ML091280061
| ML091280061 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/30/2009 |
| From: | Exelon Nuclear, Teledyne Brown Engineering Environmental Services |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091280061 (114) | |
Text
Docket No: 50 - 352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report No. 24 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Exel I
Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2009
Table Of Contents
- 1. Summary and Conclusions.....................................................................
I
- 11. Introduction.....................................................................................
3 A. Objectives of the REMP...............................................................
3 B. Implementation of the Objectives..................................................... 3 111. Program Description...........................................................................
4 A. Sample Collection......................................................................
4 B. Sample Analysis.......................................................................
6 C. Data Interpretation.....................................................................
6 D. Program Exceptions...................................................................
7 E. Program Changes......................................................................
8 IV. Results and Discussion.........................................................
8 A. Aquatic Environment.....................................................
- "**..........8
- 1. Surface Water..................................................................
8
- 2. Drinking Water............
9
- 3. Fish..............................................................................
9
- 4. Sediment.............
......... 10 B. Atmospheric Environment...........................................................
10
- 1. Airborne.......................................................................
10
- a. Air Particulates........................................................
10
- b. Airborne Iodine........................................................ 11
- 2. Terrestrial......................................................................
11
- a. Milk....................................................................
11
- b. Broad Leaf Vegetation................................................
12 C. Ambient Gamma Radiation.......................................................... 12 D. 10 CFR 20.2002 Permit Storage Area.............................................. 13 E. Land Use Survey.....................................................................
13 F. Summary of Results - Inter-Laboratory Comparison Program...................
13 V. References....................................................................................
15
Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-i:
Table B-2:
Table B-3:
Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2008.
Location Designation, Distance & Direction, and Sample Collection &
Analytical Methods Location Designation and Identification System for the Limerick Generating Station.
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2008.
Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2008.
Figures Figure B-i:
Figure B-2:
Figure B-3:
Appendix C Tables Table C-1.1 Table C-1.2 Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2008.
Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2008.
Environmental Sampling Locations Greater Than Five Miles from the Limerick Generating Station, 2008.
Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
ii
Table C-11.1 Table C-11.2 Table C-11.3 Table C-111.1 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII.1 Table C-VII.2 Table C-VII1.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Fiqures Figure C-1 Figure C-2 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Quarterly TLD Results for Limerick Generating Station, 2008.
Mean Quarterly TLD Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2008.
Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2008.
Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2008.
Mean Annual Cs-1 37 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2008.
iii
Figure C-3 Figure C-4 Figure C-5 Figure C-6 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-11.1 Table D-11.2 Table D-Ill.1 Figures Figure D-1 Figure D-2 Concentrations of Cs-137 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2008.
Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2008.
Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2008.
Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985 - 2008.
Data Tables and Figures - Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2008.
Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2008.
Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2008..
Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2008.
Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2008.
iv
Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008.
ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2008.
DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engineering, 2008.
ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2008.
DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Environmental, Inc., 2008.
Annual Radiological Groundwater Protection Program Report (ARGPPR) v
Intentionally Left Blank vi
- 1.
Summary and Conclusions In 2008 the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 73 curies of noble gas, fission and activation products and approximately 63 curies of tritium.
The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:
Gaseous and liquid radiation doses to members of the public at locations Effluent Applicable Estimated Age Location
% of Limit Unit Organ Dose Group Distance Direction Applicable (meters)
(toward)
Limit Noble Gas Gamma - Air Dose 8.55E-03 All 762 SE 4.28E-02 20 mRad Noble Gas Beta - Air Dose 5.22E-03 All 762 SE 1.31E-02 40 mRad Noble Gas Total Body (Gamma) 5.32E-03 All 762 SE 5.32E-02 10 mrem Noble Gas Skin (Beta) 9.93E-03 All 762 SE 3.31 E-02 30 mrem Iodine, Particulate &
Tritium Thyroid 5.87E-03 Infant 762 SE 1.96E-02 30 mrem Liquid
-Total Body 7.11 E-03 Adult LGS Outfall 1.19E-01 6
mrem Liquid Liver 1.02E-03 Teen.
LGS Outfall 5.1OE-02 20 mrem The doses as a result of the radiological effluents released from Limerick were a very small percentage of the allowable limits.
This report on the Radiological Environmental Monitoring Program conducted for the Limerick Generating Station (LGS) by Exelon covers the period 1 January 2008 through 31 December 2008. During that time period, 1141 analyses were performed on 929 samples.
Surface and drinking water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of total gross beta. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years.
Fish (predator and bottom feeder) and sediment samples were analyzed for concentrations of gamma emitting nuclides. No fission or activation products were detected.
Sediment samples collected below the discharge had.elevated Cesium-137 concentrations that were the result of LGS discharges. No other Plant produced fission or activation products were found in sediment. The calculated dose to a teenager's skin and whole body was 4.62E-04 mrem and 3.96E-04 mrem, respectively. This dose represents 2.31 E-03% and 6.60E-03%, respectively of the 10 CFR Part 50, Appendix I dose limits.
1
Air particulate samples were analyzed for concentrations of gross beta and gamma emitting nuclides. Cosmogenic Be-7 was detected at levels consistent with those detected in previous years. No fission or activation products were detected.
High sensitivity 1-131 analyses were performed on weekly air samples. All results were less than the minimum detectable concentration.
Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides. All 1-131 results were below the minimum detectable concentration. Concentrations of naturally occurring K-40 were consistent with those detected in previous years. No fission or activation products were found.
Broad Leaf Vegetation samples were analyzed for gamma emitting nuclides.
Concentrations of naturally occurring Be-7 and K-40 were detected. No activation or fission products were detected.
Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. Levels detected were consistent with those observed in previous years.
Review of the gamma spectroscopy results from the surface water samples located at the Limerick intake (24S1) and downstream of the 10CFR20.2002 permitted storage area showed no evidence of offsite radionuclide transport from the 2002 permitted storage area.
A radiological groundwater protection program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. Well water samples were analyzed for tritium, Sr-90 and gamma emitters. Most tritium values were less than the lower limit of detection of 200 pCi/L. However, one well located near the radwaste /cooling tower blowdown line had a tritium value as high as 902 pCi/L.
This activity was due to a cooling tower overflow while a Radwaste discharge was in progress. The discharge was secured and no radioactivity was found in the water sample obtained. Although no drinking water pathway exist, the dose via the drinking water pathway was calculated at 0.053 mrem to a child (total body), which was 0.89% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.
In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of LGS had no adverse radiological impact on the environment.
2
II.
Introduction The Limerick Generating Station (LGS), consisting of two 3,458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.
A Radiological Environmental Monitoring Program (REMP) for LGS was initiated in 1971. Review of the 1971 through 1977 REMP data resulted in the modification of the program to comply with changes in the Environmental Report Operating License Stage (EROL) and the Branch Technical Position Paper (Rev.
1, 1979). The preoperational period for most media covers the periods 1 January 1982 through.21 December 1984 and was summarized in a separate report.
This report covers those analyses performed by Teledyne Brown Engineering (TBE), Global Dosimetry, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2008 through 31 December 2008.
On 6 July 1996 a 10CFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding pond, cooling tower and spray pond systems. These materials will decay to background while in storage. Final disposition will be determined at Station decommissioning.
A.
Objective of the REMP The objectives of the REMP are to:
- 1.
Provide data on measurable levels of radiation and radioactive materials in the site environs.
- 2.
Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
B.
Implementation of the Objectives The implementation of the objectives is accomplished by:
- 1.
Identifying significant exposure pathways.
3
- 2.
Establishing baseline radiological data of media within those pathways.
- 3.
Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
Ill.
Program Description A.
Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2008. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by NAI are listed in Table B-3.
Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, drinking water, fish, and sediment.
Two-gallon water samples were collected monthly from continuous samplers located at three surface water locations (10F2, 13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish/bullhead (bottom-feeder) and sunfish (predator), were collected semiannually at two locations, 16C5 and 29C1 (control). Sediment samples composed of recently deposited substrate were collected at three locations semiannually, 16B2, 16C4 and 33A2 (control).
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at five locations (10S3, 11S1, 13C1, 14S1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.
Milk samples were collected biweekly at five locations (10F4, 18E1, 19B1, 23F1, and 25C1) from April through November, and monthly from December through March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All 4
samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.
Broad Leaf Vegetation was collected monthly at three locations (11S3, 13S3 and 31G1). The control location was 31G1. Eight different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis.
Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (CaSO4) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the LGS site as follows:
A site boundary ring consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1 and 34S2) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS releases.
An intermediate distance ring consisting of 16 locations (36D1, 2E1, 4E1, 7E1, 10E1, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.
The balance of eight locations (5H1, 6C1,9C1, 13C1, 15D1, 17B1, 20D1 and 31D1) representing control and special interests areas such as population centers, schools, etc.
The specific TLD locations were determined by the following criteria:
- 1.
The presence of relatively dense population;
- 2.
Site meteorological data taking into account distance and elevation for each of the sixteen-22 1/2 degree sectors around the site, where estimated annual dose from LGS, if any, would be most significant;
- 3.
On hills free from local obstructions and within sight of the vents (where practical);
- 4.
And near the closest dwelling to the vents in the prevailing downwind direction.
Two TLDs - each comprised of three CaSO4 thermoluminescent phosphors enclosed in plastic - were placed at each location in a PVC conduit located approximately three feet above ground level. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.
5
10CFR20.2002 Permit Storage Area The results of the surface water sampling program were used to determine. if radioactive nuclide transport from the storage area into the Schuylkill River had occurred.
B.
Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the LGS REMP in 2008. The analytical procedures used by the laboratories are listed in Table B-3.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1.
Concentrations of beta emitters in drinking water, and air particulates.
- 2.
Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, broad leaf vegetation and sediment.
- 3.
Concentrations of tritium in surface and drinking water.
- 4.
Concentrations of 1-131 in air and milk.
- 5.
Ambient gamma radiation levels at various site environs.
C.
Data Interpretation The radiological and direct radiation data collected prior to LGS becoming operational was used as a baseline with which these operational data were compared. For the purpose of this report, LGS was considered operational at initial criticality. In addition, data were compared to previous years' operational data for consistency and trending. Several factors were important in the interpretation of the data:
- 1.
Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required LGS detection limits for environmental sample analysis.
6
The minimum detectable concentration (MDC) was defined as above with the exception that the measurement is an after the fact estimate of the presence of activity.
- 2.
Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity affecting a negative number. An MDC was reported in all cases where positive activity was not detected.
If no positive activity was detected, then gamma spectroscopy MDC results for each type of sample were grouped as follows:
For surface and drinking water twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-1 34, Cs-137, E;1,---I40, and La-140 were reported.
,r fish nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65,
-131, Cs-134, and Cs-137 were reported.
For sediment and broad leaf vegetation eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-1 34, and Cs-1 37 were reported.
-r air particulate six nuclides, Be-7, Mn-54, Co-58, Co-60, Cs-1 34, and Cs-1 37 were reported.
For milk five nuclides, K-40, Cs-134, Cs-137, Ba-140, and La-140 were reported.
Means and standard deviations of positive results were calculated.
The standard deviations represent the variability of measured results for different samples rather than single analysis uncertainty.
D.
Program Exceptions For 2008 the LGS REMP had a sample recovery rate in excess of 99%.
Exceptions are listed below:
1.
Air sample from location 14S1 for the week 07/27/08 - 08/02/08 was not available due to equipment malfunction (IR828053).
- 2.
Air sample from location 13C1 for the week 09/28/08 - 10/04/08 was not available due to equipment malfunction (IR851235).
- 3.
Grab samples were taken for the composite drinking water sampler at location 16C2 during the following periods due to equipment 7
malfunction or insufficient sample collected: 04/21/08- 05/03/08 and 08/25/08 - 09/06/08.
- 4.
A grab sample was taken for the composite drinking water sampler at location 28F3 from 07/20/08 - 07/26/08, 08/03/08 - 08/09/08, 10/26/08 - 11/01/08 and 11/16/08 - 11/22/08 due to insufficient sample collection.
.5.
A grab sample was taken for the composite drinking water sampler at location 151F4 from 10/05/08 - 10/11/08 due to a change in river flow.
- 6.
A grab sample Was taken for the composite service water sampler at location 13131 from 03/30/08 - 04/05/08, 04/13/08 - 04/19/08, 04/27/08 - 05/03/08, 05/04/08 - 05/10/08, 06/15/08 - 06/21/08, 08/31/08 - 09/06/08 and 09/07/08 - 09/13/08 due to equipment failure and low river water.
- 7.
A grab sample was taken for the composite service water sampler at location 24S1 from 01/27/08 - 02/02/08 due to frozen sample line.
- 8.
Only two broad leaf vegetation samples were collected at Stations 11 S3 and 31 G1 during the month of October. Cabbage was not available.
Each program exception was reviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable.
The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.
E.
Program Changes Surface water Station 1 0F2, which draws its water from the Delaware River was placed back into service on July 14, 2008 when LGS began using the Delaware River as the source for cooling tower makeup water.
IV.
Results and Discussion A.
Aquatic Environment
- 1.
Surface Water Samples were taken from a continuous sampler at three locations (10F2, 13B1 and 24S1) on a monthly schedule. Of these locations 8
only 13B1 located downstream, could be affected by Limerick's effluent releases. The following analyses were performed.
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.1, Appendix C). All results were less than the MDC.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.2, Appendix C). All nuclides were less than the MDC.
- 2.
Drinking Water Monthly samples were collected from continuous water samplers at four locations (15F4, 15F7, 16C2, and 28F3). Three locations (15F4, 15F7, and 16C2) could be affected by Limerick's effluent releases. The following analyses were performed:
Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-11.1, Appendix C). The values ranged from 2.3 to 7.2 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).
Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). All results were less than the MDC.
Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.3, Appendix C). All nuclides were less than the MDC.
- 3.
Fish Fish samples comprised of catfish/bullhead (bottom feeder) and sunfish (predator) were collected at two locations (16C5 and 29C1) in the spring and fall season. Location 16C5 could be affected by Limerick's effluent releases. The following analysis was performed:
9'
Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-111.1, Appendix C).
Naturally occurring K-40 was found at all stations and ranged from 2,660 to 3,680 pCi/kg wet and was consistent with levels detected in previous years. No other gamma emitting nuclides were found.
Historical levels of Cs-137 are shown in Figure C-2, Appendix C.
- 4.
Sediment Aquatic sediment samples were collected at three locations (16B2, 16C4 and 33A2) semiannually. Of these locations two 166B2 and 16C4 located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:
Gamma Spectrometry Sediment samples from all three locations were analyzed for gamma emitting nuclides (Table C-IV.1, Appendix C). Nuclides detected were naturally occurring Be-7, K-40 and the fission product Cs-137.
Beryllium-7 was found at locations 06B2 and 16C4 and ranged from 1,560 to 5,990 pCi/kg dry. Potassium-40 was found at all locations and ranged from 8,920 to 17,700 pCi/kg dry. The fission product Cs-1 37 was found at downstream locations 16B2 and 16C4 at concentrations of 176 and 162 pCi/kg dry, respectively. The Cs-137 activity found is attributed to LGS radioactive effluent releases.
The dose to a teenager's skin and whole body was conservatively calculated at 4.62E-04 mrem and 3.96E-04 mrem, respectively.
This dose represents 2.31 E-03% and 6.60E-03%, of the Appendix I to 10 CFR Part 50 dose limits, respectively. The activity detected was consistent with those detected in the pre-operational years.
(Figure C-4, Appendix C). No other Limerick fission or activation products were found.
B.
Atmospheric Environment 1.
Airborne
- a.
Air Particulates Continuous air particulate samples were collected from five locations on a weekly basis. The five locations were separated into three groups: Group I represents locations within the LGS site boundary (10S3, 11S1, and 14S1),
Group II represents the location at an intermediate distance from the LGS site (13C1), and Group III represents the control location at a remote distance from LGS (22G1). The 10
following analyses were performed:
Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).
Detectable gross beta activity was observed at all locations.
The results from the On-Site locations (Group I) ranged from 7 to 33 E-3 pCi/m 3 with a mean of 16.1 E-3 pCi/m 3. The results from the Intermediate Distance location (Group II) ranged from 9 to 32 E-3 pCi/m 3 with -a mean of 16.9 E-3 pCi/m 3. The results from the Distant locations (Group Ill) ranged from 8 to 38 E-3 pCi/m 3 with a mean of 16.5 E-3 pCi/mr3. Comparison of the 2008 air particulate data with previous years data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition a comparison of the weekly mean values for 2008 indicate no notable differences among the three groups (Figure C-5, Appendix C).
Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C).
Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. These values ranged from 49 to 156 E-3 pCi/m 3. All other nuclides were less than the MDC.
- b.
Airborne Iodine Continuous air samples were collected from five locations (10S3, 11S1, 14S1, 13C1, and 22G1) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC.
- 2.
Terrestrial
- a.
Milk Samples were collected from five locations (10F4, 18E1, 199B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from two additional locations (36E1 and 25E1) were taken quarterly.
The following analyses were performed:
11
Iodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). All results were less than the MDC.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C).
Naturally occurring K-40 activity was found in all samples and ranged from 1,050 to 1,460 pCi/L. All other nuclides were less than the MDC.
- b.
Broad Leaf Vegetation Three types of broad leaf vegetation samples were collected from three locations (11S3, 13S3 and 31G1) monthly from June through September. The following analysis was performed:
Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma emitting nuclides (Table C-VIII.1, Appendix C).
Cosmogenic Be-7 was found in 30 of 43 samples and ranged from 74 to 2,060 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 1,680 to 7,060 pCi/kg wet. All other nuclides were less than the MDC.
C.
Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) thermoluminescent dosimeters. Forty TLD locations were established around the site. Results of TLD measurements are listed in Tables C-IX.1 to C-IX.3, Appendix C.
Most TLD measurements were below 10 mR/standard month, with a range of 5.5 to 12.6 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher. The historical ambient gamma radiation data from Location 5H1 were plotted along with similar data from the Site, Intermediate Distance and Outer Ring Locations (Figure C-6, Appendix C). Location 5H1 has a historical high bias, but tracked with the data from all three groups. This bias is most likely due to radon emanating from the ground.
12
D.
10 CFR 20.2002 Permit.Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.
E.
Land Use Survey A Land Use Survey conducted in August 2008 around Limerick Generating Station (LGS) was performed by Normandeau Associates, Inc.
for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 /2 degree sectors around the site. Four new gardens are included in the 2008 survey. The gardens in the ENE, E and SW sectors are further away than 2007. The garden in the WSW sector is closer than 2007. The distance and direction of all locations from the LGS reactor buildings were positioned using Global Positioning System (GPS) technology. There were no changes required to the LGS REMP, as a result of this survey. The results of this survey are summarized below.
Distance in miles from the LGS Reactor Buildings Sector Residence Garden Milk Farm Miles Miles Miles 1 N 0.6 1.8 4.7 2 NNE 0.5 1.8 3 NE 0.7 1.6 4 ENE 0.7 2.7 5 E 0.6 2.4 6 ESE 0.5 0.3 7 SE 017 0.2 8 SSE 1.0 1.1 9S 1.0 1.2 4.2 10 SSW 0.8 1.0 2.0 11 SW 1.0 1.0 12 WSW 0.6 2.3 2.7 13 W 0.7 0.8 2.8 14 WNW 0.7 0.7 15 NW 0.7 1.6 16 NNW 0.7 1.3 F.
Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 28 analytes (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:
13
Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of TBE's result and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the DOE MAPEP criteria.
- 2.
ERA Evaluation Criteria ERA's evaluation report provides an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA,' NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.
- 3.
DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.
The MAPEP defines three levels of performance: Acceptable (flag =
"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.
Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value (i.e., 20% <
bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
For the primary laboratory, 16 out of 18 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance
-criteria for the following reasons:
1.
Teledyne Brown Engineering's Analytics December 2008 Sr-89 in milk result of 18.0 pCi/L was higher than the known value of 12.6 pCi/L, resulting in a found to known ratio of 1.43. NCR 09-02 was initiated to investigate this failure.
- 2.
Teledyne Brown Engineering's Analytics' ERA Quik Response water sample January 2008 Sr-89 result of 37.33 pCi/L exceeded the upper acceptance limit of 25.2 pCi/L. NCR 08-03 was initiated to investigate this failure. No cause could be found for the failure.
Studies bracketing these results, RAD 71 and RAD 72 had acceptable Sr-89 results.
14
For the secondary laboratory, Environmental, Inc. all 15 analytes met the specified acceptance criteria.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
V.
References
- 1.
Environmental Report Operating License Stage, Limerick Generating Station, Units 1 and 2, Volumes 1-5 Philadelphia Electric Company.
- 2.
Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.
- 3.
Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
15
Intentionally Left Blank 16
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility:'LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SURFACE WATER H-3 10 200
<LLD
<LLD 0
(PCI/LITER)
GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 30 15
<LLD 15
<LLD 30
<LLD 15
<LLD 30
<LLD 15
<LLD 30
<LLD 15
<LLD 15
<LLD 18
<LLD 60
<LLD 15
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 0
0 0
0 0
0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-1
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS DRINKING WATER GR-B 48 4
4.3 3.3 4.5 15F7 INDICATOR 0
(PCI/LITER)
(33/36)
(2.3/7.2)
(12/12)
(2.3/5.1)
(11/12)
(2.7/7.2)
PHOENIXVILLE WATER WORKS 6.33 MILES SSE OF SITE H-3 16 48 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 1-131 CS-1 34 CS-1 37 BA-140 LA-140 200
<LLD 15
<LLD 15
<LLD 30
<LLD 15
<LLD 30
<LLD 15
<LLD 30
<LLD 15
<LLD 15
<LLD 18
<LLD 60
<LLD 15
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 0
0 0
0 0
0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-2
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS BOTTOM FEEDER GAMMA 4
(PCi/KG WET)
K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 1-131 CS-134 CS-137 GAMMA K-40 MN-54 CO-58 NA 3060 (2/2)
(2660/3460) 3515 (2/2)
(3350/3680) 3515 (2/2)
(3350/3680) 29C1 CONTROL POTTSTOWN VICINITY UPSTREAM OF INTAKE 130
<LLD 130
<LLD 260
<LLD 130
<LLD 260
<LLD NA
<LLD 100
<LLD 100
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 0
0 0
0 PREDATOR (PCI/KG WET) 4 NA 3295 (2/2)
(3290/3300) 2770 (2/2)
(2690/2850) 3295 (2/2)
(3290/3300) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 130
<LLD 130
<LLD 260
<LLD
<LLD
<LLD
<LLD 0
0 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-3
TABLEA-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS PREDATOR CO-60 130
<LLD
<LLD 0
(PCI/KG WET)
ZN-65 1-131 260
<LLD NA
<LLD 100
<LLD 100
<LLD CS-134 CS-137 GAMMA BE-7
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 SEDIMENT (PCI/KG DRY) 6 0
0 0
0 K-40 MN-54 C0-58 CO-60 NA 4437 (3/4)
(1560/5990)
NA 14030 (4/4)
(8920/17700)
NA
<LLD NA
<LLD NA
<LLD NA
<LLD 150
<LLD 180 169 (2/4)
(162/176) 5875 (2/2)
(5760/5990) 14750 (2/2)
(12900/16600) 13750 (2/2)
(13000/14500) 16C4 INDICATOR VINCENT DAM 2.18 MILES SSE OF SITE 16B2 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE
<LLD
<LLD
<LLD
<LLD
<LLD.
<LLD 0
1-131 CS-134 CS-137 176 (1/2) 1662 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-4
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF
- NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS AIR PARTICULATE GR-B 258 10 16 16 17 13C1 INDICATOR 0
(E-3 PCI/CU.METER)
(202/206)
(7/33)
(51/52)
(8/38)
(49/51)
(9/32)
- CS-134 CS-1 37 GAMMA 1-131 1-131 GAMMA K-40 CS-134 CS-137 20 KING ROAD 2.84 MILES SE OF SITE 13C1 INDICATOR KING ROAD 2.84 MILES SE OF SITE NA 89 (16/16)
(56/156)
NA
<LLD NA
<LLD NA
<LLD 10
<LLD 10
<LLD 70
<LLD 1
<LLD NA 1272 (92/92)
(1080/1460) 15
<LLD 18
<LLD 83.4 (4/4)
(49.1/134) 98.3 (4/4)
(63.6/156)
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 0
0 0
AIR IODINE (E-3 PCI/CU.METER) 258 118 118 MILK (PCI/LITER)
MILK (PCI/LITER) 1239 (26/26)
(1050/1360) 1314 (22/22)
(1140/1400) 19B1 INDICATOR 1.95 MILES SSW OF SITE
<LLD
<LLD 0
0 I
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-5
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS MILK BA-140 60
<LLD
<LLD 0
(PCI/LITER)
LA-140 GAMMA BE-7 VEGETATION (PCI/KG WET) 43 15
<LLD NA 227 (21/29)
(90/724)
NA 3853 (29/29)
(1680/7060)
<LLD 0
649 (9/14)
(74/2060) 4371 (14/14)
- (2010/5640) 649 (9/14)
(74/2060) 4371 (14/14)
(2010/5640) 31G1 CONTROL 31G1 CONTROL K-40 MN-54 CO-58 CO-60 NA
<LLD NA
<LLD NA
<LLD 60
<LLD 60
<LLD 80
<LLD 1-131
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 227 (1/14) 0 0
CS-134 CS-137 RA-226 NA 832 (15/29)
(165/1680) 878 (14/15)
(165/1680) 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS-AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-6
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR ANNUAL
SUMMARY
FOR THE LIMERICK GENERATING STATION, 2008 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:
50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:
2008 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M)
MEAN(M)
MEAN(M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS VEGETATION TH-228 NA 26 26 30 13S3 INDICATOR 0
(PCI/KG WET)
(13/29)
(10/53)
TH-232 NA 20 (1/29)
NA 7.8 (156/156)
(5.5/12.6)
(8/14)
(12/56) 29 (3/14)
(17/46) 9.2 (4/4)
(8.7/9.9)
(8/15)
(1 0/53) 29 (3/14)
(17/46) 11.9 (4/4)
(10.5/12.6)
VINCENT DAM 0.24 MILES SE OF SITE 31G1 CONTROL 13S2 INDICATOR 500 KV SUBSTATION 0.41 MILES SE 0
0 DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.M O.
160
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
A-7
Intentionally Left Blank A-8
APPENDIX B LOCATION DESIGNATION, DISTANCE &
DIRECTION, AND SAMPLE COLLECTION &
ANALYTICAL METHODS
TABLE B-i:
xxYz -
Location Designation and Identification System for the Limerick Generating Station General code for identification of locations, where:
XX Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a clockwise direction.
Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations).
Y S
A B
C D
on-site location 0-1 mile off-site 1-2 miles off-site 2-3 miles off-site 3-4 miles off-site E : 4-5 miles off-site F : 5-10 miles off-site G : 10-20 miles off-site H : 20-100 miles off-site Z
Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.
B-1
TABLE B-2:
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2008 Location Location Description Distance & Direction From Site A
S,'d@e Water 13B1 Vincent Dam (indicator) 24S1 Limerick Intake (control) 10F2 Perkiomen Pumping Station (control)
R Drinpinoý (Rpfphlaj jAl@nr 1.75 miles SE 0.20 miles SW 7.25 miles E 15F4 15F7 16C2 28F3 Philadelphia Suburban Water Company (indicator)
Phoenixville Water Works (indicator)
Citizens Home Water Company (indicator)
Pottstown Water Authority (control)
MAiIL-hi-
'eekly / nmonthlhy 1 0F4 18E1 19B1 23F1 Control 25C1 n
Milk -q,-rterly 25E1 36E1 Control P
Air P-,ti-',nttc I Air Iodine 8.62 miles SE 6.33 miles SSE 2.66 miles SSE 5.84 miles WNW 6.60 miles ESE 4.21 miles S 1.95 miles SSW 5.02 miles SW 2.69 miles WSW 4.27 miles WSW 4.70 miles N 10S3 11S1 11S2 13C1 14S1 22G1 Keen Road LGS Information Center LGS Information Center King Road Longview Road Manor Substation (control) 0.50 miles E 0.38 miles ESE 0.38 miles ESE 2.84 miles SE 0.63 miles SSE 17.73 miles SW F.
F=*sh 16C5 29C1 Vincent Pool (indicator)
Pottstown Vicinity (control)
Downstream of Discharge Upstream of Intake r_1
'diment 16B2 16C4 33A2 Linfield Bridge (indicator)
Vincent Dam (indicator)
Upstream of Intake (control) 1.35 miles SSE 2.18 miles SSE 0.84 miles NNW H
flrna, I eat Veogetation 11S3 13S3 31G1 LGS Information Center LGS 500 KV Yard Prout's Jollyview Farm 0.35 miles ESE 0.24 miles SE 13.6 miles NW B-2
TABLE B-2:
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2008 Location Location Description Distance & Direction From Site I I W-WU=Q.rpeflglrp I plr=nprru -
11 36S2 3S1 5S1 7S1 10S3 11S1 13S2 14S1 18S2 21S2 23S2 25S2 26S3 29S1 31S1 34S2 Evergreen & Sanatoga Road Sanatoga Road Possum Hollow Road LGS Training Center Keen Road LGS Information Center 500 KV Substation Longview Road Rail Line along Longview Road Near Intake Building Transmission Tower Sector Site Boundary Met. Tower #2 Sector Site Boundary Sector Site Boundary Met. Tower #1 Intfnrgrei~u
- nintnp, 36D1 2E1 4E1 7E1 1OE1 1 0F3 13E1 16F1 19D1 20F1 24D1 25D1 28D2 29E1 31D2 34E1 Siren Tower No. 147 Laughing Waters GSC Neiffer Road Pheasant Road Royersford Road Trappe Substation Vaughn Substation Pikeland Substation Snowden Substation Sheeder Substation Porters Mill Substation Hoffecker & Keim Streets W. Cedarville Road Prince Street Poplar Substation Vamell Road 0.60 miles N 0.44 miles NNE 0.45 miles NE 0.59 miles ENE 0.50 miles E 0.38 miles ESE 0.41 miles SE 0.63 miles SSE 0.26 miles S 0.19 miles SSW 0.53 miles SW 0.46 miles WSW 0.40 miles W 0.55 miles WNW 0.26 miles NW 0.58 miles NNW 3.51 miles N 4.76 miles NNE 4.78 miles NE 4.26 miles ENE 3.94 miles E 5.58 miles ESE 4.31 miles SE 5.04 miles SSE 3.49 miles S 5.24 miles SSW 3.97 miles SW 3.99 miles WSW 3.83 miles W 4.95 miles WNW 3.87 miles NW 4.59 miles NNW 24.76 miles NE 2.14 miles NE 2.15 miles E 2.84 miles SE 3.20 miles SE 1.60 miles S 3.06 miles SSW 3.00 miles WNW Control and QPOciall ntgornt 5H1 6C1 9C1 13C1 15D1 1781 20D1 311D1 Birch Substation (control)
Pottstown Landing Field Reed Road King Road Spring City Substation Linfield Substation Ellis Woods Road Lincoln Substation B-3
TABLE B-3:
Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2008 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Monthly composite RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Limerick Generating water compositor.
Station)
Env. Inc., GS-01 Determination of gamma emitters by gamma snectroscopy Surface Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by from a continuous radiological analysis (Limerick Generating liquid scintillation water compositor.
Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Drinking Water Gross Beta Monthly composite RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2008 Gross Alpha and/or gross beta activity in from a continuous radiological analysis (Limerick Generating various matrices water compositor.
Station)
Env. Inc., W(DS)-01 Determination of gross alpha and/or gross beta in water (dissolved solids or total residue)
Env. Inc., W(SS)-02 Determination of gross alpha and/or gross-beta On water (ustjptndpd s*nlid.g Drinking Water Gamma Monthly composite RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy from a continuous radiological analysis (Limerick Generating water compositor.
Station)
Env. Inc., GS-01 Determination of gamma emitters by gamm;; spectroscopy Drinking Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-201 1 Tritium analysis in drinking water by from a continuous radiological analysis (Limerick Generating liquid scintillation water compositor.
Station)
Env. Inc., T-02 Determination of tritium in water (direct method)
Fish Gamma Semi-annual samples RMC-ER6 Collection of fish samples for 1000 grams (wet)
TBE-2007 Gamma emitting radioisotope analysis Spectroscopy collected via radiological analysis (Limerick Generating electroshocking or Station)
Env. Inc., GS-01 Determination of gamma emitters by other techniques gamma gpectro.scopy Sediment Gamma Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry)
TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy samples radiological analysis (Limerick Generating Station)
Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta One-week composite of RMC-ER8 Collection of air particulate and air 1 filter TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air iodine samples for radiological analysis (approximately 280 various matrices sampling through glass (Limerick Generating Station) cubic meters weekly) fiber filter paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters B -4
TABLE B-3:
Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2008 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Air Particulates Gamma Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing cubic meters)
Env. Inc., GS-01 Determination of gamma emitters by air particulate filters for gamma spectroscopic gamma spectroscopy analysis Air Iodine Gamma One-week composite of RMC-ER8 Collection of air particulate and air 1 filter TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy continuous air iodine samples for radiological analysis (approximately 280 sampling through (Limerick Generating Station) cubic meters weekly)
Env. Inc., 1-131-02 Determination of 1-131 in charcoal charcoal filter canisters by oamma spectroscopy (batch method)
Milk 1-131 Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)
Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk Gamma Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis Spectroscopy when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)
Env. Inc., GS-01 Determination of gamma emitters by nther times gamma spectroscopv TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of TLD samples for 2 dosimeters Global Dosimetry Dosimetry comprised of two radiological analysis (Limerick Generating Panasonic 814 Station)
(containing 3 each CaSOA elements)
B-5
I Figure B-I Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2008 B-6
NNE NE.
WS1 ss1 Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2008 B-7
Figure B-3 Environmental Sampling Locations Greater than Five Miles from the Limerick.Generating Station, 2008 B-8
APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY
TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/2007 - 03/31/2008 03/31/2008 - 06/30/2008 07/14/2008 - 09/29/2008 09/29/2008 - 12/29/2008 10F2 13B1 24S1 (1)
< 168 (1)
< 174
< 151
< 174
< 165
< 177
< 135
< 173
< 148
< 179 MEAN C-1
TABLE C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD (1) 10F2 07/14/2008 - 07/29/2008
< 1
< 1
< 2
< 1
<2
< 1
< 2
< 12
< 1
< 1
< 16
<4 07/29/2008 - 09/02/2008
< 3
<3
< 6
<2
< 5
< 3
< 5
< 15
<2
<3
< 26
< 8 09/02/2008 - 09/29/2008
< 2
<2
<4
<2
< 3
<2
<4
< 12
<2
<2
< 21
<6 09/29/2008 - 11/03/2008
< 1
< 1
< 3
< 1
< 2
< 1
< 2
< 11
< 1
< 1
< 41
< 12 11/03/2008 - 12/02/2008
< 3
<4
< 7
<4
< 7
<3
< 7
< 7
< 3
<4
<20
< 5 12/02/2008 - 12/29/2008
< 3
< 3
<6
< 3
<6
<4
< 5
< 11
< 3
< 3
<23
< 8 MEAN 13B1 12/31/2007 01/29/2008
< 5
< 6
< 13
< 5
< 10
< 6
< 9
< 5
<4
< 5
< 21
< 8 01/29/2008 -03/04/2008
< 4
<4
< 9
< 5
<9
<4
< 7
< 5
<4
< 5
< 18
< 6 03/04/2008 -03/31/2008
< 3
<2
<4
< 3
<5
< 3
< 5
< 5
< 3
< 3
< 14
< 3 03/31/2008 -04/28/2008
< 4
<4
< 8
<4
< 9
<4
< 8
< 7
<4
<4
< 19
< 6 04/28/2008 -06/03/2008
< 4
< 5
< 11
< 6
< 10
< 5
< 8
< 13
<4
< 5
< 27
< 13 06/03/2008 -06/30/2008
< 2
< 2
< 5
< 2
< 5
< 3
< 5
< 15
< 2
< 2
< 24
< 6 06/30/2008 -07/29/2008
< 1
< 1
< 2
< 1
<2
< 1
< 2
< 12
< 1
< 1
< 15
< 5 07/29/2008 -09/02/2008
< 2
< 2
< 5
< 2
< 5
< 3
< 5
< 13
<2
<2
< 26
< 7 09/02/2008 -09/29/2008
< 2
< 2
< 5
<2
<4
<2
< 3
< 12
<2
<2
< 20
< 7 09/29/2008 -11/03/2008
< 1
< 1
< 3
< 1
<2
< 1
<2
< 11
< 1
< 1
< 36
< 14 11/03/2008 - 12/02/2008
< 7
< 5
< 12
< 4
< 13
< 6
< 10
< 14
< 5
< 5
< 32
< 10 12/02/2008 -12/29/2008.
< 3
< 3
< 8
< 3
<6
<4
< 5
< 12
< 3
< 3
<24
< 7 MEAN C-2
TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/31/2007 - 01/29/2008 01/29/2008 - 03/04/2008 03/04/2008 - 03131/2008 03/31/2008 - 04/28/2008 04/28/2008 - 06/03/2008 06/03/2008 - 06/30/2008 06/30/2008 - 07/29/2008 07/29/2008 - 09/02/2008 09/02/2008 - 09/29/2008 09/29/2008 - 11/03/2008 11/03/2008 - 12/02/2008 12/02/2008 - 12/29/2008 15F4 15F7 16C2 28F3 2.6 2.3 3.9 3.6 4.0 3.9 5.5 5.4 5.8 5.7 5.8 4.3
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
+/-
1.6 1.5 1.6 1.5 1.7 1.8 1.8 2.2 1.9 1.9 1.7 1.9 2.7 +
3.2 +
2.7 +/-
4.5 +
3.0 +/-
4.3 +
6.1 +
4.7 +/-
7.2 +/-
5.0 +/-
6.7 +/-
< 2.5 1.5 1.5 1.5 1.6 1.6 1.8 1.8 2.2 2.0 1.9 1.8
< 2.2 3.3 +/- 1.6
< 2.1 2.8 +/- 1.5 3.4 +/- 1.7 3.8 +/- 1.8 4.2 +/- 1.7 6.0 +/- 2.3 3.8 +/- 1.8 3.2 +/- 1.7 4.6 +/- 1.6 3.3 +/- 1.9 3.8 +/-
1.8 3.0 3.1 2.9 2.3 2.5 3.3 3.6 4.0 4.0 5.1 3.5 2.8
+/- 1.6
+/- 1.5
+/- 1.5
+/- 1.5
+/- 1.6
+/- 1.8
+/- 1.7
+/- 2.2
+/- 1.8
+/- 1.9
+/- 1.5
+/- 1.8 MEAN 4.6 +/-
2.3 4.7 +/-
3.1 3.4 +/- 1.6 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/31/2007 - 03/31/2008 03/31/2008 - 06/30/2008 06/30/2008 - 09/29/2008 09/29/2008 - 12/29/2008 15F4 15F7 16C2 28F3
< 168
< 176
< 147
< 174
< 165
< 177
< 145
< 174
< 160
< 178
< 147
< 172
< 164
< 176
< 148
< 174 MEAN C-3
TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC COLLECTION PERIOD 15F4 12/31/2007 - 01/29/2008 01/29/2008 - 03/04/2008 03/04/2008 - 03/31/2008 03/31/2008 - 04/28/2008 04/28/2008 - 06/03/2008 06/03/2008 - 06/30/2008 06/30/2008 - 07/29/2008 07/29/2008 - 09/02/2008 09/02/2008 - 09/29/2008 09/29/2008 - 11/03/2008 11/03/2008 - 12/02/2008 12/02/2008 - 12/29/2008 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MEAN
<5
<4
<5
<4
<1
<1
<2
<2
<1
<6
<3
<5
<5
<3
<4
<4
<2
<1
<2
<2
<1
<5
<3
<5
<5
<5
<5
< 5
<2
<1
<3
<2
<1
<7
<3
<5
<5
<2
<4
<4
<2
<1
<2
<2
<1
<5
<4
< 10
- 10
< 11
< 10
< 12
<3
<2
<7
<5
<3
< 11
<7
< 12
< 10
<5
< 11
<8
<4
<2
<5
<4
<3
< 10
<8
<4
<5
<5
<4
<4
<1
<1
<3
<2
<1
<6
<4
<7
<6
<4
<4
<3
<2
<1
<2
<2
<1
<5
<3
< 11
< 10
<9
<9
< 11
<3
<2
<5
<4
<2
< 10
<7
< 11
< 12
<6
<7
<8
<4
<2
<4
<3
<2
< 10
<8
<5
< 5
<6
<3
<4
<2
<1
<3
<2
<2
<6
<4
<5
<6
<3
<6
<4
<2
<1
<3
<2
<1
<6
<5
< 8
<8
<8
< 8
<9
<3
<2
<5
<4
< 2
<9
<7
<7
< 10
<5
<8
<7
<3
<2
<4
<3
<3
<7
<7
<7
<6
<9
< 10
<13
< 10
< 12
< 14
- 14
<12
< 14
< 12
<7
<7
<5
<8
< 12
<11
< 12
< 13
<11
< 11
-<12
< 13
<5
<5
<5
< 5
<4
<1
<1
<2
<2
<1
<6
<3
<5
<5
<3
<5
<4
<2
<1
<2
<1
<1
<5
<3
<5
<5
< 5
<6
<5
<1
< 1
<3
< 2
<1
<6
<3
<6
<7
<2
<5
<4
<2
<1
<2
<2
<1
<5
<4
< 20
< 19
< 23
< 25
< 32
< 17
< 15
< 25
< 25
< 53
- 31
< 26
< 21
< 20
< 13
< 21
< 24
< 19
< 16
< 22
<18
< 44
- 27
< 26
<7
<7
<7
<7
< 11
<5
<4
<8
<7
< 13
< 13
<7 15F7 12/31/2007 01/29/2008 03/04/2008 03/31/2008 04/28/2008 06/03/2008 06/30/2008 07/29/2008 09/02/2008 09/29/2008 11/03/2008 12/02/2008
- 01/29/2008
- 03/04/2008
- 03/31/2008
- 04/28/2008
- 06/03/2008
- 06/30/2008
- 07/29/2008
- 09/02/2008
- 09/29/2008
- 11/03/2008
- 12/02/2008
- 12/29/2008
<7
<7
<4
<6
<7
<6
<4
<8
<6
< 12
<7
<9 MEAN C-4
TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC COLLECTION PERIOD 16C2 12/31/2007 - 01/29/2008 01/29/2008 - 03/04/2008 03/04/2008 - 03/31/2008 03/31/2008 - 04/28/2008 04/28/2008 - 06/03/2008 06/03/2008 - 06/30/2008 06/30/2008 - 07/29/2008 07/29/2008 - 09/02/2008 09/02/2008 - 09/29/2008 09/29/2008 - 11/03/2008 11/03/2008 - 12/02/2008 12/02/2008
- 12/29/2008 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MEAN
<4
<5
<4
< 4
<5
<2
<1
<2
<2
<1
<6
<3
<5
<5
<3
<4
<4
<2
<1
<2
<2
<1
<4
<4
<4
<5
<6
<4
<5
<2
<1
<3
<2
<1
<6
<5
<6
<5
<4
<5
<4
<2
<1
<2
<2
<1
<5
<4
< 8
<9
< 11
<8
<9
<5
<3
<6
<4
<4
< 13
< 11
<11
<10
<6
< 12
<10
<4
<3
<5
<4
<3
< 11
< 10
< 5
<4
<6
<5
<5
<2
<1
<4
<1
<1
<6
<4
< 8
<11
<8
<9
< 11
<4
<2
<5
<3
<2
< 11
< 9
<15
<9
<7
< 10
< 11
<3
<2
<5
<3
<2
<9
<7
<4
<4
<4
< 4
<6
<2
<1
<3
<2
<1
<7
<4
<6
<5
<3
<4
<5
<2
<1
<3
<2
<1
<5
<4
<7
<8
< 10
<7
< 10
<4
<2
<5
<3
<2
< 11
<7
<9
<9
<6
<9
<8
<3
<2
<4
<3
<2
< 10
<8
<6
< 6
<9
<8
<.13
< 13
< 15
< 14
<11
<12
< 14
< 14
< 7
<5
<6
< 11
<12
<11
< 13
< 12
< 13
< 11
<12
- 14
<4
<5
<5
<4
<5
<2
<1
<2
<1
<1
<5
<4
<5
<5
<3
<5
<4
<1
<1
<2
<2
<1
<5
<4
<4
<5
<6
<5
<5
<2
<1
<2
<2
<1
<7
<4
<6
<5
<4
<6
<5
<2
<1
<2
<2
-<1
<5
<4
<17
< 16
< 29
- 21
< 30
< 22
< 19
< 25
<18
- 50
< 31
< 32
< 23
- 20
< 14
< 30
< 25
<18
<17
< 24
'< 21
< 35
< 25
< 26
<5
<5
<8
<7
<11
<7
<6
<9
<6
< 14
<9
< 10
<7
<5
<5
<7
<10
<5
<5
<7
<6
< 15
< 10
< 10 28F3 12/31/2007 01/29/2008 03/04/2008 03/31/2008 04/28/2008 06/03/2008 06/30/2008 07/29/2008 09/02/2008 09/29/2008 11/03/2008 12/02/2008
- 01/29/2008
- 03/04/2008
- 03/31/2008
- 04/28/2008
- 06/03/2008
- 06/30/2008
- 07/29/2008
- 09/02/2008
- 09/29/2008
- 11/03/2008
- 12/02/2008
- 12/29/2008
<6
<5
<4
<5
<5
<2
<1
<2
<1
<1
<7
<5 MEAN C-5
TABLE C-II1.1 CONCENTRATIONS OF GAMMA EMMITTERS IN PREDATOR AND BOTTOM FEEDER (FISH)
SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD 16C5 PREDATOR 05108/2008 10/14/2008 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-137 3300 +/- 508
< 27 3290 +/- 766
< 35
< 31
< 53
< 73
< 100
< 24
< 41
< 68
< 86
< 72
< 516
< 26
< 42
< 28
< 39 MEAN 3295 +/- 14 16C5 BOTTOM FEEDER 05/08/2008 2660 +/- 559
< 31 10/14/2008 3460 +/- 621
< 40
< 28
< 37
< 75
< 88
< 38
- 39
< 57
< 75
< 79
< 323
< 26
< 28
< 31
< 35 MEAN 3060 +/- 1131 29C1 PREDATOR 05/07/2008 2690 +/- 731
< 36 10/13/2008 2850 +/- 635
< 47 MEAN 2770 +/- 226 29C1 BOTTOM FEEDER 05/07/2008 3680 +/- 629
< 39 10/13/2008 3350 +/- 598
< 41
< 36
< 51
< 92
- 105
< 46
< 46
< 95
< 91
< 105
- 490
< 42
< 45
< 41
< 47
< 35
< 46
< 73
< 105
< 37
< 32
<84
< 95
< 95
< 454
< 38
< 40
< 37
< 37 MEAN 3515 +/- 467 C-6
TABLE C-IV.1 STC COLLECTION PERIOD 16B2 06/11/2008 12/08/2008 MEAN 16C4 06/11/2008 12/08/2008 MEAN 33A2 06/11/2008 12/08/2008 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-1 1560 +/- 774 16600 +/- 1780
< 103
< 83-
< 90
< 235
< 65 814 12900 +/- 1440
< 66
< 87
< 45
< 1550
< 55 1560 +/- 0 14750 +/- 5233 5760 +/- 1140 17700 +/- 2180
< 129
< 108
< 119
< 337
< 94 5990 +/- 1520 8920 +/- 1370
< 128
< 122
< 144
< 4030
< 100 5875 +/- 325 13310 +/- 12417 795 13000 +/- 1650
< 85
< 75
< 75
< 220
< 71 766 14500 +/- 1450
< 62
< 63
< 53
< 1340
< 59 13750 +/- 2121 34 Cs-1 37 176 +/- 69
< 77 176 +/- 0 162 +/- 123
< 124 162 +/- 0
< 74
< 58 m
C-7
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I I GROUPI 1I GROUP Ill COLLECTION PERIOD 12131/2007(
01/07/2008 01/14/2008 01/22/2008 01/28/2008 02/04/2008 02/11/2008 02/19/2008 02/25/2008 03/03/2008 03/10/2008 03/17/2008 03/24/2008 03/31/2008 04/07/2008 04/14/2008 04/21/2008 04/28/2008 05/05/2008 05/12/2008 05/20/2008 05/27/2008 06/02/2008 06/09/2008 06/16/2008 06/23/2008 06130/2008 07/07/2008 07/14/2008 07/21/2008 07/28/2008 08/04/2008 08/11/2008 08/18/2008 08/25/2008 09/01/2008 09/09/2008 09/15/2008 09/22/2008 09/29/2008 10/07/2008 10/13/2008 10/20/2008 10/27/2008 11/04/2008 11/10/2008 11/17/2008 11/24/2008 12/01/2008 12/08/2008 12/15/2008 12/22/2008 110U120UU
-01/14/2008
-01/22/2008
-0 1/28/2008
-02/04/2008
-02/11/2008
-02/19/2008
-02/25/2008
-03/03/2008
-03/10/2008
-03/17/2008
-03/24/2008
-03/31/2008
-04/07/2008
-04/14/2008
-04/21/2008
-04/28/2008
-05/05/2008
-05/12/2008 05/20/2008 05/27/2008
- 06/02/2008 06/09/2008
- 06/16/2008
- 06/23/2008
- 06/30/2008 07/0712008 07/14/2008 07/21/2008
- 07/28/2008
- 08/04/2008 08/11/2008
- 08/18/2008
- 08/25/2008
- 09/01/2008
- 09/09/2008
- 09/15/2008
- 09/22/2008
- 09/29/2008
- 10/07/2008
- 10/13/2008 10/20/2008
- 10/27/2008
- 11/04/2008 11/10/2008
- 11/17/2008
- 11/24/2008
- 12/01/2008
- 12/08/2008
- 12/15/2008
- 12/22/2008
- 12/29/2008 10S3 21+/- 5 13 +/- 5 19 +/- 4 21 +/-6 27 +/-5 15 +/-5 19 +/-5 12 +/-5 10 +/-5 12 +/-5 19 +/-5 14 t 4 12 +/- 5 13 +/- 4 8+/-4 17 +/-5 18 +/-5 16 +/-4 13 +/-4 10 +/-4 7+/-4 14 +/-5 9+/-4 15 +/-5 13 +/-4 16 +/-5 14 +/-5 15 +/-5 18 +/-5 17 +/-5 liSi 23+/- 6 12 +/- 5 15 +/- 5 24 +/- 6 32 +/- 6 18 +/- 5 18 +/- 5 22 +/- 6 10 +/- 5 12 +/- 5 19 +/- 5 15 +/- 5 16 +/- 5 15 +/- 4 8+/-4 14 +/-5 18+/-5 17 +/-5 13 +/-5 10 +/-4 8+/-4 8+/-5 13 +/-5 19 +/-5 12 +/-5 17+/-5 16 +/-5 13 +/-5 24 +/-6 19 +/-5 14S1 1b+/-b 15 +/-5 21 +/-5 22 +/-6 28 +/-6 15 +/-5 21 +/-5 17 +/-6 12 +/-5 10 +/-5 22 +/-5 14 +/-5 16 +/-5 13 +/-4 7+/-5 18 +/-5 15 +/-5 20 +/-5 15 +/-5 9+/-4 7+/-4 16 +/-5 10 +/-5 17 +/-5 12 +/-5 14 +/-5 17 +/-5 12 +/-5 20 +/-6 (1) 1301 29+/-6 12 +/-5 22 +/-5 21 +/-6 23 +/-5 14 +/-5 18 +/-5 16 +/-6 12 +/-5 13 +/-5 16 +/-5 11 +/-5 16 +/-5 14 +/-4 11 +/-5 21 +/-5 18 +/-5 15 +/-5 14 +/-5
<6 9+/-5 15 +/- 6 13 +/- 5 18 +/- 5 16 +/- 5 14 +/- 5 13 +/- 5 15 +/- 5 26 +/- 6 24 +/- 5 18 +/- 5 14 +/- 5 14 +/- 5 14 +/-5 12 +/-5 23 +/-5 18 +/-6 15 +/-5 (1) 15 +/-4 21 +/-6 21 +/-6 15 +/-5 17 +/- 4 19 +/- 6
<7 16 +/- 5 24 +/- 5 17 +/- 5.
16 +/- 5 11+/- 5 32 +/-6 22G1 24 +/-6 16 +/- 5 20 +/- 5 22 +/-6 27 +/-6 18 +/-5 19 +/-5 17 +/-6 15 +/-5 9+/-5 20 +/-5 11 +/-5 17 +/-5 13 +/-4 10 +/-5 19 +/-5 18 +/-5 18 +/-5 15 +/-5 12 +/-4 8+/-5 11 +/-5 9+/-5 15 +/-5 13 +/-5 14 +/-5 19 +/-5 14 +/-5 22 +/-6 21 +/- 5 24 +/- 5 14 +/- 5 14 +/- 5 18 +/- 5 9+/-5 22 +/-5 21+/-6 16 +/-5 10 +/-5 17 +/-5 17 +/- 6 19 +/- 6
.12 +/- 5 17 +/- 5 16 +/- 5
< 7 14 +/- 5 19 +/- 5 14 +/- 5 15 +/- 5 13 +/- 5 38 +/- 6 22 +/-5 22 +/-5 21 +/-5 13 +/-5 14 +/-5 19 +/-5 15 +/-5 17 +/-5 17 +/-5 16 +/-5 18 +/-5 16 +/-5 11 +/- 5 13 +/- 5 13 +/- 5 25 +/-5 22 +/-5 22 +/-5 13 +/-5 15 +/-6 13 +/-5 14 +/- 5 11 +/- 4 20 +/- 5 10 +/-5 10 +/-5 10 +/-5 11 +/- 4 13 +/- 4 12 +/- 4 20 +/-6 21 +/-6 19 +/-6 21 +/-6 22 +/-6 24 +/-6 15 +/-5 14 +/-5 15 +/-5 16 +/-4 17 +/-5 19 +/-5 17 +/-5 14+/-t5 11 +/-5 10 +/-5 7
<7 14 +/-5 17 +/-5 14 +/-5 20 +/-5 23 +/-5 21 +/-5 19 +/-5 17 +/-5 17 +/-5 18 +/-5 17 +/-5 17 +/-5 14 +/- 5 17 +/- 5 11 +/-5 28 +/-5 33 +/-6 32+/-6 16 +/-9 17 +/-10 16+/-10 MEAN 17 +/-10 16 +/-11
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8
TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP I - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN-2SD COLLECTION PERIOD MIN MAX MEAN+
2SD COLLECTION PERIOD MIN MAX MEAN+
2SD 1//13 IILUU U IIlOIZUUO Iz ZL-+
0.0 "
123IJ0IIU7 -
V1(LWIUO 01/28/2008 02/25/2008 03/31/2008 04/28/2008 06/02/2008 06/30/2008 07/28/2008 09/01/2008 09/29/2008 10/27/2008 12/01/2008 02/25/2008 03/31/2008 04/28/2008 06/02/2008 06/30/2008 07/28/2008 09/01/2008 09/29/2008 10/27/2008 12/01/2008 12/29/2008 12 10 7
7 9
12 11 10 11 10 32 22 18 20 19 24 22 25 24 23 20.1 14.2 13.7 12.3 13.8 16.8 16.4 15.5 17.3 16.3
+/- 11.7
+/- 7.3
+/- 8.1
+/- 8.1
+/- 5.9
+/- 6.7
+/- 7.0
+/- 10.7
+/- 8.9
+/- 7.5 01/28/08 02/25/08 03/31/08 04/28/08 06/02/08 06/30/08 07/28/08 09/01/08 09/29/08 10/27/08 02/25/08 03/31/08 04/28/08 06/02/08 06/30/08 07/28/08 09/01/08 09/22/08 10/27/08 12/01/08 Ilz 14 11 11 9
13 13 12 15 15 16 11 ZZI 4I.U
+/-
1-.2 23 16 21 15 18 26 18 23 21 24 32 17.7 13.6 16.2 13.2 15.1 19.6 14.5 18.4 17.6 18.8 19.1
+/- 7.5
+/- 5.2
+/- 9.0
+/- 5.7
+/- 4.5
+/- 13.2
+/- 4.0
+/- 7.9
+/- 7.0
+/- 7.0
+/- 17.8 12/31/07 - 01/28/08 01/28/08 - 02/25/08 02/25/08 - 03/31/08 03/31/08 - 04/28/08 04/28/08 - 06/02/08 06/02/08 - 06/30/08 06/30/08 - 07/28/08 07/28/08 - 09/01/08 09/01/08 - 09/29/08 09/29/08 - 10/27/08 10/27/08 - 12/01/08 12/01/08.- 12/29/08 16 24 20.4 +/- 6.9 17 9
10 8
9 14 9.
10 12 14 13 27 20 19 18 15 22 24 22 19 19 38 20.1 +/- 8.9 14.3 +/- 8.9 15.0 +/- 7.9 12.9 +/- 7.3 12.5 + 5.4 18.9 +/- 7.2 15.7 +/- 11.4 17.0 +/- 11.0 16.3 +/- 5.4 16.5 +/- 4.3 19.9 +/- 24.3 11 33 20.0 +/- 14.0 12/01/08 - 12/29/08 12/31/2007 - 12/29/2008 7 "
33 16.1 +/- 9.8 12/31/07 - 12/29/08 11 32 16.9 +/- 9.6 12/31/07 - 12/29/08 8
38 16.5 +/- 10.5 C-9
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 I
10US3 12/31/2007 03/31/2008 06/30/2008 09/29/2008 MEAN 1iS1 12/31/2007 03/31/2008 06/30/2008 09/29/2008 MEAN 13C1 12/31/2007 03/31/2008 06/30/2008 09/29/2008 UOJIJIILLUUO
- 06/30/2008
- 09/29/2008
- 12/29/2008
- 03/31/2008
- 06/30/2008
- 09/29/2008
- 12/29/2008
- 03/31/2008
- 06/30/2008
- 09/29/2008
- 12/29/2008
- 03/31/2008
- 06/30/2008
- 09/29/2008
- 12/29/2008
- 03/31/2008
- 06/30/2008
- 09/29/2008
- 12/29/2008 82 +/- 42 81 111 61 I
Ll
+/- 29
+/- 77
+/- 25 76 97 145 60
+/- 21
+/- 24
+/- 73
+/- 25 94 +/- 74
<2
<3
<3
<3
<2
<4
<4 64 94 156 79
<4
<8
<3
+/- 25
+/- 28
+/- 65
+/- 22
<3
<3
<4
<2
<3
<3
<10
<4
<4
<4
<10
<3
<4
<4
<12
<3
<3
<3
<2
<2
<2
<5
<3
<3
<4
<4
<3
<3
<2
<4
<3
<4
<3
<3
<3
<3
<4
<3
<3
<2
<5
<3
<3
<3
<4
<2
<3
<2
<5
<3
<4
<3
<4
<3
<2
<3
<2 MEAN 98 +/- 81
<2
<2
<3
<3
<2
<3
<4
<2
<3
<2
<3
<3
<4
<3
<3
<3 14S1 12/31/2007 03/31/2008 06/30/2008 09/29/2008 68 74 128 56
+/- 33
+/- 33
+/- 75
+/- 25 MEAN 22G1 12/31/2007 03/31/2008 06/30/2008 09/29/2008 MEAN 82 +/- 64 85 +/- 33 66 +/- 31 134 +/- 48 49 +/- 19 83 +/- 73
<3
<3
<5
<3
<3
<2
<5
<2
<4
<4
<9
<3 C-10
TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/31/2007 01/07/2008 01/07/2008 -01/14/2008 01/14/2008 -01/22/2008 01/22/2008
-01/28/2008 01/28/2008
-02/04/2008 02/04/2008-02/11/2008 02/11/2008
-02/19/2008 02/19/2008
-02/25/2008 02/25/2008
-03/03/2008 03/03/2008
-03/10/2008 03/10/2008
-03/17/2008 03/17/2008
-03/24/2008 03/24/2008 -03/31/2008 03/31/2008
-04/07/2008 04/07/2008
-04/14/2008 04/14/2008 -04/21/2008 04/21/2008 -04/28/2008 04/28/2008
-05/05/2008 05/05/2008 -05/12/2008 05/12/2008 -05/20/2008 05/20/2008 -05/27/2008 05/27/2008
-06/02/2008 06/02/2008 -06/09/2008 06/09/2008 -06/16/2008 06/16/2008 -06/23/2008 06/23/2008 -06/30/2008 06/30/2008
-07/07/2008 07/07/2008
-07/14/2008 07/14/2008
-07/21/2008 07/21/2008 - 07/28/2008 07/28/2008 - 08/04/2008 08/04/2008 - 08/11/2008 08/11/2008 - 08/18/2008 08/18/2008 - 08/25/2008 08/25/2008 - 09/01/2008 09/01/2008 - 09/09/2008 09/09/2008 - 09/15/2008 09/15/2008 - 09/22/2008 09/22/2008 - 09/29/2008 09/29/2008 - 10/07/2008 10/07/2008 - 10/13/2008 10/13/2008 - 10/20/2008 10/20/2008 - 10/27/2008 10/27/2008 - 11/04/2008 11/04/2008 - 11/10/2008 11/10/2008 - 11/17/2008 11/17/2008 - 11/24/2008 11/24/2008 - 12/01/2008 12/01/2008 - 12/08/2008 12/08/2008 - 12/15/2008 12/15/2008 - 12/22/2008 12/22/2008 - 12/29/2008 10S3
- <19
- 15
- 18
- 26
- 16
- 31
- 20
- 29
- 10
< 22
< 48
- 24
- 14
- 16
- 19
- 57
- 19
- 23
- 33
- 17
- 25
- 27
- 19
- 13
- 29
< 44
- 40
- 22
- 20
- 12
- 23
- 37
- 29
- 23
- 31
- 22
- 22
- 35
- 59
- 33
- 24
- 26
- 23
- 25
- 25
- 52
- 24
- 20
- 37
- 31
- 28
- 26 GROUP I lisi
- <31
- 30
< 20
- 51
- 27
- 33
- 39
< 47
- 21
- 38
- 52
- 40
- 36
< 18
< 42.
- 61
- 48
- 58
- 20
- 34
- 54
- 68
- 49
- 27
- 57
- 59
- 66
- 41
- 29
- 20
- 42
- 67
- 69
- 54
- 62
- 51
- 50
- 44
- 59
- 65
- 43
< 62
- 53
- 59
- 60
- 68
- 57
< 47
- 55
- 63
- 66
- 59 14
- <31
- 31
- 20
- 51
- 27
< 34
- 39
- 48
- 21
- 39
- 53
- 40
- 36
- 18
- <42
- 62
- <49
- 59
- 37
- 34
- 56
- 68
- 50
- 27
- 59
- 59
- 67
< 41
- 30
< 43
- 67
- 70
< 54
< 64
- 51
- 51
- 45
- 59
- 66
- 44
< 62
- 54
- 59
- 60
< 58
- 57
< 47
- 56
- 63
- 67
- 60 IGROUP 11 Si 1301
< 31
< 31
- 20
- 52
- 27
- 25
< 40
- 48
- 21
- 39
- 54
- 40
- 37
- 18
- 43
- 27
- 49
- 60
- 37
< 35
< 55
<70
<50
<28
<58
< 59
<66
<42
<29 (1)
< 20
< 42
<66
<69
< 53
<62
<51
<50
< 44
<65
< 43
<61
< 53
<58
< 59
<68
<56
<46
< 55
<62
<65
< 59 IGROUP III 22G1
- <31
- 31
- 12
- 51
- 27
- <34
< 39
- 48
- 21
- 39
- 29
< 40
- 36
- 42
- 62
< 49
- 59
- 37
- <34
- 56
- 68
- 50
- 27
- 58
- 59
- 67
< 41
- 30
- 20
< 43
- 68
- 70
- 54
< 64
- 51
< 49
- 46
- 59
- 66
- <44
- 62
- 54
- 60
- 60
- 58
< 57
< 47
- 56
- 63
- 67
- 60
-J MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION 6-11
TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARMS 23F1 36E1 I
INDICATOR FARMS 19B1 COLLECTION PERIOD 10F4 18E1 25C1 25E1 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/29/2008 11/11/2008 11/25/2008 12/16/2008
< 0.6
< 0.6
< 0.6
< 0.5
< 0.5
< 0.5
< 0.8
< 0.9
< 0.8
< 0.4
< 0.8
< 0.8
< 0.6
< 0.8
< 0.6
< 0.5
< 0.9
< 0.6
<*0.8
< 0.9
< 0.7
< 0.8
< 0.7
< 0.5
< 0.8
< 0.8
< 0.5
< 0.6
< 0.9
< 0.3
< 0.6
< 0.5
< 0.8
< 0.8
< 0,6
< 0.4
< 0.7
< 0.7
< 0.7
< 0.9
< 0.6
< 0.6
< 1.0
< 0.7
< 0.6
< 0.8
< 0.7
< 0.6
< 0.7
< 0.6
< 0.7
< 0.4
< 0.5
< 0.6
< 0.9
< 0.8
< 0.8
< 0.4
< 0.8
< 0.8
< 0.6
< 0.8'
< 0.5
< 0.5
< 0.8
< 0.6
< 0.9
< 0.9
< 0.7
< 0.6
< 0.7
< 0.6
< 0.6
< 0.5
< 0.6
< 0.5
< 0.8
< 0.7
< 0.7
< 0.4
< 0.7
< 0.7
< 0.6
< 0.9
< 0.5
< 0.5
< 0.9
< 0.6
< 0.8
< 0.7
< 0.8
< 0.8
< 0.7
< 0.8
< 0.5
< 0.6
< 0.5
< 0.4
< 0.7
< 0.8
< 0.9
< 0.6
< 0.8
< 0.8
< 0.7
< 0.9
< 0.6
< 0.6
< 0.9
< 0.8
< 0.8
< 0.9
< 0.8
< 0.6
< 1.0
< 0.6
< 0.6
< 0.8 MEAN C-12
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 10F4 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/29/2008 11/11/2008 11/25/2008 12/16/2008 MEAN 18E1 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/28/2008 11/11/2008 11/25/2008 12/16/2008 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1160 1450 1230 1200 1220 1230 1190 1300 1160 1290 1240 1320 1410 1190 1220 1370 1280 1280 1230 1290 1270 1210
+/- 108
+/- 165
+/- 114
+/- 161
+/- 146
+/- 144
+/- 152
+/- 143
+/- 137
+/- 150
+/- 113
+/- 129
+/- 135
+/- 138
+/- 123
+/- 151
+/- 55
+/- 134
+/- 54
+/- 42
+/- 67
+/- 141 1261 +/- 152
<4
<8
<4
<6
<7
<5
<6
<6
<5
<7
<4
<5
<5
<5
<5
<7
<2
<5
<2
<1
<1
<6
<5
<5
<7
<6
<6
<6
<7
<5
<7
<7
<6
<5
<5
<4
<6
<5
<2
<5
<2
<1
<2
<6
<4
<9
<5
<7
<8
<6
<6
<6
<6
<6
<5
<6
<6
<6
<6
<7
<2
<6
<2
<1
<1
<6
<6
<6
<7
<7
<6
<7
<8
<6
<8
<7
<7
<5
<5
<5
<6
<5
<2
<6
<2
<1
<2
<8
< 21
< 42
< 19
< 25
< 36
< 21
< 36
< 31
< 17
< 43
<31
< 44
< 59
< 41
< 36
< 43
< 52
< 44
< 48
<41
< 37
< 31
< 26
<'24
< 33
< 22
- 27
< 27
< 34
< 31
< 29
< 47
< 43
< 36
< 53
< 33
< 51
< 31
< 41
< 35
< 42
< 52
< 48
< 32 6
14 5
5 12 6
8 6
7 15 8
14 12 11 10 11 15 14 14 13 10 10 1200 1370 1180 1330 1210 1170 1310 1310 1190 1400 1290 1270 1080 1160 1190 1130 1300 1170 1360 1190 1310 1090
+/- 126
+/- 132
+/- 145
+/- 147
+/- 131
+/- 141
+/- 181
+/- 157
+/- 171
+/- 171
+/- 140
+/- 118
+/- 118
+/- 104
+/- 146
+/- 118
+/- 51
+/- 131
+/- 51
+/- 53
+/- 80
+/- 150
<9
<7
< 10
<7
<8
<7
< 13
<4
<8
< 15
< 15
< 10
< 13
<8
.< 12
<7
< 12
< 12
< 12
< 12
< 13
<7 1237 +/- 183 C-13
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 19B1 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/28/2008 11/11/2008 11/25/2008 12/16/2008 MEAN 23F1 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/28/2008 11/11/2008 11/25/2008 12/16/2008 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1310 +/- 112 1280 +/- 151 1140 +/- 130 1280 +/- 146 1290 +/- 152 1310 +/- 160 1220 +/- 169 1320 +/- 126 1270 +/- 158 1320 +/- 133 1390 +/- 129 1400 +/- 148 1380 +/- 91 1380 +/- 131 1300 +/- 134 1310 +/- 148 1300 +/- 57 1300 +/- 143 1350 +/- 57 1290 +/- 50 1370 +/- 69 1390 +/- 149 1314 +/- 121
<4
<6
<5
<6
<6
<5
<7
<5
<5
<7
<5
<5
<4
<6
<4
<7
<2
<5
<2
<1
<1
<5
<5
<3
<6
<6
<6
<6
<6
<6
<8
<7
<7
<5
<4
<5
<5
<6
<2
<5
<2
<1
<1
<6
<5
<6
<6
< 6
<8
<6
<8
<5
<9
<6
<6
<6
<3
<6
<6
<8
<3
<6
<2
<1
<2
<6
<6
<4
<7
<8
<7
<7
<8
<7
<8
<8
<7
<5
<5
<6
<5
<7
<2
<5
<2
<1
<2
<8
< 19
< 35
< 28
< 23
< 28
< 23
< 29
< 30
< 26
< 41
< 37
< 44
< 36
< 46
< 40
< 37
< 51
< 37
< 46
< 43
< 39
< 31
< 30
< 14
< 29
< 26
< 36
< 22
< 37
< 38
< 27
< 58
< 46
< 43
< 51
< 36
< 36
< 31
< 37
< 35
< 49
< 39
< 36
< 33
<6
<8
< 8
<7
< 12
< 7
< 14
< 10
<7
< 13
<9
< 14
< 13
< 13
< 12
< 10
<-15
< 10
< 14
< 14
<11
<8
<7
<4
<7
<5
<9
<5
<9
<8
< 11
< 14
< 14
< 15
< 14
< 12
< 13
< 10
< 12
<8
< 15
< 14
< 12
<8 1160 1310 1130 1130 1050 1180 1310 1320 1290 1120 1240 1360 1280 1270 1260 1310 1330 1270 1340 1260 1210 1290
+/- 132
+/- 130
+/- 142
+/- 159
+/- 151
+/- 153
+/- 212
+/- 144
+/- 171
+/- 153
+/- 146
+/- 121
+/- 112
+/- 143
+/- 110
+/- 136
+/- 46
+/- 113
+/- 52
+/- 44
+/- 66
+/- 156 1246 +/- 168 C-14
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 25C1 01/15/2008 02/12/2008 03/11/2008 04/01/2008 04/15/2008 04/29/2008 05/13/2008 05/27/2008 06/10/2008 06/24/2008 07/08/2008 07/22/2008 08/05/2008 08/19/2008 09/02/2008 09/16/2008 09/30/2008 10/14/2008 10/28/2008 11/11/2008 11/25/2008 12/16/2008 MEAN 25E1 01/15/2008 04/01/2008 07/08/2008 10/14/2008 K-40 Cs-134 Cs-137 Ba-140 La-140 1340 +/- 127 1110 +/- 151 1310 +/- 161 1280 +/- 141 1330 +/- 159 1210 +/- 139 1140 +/- 156 1430 +/- 134 1230 +/- 189 1200 +/- 127 1160 +/- 122 1210 +/- 107 1330 +/- 125 1170 +/- 123 1270 +/- 153 1330 +/- 146 1340 +/- 52 1460 +/- 141 1260 +/- 44 1280 +/- 52 1450 +/- 77 1400 +/- 158 1284 +/- 199 1090 +/- 120 1270 +/- 139 1300 +/- 158 1230 +/- 102
<5
<6
<7
<6
<6
<6
<7
<5
<8
<5
<9
<4
<4
<5
<5
<5
<2
<6
<2
<1
<2
<6
<5
<5
<7
<4
<3
<5
<5
<4
<6
<8
<7
<7
<6
<7
<7
<6
<9
<6
<9
<5
<5
<6
<7
<5
<2
<6
<2
<1
<2
<7
<5
<6
<7
<4
<4
<5
<5
<5
< 28
< 36
< 28
< 24
< 29
< 26
< 31
< 35
< 24
< 31
< 45
< 37
<51
< 35
< 41
< 40
< 44
< 40
< 40
< 54
< 40
< 34
< 27
< 22
< 39
< 44
< 19
< 12
< 27
< 45
<8
< 11
<7
<7
<8
<7
<8
<8
<7
< 12
< 14
< 13
< 14
< 13
< 12
<7
< 11
<8
< 12
<15
< 12
< 10
<7
<7
<9
< 12
<7
<6
<7
< 14 MEAN 1223 +/- 186 36E1 01/15/2008 04/01/2008 07/08/2008 10/14/2008 1200 1090 1250 1260
+/- 104
+/- 114
+/- 117
+/- 102 MEAN 1200 +/- 156
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-15
TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 11S3 06/25/2008
'06/25/2008 0612512008 07/24/2008 07/24/2008 07/2412008 08/25/2008 08/25/2008 08/2512008 09/15/2008 09/15/2008 09115/2008 10/21/2008 10/21/2008 MEAN Cabbage Collards Kale Cabbage Collards Kale Cabbage Collards Kale Cabbage Collards Kale Collards Kale Cabbage Collards Kale Cabbage Collards Kale Cabbage Collards Kale Cabbage Collards Kale Cabbage Collards Kale 304 +/- 185 245 +/- 210 217 +/- 113 170 +/- 70 254 +/- 70 234 +/- 54
< 139
< 163 279 +/- 113 140 +/- 67 199 +/- 68 196 +/- 72 209 +/- 77 167 +/- 65 3300 4830 4210 2490 2530 2660 2540 3390 3840 3160 3180 3360 4040 3790
+/- 444
+/- 536
+/- 373
+/- 151
+/- 152
+/- 134
+/- 275
+/- 348
+/- 330
+/- 167
+/- 151
+/- 197
+/- 175
+/- 164 218 +/- 96 13S3 06125/2008 06/25/2008 06/25/2008 07/24/2008 07/24/2008 07/24/2008 08/25/2008 08/25/2008 08/25/2008 09/15/2008 09/15/2008 09/15/2008 10/21/2008 10/21/2008 10/21/2008
< 250
< 195
< 108 104 +/- 62 724 +/- 90 253 +/- 100
< 100 319 +/- 110 234 +/- 129
< 67
< 85 109 +/- 55 207 +/- 107 119 +/- 116 90 +/- 67 3380 +/- 1408 5000 +/- 514 5540 +/- 420 4630 +/- 279 3020 +/- 162 7060 +/- 195 5070 +/- 172 1680 +/- 200 5370 +/- 332 4870 +/- 392 2270 +/- 131 3510 +/- 168 3320 +/- 133 4630 +/- 190 4010 +/- 177 4440 +/- 161
< 20
< 21
< 17
<6
<5
<5
< 15
<16
< 15
<8
<6
<9
<4
<3
< 23
< 20
<12
<6
<6
<5
< 12
< 16
- 19
<6
<7
<6
< 3
<3
<3
- 22
- 20
< 16
<7
<6
<6
< 15
< 17
< 17
<9
<7
< 11
<5
<5
- 24
- 21
< 11
<7
<7
<5
< 11
< 16
< 19
<7
<9
<7
<4
<4
<4
< 22
< 19
< 16
<6
<5
<5
< 16
< 14
< 18
<7
<6
<8.
<3
<3
- 56
< 57
<44
< 52
<54
< 50
< 36
< 45
< 45
< 54
< 47
< 59
< 59
< 58
< 59
< 54
< 24
< 53
< 58
<44
< 36
< 46
< 55
<48
< 55
< 47
< 59
< 57
< 59
< 21
- 19
< 13
<5
<5
<5
< 14
< 14
< 14
<7
<6
<7
<3
<3
< 23
< 18
< 11
<5
<5
<4
< 10
< 15
< 16
<6
<7
<6
<3
<3
<3
< 19
< 22
<19
<6
<5
<5
< 17
< 17
< 15
<8
<7
<9
<4
<3
< 21
- 21
< 12
<6
<6
<5
< 10
- 16
< 19
<6
<7
<6
<3
<3
<3
< 24
< 18
< 12
<5
<6
<4
< 10
< 15
< 15
<6
<8
<6 S<3
<3
<3 MEAN 240 +/- 397 4295 +/- 2738 C-16
TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD 31G1 06/25/2008 06/25/2008 06/25/2008 07/24/2008 07/24/2008 07/24/2008 08/25/2008 08/25/2008 08/25/2008 09/15/2008 09/15/2008 09/15/2008 10/21/2008 10/21/2008 Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 Brussel Sprout Leaves Cabbage Lettuce Brussel Sprout Leaves Cabbage Zucchini Leaves Broccoli Leaves Cabbage Squash Leaves Broccoli Leaves Cabbage Squash Leaves Broccoli Leaves Cabbage 167 +/- 108
< 139 286 +/- 125 521 +/- 95 673 +/- 89 1290 +/- 101
< 140
< 118 615 +/- 162 74 +/- 39
< 79 2060 +/- 79.
134 +/- 67
< 40 5640 +/-
4200 +/-
5630 +/-
5080 +/-
3950 +/-
5080 +/-
5160 +/-
4580 +/-
4910 +/-
3350 +/-
2400 +/-
5220 +/-
3980 +/-
2010 +/-
349 361 383 192 172 195 374 302 352 111 142 129 157 120
< 15
< 16
< 17
<7
<5
<5
< 15
< 12
< 14
<5
<7
<5
<3
<3
< 14
< 17
< 17
<8
<5
<5
< 17
< 12
< 15
<6
<8
<6
<4
<4
< 16
< 13
< 15
<6
<4
<4
< 15
< 12
< 15
<5
<7
<5
<3
<3
< 33
< 44
< 36
< 60
< 47
< 45
< 49
< 38
< 43
< 40
< 57
< 43
< 55
< 60
< 12
< 15
< 14
<6
<4
<4
< 13
< 11
<13
<5
<7
<5
<2
<3
< 14
< 14
< 16
<7
<5
<5
< 17
< 12
< 14
<5
<8
<5
<3
<4 MEAN 649 +/- 1296 4371 +/- 2269
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-17
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE
+/- 2 S. D.
2E1 8.3 +/- 1.1 9.1 + 1.1 7.9 +/- 1.6 7.9 +/- 0.5 8.4 + 0.5 3S1 7.9 +/- 1.8 8.7 +/- 0.6 6.6 +/- 0.1 7.9 +/- 0.8 8.3 +/- 0.6 4E1 6.4 +/- 1.3 7.2 + 0.7 5.8 +/- 0.4 5.9 +/- 0.4 6.6 +/- 0.4 5H1 9.2 +/- 1.1 9.5 +/- 0.9 8.7 +/- 0.7 8.8 + 0.4 9.9 + 1.3 5S1 8.7 +/- 1.5 9.3+/- 1.1 7.6 +/- 0.5 8.6 +/- 0.2 9.1 + 0.6 6C1 7.9 +/- 1.0 8.2 +/- 0.7 7.3 +/- 0.5 7.8 +/- 0.3 8.4 +/- 0.7 7E1 8.3 +/- 1.2 9.0. +/- 0.5 7.6 +/- 0.5 8.1 +/- 0.4 8.6 +/- 0.6 7S1 8.2 +/- 1.3 8.9 +/- 0.6 7.3 +/- 0.4 8.1 +/- 0.6 8.4 +/- 0.8 9C1 7.8 +/- 1.4 8.4 +/- 0.8 6.9 +/- 0.4 7.5 +/- 0.6 8.2 +/- 0.5 10E1 8.0 +/- 2.0 9.0 +/- 0.6 7.6 +/- 0.5 6.7 +/- 0.7 8.5 +/- 0.9 10F3 7.8 +/- 1.5 8.5 +/- 0.3 7.6 +/- 1.4 6.8 +/- 0.9 8.2 +/- 0.5 10S3 7.7 + 0.7 8.1 +/- 0.7 7.2 +/- 0.4 7.7 +/- 0.6 7.8 +/- 0.6 1iSi 9.0 + 1.3 9.4 +/- 1.1 8.0 +/- 0.5 9.3 +/- 0.6 9.1 +/- 0.7 13C1 6.1 +/- 0.9 6.5 +/- 0.4 5,9 +/- 0.7 5.5 +/- 0.2 6.4 +/- 0.7 13E1 7.8 +/- 1.6 8.8 +/- 0.6 7.3 +/- 0.5 7.0 +/- 1.2 8.0 +/- 0.5 13S2 11.9 +/- 1.9 12.6 +/- 1.2 10.5. +/- 0.6 11.9 +/- 0.7 12.5 +/- 1.4 14S1 7.3 + 1.5 8.0 +/- 0.5 6.2 +/- 0.6 7.4 +/- 1.3 7.5 +/- 0.7 15D1 8.1 +/- 0.7 8.5 +/- 0.5 7.8 +/- 1.1 7.8 +/- 0.4 8.1 +/- 0.7 16F1 8.2 +/- 1.0 8.8 +/- 0.4 7.6 +/- 0.6 8.2 +/- 0.3 8.2 +/- 0.4 1781 7.7 +/- 0.9 8.1 +/- 0.6 7.3 +/- 0.9 7.4 +/- 1.0 8.1 +/- 0.2 18S2 8.6 +/- 1.3 9.2 +/- 0.4 7.8 +/- 0.8 8.4 +/- 1.2 9.0 +/- 1.1 19D1 7.4 +/- 1.3 8.3 +/- 0.9 6.8 +/- 0.4 7.2 +/- 0.3 7.1 +/- 0.4 20D1 7.3 +/-1.1 7.9 +/- 0.2 6.8 +/- 0.3 6.9 +/- 0.4 7.6 +/- 0.6 20F1 7.7 +/- 1.2 8.5 +/- 0.8 7.2 +/- 0.3 7.2 +/- 0.6 7.8 +/- 1.3 21S2 7.2 + 1.4 7.9 +/- 0.4 6.4 +/- 0.2 6.9 +/- 0.3 7.6 +/- 0.4 23S2 7.3 +/- 1.6 8.2 +/- 0.5 6.5 +/- 0.7 6.7 +/- 0.2 7.6 +/- 0.5 24D1 7.0 +/- 1.2 7.7 +/- 0.8 6.3 +/- 1.1 6.8 +/- 0.4 7.1 +/- 0.4 25D1 6.8 +/- 1.7 8.0 +/- 1.1 6.1 +/- 0.5 6.3 +/- 0.6 6.6 +/- 0.5 25S2 7.2 +/- 1.5 8.2 +/-,0.5 6.4 +/- 1.0 7.1 +/- 0'6 7.0 +/- 0.7 26S3 7.0 +/- 1.1 7.4 +/- 0.3 6.2 +/- 0.4 6.9 +/- 0.4 7.3 +/- 0.5 28D2 7.3 +/- 1.4 8.3 +/- 0.7 6.9 +/- 0.4 6.7 +/- 0.3 7.3 +/- 0.4 29E1 7.6 +/- 1.4 8.4 +/- 0.7 6.9 +/- 0.6 7.0 +/- 0.5 7.9 +/- 0.6 29S1 7.1 +/- 1.4 8.1 +/- 0.9 6.6 +/- 0.6 6.7 +/- 0.5 6.9 +/- 0.4 31D1 9.0 +/- 0.8 9.6 +/- 0.2 8.7 +/- 0.6 8.8 +/- 1.1 8.8 +/- 0.3 31D2 8.0 +/- 0.5 8.1 +/- 0.8 7.7 +/- 1.2 7.8 +/- 0.4 8.2 +/- 0.7 31S1 8.0 +/- 1.1 8.7 +/- 1.4 7.5 +/- 0.8 7.6 +/- 0.8 8.0 +/- 0.4 34E1 7.6 +/- 0.7 7.9 +/- 0.9 7.1 +/- 0.8 7.5 +/- 0.5 7.8 +/- 0.8 34S2 8.2 +/- 1.1 8.9 +/- 1.1 7.6 +/- 1.0 7.9 +/- 0.3 8.4 +/- 1.1 36D1 7.1 +/- 1.7 8.3 +/- 1.7 6.5 +/- 0.5 6.5 +/- 0.7 7.0 + 0.6 36S2 7.9 +/- 1.5 8.8 +/- 0.4 7.0 +/- 0.8 7.8 +/- 0.6 8.0 +/- 0.8 C-18
TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD SITE BOUNDARY MIDDLE CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 8.8 +/- 2.3 7.2 +/- 2.1 7.9 +/- 2.6 8.3 +/- 2.6 8.3 +/- 1.3 7.1 +/- 1.4 7.2 +/- 1.5 7.8 +/- 1.4 9.5 +/- 0.0 8.7 +/- 0.0 8.8 +/- 0.0 9.9 +/- 0.0 TABLE C-IX.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES ANALYZED SITE BOUNDARY MIDDLE CONTROL 64 92 4
PERIOD PERIOD MINIMUM MAXIMUM 6.2 12.6 5.5 9.6 8.7 9.9 I
PERIOD MEAN
+/-2 S.D.
8.1 +/- 2.6 7.6 +/- 1.7 9.2 +/- 1.1 SITE BOUNDARY STATIONS - 10S3, 11S1, 13S2,14S1, 18S2, 21S2,23S2,25S2, 26S3, 29S1, 31S1 34S2, 36S2, 3S1, 5S1, 7S1 MIDDLE STATIONS - 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1, 28D2, 29E1, 2E1, 31D1, 31D2, 34E1, 36D1, 4E1, 6C1, 7E1, 9C1 CONTROL STATIONS - 5H1 C-19
FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2008 12 12 10 F--:k U
0.
6 4
-rn-CONTROL i
--A--INDICATOR 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YEAR LGS CRITICALITY UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING OF 2005. PREVIOUS DATA INCLUDED SUMMATION OF LESS THAN VALUES.
C - 20
FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 -2008 65 4 5 35 E
LGS CRITICALITY 2*
-UNIT NO. 1: 12122/84 U
Note: Second half of 2000 o
UNIT NO. 2: 08/11/89 switched to reporting < MDC 25 I
when no activity was detected.
Using MDC values result in a i/
larger number. LLD <150 pCi/kg.
15---------
5
-5 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 YEAR CONTROL =29C1 Station 20S1 discontinued in 1995 C -21
FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982-2008 1400 1200 1000 I
E 0) 0 0m 800 600 400 -16B2 I
a a
I I
S a
a a
a I
a I
I a
1614 a
LGS CRITICALITY a
a a,
UNIT NO. 1: 12/22/84 33A2 UNIT NO. 2: 08/11/89 I..
a a
a CONTROL 33A2 I I I
o o
I lo I
o o
i o
oI, ko 4o o
io ot ooo o
oi o oo ooe io ooo o
eoI I
o I o I o
I o 1 0 1 o
I I
1 0
'200 1
"*-.W I
I I
I I
I I
I I
I I
I I
I I
I I
I II 82 83 85 86 88 89 91 92 94 95 97 98 00 01 03 04 06 07 09 Year C - 22
FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2008 150 1.-
Group I 135
- Group 11 u
I I
-'- Group III 120------
I r u E 90 7
m 75ii, m
105 CL 60U IT NO 1: 1222 4
90 NO 2:
'08/..
75..............
82 8
86 88 90 9
4 9
9 0
2 0
6 0
I U
I O.2 0 1 1 8 I
S 0
4 5 -.....--
3 0 4
UNT O...
22.8 82 84 86 88 90 92 94 96 98 00 02 04 06 08 YEAR C-23
FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2008 50 40 E30 S20 cv 10 GROUP I
--=--GROUP II
- GROUP III 0
- .l. I. I.*
I I
l I,
..I...
I il
.I
. II
.I
. I.
. Il. I. I.
I.
....I i i.
i*
i I
- i i
i I
I 1 1 i i 1 1
- i I
I I
I I
.I
.......... 1 1 1 1
1 1
1 1
1 A-4.A I
I l
l I
I I
I I
I I
I I
I I
I i
I a
I.
I I
I.
1 1
1 1 1 1 1.
3 6
9 12 15 18 21 24 27 30 33 36 39 42 45 48 51 WEEK NO.
C - 24
FIGURE C-6 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (TLD)
IN THE VICINITY OF LGS, 1985 - 2008 13
-- K-SITE 2---- INTERMEDIATE 12
-u CONTROL 11
-c- --
Control 51-1 19 o- -
- 9, 8
Si.
i
':i 6
1 1
7 ~ ~
~
~
i i-K 7
6 5
° 4
85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 YEAR NOTE: Control Station 5H1 became the only distant location beginning in 1995 C - 25
Intentionally Left Blank C - 26
APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY
The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Environmental Incorporated (ENV). Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and ENV. Comparison of the results for most media were within expected ranges.
D-1
Intentionally Left Blank D-2
TABLE D-1.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/31/07 01/29/08 03/04/08 03/31/08 04/28/08 06/03/08 06/30/08 07/29/08 09/02/08 09/29/08 11/03/08 12/02/08 01/29/08 03/04/08 03/31/08 04/28/08 06/03/08 06/30/08 07/29/08 09/02/08 09/29/08 11/03/08 12/02/08 12/29/08 3.15 2.69 0.87 1.25 0.92 1.25 2.51 2.07 1.98 2.24 3.88 3.41
+ 1.1
+ 1.1
+ 0.5
+ 0.6
+/- 0.5
+/- 0.4
+/- 1.0
+/- 0.6
+/- 0.6
+/- 0.7
+ 1.2
+ 1.1 MEAN 0.8 +/- 0.6 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/31/07 03/31/08 06/30/08 09/29/08 16C2 03/31/08 06/30/08 09/29/08 12/29/08
< 180
< 149
< 145
< 173 MEAN D-3
TABLE D-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC Co 16C2 12/31/07 01/29/08 03/04/08 03/31/08 04/28/08 06/03/08 06/30/08 07/29/08 09/02/08 09/29/08 11/03/08 12/02/08 LLECTION PERIOD 01/29.
03/04 03/31 04/28 06/03 06/30.
07/29 09/02.
09/29.
11/03.
12/02.
12/29 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140
/08
/08
/08
/08
/08
/08
/08
/08
/08
/08
/08
/08
<3
<3
<5
<4
<7
<3
<3
<2
<4
<2
<2
<2
<2
<3
<3
<2
<4
<3
<2
<1
<3
<3
<3
<3
<5
<3
< 12
<9
<7
<7
<3
<4
<9
<6
<4
<7
<2
<3
<5
<3
<3
<3
<3
<2
<2
<2
<4
<2
<7
<6
<7
<4
<8
<6
<5
<4
<5
<5
<4
<6
<4
<6
< 11
<8
<8
<5
<8
<3
<6
< 6
<5
<5
<4
<3
<4
<3
<4
<3
<3
<3
<4
<3
<2
<3
<4
<5
<7
<5
<5
< 12
<6
<6
< 10
< 12
<4
<8
<2
<3
<5
<2
<3
<4
<3
<2
<5
<5
<3
<3
<3
<3
<5
<3
<4
<3
<3
<2
<4
<3
<3
<3
< 11
< 16
< 13
< 13
< 11
< 21
< 19
- 17
< 14
< 18
< 16
< 11
<2
<3
<5
<5
<5
<6
<4
<3
<3
<4
<2
<4 MEAN D-4
TABLE D-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION 11 S2 PERIOD 12/31/07 01107108 35b +/- 5 01/07/08 01/14/08 17 +/- 4 01/14/08 01/22/07 28 +/- 4 01/22/07 01/28/08 33 +/-6 01/28/08 02/04/08 36 +/-4 02/04/08 02/11/08 23 +/-4 02/11/08 02/19/08 24 +/-4 02/19/08 02/25/08 24 +/-5 02/25/08 03/03/08 21
+/- 4 03/03/08 03/10/08 16 +/- 4 03/10/08 03/17/08 27 +/- 5 03/17/08 03/24/08 21
+/- 4 03/24/08 03/31/08 21
+/- 4 03/31/08 04/07/08 21
+/- 4 04/07/08 04/14/08 12 +/- 4 04/14/08 04/21/08 26 +/- 5 04/21/08 04/28/08 16 +/- 4 04/28/08 05/05/08 26
+/- 4 05/05/08 05/12/08 18 +/- 5 05/12/08 05/20/08 17 +/- 4 05/20/08 05/27/08 13
+/- 4 05/27/08 06/02/08 17 +/- 5 06/02/08 06/09/08 14 +/- 4 06/09/08 06/1 6/08 20 +/- 5 06/16/08 06/23/08 16 +/- 4 06/23/08 06/30/08 21
+/- 4 06/30/08 07/07/08 25 +/- 4 07/07/08 07/14/08 22 +/- 4 07/14/08 07/21/08 30 +/- 4 07/21/08 07/28/08 25 +/- 4 07/28/08 08/04/08 30 +/- 4 08/04/08 08/11/08 22 +/- 4 08/11/08 08/18/08 21
+/- 4 08/18/08 08/25/08 24
+/- 4 08/25/08 09/01/08 21
+/- 4 09/01/08 09/09/08 30 +/- 4 09/09/08 09/15/08 17
+/- 4 09/15/08 0 9/22/08 25 +/- 4 09/22/08 09/29/08 17
+/- 4 09/29/08 10/07/08 24 +/- 4 10/07/08 10/13/08 31
+/- 5 10/13/08 10/20/08 29 +/- 4 10/20/08 10/27/08 14 +/- 4 10/27/08 11/04/08 19 +/- 4 11/04/08 11/10/08 18 +/- 4 11/10/08 11/17/08 15 +/- 4 11/17/08 11/24/08 15 +/- 4 11/24/08 12/01/08 24 +/- 4 12/01/08 12/08/08 21
+/- 4 12/08/08 12/15/08 16 +/- 4 12/15/08 12/22/08 24 +/- 4 12/22/08 12/29/08 37 +/- 5 MEAN 22 +/- 12 D-5
TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF E-3 PCI/CU METER + 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137' PERIOD 11S2 12/31/07 -
03/31/08 83 +/- 15
< 0.7
< 0.5
< 0.9
< 0.5
< 0.4 03/31/08 -
06/30/08 83 +/- 15
< 0.6
< 0.5
< 0.8
< 0.8
< 0.7 06/30/08 -
09/29/08 153 +/- 20
< 1.0
< 1.1
< 0.8
< 0.7
< 0.8 09/29/08 -
12/29/08 65 +/- 15
< 0.7
< 0.5
< 1
< 0.7
< 0.5 MEAN 96 +/- 78 D-6
TABLE D-I11.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY.OF LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 1981 1/15/008 04/01/08 07/08/08 10/14/08 MEAN 10F4 1/15/008 04/01/08 07/08/08 10/14/08
< 7.8
< 6.6
< 6.2
< 6.4
< 5.7
- 6.5
<5
< 7.7
< 7.8
< 8.5
<5.1
< 9.6 1287 1303 1431 1407 1357 +/- 145
+/- 104
+/- 115
+/- 106
+/- 113 1350 1447 1360 1300
+/- 95
+/- 122
+/- 115
+/- 124
<3
<4
<3
<5
<4
<5
<3
<3
<4
<4
<4
<5
<3
<4
<3
<4
<3
<4
<3
<4
<2
<3
<3
<4 10 18 13 17 11 20 14 23 11 15 16 21
<7
<3
<3
<4
<2
<2
<3
<5
<3
<3
<3
<3 MEAN 1364 +/- 122 25C1 1/15/008 04/01/08 07/08/08 10/14/08 1262 1348 1331 1462
+/- 82
+/- 127
+/- 102
+/- 113 MEAN 1351 +/- 166 D-7
FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2008 10 9
-- ENV 8
.TBE 7
5
.T..... k.................
0 I
I I
I I
I I
I I
I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH D-8
FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2008 50
-a--11S2-ENV
-- S1 -TBE 40 C) 0)
i 4".
i
,4
~2 ----------------------
\\-
I I i l
', " 'A ", ",'=
d
'=,',,, * l l,' 4,;,,
1 4
7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO.
D-9
Intentionally Left Blank D-IO
APPENDIX E INTER-LABORATORY COMPARISON PROGRAM
TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b)
TBE/Analytics Evaluation(d)
March 2008 E5847-396 Milk Sr-89 pCi/L 83.5 95.8 0.87 A
Sr-90 pCi/L 13.9 12.9 1.08 A
E5848-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 57.3 229 336 106 141 71.8 98.1 102 135 230 163 233 72.6 98.3 46.7 69.8 72.2 106 156 60.0 249 359 125 146 70.8 94.2 102 137 236 157 227 79.0 92.0 44.7 59.4 64.5 86.4 149 E5850A-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi 0.96 0.92 0.94 0.85 0.97 1.01 1.04 1.00 0.99 0.97 1.04 1.03 0.92 1.07 1.04 1.18 1.12 1.23 1.05 1.09 0.99 0.91 0.99 0.90 1.15 0.91 0.99 0.95 1.03 1.07 1.02 0.97 A
A A
A A
A A
A A
A A
A A
A A
A A
W A
A A
A A
A A
A A
A A
A A
A June 2008 E5849-396 Charcoal 1-131 E5971-396 Milk Sr-89 Sr-90 E5972-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi 65.5 pCi/L 83.9 pCi/L 14.4 60.1 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 70.9 157 159 69.7 115 59.1 139 98.4 129 101 85.0 15.8 71.4 174 138 76.7 116 61.9 135 91.7 127 104 E-1
TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a) Value (b)
TBE/Analytics Evaluation (d)
June 2008 E5974-396 AP Ce-141 oCi 206 207 1.00 A
Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi 173 95.9 142.0 72.0 180 108.0 159 129 164 91.0 138.0 73.4 160.0 109.0 150 124 1.05 1.05 1.03 0.98 1.13 0.99 1.06 1.04 A
A A
A A
A A
A June 2008 E5973-396 Charcoal 1-131 pCi 73.8 pCi/L 76.2 pCi/L 12.3 September 2008 E6284-396 Milk Sr-89 Sr-90 E6285-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E6287-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E6286-396 Charcoal 1-131 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 65.7 145 406 196 147 167 165 161 305 218 79.5 208 106 79.3 87.7 90.3 81.7 144 111 84.1 73.9 11.0 67.9 161 421 232 162 179 166 144 319 234 76.3 199 110 76.7 84.4 78.6 68.3 151 111 0.88 1.03 1.12 0.97 0.90 0.96 0.84 0.91 0.93 0.99 1.12 0.96 0.93 1.04 1.05 0.96 1.03 1.04 1.15 1.20 0.95 1.00 1.04 1.07 1.43 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
pCi 93.2 90.0 December 2008 E6415-396 Milk Sr-89 Sr-90 pCi/L 98.4 pCi/L 18.0 91.9 12.6 A
N (i)
E-2
TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY'CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 3 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value(a)
Value (b) TBE/Analytics Evaluation (d)
December 2008 ' E6416-396 Milk 1-131 DCi/L 69.2 79.9 0.87 A
Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 177 231 117 119 104 153 99.6 177 133 191 246 134 120 104 152 100 183 133 0.93 0.94 0.87 0.99 1.00 1.01 1.00 0.97 1.00 1.01 1.08 1.01 1.05 1.03 0.97 1.00 0.88 1.07 A
A A
A A
A A
A A
A A
A A
A A
A A
A E6418-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 148 202 103 95.4 81.4 113 76.5 122 108 65.8 146 187 102 91.2 79.2 116.0 76.4 139 101 December 2008 E6417-396 Charcoal 1-131 74.1 0.89 A
(1)
(a)
(b)
(c)
(d)
NCR 09-02 initiated to investigate the failure.
Teledyne Brown Engineering reported result.
The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
Ratio of Teledyne Brown Engineering to Analytics results.
Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.
W-Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30. N =Not Acceptable. Reported result falls outside the ratio limits of < 0.70 and > 1.30.
E-3
TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 1)
Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b)
Control Limits Evaluation (c)
January 2008 January 2008 April 2008 Quiktm Respon, Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B H-3 RAD 72 Rad 73 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCilL pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 37.33 40.40 87.8 80.67 222.33 98.9 352 13.0 32.7 11100 69.0 35.6 25.9 86.5 155 16.0 214 13.3 21.2 22.8 3390 65.47 39.80 59.63 45.00 97.97 75.47 109 41.03 50.20 26.67 11633 19.0 42.7 90.5 88.9 231 101.0 350 12.7 36.2 11300 65.3 41.4 25.7 92.6 158 14.4 204 14.8 22.5 23.6 3540 60.4 39.2 58.3 46.6 102 76.6 106 50.8 51.4 28.7 12000 11.8-25.2 31.5-49.0 76.2 - 99.6 72.9 - 97.8 208 - 256 90.9-113 315-408 6.02-18.7 23.8 - 43.8 9840- 12400 53.0 - 73.4 30.5 - 47.6 20.0 - 29.5 76.0- 102 142-176 11.4-18.7 184-240 7.15-21.2 13.7 - 30.6 19.6 - 28.0 3000- 3910 48.6 - 68.2 28.8-45.1 48.3 - 64.3 37.4 - 51.3 91.8-115 68.9 - 86.7 95.4-126 26.5 - 63.7 35.0 - 58.4 23.9 - 33.6 10400 - 13200 N (1)
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A (1) Could find no cause for Sr-89 failure. Sample sent to outside lab for verification, but the outside laboratory was unable to confirm our numbers or ERA numbers. Studies bracketing these results, RAD 71 and RAD 72, had acceptable Sr-89 results. NCR 08-03 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
E-4
TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2008 (PAGE 1 OF 2)
Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b)
Range Evaluation (c)
January 2008 07-MaW 18 Water Cs-134 Bq/L
-0.26 (1)
A Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 0.029 21 8.2 473 12 10.70 15.6 22.8 8.40 472 12.1 11.4 16.3 (1) 16.0-29.6 5.88-10.92 330-614 8.5-15.7 7.98-14.82 11.4-21.2 A
A A
A A
A A
07-GrW18 Water Gr-A Gr-B Bq/L 1.4 1.399
>0.0 - 2.798 Bq/L 3.06 2.43 1.22 - 3.65 07-MaS18 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bqfkg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 790 568 424 2.307 611 6.09 454 0.162 2.73 2.88 3.493 1.357 0.006 1.61 2.59 854.0 545 421 2.9 570 571 493.0 598-1110 382-709 295-547 (2) 399-741 400-742 345-641 (1) 07-RdF18 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 2.5200 1.76-3.28 2.7 1.89-3.51 3.55 2.49 - 4.62 1.31 0.92-1.70 (1) 1.548 1.084 - 2.012 2.04 1.43 - 2.65 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A 07-GrF18 AP Gr-A Bq/sample 0.131 0.348
>0.0 - 0.696 Gr-B Bq/sample 0.261 0.286 0.143 - 0.429 January 2008 07-RdV1 8 Vegetatior Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 5.25 3.13 6.837 2.44 4.45 61.3 1.33 0.085 6.28 3.41 6.89 2.77 4.74 4.40-8.16 2.39 - 4.43 4.82 - 8.96 1.94-3.60 3.32-6.16 (1) 1.273 0.891 - 1.655 (1)
E-5
TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2008 (PAGE 2 OF 2)
Month/Year August 2008 Identification Number 08-MaW19 Media Nuclide Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Units Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Reported Value (a) 17.1 21.4
-0.044 10.8 334 13.0 6.55 16.5 Known Value (b) 19.5 23.6 11.6 341 13.7 6.45 17.1 Acceptance Range 13.7-25.4 16.5-30.7 (1) 8.1 - 15.1 239 - 443 9.6 - 17.8 4.52-8.39 12.0-22.2 Evaluation (c)
A A
A A
A A
A A
August 2008 08-GrW19 Water Gr-A Gr-B Bq/L 0.0612
<0.56 Bq/L 0.222
<1.85 (3)
(3) 08-MaS19 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 546 2.52 340 157 460 650 1.40
-1.53 2.46 0.0063 1.36 0.0143 2.70 1.42 0.975 581 2.8 333 145.0 415 571 407 - 755 (2) 233 - 433 102-189 291 - 540 399 - 741 (1)
(1) 08-RdF19 AP Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 2.6300 1.84 - 3.42 (1) 1.50 1.05-1.95 (1) 2.64 1.85-3.43 1.12 0.78-1.46 0.94 0.66-1.22 (4) 0.525 0.263 - 0.788 A
A A
A A
A A
A A
A A
A A
A A
W A
A A
W A
A A
A A
A 08-GrF19 AP Gr-A Bq/sample -0.0037 Gr-B Bq/sample 0.540 08-RdV19 Vegetatior Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 4.36
-0.03 6.72 4.04 5.22 64.4 1.62 6.160 5.5 7.1 4.70 5.8 1.9 6.9 3.9 - 7.2 (1) 5.0 - 9.2 3.3-6.1 4.1 -7.5 (1) 1.3-2.5 4.8-9.0 (1) Not evaluated by MAPEP.
(2) Reported a statistically zero result.
(3) Designed to test the Safe Drinking Water screening levels. Labs reporting values less than ref values were found to be acceptable.
(4) False positive test.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.
E-6
TABLE E-4 ERA (a) STATISTICAL
SUMMARY
PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2008 (Page 1 of 1)
Concentration (pCi/L)
Lab Code D Date Analysis STAP-1 143 STAP-1143 STAP-1 143 STAP-1 143 e STAP-1 143 STAP-1 143 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 STAP-1 144 03/24/08 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1 145 STSO-1145 STSO-1145 STSO-1 145 STSO-1145 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 STVE-1 146 STW-1 147 STW-1 147 STW-1 147 STW-1 147 e STW-1 147 STW-1 147 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 e 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 6 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 03/24/08 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 Gr. Beta Ac-228 Bi-212 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Pb-212 Pb-214 Sr-90 Th-234 Zn-65 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 Laboratory Result c 650.72 +/- 3.00 467.50 +/- 5.53 1375.90 +/- 25.41 0.00 +/- 0.00 157.60 +/- 7.70 889.90 +/- 15.90 ERA Result c 730.0 523.0 1450.0 0.0 152.0 872.0 Control Limits 565.0 341.0 1090.0 0.0 66.9 604.0
- 912.0
- 647.0
- 1900.0
- 10.0
- 236.0
- 1210.0 99.90 +/- 3.09 AcceItance 92.2 56.80 - 135.0 1269.02 +/- 36.81 1407.10 +/- 56.64 5219.70 +/- 90.30 5427.30 +/- 102.94 6346.60 +/- 201.80 11052.70 +/- 181.80 0.00 +/- 0.00 1198.20 +/- 96.58 2253.30 +/- 291.60 6407.00 +/- 277.00 2421.80 +/- 321.00 2936.20 +/- 73.50 912.41 +/- 13.59 1547.70 +/- 38.81 1163.80 +/- 20.62 22186.00 +/- 339.40 0.00 +/- 0.00 3825.90 +/- 140.66 1676.80 +/- 43.00 1430.00 +/- 33.33 730.18 +/- 33.39 1947.80 +/- 13.80 0.00 +/- 0.00 512.03 +/- 43.37 708.90 +/- 29.00 2009.00 +/- 36.40 1180.0 1360.0 5130.0 5640.0 6010.0 11000.0 0.0 1080.0 2020.0 5360.0 2030.0 2660.0 888.0 1540.0 1100.0 24600.0 0.0 4130.0 1430.0 1420.0 751.0 1990.0 0.0 512.0 694.0 757.0 357.0 3730.0 3630.0 4600.0 7980.0 0.0 697.0 1210.0 1940.0 644.0 2110.0 600.0 882.0 807.0 17700.0 0.0 2310.0 1030.0 1240.0
. 555.0 1690.0 0.0 325.0 588.0
-1660.0
-2030.0
-6890.0
-6790.0
-7810.0
-14900.0
-10.0
-1520.0
-3010.0
-8750.0
-3870.0
-3570.0
-1280.0
-2130.0
-1530.0
-34800.0
-10.0
-5480.0
-1960.0
-1680.0
-862.0
-2380.0
- 10.0
- 684.0
- 865.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1120 03/19/07 Zn-65 1910.0 1600.0 - 2410.0 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
e Included in the testing series as a "false positive". No activity expected.
E-7
TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2008 (Page 1 of 2)
Concentration D Lab Codec STW-1137 STW-1137 STW-1137 STW-1 137 STW-1 137 STW-1137 STW-1 137 STW-1137 Date 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 01/01/08 Analysis Co-57 Co-60 Cs-134 Cs-137 H-3 Mn-54 Sr-90 Zn-65 Laboratory result 23.80 +/- 0.60 8.60 +/- 0.50
-0.021 +/- 0.10 0.00 +/- 0.10 515.10 +/- 12.70 12.90 +/- 0.80 12.00 +/- 1.50 16.90 +/- 1.40 Known Activity 22.80 8.40 0.00 0.00 472.00 12.10 11.40 16.30 Control Limits d 16.00 - 29.60 5.88 - 10.92
-1.00-1.00
-1.00-1.00 330.00 - 614.00 8.50 - 15.70 7.98 - 14.82 11.40 - 21.20 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass STW-1138 01/01/08 STAP-1139 '01/01/08 STAP-1139 01/01/08 STAP-1 139 01/01/08 STAP-1139 01/01/08 STAP-1139 01/01/08 STAP-1139 01/01/08 STAP-1 139 01/01/08 Gr. Beta Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Sr-90 Zn-65 2.30 +/- 0.15 3.90 +/- 0.07 1.43 +/- 0.07 2.59 +/- 0.16 3.05 +/- 0.12 0.43 +/- 0.58 1.30 +/- 0.27 2.36 +/- 0.18 0.34 +/- 0.04 2.43 3.55 1.31 2.52 2.70 0.00 1.55 2.04 0.29 6.89 2.77 6.28 3.41 4.74 0.00 1.22 - 3.65 2.49 - 4.62 0.92-1.70 1.76 - 3.28 1.89 -3.51 0.00 - 1.00 1.08 -2.01 1.43 -2.65 0.14 -0.43 4.82 - 8.96 1.94 -3.60 4.40 -8.16 2.39 - 4.43 3.32 -6.16 0.00 - 1.00 STAP-1 140 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STVE-1 141 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 142 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 STSO-1 158 01/01/08 Gr. Beta 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 01/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 8.30 3.03 6.53 3.90 5.43 0.033
+/- 0.18
+/- 0.13
+/- 0.29
+/- 0.19
+/- 0.21
+/- 0.10 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 483.00 +/- 3.00 3.00 +/- 0.80 896.50 +/- 7.40 624.40 +/- 4.10 667.20 +/- 3.80 0.093 +/- 0.91 353.02 +/- 2.01 151.99 +/- 1.58 499.72 +/- 2.65 2.54 +/- 0.25 643.94 +/- 15.50 452.14 +/- 2.96 1.95 +/- 2.04 0.10 +/- 2.04 421.00 2.90 854.00 545.00 570.00 0.00 333.00 145.00 581.00 2.80 570.00 415.00 0.00 0.00 295.00 - 547.00 0.00 -5.00 598.00 - 1110.00 382.00 - 709.00 399.00 - 741.00 0.00 -1.00 233.00 - 433.00 102.00 - 189.00 407.00 - 755.00 0.00 -5.00 399.00 - 741.00 291.00 - 540.00 0.00 -5.00 0.00 -5.00 E-8
TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2008 (Page 2 of 2)
Concentration Known Control Lab Codec Date Analysis Laboratory result -
Activity Limits d Acceptance STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STVE-1 159 STW-1 162 STW-1162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 STW-1 162 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 08/01/08 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 H-3 Mn-54 Sr-90 Zn-65 8.52 +/- 0.23 5.08 +/- 0.19 5.26 +/- 0.18 0.01 +/- 0.14 6.39 +/- 0.28 7.73 +/- 0.45 0.03 +/- 0.16 11.27 +/- 0.23 17.93 +/- 0.52 23.72 +/- 0.43 385.15 +/- 8.93 13.87 +/- 0.37 6.49 +/- 1.12 17.64 +/- 0.61 0.12 +/- 0.05 7.10 4.70 5.50 0.00 5.80 6.90 5.00 - 9.20 3.30 -6.10 3.90 - 7.20 0.00 - 1.00 4.10 - 7.50 4.80 - 9.00 Pass Pass Pass Pass Pass Pass 0.00 11.60 19.50 23.60 341.00 13.70 6.45 17.10 0.00 0.00 - 5.00 8.10 - 15.10 13.70 - 25.40 16.50 - 30.70 239.00 - 443.00 9.60 - 17.80 4.52 - 8.39 12.00 - 22.20 0.00 - 1.85 Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1163 08/01/08 Gr. Beta a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation),
Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
E-9
Intentionally Left Blank E - 10
APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)
Docket No:
50 - 352 50 - 353 LIMERICK GENERATING STATION UNITS I and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2008 Prepared By Teledyne Brown Engineering Environmental Services Exelin Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2009
Table Of Contents~
- 1. Summary and Conclusions.....................................................................
I
- 11. Introduction......................................................................................
2 A. Objectives of the RGPP...............................................................
2 B. Implementation of the Objectives..................................................... 2 C. Program Description...................................................................
3 D. Characteristics of Tritium (H-3)....................................................... 4 111. Program Description...........................................................................
4 A. Sample Analysis.......................................................................
4 B. Data Interpretation.....................................................................
5 C. Background Analysis..................................................................
6
- 1. Background Concentrations of Tritium.......................................
6 IV. Results and Discussion.......................................................................
8 A. Groundwater Results..................................................................
8 B. Surface Water Results.................................................................
9 C. Drinking Water Well Survey................................................
I......... 9 D. Summary of Results - Inter-laboratory Comparison Program.................... 10 E. Leaks, Spills, and Releases.........................................................
10 F. Trends.................................................................................
10 G. Investigations.........................................................................
10 H. Actions Taken..............................I...........................................
10 V. References.....................................................................................
11
Appendices Appendix A Tables Table A-1 Location Designation Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2008 Figures Figure 1 Appendix B Tables Table B-1.1 Table B-1.2 Table B-II.1 Table B-11.2 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2008 Data Tables Concentrations of Tritium and Stronium-90 in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2008.
Concentrations of Tritium and Stronium-90 in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2008.
Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2008.
ii
I.
Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2008 through 31 December 2008. During that time period, 103 analyses were performed on 58 samples from 21 groundwater and surface water locations collected from the environment, both on and off station property in 2008.
There was one known release into the groundwater at Limerick Generating Station that occurred from a cooling tower overflow while a Radwaste discharge was in progress. The discharge was secured and no radioactivity was found in the water sample obtained.
Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater or surface water samples.
Strontium-90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater or surface water samples tested.
Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 5 of 15 groundwater monitoring locations and I of 6 surface water monitoring locations. The tritium concentrations ranged from 208 to 902 pCi/L. Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.053 mrem to a child (total body), which was 0.89% of the 10 CFR 50, Appendix I dose limit.
In assessing all the data gathered for this report, it was concluded that the operation of Limerick Generating Station had no adverse radiological impact on the environment offsite of LGS.
1
II.
Introduction The Limerick Generating Station (LGS), consisting of two 3458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. I went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL.
This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2008.
In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of Limerick Generating Station. This evaluation involved numerous station personnel and contractor support personnel.
A.
Objective of the RGPP The long-term objectives of the RGPP are as follows:
- 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
- 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.
- 3. Perform routine water sampling and radiological analysis of water from selected locations.
- 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
- 5. Regularly assess analytical results to identify adverse trends.
- 6. Take necessary corrective actions to protect groundwater resources.
B.
Implementation of the Objectives The objectives identified have been implemented at Limerick Generating Station as discussed below:
- 1.
Exelon and its consultant identified locations as described in the 2006 Phase 1 study. The Phase 1 study results and conclusions 2
were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.
www.exeloncorp.com/ourcompanies/powerqen/nuclear/Tritium.htm
- 2.
The Limerick Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
- 3.
Limerick Generating Station will continue to perform routine sampling and radiological analysis of water from selected locations.
- 4.
Limerick Generating Station has implemented new procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
- 5.
Limerick Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.
C.
Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, lnc.(NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2008. Sample locations can be found in Table A-I, Appendix A.
- 1.
Sample Collection Groundwater and Surface Water Samples of water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Both groundwater and surface water were collected.
Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits.
Station personnel reviewed and evaluated.all analytical data deliverables as data were received.
3
Both station personnel and an independent hydrogeologist reviewed analytical data results for adverse trends or changes to hydrogeologic conditions.
D.
Characteristics of Tritium (H-3)
Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.
Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.
Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium.
Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.
Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.
Ill.
Program Description A.
Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick 4
Generating Station RGIPP in 2008.
In order to achieve the stated objectives, the current program includes the following analyses:
- 1.
Concentrations of gamma emitters in groundwater and surface water.
- 2.
Concentrations of strontium in groundwater and surface water.
- 3.
Concentrations of tritium in groundwater and surface water.
B.
Data Interpretation The radiological data collected prior to Limerick Generating Station becoming operational were used as a baseline with which these operational data were compared. For the purpose of this report, Limerick Generating Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:
- 1.
Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required LGS detection capabilities for environmental sample analysis.
The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.
- 2.
Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.
Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the 5
uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.
Exelon reports the TPU by following the result with plus or minus +
the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.
Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.
C.
Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface Water, aquatic life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
The pre-operational REMP contained analytical results from samples collected from both surface water and groundwater.
Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes. During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and are radioactively decaying as predicted.
Gamma isotopic results from the preoperational program were all less than or at the minimum detectable concentration (MDC) level.
- 1.
Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.
- a.
Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper 6
atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
- b.
Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected world wide since 1960. RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time.
Tritium concentrations in have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.
7
- c.
Surface Water Data Tritium concentrations are routinely measured in the Schuylkill and Delaware Rivers. Pennsylvania surface water data are typically less than 100 pCi/L.
The USEPA RadNet surface water data typically has a reported 'Combined Standard Uncertainty' of 35 to 50 pCi/L.
According to USEPA, this corresponds to a +/-70 to 100 pCi/L 95% confidence bound on each given measurement.
Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.
The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 -
240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.
IV.
Results and Discussion Gamma spectroscopy results for groundwater and surface water sample were reported for twelve nuclides (Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, I-131, Cs-134, Cs-137, Ba-140 and La-140).
A.
Groundwater Results Samples were collected from onsite wells throughout the year in accordance with the station radiological groundwater protection program.
Analytical results and anomalies are discussed below.
Tritium Samples from fifteen locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium values ranged from non detectable to 902 pCi/L.
Well MW-LR-5 had the highest value of 902 pCi/L. Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.053 mrem to a child (total body), which was 0.889% of the 10 CFR 50, Appendix I dose limit.
Strontium No Sr-90 activity was detected in any of the ground water samples analyzed (Table B-1.1, Appendix B).
8
Gamma Emitters No gamma emitting nuclides were detected (Table B-1.2, Appendix B).
B.
Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.
Tritium Samples from six locations were analyzed for tritium activity Tritium activity was detected in station SW-LR-6 at a concentration of 208 pCi/Liter (Table B-1.3, Appendix B).
Strontium No Sr-90 activity was detected in any of surface water samples analyzed (Table B-1.3, Appendix B).
Gamma Emitters Potassium-40 was detected in two of six samples. Potassium-40 values ranged from 54 pCi/Liter to 69 pCi/Liter. No other gamma emitting nuclides were detected (Table B-1.4, Appendix B).
C.
Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CRA 2006) around the Limerick Generating Station. CRA reviewed the Pennsylvania Groundwater Information System database to identify wells within a 1-mile radius from the center of the Station. Forty-six domestic withdrawal wells, two industrial wells, two commercial wells, and one institutional well were identified within the specified radius. The well depths range from 78 to 345 feet blow ground surface (bgs), and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.
The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 9
175 feet east of the Reactor Building. The Station estimates that the well is pumped at approximately 2 gpm. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.
D.
Summary of Results, - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report.
E.
Leaks, Spills, and Releases There was one known release into the groundwater at Limerick Generating Station that occurred from a cooling tower overflow on March 20, 2008, while a Radwaste discharge was in progress (IR752414). The discharge was secured and no radioactivity was found in the water sample obtained; however tritium was identified in a nearby well. as part of the RGPP.
F.
Trends No trends have been identified.
G.
Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going.
H.
Actions Taken
- 1. Compensatory Actions
-There have been no station events requiring compensatory actions at the Limerick Generating Station.
- 2. Installation of Monitoring Wells No new wells have been installed in 2007
- 3. Actions to Recover/Reverse Plumes No actions were required to recover or reverse groundwater plumes.
10
V.
References
- 1. Conestoga Rovers and Associates, Fleetwide Assessment, Limerick Generating Station, Sanatoga, Pennsylvania, Ref. No. 045136(17), September 2006
- 2. Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.
11
Intentionally Left Blank 12
APPENDIX A LOCATION DESIGNATION
TABLE A-1:
Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2008 Location MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 P1l P14 P16 P17 P3 SP22 Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Distance Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 SW-LR-9 Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Offsite Offsite Offsite Onsite Onsite Onsite A -I
/
I Mile Radius
-I NNW MW-I T O NNE NE f*,.LRA*
- WNW, 5~22 (4
ENE "N
ft-OS>
-\\.,19 R E I-L R-20
~bLR-6S /
.12 WSW
~SE
/
/
I X
./I; SSE.
.4,,;.
SW 7
<-A SSW 0
500 1,000 1,500 2,000 Feet S
Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2008 A-2
APPENDIX B DATA TABLES
TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-LR-1 MW-LR-1 MW-LR-2 MW-LR-2 MW-LR-3 MW-LR-3 MW-LR-4 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-6 MW-LR-6 MW-LR-7 MW-LR-7 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-9 MW-LR-9 MW-LR-9 P3 P3 P11 P11 P11 P11 P14 P14 P16 P16 P17 P17 SP22 SP22 COLLECTION DATE 04/29/08 10/08/08 04/30/08 10/09/08 04/30/08 10/09/08 04/30/08 10/08/08 ORIGINAL 04/28/08 RERUN 04/28/08 ORIGINAL 04/29/08 RERUN 04/29/08 ORIGINAL 07/21/08 RERUN 07/21/08 DUPLICATE 07/21/08 ORIGINAL 08/18/08 RERUN 08/18/08 ORIGINAL 09/17/08 RERUN 09/17/08 ORIGINAL 10/09/08 DUPLICATE 10/09/08 04/30/08 10/09/08 04/30/08 10/09/08 ORIGINAL 04/29/08 RERUN 04/29/08 10/08/08 04/28/08 04/29/08 10/08/08 04/29/08 10/09/08 ORIGINAL 04/29/08 RERUN 04/29/08 ORIGINAL 10/08/08 DUPLICATE 10/08/08 04/29/08 10/08/08 04/30/08 10/09/08 04/29/08 10/08/08 04/29/08 10/08/08 H-3 SR-90
< 186
< 143
< 187
< 146
< 187
< 138
< 190
< 143 902 +/- 180 832 +/- 171 806 +/- 171 791 +/- 166
< 196 275 +/- 110 366 +/- 138 420 +/- 133 425 +/- 136 375 +/- 106 432 +/- 106 167 +/- 93.6
< 147
< 190
< 140
< 187
< 144 241 +/- 124 230 +/- 131 218 +/- 97
< 186
< 186 240 +/-. 108
< 188
< 139 256 +/- 125 222 +/- 130 185 +/- 94 197 +/- 103
< 187 212 +/- 98
< 189
< 139
< 184
< 136
< 186
< 150
< 1.0
< 0.9
< 1.1
< 1.0
< 1.3
< 0.9
< 0.9
< 0.8
< 0.7
< 0.9
< 0.7
<0.9
< 1.6
< 0.8
< 1.3
< 0.9 Samples are distilled for H-3 analysis B-1
TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 P1l Pl1 P14 P-16 P17 P3 SP22 COLLECTION PERIOD 10/08/08 10/09/08 10/09/08 10/08/08 07/21/08 10/09/08 10/09/08 10/09/08 10/09/08 10/08/08 10/08/08 10/08/08 10/08/08 10/08/08 10/08/08 (1) 10/08/08 10/09/08 10/08/08 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 32
< 34
< 26
< 34
< 52
< 35
< 27
< 30
< 33
< 39
< 34
<41
< 34
< 26
< 23
< 28
< 59
< 63
<54
< 32
< 25
< 70
< 28
< 32
< 25
< 34
<34
< 21
<3
<3
<2
<3
<6
<3
<2
<3
<4
<3
<3
<3
<3
<2
<3
<2
<3
<4
<4
<3
<4
<6
<3
<3
<4
<4
<4
<4
<4
<4
<3
<4
<2
<3
<8
<8
<6
<8
< 12
<9
<7
<8
<8
<9
< 7
< 10
< 7
<7
<9
<5
<6
<3
<3
<3
<3
<6
<3
<3
<3
<3
<4
<3
<3
<3
<3
<3
<2
<3
<5
<6
<5
<6
< 11
<5
<5
<6
<8
<7
<7
<8
<6
<5
<7
<4
<6
<3
<4
<3
<4
<8
<5
<3
<4
<4
<5
<4
<5
<4
<3
<4
<3
<3
<6
<6
<5
<6
< 10
<7
<5
<7
<7
<8
<6
<8
<7
<5
<8
<4
<5
< 19
< 20
< 15
< 21
< 10
< 23
< 22
< 17
< 19
< 26
< 21
<34
< 19
< 17
<3
<3
<2
<3
<5
<3
<2
<3
<3
<3
<3
<3
<3
<2
<3
<3
<3
<3
<7
<4
<3
<3
<4
<4
<3
<4
<3
<3
<4
<2
<3
< 33
< 33
< 27
< 35
< 28
< 37
< 30
< 33
< 34
< 38
< 37
< 51
< 34
< 29
< 10
< 11
<7
< 12
<8
< 11
< 10
< 12
< 11
< 13
<9
< 15
< 10
<9
< 34
< 57
< 22
< 45
< 28
< 24
<29
< 3
<13
<2
<17
<3
<42
< 15
<24
<7
<30
< 11 (1) INSUFFICIENT VOLUME FOR GAMMA ANALYSIS B-2
TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-4 SW-LR-4 SW-LR-6 SW-LR-6 SW-LR-7 SW-LR-7 SW-LR-8 SW-LR-8 SW-LR-9 SW-LR-9 COLLECTION DATE 04/28/08 04/28/08 10/07/08 04/28/08 10/07/08 04/28/08 10/07/08 04/28108 10/07/08 04/28/08 10/09/08 04/28/08 10/10/08 H-3
< 186
< 190
< 142
< 185
< 147
< 183 208 + 102
< 186
< 131
< 186
< 145
< 190
< 166 SR-90
< 1.3
< 1.0
< 0.9
< 1.1
< 1.0
< 1.7 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-3
TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2008 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 SW-LR-9 10/07/08 10/07t08 10/07/08 10/07/08 10/09/08 10/10/08
< 31
< 37
< 28
< 33
< 34
< 20 54+/-33 <3
<3
<8
<3
<60
<3
<4
<10
<3 69 +/-32 <3
<3
<7
<3
<33
<3
<4
<8
<3
<27
<3
<4
<7
<3
<29
<1
<2
<5
<1
<6
<3
<6
<20
<6
<5
<7
<23
<5
<3
<6
<19.
<6
<4
<7
<21.
<7
<3
<6
<18
<3
<2
<4
<54
<3
<3
<2
<3
<3
<1
<3
<3
<3
<4
<3
<1
< 34
< 35
< 31
< 38
< 32
< 48 10 12 10 12 11 14 B-4