 59342 59342 59342 59342 59342 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/03/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 01/30/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 02/26/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 04/03/01 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-43 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
- 0. OOE+00
-2. 14E+00
- 0. 90E+00
-0.33E+00
-1.
56E+00
-0. 32E+00
- 2. 93E+00
- 5. 07E+02
-0. 99E+00
- 0. 65E+00
- 8. 22E+00
-0. 28E+00
-0. 82E+00
-0. 22E+00
-0. 72E+00
-0. 19E+00
-1.
67E+00
-4.47E+00 7.48E+00
-3.42E+01
- 2. 66E+00
-0. 64E+00
-1.
03E+00 2.25E+00
-2.4 4E+00
-0. 33E+00
- 1. 40E+00
-2. 07E+00 0.29E+00
- 8. 52E+00
- 1. O1E+01
- 1. 61E+01
-6. 86E+00
-1.24E+00
- 1. 56E+00
- 6. 43E+00
-0.45E+00
-2. 52E+00
-0.25E+00
- 0. 16E+00
- 0. 46E+00
- 3. 86E+00
- 1. 33E+01
-4.08E+02
-1.
O1E+01
-1. OOE+00
-0. 52E+00 0.24E+00
- 1. 83E+00
- 0. 96E+00
- 1. 19E+00
- 0. 87E+00
- 1. 16E+00
- 1. 95E+00
- 0. 72E+00
- 3. 68E+02
- 2. 26E+00
- 0. 87E+00
- 5. 56E+00
- 1. 66E+00 1.41E+00
- 0. 90E+00
- 1. 06E+00
- 1. 03E+00
- 1. 13E+00 2.70E+00
- 1. 02E+00
- 3. 34E+02 1.79E+00
- 0. 80E+00
- 5. 54E+00
- 1. 88E+00
- 3. 73E+00
- 2. 04E+00
- 1. 99E+00 1.55E+00
- 2. 01E+00
- 5. 4 6E+00
- 0. 89E+00
- 3. 68E+02 4.50E+00
- 1. 64E+00
- 3. 98E+00
- 3. 69E+00 2.31E+00
- 1. 18E+00
- 1. OOE+00
- 1. 06E+00 1.06E+00
- 2. 77E+00
- 0. 86E+00
- 3. 54E+02
- 3. 50E+00
- 1. 07E+00
- 5. 18E+00 1.71E+00
- 6. 83E+00
- 4. 02E+00 4.17E+00
- 3. 34E+00 4.44E+00
- 7. 38E+00 2.22E+00 1.22E+03
- 8. 10E+00
- 3. 05E+00
- 1. 84E+01
- 6. 19E+00
- 5. 64E+00
- 3. 38E+00 4 16E+00
- 3. 83E+00
- 4. 38E+00
- 1. 13E+01 3.07E+00 *
- 1. 16E+03
- 5. 92E+00
- 3. 14E+00
- 1. 92E+01
- 6. 33E+00
- 1. 53E+01
- 7. 69E+00 7.22E+00
- 6. 75E+00
- 7. 34E+00 1.78E+01 2.46E+00
- 1.25E+03
- 1. 72E+01
- 6. 62E+00
- 1. 47E+01
- 1. 19E+01
- 8. 96E+00 4. 82E+00
- 3. 89E+00
- 3. 88E+00
- 3. 76E+00
- 9. 22E+00 2.46E+00
- 1.24E+03 1.41E+01 4.13E+00 1.81E+01
- 6. 29E+00 WW WW WW WW WW WW WW WW WW WW WW WW
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 WW WW WW WW WW WW WW WW WW WW 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 59761 59761 59761 59761 59761 59761 59761 59761 59761 59761 59761 59761 60353 60353 60353 60353 60353 60353 60353 60353 60353 60353 60353 60353 60852 60852 60852 60852 60852 60852 60852 60852 60852 60852 60852 60852 61275 61275 61275 61275 61275 61275 61275 61275 61275 61275 61275 61275 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
C-44 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg) 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/02/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 05/29/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 07/03/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 08/01/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95
- 0. OOE+00
-0. 84E+00
-0. 63E+00
-0. 45E+00
-1. 17E+00
- 1. 39E+00
- 5. 38E+00
- 3. 73E+02
-1. 48E+00
-0. 76E+00 0.OOE+00
- 2. 13E+00
-5. 25E+00
-0. 30E+00
- 2. 62E+00
-0. 51E+00
-1. 90E+00
-5. 35E+00
- 6. 73E+00
- 7. 09E+01 0.4 9E+00
-0. 69E+00
-3. 93E+00
-4.49E+00
-1. 78E+00
-0. 85E+00 0.41E+00
-0.86E+00
- 0. 56E+00
- 1. 18E+00 5.70E+00
-3.4 6E+02
-6. 56E+00 5.06E-02
-5. 58E+00
-0. 17E+00
-2. 29E+00
-1. 38E+00
- 0. 17E+00
- 1. 45E+00
-0. 96E+00
-3. 04E+00
- 8. 22E+00
-1.
27E+03
- 1. 93E+00
-0. 43E+00
- 3. 48E+00 1.08E+00
- 1. 65E+00
- 0. 95E+00
- 0. 91E+00
- 0. 90E+00
- 1. 18E+00
- 2. 18E+00 0.71E+00
- 3. 56E+02 1.74E+00 0.81E+00
- 2. 23E+00 1.81E+00
- 2. 60E+00 1.26E+00 1.20E+00
- 1. 06E+00
- 1. 15E+00 4.10E+00
- 0. 90E+00
- 3. 63E+02 4.78E+00
- 1. 07E+00 2.78E+00
- 2. 04E+00
- 2. 09E+00
- 0. 93E+00
- 1. 08E+00
- 0. 91E+00 1.01E+00
- 3. 13E+00
- 0. 76E+00
- 3. 66E+02 3.53E+00
- 0. 76E+00
- 2. 10E+00
- 1. 65E+00
- 1. 70E+00
- 0. 98E+00
- 0. 92E+00
- 0. 96E+00 1.01E+00
- 2. 88E+00
- 0. 64E+00
- 4. 59E+02 2.24E+00
- 1. 12E+00
- 2. 09E+00 1.4 9E+00 6.21E+00 3.69E+00
- 3. 67E+00
- 3. 47E+00 4.44E+00
- 7. 94E+00 2.08E+00
- 1. 19E+03
- 6. 48E+00
- 3. 21E+00
- 8. 19E+00 6.14E+00
- 1. 24E+01 4.81E+00 3.55E+00 4.23E+00 4.76E+00 1.72E+01 2.63E+00
- 1. 25E+03
- 1. 70E+01 4.24E+00
- 1. 16E+01
- 8. 99E+00
- 8. 68E+00
- 3. 70E+00
- 3. 94E+00
- 3. 62E+00
- 3. 55E+00
- 1. 14E+01 2.22E+00
- 1. 28E+03
- 1. 37E+01
- 2. 84E+00 9.12E+00
- 6. 19E+00
- 7. 15E+00
- 3. 97E+00
- 3. 50E+00
- 3. 15E+00 3.92E+00
- 1. 17E+01 1.45E+00 *
- 1. 69E+03
- 7. 63E+00 4.17E+00 6.77E+00 5.27E+00 DEV. )
Yankee Nuclear Power Station Radiological Environmental Monitoring System Summary of 2001 Data MEDIA STA LSN END DATE 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 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52 52
- 5. 91E+00
- 3. 44E+00
- 4. 61E+00
- 3. 75E+00
- 3. 51E+00 8.26E+00 1.37E+00
- 9. 84E+02
- 5. 18E+00
- 4. 15E+00
- 8. 95E+00
- 6. 04E+00 62239 62239 62239 62239 62239 62239 62239 62239 62239 62239 62239 62239 62738 62738 62738 62738 62738 62738 62738 62738 62738 62738 62738 62738 63059 63059 63059 63059 63059 63059 63059 63059 63059 63059 63059 63059 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/03/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 10/31/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 11/28/01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 GR-B H-3 1-131 Mn-54 Zn-65 Zr-95 Radioactivity detected in sample (i.e.,
CONC > 3 STD.
DEV.)
C-45 NUCLIDE CONC (pCi/kg)
STD DEV.
(pCi/kg)
MDC (pCi/kg)
-1.39E+00
-0. 15E+00
-1.39E+00
-0. 32E+00 0.85E+00
- 2. 90E+00 9.78E+00
-4.
91E+02
- 0. 33E+00
-0.29E+00
-4.48E+00
-0.48E+00
- 3. 62E+00
-2. 12E+00
- 0. OOE+00
- 2. 92E+00
-0. 12E+00
- 3. 09E+00
- 8. 37E+00
-8. 67E+02
-1. 59E+00
-1. 29E+00
-5. 19E+00
- 2. 83E+00
- 1. 72E+00
-1.20E+00
- 0. 82E+00
- 2. 38E+00
-0. 37E+00 4.83E+00
- 5. 84E+00
-8. 28E+01
-0.45E+00
- 0. 94E+00 1.56E+01
- 1. 72E+00
- 1. 44E+00
- 0. 91E+00
- 1. 13E+00
- 0. 98E+00
- 1. 01E+00
- 2. 42E+00
- 0. 68E+00
- 2. 88E+02
- 1. 46E+00
- 1. 12E+00
- 2. 10E+00
- 1. 59E+00
- 2. 56E+00
- 1. 21E+00
- 1. 63E+00
- 1. 44E+00
- 1. 51E+00
- 3. 98E+00
- 0. 68E+00
- 3. 45E+02
- 2. 52E+00
- 1. 18E+00
- 3. 55E+00
- 2. 11E+00 2.09E+00
- 1. 58E+00
- 1. 48E+00
- 1. 4 6E+00
- 1. 39E+00 4 42E+00
- 0. 45E+00
- 3. 52E+02
- 2. 30E+00
- 1. 30E+00 7 44E+00
- 2. 03E+00
- 7. 43E+00
- 5. 97E+00
- 5. 35E+00 4.76E+00
- 5. 17E+00
- 1. 51E+01 1.OOE+00
- 1. 12E+03 8.26E+00
- 4. 57E+00
- 2. 41E+01
- 7. 12E+00
- 8. 52E+00 5.41E+00 6.38E+00 4 42E+00
- 5. 67E+00
- 1. 44E+01
- 1. 40E+00
- 1. 16E+03
- 9. 48E+00
- 5. 04E+00
- 1. 49E+01
- 7. 09E+00