ML093340219
| ML093340219 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna, Bell Bend  |
| Issue date: | 05/07/2004 |
| From: | Shriver B PPL Bell Bend, Susquehanna |
| To: | Office of New Reactors |
| Shared Package | |
| ML093270273 | List: |
| References | |
| BNP-2009-356 | |
| Download: ML093340219 (182) | |
Text
Bryce L Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 blshriver@pplweb.com MAY 07 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OPI-I7 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PLA-5748 Docket Nos. 50-387 and 50-388 The Susquehanna SES Annual Radiological Environmental Operating Report is hereby submitted for the calendar year 2003 in accordance with Technical Specification Section 5.6.2.
If you have any questions, please contact Mr. Rocco R. Sgarro at (610) 774-7552.
Sincerely, Attachments copy: NRC Region I Mr. R. V. Guzman, NRC Project Manager Mr. S. Hansell, NRC Sr. Resident Inspector Mr. R. Janati, DEPIBRP Bryce L Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 blshriver@pplweb.com MAY 07 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OPI-I7 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PLA-5748 Docket Nos. 50-387 and 50-388 The Susquehanna SES Annual Radiological Environmental Operating Report is hereby submitted for the calendar year 2003 in accordance with Technical Specification Section 5.6.2.
If you have any questions, please contact Mr. Rocco R. Sgarro at (610) 774-7552.
Sincerely, Attachments copy: NRC Region I Mr. R. V. Guzman, NRC Project Manager Mr. S. Hansell, NRC Sr. Resident Inspector Mr. R. Janati, DEPIBRP
susq*ue*hannast~.am Electric Station 2003 ANNUAL REPORT, Annual Radiological Environmental
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SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT REPORT PERIOD: 12/30/02 -1/30/04 Prepared by:
F.~£~~
Health Physicist I
Reviewed by:
R.E. Doebler Chemistry Support Supervisor - SSES Approved by:
B.~~l Manager - Plant Chemistry PPL Susquehanna, LLC 769 Salem Boulevard Berwick, Pennsylvania 18603 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT REPORT PERIOD: 12/30/02 -1/30/04 Prepared by:
F.~£~~
Health Physicist I
Reviewed by:
R.E. Doebler Chemistry Support Supervisor - SSES Approved by: (I r4&..$3 B.~~l Manager - Plant Chemistry PPL Susquehanna, LLC 769 Salem Boulevard Berwick, Pennsylvania 18603
TABLE OF CONTENTS
SUMMARY
AND CONCLUSIONS........................................................................................ 1 INTRODUCTION...................................................................................................................... 5 AMBIENT RADIATION MONITORING.............................................................................. 16 AQUATIC PATHWAY MONITORING................................................................................ 20 ATMOSPHERIC PATHWAY MONITORING...................................................................... 33 TERRESTRIAL PATHWAY MONITORING....................................................................... 37 GROUND WATER MONITORING....................................................................................... 42 REFERENCES........................................................................................................................ 44 APPENDICES A.
2003 REMP CHANGES A-I B.
2003 REMP MONITORING SCHEDULE (SAMPLING AND ANALYSIS)
B-1 C.
2003 REMP MONITORING LOCA nON DESCRIPTIONS C-l D.
2003 LAND USE CENSUS RESULTS D-I E.
SUMMARY
DESCRIPTION OF SSES REMP ANALYTICAL E-I METHODS F.
2003 EXCEPTIONS TO THE SSES TECHNICAL F-I REQUIREMENTS SAMPLE SCHEDULE, METHODS AND ANALYSIS SENSITIVITIES G.
SUMMARY
OF DATA G-l H.
COMPARISON OF INDICATOR AND CONTROL 2003 H-l REMP ANNUAL MEANS FOR SELECTED MEDIA ANALYSIS RESULTS WITH MEANS FROM PREOPERATIONAL AND PRIOR OPERATIONAL PERIODS
- 1.
SPECIFIC ANALYSIS RESULTS TABULATED BY MEDIA I-I AND SAMPLING PERIOD J.
PERFORMANCE
SUMMARY
FOR THE RADIOANALYSES OF J-l SPIKED ENVIRONMENTAL SAMPLE MEDIA - 2003 I
TABLE OF CONTENTS
SUMMARY
AND CONCLUSIONS........................................................................................ 1 INTRODUCTION...................................................................................................................... 5 AMBIENT RADIATION MONITORING.............................................................................. 16 AQUATIC PATHWAY MONITORING................................................................................ 20 ATMOSPHERIC PATHWAY MONITORING...................................................................... 33 TERRESTRIAL PATHWAY MONITORING....................................................................... 37 GROUND WATER MONITORING....................................................................................... 42 REFERENCES........................................................................................................................ 44 APPENDICES A.
2003 REMP CHANGES A-I B.
2003 REMP MONITORING SCHEDULE (SAMPLING AND ANALYSIS)
B-1 C.
2003 REMP MONITORING LOCA nON DESCRIPTIONS C-l D.
2003 LAND USE CENSUS RESULTS D-I E.
SUMMARY
DESCRIPTION OF SSES REMP ANALYTICAL E-I METHODS F.
2003 EXCEPTIONS TO THE SSES TECHNICAL F-I REQUIREMENTS SAMPLE SCHEDULE, METHODS AND ANALYSIS SENSITIVITIES G.
SUMMARY
OF DATA G-l H.
COMPARISON OF INDICATOR AND CONTROL 2003 H-l REMP ANNUAL MEANS FOR SELECTED MEDIA ANALYSIS RESULTS WITH MEANS FROM PREOPERATIONAL AND PRIOR OPERATIONAL PERIODS
- 1.
SPECIFIC ANALYSIS RESULTS TABULATED BY MEDIA I-I AND SAMPLING PERIOD J.
PERFORMANCE
SUMMARY
FOR THE RADIOANALYSES OF J-l SPIKED ENVIRONMENTAL SAMPLE MEDIA - 2003
LIST OF FIGURES Figure Numbers Title Page
- 1.
Exposure Pathways to Humans 9
- 2.
2003 TLD Monitoring Locations within One Mile of the SSES 10
- 3.
2003 TLD Monitoring Locations from One to Five Miles of the 11 SSES
- 4.
2003 TLD Monitoring Locations Greater than Five Miles from the 12 SSES
- 5.
2003 Environmental Sampling Locations within One Mile of the 13 SSES
- 6.
2003 Environmental Sampling Locations from One to Five Miles of 14 the SSES
- 7.
2003 Environmental Sampling Locations Greater than Five Miles 15 from the SSES
- 8.
Ambient Radiation Levels Based on TLD Data 19
- 9.
Gross Beta Activity in Surface Water 30
- 10.
Tritium Activity in Surface Water 31
- 11.
Gross Beta Activity in Drinking Water 32
- 12.
Gross Beta Activity in Air Particulates 36
- 13.
Iodine-I31 Activity in Milk 41 ii LIST OF FIGURES Figure Numbers Title Page
- 1.
Exposure Pathways to Humans 9
- 2.
2003 TLD Monitoring Locations within One Mile of the SSES 10
- 3.
2003 TLD Monitoring Locations from One to Five Miles of the 11 SSES
- 4.
2003 TLD Monitoring Locations Greater than Five Miles from the 12 SSES
- 5.
2003 Environmental Sampling Locations within One Mile of the 13 SSES
- 6.
2003 Environmental Sampling Locations from One to Five Miles of 14 the SSES
.\\.J
- 7.
2003 Environmental Sampling Locations Greater than Five Miles 15 from the SSES
- 8.
Ambient Radiation Levels Based on TLD Data 19
- 9.
Gross Beta Activity in Surface Water 30
- 10.
Tritium Activity in Surface Water 31
- 11.
Gross Beta Activity in Drinking Water 32
- 12.
Gross Beta Activity in Air Particulates 36
- 13.
Iodine-I31 Activity in Milk 41 ii
SUMMARY
AND CONCLUSIONS Radiological Dose Impact The extent of the 2003 Radiological Environmental Monitoring Program (REMP) sampling met or exceeded the requirements of the Susquehanna Steam Electric Station (SSES) Technical Requirements. The types of analyses that were performed on these samples for the identification and quantification of radioactivity also met or exceeded the SSES Technical Requirements. The result of this effort was the verification of the SSES Effluent Monitoring Program data that indicate that the SSES operation has no deleterious effect on the health and safety of the public or the environment.
The amounts of the radionuclides detected in environmental samples during 2003 were very small, as in past years. Based on the radionuclide levels measured by the REMP, the maximum whole body dose or maximum organ dose to a member of the public from SSES operation is estimated to be less than one-tenth of one percent of the per unit dose guidelines established by the Nuclear Regulatory Commission (NRC) as stated in 10 CFR 50, Appendix I.
The maximum hypothetical off-site whole body and organ doses from radionuclides detected by the REMP and attributable to the SSES operations were calculated to be approximately 0.0015 mremlyear.
By contrast, potassium-40, a very long-COMPARISON OF PERCENT OF AVERAGE ANNUAL PUBLIC EFFECTIVE DOSE-EQUIVALENT FROM OTHER SOURCES WITH THAT FROM THE SSES Sources for the values provided, with the exception of Susquehanna, are the foUowing from NCRP Report #93 (1987): Tables 2.4 (Natural Background), 5.1 (Consumer Products), and 7.4 (Medical).
2003 Radiological Environmental Monitoring Report 1
SUMMARY
AND CONCLUSIONS Radiological Dose Impact The extent of the 2003 Radiological Environmental Monitoring Program (REMP) sampling met or exceeded the requirements of the Susquehanna Steam Electric Station (SSES) Technical Requirements. The types of analyses that were performed on these samples for the identification and quantification of radioactivity also met or exceeded the SSES Technical Requirements. The result of this effort was the verification of the SSES Effluent Monitoring Program data that indicate that the SSES operation has no deleterious effect on the health and safety of the public or the environment.
The amounts of the radionuclides detected in environmental samples during 2003 were very small, as in past years. Based on the radionuclide levels measured by the REMP, the maximum whole body dose or maximum organ dose to a member of the public from SSES operation is estimated to be less than one-tenth of one percent of the per unit dose guidelines established by the Nuclear Regulatory Commission (NRC) as stated in 10 CFR 50, Appendix I.
The maximum hypothetical off-site whole body and organ doses from radionuclides detected by the REMP and attributable to the SSES operations were calculated to be approximately 0.0015 mrem/year.
By contrast, potassium-40, a very long-COMPARISON OF PERCENT OF AVERAGE ANNUAL PUBLIC EFFECTIVE DOSE-EQUIVALENT FROM OTHER SOURCES WITH THAT FROM THE SSES SSES
<0.01 %
Medical 14%
Natural Background 81%
Consumer Products 5%
Sources for the values provided, with the exception of Susquehanna, are the foUowing from NCRP Report #93 (1987): Tables 2.4 (Natural Background), 5.1 (Consumer Products), and 7.4 (Medical).
2003 Radiological Environmental Monitoring Report 1
SlImmarv and Conclllsions lived, naturally occurring radionuclide found in the human body, is estimated to deliver an average annual dose to the blood forming organs of individuals in the United States of about 27 millirem.
While a small portion ofthe background dose from natural radiation sources, potassium-40 dose is still 18,000 times the estimated maximum whole body and organ doses to a hypothetical member of the public from ingestion of radionuclides attributable to the SSES.
The maximum direct radiation dose from SSES operation to a member of the public was determined to be approximately 0.0314 milliremlyear.
The total whole body dose from both ingested radionuclides and direct radiation is negligible compared to the public's exposure from natural background radiation, medical irradiation, and radiation from consumer products of more than 300 milliremlyear effective dose-equivalent.
Identified Radionuclides and Their Contributions Naturally OcclIrring Radionllc/ides In 2003, the SSES REMP reported the naturally occurring radionuclides beryllium-7, potassium-40, radium-226, and thorium-228 in the environment at levels exceeding the minimum detectable concentrations (MDCs) for their respective gamma spectroscopic analyses. Beryllium-7 was identified in air and sediment. Potassium-40 was observed in fish, sediment, surface water, ground water, milk, soil, and fruit and vegetables. Thorium-228 and 1
radium-226 were reported in sediment.
These radiomiclides are not related to the operation of the SSES. Doses from the presence of these radiomiclides were not included in the estimate of the dose from SSES attributable radionuclides.
Man-made Radionllc/ides Although not all due to SSES operation, the following man-made radionucIides were reported at levels in the environment in excess of the MDCs for their respective analyses: tritium, iodine-131 andcesium-137. These radionuclides, with the exception of' cesium-I 37, were identified in surface, ground and drinking water. Tritium was measured above minimum detectable concentrations in some surface water, drinking water, and ground water samples. Iodine-13l was identified in surface water and drinking water. Cesium-I37 was observed in sediment and soil.
Tritium is the only man-made radionucIide attributed to SSES operation. Tritium in media other than the Susquehanna River water downstream of the SSES was attributed to both natural production by the interaction of cosmic radiation with the upper atmosphere and previous atmospheric testing of nuclear weapons.
The presence of cesium-I 3 7 was attributed to non-SSES sources.
Cesium-137 was considered to be present only as residual fallout from atmospheric weapons testing. Iodine-131 was found in the aquatic pathway.
Evidence indicates that it is there only as the result of the discharge of medical
. waste to the Susquehanna or Lackawanna Rivers through sewage treatment plants upstream of the SSES.
2003 Radiological Environmental Monitoring Report I I SlImmarv and Conclllsions lived, naturally occurring radionuclide found in the human body, is estimated to deliver an average annual dose to the blood forming organs of individuals in the United States of about 27 millirem.
While a small portion ofthe background dose from natural radiation sources, the'.
potassium-40 dose is still 18,000 times the estimated maximum whole body and organ doses to a hypothetical member of the public from ingestion of radionuclides attributable to the SSES.
The maximum direct radiation dose from SSES operation to a member of the public was determined to be approximately 0.0314 milliremlyear.
The total whole body dose from both ingested radionuclides and direct radiation is negligible compared to the public's exposure from natural background radiation, medical irradiation, and radiation from consumer products of more than 300 milliremlyear effective dose-equivalent.
Identified Radionuclides and Their Dose*
Contributions Naturally OcclIrring Radionllc/ides In 2003, the SSES REMP reported the naturally occurring radionuclides beryllium-7, potassium-40, radium-226, and thorium-228 in the environment at levels exceeding the minimum detectable concentrations (MDCs) for their respective gamma spectroscopic analyses. Beryllium-7 was identified in air and sediment. Potassium-40 was observed in fish, sediment, surface water, ground water, milk, soil, and fruit and vegetables. Thorium-228 and 1
radium-226 were reported in sediment.
These radiomiclides are not related to the operation of the SSES. Doses from the presence of these radiomiclides were not included in the estimate of the dose from SSES attributable radionuclides.
Man-made Radionllc/ides Although not all due to SSES operation, the following man-made radionucIides were reported at levels in the environment in excess of the MDCs for their respective analyses: tritium, iodine-131 andcesium-137. These radionuclides, with the exception of' cesium-I 37, were identified in surface, ground and drinking water. Tritium was measured above minimum detectable concentrations in some surface water, drinking water, and ground water samples. Iodine-13l was identified in surface water and drinking water. Cesium-I37 was observed in sediment and soil.
Tritium is the only man-made radionucIide attributed to SSES operation. Tritium in media other than the Susquehanna River water downstream of the SSES was attributed to both natural production by the interaction of cosmic radiation with the upper atmosphere and previous atmospheric testing of nuclear weapons.
The presence of cesium-I 3 7 was attributed to non-SSES sources.
Cesium-137 was considered to be present only as residual fallout from atmospheric weapons testing. Iodine-131 was found in the aquatic pathway.
Evidence indicates that it is there only as the result of the discharge of medical
. waste to the Susquehanna or Lackawanna Rivers through sewage treatment plants upstream of the SSES.
2003 Radiological Environmental Monitoring Report I I
All of the man-made radionuclides mentioned above were not analyzed for in all media. For example, no analyses were perfonned in an effort to determine iodine-I3I levels in ground water. When selecting the types of analyses that would be perfonned, consideration was given to the potential importance of different radionuclides in the pathways to man and the regulatory analysis requirements for various environmental media.
Relative Radionuclide Activity Levels in Selected Media Some media monitored in the environment are significant for the numbers of gamma-emitting radionuclides routinely measured at levels exceeding analysis MDCs.
Sediment in the aquatic pathway and soil in the terrestrial pathway are two such media.
The following pie graphs show the relative activity contributions for the types of gamma-emitting radionuclides reported at levels above the analysis MDCs in sediment and soil at indicator locations during 2003.
2003 Radiological Environmental Monitoring Report Summary and Conclusions AQUATIC PATHWAY PERCENT TOTAL GAMMA ACTIVITY TERRESTRIAL PATHWAY PERCENT TOTAL GAMMA ACTIVITY Naturally occurring radionuclides accounted for 99.5 % and 99.4 % ofthe gamma-emitting activity in sediment and in soil, respectively, in 2003. Man-made radionuclides of SSES origin accounted for 0.1 % of the gamma-emitting activity in sediment during 3
CO"Z-All of the man-made radionuclides mentioned above were not analyzed for in all media. For example, no analyses were performed in an effort to determine iodine-I 3 I levels in ground water. When selecting the types of analyses that would be performed, consideration was given to the potential importance of different radionuclides in the pathways to man and the regulatory analysis requirements for various environmental media.
Relative Radionuclide Activity Levels in Selected Media Some media monitored in the environment are significant for the numbers of gamma-emitting radionuclides routinely measured at levels exceeding analysis MDCs.
Sediment in the aquatic pathway and soil in the terrestrial pathway are two such media.
The following pie graphs show the relative activity contributions for the types of gamma-emitting radionuclides reported at levels above the analysis MDCs in sediment and soil at indicator locations during 2003.
2003 Radiological Environmental Monitoring Report Summary and Conclusions AQUATIC PATHWAY PERCENT TOTAL GAMMA ACTIVITY SEDIMENT TERRESTRIAL PATHWAY PERCENT TOTAL GAMMA ACTIVITY SOIL Naturally occurring radionuclides accounted for 99.5 % and 99.4 % ofthe gamma-emitting activity in sediment and in soil, respectively, in 2003. Man-made radionuclides of SSES origin accounted for 0.1 % of the gamma-emitting activity in sediment during 3
co-z...
Summary and Conclusions 2003. Man-made radionuclides of non-SSES origin account for the rest of the gamma-emitting activity in sediment and soil during 2003. Generally, the activity for naturally occurring radionuclides reported in sediment and soil dwarfs the activity of the man-made radio nuclides also reported.
Radionuclides. Contribllting to Dose fron, SSES Operation Of the three man-made radionuclides reported in the environment by the SSES REMP, tritium is the only radionuclide attributable to SSES operation.
The dose to members of the public attributable to the identified Tritium was 0.0015 mrem.
Tritium was included in the dose calculation because it was identified in the REMP samples of water being discharged to the river. The concentration of tritium in the water and the volume of water discharged were used to determine the amount of tritium released. The presumed exposure pathways to the public from this radionuclide were drinking water taken from the Susquehanna River at Danville, P A, and eating fish caught near the SSES discharge to the river.
This assumption is based on the fact that tritium does not emit gamma radiation and the beta radiation emitted by tritium is not sufficiently penetrating to reach an individual on the shore.
I I
\\.J 2003 Radiological En'vlronmentalMonitoring Report Summary and Conclusions 2003. Man-made radionuclides of non-SSES origin account for the rest of the gamma-emitting activity in sediment and soil during 2003. Generally, the activity for naturally occurring radionuclides reported in sediment and soil dwarfs the activity of the man-made radio nuclides also reported.
Radionuclides. Contribllting to Dose fron, SSES Operation Of the three man-made radionuclides reported in the environment by the SSES REMP, tritium is the only radionuclide attributable to SSES operation.
The dose to members of the public attributable to the identified Tritium was 0.0015 mrem.
Tritium was included in the dose calculation because it was identified in the REMP samples of water being discharged to the river. The concentration of tritium in the water and the volume of water discharged were used to determine the amount of tritium released. The presumed exposure pathways to the public from this radionuclide were drinking water taken from the Susquehanna River at Danville, P A, and eating fish caught near the SSES discharge to the river.
This assumption is based on the fact that tritium does not emit gamma radiation and the beta radiation emitted by tritium is not sufficiently penetrating to reach an individual on the shore.
I I
\\.J 2003 Radiological En'vlronmentalMonitoring Report
Radiological Environme~~1 Monitoring The enclosed information is consistent with the objectives outlined in the SSES ODCM and in10CFR50 Appendix I,Section IV.B.2, IV.B.3 and IV.C.
In addition to the steps taken to and to monitor radioactive effluents from the SSES, the SSES Technical Specifications also require a program for the radiological monitoring of the environment in the vicinity of the SSES:
The objectives of the SSES REMP are as follows:
Fulfillment of SSES Technical Requirements' radiological environmental surveillance obligations; Verification of no detrimental effects on public health and safety
~'
and the environment from SSES operations, Assessment of dose impacts to the' public, if any, Verification of adequate SSES radiological effluent controls, and<~"
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Identification: measurement,
- trending, and evaluation' of" radionuclides' and their concentrations in critical environmental pathways near the SSES.
2003 Radiological Environmental Monitoring Report PPL has maintained a Radiological Environmeritru Monitoring Program (REMP) in the vicinity of the existing Susquehanna Stearn Electric'Station Units 1 and 2 sirice April, 1972, prior to construction of both units and ten years prior to the initial operation of Unit 1 in September, 1982. The SSES is located.
on an approximately 1500 acre tract' along the Susquehanna River, five miles northeast of Berwick in Salem Township, Luzerne County, Pennsylvania. The area around the site is primarily rural, consisting predominately of forest and agricultural lands. (More specific information on the demography, hydrology, meteorology, and land use characteristics of the area in the vicinity of the SSES can be found in the Environmental Report (Reference 1),
the Final Safety Analysis Report (Reference 2), and the Final '
Environmental Statement (Reference 3) for the SSES.) The purpose of the preoperational REMP (April, 1972 to September, 1982) was to establish a baseline for radioactivity in the local environment that could be compared with the radioactivity levels observed in various environmental media throughout the operational lifetime of the SSES. : This comparison facilitates assessments of the radiological impact of the SSES operation.
The SSES ~MP was designed on the basis of the NRC's Radiological Assessment Branch Technical Position on radiological,environmental <
monitoring, as described in Revision,!,
November 1979.(Reference 4) s Radiological Environme~~1 Monitoring ' "
The enclosed information is consistent,',
with the objectives outlined in the SSES ODCM and in10CFR50 Appendix I,Section IV.B.2, IV.B.3 and IV.C.
In addition to the steps taken to control,',' ;
and to monitor radioactive effluents ' "
from the SSES, the SSES Technical ',.,',
Specifications also require a program,,:
for the radiological monitoring of the :; <' '
environment in the vicinity of the SSES: :.:
The objectives of the SSES REMP are ":'
as follows:
Fulfillment of SSES Technical Requirements' radiological environmental surveillance obligations; Verification of no detrimental effects on public health and safety
~'
and the environment from SSES operations, Assessment of dose impacts to the' '
public, if any, Verification of adequate SSES '.): I.',':' :
radiological effluent controls, and<~" '.I:
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Identification: measurement, :'
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- trending, and evaluation' of" radionuclides' and their ". :
concentrations in critical environmental pathways near the SSES.
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2003 Radiological Environmental Monitoring Report PPL has maintained a Radiological.
Environmeritru Monitoring Program (REMP) in the vicinity of the existing Susquehanna Stearn Electric'Station Units 1 and 2 sirice April, 1972, prior to '
construction of both units and ten years prior to the initial operation of Unit 1 in September, 1982. The SSES is located.
on an approximately 1500 acre tract' along the Susquehanna River, five miles northeast of Berwick in Salem :
Township, Luzerne County, '
Pennsylvania. The area around the site is primarily rural, consisting predominately of forest and agricultural lands. (More specific information on the demography, hydrology, meteorology, and land use characteristics of the area in the vicinity of the SSES can be found in the Environmental Report (Reference 1),
the Final Safety Analysis Report (Reference 2), and the Final '
Environmental Statement (Reference 3) for the SSES.) The purpose of the preoperational REMP (April, 1972 to September, 1982) was to establish a baseline for radioactivity in the local environment that could be compared with the radioactivity levels observed in various environmental media throughout the operational lifetime of the SSES. : This comparison facilitates assessments of the radiological impact of the SSES operation.
The SSES ~MP was designed on the basis of the NRC's Radiological Assessment Branch Technical Position on radiological,environmental <
monitoring, as described in Revision,!,,
November 1979.(Reference 4) s
In trodllction However, the REMP conducted by PPL for the SSES exceeds the monitoring suggested by the NRC's branch technical position, as well as the SSES Technical Req~irements in terms of the number of monitoring locations, the frequency of certain monitoring, the types of analyses required for the samples, and the achievable analysis sensitivities.
Potelltial Exposure Pat~ways The three pathways through,which radioactive material may reach the pubJic from nuclear power plants are the atmospheric, terrestrial, and aquatic pathways. (Figure 1 depicts these pathways for the intake of radioactive materials.) Comprehensive radiological environmental monitoring must sample media from all of these pathways.
Mechanisms by which people may be exposed to radioactivity and radiation in the environment vary with the pathway.
Three mechanisms by which a member of the public has the potential to be exposed to radioactivity or radiation from nuclear power plants such as the SSES are as follows:
inhalation (breathing) ingestion (eating and drinking). and whole body irradiation directly from a plant or from immersion in the radioactive effluents.
REiYPScope During the operational period of the SSES, it has been important'to establish two different categories of monitoring locations, called control and indicator locations, to further assist in assessing the impact of the station operation.
Control locations have been situated at sites where it is considered unlikely that radiation or radioactive material from normal station operation would be detected. Indicator locations are sited where it is expected that radiation and radio~ctive material that might originate from the station would be most readily detectable.
Control locations for the atmospheric and terrestrial pathways are more than 10 miles from the station. Preferably, the controls also are in directions from the station less likely to be exposed to wind blowing from the station than are the indicator locations. Control locations for: the aquatic pathway, the Susquehanna River, are upstream of the station's discharge to the river.
Indicator locations are selected primarily on the basis of prox.imity to the station, although factors such as meteorology, topography, and sampling practicality also are considered.
Indicator locations for the atmospheric and terrestrial pathways are typically less than 10 miles from the station.
Most often, they are within 5 miles of the station. Indicator locations in the Susquehanna River are downstream of the station's discharge. Monitoring results from indicator locations are compared with results from control locations. These comparisons are made to discern any differences in the levels andlor types of radioactive material andlor radiation that might exist between indicators and controls and that could be attributable to the station.
In 2003, the SSES REMP collected more than 850 samples at more than 40 6
2003 Radiological Environmental Monitoring Report I I In trodllction However, the REMP conducted by PPL for the SSES exceeds the monitoring suggested by the NRC's branch technical position, as well as the SSES Technical Req~irements in terms of the number of monitoring locations, the frequency of certain monitoring, the types of analyses required for the samples, and the achievable analysis sensitivities.
Potelltial Exposure Pat~ways The three pathways through,which radioactive material may reach the pubJic from nuclear power plants are the atmospheric, terrestrial, and aquatic pathways. (Figure 1 depicts these pathways for the intake of radioactive materials.) Comprehensive radiological environmental monitoring must sample media from all of these pathways.
Mechanisms by which people may be exposed to radioactivity and radiation in the environment vary with the pathway.
Three mechanisms by which a member of the public has the potential to be exposed to radioactivity or radiation from nuclear power plants such as the SSES are as follows:
inhalation (breathing) ingestion (eating and drinking). and whole body irradiation directly from a plant or from immersion in the radioactive effluents.
REiYPScope During the operational period of the SSES, it has been important'to establish two different categories of monitoring locations, called control and indicator locations, to further assist in assessing the impact of the station operation.
Control locations have been situated at sites where it is considered unlikely that radiation or radioactive material from normal station operation would be detected. Indicator locations are sited where it is expected that radiation and radio~ctive material that might originate from the station would be most readily detectable.
Control locations for the atmospheric and terrestrial pathways are more than 10 miles from the station. Preferably, the controls also are in directions from the station less likely to be exposed to wind blowing from the station than are the indicator locations. Control locations for: the aquatic pathway, the Susquehanna River, are upstream of the station's discharge to the river.
Indicator locations are selected primarily on the basis of prox.imity to the station, although factors such as meteorology, topography, and sampling practicality also are considered.
Indicator locations for the atmospheric and terrestrial pathways are typically less than 10 miles from the station.
Most often, they are within 5 miles of the station. Indicator locations in the Susquehanna River are downstream of the station's discharge. Monitoring results from indicator locations are compared with results from control locations. These comparisons are made to discern any differences in the levels andlor types of radioactive material andlor radiation that might exist between indicators and controls and that could be attributable to the station.
In 2003, the SSES REMP collected more than 850 samples at more than 40 6
2003 Radiological Environmental Monitoring Report I I
locatio~s and peffonned more than 1,500 analyses. In additio~~ ih~ RE~',~
monitors ambient radiation)evels, using.
thennoIiiminescent dosimeters CfI.Ds) :'
at 84 indicator and control locations;,,',
making as manya~ 33~ radiation, level, ",f measurements each year. The media " '
monitored and analyses performed 'are';'
summarized in the table below.
Figures 2 through,7 di~play the REf>4P ' (
TLDs and sampJing locations in the,,',,',
vicinity or'the SSES:,;Appendix C,,':,',
provides directions; distances, and,a,',,',,,'
brief description of each of the l,ocations in Figures 2 through 7.
Regulatory agencies also participate in, '
monitoring the SSES environment and. "
also oversee PPL's monitoring efforts~, '"
The Stat~.ofJ>ennsy]vania*s Department of Environmental Protection (PADEP) "
monitors air "for radioactive particulat~s' '
and radioactive iodine. It also monitors',
milk, fruits and vegetables, surface and drinking water, fish, river sediments, and ambient radiation levels. P ADEP makes this data available to the NRC.
Inspectors from the NRC regularly visit the SSES to review procedures and lntrodtiction supporting the, (!ff1,uent and environmental monitoring for the SSES.
REMP Monitoring Sensitivity The sensitivity of the SSES REMP was demonstrated in 1986, following the problem with the Chemobyl reactor in,
the fonner Soviet Union. When the Chemobyl incident occurred, the SSES REMP was able to detect a relatively small increase in the level of gross beta activity in air samples at,both control '
and indicator locations; as well asJhe presence of some specific radioactive materials that are not normaJIy.
observed.
Detection of radiation and radioactive material from the SSES in the, environment is complicated by the
,~
presence of naturally occurring radiation and radioactive materials from both terrestrial and cosmic sources. Man-made radiation and radioactive materiai from non-SSES sources, such as nuclear, fanout from previous nuclear weapons tests and medical wastes, also can make
~
identification of SSES,radiation and radioactive material difficult. Together, SSESREMP T"pe of Monitorine Gross Alpha Activitv Gross Beta Activity Gamma-Emittin~ Radionuclide Activities Tritium Activity lodine-131 Activity Exposure Rates (byTLD) records, conduct personnel interviews, observe activities first-hand, and generally examine the programs Media Monitored.
Drinkine: Water All Waters. except Ground Water, and Air Particulates All Media All Waters Surface Water. Drinking Water. 'Air & Milk' Ambient Radiation Levels
~
this radiation and radioactive material, present backgr?l;lnd levels fro~ which an attempt is made to distinguish 2003 Radiological Environmental Monitoring Report 7
locatio~s and peffonned more than 1,500 analyses. In additio~~ ih~ RE~',~
monitors ambient radiation)evels, using.
thennoIiiminescent dosimeters CfI.Ds) :'
at 84 indicator and control locations;,,',
making as manya~ 33~ radiation, level, ",f measurements each year. The media " '
monitored and analyses performed 'are';'
summarized in the table below.
Figures 2 through,7 di~play the REf>4P ' (
TLDs and sampJing locations in the,,',,',
vicinity or'the SSES:,;Appendix C,,':,',
provides directions; distances, and,a,',,',,,'
brief description of each of the l,ocations in Figures 2 through 7.
Regulatory agencies also participate in, '
monitoring the SSES environment and. "
also oversee PPL's monitoring efforts~, '"
The Stat~.ofJ>ennsy]vania*s Department of Environmental Protection (PADEP) "
monitors air "for radioactive particulat~s' '
and radioactive iodine. It also monitors',
milk, fruits and vegetables, surface and drinking water, fish, river sediments, and ambient radiation levels. P ADEP makes this data available to the NRC.
Inspectors from the NRC regularly visit the SSES to review procedures and lntrodtiction
',{
J
~,;.!
supporting the, (!ff1,uent and environmental monitoring for the SSES.
REMP Monitoring Sensitivity The sensitivity of the SSES REMP was ':
demonstrated in 1986, following the problem with the Chemobyl reactor in,
the fonner Soviet Union. When the Chemobyl incident occurred, the SSES REMP was able to detect a relatively small increase in the level of gross beta activity in air samples at,both control '
and indicator locations; as well asJhe presence of some specific radioactive materials that are not normaJIy.
observed.
Detection of radiation and radioactive material from the SSES in the, '
environment is complicated by the '.,~
presence of naturally occurring radiation and radioactive materials from both ',,'
terrestrial and cosmic sources. Man-made radiation and radioactive materiai from non-SSES sources, such as nuclear,,
fanout from previous nuclear weapons tests and medical wastes, also can make, ~
identification of SSES,radiation and radioactive material difficult. Together, J
SSESREMP.
~: ~ ~'".'
T"pe of Monitorine Gross Alpha Activitv Gross Beta Activity Gamma-Emittin~ Radionuclide Activities Tritium Activity lodine-131 Activity Exposure Rates (byTLD) records, conduct personnel interviews, observe activities first-hand, and generally examine the programs Media Monitored.
Drinkine: Water '
All Waters. except Ground Water, and Air Particulates All Media All Waters Surface Water. Drinking Water. 'Air & Milk' Ambient Radiation Levels
~
~..,,:: 1:..1.
this radiation and radioactive material, present backgr?l;lnd levels fro~ which an attempt is made to distinguish 2003 Radiological Environmental Monitoring Report 7
11ltrodllction relatively small contributions from the SSES. This effort is further' complicated by the natural variations that typically occur from both monitoring location to location and with time at the same locations.
The naturally occurring radionucJides potassium-40, berylJium-7, radium-226, and thorium-228 are routinely observed in certain environmental media.
Potassium-40 has been observed in all monitored media and is routinely seen at readily detectable levels in such media as milk. fish, fruits and vegetables. Seasonal variations in beryllium-7 in air samples are regularly observed. Man-made radionuclides, such as cesium-1371eft over from nuclear weapons testing are often observed as well.. In addition~ the radionuclide tritium, produced by both cosmic radiation interactions in upper atmosphere as well as man-made (nuclear weapons), is another radionuclide typically observed.
Radioactivity levels in environmental media are usually so low that their measurements, even with art measurement methods, typically have significant degrees of uncertainty associated with As a resuH, expressions are often used when referring to these meas.urements that convey infonnation about the levels being measured relative to the measurement sensitivities. Tenns such as "minimum detectable concentration" (MDC) are used for this purpose. The fonnulas used to calculate MDCs may be in Appen(fix E.
The methods of measurement for sample radioactivity levels used by PPL's contracted REMP radioanalytical laboratories are capable of meeting the analysis sensitivity requirements found in the SSES Technical Requirements.
SummarY descriptions of the analytical procedures and the accompanying calculational methods used by the laboratories can be found in Appendix E.
Additional terrestrial and aquatic environmental monitoring is perfonned independent of the SSES REMP by the Academy of of PhiIadelphia~ Pennsylvania. The monitoring program is titled "Safety Net" and an annual report is provided to PPL Susquehanna, LLe. Although the Safety Net' program is not part of the SSES REMP, the data has provided additional infonnation relative to the environmental impact of the operation of the SSES.
8 2003 Radiological Environmental Monitoring Report 11ltrodllction relatively small contributions from the SSES. This effort is further'.
complicated by the natural variations that typically occur from both monitoring location to location and with time at the same locations.
The naturally occurring radionucJides potassium-40, berylJium-7, radium-226, and thorium-228 are routinely observed in certain environmental media.
Potassium-40 has been observed in all monitored media and is routinely seen at readily detectable levels in such media as milk. fish, fruits and vegetables. Seasonal variations in beryllium-7 in air samples are regularly observed. Man-made radionuclides, such as cesium-1371eft over from nuclear weapons testing are often observed as well.. In addition~ the radionuclide tritium, produced by both cosmic radiation interactions in the*
upper atmosphere as well as man-made (nuclear weapons), is another radionuclide typically observed.
Radioactivity levels in environmental media are usually so low that their measurements, even with state-of-the-art measurement methods, typically have significant degrees of uncertainty associated with ihem:(Reference5)* As a resuH, expressions are often used when referring to these meas.urements that convey infonnation about the levels being measured relative to the measurement sensitivities. Tenns such as "minimum detectable concentration" (MDC) are used for this purpose. The fonnulas used to calculate MDCs may be fo*und in Appen(fix E.
The methods of measurement for sample radioactivity levels used by PPL's contracted REMP radioanalytical laboratories are capable of meeting the analysis sensitivity requirements found in the SSES Technical Requirements.
SummarY descriptions of the analytical procedures and the accompanying calculational methods used by the laboratories can be found in Appendix E.
Additional terrestrial and aquatic environmental monitoring is perfonned independent of the SSES REMP by the Academy of Natuml*Sciences of PhiIadelphia~ Pennsylvania. The monitoring program is titled "Safety Net" and an annual report is provided to PPL Susquehanna, LLe. Although the Safety Net' program is not part of the SSES REMP, the data has provided additional infonnation relative to the environmental impact of the operation of the SSES.
8 2003 Radiological Environmental Monitoring Report I I
,J
Figure 1
\\
\\......J
\\
Uquid
~
EfHuent Direct Irradiation Fuel Transport I
- 1 Figure 1
FIGURE 2 2003 TLD MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES
~
FIGURE 2 2003 TLD MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES
FIGURE 3 2003 TLD MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES FIGURE 3 2003 TLD MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES
FIGURE 4 2003 TlO MONITORING lOCATIONS GREATER THAN FIVE MilES FROM THE SSES cos FIGURE 4 2003 TLD MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE SSES cos
FIGURE 5 2003 ENVIRONMENTAL SAMPLING LOCATIONS WITHIN ONE MILE OF THE SSES coc.
FIGURE 5 2003 ENVIRONMENTAL SAMPLING LOCATIONS WITHIN ONE MILE OF THE SSES 1'MILE.
FIGURE 6 2003 ENVIRONMENTAL SAMPLING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES co FIGURE 6 2003 ENVIRONMENTAL SAMPLING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES col
FIGURE 7 2003 ENVIRONMENTAL SAMPLING LOCATIONS GREATER THAN FIVE MILES FROM THE SSES FIGURE 7 2003 ENVIRONMENTAL SAMPLING LOCATIONS GREATER THAN FIVE MILES FROM THE SSES
INTRODUCTION The principal or primary,method for the SSES REMP's measurement of ambient, radiation levels is the use of
~
~';:..
thennoluminescent dosimeters The TLDs are crystals (calcium sulfate) capable of detecting and measuring lo~
~
levels of radiation by absorbing portion of the radiation's energy tha,t~s'.
incident upon them and storing.the ~.;.,
captured energy until the TLDs are processed (read). Processing involves ~':{
heating the TLDs to release their stored.
energy in the fonn of light measuring the intensity of the light that they emit. Th~ intensity of the light is proportional to the amountof radiation to which they were exposed.
Calibration of the TLD processors pennits a reliable relationship to be established between the light emitted and the amount of radiation dose received by the t~e result pennits accurate measurements of the ambient, radiation in the environment.
'i';~
~
~
Environm'ental TLDs exposed to natural radiation from ground (terrestrial radiation) and from the sky (cosmic) radiation. In addition,.
they also may be exposed to radiation. Most ofthe environmental TLD's natural radiation exposure comes, from sources in the ground..'Thesei'l::~;):
terrestrial sources vary naturally' wiih time due to changes 'in soil snow cover, etc. The natural-radiation, ~
picture is complicated because the factors affecting radiation reaching the TLDs from the ground vary differently with time from one location to another 2003 Environmental Radiological Monitoring Report Ambient Radiation Monitoring due to loeational differences'in such factors soil characteristics (amounts of organic matter, particle size, 'etc.),
drnitiage opporturiities~ and exposure 'to sunlight. 'Environmental TLDs can also be affected by direcfradiation (shine) from the ?SSES turbine buildings during:
transfer and storage, and radioactive gaSeous effluents from the SSES.
Unfortunately, 'fLDs do n~t have any.
inherent ability to indicate the source of the radiatio~ to which'theYareexposed.
The placement of nu~erous TLDs'in the environment can facilitate decision-'
making ~bo~,t the possible radiation, soiirces'to which TLDs are However~ a method for TLD data is still required The SSES relies on 'a statistically based approach to simultaD(!ously compare indicator TLD data with control TLDdata and operntionafTLIidata preoperational TLD'data.' This approach peririits the.flagging of '
environmental TLD doses that might have !been produced by'both man-made sources ofradiaiion; as well as'natUral radiation sources; It also provfde'sa' means for attributing a portion of the total TLD dose to SSES operation if appropriate. Appendix E, pages. ~-~
through E-IO~ provides a tb.e process for the results of TLD measurements.
16 TLDs; INTRODUCTION The principal or.primary,method for the SSES REMP's measurement of ambient, radiation levels is the use of
~ *. ',' :. ~';:..
thennoluminescent dosimeters (TLDs).:'
The TLDs are crystals (calcium sulfate) ;'
capable of detecting and measuring lo~
~
levels of radiation by absorbing a..:,,:,!
portion of the radiation's energy tha,t~s'.
incident upon them and storing.the ~.;., ;
captured energy until the TLDs are ':', d processed (read). Processing involves ~':{
heating the TLDs to release their stored..
energy in the fonn of light and.,': "',,:
measuring the intensity of the light that.
they emit. Th~ intensity of the emitted.,.:'
light is proportional to the.amountof i:,' :'
radiation to which they were exposed. '
Calibration of the TLD processors
' ;.;! r pennits a reliable relationship to be, ; 1 \\:.
established between the light emitted :," I:
and the amount of radiation dose.... !.'
received by the ;fLDs; t~e result pennits i accurate measurements of the ambient, radiation in the environment.
'i';~ :' ~
,. ~ ~ [ ; 1 ~
Environm'ental TLDs,are"continually** ",. ;
exposed to natural radiation from the,:.,,;
ground (terrestrial radiation) and from,i..
the sky (cosmic) radiation. In addition,. :
they also may be exposed to man-made::
radiation. Most ofthe environmental :::
TLD's natural radiation exposure comes, from sources in the ground..'Thesei'l::~;): ':
terrestrial sources vary naturally' wiih :J..:: j' time due to changes 'in soil moisture;, ::.. i snow cover, etc. The natural-radiation, ~.
picture is complicated because the factors affecting radiation reaching the TLDs from the ground vary differently with time from one location to another 2003 Environmental Radiological Monitoring Report Ambient Radiation Monitoring
. -~ ",.,'
'oi.';
due to loeational differences'in such "
factors.8S soil characteristics (amounts.
of organic matter, particle size, 'etc.),
drnitiage opporturiities~ and exposure 'to '
sunlight. 'Environmental TLDs can also be affected by direcfradiation (shine) :
from the ?SSES turbine buildings during:
operation,*radivaste transfer and storage, and radioactive gaSeous effluents from '
the SSES..
Unfortunately, 'fLDs do n~t have any.
inherent ability to indicate the source of the radiatio~ to which'theYareexposed.
The placement of nu~erous TLDs'in '. '
the environment can facilitate decision-',
making ~bo~,t the possible radiation,,
soiirces'to which TLDs are exposed.':* ' '
However~ a method for evalu*atiiig TLD.
data is still required:' The SSES *.REMP :
relies on 'a statistically based approach ;.
to simultaD(!ously compare indicator ::.:
TLD data with control TLDdata and operntionafTLIidata With':";:, "
preoperational TLD'data.' This '..
approach peririits the.flagging of '
environmental TLD doses that might have !been produced by'both man-made sources ofradiaiion; as well as'natUral,.
radiation sources; It also provfde'sa' means for attributing a portion of the '.
total TLD dose to SSES operation if appropriate. Appendix E, pages. ~-~ :
through E-IO~ provides a description*of tb.e process for evaluating the results of TLD measurements.
t
\\
16
Ainhiimt Radiatiijn l~fonitoring Scope TLDs The area around the SSES was divided for monitoring purPoses into sixteen sectors radiating outwards, from the plant site, each en'compaSsing an area described by an ar~
2~.~
TLDs were placed in all 16 sectors at varying distances from the plant.
Monitoring locations ~ere chosen.
according to the criteria presented in the NRC Branch Technical Position on Radiological Monitoring (Revision 1, November, 1979). The locations for the TLDs were selected by considering factors such as loc~l meteorological, topographical, and population' distribution characteristics.
During 2003, the SSES REMP had 76 indi,cator TLD' l~cations and ei~t controlTLD locations. This 'level of monitoring exceeds that which IS required by th~ Nuclear Regula'tory,
Commission. The indicator TLDs,,
nearest the SSES are positioned at the secu~ity or ~e?met~rfe~ces su~ounding the SIte. This ]s the closest that a' member of the public would be abi~ to approach the station.. The co'ntrol TLDs are the most distant from the SSES '
ranging from 10 to 20 miles from the site.
Monitoring Results TLDs TLDs were retrieved and quarterly in 2003. Average ambient radiation levels measured by environmental TLDs generally remained constant throughout 2003, as 17 sho~ in the bar ~phon the following page. Refer to Figure 8 whIch trends both indicator and control data quarterly from 1973 through 2003.
The 2003 arimial average exposures indicator and' control locations were 20.2 mR/std. qtr. and 19.0 mR/std. qtr.,
respectively. The 2003 exposures are within the ranges of annual averages for the prior operational 'periods at each type of monitoring location. Refer Figure 8 at the end of this section which trends quarterly TLD results for both preoperational and operational periods at the SSES. Refer to Appendix H, Table HI, page H 3 for a comparison of the 2003 mean indicator and control' TLD results with the means for the' preoperational and prior operational periods at the SSES.
Indicator environmental TLD results for 2003 were examined quarterly on an individual location basis and compared with both current contiollocation results and preoperational data. Very small SSES exposure contributions were suggested during 2003 at the following onsite locations: IS2, 6S4, 6S9, 7S6,8S2~9S2, 10S2, 11S3, 12S4, 13S2, 13S4, 13S5, 16SI~ and 16S2.
Thus; there' were 10 monitored locations in 2003 where a SSES dose contribution is considered to have been discernible.
Refer to Appendix E, page E-6, for'a discussion of4'TLD Data Interpretation.'" TLD results for all locations for each quarter of 2003 may be found in Appendix I, Table I-I, beginning at page 1-2.
2003 Environmental Radiologic:alMonitoring Report
Ambient Radiation Monitoring The estimated quarterly exposure contributions were summed by location for the entire year. The largest dose suggested was approximately 0.0314 rnrem at an on site monitoring location, 9S2, 0.2 mile south of the SSES. This dose was used for determining compliance with SSES Technical Requirement Limit 3.11.3 for annual effluent reporting purposes.
This dose amounts to only 0.13% of the 25 rnrem whole-body dose limit of SSES Technical Requirement 3.11.3.
2003 Environmental Radiological Monitoring Report 18 c.O~
Ambient Radiation Monitoring 2003 REMP Quarterly TLD Averages 25.0
..: 20.0 tT 15.0
-c - 10.0 III
~
E 5.0 0.0 The estimated quarterly exposure contributions were summed by location for the entire year. The largest dose suggested was approximately 0.0314 rnrem at an on site monitoring location, 9S2, 0.2 mile south of the SSES. This dose was used for determining compliance with SSES Technical Requirement Limit 3.11.3 for annual effluent reporting purposes.
This dose amounts to only 0.13% of the 25 rnrem whole-body dose limit of SSES Technical Requirement 3.11.3.
2 3
Calendar Quarters 2003 Environmental Radiological Monitoring Report 4
18 c.O~
FIGURE 8 - AMBIENT RADIATION LEVELS BASED ON TLD DATA CJQ FIGURE 8 - AMBIENT RADIATION LEVELS Exposure Rate (mRlSTD Qtr)
BASED ON TLD DATA 50,--------------------------,,--------------------------------------------------------,
PREOPERATIONAL 45 40 35 30 25 20 15 10 5
0
~
l£l r---
0\\
~
r---
r---
r---
r---
at) at) 0\\
0\\
0\\
0\\
0\\
0\\
OPERATIONAL l£l at) 0\\
Unit 2 Criticality r---
at) 0\\
0\\
at) 0\\
~
0\\
0\\
0\\
0\\
l£l t-0\\
~
0\\
0\\
0\\
=
=
0\\
0\\
0\\
=
=
M M
Indicator Control CJQ
Aquatic Patlrwaj; Monitoring E:t'~Uj!l0~QY.At~p:~~r~l\\¥;M_QNi:rPRiNG.;C:::Q:*:;~;c~7 INTRODUCTION The fol1owing media were monitored in 2003 by th~ SSES REMP in the pathway: surface water~ drinking fish, and sediment. Some of the' media (e.g., drinking water and fish) infonnation that can be especially useful to the estimation of possible dose to the public from potentially ingested' radioactivity, if detected. Other media, such as' sediment, can be useful for trending radioactivity levels in the' aquatic pathway, primanJytJecause of' their tendency to assimilate certain materials that might enter the surface water to wh~c~ they are exposed. The results from monitoring all of media provide a of the aquatic!
pathway that is clearer th~m that could be obtained if one or more were:
not included in the REMP.
Fruits or vegetables that are grown fields irrigated with surface water would also be inthe aquatic pathway. The land use census (Reference 11) conducted in 2003 looked at fanns within 10 miles downstream of the SSES. Two fann fields were found to have been irrigated during the growing season.
The aquatic pathway in the vicinity of, the SSES is the Susquehanna Rjver~
Monitoring of al1 'of the aquatic except drinking water, is conducted' both downstream' arid upstream of location from which occasional SSES' low-level radioactive discharges' enter the river/The upstream monitoring locations serve as controls to provide' 2003 Radiological Environmental Monitoring Report data for comparison with downstream monitoring results. The poteniial exists for radioactive material that might be present in SSES airborne releases to eJiter the Susquehanna River upstream of the plant through either direct deposition (e.g., settling or'washout) by way of runoff from deposition on land adjacent to the river. However direct deposition and runoff are considered to be insignificant as means of entry for SSES radioactivity into the Susquehanna River when compared to Jiquid discharges under nOrnlal conditions.
Lake Took-a-While (LTAW). which is located in PPL's Riverlands Recreation Area adjacent to the Susquehanna River, is a]so considered to be part of the aquatic pathway for monitoring purposes. Although it is not in pos~tion to receive water discharged to the river from the'SSES, it can receive stonn runoff from theSSES. Stonn' runoff from the SSESsite sho'uld not nonnally contain any measurable radioactivity from the plant. However, the SSES REMP, consistent with other' aspects of aquatic monitoring and the REMP. ingfmeral~ goes beyond its requirements by monitoringLTAW.
Scope Surface Water Surface water was routinely sampled from the Susquehanna River at one indicator ]o~ation (6S5) and one con'lro]
location (6S6)'iitthe SSES River Water Intake during 2003. Sampling also took 20 Aquatic Patlrwaj; Monitoring v
E:t'~Uj!l0~QY.At~p:~~r~l\\¥;M_QNi:rPRiNG.;C:::Q:*:;~;c~7 INTRODUCTION The fol1owing media were monitored in 2003 by th~ SSES REMP in the aquatic' pathway: surface water~ drinking water,"
fish, and sediment. Some of the' media :
(e.g., drinking water and fish) provide,r:'
infonnation that can be especially useful to the estimation of possible dose to the public from potentially ingested' radioactivity, if detected. Other media, :.
such as' sediment, can be useful for trending radioactivity levels in the' aquatic pathway, primanJytJecause of' their tendency to assimilate certain materials that might enter the surface '
water to wh~c~ they are exposed. The results from monitoring all of these' '
media provide a p,icture of the aquatic! r pathway that is clearer th~m that 'which"; !
could be obtained if one or more were: ','
not included in the REMP. "if, Fruits or vegetables that are grown in',"
fields irrigated with surface water would also be inthe aquatic pathway. The.';
land use census (Reference 11) conducted in 2003 looked at fanns within 10 miles downstream of the SSES. Two fann fields were found to have been irrigated during the 2003'* "
growing season.
The aquatic pathway in the vicinity of, f' the SSES is the Susquehanna Rjver~,'",
Monitoring of al1 'of the aquatic media;'-'
except drinking water, is conducted' 'j ;
both downstream' arid upstream of the;;'
location from which occasional SSES' -','
low-level radioactive discharges' enter,';" I the river/The upstream monitoring <"
.,j ;.
locations serve as controls to provide' '.' :
2003 Radiological Environmental Monitoring Report data for comparison with downstream monitoring results. The poteniial exists for radioactive material that might be present in SSES airborne releases to eJiter the Susquehanna River upstream of the plant through either direct deposition (e.g., settling or'washout) or' by way of runoff from deposition on land adjacent to the river. However direct deposition and runoff are considered to be insignificant as means of entry for SSES radioactivity into the Susquehanna River when compared to Jiquid discharges under nOrnlal conditions.
Lake Took-a-While (LTAW). which is.
located in PPL's Riverlands Recreation Area adjacent to the Susquehanna River, is a]so considered to be part of the aquatic pathway for monitoring,
purposes. Although it is not in a' pos~tion to receive water discharged to.
the river from the'SSES, it can receive stonn runoff from theSSES. Stonn' runoff from the SSESsite sho'uld not nonnally contain any measurable radioactivity from the plant. However, the SSES REMP, consistent with other' aspects of aquatic monitoring and the REMP. ingfmeral~ goes beyond its requirements by monitoringLTAW.
Scope Surface Water Surface water was routinely sampled from the Susquehanna River at one indicator ]o~ation (6S5) and one con'lro].
location (6S6)'iitthe SSES River Water Intake during 2003. Sampling also took 20
Aqllatic Pathway Monitoring place at the fol1owing additional indicator locations:' the SSES discharge, line to the river (2S7/6S7) and Lake Took-A-Whi1e (LTAW).
Drinking Water Drinking water samples were collected at location 12H2, the Danville Municipal Water Authoriiy's treatment facility on the Susquehanna River, in 2003. Treated water is collected from the end of the processing fjowpath, representing finished wat~r that is suitable for drinking. This is the nearest point downstream of the SSES discharge to the River at which drinking water is obtained. No drinking water control location is sampled. ' For all intents and purposes, control surface water sampling locations would be suitable for comparison.
Fish Fish were sampled from the Susquehanna River in the spring and fall of 2003 at one indicator, location, IND, downstream of the SSES liquid discharge to the River and one control location, 2H, sufficiently upstream to essentially preclude the likelihood that the fish caught there would spend any time below the SSES discharge. In addition, fish we~e also sampled in the fall from PPVs Lake Took-a-While, location LTAW. This location is not downstream of the SSES discharge. It is sampled because of its potential for receiving runoff from the SSES.
LTAW is considered an indicator location.
Sediment Sediment sampling was performed in the spring and fail at i'ndicator locations 7B and 12F and control location 2B on 21 the Susquehanna River. In addition, sediment' was also obtained from location LTAW.
Sampling Surface Water Weekly grab sampling was performed at the indicator location 6S5. Weekly grab samples were composited both monthly and biweekly at this location. Location 6S5 was considered a backup for locations 2S7 and 6S7 in the event that water could not be obtained from the automatic samplers at these locations.
Nevertheless, 6S5.was sampled routinely throughout 2003, since it is the closest downstream sampling point to the SSES discharge.
Indicator locations 2S7 and 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) line, and control location 6S6, the SSES River Water Intake structure, were sampled time proportionally using automatic continuous samplers. The samplers were typically set to obtain 30-60 ml aliquots every 20-25 minutes. Weekly, the water obtained by these samplers was retrieved for both biweekly and monthly compositing.
The other surface water monitoring location, LTAW, was grab sampled once each month.
Drinking Water Treated water was sampled time proportionally by an automatic sampler.
The sampler was typically set to obtain three 12-ml aliquots every twenty minutes. Weekly, the water obtained by this sampler was retrieved for both biweekly and monthly compositing.
2003 Radiological Environmental Monitoring Report I I Aqllatic Pathway Monitoring place at the fol1owing additional indicator locations:' the SSES discharge, line to the river (2S7/6S7) and Lake Took-A-Whi1e (LTAW).
Drinking Water Drinking water samples were collected at location 12H2, the Danville Municipal Water Authoriiy's treatment facility on the Susquehanna River, in 2003. Treated water is collected from the end of the processing fjowpath, representing finished wat~r that is suitable for drinking. This is the nearest point downstream of the SSES discharge to the River at which drinking water is obtained. No drinking water control location is sampled. ' For all '
intents and purposes, control surface water sampling locations would be suitable for comparison.
Fish Fish were sampled from the Susquehanna River in the spring and fall of 2003 at one indicator, location, IND, downstream of the SSES liquid discharge to the River and one control location, 2H, sufficiently upstream to essentially preclude the likelihood that the fish caught there would spend any time below the SSES discharge. In addition, fish we~e also sampled in the fall from PPVs Lake Took-a-While, location LTAW. This location is not downstream of the SSES discharge. It is sampled because of its potential for receiving runoff from the SSES.
LTAW is considered an indicator location.
Sediment Sediment sampling was performed in the spring and fail at i'ndicator locations 7B and 12F and control location 2B on 21 the Susquehanna River. In addition, sediment' was also obtained from location LTAW.
Sampling Surface Water Weekly grab sampling was performed at the indicator location 6S5. Weekly grab samples were composited both monthly and biweekly at this location. Location 6S5 was considered a backup for locations 2S7 and 6S7 in the event that water could not be obtained from the automatic samplers at these locations.
Nevertheless, 6S5.was sampled routinely throughout 2003, since it is the closest downstream sampling point to the SSES discharge.
Indicator locations 2S7 and 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) line, and control location 6S6, the SSES River Water Intake structure, were sampled time proportionally using automatic continuous samplers. The samplers were typically set to obtain 30-60 ml aliquots every 20-25 minutes. Weekly, the water obtained by these samplers was retrieved for both biweekly and monthly compositing.
The other surface water monitoring location, LTAW, was grab sampled once each month.
Drinking Water Treated water was sampled time proportionally by an automatic sampler.
The sampler was typically set to obtain three 12-ml aliquots every twenty minutes. Weekly, the water obtained by this sampler was retrieved for both biweekly and monthly compositing.
2003 Radiological Environmental Monitoring Report I I
.J J
Fish Fish were obtained by electrofishi~g.
~
Electrofishing stuns the fish and allows them to float to the surface so that tho~~
ofthe desired species and sufficient si~e can be sampled. Sampled fish include, recreationally important species, such as smallmouth bass, and also channel catfish and shorthead redhorse. The fish are filleted and the edible portions are kept for analysis.
Sediment Shoreline sediment was collected to depths of four feet of water.
Sample Preservation and Analysis' Sllrface and,Drinking Water Surface and drinking water samples were analYzed monthly for ~eta activities, the activities of gamma-emitting radion~clides, and tritium acti~ities. Biweekly composite samp'l~s were anaIYzcdforI-13'1. In addition, drinking water samples were analyZed, for gross alpha activity.
The use of~tri~~cid and bisulfite as presen;atives in,surface an'~
drinking water samples ~\\Y~
discontinued in _~003 (at d.te req~es.t ~f..::
thevendorlabora!ory),
~ ~
Sedi;lIent and Fish' Fish are frozen until shipment. All samples are analyzed by gamma, spectroscopy for the activities of any gamma emitting radignuclides that mi:\\y,
be present.
2003 Radiological Environmental Monitoring Report Aquatic Patlnvar Monitoring Monitoring Results Surface JVater Results from specific sample analyses of surface water may be found in Tables 1-2 and 1.;3 of Appendix I. A summary of the 2003 surface water data may be located in Table G of Appendix G. Comparisons of 2003 monitoring results with those of past years may be found in Tables H 2 through H 4 of Appendix H.
The Nuclear Regulatory Commission (NRC) requires that averages ofthe activity levels for indicator; environmental monitoring locations and for control environmental monitoring' locations of surface water, as well as other monitored media, be reported to the NRC annually. Data from the following three surface water monitoring locations were averaged together as indicators for reporting, purposes: one location (6S5) on the Susquehanna River doWnstream 'of the
- SSES, While (LTA W) adjacent to the river, and the SSES cooling tower,blowdown discharge" (CTBD) line to the river (2S7).
Technically; the CTBD line is not part of the environment.. The CTBD line is a below ground pipe to which the public has no access; contrary to' the environmental monitoring locations on the Susquehanna River to which the public does have access.
currently there is no automatic composite sampling of an indicator location on the Susquehanna River, so the CTBD line from the SSES is included as an indicator monitoring 22 Fish
),'
Fish were obtained by electrofishi~g. ? * ~
Electrofishing stuns the fish and allows them to float to the surface so that tho~~
ofthe desired species and sufficient si~e can be sampled. Sampled fish include, recreationally important species, such as smallmouth bass, and also channel i catfish and shorthead redhorse. The "
fish are filleted and the edible portions,
are kept for analysis.
Sediment Shoreline sediment was collected to depths of four feet of water.
.... ~. :.
Sample Preservation and Analysis' Sllrface and,Drinking Water Surface and drinking water samples were analYzed monthly for ~eta activities, the activities of gamma-emitting radion~clides, and tritium
'\\'
acti~ities. Biweekly composite samp'l~s.
were anaIYzcdforI-13'1. In addition, drinking water samples were analyZed, '.
for gross alpha activity.
- /;1 r*
I
~"
The use of~tri~~cid and sodium."
~. "i bisulfite as presen;atives in,surface an'~,,
drinking water samples ~\\Y~ j 1 ; **,t:;,:,:
discontinued in _~003 (at d.te req~es.t ~f..::
thevendorlabora!ory),
"';'1.1'-
, : ~ ~
Sedi;lIent and Fish',;, ;;::.
.1 t,'"jj Fish are frozen until shipment. All samples are analyzed by gamma,...,
spectroscopy for the activities of any gamma emitting radignuclides that mi:\\y,
be present..
I
.,~.
2003 Radiological Environmental Monitoring Report Aquatic Patlnvar Monitoring Monitoring Results Surface JVater Results from specific sample analyses of surface water may be found in Tables 1-2 and 1.;3 of Appendix I. A summary of the 2003 surface water data may be located in Table G of Appendix G. Comparisons of 2003,,
monitoring results with those of past years may be found in Tables H 2 through H 4 of Appendix H.
The Nuclear Regulatory Commission (NRC) requires that averages ofthe activity levels for indicator; environmental monitoring locations and for control environmental monitoring' locations of surface water, as well as other monitored media, be reported to the NRC annually. Data from the '
following three surface water,
monitoring locations were averaged together as indicators for reporting, ;
purposes: one location (6S5) on the Susquehanna River doWnstream 'of the SSES, Lake* Took*a While (LTA W) adjacent to the river, and the SSES '
cooling tower,blowdown discharge" (CTBD) line to the river (2S7).
Technically; the CTBD line is not part of the environment.. The CTBD line is a below ground pipe to which the public '
has no access; contrary to' the other-:
environmental monitoring locations on the Susquehanna River to which the.;.
public does have access. However,:
currently there is no automatic.. ' '
composite sampling of an indicator location on the Susquehanna River, so.'
the CTBD line from the SSES is included as an indicator monitoring 22
Aquatic PatltwavMonitoring location in the radiological envirorunental monitoring program.
Most of the water entering the Susquehanna River through the SSES CTBO line is simply water that was taken from the river upstream of the SSES, used for cooling purposes without being radioactively!
contaminated by SSES operation, and returned to the river. Nevertheless, batch discharges of relatively small volumes of slightly radioactively contaminated water are made to the river through the SSES CTBO at times throughout each year. The water is released from tanks of radioactively
, contaminated water on site to the CTBO and mixes with,the noncontaminated water already present in the CTBO.
Flow rates from the tanks containing radioactively contaminated water being discharged to the CTBO vary based on the radioactivity level of the batch release. In addition, the minimum flow rate for the returning water in the CTBO is maintained at a flow rate of 5,000 gpm or higher. These requirements are in place to' ensure adequate dilution of radioactively contaminated water by the returning noncontaminated water in the CTBO prior to entering the river.
At the point that CTBO water enters the river, additional, rapid dilution of the discharged water by the river is promoted by releasing it through a diffuser. The diffuser is a large pipe with numerous holes in it that is positioned near the bottom of the river.
CTBO discharges exit the diffuser through the many holes, enhancing the mixing ofthe discharge and river waters. The concentrations of contaminants are reduced significantly 23 as the discharged water mixes with the much larger flow of river water. The mean flow rate of the Susquehanna River in 2003 was approxhllately 9,910,000 gpm: This is more than 1,900 tim~s the required minimum flow rate through the CTBO for discharges to be permitted.
The amounts of radioactively contaminated water being discharged are small. Nevertheless, sensitive analyses of the water samples can often detect the low levels of certain types of radioactivity in the CTBO water following dilution. Though the levels of radioactivity measured in the CTBO water are generally quite low, they tend to be higher than those in the river downstream of the SSES. Most radionuclides discharged from the SSES CTBO are at such low levels in the downstream river water that, even with the sensitive analyses performed, they cannot be detected.
When the radioactivity levels from the CTBO samples throughout the year are averaged with those obtained from actual downstream monitoring locations, the result is an overall indicator location average that is too high to be 'representative' of the actual average radioactivity levels of the downstream river water. As the following discussions are reviewed, consideration should be given to this inflation of average radioactivity levels from the inclusion of CtBO (location 2S7/6S7) results in the indicator data that is averaged.
The 2003 data for gross beta activity analyses of surface water indicator locations is higher than those of 2002.
2003 Radiological, Environmental Monitoring Report I I Aquatic PatltwavMonitoring location in the radiological envirorunental monitoring program.
Most of the water entering the Susquehanna River through the SSES CTBO line is simply water that was taken from the river upstream of the SSES, used for cooling purposes without being radioactively! :'
contaminated by SSES operation, and returned to the river. Nevertheless, batch discharges of relatively small volumes of slightly radioactively contaminated water are made to the river through the SSES CTBO at times throughout each year. The water is released from tanks of radioactively
, contaminated water on site to the CTBO and mixes with,the noncontaminated water already present in the CTBO.
Flow rates from the tanks containing radioactively contaminated water being discharged to the CTBO vary based on the radioactivity level of the batch release. In addition, the minimum flow rate for the returning water in the CTBO is maintained at a flow rate of 5,000 gpm or higher. These requirements are in place to' ensure adequate dilution of radioactively contaminated water by the returning noncontaminated water in the CTBO prior to entering the river.
At the point that CTBO water enters the river, additional, rapid dilution of the discharged water by the river is promoted by releasing it through a diffuser. The diffuser is a large pipe with numerous holes in it that is positioned near the bottom of the river.
CTBO discharges exit the diffuser through the many holes, enhancing the mixing ofthe discharge and river waters. The concentrations of contaminants are reduced significantly 23 as the discharged water mixes with the much larger flow of river water. The mean flow rate of the Susquehanna River in 2003 was approxhllately 9,910,000 gpm: This is more than 1,900 tim~s the required minimum flow rate through the CTBO for discharges to be permitted.
The amounts of radioactively contaminated water being discharged are small. Nevertheless, sensitive analyses of the water samples can often detect the low levels of certain types of radioactivity in the CTBO water following dilution. Though the levels of radioactivity measured in the CTBO water are generally quite low, they tend to be higher than those in the river downstream of the SSES. Most radionuclides discharged from the SSES CTBO are at such low levels in the downstream river water that, even with the sensitive analyses performed, they cannot be detected.
When the radioactivity levels from the CTBO samples throughout the year are averaged with those obtained from actual downstream monitoring locations, the result is an overall indicator location average that is too high to be 'representative' of the actual average radioactivity levels of the downstream river water. As the following discussions are reviewed, consideration should be given to this inflation of average radioactivity levels from the inclusion of CtBO (location 2S7/6S7) results in the indicator data that is averaged.
The 2003 data for gross beta activity analyses of surface water indicator locations is higher than those of 2002.
2003 Radiological, Environmental Monitoring Report I I
The 2003 !mean gross beta of 6.1 pCilliter for indicator greater than the 2002 indicator mean gross beta activity of 5.4 pCilliter.
2003 indicator mean activity is the range of the annual means for the ~
previous operational period of the SSES. The 2003 mean gross beta activity of 2.4,pCilliter for control locations is 'Jess than the 2.9 pCi/liter forthe 2002 control mean gross activity. 'The 2003 control mean activity is within the range of the annual means for previous operational periods~'
The 2003 control mean is bel'ow the' range of annual means for" p~eoperati~nal periods. 'Refer to Figure 9 which trends gross beta activitie~ separately for surface water',
indjc~to~. and control,lo~ations quarter~y from 1975 thro'ugh Comparison of the 2003 indicator mean' (6.1 pCill)to the 2003 control mean (2.4 pCi/l) suggests a contribution of beta activity from the SSES. The 2003 data is similar in this regard to the averages of annual' means for indicator and control locations for the' prior'
~
operational period. 'During the prior operatj~naI~nod, the average of annmll iridic'ator means exceeds the average of annual control m'eans for gross beta activity.
The 2003 means foi iridin~~131'activityi ~;
~
at indicator and control surface water monitoring location's ~~re 0.~6'pci/i!t~V' and ~)'26 pCillitei~ 'respectively.,
2003 indicator and control means less than the corresponding 2002 means.
The 2003;ipdic,at?r m~a~ ~ctivity is greater than the averages of the annual, means for indicator.1ocations for the',
prior operational and preoperational 2003 RadiologicaJ Environmental Monitoring Report Aqilatic Patllway Monitoring periods of the SSES. The 2003 control mean activity is less than the averages of the annual means' for control locations for the prior operational and preoperational period of the SSES.-
Throughout the course of a year, iodine-131 is typically measured at levels in excess of analysis MDCs in some samples obtained from control surface water monitoring locations on the Susquehanna River upstream of SSES as well as indicator locations downstream of the SSES.': As determined by measurements of samples obtained by the 'SSES REMP, thernean iodine-i31 activity level from the CTBD forall of 2003 was approximately'0.78 pCilliter. This ni"ay be compared to the activity level of 0.26 pCi/liter for control surface water monitoring locations in 2003.
~
Iodine-131 from the discharge 'of medical wastes into the Susqueh,anna River upstream of the SSES is drawn into the SSES cooling tower through the SSES River Water Intake:
Stn.fcture. It is reasonable to assume' that concentration of the already existing iodine-131 in the cooling tower basins occiiis as it does for other" substances found in the'river. For example, the SSES routhielyassumes concen'trati'on factors in the basin for calcium offouT'to five times the concentrations in'th;e ri'ver' water ent~ri'rlg the basins, based 'on past measurements. :This concentrating, effect occurS because of the evaporation of the water in :the basins, ieavin'g' "
behind most dissoiv~~f and suspended materials in' the unevapornted water remaining in the basins~
concentration factor of four for iodine-24 The 2003 !mean gross beta 'aativity of ',: '
6.1 pCilliter for indicator locations' is'.', ~ i greater than the 2002 indicator mean gross beta activity of 5.4 pCilliter. The",
2003 indicator mean activity is within",r,
the range of the annual means for the ~,
previous operational period of the ' ',,;,
SSES. The 2003 mean gross beta,,;,-;
activity of 2.4,pCilliter for control "1
locations is 'Jess than the 2.9 pCi/liter ; "
forthe 2002 control mean gross beta' ;: :-'
activity. 'The 2003 control mean activity is within the range of the annual
- means for previous operational periods~' :
The 2003 control mean is bel'ow the' ':;::
range of annual means for" p~eoperati~nal periods. 'Refer to Figure 9 which trends gross beta ', ",
activitie~ separately for surface water', i'"
indjc~to~. and control,lo~ations quarter~y from 1975 thro'ugh 2003.' :;
Comparison of the 2003 indicator mean',,
(6.1 pCill)to the 2003 control mean (2.4 pCi/l) suggests a contribution of :,': I, beta activity from the SSES. The 2003 ': 'J data is similar in this regard to the ",',
averages of annual' means for indicator '
and control locations for the' prior' :', ~
operational period. 'During the prior '.":"
operatj~naI~nod, the average of,',
annmll iridic'ator means exceeds the average of annual control m'eans for " '::,~':
gross beta activity.
.', : I The 2003 means foi iridin~~131'activityi ~;
,\\
~
I'
"(
at indicator and control surface water '
monitoring location's ~~re 0.~6'pci/i!t~V' and ~)'26 pCillitei~ 'respectively., The','.,"
2003 indicator and control means 'are:':',.'.
I, 1
." '-J less than the corresponding 2002 means. '
The 2003;ipdic,at?r m~a~ ~ctivity is :, " 1 '
greater than the averages of the annual,,',
means for indicator.1ocations for the', "-'
prior operational and preoperational "f I' 2003 RadiologicaJ Environmental Monitoring Report Aqilatic Patllway Monitoring periods of the SSES. The 2003 control mean activity is less than the averages of the annual means' for control locations for the prior operational and preoperational period of the SSES.-
Throughout the course of a year, iodine-131 is typically measured at levels in excess of analysis MDCs in some samples obtained from control surface water monitoring locations on the Susquehanna River upstream of the' SSES as well as indicator locations downstream of the SSES.': As determined by measurements of samples obtained by the 'SSES REMP, thernean iodine-i31 activity level from the CTBD forall of 2003 was :, '
approximately'0.78 pCilliter. This ni"ay be compared to the activity level of 0.26 pCi/liter for control surface water monitoring locations in 2003.
~
t' 1
Iodine-131 from the discharge 'of medical wastes into the Susqueh,anna River upstream of the SSES is drawn '
into the SSES cooling tower basin's'*
through the SSES River Water Intake:
Stn.fcture. It is reasonable to assume' that concentration of the already existing iodine-131 in the cooling tower basins occiiis as it does for other",
substances found in the'river. For example, the SSES routhielyassumes concen'trati'on factors in the basin for calcium offouT'to five times the concentrations in'th;e ri'ver' water {
ent~ri'rlg the basins, based 'on past measurements. :This concentrating, '
effect occurS because of the evaporation of the water in :the basins, ieavin'g' "
behind most dissoiv~~f and suspended,
materials in' the unevapornted water remaining in the basins~ If a concentration factor of four for iodine-24
Aquatic Pat/nvav llfonitoring 131 were to be applied to the 2003 mean iodine-I31 acti~ity level for the control samples from the Susquehanna River, a mean concentration of 1.04 pCilliter for iodine-13 i itl the basin water and the water being discharged from the basi~ woul~ b~ expected The actual 2003 mean of 0.78 pCilliter for the CTBD iodine-I31 activity level was less than this.
Because iodine-131 is radioactive, unlike the calcium that hasheen measured, iodine-131 is removed from the water while it is in the baSins through the radioactive decay process, Thus, it might be expected ihat the net concentration factor for iodine-131 would be somewhat less than that for calcium, considering'this additional removal process. The extent to which the iodine-I31 concentration factor is less than that for calcium would depend on the mean residence time for the water in the basins compared to iodine-131 's radioactive hat'f-life - the greater the ratio of the mean residence time to the half-life, the smaller the concentration factor. A mean residence time for water in the basins is expected to be about two days, This is only about one-fourth of the approximately eight-day half-life of iodine-13l," Thus, radioactive decay wO,uld ri~~ be :
expected to reduce the concentration factor for iodine-I3I by a large amount.
Therefore, the difference between the 2003 mean jodine~ 131 activity of about 0,78 pCi/liter in the CTBD and the 2003 mean iodiIie-131 activity for the control location of 0.26' pCilliter sliould be the result of concentration in the basins.
Iodine-I31 was "not reported to have been discharged with water released 2S from the SSES to the Susquehanna River during 2003.
The 2003 mean tritium activity for indicator locations is more than the corresponding,2002 mean. The 2003 means for tritium activity at indicator and contr-ollocations were 1,567 pCilliter and 31.8 pCi/liter, respectively,',The2003 indicator mean is greater than the annual average mean for prior operational and preoperational periods of the SSES. Note that the 2003 mean tritium activity at indicator locations i~ higher than the range for both operational and preoperational periods. The control mean is within the range of the corresponding annual mean reported for the prior operational period of the SSES. Refer to Figure 10 which trends tritium activity levels separately for surface water indicator and control locations from 1972 through 2003.
The 2003 indicator mean tritium level for all surface water locations can be misleading for those interested in the mean tritium l<:vel in the Susquehanna River downstream of the SSES for 2003. The much higher levels of tritium observed in the CTBD line (location 2S7/6S7), when averaged with the low levels from the downstream location 6S5 sample analysis results distort the real environmental picture. The mean tritium activity level from indicator location 6S5 for 2003 was 140 pCilliter, which is greater than the mean tritium activity, 31.8 pCiIliter, for the control location, but is within the range of prior operational' and preoperational periods.
In spite of the fact that the tritium activity levels reported for 2S7/6S7 are from the discharge line prior to dilution 2003 Radiological Environmental Monitoring Report I I I
~
Aquatic Pat/nvav llfonitoring 131 were to be applied to the 2003 mean iodine-I31 acti~ity level for the control samples from the Susquehanna River, a mean concentration of 1.04 pCilliter for iodine-13 i itl the basin water and the water being discharged from the basi~ woul~ b~ expected.. The actual 2003 mean of 0.78 pCilliter for the CTBD iodine-I31 activity level was less than this.
Because iodine-131 is radioactive, unlike the calcium that hasheen measured, iodine-131 is removed from the water while it is in the baSins through the radioactive decay process, Thus, it might be expected ihat the net concentration factor for iodine-131 would be somewhat less than that for calcium, considering'this additional removal process. The extent to which the iodine-I31 concentration factor is less than that for calcium would depend on the mean residence time for the water in the basins compared to iodine-131 's radioactive hat'f-life - the greater the ratio of the mean residence time to the half-life, the smaller the concentration factor. A mean residence time for water in the basins is expected to be about two days, This is only about one-fourth of the approximately eight-day half-life of iodine-13l," Thus, radioactive decay wO,uld ri~~ be :
expected to reduce the concentration factor for iodine-I3I by a large amount.
Therefore, the difference between the 2003 mean jodine~ 131 activity of about 0,78 pCi/liter in the CTBD and the 2003 mean iodiIie-131 activity for the control location of 0.26' pCilliter sliould be the result of concentration in the basins. '
Iodine-I31 was "not reported to have been discharged with water released 2S from the SSES to the Susquehanna River during 2003.
The 2003 mean tritium activity for indicator locations is more than the corresponding,2002 mean. The 2003 means for tritium activity at indicator and contr-ollocations were 1,567 pCilliter and 31.8 pCi/liter, respectively,',The2003 indicator mean is greater than the annual average mean for prior operational and preoperational periods of the SSES. Note that the 2003 mean tritium activity at indicator locations i~ higher than the range for both operational and preoperational periods. The control mean is within the range of the corresponding annual mean reported for the prior operational period of the SSES. Refer to Figure 10 which trends tritium activity levels separately for surface water indicator and control locations from 1972 through 2003.
The 2003 indicator mean tritium level for all surface water locations can be misleading for those interested in the mean tritium l<:vel in the Susquehanna River downstream of the SSES for 2003. The much higher levels of tritium observed in the CTBD line (location 2S7/6S7), when averaged with the low levels from the downstream location 6S5 sample analysis results distort the real environmental picture. The mean tritium activity level from indicator location 6S5 for 2003 was 140 pCilliter, which is greater than the mean tritium activity, 31.8 pCiIliter, for the control location, but is within the range of prior operational' and preoperational periods.
In spite of the fact that the tritium activity levels reported for 2S7/6S7 are from the discharge line prior to dilution 2003 Radiological Environmental Monitoring Report I I I
~
in the river, the highest quarterly average tritium actiVity'reported at 2S7/6S7 during 2003 was' approximately 6,990 pCilliter for the, first quarter, well below the NRC non-routine reporting levels for quarterly average activity levels of 20,000' pCiIliter when a dnnking water pathway' exists or 30,000 pCiniter wh'en no drinking water pathway exists:
The tritium activity reported in the CTBD line from location 2S'7/6S7 attributable to the SSES. Refer to the "Dose from the Aquatic Pathway" discussion at the end of this section for' additional iriformation' on the dose 'to 'the population from tritium 'and' other radionuclides in the aquatic pathway attributableto'the SSES.
With the following exceptions, no gamina-errutting radion~clides were' measured in surface water primary samples at an activity level exceeding an analysis MDC in 2003: potassium-40 and iodine-I3l.
Drinlf,i~g' Water Drinking' water was monitored during 2003 at the' Danville Water CompanY's il facility '26 miles'WSW ofth~ SSES on'~'
the SusquehaiUia River. From (when dritlking'water samples'\\vere first' collected) thi-oughJ 984;driIild~g water' samples were' also obtained from BerWickWater 12F3; s;i'riiiies WSW 'Of the' The drinking water supply for the:
- ~
BeiwickWater Company is however, :wilierfroiftihe Susquehanna:
River; it is actually well water,"
t~.~
~.~.
There are'noknow~ drinking water supplies in Pennsylvania on the' 2003 Radiologieal Environmental Monitoring Report Aquatic PathlVa)~ Monitoring Susquehanha ruver upstream of the SSES.and th~iefore n~ drinking water control monitoring locations. Danville' drinking water analysis results may be compared to the results for surface water control monitoring locations.
Results from specific sample analyses of drinking water may pe found in Table 1-4 of Appendix I. A summary of the 2003 drinking water data niay be located in Table G of AppendixG~
Co~parisons of 2003 'f!lonitoririg results with those, of past years may be found in Tables HS through H 7 of Ap~~~dix Gross alpha activity has been monitor~d in'drinking water since 1980. 'Gross alpha activity has ~een ob~erved at levels above the analysis'MDCs in a small minority of the samples during most years since 1980. The 2003 'mean gross alpha activity level for,drlnldng water was 0.18 pCiniter. The 2003.
mean alpha activity level is within the range of the corresponding annual means fo'r the prior operational years.
No gross alpha activity'in dnnking water during '2003 is attributed to liquid discharges from theSSES to'the' Gross beta activity has been monitored' in diinking water since i 977. 'Gross beta activity is' typically ineasurc'd at levels exceeding the MDCs in'drinking water samples~ The 2003 mean gross beta activityievel for'driflking water" was 2J3 'pcilliter~ The 2003 mean'is' belO\\y the 2002 'mean gross beta activity level for drinking water but\\viihin range of the corresponding: annual means for prior operational periods.
The 2003 mean is below the range of the 'corresponding annual 26
,.',:-.I ~.' r,
~
in the river, the highest quarterly average tritium actiVity'reported at 2S7/6S7 during 2003 was' approximately 6,990 pCilliter for the, '
first quarter, well below the NRC non- '
routine reporting levels for quarterly '--..
average activity levels of '
- i';,
20,000' pCiIliter when a dnnking water '
pathway' exists or 30,000 pCiniter wh'en no drinking water pathway exists:.'
The tritium activity reported in the CTBD line from location 2S'7/6S7 is,'*;
attributable to the SSES. Refer to the "Dose from the Aquatic Pathway",
j 'r:
discussion at the end of this section for' additional iriformation' on the projected" dose 'to 'the population from tritium 'and' other radionuclides in the aquatic ::',
pathway attributableto'the SSES.
'; "I With the following exceptions, no gamina-errutting radion~clides were' "
measured in surface water primary samples at an activity level exceeding "
an analysis MDC in 2003: potassium-40 and iodine-I3l.
.*.. t;.
Drinlf,i~g' Water Drinking' water was monitored during, :
2003 at the' Danville Water CompanY's il facility '26 miles'WSW ofth~ SSES on'~'
the SusquehaiUia River. From 1977:;-:'
(when dritlking'water samples'\\vere first' collected) thi-oughJ 984;driIild~g water' samples were' also obtained from the':' ':
BerWickWater Companyatlocation':' J' 12F3; s;i'riiiies WSW 'Of the' SSES.'!'.',"
The drinking water supply for the:
' :~.. (!
BeiwickWater Company is not," " ",. i' however, :wilierfroiftihe Susquehanna: :",
River; it is actually well water,"
":-:r,l' t~.~
~.~.
',':ttur There are'noknow~ drinking water <"
supplies in Pennsylvania on the', ',,; : ~I' 2003 Radiologieal Environmental Monitoring Report
-- Aquatic PathlVa)~ Monitoring Susquehanha ruver upstream of the SSES.and th~iefore n~ drinking water control monitoring locations. Danville' drinking water analysis results may be compared to the results for surface I'
water control monitoring locations.
Results from specific sample analyses of drinking water may pe found in Table 1-4 of Appendix I. A summary of the 2003 drinking water data niay be,"
located in Table G of AppendixG~,
Co~parisons of 2003 'f!lonitoririg results with those, of past years may be found in Tables HS through H 7 of Ap~~~dix H.'
Gross alpha activity has been monitor~d in'drinking water since 1980. 'Gross '
alpha activity has ~een ob~erved at levels above the analysis'MDCs in a small minority of the samples during most years since 1980. The 2003 'mean '
gross alpha activity level for,drlnldng ",
water was 0.18 pCiniter. The 2003.
mean alpha activity level is within the range of the corresponding annual means fo'r the prior operational years.
No gross alpha activity'in dnnking water during '2003 is attributed to liquid discharges from theSSES to'the' Susquehanna'River',
Gross beta activity has been monitored' in diinking water since i 977. 'Gross beta activity is' typically ineasurc'd at '
levels exceeding the MDCs in'drinking :
water samples~ The 2003 mean gross beta activityievel for'driflking water" was 2J3 'pcilliter~ The 2003 mean'is' belO\\y the 2002 'mean gross beta activity level for drinking water but\\viihin the':,
range of the corresponding: annual ' ','
means for prior operational periods.
The 2003 mean is below the range of the 'corresponding annual 'means for' 26
Aqllatic PatltHJayMonitoring preoperational peJiods. ~efer to Figure II, w~ich trerds gross beta activity levels separately for drinking water indicator arid coritrollocations from 1977 through '2003~ No gross beta activity in drinking water during 2003 is attributed to liquid discharges from the SSES to the Susquehanna River.
Iodine-I31 was measured in excess of analysis MDCs in 2 out of26~rinking water samples in 2003. This compares with results from 6 samples for which analysis MDCs ~ere ex'ceeded in 2002.
The 2003 mean iodine-I31 activity level in drinking water samples was 0.18 pCiIliter. This isJess than the 2002 mean drinking water activity level of 0.22 pCilJiter. Also, it is less than the 2003 mean of 0.26 pCiJliter for the surface water control location. No iodine-I3l activity in drinking water during 2003 is attributed to liquid discharges from'the SSES to the Susquehanna River.
Tritium was measured in excess of analysis MDC~ twice in 2003 in, drinking water., The 2003 mean tritium activity level for'drinking water was 62 pCiJliter. The 2003 me~ is equal to the averages of the corresponding annual means for both the prior operational and preoperational periods of the SSES. The 2003 mean tritium activity level for driIlking water is higher than the 2003 mean tri~ium activity level for the surface w~ter control location. ' Tritium activity in drinking water can be attributed to liquid discharges from the SSES to the Susquehanna River.
With the exception ofI~13.I, no gamma-emitting radionudides were, measured 27 above the analysis MDCs for gamma spectroscopic analyses of drinking water samples during 2003.
Fish Results from specific sampJe analyses of fish may be found in Table I 5 of Appendix I. A summary of the 2003 fish data may be located in Table G of Appendix G.. A comparison of2003 monitoring results with those of past years may be found in Table H 8 of Appendix H.
Three species of fish wer,? sampled at each of one indicator location and one control location on the Susquehanna River in May 2003 and again in October 2003. The species included the following: smallmouth bass, channel catfish, shorthead redhorse, 'and white sucker. In addition, one largemouth bass was sampled from PPL's LTAW.
A total of 13 fish were collected and analyzed.
The only gamma-emitting radionuclide reported in excess of analysis MDCs in fish during 2003 was naturally occurring potassium-40. The 2003 indicator and control means for the activity levels of potassium-40 in fish were 3.57 pCiJgram and 3.16 pCi/gram, respectively. The 2003 indicator and control means were less than the 2002 means. Both the 2003 indicator and control me~ns are within the ranges of their corresponding annual means for prior operational years. The 2003 indicator mean is greater, than the range of corresponding anIlUal means for preoperational periods. !he 2003 control mean is within the range of corresponding annual means for preoperational periods. Naturally 2003 Radiological Envir~nmental Monitoring Report Aqllatic PatltHJayMonitoring preoperational peJiods. ~efer to Figure II, w~ich trerds gross beta activity levels separately for drinking water indicator arid coritrollocations.
from 1977 through '2003~ No gross beta activity in drinking water during 2003 is attributed to liquid discharges from the SSES to the Susquehanna River.
Iodine-I31 was measured in excess of analysis MDCs in 2 out of26~rinking water samples in 2003. This compares with results from 6 samples for which analysis MDCs ~ere ex'ceeded in 2002.
The 2003 mean iodine-I31 activity level in drinking water samples was 0.18 pCiIliter. This isJess than the 2002 mean drinking water activity level of 0.22 pCilJiter. Also, it is less than the 2003 mean of 0.26 pCiJliter for the surface water control location. No iodine-I3l activity in drinking water during 2003 is attributed to liquid discharges from'the SSES to the Susquehanna River.
Tritium was measured in excess of analysis MDC~ twice in 2003 in, drinking water., The 2003 mean tritium activity level for'drinking water was 62 pCiJliter. The 2003 me~ is equal to the averages of the corresponding annual means for both the prior operational and preoperational periods of the SSES. The 2003 mean tritium activity level for driIlking water is higher than the 2003 mean tri~ium activity level for the surface w~ter control location. ' Tritium activity in drinking water can be attributed to liquid discharges from the SSES to the Susquehanna River.
With the exception ofI~13.I, no gamma-emitting radionudides were, measured 27 above the analysis MDCs for gamma spectroscopic analyses of drinking water samples during 2003.
Fish Results from specific sampJe analyses of fish may be found in Table I 5 of Appendix I. A summary of the 2003 fish data may be located in Table G of Appendix G.. A comparison of2003 monitoring results with those of past years may be found in Table H 8 of Appendix H.
Three species of fish wer,? sampled at each of one indicator location and one control location on the Susquehanna River in May 2003 and again in October 2003. The species included the following: smallmouth bass, channel catfish, shorthead redhorse, 'and white sucker. In addition, one largemouth bass was sampled from PPL's LTAW.
A total of 13 fish were collected and analyzed.
The only gamma-emitting radionuclide reported in excess of analysis MDCs in fish during 2003 was naturally occurring potassium-40. The 2003 indicator and control means for the activity levels of potassium-40 in fish were 3.57 pCiJgram and 3.16 pCi/gram, respectively. The 2003 indicator and control means were less than the 2002 means. Both the 2003 indicator and control me~ns are within the ranges of their corresponding annual means for prior operational years. The 2003 indicator mean is greater, than the range of corresponding anIlUal means for preoperational periods. !he 2003 control mean is within the range of corresponding annual means for preoperational periods. Naturally 2003 Radiological Envir~nmental Monitoring Report
occuning 'p~tassium-40 in fish is attributable to the liquid discharges from the SSES to the Susquehanna' River Sedilllellt Shoreline sediment was sampled in May 2003 and again in October 2003.
Results from specific sample analyses of sediment may be found in Table 1-6 ~.
of Appendix 1. A summary of the 2003 sediment data is located in Table G or, Appendix G. Comparisons of 2003 monitoring results with those of past years may be found in Tables H 9 through H 12 of Appendix H.
Naturally occuning potassium-40, radium-226, and thorium-228 were measured at activity levels above analysis MDCs in aU shoreline sediment samples in 2003.
The 2003 indicator and control means for potassium-40 activity levels. in
. shoreline sediment were 12.3 pCi/gram and 12.9 pCilgram,. respectively. :The 2003 indicator mean for potassium-40 activity is less than the corresponding 2002 mean. The 2003 control mean is greater than the corresponding' 2002 mean. The 2003 indicator and control means were within the ranges of corresponding annual means for all prior operational years.
The 2003 indicator and control means were greater than the ranges of corresponding means for preoperational periods.
The 2003 indicator and control means for radium-226 activity levels in shoreline sediment were 2.38 pCi/gram and 1.6 pCi/gram, respectively. The 2003 indicator mean radium-226 activity is higher than the corresponding 2003 Radiological EnYironmental Monitoring Report Aquatic Pathway Afonitoring 2002 meari.. The 2003 controf mean radium-226 activity is lower than the corresponding 2002 means. The 2003 radium":226 mean was above the range of corresponding annual means for all prior operational years. The 2003 control mean was within the range of corresponding annual means for all prior operational years.
The 2003 indicator and control means for thorium-228 activity levels in shoreline sediment were 3.2 and 3.0 pCi/gram, respectively. The 2003 indicator and control means are higher than the corresponding 2002 means.
The 2003 indicator and control means are greater than the range of corresponding means for prior operational years. The naturally occuning radionuclides in sediment discussed above are not attributable to the liquid discharges from the SSES to.
the Susquehanna River..
Cesium-137 was measured at activity levels in shoreline sediment exceeding analysis MDCs in 5 of 6 analyses during 2003. The 2003 indicator and control means for cesium-137 activity levels in sediment were 0.07 pCi/gram and 0.08 pCi/gram, respectively. The 2003 indicator mean is greater than the corresponding 2002 mean.. The 2003 control mean is less 'than the corresponding 2002 mean. The 2003 indicator and control means are Jess than the average of corresponding annual means for both prior operational as well as preoperational years. 'The' cesium-137 in sediment is attributed to residual fa110ut from past atmospheric nuclear weapons tests.
28 occuning 'p~tassium-40 in fish is not,*.
attributable to the liquid discharges,,;.
from the SSES to the Susquehanna'.
River..
Sedilllellt Shoreline sediment was sampled in May 2003 and again in October 2003.
Results from specific sample analyses of sediment may be found in Table 1-6 ~.
of Appendix 1. A summary of the 2003 sediment data is located in Table G or,.
Appendix G. Comparisons of 2003.,;
monitoring results with those of past years may be found in Tables H 9 through H 12 of Appendix H.
I Naturally occuning potassium-40, radium-226, and thorium-228 were.
measured at activity levels above analysis MDCs in aU shoreline sediment samples in 2003.
The 2003 indicator and control means for potassium-40 activity levels. in
. shoreline sediment were 12.3 pCi/gram and 12.9 pCilgram,. respectively. :The 2003 indicator mean for potassium-40 activity is less than the corresponding 2002 mean. The 2003 control mean is greater than the corresponding' 2002 mean. The 2003 indicator and control means were within the ranges of corresponding annual means for all prior operational years.
The 2003 indicator and control means were greater than the ranges of corresponding means for preoperational periods.
The 2003 indicator and control means for radium-226 activity levels in shoreline sediment were 2.38 pCi/gram and 1.6 pCi/gram, respectively. The 2003 indicator mean radium-226 activity is higher than the corresponding 2003 Radiological EnYironmental Monitoring Report Aquatic Pathway Afonitoring 2002 meari.. The 2003 controf mean radium-226 activity is lower than the corresponding 2002 means. The 2003 radium":226 mean was above the range of corresponding annual means for all prior operational years. The 2003 control mean was within the range of corresponding annual means for all prior operational years.
The 2003 indicator and control means for thorium-228 activity levels in shoreline sediment were 3.2 and 3.0 pCi/gram, respectively. The 2003 indicator and control means are higher than the corresponding 2002 means.
The 2003 indicator and control means are greater than the range of corresponding means for prior operational years. The naturally occuning radionuclides in sediment discussed above are not attributable to the liquid discharges from the SSES to.
the Susquehanna River..
Cesium-137 was measured at activity levels in shoreline sediment exceeding analysis MDCs in 5 of 6 analyses during 2003. The 2003 indicator and control means for cesium-137 activity levels in sediment were 0.07 pCi/gram and 0.08 pCi/gram, respectively. The 2003 indicator mean is greater than the corresponding 2002 mean.. The 2003 control mean is less 'than the corresponding 2002 mean. The 2003 indicator and control means are Jess than the average of corresponding annual means for both prior operational as well as preoperational years. 'The' cesium-137 in sediment is attributed to residual fa110ut from past atmospheric nuclear weapons tests.
28
Aquatic Pathway Monitoring Dose from the Aquatic Pathway Tritium was the only radionuclide identified in 2003 by the SSES REMP in the aquatic pathway that was attributable to SSES operation and also included in the pathway to man.
The total tritium activity released from the SSES for the year was estimated based on REMP monitoring results for use in projecting maximum doses to the public. This estimate assumed that the tritium was present continuously in the CTBD line throughout 2003 at a level equivalent to,the annual mean activity level of tritium. It was also assumed that the annual average activity level of tritium being contributed to the Susquehanna River water could be represented by the difference between the annual mean activity levels of tritium in the CTBD line (without correction for cooling tower basin reconcentration) and in the river upstream of the SSES.
The annual mean activity level of tritium in the CTBD line (monitoring location 2S7\\6S7) for 2003 was 4,416 pCiIl. The annual mean activity level for the river upstream of the SSES (monitoring location 6S6) was approximately 32 pCill. Thus, the difference in the mean activity levels for these two locations was about 4,384 pCi/I. The annual mean flow rate for the CTBD line was 7,703 gpm.
Using the proper unit conversions and mUltiplying 7,703 gpm times 4,384 pCiIl yields a value,of 67.2 curies for the estimate of tritium released during 2003 based on the results of radiological environmental monitoring.
29 This estimate is 3 curies less than the amount of tritium determined by effluent monitoring to have been released to the river by the SSES in 2003. This agreement between the estimate based on environmental monitoring and the amount reported by effluent monitoring is consistent with previous years comparisons.
Given the total tritium activity released, the maximum whole-body and organ doses to hypothetical exposed individuals in four age groups (adult, teenager, child, and infant) were determined according to the methodology of the Offsite Dose Calculation' manual using the RETDAS computer program. This is in accordance with SSES Technical Requirement 3.11.4.1.3.
The maximum dose obtained from the ingestion of tritium was estimated at the nearest downriver municipal water supplier via the drinking water pathway and near the outfall of the SSES discharge to the Susquehanna River via the fish pathway. The maximum whole body and organ doses were each estimated to be approximately 0.0015 mrem.
2003 Radiological Environmental Monitoring Report I *
,.J Aquatic Pathway Monitoring Dose from the Aquatic Pathway Tritium was the only radionuclide identified in 2003 by the SSES REMP in the aquatic pathway that was attributable to SSES operation and also included in the pathway to man.
The total tritium activity released from the SSES for the year was estimated based on REMP monitoring results for use in projecting maximum doses to the public. This estimate assumed that the tritium was present continuously in the CTBD line throughout 2003 at a level equivalent to,the annual mean activity level of tritium. It was also assumed that the annual average activity level of tritium being contributed to the Susquehanna River water could be represented by the difference between the annual mean activity levels of tritium in the CTBD line (without correction for cooling tower basin reconcentration) and in the river upstream of the SSES.
The annual mean activity level of tritium in the CTBD line (monitoring location 2S7\\6S7) for 2003 was 4,416 pCiIl. The annual mean activity level for the river upstream of the SSES (monitoring location 6S6) was approximately 32 pCill. Thus, the difference in the mean activity levels for these two locations was about 4,384 pCi/I. The annual mean flow rate for the CTBD line was 7,703 gpm.
Using the proper unit conversions and mUltiplying 7,703 gpm times 4,384 pCiIl yields a value,of 67.2 curies for the estimate of tritium released during 2003 based on the results of radiological environmental monitoring.
29 This estimate is 3 curies less than the amount of tritium determined by effluent monitoring to have been released to the river by the SSES in 2003. This agreement between the estimate based on environmental monitoring and the amount reported by effluent monitoring is consistent with previous years comparisons.
Given the total tritium activity released, the maximum whole-body and organ doses to hypothetical exposed individuals in four age groups (adult, teenager, child, and infant) were determined according to the methodology of the Offsite Dose Calculation' manual using the RETDAS computer program. This is in accordance with SSES Technical Requirement 3.11.4.1.3.
The maximum dose obtained from the ingestion of tritium was estimated at the nearest downriver municipal water supplier via the drinking water pathway and near the outfall of the SSES discharge to the Susquehanna River via the fish pathway. The maximum whole body and organ doses were each estimated to be approximately 0.0015 mrem.
2003 Radiological Environmental Monitoring Report I *
,.J
pCi/Liter FIGURE 9 - GROSS BETA ACTIVITY IN SURFACE WATER 20 ~----------------------------------------------------------------~
18 PRE OPERA TIONAL OPERATIONAL 16 14 12 10 8
6 4
2 o+-----------------~--------------------------------------~------~
-2
-4 +-~~~~--~~~_r~~--~~~~~--~~~~~~--~~~~~~--~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
Indicator -
Control Gl, pCi/Liter FIGURE 9 - GROSS BETA ACTIVITY IN SURFACE WATER 20 ~----------------------------------------------------------------~
18 PRE OPERA TIONAL OPERATIONAL 16 14 12 10 8
6 4
2 o+-----------------~--------------------------------------~------~
-2
-4 +-~~~~--~~~_r~~--~~~~~--~~~~~~--~~~~~~--~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
Indicator -
Control Gl,
FIGURE 10 - TRITIUM ACTIVITY IN SURFACE WATER pCi/Liter 3000 ~----------------------~--------------------------------~------------.
2500 2000 1500 1000 500 PREOPERATIONAL OPERATIONAL Unit2 Criticality
~
-500 +-~~~~~~--~~~~-r~~~~~~~~~~~~~--~~~~~~~~~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
Indicator Control
)
FIGURE 10 - TRITIUM ACTIVITY IN SURFACE WATER pCilLiter 3000 ~----------------------~--------------------------------~------------.
2500 2000 1500 1000 500 PREOPERATIONAL OPERATIONAL Unit2 Criticality
~
-500 +-~~~~~~--~~~~-r~~~~~~~~~~~~~--~~~~~~~~~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
Indicator Control
)
c c
FIGURE 11 - GROSS BETA ACTIVITY IN DRINKING WATER c
pCilLitcr 10~------------~~--------------------------------------------------~
9 PREOPERATIONAL OPERATIONAL 8
7 6
5 Unltl 4
3 2
1 O+-~~--~~-r~~~~-r~--~~-T--~~~~--~~~~--~~-T~~~~
f\\'\\
~
c c
FIGURE 11 - GROSS BETA ACTIVITY IN DRINKING WATER c
pCilLitcr 10~------------~~--------------------------------------------------~
9 PREOPERATIONAL OPERATIONAL 8
7 6
5 Unltl 4
3 2
1 O+-~~--~~-r~~~~-r~--~~-T--~~~~--~~~~--~~-T~~~~
f\\'\\
~
Atmospheric Pathway Monitoring INTRODUCTION Atmospheric. monitoring by th.e SSES" REMP involves the sampling and, analysis of air. Because ihe air is the first medium that SSES vent releases enter in the pathway to man, it is
.;~
fundamenta1 that it be monitored.
Mechanisms do exist for the transport of airborne contaminants to other media' and their concentration in them.
examp1e, airborne contaminants move to the'terrestrial environment concentrate in milk. Concentrations radionuclides can make the sampling, and analysis:ofmedi,a like ~lkmore' sensitive approaches for the detection o~.
radionuclides, such as iodine-131: in the pathway t<? man than the monitoring ~fiA',
air directly. : (PPL also samples milk; refer to the Terrestrial Pathway,
Monitoring section of this report~)
Nevertheless, the sensitivity of air monitoring can be optimized by the proper selection of sampling te~hnique~
and the choice of the proper types analyses for the collected samples.
Scope Air samples were col1ected on particulate filters and charcoa1,
cartridges at indicator locations 3S2, 12S1, 13S6 and 12El. and control' locations 6Gl and 2003 Radiological Environmental Monitoring Report Samplintfand 'Analysis Air' The 'SSES REMP monitored the air at fo~r indicator locations and two control locations during' 2003. The SSES Tech~ic~i ~equirements require.
monitoring afonly a total of five site~.
Monitoring is' require~. at three locations, at the SSES'site'boundaryin different sectorS 'with 'the greatest pre~icted sensitivities for the'detection of SSES releases. M~nitoring must bepefforI,ned at the community'in the 'vicinity of the SSES with the greatest pre,dicted sensitivity. A controllocati0!l that is expected to be umiffe~ted by a~yroutine(
SSES releases must be mon~tored.
Airborne parti~uhites ~ere~~llected on glass fiber filters' using low volume, (typically 2.0 to 2.5 cfm 'sampling rates) air ~amplers that run continuously. Air iodine samples were collected on' charcoa1 cartridges, placed downstream of the particulate filters:
Particulate filters and charcoal cartridges were exchanged weekly at the, air monitoring sites. SampHng were reco~ded 'o~\\elapsed-tirrie meters.
Air sample :v,?lti~es fo~ p~i~ul~te filters and charcoal cartridges wer~
measured with dry-gas meterS.
~.
Air fillers~ere anhlyzed weekly'for gross beta 'activity., then composi,ted quarter1y and ~mi,lyzed for the ~cti~ities of g'amma-einitthlg'radionuclide~. The, charcoal cartridges were analyz(!d weekly for iodine-131.
33 Atmospheric Pathway Monitoring INTRODUCTION t
'if Atmospheric. monitoring by th.e SSES" ~ "
REMP involves the sampling and, !ji:,
analysis of air. Because ihe air is the first medium that SSES vent releases
{" I enter in the pathway to man, it is
.;~. i fundamenta1 that it be monitored.
Mechanisms do exist for the transport i.,"
of airborne contaminants to other media' and their concentration in them. For'.. :.
examp1e, airborne contaminants may,':,';
move to the'terrestrial environment and,.
concentrate in milk. Concentrations of'...,
radionuclides can make the sampling, d,
and analysis:ofmedi,a like ~lkmore'.;;',
sensitive approaches for the detection o~.
radionuclides, such as iodine-131: in the pathway t<? man than the monitoring ~fiA',
air directly. : (PPL also samples milk;,;.,.
refer to the Terrestrial Pathway,
Monitoring section of this report~)
,.,:},
Nevertheless, the sensitivity of air monitoring can be optimized by the, '
proper selection of sampling te~hnique~ ',:'
and the choice of the proper types of,..:,.,
analyses for the collected samples. "
Scope
'j Air samples were col1ected on '",
particulate filters and charcoa1,
cartridges at indicator locations 3S2, 12S1, 13S6 and 12El. and control' ':,.., I locations 6Gl and 8Gl.*
,.-- -," 'r: ;,'
2003 Radiological Environmental Monitoring Report Samplintfand 'Analysis Air' The 'SSES REMP monitored the air at.,
fo~r indicator locations and two control locations during' 2003. The SSES Tech~ic~i ~equirements require.
monitoring afonly a total of five site~.,
Monitoring is' require~. at three locations, at the SSES'site'boundaryin different sectorS 'with 'the greatest pre~icted.
sensitivities for the'detection of SSES releases. M~nitoring must bepefforI,ned at the community'in the 'vicinity of the SSES with the greatest pre,dicted sensitivity. A controllocati0!l that is expected to be umiffe~ted by a~yroutine(
SSES releases must be mon~tored.
Airborne parti~uhites ~ere~~llected on glass fiber filters' using low volume, '
(typically 2.0 to 2.5 cfm 'sampling rates) air ~amplers that run continuously. Air iodine samples were collected on' charcoa1 cartridges, placed downstream of the particulate filters:.
Particulate filters and charcoal cartridges were exchanged weekly at the, air monitoring sites. SampHng times', '
were reco~ded 'o~\\elapsed-tirrie meters. '
Air sample :v,?lti~es fo~ p~i~ul~te ",' "
filters and charcoal cartridges wer~
measured with dry-gas meterS.
- ~.
Air fillers~ere anhlyzed weekly'for '
gross beta 'activity., then composi,ted quarter1y and ~mi,lyzed for the ~cti~ities of g'amma-einitthlg'radionuclide~. The, charcoal cartridges were analyz(!d weekly for iodine-131.
33
Atmospheric Pathway Monitoring Monitoring Results Air Particulates Gross beta activity is always measured at levels in excess of the analysis MDCs on the fiber fi)ters. The highest gross beta activity levels that have been measured during the operational period of the SSES were obtained in' i986 following the Chemobyl accident in the former Soviet Union. Figure 12 trends the quarterly mean gross beta' activities for the indicator and control locations separately from 1~14 throutih 2003.
Note that prior to SSES operation, before 1982, the unusually high gross beta activities were generally attributable to faJlout from atmospheric nuclear weapons tests. Typical gross beta activities measured on air particulate filters are the result of naturally occurring radionucHdes associated with dust particles suspended in the sampled air. They are thus terrestrial in origin.
Particulate gross beta activity levels for each monitoring location and monitoring period in 2003 are presented in Table 1-8 of Appendix I.
Comparisons of 2003 gross beta analysis results with those of previous years may be found in Table H 13 of Appendix H. For 2003, the annu'al means for the beta activities of the indicator and control locations are 1.47E-2 pCilm3 and 1.34E-2 pCilm3, respectively. These are near the low end of the corresponding ranges of previous operational yearly av~rages. They are significantly below the corresponding lower ends of their preoperational yearly averages. A contribution of radioactivity from the SSES may be suggested from the 2003 airborne gross beta data based 34 on the higher mean activity reported for indicator location.
The SSES Technical Requirements Manual requires radionuclide analysis if any weekly gross beta result was greater than ten times the yearly mean of control sample results. This condition did not oc~ur during 2003.
Quarterly gamma spectroscopic measurements of composited filters often show the naturally occurring radionuclide beryHium-7. Occasionally.
other naturally occurring radionuclides potasstum-40 and radtum-226, are also observed. ~ery1lium-7 is cosmogenic in origin, being produced by the interaction of cosmic radiation with the earth's atmosphere. The other two gamma-emitting radionucIides originate from soil and rock.
BeryHium-7 was measured above analysis MDCs fO,r all quarterly composite samples in 2003. The 2003 indicator and control means for beryllium-7 activity were 9.IOE-2 pCi/m3, and 8.20E-2 pCi/m3, respectively. The 2003 means are lower than the corresponding 2002 means.
The 2003 iridicator and control means were lower than the averages of the corresponding annual means for the prior operational and preoperational periods. BerylJium-7 activity levels for each 2003 calendar quarter at each monitoring location are presented in Table 1-9 of Appendix I. Comparisons of 2003 beryIlium-7 analysis results with previous years m'ay be found in Table H 14 of Appendix H. Potassium-40 was measured above analysis MDCs for one quarterly composite sample during 2003 (control location 6Gl).
2003 Radiological Environmental Monitoring Report Atmospheric Pathway Monitoring Monitoring Results Air Particulates Gross beta activity is always measured at levels in excess of the analysis MDCs on the fiber fi)ters. The highest gross beta activity levels that have been measured during the operational period of the SSES were obtained in' i986 following the Chemobyl accident in the former Soviet Union. Figure 12 trends the quarterly mean gross beta' activities for the indicator and control locations separately from 1~14 throutih 2003.
Note that prior to SSES operation, before 1982, the unusually high gross beta activities were generally attributable to faJlout from atmospheric nuclear weapons tests. Typical gross beta activities measured on air particulate filters are the result of naturally occurring radionucHdes associated with dust particles suspended in the sampled air. They are thus terrestrial in origin.
Particulate gross beta activity levels for each monitoring location and monitoring period in 2003 are presented in Table 1-8 of Appendix I.
Comparisons of 2003 gross beta analysis results with those of previous years may be found in Table H 13 of Appendix H. For 2003, the annu'al means for the beta activities of the indicator and control locations are 1.47E-2 pCilm3 and 1.34E-2 pCilm3, respectively. These are near the low end of the corresponding ranges of previous operational yearly av~rages. They are significantly below the corresponding lower ends of their preoperational yearly averages. A contribution of radioactivity from the SSES may be suggested from the 2003 airborne gross beta data based 34 on the higher mean activity reported for indicator location.
The SSES Technical Requirements Manual requires radionuclide analysis if any weekly gross beta result was greater than ten times the yearly mean of control sample results. This condition did not oc~ur during 2003.
Quarterly gamma spectroscopic measurements of composited filters often show the naturally occurring radionuclide beryHium-7. Occasionally.
other naturally occurring radionuclides potasstum-40 and radtum-226, are also observed. ~ery1lium-7 is cosmogenic in origin, being produced by the interaction of cosmic radiation with the earth's atmosphere. The other two gamma-emitting radionucIides originate from soil and rock.
BeryHium-7 was measured above analysis MDCs fO,r all quarterly composite samples in 2003. The 2003 indicator and control means for beryllium-7 activity were 9.IOE-2 pCi/m3, and 8.20E-2 pCi/m3, respectively. The 2003 means are lower than the corresponding 2002 means.
The 2003 iridicator and control means were lower than the averages of the corresponding annual means for the prior operational and preoperational periods. BerylJium-7 activity levels for each 2003 calendar quarter at each monitoring location are presented in Table 1-9 of Appendix I. Comparisons of 2003 beryIlium-7 analysis results with previous years m'ay be found in Table H 14 of Appendix H. Potassium-40 was measured above analysis MDCs for one quarterly composite sample during 2003 (control location 6Gl).
2003 Radiological Environmental Monitoring Report I I
No other gamma-emitting radionucHdes were reported for air in 2003.
Beryllium-7 and potassium-40 are not attributable to SSES operation.
.1 Air Iodine Iodine-131 has been detected infrequently from 1976, when it was first monitored, through 2003. Since operation of the SSES began in 1982, iodine-131 has only been positively detected in air samples in 1986 due to the Chemobyl accident. No iodine-131 was reported for the 2003 air monitoring results.
2003 RadiologicaJ Environmental Monitoring Report Atmospheric Pathway Monitoring 3S
'-.J No other gamma-emitting radionucHdes were reported for air in 2003.
Beryllium-7 and potassium-40 are not attributable to SSES operation.
.1 Air Iodine Iodine-131 has been detected infrequently from 1976, when it was first monitored, through 2003. Since operation of the SSES began in 1982, iodine-131 has only been positively detected in air samples in 1986 due to the Chemobyl accident. No iodine-131 was reported for the 2003 air monitoring results.
2003 RadiologicaJ Environmental Monitoring Report Atmospheric Pathway Monitoring 3S
FIGURE 12 - GROSS BETA ACTIVITY IN AIR PARTICULATES E-03 pCi/M3 500,---------------------~----------------------------------------------------~
450 PREOPERA TIONAL 400 A +
350 300 250 200 D E 150
~
100 F
50 0
t\\~
~
UNIT2 OPERA TIONAL CHERNOBYL 4/26/86 CRITICALITY I CHINESE WEAPONS TEST A - 06/17174 B - 09/26176 C-11117176 D - 09/17177 E - 03/14178 F - 10/15/80 Indicator Control FIGURE 12 - GROSS BETA ACTIVITY IN AIR PARTICULATES E-03 pCi/M3 500,---------------------~----------------------------------------------------~
450 PREOPERA TIONAL 400 A +
350 300 250 200 D E 150
~
100 F
50 0
t\\~
~
UNIT2 OPERA TIONAL CHERNOBYL 4/26/86 CRITJCALITY I CHINESE WEAPONS TEST A - 06/17174 B - 09/26176 C-11117176 D - 09/17177 E - 03/14178 F - 10/15/80 Indicator Control
T~"e~trial P~thway Monitoring
.~:TERREs~fRiAi3PAt'HWAy~'MONiT*O*RiNG;.',:F;~!;ri
- .~.,_,~.
INTRODUCTION The following media,were monit9red in, the Terrestrial Pathway in 2003:
milk, ~ruits and vegetables.
Soil can be a great accumulator of man~','
made radionuclides that enter it. The',
extent of the accumulation in the soil' depends of course on the amount of the, radionuclides reaching it, but it also.
depends on the chemical nature of those' radionucJides an4 the particular characteristics of the soil. For the elemerlt cesium, and, therefore, cesium-137 can be bound very tightJ,fto clay in soils. The amount'of clay i!l soil can vary greatly frorilone location to anoth'er. In clay soils, cesium-137 may move very slowly and also may be up very slowly in plants as they absorb soil moisture.
Any medium, such as soil, th~t ten~s accumulate radioactiVe mateiials cari,:
also provide more sensitivity for radionuclide detection in the environment than those media
~
don't. Such a medium facilitates the early identification of radionuclides in the environment, as well as a\\vareness! ;-
of changesihat 'subsequently may occur in the environmental levels of identified radionuclides.
The SSES REMP sampfes 's~iI nead'o~r'-::
of the six REMPair sampling The purpose for soil sampling near the' r:~.'
rl'~ t" air sampling sites is to make it easier to" correlate. air samplfng results with'soil sampling results if any SSES related"'
radioactive material were found,in either medium. Sampling is performed,
at different depths near the surface to.
help provide information on how recently certain radioactive materials may have enieredihesoiL Sampling at more than one depth also may help ensure the detection of materials that move relatively quickly through the soil.
Such quick-moving materials may have already passed through the topmost layer of soil at the time of sampling.
Milk was sampled at four locations and fruit and vegetable samples ~ere obtained at 210cations in 2003~ SSES Technical Requirements requi~e th~t. the SSES REMP'sample milk at the three '
most sensitive monitoring locations near the SSES :and 'one.coritrollocation distant from the SSES. SSES Technical Rt:quirements only require ~hat fruit and vegetables be sampled at locations irrigated by Susquehanna River water from points downstream of the SSES "
dischargeto the Riv~r. There are only.-
three 10catic)Jls'withiri 10 miles' downstream i:>fthe SSES that have been known to irrig~te: ~ith water from the Susque~anna ;River during unusually dry periods. These locations do ~ot, irrigate eve.ry year. Irrigation was.
performed at the Chapin FarmsDrake Field" (l1F2) and,the Lupln'i Farm :
, "Route 93 Nescopeck Field" (11D2),
during 2003 as identified by the '2003 Land Use 'Census (Refe.rence i 1).,. '
~
No requirement exists for the SSES REMP'to monitor'soil. AlJ,monitqring of the terrestrial pathway that is
~<.?~d~~!ed
.~he SSES REMP in 2003 Radiological Em'ironmental Monitoring Report 37 T~"e~trial P~thway Monitoring
. ~
.~:TERREs~fRiAi3PAt'HWAy~'MONiT*O*RiNG;.',:F;~!;ri
.... ~.-,. ___.......,.. 'I.l..
_>~........ >.#...-. _ ** ~.........,_.....,,_............ _.... "'.. ""'... _~~ *....-__..
,.;..:_._~~ "\\..I>:r;~'.... _~'.'~; __
l~ ** ""'-
.~
~
...,.,....... tl :-1t......... 'c;.~ :;.~.,_,~.
INTRODUCTION The following media,were monit9red in, the Terrestrial Pathway in 2003: soil,*' *.,
milk, ~ruits and vegetables.
Soil can be a great accumulator of man~','
made radionuclides that enter it. The',.'
extent of the accumulation in the soil' depends of course on the amount of the,.
radionuclides reaching it, but it also. '
depends on the chemical nature of those',
radionucJides an4 the particular characteristics of the soil. For example,: ;',
the elemerlt cesium, and, therefore, ' :', ;',
cesium-137 can be bound very tightJ,fto clay in soils. The amount'of clay i!l soil,,'
can vary greatly frorilone location to ','
anoth'er. In clay soils, cesium-137 may move very slowly and also may be takeri" up very slowly in plants as they absorb '!
soil moisture.
Any medium, such as soil, th~t ten~s tQ.
accumulate radioactiVe mateiials cari,: __
also provide more sensitivity for radionuclide detection in the : I environment than those media thai'.
~ ;l:('!'
don't. Such a medium facilitates the ::;;;::
early identification of radionuclides in J!.";
the environment, as well as a\\vareness! ;- i of changesihat 'subsequently may occur,-;
in the environmental levels of the':;*': :
identified radionuclides.
' ',' ;' d' The SSES REMP sampfes 's~iI nead'o~r'-::
of the six REMPair sampling stations.'" :
The purpose for soil sampling near the' r:~.'
t I,
rl'~ t" t -
air sampling sites is to make it easier to" correlate. air samplfng results with'soil ":', :
sampling results if any SSES related"' ' :
radioactive material were found,in either medium. Sampling is performed,
at different depths near the surface to.
help provide information on how
, recently certain radioactive materials may have enieredihesoiL Sampling at more than one depth also may help ensure the detection of materials that move relatively quickly through the soil.
Such quick-moving materials may have already passed through the topmost layer of soil at the time of sampling.
Milk was sampled at four locations and fruit and vegetable samples ~ere obtained at 210cations in 2003~ SSES Technical Requirements requi~e th~t. the SSES REMP'sample milk at the three '
most sensitive monitoring locations near the SSES :and 'one.coritrollocation distant from the SSES. SSES Technical Rt:quirements only require ~hat fruit and vegetables be sampled at locations irrigated by Susquehanna River water from points downstream of the SSES "
dischargeto the Riv~r. There are only.-
three 10catic)Jls'withiri 10 miles' downstream i:>fthe SSES that have been known to irrig~te: ~ith water from the ' ::
Susque~anna ;River during unusually,
dry periods. These locations do ~ot, ",
irrigate eve.ry year. Irrigation was.,:'
I performed at the Chapin FarmsDrake Field" (l1F2) and,the Lupln'i Farm :
, "Route 93 Nescopeck Field" (11D2),
during 2003 as identified by the '2003 Land Use 'Census (Refe.rence i 1).,. '
~
No requirement exists for the SSES REMP'to monitor'soil. AlJ,monitqring of the terrestrial pathway that is
"' _ ~<.?~d~~!ed,:>y.~he SSES REMP in 2003 Radiological Em'ironmental Monitoring Report 37
addition to milk and certain fruit and veoetables is voluntary and reflects c
PPL's wi1Jingness to exceed regulatory requirements to ensure that the public and the environment are protected.
Scope Soil Soil was sampled in September 2003 in accordance with its scheduled annual sampling frequency, a~ the f.0l1owing four REMP air sampling locations, 3S2, 12S1, 13S6, and 801. Location 801 was a control sampling location; the remaining sampling sites wer~ indicator locations.
Twelve soil plugs were taken at selected spots at each monitoring location. The plugs were separated into "top" (0-2 inches) and "bottorr( (2-6 inches) segments. Each set of top and bottom segments was comp6sited to -yield 2 soil samples from each location for analysis.
Since there are four monitoring locations, a total of 8 soil samples were analyzed in 2003.
Milk Milk was sampled at least monthly at the foUowing four locations in 2003:
lOD-l, IOD2, 12B2 and 1001:
Milk was sampled semi-monthly from April through Octobe~ when cows were more Hkely to be on pasture. U?cations 10DI, lOD2. and 12B2 are believed to be the most sensitive indicator sites avaiJable for the detection of radionucHdes released from the SSES.
Location 1001 is the control location. A total of 76 milk samples from both indicator and control locations were analyzed in 2003.
2003 Radiological Environmental Monitoring Report Terrestrial Pathway Monitoring Fruits and Vegetables Potatoes were sampJed during the harvest season at 2 locations surrounding the SSES. A total of 2 samples were coJ1ected from locations I1D2, and I1F2.
Both locations were identified as having irrigated with Susquehanna River water from downstream of the SSES during 2003. There are often years with adequate rainfall when no irrigation is performed.
Sample Preservation and Analysis AU media in the terrestrial pathway are analyzed for the activities of garnma-emitting radionuclides using gamma spectroscopy. The other analysis that is routinely performed is the radiochemical analysis for iodine-131 in milk. The use of sodium bisulfite as a preservative in milk samples was discontinued in 2003 (at the request of the vendor laboratory).
Monitoring Results The only man-made radionuclides normally ~xpected at levels in excess of analysis MDC~ in the terrestrial pathway are strontium-90 and cesium-137. Both of these radionuclides are '
present in the environment as a residual from previous atmospheric nuclear weapons testing.
Strontium-90 analyses are not now routinely performed for any media samples in the terrestrial pathway.
Strontium-90 activity would be expected to be found in milk. SSES Technical Requirements do not require 38 I I I
i addition to milk and certain fruit and veoetables is voluntary and reflects c
PPL's wi1Jingness to exceed regulatory requirements to ensure that the public and the environment are protected.
Scope Soil Soil was sampled in September 2003 in accordance with its scheduled annual sampling frequency, a~ the f.0l1owing four REMP air sampling locations, 3S2, 12S1, 13S6, and 801. Location 801 was a control sampling location; the remaining sampling sites wer~ indicator locations.
Twelve soil plugs were taken at selected spots at each monitoring location. The plugs were separated into "top" (0-2 inches) and "bottorr( (2-6 inches) segments. Each set of top and bottom segments was comp6sited to -yield 2 soil samples from each location for analysis.
Since there are four monitoring locations, a total of 8 soil samples were analyzed in 2003.
Milk Milk was sampled at least monthly at the foUowing four locations in 2003:
lOD-l, IOD2, 12B2 and 1001:
Milk was sampled semi-monthly from April through Octobe~ when cows were more Hkely to be on pasture. U?cations 10DI, lOD2. and 12B2 are believed to be the most sensitive indicator sites avaiJable for the detection of radionucHdes released from the SSES.
Location 1001 is the control location. A total of 76 milk samples from both indicator and control locations were analyzed in 2003.
2003 Radiological Environmental Monitoring Report Terrestrial Pathway Monitoring Fruits and Vegetables Potatoes were sampJed during the harvest season at 2 locations surrounding the SSES. A total of 2 samples were coJ1ected from locations I1D2, and I1F2.
Both locations were identified as having irrigated with Susquehanna River water from downstream of the SSES during 2003. There are often years with adequate rainfall when no irrigation is performed.
Sample Preservation and Analysis AU media in the terrestrial pathway are analyzed for the activities of garnma-emitting radionuclides using gamma spectroscopy. The other analysis that is routinely performed is the radiochemical analysis for iodine-131 in milk. The use of sodium bisulfite as a preservative in milk samples was discontinued in 2003 (at the request of the vendor laboratory).
Monitoring Results The only man-made radionuclides normally ~xpected at levels in excess of analysis MDC~ in the terrestrial pathway are strontium-90 and cesium-137. Both of these radionuclides are '
present in the environment as a residual from previous atmospheric nuclear weapons testing.
Strontium-90 analyses are not now routinely performed for any media samples in the terrestrial pathway.
Strontium-90 activity would be expected to be found in milk. SSES Technical Requirements do not require 38 I I I
i
Terrestrial Pathway Monitoring that miik be analyzed fo,r.strontiun:t:-,99:
Strontiu~-90 analys~s may be' ""
performed at anytime if the results of,..
other milk analyses would show. ~:,
detectable levels of fission 'product, activity which might suggest the ~S;t;S as the sourc,e.,
Cesium-137 nOrinally has been me~sured iti excess,of analysis MDCs' in.
most s()il samples. Although game is not cu~nily'~fng' Irionitored, ces~um~
137 has also been'seen often at levels' above the ~~s iIi 'game :in the past.:
Certain natuiaiIy Occurring radioriuCiides are also 'routinely fourid '
above analysis MDCs in'terrestrial' pathway media. Potassium40, a ' '
primordial and very long-lived radionuc1ide, which is terrestrial in',. ";
origin, is obse'rved in all terrestrial'
', )
pathway media. Other naturally
.*. ~ :
occurring'radionuc1ides often observed:'
are thorium~228 and radium-226 in soil,"
and bery11ium-7 in fruits and vegetables. '
The results of the 2003 terrestrial pathway monitoring resemble those of / I the past~ Results for specific sample analyses of terrestrial pathway media, may be found in Tables 1-10 1-12 of Appendix 1. A summary ofthe :-
2003 terrestrial monitoring data may be located in Appendix'G. Comparisons of 2003 monitoring results with those of. ~ t past years may be found in Tables H 15 \\~;
through'H 19 of Appendix H.
Soil The following gamma-emitting radionucHdes are routinely measured in' soil at levels exceeding analysiS MDCs:
naturaHy occurring potassium40t radium-226, and thorium-228 and man-made cesium-137. The 2003 analysis results were simi1ar to those for previous years. No other gamma-emitting radionuclides were reported at le~els above analysis MDCs. '
The 2003 means for indicator and control location sample potassium40 activitywere 14.4 p'Ci/gram and 10.6 pCilgram. respectively. The indicator and control means are within the range of corresponding means for both prio~ ~perational and preoperational years'.: This is not the result of SS'ES op~ration because the potassium40 is naturaIly occurring. The 2003 indicator and control means for potassium40 were greater than the corresponding 2002 means.
Ra-226 analysis of soi1 samples was deleted from the SSES REMP iri 2002.
Ra-226 was not performed on any soil samples in 2003 and has been discontinued from the SSES REMP soil sample analysis library.
The 2003 means for indicator and control location sample thorium~228 activity were both 0.8 pCi/gram. The 2003 indicator mean is e.qual to the corresponding 2002 mean. 'The 2003 '
control mean for thorium-228 is greater than the corresponding 2002 mean. The indicator and 'control means are within the ranges of the corresponding means':. ~
for both the previous operation a) and.
preoperational 'periods, as applicablet of" the SSES. Thorium-228 in soil is not ': :
the result ofSSES operation because it, is naturaIJy occurring. '
The 2003 means for indicator and control location sample cesium-137,
activity were 0.04 pCi/g and 0.07 pCi/g, respectively. The 2003 indicator mean is within the range of the corresponding 39 2003 Radiological Environmental Monitoring Report Terrestrial Pathway Monitoring that miik be analyzed fo,r.strontiun:t:-,99:.
Strontiu~-90 analys~s may be' ""
performed at anytime if the results of,.. '
other milk analyses would show. ~:, :..,
detectable levels of fission 'product, activity which might suggest the ~S;t;S :
as the sourc,e.,
Cesium-137 nOrinally has been me~sured iti excess,of analysis MDCs' in.
most s()il samples. Although game is,,",
not cu~nily'~fng' Irionitored, ces~um~,
137 has also been'seen often at levels' above the ~~s iIi 'game :in the past.: ',:;,
Certain natuiaiIy Occurring radioriuCiides are also 'routinely fourid '
above analysis MDCs in'terrestrial' pathway media. Potassium40, a ' '
primordial and very long-lived radionuc1ide, which is terrestrial in',. ";
origin, is obse'rved in all terrestrial'
', )
pathway media. Other naturally
.*. ~ :
occurring'radionuc1ides often observed:'
are thorium~228 and radium-226 in soil,"
and bery11ium-7 in fruits and vegetables. '
The results of the 2003 terrestrial pathway monitoring resemble those of / I the past~ Results for specific sample analyses of terrestrial pathway media, :.,.:
may be found in Tables 1-10 through* ':
1-12 of Appendix 1. A summary ofthe :-.J',
2003 terrestrial monitoring data may be,"
located in Appendix'G. Comparisons of ",
2003 monitoring results with those of. ~ t 'r;,
past years may be found in Tables H 15 \\~;
through'H 19 of Appendix H.
Soil
.. l'
~
The following gamma-emitting
) ':!;,
radionucHdes are routinely measured in',: I soil at levels exceeding analysiS MDCs:
naturaHy occurring potassium40t radium-226, and thorium-228 and man-made cesium-137. The 2003 analysis results were simi1ar to those for previous years. No other gamma-emitting radionuclides were reported at le~els above analysis MDCs. '
The 2003 means for indicator and control location sample potassium40 activitywere 14.4 p'Ci/gram and 10.6 pCilgram. respectively. The indicator and control means are within the range of corresponding means for both prio~ ~perational and preoperational years'.: This is not the result of SS'ES op~ration because the potassium40 is naturaIly occurring. The 2003 indicator and control means for potassium40 were greater than the corresponding 2002 means.
Ra-226 analysis of soi1 samples was deleted from the SSES REMP iri 2002.
Ra-226 was not performed on any soil samples in 2003 and has been discontinued from the SSES REMP soil sample analysis library.
The 2003 means for indicator and control location sample thorium~228 activity were both 0.8 pCi/gram. The 2003 indicator mean is e.qual to the corresponding 2002 mean. 'The 2003 '
control mean for thorium-228 is greater than the corresponding 2002 mean. The indicator and 'control means are within the ranges of the corresponding means':. ~
for both the previous operation a) and.
preoperational 'periods, as applicablet of" the SSES. Thorium-228 in soil is not ': :
the result ofSSES operation because it, is naturaIJy occurring. '
t r
The 2003 means for indicator and control location sample cesium-137,
activity were 0.04 pCi/g and 0.07 pCi/g, respectively. The 2003 indicator mean is within the range of the corresponding 39 2003 Radiological Environmental Monitoring Report
annual means for prior operational years. The 2003 indicator mean is below the ranges of the corresponding means for preoperational years~ The 2003 control mean is below the 'ranges of corresponding. annual means for both prior operational and preoperational years. Cesium-137 levels in soil samples typically vary widely from sample to sample. Levels of cesium-137 activity in 2003 samples varied by a factor of four over the entire range.
Cesium-137 in soil, althoughmim-made, is not from the operation of the SSES. It is residual faJIout from previous atmospheric nuclear weapons testing.
Milk Iodine-131 has been chemically separated in milk samples and counted routinely since 1977. Refer to Figure 13 which trends iodine-131 activity in milk for indicator and control locations separately from 1977 through 2003.
Typically, iodine-131 is not reported at levels exceeding the l\\1DCs for the analyses in any milk samples during a monitored year. The 2003 monitoring year was no exception; no iodine-131 above the analysis l\\1DCs was observed in either indicator or control samples.
The preoperational years 1976, 1978, and 1980 were exceptional years in the sense that iodine-131 activity was observed in excess of l\\1DCs due to fallout from atmospheric nuclear weapons testing. Iodine-131-activity was also measured at levels exceeding l\\1DCs in milk samples in 1986 in the vicinity of the SSES as a result of the Chemobyl incident.
2003 Radiological Environmentall\\'onitoring Report Terrestrial Pathway Monitoring With the exception of the naturally occurring potassium-40, no gamma-emitting radionuclides were measured in excess of analysis l\\1DCs in 2003.
The 2003: means for indicator and control location sample potassium-40 activity were 1383 pCilliter and 1406 pCi/Hter, respectively. The 2003 indicator mean is less than the 2002 mean. The 2003 control mean is greater than the corresponding 2002 mean. The 2003 indicator and control means for potassium-40 activity are within the corresponding ranges of annual means for previous operational and preoperational years. The potassi um-40 activity in milk is not attributable to the SSES operation because it is naturally occurring.
Fruits alld Vegetables Naturally occurring potassium-40 was the only gamma-emitting radionuclide measured in fruits and vegetables at an activity level in excess of analysis l\\1DC during 2003.
Due to excessive rainfall during the 2003 growing season, fruits andlor vegetables were only sampled twice, both from indicator locations. The 2003 indicator location sample potassium-40 activity mean was 4.6 pCi/gram. The 2003 indicator mean is higher than its corresponding 2002 mean. The 2003 indicator mean is above the range of the corresponding annual means for pre-operational and prior operational years.
Potassium-40 in fruits and vegetables is not attributable to SSES operation because it is a naturally occurring radionuclide.
40 I I annual means for prior operational years. The 2003 indicator mean is below the ranges of the corresponding means for preoperational years~ The 2003 control mean is below the 'ranges of the*
corresponding. annual means for both prior operational and preoperational years. Cesium-137 levels in soil samples typically vary widely from sample to sample. Levels of cesium-137 activity in 2003 samples varied by a factor of four over the entire range.
Cesium-137 in soil, althoughmim-made, is not from the operation of the SSES. It is residual faJIout from previous atmospheric nuclear weapons testing.
Milk Iodine-131 has been chemically separated in milk samples and counted routinely since 1977. Refer to Figure 13 which trends iodine-131 activity in milk for indicator and control locations separately from 1977 through 2003.
Typically, iodine-131 is not reported at levels exceeding the l\\1DCs for the analyses in any milk samples during a monitored year. The 2003 monitoring year was no exception; no iodine-131 above the analysis l\\1DCs was observed in either indicator or control samples.
The preoperational years 1976, 1978, and 1980 were exceptional years in the sense that iodine-131 activity was observed in excess of l\\1DCs due to fallout from atmospheric nuclear weapons testing. Iodine-131-activity was also measured at levels exceeding l\\1DCs in milk samples in 1986 in the vicinity of the SSES as a result of the Chemobyl incident.
2003 Radiological Environmentall\\'onitoring Report Terrestrial Pathway Monitoring With the exception of the naturally occurring potassium-40, no gamma-emitting radionuclides were measured in excess of analysis l\\1DCs in 2003.
The 2003: means for indicator and control location sample potassium-40 activity were 1383 pCilliter and 1406 pCi/Hter, respectively. The 2003 indicator mean is less than the 2002 mean. The 2003 control mean is greater than the corresponding 2002 mean. The 2003 indicator and control means for potassium-40 activity are within the corresponding ranges of annual means for previous operational and preoperational years. The potassi um-40 activity in milk is not attributable to the SSES operation because it is naturally occurring.
Fruits alld Vegetables Naturally occurring potassium-40 was the only gamma-emitting radionuclide measured in fruits and vegetables at an activity level in excess of analysis l\\1DC during 2003.
Due to excessive rainfall during the 2003 growing season, fruits andlor vegetables were only sampled twice, both from indicator locations. The 2003 indicator location sample potassium-40 activity mean was 4.6 pCi/gram. The 2003 indicator mean is higher than its corresponding 2002 mean. The 2003 indicator mean is above the range of the corresponding annual means for pre-operational and prior operational years.
Potassium-40 in fruits and vegetables is not attributable to SSES operation because it is a naturally occurring radionuclide.
40 I I
c FIGURE 13 - IODINE-131 ACTIVITY IN MILK 100 pCilLiter CHINESE WEAPONS TEST 90 -
A - 09/12177 PRE-B- 03/14178 OPERATIONAL OPERATIONAL C -10/15/80 80 70 -
60 -
so A
40 CIIERNOBYL 30 4/26/86 20 UNIT2 10 CRITICALIT B
C
+
D 1M I
o 121 Indicator
[J Control c*
c FIGURE 13 - IODINE-131 ACTIVITY IN MILK 100 pCilLiter CHINESE WEAPONS TEST 90 -
A - 09/12177 PRE-B- 03/14178 OPERATIONAL OPERATIONAL C -10/15/80 80 70 -
60 -
so A
40 CIIERNOBYL 30 4/26/86 20 UNIT2 10 CRITICALIT B
C
+
D 1M I
o 121 Indicator
[J Control
Water Monitoring INTRODUCTION ~.
Nonnal operation of the SSES does not',
involve the release of radioactive material to ground water directly 'or
, in'directly through' the ground. As a result, there are no effluent monitoring',
data to compare with REMP ground water monitoring results. Ground water could conceivably become contaminated by leakage or spills from the plant or by the washout deposition of radioactive material that might be airborne. If deposited 'on the ground, precipitation/soil moisture could aid in' the movement of
~!
radioactive materials through the:"
ground to water that could conceivably be pumped for drinking purposes.
\\~:
use of ground water for irrigation near the SSES has been identified.
Because routine SSES operation releases primarily tritium and, to a Jesser extent, isotopes of xenon and krypton to the air, no radionuclides attributable to SSES operation are expected to be observed in ground water. Iodine and particulate releases to the air are negJigible. Gaseous xenon and krypton tend to remain airborne; deposition or washout of these would be expected to be very minimal. Tritium would be the most likeJy radionuc1ide to reach the ground with precipitation and, if not lost to streams (surface water) by runoff, move readily through the soil to the ground water.
2003 Radiological EnYironmental Monitoring Report Ground water in the SSES vicinity was sampled'monthlY' at 2 indicator
, )
locations and one c'ontr01 location (12F3) during 2003.
With the exception of location 4S4 untreated gro'und water was sampled.
Untreated means that the water has'not undergone. any processing such as.,
filtration,'chlorinaiio~: or softening. At" location the SSES Training' we)) water actually.is obtained frop} on~
site and piped to the,Training Genter" after treatment. This sampling is' performed as a check toensure thai water:has not' been
~
contaminated. Sampling is performed at,
the Training Center to facilitate the
. sample collec.tion Sample Preservation &
Analysis Ground water samples were analyzed
~or the 'activities of gamma-emitting radiolniclides'an4 tritium activity.
Gamma spectrometric 'analyses of ground \\vater were begilrdn 1979 and tritiuin C analyses in 1972, b'oth prior to' SSES operation. 'The use ofnitrlc'acid as a preservative in ground water'-
samples was discontinued in 2003 '(at the request of the vendor laboratory).
42
\\
I
,*Ground Water Monitoring "
~
> J".: !', : f,.
I J, INTRODUCTION ~.
'_, i, ",
Nonnal operation of the SSES does not',
involve the release of radioactive.: ", J\\:
material to ground water directly 'or,"
, in'directly through' the ground. As a,"": "
result, there are no effluent monitoring',
data to compare with REMP ground,":"
water monitoring results. Ground water could conceivably become contaminated by leakage or spills from,",
the plant or by the washout or'*.,' :.: ;.
deposition of radioactive material that ;; :-:
might be airborne. If deposited 'on the :;:':
ground, precipitation/soil moisture '", ".';';
could aid in' the movement of.:,' ~! 'JJ " !
radioactive materials through the:",.. ! L:.,
ground to water that could conceivably ;.(;
be pumped for drinking purposes. No \\~: r';,
use of ground water for irrigation near the SSES has been identified.
Because routine SSES operation releases primarily tritium and, to a Jesser extent, isotopes of xenon and krypton to the air, no radionuclides attributable to SSES operation are expected to be observed in ground water. Iodine and particulate releases to the air are negJigible. Gaseous xenon and krypton tend to remain airborne; deposition or washout of these would be expected to be very minimal. Tritium would be the most likeJy radionuc1ide to reach the ground with precipitation and, if not lost to streams (surface water) by runoff, move readily through the soil to the ground water.
2003 Radiological EnYironmental Monitoring Report Scope**... '
Ground water in the SSES vicinity was sampled'monthlY' at 2 indicator
, )
locations (2S2 arid 4S4) and one c'ontr01.
location (12F3) during 2003.
With the exception of location 4S4 *.,
untreated gro'und water was sampled.
Untreated means that the water has'not undergone. any processing such as.,
filtration,'chlorinaiio~: or softening. At" location *4S4. the SSES Training' Center, we)) water actually.is obtained frop} on~
site and piped to the,Training Genter".
after treatment. This sampling is' performed as a check toensure thai water:has not' been radioactiveh< ~
contaminated. Sampling is performed at,
the Training Center to facilitate the
. sample collec.tion process..,
Sample Preservation &
Analysis Ground water samples were analyzed
~or the 'activities of gamma-emitting radiolniclides'an4 tritium activity.
Gamma spectrometric 'analyses of ground \\vater were begilrdn 1979 and ',
tritiuin C analyses in 1972, b'oth prior to' SSES operation. 'The use ofnitrlc'acid ' '
as a preservative in ground water'-
samples was discontinued in 2003 '(at the request of the vendor laboratory).
'f':
42
Ground Water iWonitoring Monitoring Results Tritium activity levels in ground water have typically been observed to _be lower than in surface water. A
. noticeable decline 'occurred between 1992 and 1993. Fewer measurements were above the analysis sensitivities in 1993 than in 1992.
Gamma-emitting radionucIides in excess ofMDCs have been found in only a few samples in' an the years that these analyses have been performed.
The natural1y occurring radionuclides potassium-40 and thorium-228 have been measured above their MDCs occasionaUy in ground water..
Potassium-40 was reported in 1979, 1981, 1985. 1991, 1992, 199~,and 1997. Thorium-228 was found in 1985 and 1986. The man-made radionuclide cesium-137 has been, detected only occasionally since 1979. Its presence has always been attributed to residual fallout from previous atmospheric nuclear weapons tests.
The results of the 2003 REMP ground water survei1Iance resemble those of the past. Res~Its for specific ground water sample analyses may be found in Table 1-7 of Appendix I. A summary of the 2003 ground water monitoring data may be located in Appendix G.
Comparisons of 2003 monitoring results for tritium with those of past years may be found,in Table H 20 of Appendix H.
During 2003, tritium was measured in excess of analysis MDCs on 4 occasions. The 2003 mean tritium activity levels for indicator and control monitoring locations were 54 pCi/Jiter and 17 pCilliter, respectively. The 43 indicator and control means are lower than those for 2002. Both the 2003 indicator and control mean tritium activity levels are withi~:.!he range of corresponding averages of annual means for prior operational years. The 2003 indicator mean tritium activity is lower than the corresponding means for preoperational years. The 2003 control mean is within the range of corresponding means for preoperational years.
Natural1y occurring potassium-40 was measured in excess of analysis MDCs in 2 ground water samples during 2003.
No man-made gamma-emitting radionuclides were determined to be at levels in excess of analysis MDCs. No radioactivity contributions to ground water from the SSES were identifiable in 2003.
2003 Radiological Envjron~ental Monitoring Report I
._-....../
Ground Water iWonitoring Monitoring Results Tritium activity levels in ground water have typically been observed to _be lower than in surface water. A
. noticeable decline 'occurred between 1992 and 1993. Fewer measurements were above the analysis sensitivities in 1993 than in 1992.
Gamma-emitting radionucIides in excess ofMDCs have been found in only a few samples in' an the years that these analyses have been performed.
The natural1y occurring radionuclides potassium-40 and thorium-228 have been measured above their MDCs occasionaUy in ground water..
Potassium-40 was reported in 1979, 1981, 1985. 1991, 1992, 199~,and 1997. Thorium-228 was found in 1985 and 1986. The man-made radionuclide cesium-137 has been, detected only occasionally since 1979. Its presence has always been attributed to residual fallout from previous atmospheric nuclear weapons tests.
The results of the 2003 REMP ground water survei1Iance resemble those of the past. Res~Its for specific ground water sample analyses may be found in Table 1-7 of Appendix I. A summary of the 2003 ground water monitoring data may be located in Appendix G.
Comparisons of 2003 monitoring results for tritium with those of past years may be found,in Table H 20 of Appendix H.
During 2003, tritium was measured in excess of analysis MDCs on 4 occasions. The 2003 mean tritium activity levels for indicator and control monitoring locations were 54 pCi/Jiter and 17 pCilliter, respectively. The 43 indicator and control means are lower than those for 2002. Both the 2003 indicator and control mean tritium activity levels are withi~:.!he range of corresponding averages of annual means for prior operational years. The 2003 indicator mean tritium activity is lower than the corresponding means for preoperational years. The 2003 control mean is within the range of corresponding means for preoperational years.
Natural1y occurring potassium-40 was measured in excess of analysis MDCs in 2 ground water samples during 2003.
No man-made gamma-emitting radionuclides were determined to be at levels in excess of analysis MDCs. No radioactivity contributions to ground water from the SSES were identifiable in 2003.
2003 Radiological Envjron~ental Monitoring Report I
._-....../
References r7~:"~:~~';:~
- 1.
Pennsylvania Power and Light Company, ffSusquehanna Steam Electric Station, Environmental Report, Operating License Stage,ff May
- 2.
Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station, Final Safety Analysis Report".
- 3.
United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, "Final Environmental Statement Related to the Operation of Susquehanna Steam Electric Station, Units 1 and 2," Docket Nos. 50-387 and 50-388, June 1981.
- 4.
United States Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Radiological' Assessment Branch Technical Position, November 1979, Revision 1.
- 5.
National Council on Radiation Protection and Measurements, ttEnvironmental Radiation Measurement:t NCRP Report No. 50, Washington, D.C.,
December 27, 1976.
- 6.
Oakley, D.C., tlNatural Radiation Exposure in the United States:' ORP/SID 72-1 Office of Radia"tion Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972.
- 7.
Denham, D.H., Roberts, M.C., Novitsky, W.M., Testa, E.D., "Investigation of Elevated Cesium-137 Concentrations in Small Game in Luzerne County, PennsyJ vania." Proceedings of Papers presented at Health Physics Society Tenth Midyear Topical Symposium~ October 11-13, 1976, pgs. 271-279.
- 8.
Cunie L.A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4007, September 1984.
- 9.
PPL, "Susquehanna Steam Electric Station, 2002 Annual Radiological Environmental Operating Report." April 2003.
- 10. PPL, "Susquehanna Steam Electric Station, Radioactive Effluent Release Report,"
Data Period: January - December 2003; April 2004.
- 11. Ecology ill, "Susquehanna Steam Electric Station, 2003 Land Use Census,"
November 2003.
2003 Radiological Em'ironmental Monitoring Report 44
APPENDIX A 2003 Radiological Environmental Monitoring Report APPENDIX A
"/ ;"
1",
r 17.'
r r:.
2003 Radiological Environmental Monitoring Report A*I
Appendix A REMP Sample Analyses The fol1owing table summarizes the REMP sample analyses for which different laboratories were responsible during 2003. Note that TBE represents Teledyne Brown Engineering and E-LAB represents Framatome ANP.
SOURCE OF REMP DA TA FOR MONITORING YEAR 2003 Sample Analysis Sample/Analysis Medium Type Frequency Data Period Lab Air Gross Beta Weekly All Year TBE Air 1-131 Weekly All Year TBE Air Gamma Quarterly All year TBE Surface Gross Beta Monthly All Year TBE Water Drinking Gross Beta &
Monthly An Year TBE Water Gross Alpha All Water Tritium Monthly All Year TBE Surface &
Gamma Monthly All Year E-LAB Drinking Water Surface 1-131 Monthly All Year E-LAB Water (LTAW)
Ground Gamma Monthly All Year E-LAB Water Surface &
1-131 Bi/weekly An Year E-LAB Drinking Water Milk Gamma Monthly!
All Year E-LAB Semi-Monthly Milk 1-131 Monthly!
All Year E-LAB Semi-Monthly Fish Gamma Semi-Annually Spring/Fall TBE Sediment Gamma Semi-Annually Spring/Fall TBE 2003 Radiological Environmental Monitoring Report I I Appendix A REMP Sample Analyses The fol1owing table summarizes the REMP sample analyses for which different laboratories were responsible during 2003. Note that TBE represents Teledyne Brown Engineering and E-LAB represents Framatome ANP.
SOURCE OF REMP DA TA FOR MONITORING YEAR 2003 Sample Analysis Sample/Analysis Medium Type Frequency Data Period Lab Air Gross Beta Weekly All Year TBE Air 1-131 Weekly All Year TBE Air Gamma Quarterly All year TBE Surface Gross Beta Monthly All Year TBE Water Drinking Gross Beta &
Monthly An Year TBE Water Gross Alpha All Water Tritium Monthly All Year TBE Surface &
Gamma Monthly All Year E-LAB Drinking Water Surface 1-131 Monthly All Year E-LAB Water (LTAW)
Ground Gamma Monthly All Year E-LAB Water Surface &
1-131 Bi/weekly An Year E-LAB Drinking Water Milk Gamma Monthly!
All Year E-LAB Semi-Monthly Milk 1-131 Monthly!
All Year E-LAB Semi-Monthly Fish Gamma Semi-Annually Spring/Fall TBE Sediment Gamma Semi-Annually Spring/Fall TBE 2003 Radiological Environmental Monitoring Report I I
Appendix A SOURCE OF REMP DATA FOR MONITORING YEAR 2003
. (continued)
Sample Analysis Sample! Analysis Medium Type Frequency Data Period Lab Fruits &
Gamma In Season All Year TBE Vegetables (when irritgated)
Soil Gamma Annually All Year E-LAB Direct Radiation Monitoring There were no changes to direct radiation monitoring in 2003.
Air Monitoring There were no changes to the air monitoring program during 2003 Milk Monitoring There were no changes to the milk monitoring program in 2003.
Ground Water Monitoring There were no changes to the ground water monitoring program during 2003.
Fruits & Vegetables Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway. Fruits and vegetables are sampled from locations that irrigate with water taken from the Susquehanna River downstream from the SSES diffuser. The only change to the fruit and vegetable monitoring program in 2003 was the addition of Contro] Location 5S10. Location 5S10 is a farm irrigated with Susquehanna River water upstream of the SSES diffuser. Due to excessive rainfall, no irrigation was performed at Location 5S10 during 2003.
2003 Radiological Environmental Monitoring Report Appendix A SOURCE OF REMP DATA FOR MONITORING YEAR 2003
. (continued)
Sample Analysis Sample! Analysis Medium Type Frequency Data Period Lab Fruits &
Gamma In Season All Year TBE Vegetables (when irritgated)
Soil Gamma Annually All Year E-LAB Direct Radiation Monitoring There were no changes to direct radiation monitoring in 2003.
Air Monitoring There were no changes to the air monitoring program during 2003 Milk Monitoring There were no changes to the milk monitoring program in 2003.
Ground Water Monitoring There were no changes to the ground water monitoring program during 2003.
Fruits & Vegetables Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway. Fruits and vegetables are sampled from locations that irrigate with water taken from the Susquehanna River downstream from the SSES diffuser. The only change to the fruit and vegetable monitoring program in 2003 was the addition of Contro] Location 5S10. Location 5S10 is a farm irrigated with Susquehanna River water upstream of the SSES diffuser. Due to excessive rainfall, no irrigation was performed at Location 5S10 during 2003.
A*3 2003 Radiological Environmental Monitoring Report
"I" APPENDIXB 1 ~,
/", '
2003 Radiological Environmental Monitoring Report "I"
APPENDIXB 1 ~,
/", '
2003 Radiological Environmental Monitoring Report B*l
AppendixB TABLE 1 (Page 1 of2)
Annual Analytical Schedule for the PPL Susquehanna Steam Electric Station Radiological Environmental 'Monitoring Program - 2003 Media & Code Airborne Particulates Airborne Iodine Sediment Fish Surface Water Well (ground)
Water (d)
Drinking Water (e)
Cow Milk Food Products (Potatoes)
Soil Direct Radiation No. of Sample Locations Freq.(a) 6 W
6 W
4 SA 2
SA 1
A 4
MC, M,or BWe 3
MC,Bwe 4(0 M. SM(!)
2 A
4 A
84 Q
Note: See footnotes at end of table.
Analyses Required Gross Beta (c)
Gamma Spectrometry 1-13 ]
Gamma Spectrometry Gamma Spectrometry (on edible portion)
Gross Beta 1-13 I Gamma Spectroscopy Tritium Gamma Spectroscopy Tritium Gross Alpha Gross Beta 1-131 Gamma Spectrometry Tritium 1-131 Gamma Spectrometry Gamma Spectrometry Gamma Spectrometry TLD 2003 Radiological Environmental Monitoring Report Analysis Freq. (b)
W QC W
SA SA M
BW M
M M
M M
M BW M
A Q
I AppendixB TABLE 1 (Page 1 of2)
Annual Analytical Schedule for the PPL Susquehanna Steam Electric Station Radiological Environmental 'Monitoring Program - 2003 Media & Code Airborne Particulates Airborne Iodine Sediment Fish Surface Water Well (ground)
Water (d)
Drinking Water (e)
Cow Milk Food Products (Potatoes)
Soil Direct Radiation No. of Sample Locations Freq.(a) 6 W
6 W
4 SA 2
SA 1
A 4
MC, M,or BWe 3
M*
MC,Bwe 4(0 M. SM(!)
2 A
4 A
84 Q
Note: See footnotes at end of table.
Analyses Required Gross Beta (c)
Gamma Spectrometry 1-13 ]
Gamma Spectrometry Gamma Spectrometry (on edible portion)
Gross Beta 1-13 I Gamma Spectroscopy Tritium Gamma Spectroscopy Tritium Gross Alpha Gross Beta 1-131 Gamma Spectrometry Tritium 1-131 Gamma Spectrometry Gamma Spectrometry Gamma Spectrometry TLD 2003 Radiological Environmental Monitoring Report Analysis Freq. (b)
W QC W
SA SA M
BW M
M M
M M
M BW M
A Q
B-2 I
Appelldix B (a)
W = weekly, BW = biweekly, BWC = biweekly composite, M = monthly, SM =
semi-monthly, Q = quarterly, QC =,quarterly composite, SA = semi-annually, A = annually, MC = monthly composite.
(b)
Codes are the same as for sample frequency.
(c)
If the gross beta activity were greater than 10 times the yearly mean of the control sample, gamma analysis would be performed on the individual filter. Gross beta analysis was performed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and thoron daughter decay.
(d)
Locations 6S6,657, and 2S7 were checked at least weekly to ensure that the automatic composite samplers were operational. Time proportional sampling was performed at locations 656, 657 and 2S7 the entire year. Station 6S5 was grab sampled weekly. Individual composites of the weekly samples were made both monthly (MC) and biweekly (BWC) for analysis.
(e)
Water from location 12H2 was retrieved weekly.
Composite samples of the weekly collections at this location were made both monthly (MC) and biweekly (BWC) for analysis.
Sampling at 12H2 was performed using an automatic continuous sampler (ACS) that was operated in the time proportional mode.
(f)
Locations lODI, IOD2, IOGl, and 12B2 were sampled semi-monthly from April through October.
2003 Radiological Environmental Monitoring Report Appelldix B (a)
W = weekly, BW = biweekly, BWC = biweekly composite, M = monthly, SM =
semi-monthly, Q = quarterly, QC =,quarterly composite, SA = semi-annually, A = annually, MC = monthly composite.
(b)
Codes are the same as for sample frequency.
(c)
If the gross beta activity were greater than 10 times the yearly mean of the control sample, gamma analysis would be performed on the individual filter. Gross beta analysis was performed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and thoron daughter decay.
(d)
Locations 6S6,657, and 2S7 were checked at least weekly to ensure that the automatic composite samplers were operational. Time proportional sampling was performed at locations 656, 657 and 2S7 the entire year. Station 6S5 was grab sampled weekly. Individual composites of the weekly samples were made both monthly (MC) and biweekly (BWC) for analysis.
(e)
Water from location 12H2 was retrieved weekly.
Composite samples of the weekly collections at this location were made both monthly (MC) and biweekly (BWC) for analysis.
Sampling at 12H2 was performed using an automatic continuous sampler (ACS) that was operated in the time proportional mode.
(f)
Locations lODI, IOD2, IOGl, and 12B2 were sampled semi-monthly from April through October.
2003 Radiological Environmental Monitoring Report
APPENDIXC
~...."
. r'.~
.~,. J
,1 '
2003 Radiological Environmental Monitoring Report C-l APPENDIXC
~...."
. r'.~
.~,. J
,1 '
2003 Radiological Environmental Monitoring Report C-l
I I Appendix C TABLECI (Page 1 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One Mile from the SSES(a) - See Fi2Ure 2 Location Distance Direction Description Code(b}
(miles)
IS2 0.2 N
Perimeter Fence 2S2 0.9 NNE Energy Infonnation Center 2S3 0.2 NNE Perimeter Fence 3S2 0.5 NE SSES Backup Met Tower 3S3 0.9 NE ANSP Riverlands Garden 3S4 0.3 NE Perimeter Fence 4S3 0.2 ENE Post, West of SSES APF 4S6 0.7 ENE.
Riverlands 5S4 0.8 E
West of Environmental Laboratory 5S7 0.3 E
Perimeter Fence 6S4 0.2 ESE Perimeter Fence (north) 6S9
.0.2 "
ESE Perimeter Fence (south) 7S6 0.2 SE Perimeter Fence 7S7 0.4 SE End ofK1ine's Road 8S2 0.2 SSE Perimeter Fence 9S2 0.2 S
Security Fence 10S1 0.4 SSW Post - south of switching station 10S2 0.2 SSW Security Fence 10S3 0.6 SSW Confer's Lane - east of Confer's Lane.
south of Towers Club l1S3 0.3 SW Security Fence l1S7 0.4 SW SSES Access Road Gate #50 12S1 0.4 WSW SSES West Building 2003 Radiological Environmental Monitoring Report I I Appendix C TABLECI (Page 1 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One Mile from the SSES(a) - See Fi2Ure 2 Location Distance Direction Description Code(b}
(miles)
IS2 0.2 N
Perimeter Fence 2S2 0.9 NNE Energy Infonnation Center 2S3 0.2 NNE Perimeter Fence 3S2 0.5 NE SSES Backup Met Tower 3S3 0.9 NE ANSP Riverlands Garden 3S4 0.3 NE Perimeter Fence 4S3 0.2 ENE Post, West of SSES APF 4S6 0.7 ENE.
Riverlands 5S4 0.8 E
West of Environmental Laboratory 5S7 0.3 E
Perimeter Fence 6S4 0.2 ESE Perimeter Fence (north) 6S9
.0.2 "
ESE Perimeter Fence (south) 7S6 0.2 SE Perimeter Fence 7S7 0.4 SE End ofK1ine's Road 8S2 0.2 SSE Perimeter Fence 9S2 0.2 S
Security Fence 10S1 0.4 SSW Post - south of switching station 10S2 0.2 SSW Security Fence 10S3 0.6 SSW Confer's Lane - east of Confer's Lane.
south of Towers Club l1S3 0.3 SW Security Fence l1S7 0.4 SW SSES Access Road Gate #50 12S1 0.4 WSW SSES West Building 2003 Radiological Environmental Monitoring Report
Appendix C TABLECI (page'2 of sj TLD 'Lo'catioris' for 'the S'SES' Radio)o~dca) Enviromliental Monitoring p~ogninf':"io03.
Less Than One l\\1i1e from the SSES(a) -: See Fieure 2 Location
.Code (b)
.. J2S3
.. 12S4
,12S5 12S6
.13S2 13S4 13S5 13S6 14S5 14S6 15S5'.
16S1 I6S2 6A4 SA3 15A3 16A2 Distance'"
. (miles)
.0.4 0.4 0.4
'0.4 0.4 Direction
. 'Description
- WSW.
- Penmeter.Fence
~.,
.. WSW
'~ :Perimeter Fence' wsw
~Perimetei Fence.
. WSW
'Perimeter Fence W
- PerimeteiFence
, W
.' Perimeter 0.4
. Former Laydown Area-west of Confer's Lane 0.5 0.7 0.3 0.3 0.6 0.9 0.9 O.S WNW Beach'Grove RoadlConfer's Larie:
~~
- WNW
- Beach Grove Road (pole)
NNW,;'
PerimeteiFence (east),
NNW Perimeter Fence (west)
ESE. ;,Restaurant (U.S. Route 11)
SSE.PPLWetlarids Sign (U. S. Route 11)
NW " Hosler Residence.,
... NNW,,"BenldnneyResidence' 1
~ ': _
'~'!: >~L. :)L~~<.~
From One to Five Miles from theSSES(~):::Soo-Fi2Ure"3 I2S7 1.1 -
. WSW 'Kisner Residence IBI 1.4' -.
2B3 1.3 NNE.... Leggeff&'Platt 2B4 1.4 NNE U.S. Route lllMingle Inn Road Intersection 5B3 1.6 E
PPL Switchyard 7B2 1.5 SE HeUer's Orchard Store SB2 1.4 SSE Lawall Residence C-3 2003 Radiological Environmental Monitoring'Report
\\J Appendix C TABLECI (page'2 of sj TLD 'Lo'catioris' for 'the S'SES' Radio)o~dca) Enviromliental Monitoring p~ogninf':"io03..,..
Less Than One l\\1i1e from the SSES(a) -: See Fieure 2
~
Location
.Code (b)
.. J2S3..,
.. 12S4
,12S5 12S6
.13S2 13S4 13S5 13S6 14S5 14S6 15S5'. :,;
16S1 I6S2 6A4 SA3 15A3 16A2 Distance'"
. (miles)
.0.4 0.4 0.4*.':
0.4 '.'
'0.4 0.4 Direction
. 'Description to ** '
'.... :...... '. ~"". -.
- WSW.
- ... :Penmeter.Fence.......
L......
if
~., ** '
.... 1'-<<,.,-
.. WSW
'~ :Perimeter Fence'. : '
wsw... ~Perimetei Fence.
. WSW
'Perimeter Fence 'I J
W
!IPerinieter.Fence*, _.............. '
"., W*** : :PerimeteiFence i
, W
.' Perimeter Fence'* '
I < I
- 0.4
.:),.J :.:iW,':". Former Laydown Area-west of Confer's Lane.': r 0.5 0.7
',;.:;,.0.4 "
0.3 0.3 0.6 0.9 0.9 O.S WNW.' Beach'Grove RoadlConfer's Larie:
~~.
- WNW.ll ;Beach Grove Road (pole)
NNW,;',,' PerimeteiFence (east),
r...
NNW Perimeter Fence (west)
ESE. ;,Restaurant (U.S. Route 11)
SSE.PPLWetlarids Sign (U. S. Route 11)
NW " Hosler Residence.,
... NNW,,"BenldnneyResidence'
..* i 1
~ ': _
'~'!: >~L. :)L~~<.~ (i".. =c '//.
From One to Five Miles from theSSES(~):::Soo-Fi2Ure"3 -... :';
I2S7
... 1.1 -
. WSW 'Kisner Residence
... IBI 1.4' -.
I,'*
- o*
.. 2B3 1.3 NNE.... Leggeff&'Platt 2B4 1.4 NNE U.S. Route lllMingle Inn Road Intersection 5B3 1.6 E
PPL Switchyard 7B2 1.5 SE HeUer's Orchard Store SB2 1.4 SSE Lawall Residence C-3 2003 Radiological Environmental Monitoring'Report
I,
Appendix C (page,3 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 From One to Five Miles from the SSES(a) - See Fi~re 3
,~,'-
Location Distance. ;
Direction
~escription Code (b)
(miles)'"
'-'9Br 1.3'.,.
... S Transmission Line -'east of Route 11
.. lOB2 2.0 ---....... SSW.~-,.* AIgatt Re'siderice '.
IOB3 1.7.
. Castek Inc;.
- ) '.. /
.. IOB4 1.4
.~.---- SSW' "" u. S; Route lllRiver Road Intersection 12B4 1.7
- Berger. Fann 13Bl 1.3
' : Walker Run Creek (fele.PoIe #36) 14B3 1.3
, Moskaluk Residence ISBl:
, ~'1.7;*.
. Country Estates Trailer Park I6B2 Walton Power Line" '.
I llC2 2.0 MP Metals (U.S. Rotite 11)
IDS 4.0
.. ShickshinnylMoeanaqua Sewage Treatment PIt.
6DI 3.S
' ESE.:
St. Peters Church:: Hobbie 8D3 4.0
'.SSE "
Mowry 904 3.6
' S', J '.' Country Folk Store"':
1001
. SSW,:,:' :R~ & C. Ryman Farm 12D2 3.7
- WSW, Dagostin Residence ",
1401 3.6 WNW:,
Moore's HilllMingleInn Roads Intersection 3EI 4.7 NE Webb Residence - Lilly Lake 4E2 4.7 ENE Ruckles HiIVPond Hin Roads Intersection
.SE2 4.S E "
BlossFann 6EI 4.7 ESE; St.;Jarries Church 2093 Radiological Environmental Monitoring Report C-4 I,
Appendix C
,.-.. ~.. '
, TABLE'CI (page,3 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003
."...... \\~.. '.
From One to Five Miles from the SSES(a) - See Fi~re 3
,~,'-
Location Distance. ;
Direction
\\
~escription Code (b)
(miles)'"
i '-'9Br 1.3'.,.
..... S Transmission Line -'east of Route 11
.. lOB2 2.0 ---....... SSW.~-,.* AIgatt Re'siderice '.
IOB3 1.7.
. Castek Inc;.
- ) '.. /
.. IOB4 1.4
.~.---- SSW' "" u. S; Route lllRiver Road Intersection 12B4 1.7
'.. ~ - '*WSW'*,. ; Berger. Fann 13Bl 1.3 W*.... ' : Walker Run Creek (fele.PoIe #36) 14B3 1.3 WNW*;', Moskaluk Residence ISBl:
, ~'1.7;*. :.,.
.NW... Country Estates Trailer Park I6B2 h71'!', \\'.NNW*.'* Walton Power Line" '.
I llC2 2.0
'. :**SW*
MP Metals (U.S. Rotite 11)
IDS 4.0 N
.. ShickshinnylMoeanaqua Sewage Treatment PIt.
6DI 3.S
' ESE.:
St. Peters Church:: Hobbie 8D3 4.0
'.SSE "
Mowry Residence*'
'j 904 3.6
' S', J '.' Country Folk Store"':
1001 3.0:".:'*.,
. SSW,:,:' :R~ & C. Ryman Farm 12D2 3.7
- WSW, Dagostin Residence ",
1401 3.6 WNW:,
Moore's HilllMingleInn Roads Intersection 3EI 4.7 NE Webb Residence - Lilly Lake
' ___ 4E2 4.7 ENE Ruckles HiIVPond Hin Roads Intersection
.SE2 4.S E "
BlossFann 6EI 4.7 ESE; St.;Jarries Church 2093 Radiological Environmental Monitoring Report C-4
APPelldix C TABLECI (page 4 of 5)
TLD for the SSEs Radiological Environmentai Monitoring Program -2003 From One to Five Miles from the SSEs(a).: See Figure 3 Location Distance DireCtion'-'
Descript~on Code(b)
'(miles)
J 7EI
' 4.2 SEt"
" Harwood Transmission Line Pole #2 llE1 4.7 SW Thomas Residence 12EI 4.7 WSW" Berwick Hospital 13E4 4.1 W
Kessler Fann Greater than Five Miles from the SSES(a) - See Figure 4.
2Fl 5.9 NNE St. Adalberts Cemetery.
SF2 8.5 SSE Huff Residence 12F2 5.2 WSW' I 'Beiwick Substation 15Fl
'5.4 NW Z8watSki Fann 16Fl
'7.S'
'NNW, Hidlay Residence 3G4
, 17..
NE Wilkes Barre Service Center
' 14
.ENE"
,Mountaintop - Crestwood Industrial Park 6G1.
.:13.5 ESE' Freeland Substation 7Gl 14
,"SE "," HazletonPP&L Complex:,.
7G2 12 SE Hazleton Cemetery - 14th Street SG1
'12
' SSE' PPL'SFC ;;"HumboltIndustriaI Park' '
12G1' 15 '
.. 'WSW'
' PPL Service Center. Bloomsburg.
~
12G4 10 WSW Naus Residence c-s 2003 Radiological Environmental Monitoring Report APPelldix C TABLECI (page 4 of 5)
TLD *LoCationS for the SSEs Radiological Environmentai Monitoring Program -2003 From One to Five Miles from the SSEs(a).: See Figure 3 Location Distance DireCtion'-',
, ~ : ~...;;
Descript~on Code(b),.,. '(miles)
.,'_I.,
J 7EI
' 4.2 SEt"
" Harwood Transmission Line Pole #2 llE1 4.7 SW Thomas Residence 12EI 4.7 WSW" Berwick Hospital 13E4 4.1 W
Kessler Fann Greater than Five Miles from the SSES(a) - See Figure 4.
2Fl 5.9 NNE St. Adalberts Cemetery.
SF2 8.5 SSE Huff Residence 12F2 5.2 WSW' I 'Beiwick Substation
,.1 '
15Fl
' '5.4 NW Z8watSki Fann 16Fl
'7.S'
'NNW, Hidlay Residence 3G4
, 17..
NE Wilkes Barre Service Center r ** ;
4GI,*
' 14
.:.ENE"
,Mountaintop - Crestwood Industrial Park 6G1..,
.:13.5 ESE' Freeland Substation ', :..
7Gl 14
,"SE "," HazletonPP&L Complex:,.
7G2 12 SE Hazleton Cemetery - 14th Street SG1
'12
' SSE' PPL'SFC ;;"HumboltIndustriaI Park' '
12G1' 15 '
.. 'WSW'
' PPL Service Center. Bloomsburg. '.
~
12G4 10 WSW Naus Residence c-s 2003 Radiological Environmental Monitoring Report
Appendix C TABLECI (Page 5 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 a)
All distances from the SSES ~o monitoring locations are measured from the standby gas treatment vent at 442001N34117 (pa. Grid System). The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations 'are on site (wfthin the site boundary) or, if they are not on site, the approximate distances of the locations from the SSES as described below:
S -on site A- <1 mile B 2 miles C 3 miles D 4 miles E-4-5 miles F 10 miles G 20 miles H- >20miles The numbers preceding'the letters'in rhe location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity. with the SSES at the center of the circle. The middle of sector i is directed due north (N). Moving clockwise from sector 1, the sector immediately adjacent to sector 1 is sector 2, the middle of which is directed due ~orth, northeast (NNE). Continuing to move clockwise, the sector numbers increase to I~, which is the north, northwest sector.
The numbers following the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.
2003 Radiological Environmental Monitoring Report C-6 I I Appendix C TABLECI (Page 5 of 5)
TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 a)
All distances from the SSES ~o monitoring locations are measured from the standby gas treatment vent at 442001N34117 (pa. Grid System). The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations 'are on site (wfthin the site boundary) or, if they are not on site, the approximate distances of the locations from the SSES as described below:
S -on site A- <1 mile B 2 miles C 3 miles D 4 miles E-4-5 miles F 10 miles G 20 miles H- >20miles The numbers preceding'the letters'in rhe location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity. with the SSES at the center of the circle. The middle of sector i is directed due north (N). Moving clockwise from sector 1, the sector immediately adjacent to sector 1 is sector 2, the middle of which is directed due ~orth, northeast (NNE). Continuing to move clockwise, the sector numbers increase to I~, which is the north, northwest sector.
The numbers following the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.
2003 Radiological Environmental Monitoring Report C-6 I I
Atmendix C TABLEC2 (pagelof4)
Sampling LOCations for the SSES Radiological Environmentill Monitoring Program ~ 2003 Less Than One Mile from the SSES(a)
See Figure 5 Location Code Distance Direction Description (miles)
- ,<~~;~*t~.-',:;*c* It;*.~
,.:~.':;:.,
:~
~':'>,:'i"'SURFACE:WATER'"
- .'B~
- ,.~:~~(~;: J(:~
,~:{:'~~:
2S7 OJ NNE; Cooling Tower BIowdown Line' 6S5 0.9
. ESE Outfall Area 6S6 0.8 ESE Water Intake Line 6S7 0.4 ESE Cooling Tower Blowdown Line (alternate for 2S7)
LTAW NE;.ESE Lake Took.:A-While (on site)
'~::*:.:~*::~~t~:~>":~*:~*:~~~:~;~'~~~j:*~:' ;¢~;'~ ~~~<:;'.~::~~~ ~:~ ~;:-~,~~.~~ ~:~~.r~:~:\\:~,;~::t~1~*~~*;~;)FISH,;t:!:~*~':~f*~*~).~*;~.~'~ ~::~.~.
~:;
- .:~:
~"'-,"',.
LTAW NE-ESE,. Lake Took.!A-While (on site)
~~**>'~?>2:*::L~:
'2.'*:"f~,,;:-:;,.r;*;'>';;SEDIMENT(c)':";* :.~[;.("
'~l' '
':'~~
.~"~~,."(~:-:>;)i.r!~~'i ",~"
,:'.~~~
,,:.;.:~.
~
- ',~Jry.:*t:H~:::
LTAW NE-ESE Lake Took-A-While (on site)
- ~""~,
- <:,::( ~:(:.4~::;:~:::*~/:(\\:}c.t;;~*\\'.2 i.'~'.::'
~~ ':q.~: F~
t~!'
",;:-;~:;:~,: ::~i:" ::~*ot)/*)~.;;:<~.,
":'~:~".!';',
~'
"3S2 0.5 NE SSES Backup Meteorological Tower 12S1 0.4 SSES WesfBiIilding 13S6"
'0.4'
'PormerLaydown Area, WesfofConfers Lane' f:*~~'?~~~?i.:.~:'(!7*_t*7'.*~:~ ;;~~ :.~.:~ !::".~:::=#t=I~~*~.'~~ ;i.:,:*;:~~~~( y~t:~?7~~t!t~SOIU;}~: {;::~~. ::':~~.:~;~T
- ~f~~1~i
- ~ T1~~Y:\\~;',~~j-:~t?;~:~
3S2
'0.5 NE
'SSES Backup Meteorological Tower 12S1 0.4' SSES West Building' 13S6 0.4'"
'W F01Tl1er Layd6wn'Area, West of Confers Lane 2003 Radiological Em'ironmental Monitoring Report
Appendix C TABLEC2 (Page 2 of 4)
Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One l\\'liIe from the SSES(&)
- See Figure 5 Location Distance Direction Description Code (miles)
- ~\\:.~;~', :_~:*,;.~~i;:*(',s*.;:Y~f
- ~:,:;;':'::; ~£~~-lt; GROUND,WATER;~;;;::!I~{:.~f\\~",~::~::,':~::-:-,:t:,
2S2 0.9
'. '. NNE -,
SSES Energy Infonnation Center 4S4 0.5 ENE, SSES Learning Center From One to Five Miles From the SSES
- See Figure 6
~ "~i~.<:,;;.:::*:t:i:.'\\~~""
'~:'!t~/;:i:\\.rj:-:)i,'In?f~';:;:~';::f;)>;'; FISW~!;':A:;;-"~;: ::~'~~S:'j,:',~:;:,!;;,:~;n;; 't~,',ll~,~.<~
IND 0.9 - 1.4 ESE At or Below the SSES Discharge Diffuser 2B 1.6
-NNE Gould Island 7B 1.2 SE Bell Bend' lOD1 3.0,
_ SSW,_. R. & C: Ryman Farm
'3.1 SSW Raymond Ryman Fann 12B2 1.7 WSW _,
Berger Fann I1D2 3.5 Lupini Field-U.S. Route 93.
2003 Radiological Environmental Monitoring Report e-g I I Appendix C TABLEC2 (Page 2 of 4)
Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One l\\'liIe from the SSES(&)
- See Figure 5 Location Distance Direction Description Code (miles)
- ~\\:.~;~', :_~:*,;.~~i;:*(',s*.;:Y~f
- ~:,:;;':'::; ~£~~-lt;.: GROUND,WATER;~;;;::!I~{:.~f\\~",~::~::,':~::-:-,:t:, -,
~.
2S2 0.9
'. '. NNE -,
SSES Energy Infonnation Center 4S4 0.5 ENE, SSES Learning Center From One to Five Miles From the SSES
- See Figure 6
~ "~i~.<:,;;.:::*:t:i:.'\\~~""
'~:'!t~/;:i:\\.rj:-:)i,'In?f~';:;:~';::f;)>;'; FISW~!;':A:;;-"~;: ::~'~~S:'j,:',~:;:,!;;,:~;n;; 't~,',ll~,~.<~. >"' ~ "
- -:~ _.'::"~~~,
IND 0.9 - 1.4.. - ',.' ESE ':'
At or Below the SSES Discharge Diffuser 2B 1.6
-NNE Gould Island 7B 1.2 SE Bell Bend' lOD1 3.0,
_ SSW,_. R. & C: Ryman Farm
_,_10D2
. '3.1 SSW Raymond Ryman Fann 12B2 1.7 WSW _,
Berger Fann I1D2 3.5 Lupini Field-U.S. Route 93.
2003 Radiological Environmental Monitoring Report e-g I I
AppendixC TABLEC2 (page 3 of 4)
Samplhig LOcations fo'r the SSES
., Radiological Environmental Mo'nitoring Program ~ 2003 Greater than Five Miles from the SSES(a) - See Figure 7 Location' Code 12H2 2H 12F 6G1 8G1 8G1 lOG1 12F3 C-9 Distance (miles) 26 30
~
Direction Description wsw Danville.Water Co. (treated)
NNE' Near Falls. Pa.
6.9
'WSW.'
Old Berwick Test Track 13.5 ESE Freeland Substation 12 SSE PPL SFC - Humbo1t Industrial Park
,12 SSE PPL SFC - Humbolt Industrial
,SSW, Farm 5.2 WSW Berwick Water Company 2003 Radiological Environmental Monitoring Report AppendixC TABLEC2 (page 3 of 4)
Samplhig LOcations fo'r the SSES
., Radiological Environmental Mo'nitoring Program ~ 2003 Greater than Five Miles from the SSES(a) - See Figure 7 Location' Code 12H2 2H 12F 6G1 8G1 8G1 lOG1 12F3 C-9 Distance (miles) 26 30
."\\
~
i
~
Direction
. Description wsw Danville.Water Co. (treated)
NNE' Near Falls. Pa.
6.9 ;. -.- 'WSW.'
Old Berwick Test Track 13.5 ESE Freeland Substation 12 SSE PPL SFC - Humbo1t Industrial Park
,12 SSE.'
PPL SFC - Humbolt Industrial Park*
- 14
,SSW,.. *Davis Farm 5.2 WSW Berwick Water Company
).
2003 Radiological Environmental Monitoring Report
AppendixC TABLEC2 (Page 4 of 4)
Sat:npling Locations for th~ SSES Radiological Environmental Monitoring Program - 2003 a)
AU distances from the SSES to monitoring locations are measured from the standby gas treatment vent at 442001N34117 (Pa. Grid System. The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations are on site (within the site boundary) or, jf they are not on site, the approximate distances of the locations from the SSES as described below:
S -on site A - <1 mile B 2 miles C 3 miles D 4 miles E-4-5 miles F 10 miles G 20 miles H- >20 miles The numbers preceding the letters in the location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total 'of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity, with the SSES at the center of the circle. The middle of sector 1 is directed due north (N). Moving clockwise from secto~ 1, the s.ectorimmediately adjacent to sector 1 is sector 2, the middle,of which is directed due north, northeast (NNE). Continuing to move clockwise, the sector numbers increase to 16, which is the north, northwest sector.
The numberS folJowing the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.
b)
No actual location is indicated since fish are sampled over an area which extends through 3 sectors (5, 6, 7) near the outfall area.
c)
No pennanent locations exist; samples are taken based on availability.
Consequently, it is not necessary to assign a number fonowing the letter in the location code.
2003 Radiological Environmental Monitoring Report I I AppendixC TABLEC2 (Page 4 of 4)
Sat:npling Locations for th~ SSES Radiological Environmental Monitoring Program - 2003 a)
AU distances from the SSES to monitoring locations are measured from the standby gas treatment vent at 442001N34117 (Pa. Grid System. The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations are on site (within the site boundary) or, jf they are not on site, the approximate distances of the locations from the SSES as described below:
S -on site A - <1 mile B 2 miles C 3 miles D 4 miles E-4-5 miles F 10 miles G 20 miles H- >20 miles The numbers preceding the letters in the location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total 'of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity, with the SSES at the center of the circle. The middle of sector 1 is directed due north (N). Moving clockwise from secto~ 1, the s.ectorimmediately adjacent to sector 1 is sector 2, the middle,of which is directed due north, northeast (NNE). Continuing to move clockwise, the sector numbers increase to 16, which is the north, northwest sector.
The numberS folJowing the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.
b)
No actual location is indicated since fish are sampled over an area which extends through 3 sectors (5, 6, 7) near the outfall area.
c)
No pennanent locations exist; samples are taken based on availability.
Consequently, it is not necessary to assign a number fonowing the letter in the location code.
2003 Radiological Environmental Monitoring Report C*lO I I
APPENDIXD t 2003 Radiological Environmental Monitoring Report '
,r r,,,,
f;. "
APPENDIXD
.;i t 2003 Radiological Environmental Monitoring Report '
D*l
Appendix D 2003 LAND USE CENSUS RESULTS The SSES Technical Requirements require that a census be conducted annually during the growing season to detennine the location of the nearest milk animal, residence and garden greater than 50 m2 (approx. 500 ft2) producing broad leaf vegetation within a distance of 8 km (approx. 5 miles) in each of the 16 meteorological sectors surrounding the SSES. To comply with this requirement, a land-use census was conducted for the SSES during 2003.
A comparison of the 2002 and 2003 Land Use Census results for the SSES indicates the changes listed in the tables below. TabJes 1 display the changes in the nearest gardens and Table 2 displays the changes in sampling of irrigated foods from 2002 to 2003.
Overall, the changes since the 2002 Land Use Census were minimal. In 2003, the nearest garden in sector 5 was revised from 1.4 miles to 1.8 miles from the There was no garden identified in sector 14 which met the requirements for sampling in 2003. The farm identified in 2002 (P. Moskaluk, Jr.) in sector 14. did not plant a garden in 2003.
TABLEt CHANGE FROM 2002 TO' 2003'IN NEAREST GARDENS AS DETERMINED BY THE 2003 LAND USE CENSUS 2002 2003 Distance Distance Sectorl Owner's fromSSES Owner's fromSSES Direction Name (mi.)
Name (mi.)
51E KozlowskilWitts 1.4 W. Daily 1.8 14IWNW P. Moskaluk. Jr.
1.3 N/A N/A These changes in gardens had no impact on the intended sampling of fruits and vegetables during 2003. Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway.
Radiological Environmental Monitoring Report Appendix D 2003 LAND USE CENSUS RESULTS The SSES Technical Requirements require that a census be conducted annually during the growing season to detennine the location of the nearest milk animal, residence and garden greater than 50 m2 (approx. 500 ft2) producing broad leaf vegetation within a distance of 8 km (approx. 5 miles) in each of the 16 meteorological sectors surrounding the SSES. To comply with this requirement, a land-use census was conducted for the SSES during 2003.
A comparison of the 2002 and 2003 Land Use Census results for the SSES indicates the changes listed in the tables below. TabJes 1 display the changes in the nearest gardens and Table 2 displays the changes in sampling of irrigated foods from 2002 to 2003.
Overall, the changes since the 2002 Land Use Census were minimal. In 2003, the nearest garden in sector 5 was revised from 1.4 miles to 1.8 miles from the SSES.
There was no garden identified in sector 14 which met the requirements for sampling in 2003. The farm identified in 2002 (P. Moskaluk, Jr.) in sector 14. did not plant a garden in 2003.
TABLEt CHANGE FROM 2002 TO' 2003'IN NEAREST GARDENS AS DETERMINED BY THE 2003 LAND USE CENSUS 2002 2003 Distance Distance Sectorl Owner's fromSSES Owner's fromSSES Direction Name (mi.)
Name (mi.)
51E KozlowskilWitts 1.4 W. Daily 1.8 14IWNW P. Moskaluk. Jr.
1.3 N/A N/A These changes in gardens had no impact on the intended sampling of fruits and vegetables during 2003. Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway.
- 2003 Radiological Environmental Monitoring Report D*2 I I
Irrigated fruits and vegetables were monitored at 2 indiCator locations during 2003. The only crop irrigated in 2003 was potatOes; : No other' fields within 10 miles downriver of the SSES were irrigated in 2003, because wet weather prevailed much of the spring and summer."
TABLE 2 CHANGE FROM 2002 TO '2003 IN VEGETABLES IRRIGATED WITH SUSQUEHANNA RIVER WATER FROM DO\\VNSTREAM OF THE SSES SectorlDirection I1F21SW I1D2ISW D-3 DISCHARGE DURING 2003 Distance fromSSES Owner.
(mi.)
Chapin (Drake) Farm 5.5 Lupini Farm (Rt. 93) 3.5
- 2002, 2003 N/A' Potatoes N/A' Potatoes 2003 Radiological Environmental Monitoring Report Irrigated fruits and vegetables were monitored at 2 indiCator locations during 2003. The only crop irrigated in 2003 was potatOes; : No other' fields within 10 miles downriver of the SSES were irrigated in 2003, because wet weather prevailed much of the spring and summer."
TABLE 2 CHANGE FROM 2002 TO '2003 IN VEGETABLES IRRIGATED WITH SUSQUEHANNA RIVER WATER FROM DO\\VNSTREAM OF THE SSES SectorlDirection I1F21SW I1D2ISW D-3 DISCHARGE DURING 2003 Distance fromSSES Owner.
(mi.)
Chapin (Drake) Farm 5.5 Lupini Farm (Rt. 93) 3.5 "I' '
~..!.'"
"f ~,
,I f
..,: ~ f
- , f"'; :
i.': ~
- 2002, 2003 N/A' Potatoes N/A' Potatoes 2003 Radiological Environmental Monitoring Report
AppendixD TABLE 3 Nearest residence, garden, and dairy anima] in each of the 16 meteorological sectors within a 5-miIe radius of the Susquehanna Steam Electric Station, 2003.
NEAREST NEAREST SECTOR DIRECTION RESIDENCE GARDEN 1
N 1.3 mi 3.2mi 2
NNE 1.0mi 2.3 mi i 3
NE O.9mi 2.7mi 4
ENE 2.1 mi 2.4 mi a,c,d,f,1 5
E 1.4 mi ll,C 1.8 mi 6
ESE O.5mi 2.5 mi 7
SE 0.5 mi 0.6 mi 8
SSE 0.6 mi 1.5 mi 9
S 1.0mi 1.1 mi 10 SSW 0.9mi 1.2mi 11 SW 1.5 mi 1.9mi 12 WSW 1.1 mi 1.1 mi 13 W
1.2 mi 1.2 mi 14 WNW 0.8mi
>5.0mi 15 NW 0.8mi 16 NNW 0.6mi a Chickens raised for consumption at this location.
b Ducks raised for consumption at this location.
C Eggs consumed from chickens at this location.
d Geese raised for consumption at this location.
e Pigs raised for consumption at this location.
f Turkeys raised for consumption at this location.
1.8 mi 1 4.0mi S Fruits/vegetables raised for consumption at this location.
b Rabbits raised for consumption at this location.
- i Beef cattle raised for consumption at this location.
j Goats raised for consumption at this location.
- Ie Pheasants raised for consumption at this location.
- I Sheep raised for consumption at this location.
NEAREST.
DAIRY ANIMAL
>5.0 mi
>5.0 mi
>5.0 mi
>5.0 mi 4.5 mi g 2.7 mi
>5.0' mi
>5.0 mi
>5.0 mi 3.0 mi ll,b,c.d,e,g
>5.0 mi 1.7 mi g.i 5.0 mi g
>5.0 mi
>5.0mi 4.2mi
- No locations were identified as raising rabbits, goats, and pheasants during 2003.
2003 Radiological Environmental Monitoring Report D4 AppendixD TABLE 3 Nearest residence, garden, and dairy anima] in each of the 16 meteorological sectors within a 5-miIe radius of the Susquehanna Steam Electric Station, 2003.
NEAREST NEAREST SECTOR DIRECTION RESIDENCE GARDEN 1
N 1.3 mi 3.2mi 2
NNE 1.0mi 2.3 mi i 3
NE O.9mi 2.7mi 4
ENE 2.1 mi 2.4 mi a,c,d,f,1 5
E 1.4 mi ll,C 1.8 mi 6
ESE O.5mi 2.5 mi 7
SE 0.5 mi 0.6 mi 8
SSE 0.6 mi 1.5 mi 9
S 1.0mi 1.1 mi 10 SSW 0.9mi 1.2mi 11 SW 1.5 mi 1.9mi 12 WSW 1.1 mi 1.1 mi 13 W
1.2 mi 1.2 mi 14 WNW 0.8mi
>5.0mi 15 NW 0.8mi 16 NNW 0.6mi a Chickens raised for consumption at this location.
b Ducks raised for consumption at this location.
C Eggs consumed from chickens at this location.
d Geese raised for consumption at this location.
e Pigs raised for consumption at this location.
f Turkeys raised for consumption at this location.
1.8 mi 1 4.0mi S Fruits/vegetables raised for consumption at this location.
b Rabbits raised for consumption at this location.
- i Beef cattle raised for consumption at this location.
j Goats raised for consumption at this location.
- Ie Pheasants raised for consumption at this location.
- I Sheep raised for consumption at this location.
NEAREST.
DAIRY ANIMAL
>5.0 mi
>5.0 mi
>5.0 mi
>5.0 mi 4.5 mi g 2.7 mi
>5.0' mi
>5.0 mi
>5.0 mi 3.0 mi ll,b,c.d,e,g
>5.0 mi 1.7 mi g.i 5.0 mi g
>5.0 mi
>5.0mi 4.2mi
- No locations were identified as raising rabbits, goats, and pheasants during 2003.
2003 Radiological Environmental Monitoring Report D4 I I U!
V
APPENDIXE 2003 Radiological Environmental Monitoring Report E-1 APPENDIXE
- r
.j,
':i i'
- ,", * ~' t "
I; I"
.,;1 i'.'
2003 Radiological Environmental Monitoring Report -
E-1
AppendixE TLD MEASUREMENTS The PPL dosimetry system used for monitoring ambient radiation levels in the environment consists of Panasonic 710A readers and Panasonic UD-S14 TLDs. The UD-SI4 TLD badges each contain four elements. Elements 2, 3, and 4 in each badge are made of calcium sulfate with SOO mg/cm2 of filtering and element 1 is composed of Hthium tetraborate with filtering of 25 mg/cm2* Only the calcium sulfate elements are normally used for environmental measurements because of their higher Jight output per unit of radiation exposure relative to the lithium tetraborate and, consequently, greater sensitivity for the detection and measurement of radiation.
Note: Element 1 would be of value in the event ofan unusually large release of noble gases, especialIy xenon, that would produce relatively low-energy X-ray or gamma emissions. This is because the lithium tetraborate does not over-respond to such low-energy emissions as does the calcium sulfate.
The TLD element manufacturers' attempt to make each element as similar as possible to each of the other elements in each batch that is produced. Nevertheless, each element ends up somewhat different in its resp~nse to radiation. In order to minimize the effect of these inherent differences when comparing actual monitoring results for different' elements, Element Correction Factors (ECFs) are determined for each element. The ECFs are used to effectively, normaIiz~ the. readings of the field elements placed at particular monitoring locations for given. monitoring periods to the average of the readings that would De expected if so-called elements were to be placed simultaneously at those individual locations. Reference elements are elements that have been demonstrated to display superior measurement performance.
The selection process for reference elements involves repeatedly irradiating a large set of elements, processing them, calculating the mean response for each set of elements, and evaluating the deviation of each individual element response from the mean response. After this process has been repeated at least several times, the elements with the least variability in their responses and with mean responses nearest to the. mean response of the entire population of elements are chosen as reference elements.
To determine ECFs for individual field elements, the elements are first exposed to known amounts of radiation (100 mR) and processed, a minimum of three times each.
Each element reading is then divided by the mean of the readings obtained from reference elements (typically 30 to 35) that were exposed to the same amounts of radiation as the elements for which the ECFs are being determined and that were processed at the same time as these elements. The mean quotient (ratio) is then calculated for each element by summing the quotients obtained for each processing and then dividing by the total number of the processings performed.
2003 Radiological Environmental Monitoring Report E-2 I I AppendixE TLD MEASUREMENTS The PPL dosimetry system used for monitoring ambient radiation levels in the environment consists of Panasonic 710A readers and Panasonic UD-S14 TLDs. The UD-SI4 TLD badges each contain four elements. Elements 2, 3, and 4 in each badge are made of calcium sulfate with SOO mg/cm2 of filtering and element 1 is composed of Hthium tetraborate with filtering of 25 mg/cm2* Only the calcium sulfate elements are normally used for environmental measurements because of their higher Jight output per unit of radiation exposure relative to the lithium tetraborate and, consequently, greater sensitivity for the detection and measurement of radiation.
Note: Element 1 would be of value in the event ofan unusually large release of noble gases, especialIy xenon, that would produce relatively low-energy X-ray or gamma emissions. This is because the lithium tetraborate does not over-respond to such low-energy emissions as does the calcium sulfate.
The TLD element manufacturers' attempt to make each element as similar as possible to each of the other elements in each batch that is produced. Nevertheless, each element ends up somewhat different in its resp~nse to radiation. In order to minimize the effect of these inherent differences when comparing actual monitoring results for different' elements, Element Correction Factors (ECFs) are determined for each element. The ECFs are used to effectively, normaIiz~ the. readings of the field elements placed at particular monitoring locations for given. monitoring periods to the average of the readings that would De expected if so-called reference* elements were to be placed simultaneously at those individual locations. Reference elements are elements that have been demonstrated to display superior measurement performance.
The selection process for reference elements involves repeatedly irradiating a large set of elements, processing them, calculating the mean response for each set of elements, and evaluating the deviation of each individual element response from the mean response. After this process has been repeated at least several times, the elements with the least variability in their responses and with mean responses nearest to the. mean response of the entire population of elements are chosen as reference elements.
To determine ECFs for individual field elements, the elements are first exposed to known amounts of radiation (100 mR) and processed, a minimum of three times each.
Each element reading is then divided by the mean of the readings obtained from reference elements (typically 30 to 35) that were exposed to the same amounts of radiation as the elements for which the ECFs are being determined and that were processed at the same time as these elements. The mean quotient (ratio) is then calculated for each element by summing the quotients obtained for each processing and then dividing by the total number of the processings performed.
2003 Radiological Environmental Monitoring Report E-2 I I
~-
Appendix E The following equation shows how ECFs,are calculated:
where
~ ~
an uncorrected exp'osure reading for the 'element.
n =the total number of individual element exposures averaged.
Er~/ = the mean of tlie ECF~corrected exposure readings of the reference elements.
Irradiated control1LDs are processed (read) with the batches of TI.Ds from the field to provide both processing calibration information and quality control. Field control 11.Ds, which accompany the field TLDs when they are being taken to their monitoring locations and subsequently retrieved from these locations, and cave control TLDs, which are stored with the field TLDs for the periods between annealing and field distribution and between retrieval from the field' and processing, are also read with the field 11.Ds to provide checks on the exposures that the field TIDs might receive on their way to and from their monitoring locations arid while in storage, respectively.
The raw data from the field 11.D processings is Run Calibration Factor (RCF) corrected using the irradiated control1LD data. The irradiated control 11.Ds are exposed to 100 mR from a cesium-137 source at the Battelle Lab in Richland WA. The irradiated 11.Ds are accompanied en route to and from the: Battelle Lab by:transit control 11.Ds. An estimate of the exposures received by the irradiated 11.Ds in-transit is obtained by processing the transit controls and determining the transit control mean by the following equation:
where the mean of the elementally corrected exposure readings of all the transit control elements.
the uncorrected exposure reading of each individual transit control element:
Radiological Environmental Monitoring Report
~~
~
~-
Appendix E The following equation shows how ECFs,are calculated:
where
-it' E 2;-::-L
'1 EuJ ECF= ': n
. (,
t ~ ~ -: #:
an uncorrected exp'osure reading for the 'element.
- "'-; ; ';' )1' :;,. ""
n =the total number of individual element exposures averaged.
Er~/ = the mean of tlie ECF~corrected exposure readings of the reference elements.
Irradiated control1LDs are processed (read) with the batches of TI.Ds from the field to provide both processing calibration information and quality control. Field control 11.Ds, which accompany the field TLDs when they are being taken to their monitoring locations and subsequently retrieved from these locations, and cave control TLDs, which are stored with the field TLDs for the periods between annealing and field distribution and between retrieval from the field' and processing, are also read with the field 11.Ds to provide checks on the exposures that the field TIDs might receive on their way to and from their monitoring locations arid while in storage, respectively.
The raw data from the field 11.D processings is Run Calibration Factor (RCF) corrected using the irradiated control1LD data. The irradiated control 11.Ds are exposed to 100 mR from a cesium-137 source at the Battelle Lab in Richland WA. The irradiated 11.Ds are accompanied en route to and from the: Battelle Lab by:transit control 11.Ds. An estimate of the exposures received by the irradiated 11.Ds in-transit is obtained by processing the transit controls and determining the transit control mean by the following equation:
where E*3
, n
. } '<;-
-i' _',.
the mean of the elementally corrected exposure readings of all the transit control elements.
the uncorrected exposure reading of each individual transit control element:
"",2003 Radiological Environmental Monitoring Report f -
~~
1
~
AppendixE ECP; = the elemental correction factor of each individual transit control element.
n =
the total number of individual element exposures averaged.
The mean of the transit control exposures is then subtracted from each of the elementally corrected exposures of the irradiated elements to obtain the net exposures for each element resulting from the irradiation. The mean of these net exposures is then divided by the known exposure (100 mR) from the irradiation to determine the ReF.
The following equation describes the calculations performed:
where
+/-(~-E RCF==---------~
RCF = the run correction factor for an individual field monitoring element.
E/ =
the exposure reading of each individual irradiated control element.
ECP; = the elemental correction factor of each individual irradiated control element.
n =
the total number of individual element exposures averaged.
KEic = the known exposure for each of the irradiated control elements.
Exposure readings for individual field monitoring elements are corrected using the appropriate mean transit exposure and the elemental and run correction factors as follows:
where CE =
x the corrected exposure reading for field monitoring element x.
UE =
x the uncorrected exposure reading for field monitoring element x.
2003 Radiological Environmental Monitoring Report E-4 I I AppendixE ECP; = the elemental correction factor of each individual transit control element.
n =
the total number of individual element exposures averaged.
The mean of the transit control exposures is then subtracted from each of the elementally corrected exposures of the irradiated elements to obtain the net exposures for each element resulting from the irradiation. The mean of these net exposures is then divided by the known exposure (100 mR) from the irradiation to determine the ReF.
The following equation describes the calculations performed:
where
+/-(~-E )
n RCF==---------~
KEiC RCF = the run correction factor for an individual field monitoring element.
E/ =
the exposure reading of each individual irradiated control element.
ECP; = the elemental correction factor of each individual irradiated control element.
n =
the total number of individual element exposures averaged.
KEic = the known exposure for each of the irradiated control elements.
Exposure readings for individual field monitoring elements are corrected using the appropriate mean transit exposure and the elemental and run correction factors as follows:
where CE =
x the corrected exposure reading for field monitoring element x.
UE =
x the uncorrected exposure reading for field monitoring element x.
2003 Radiological Environmental Monitoring Report E-4 I I I
'J
Appendix E.
ECF: =
the elemental correction factor for field monitoring element x.
ETC = mean transit exposure RCFx =
the run correction f~ctor for field monitoring element x.
NOTE:
The mean transit exposure'is"determined from the elements of the TLDs that accompany the field TLDs during transportation to and from the field locations,'
The representing each environmental' nionitoring' location ~ and monitoring period is normaliy the mean ofthe corrected exposure readings for a total of six calcium sulfate elements, three from each of tWo differerit,TLDs at location. The:following equati~n shows the calculation ofthis exposure:
where E=
c the mean of the corrected exposure readings for a given monitoring location and period,."'
CEI =
the corrected exposure reading of an individual element for a given monitoring location and period.
n
= the total number of individual element exposures averaged.
The mean of th~ corrected eXp'osure readings: for' a give~ location and period may be calculated using less than the six calcium sulfate elements if the reading from one ofthe elements is more than two standilrd deviations' !from' the" mean. In this situation, the mean would be recalculated with only five element readings, excluding the element reading that was more than' two stan~~~ d~v~at~<?ns from~heoriginally calculated mean.
The mean'may be automaticaHy'calculated by'the dosimetty software with as few as four element readings before the dahds flagged".' "The toliowing' calculation is used to determine the standard deviatiori of~e \\~~rrectea elemental exposure readings:
where 2003 Radiological Environmental Monitoring Report Appendix E.
\\..../
I
~'::.:,~>;
_1" ECF: =
the elemental correction factor for field monitoring element x.
ETC = mean transit exposure :.,' " '
RCFx =
the run correction f~ctor for field monitoring element x.
NOTE:
The mean transit exposure'is"determined from the elements of the TLDs that accompany the field TLDs during transportation to and from the field locations,'
The exposure* representing each environmental' nionitoring' location ~ and monitoring period is normaliy the mean ofthe corrected exposure readings for a total of six calcium sulfate elements, three from each of tWo differerit,TLDs at ea*ch location. The:following equati~n shows the calculation ofthis exposure:
where E=
c the mean of the corrected exposure readings for a given monitoring location and period,."'
CEI =
the corrected exposure reading of an individual element for a given monitoring location and period.
n
= the total number of individual element exposures averaged.
The mean of th~ corrected eXp'osure readings: for' a give~ location and period may be calculated using less than the six calcium sulfate elements if the reading from one ofthe elements is more than two standilrd deviations' !from' the" mean. In this situation, the mean would be recalculated with only five element readings, excluding the element reading that was more than' two stan~~~ d~v~at~<?ns from~heoriginally calculated mean.
The mean'may be automaticaHy'calculated by'the dosimetty software with as few as four element readings before the dahds flagged".' "The toliowing' calculation is used to determine the standard deviatiori of~e \\~~rrectea elemental exposure readings:
~.
. \\
\\
where E-S
" 2003 Radiological Environmental Monitoring Report
AppendixE the standard deviation of the corrected exposure readings from a given monitoring location and period for (n-l) degrees of freedom.
Ee =
the mean of the corrected exposure readings for a given monitoring location and period.
CEi =
the corrected exposure reading of an individual element for a given monitoring location and period.
n = the total number of individual element exposures averaged.
The standard monitoring period for the r.eporting of TLD exposures is the calendar quarter.
The calendar quarter is defined as a period of 91.25 days.
The actual monitoring periods for TLDs in the field are often for times other than 91.25 days. The means of the corrected exposures for these nonstandard periods must be normalized to the standard calendar quarter. The following equation shows how the normalization is performed:
where NE= ~x91.25 MP NE = mean corrected exposure normalized to a standard calendar quarter of 91.25 days.
Ee =
the mean of the corrected exposure readings for a given monitoring location and period.
MP = the actual TLD monitoring period (time in the field) in days.
TLD DATA INTERPRETATION Pre-operational and operational data are compared for the purpose of determining whether or not TLD data may indicate a dose contribution from SSES operation.
Between 1979 and 1994, bothTLD types and TLD processing systems changed more than once. In order to avoid possible confusion in data interpretation as a result of these changes, ratios ofTLD doses for specific indicator locations to the average of the TLD doses for control locations from operational periods compared to their counterparts from the preoperational period. Comparison of these ratios is performed in lieu of comparing the actual operational and preoperational doses. The following equation shows how these ratios are calculated:
2003 RadioJogicaJ Environmental Monitoring Report E-6 I
AppendixE the standard deviation of the corrected exposure readings from a given monitoring location and period for (n-l) degrees of freedom.
Ee =
the mean of the corrected exposure readings for a given monitoring location and period.
CEi =
the corrected exposure reading of an individual element for a given monitoring location and period.
n = the total number of individual element exposures averaged.
The standard monitoring period for the r.eporting of TLD exposures is the calendar quarter.
The calendar quarter is defined as a period of 91.25 days.
The actual monitoring periods for TLDs in the field are often for times other than 91.25 days. The means of the corrected exposures for these nonstandard periods must be normalized to the standard calendar quarter. The following equation shows how the normalization is performed:
where NE= ~x91.25 MP NE = mean corrected exposure normalized to a standard calendar quarter of 91.25 days.
Ee =
the mean of the corrected exposure readings for a given monitoring location and period.
MP = the actual TLD monitoring period (time in the field) in days.
TLD DATA INTERPRETATION Pre-operational and operational data are compared for the purpose of determining whether or not TLD data may indicate a dose contribution from SSES operation.
Between 1979 and 1994, bothTLD types and TLD processing systems changed more than once. In order to avoid possible confusion in data interpretation as a result of these changes, ratios ofTLD doses for specific indicator locations to the average of the TLD doses for control locations from operational periods compared to their counterparts from the preoperational period. Comparison of these ratios is performed in lieu of comparing the actual operational and preoperational doses. The following equation shows how these ratios are calculated:
2003 RadioJogicaJ Environmental Monitoring Report E-6 I
'--./
I
'-...-/
I
AppendixE where Note:
rj = the indicator-to-control-average dose ratio for a particular location and calendar quarter, dj = -the quarterly dose for a particular indicator location, and
-de = the average quarterly dose for certain control locations.
The rj are the quotients ofth(dndicator doses to the average doses of the following control locations: 3G4, 4Gl~ 7GI, 12Gl, and 12G4. Only these control10cations are used because they were the only ones existing during the preoperational period.
Operational rj for indicator locations that do not have preoperational histories are compared with the range of preoperational-con'trol-to:.control-average. dose ratios (rc) experienced at control locations. -It dm'be'safely assumed that the preoperational range of these rc at control locations are the result of variations in the levels of background radiation at those locations. Any operational indicator rj for an indicator location without a preoperational history that is above the uppermost range expected at control locations based on preoperational data is assumed to suggest a possible contribution from the SSES operation. The following equation shows how rc is calculated:
where E-7 rc is the control-to-control-average dose ratio for a particular location and calendar quarter, de is the quarterly dose for a particular control location, and de is the average quarterly dose for certain control locations.
-2003 Radiological En\\'ironmental Monitoring Report AppendixE where Note:
rj = the indicator-to-control-average dose ratio for a particular location and calendar quarter, dj = -the quarterly dose for a particular indicator location, and
-de = the average quarterly dose for certain control locations.
The rj are the quotients ofth(dndicator doses to the average doses of the following control locations: 3G4, 4Gl~ 7GI, 12Gl, and 12G4. Only these control10cations are used because they were the only ones existing during the preoperational period.
Operational rj for indicator locations that do not have preoperational histories are compared with the range of preoperational-con'trol-to:.control-average. dose ratios (rc) experienced at control locations. -It dm'be'safely assumed that the preoperational range of these rc at control locations are the result of variations in the levels of background radiation at those locations. Any operational indicator rj for an indicator location without a preoperational history that is above the uppermost range expected at control locations based on preoperational data is assumed to suggest a possible contribution from the SSES operation. The following equation shows how rc is calculated:
where E-7 rc is the control-to-control-average dose ratio for a particular location and calendar quarter, de is the quarterly dose for a particular control location, and de is the average quarterly dose for certain control locations.
-2003 Radiological En\\'ironmental Monitoring Report
where Appendix E DSSES = the dose attributable to SSES fuel cycle operations,
= the indicator-to-control average ratio for a particular location and calendar quarter, 1.22 = the highest expected rc for control locations due to variations in natural radiation levels based on preoperational data. Refer to location 12G4 in Attachment 1.
DCA = the average quarterly dose for control locations.
OF
= the occupancy factor.
Each year, the SSES attributable doses calculated.for each calendar quarter are summed for all calendar quarters at each location to obtain annual doses by location.
2003 Radiological Environmental Monitoring Report
£-10 where Appendix E DSSES = the dose attributable to SSES fuel cycle operations,
= the indicator-to-control average ratio for a particular location and calendar quarter, 1.22 = the highest expected rc for control locations due to variations in natural radiation levels based on preoperational data. Refer to location 12G4 in Attachment 1.
DCA = the average quarterly dose for control locations.
OF
= the occupancy factor.
Each year, the SSES attributable doses calculated.for each calendar quarter are summed for all calendar quarters at each location to obtain annual doses by location.
2003 Radiological Environmental Monitoring Report
£-10 I
> ** J I
"....J
DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITY..
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Aliquots of water samples are evaporated to near dryness in beakers. The remaining volumes (approximately five milliliters or less) are transferred to stainless steel planchets and evaporated to dryness..;
All planchets are counted in, Jow background gas-flow proportional counters.
Calculations of both gross alpha and beta activities include the use of empirical self-absorption correction curves to account for changes in effective counting efficiency occurring as a result of changes in the masses of residue being counted.
Weekly air particulate " filters are placed into'planchets as received and counted in low background gas-flow proportional counterS. No corrections 'are made for beta self-absorption when calculating the gross beta activities of the air particulate filters because of the impracticality of weighing the deposit and: because the penetration depth of the deposit into the filter is unknown.
E-11 CALCULATION OF THE SAl\\1PLE ACTIVITY pC; unit volume or mass [f-R.] + 2~
222 (V)(E) 222 (V) (E) net activity random uncertainty 2003 Radiological Environmental Monitoring Report DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITY..
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Aliquots of water samples are evaporated to near dryness in beakers. The remaining volumes (approximately five milliliters or less) are transferred to stainless steel planchets and evaporated to dryness..;
All planchets are counted in, Jow background gas-flow proportional counters.
Calculations of both gross alpha and beta activities include the use of empirical self-absorption correction curves to account for changes in effective counting efficiency occurring as a result of changes in the masses of residue being counted.
Weekly air particulate " filters are placed into'planchets as received and counted in low background gas-flow proportional counterS. No corrections 'are made for beta self-absorption when calculating the gross beta activities of the air particulate filters because of the impracticality of weighing the deposit and: because the penetration depth of the deposit into the filter is unknown.
E-11 CALCULATION OF THE SAl\\1PLE ACTIVITY pC; unit volume or mass [f-R.] + 2~
222 (V)(E) 222 (V) (E) net activity random uncertainty 2003 Radiological Environmental Monitoring Report
where:
C
=
total counts for sample t
=
count time for sample/background (minutes)
~ =
background count rate of counter (cpm) 2.22 =
dpm pCi V(M) = volume or mass of sample analyzed E
=
efficiency of the counter (cpm/dpm) 4.66 = sigma level Calculation of the Minimum Detectable Concentration (MDC) Value 4.66~R.
MDC=
I 2.22 (V) (E) 2003 Radiological Environmental Monitoring Report AppendixE E-12
~J
)
where:
C
=
total counts for sample t
=
count time for sample/background (minutes)
~ =
background count rate of counter (cpm) 2.22 =
dpm pCi V(M) = volume or mass of sample analyzed E
=
efficiency of the counter (cpm/dpm) 4.66 = sigma level Calculation of the Minimum Detectable Concentration (MDC) Value 4.66~R.
MDC=
I 2.22 (V) (E) 2003 Radiological Environmental Monitoring Report AppendixE E-12 I *
~J
\\
)
---../
I
V AppendixE RADIOCHEMICAL DETERMINATION OF 1-131
,.<-' 1.)4 J
,IN CHARCOAL AND VEGETATION SAMPLES TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Radioiodine is separated from the sample matrix to periodate solution.
Charcoal filters are 'opened and the exPosed : charcoal is' emptied 'into a refluxing flask, iodide carrier is added, and the mixture is refluxed in sodium hydroxide to remove the iodine absorbed on the charcoal and bringing it into sohition. The resulting iodide solution is oxidized with hypochlorite to periodate.
Vegetation samples are chopped,':iodide 'carner added, the mixture 'evaporated to dryness, leached with sodium hydroxide, and fused in a muffle furnace. The resulting melt is dissolved in distilled water and filtered.
The resulting iodide solution is oxidized with hypochlorite to periodate.
- '\\ i The periodate solution is reduced t~ 'iodine with hydroxylamine hydrochloride, and extracted into toluene as free iodine.: "'The;iC)~ineJs back extracted into disti11ed water through reduction to iodide with aqueous 'sodium bisulfite and is ultimately precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
The dried precipitate is beta counted on a low-level counter.
where:
A C
t Rb 2.22 E-13 CALCULATION OF THE SAMPLE ACTIVITY C
-+Rb
~
[--R6]
2 t
A=
t
+/-
t 2.22(V )( )')( DF )( E) 2.22(V )( y)( DF )( E)
=
=
=
=
=
net activity random uncertainty activity concentration (PCill) total counts from sample counting time for sample (min) background count rate of counter (cpm) dpm pCi "2003 Radiological Environmental Monitoring Report V
AppendixE RADIOCHEMICAL DETERMINATION OF 1-131
,.<-' 1.)4 J
,IN CHARCOAL AND VEGETATION SAMPLES TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Radioiodine is separated from the sample matrix to periodate solution.
Charcoal filters are 'opened and the exPosed : charcoal is' emptied 'into a refluxing flask, iodide carrier is added, and the mixture is refluxed in sodium hydroxide to remove the iodine absorbed on the charcoal and bringing it into sohition. The resulting iodide solution is oxidized with hypochlorite to periodate.
Vegetation samples are chopped,':iodide 'carner added, the mixture 'evaporated to dryness, leached with sodium hydroxide, and fused in a muffle furnace. The resulting melt is dissolved in distilled water and filtered.
The resulting iodide solution is oxidized with hypochlorite to periodate.
- '\\ i The periodate solution is reduced t~ 'iodine with hydroxylamine hydrochloride, and extracted into toluene as free iodine.: "'The;iC)~ineJs back extracted into disti11ed water through reduction to iodide with aqueous 'sodium bisulfite and is ultimately precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
The dried precipitate is beta counted on a low-level counter.
where:
A C
t Rb 2.22 E-13 CALCULATION OF THE SAMPLE ACTIVITY C
-+Rb
~
[--R6]
2 t
A=
t
+/-
t 2.22(V )( )')( DF )( E) 2.22(V )( y)( DF )( E)
=
=
=
=
=
net activity random uncertainty activity concentration (PCill) total counts from sample counting time for sample (min) background count rate of counter (cpm) dpm pCi "2003 Radiological Environmental Monitoring Report
AopendixE v
= volume of sample analyzed (liters) y
=
chemical yield of the mount or sample counted DF
=
decay factor from the collection (milk/vegetables) or midpoint of compositing period (water/charcoal cartridges) to the mid-count time E
=
efficiency of the counter for the 1-131 betas.
4.66 =
sigm~ level Note: Efficiency is detennined by counting an 1-131 st~ndard.
Calculation of the MDC MDC 4.66~*
2.22(V)(y)( DF)(E) 2003 Radiological Environmental Monitoring E-t4 AopendixE v
= volume of sample analyzed (liters) y
=
chemical yield of the mount or sample counted DF
=
decay factor from the collection (milk/vegetables) or midpoint of compositing period (water/charcoal cartridges) to the mid-count time E
=
efficiency of the counter for the 1-131 betas.
4.66 =
sigm~ level Note: Efficiency is detennined by counting an 1-131 st~ndard.
Calculation of the MDC MDC 4.66~*
2.22(V)(y)( DF)(E) 2003 Radiological Environmental Monitoring Report*
'l:
E-t4 I I
\\.J
'-.-/
AppendixE RADIOCHEMICAL~DETERMINATION OF 1-131
~
IN MILK AND WATER SAMPLES FRAMATOMEANP ENVIRONMENTAL LABORATORY First, iodide carrier is added to either a two-kilogram sample aliquot of milk or water.
For water, the next step is to add sodium hypochlorite, followed by hydroxylamine hydrochoride, and finalJy sodium bisulfite; to convert all of the iodine in the sample to iodide.
After sufficient time for equilibration of the stable iodide carrier, anion exchange resin is added to the sample to extrac(the iodide from the sample aliquot. The iodide ion is subsequently removed from the 'resin using sodium hypochlorite. It is then reduced to elemental iodine and transferred from the aqueous phase to the toluene. The iodine is then reduced to iodide using sodium bisulfite and back extracted into the aqueous phase. Once in the aqueous phase, the iodide is precipitated as cuprous iodide following the addition of cuprous chloride. -: :.,.
Another aliquot of sample may be used, if activity is detected in the sample, to determine the original stable iodide content of the sample using a specific-ion electrode.
This information would then be used to correct the chemical yield determined from the
\\.../~
mass ofthe dried precipitate.
The dried precipitate is then counted using a beta/gamma coincidence counter.
CALCULATION OF SAMPLE ACTIVITY A =-t----:~----'-----
Where:
E-IS A = activity concentration (pCi/l)
G = gross count at the end of the sample counting interval (t) t = sample counting interval B = background count rate (cpm)
A = decay constant for 1-131 (5.987E-5 min-I) 2.22 = dpm/pCi.
V = volume of sample (I) y = chemical yield (recovery) of the iodide 2003 Radiological Environmental Monitoring Report AppendixE RADIOCHEMICAL~DETERMINATION OF 1-131
".. J.
~
- IN MILK AND WATER SAMPLES FRAMATOMEANP ENVIRONMENTAL LABORATORY First, iodide carrier is added to either a two-kilogram sample aliquot of milk or water.
For water, the next step is to add sodium hypochlorite, followed by hydroxylamine hydrochoride, and finalJy sodium bisulfite; to convert all of the iodine in the sample to iodide.
After sufficient time for equilibration of the stable iodide carrier, anion exchange resin is added to the sample to extrac(the iodide from the sample aliquot. The iodide ion is subsequently removed from the 'resin using sodium hypochlorite. It is then reduced to elemental iodine and transferred from the aqueous phase to the toluene. The iodine is then reduced to iodide using sodium bisulfite and back extracted into the aqueous phase. Once in the aqueous phase, the iodide is precipitated as cuprous iodide following the addition of cuprous chloride. -: :.,.
Another aliquot of sample may be used, if activity is detected in the sample, to determine the original stable iodide content of the sample using a specific-ion electrode.
This information would then be used to correct the chemical yield determined from the
\\.../~
mass ofthe dried precipitate.
The dried precipitate is then counted using a beta/gamma coincidence counter.
CALCULATION OF SAMPLE ACTIVITY A =-t----:~----'-----
Where:
E-IS A = activity concentration (pCi/l)
G = gross count at the end of the sample counting interval (t) t = sample counting interval B = background count rate (cpm)
A = decay constant for 1-131 (5.987E-5 min-I) 2.22 = dpm/pCi.
V = volume of sample (I) y = chemical yield (recovery) of the iodide 2003 Radiological Environmental Monitoring Report
Where:
Appendix E D = decay factor (e>i.T) where A is the decay constant for 1-131 and T is the decay period from sample colIection (milk) or the mid-point of the sample compositing p'eriod (water) to the mid-point of the counting interval E = is the 1-131 beta/gamma counting efficiency (cpmJdpm)
CALCULATION OF MDC MDC 4.66 *J.. *t' J~
MDC = minimum detectable activity concentration (pei/l) 2003 Radiological Environmental Monitoring Report E-16 I
\\-......,/
I I
Where:
Appendix E D = decay factor (e>i.T) where A is the decay constant for 1-131 and T is the decay period from sample colIection (milk) or the mid-point of the sample compositing p'eriod (water) to the mid-point of the counting interval E = is the 1-131 beta/gamma counting efficiency (cpmJdpm)
CALCULATION OF MDC MDC 4.66 *J.. *t' J~
MDC = minimum detectable activity concentration (pei/l) 2003 Radiological Environmental Monitoring Report E-16 I
\\-......,/
I I
AppendixE DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION :COUNTING TELEDYNE BROWN ENGINEERING ENVIRONMENTAL'SERVICES Ten mjlJiJiters of water is mixed witli' liquid scintillation material and counted for typicaI1y 200 minutes to determine its a~tiYitY.'
CALCULATION OF THE SAMPLE 'ACTIVITY FOR TRITIUM
- ~.
[~~&]
.e
.2.22(V)(E) -, 2.22(V)(E) net activity random uncertainty where:
C
=
total counts from,sample t
=
count time for sample (minutes)
Rb
=
background count rate of counter (cpm) 2.22 =
dpm pCi v
=
initial volume before enrichment (liters)
E
=
efficiency of the counter for tritium (cpm/dpm)
Calculation the MDC 4_66~R'
~003 Radiological Environmental Monitoring Report AppendixE DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION :COUNTING OJ
."co TELEDYNE BROWN ENGINEERING ENVIRONMENTAL'SERVICES Ten mjlJiJiters of water is mixed witli' liquid scintillation material and counted for typicaI1y 200 minutes to determine its a~tiYitY.'
I
~,; *
~....
CALCULATION OF THE SAMPLE 'ACTIVITY FOR TRITIUM
,.;.. :~. i' ':
_pCi= [~~&] + 2P;
.e
.2.22(V)(E) -, 2.22(V)(E)
)
net activity random uncertainty.,
where:
C
=
total counts from,sample r,'. f'
~, (
t
=
count time for sample (minutes)
Rb
=
background count rate of counter (cpm) 2.22 =
dpm pCi v
=
initial volume before enrichment (liters)
E
=
efficiency of the counter for tritium (cpm/dpm)
I Calculation of the MDC.
': "t-
-,'--. 4_66~R' MDC b;;,,,:.'
t (2.22)(V)(E)
'J
',1, i
~.
- -0'"
E*l7
- " ~.. ~003 Radiological Environmental Monitoring Report
AppendixE Calculation of SSES Attributable Direct Radiation Dose based on Onsite Indicator TLD,Measurements For TLD locations where direct radiation dose contributions from the SSES are indicated, these calendar quarter doses are estimated based on the amounts referred to as the excess ratios. Excess ratio for each location '5 rj for a particular calendar quarter is the amount by which that fi exceeds the high end of its range of preoperationa'l rj. The excess ratio at a specific location is multiplied times both the average dose for control locations measured during that calendar quarter and an occupancy factor based on a reasonable estimate of the portion of the calendar quarter that a MEMBER OF THE PUBLIC might spend near an onsite TLD location.
The following is a table of occupancy factors that are used:
Environmental TLD Monitoring Locations Occupancy Factors Onsite 4.56E-4 Off site (other than Private Residences) 3.65E-3 Private Residences 1
The following equation is used for obtaining direct radiation doses attributable to the SSES at indicator TLD locations when preoperational data exists for those locations:
where DssEs =
the dose attributable to SSES fuel cycle operations, rj
= the indicator-to-control average ratio for a particular location and calendar quarter, ru
= the indicator-to-control average ratio corresponding to the upper end of the 95% confidence range for a particular location for the preoperational period, and DCA
= the average quarterly dose for control locations.
OF
= the occupancy factor.
The equation below is used for obtaining direct radiation doses attributable to the SSES at indicator locations when preoperational data does not exist for those locations:
2003 Radiological Environmental Monitoring Report I
I AppendixE Calculation of SSES Attributable Direct Radiation Dose based on Onsite Indicator TLD,Measurements For TLD locations where direct radiation dose contributions from the SSES are indicated, these calendar quarter doses are estimated based on the amounts referred to as the excess ratios. Excess ratio for each location '5 rj for a particular calendar quarter is the amount by which that fi exceeds the high end of its range of preoperationa'l rj. The excess ratio at a specific location is multiplied times both the average dose for control locations measured during that calendar quarter and an occupancy factor based on a reasonable estimate of the portion of the calendar quarter that a MEMBER OF THE PUBLIC might spend near an onsite TLD location.
The following is a table of occupancy factors that are used:
Environmental TLD Monitoring Locations Occupancy Factors Onsite 4.56E-4 Off site (other than Private Residences) 3.65E-3 Private Residences 1
The following equation is used for obtaining direct radiation doses attributable to the SSES at indicator TLD locations when preoperational data exists for those locations:
where DssEs =
the dose attributable to SSES fuel cycle operations, rj
= the indicator-to-control average ratio for a particular location and calendar quarter, ru
= the indicator-to-control average ratio corresponding to the upper end of the 95% confidence range for a particular location for the preoperational period, and DCA
= the average quarterly dose for control locations.
OF
= the occupancy factor.
The equation below is used for obtaining direct radiation doses attributable to the SSES at indicator locations when preoperational data does not exist for those locations:
'0 2003 Radiological Environmental Monitoring Report I
I
AppendixE Flagging Em'ironmental TLD Measurements for Possible Non-Natural Dose Contributions Confidence ranges, within which: 95% i of 'environmental TLD doses resulting from natural, background radiation are expected'to be; have been derived for each location with a preoperational history by multiplying "the' standard deviation (S) of the fj for the location by P1e appropriate t scor~ (t) base~;on the applicable degrees of freedom for each location. (Degrees of freedom,(dflare.equal to thenumber of ratios that were averaged les~ one.). The product of the t score arid the standard deviation (tS) was then subtracted from the mean (x) to dete~ine t~elower end of the 95% confidence range (R) and added to the obtain t~t:upper. end of the range (R) as indicated by the following equation:
The following t scores were used in the' ~ge calculaiions:
df to.os 1
12.706 2
. 4.303 3
. 3.182 4
2.776 5
2.571 6
2.447 7
2.365 For indicator locations with no preoperational history, TLD results are flagged for potential non-natural,dose contributions to TLD.measurements based on comparisons to the maximum. expected variation,,in,control,,;,to-control-average dose ratios (re:) for control locations. The expected ranges of fe for each coni,rol location for each calendar quarter during the 1980-81 preoperational period have been calculated. The highest expected re, for all the preope~tional co~tr~lloca~i~ms is 1.22.
Ratios for indicator locations greater. than 1.22, are,flagged for possible SSES direct radiation dose contributions.
2003 Radiological Environmental Monitoring Report E-8 AppendixE
\\...../'
Flagging Em'ironmental TLD Measurements for Possible Non-Natural Dose Contributions L
~:
~, -:
' :; ~
~"'"
Confidence ranges, within which: 95% i of 'environmental TLD doses resulting from natural, background radiation are expected'to be; have been derived for each location with a preoperational history by multiplying "the' standard deviation (S) of the fj for the location by P1e appropriate t scor~ (t) base~;on the applicable degrees of freedom for --
each location. (Degrees of freedom,(dflare.equal to thenumber of ratios that were averaged les~ one.). The product of the t score arid the standard deviation (tS) was then subtracted from the mean (x) to dete~ine t~elower end of the 95% confidence range (R) and added to the mean*to obtain t~t:upper. end of the range (R) as indicated by the following equation:
The following t scores were used in the' ~ge calculaiions:.
,. t SCORES* ;,
df to.os 1
12.706 2
[. 4.303 3
. 3.182 4
2.776 5
2.571 6
2.447 7
2.365
! * ~.
1
- f For indicator locations with no preoperational history, TLD results are flagged for potential non-natural,dose contributions to TLD.measurements based on comparisons to the maximum. expected variation,,in,control,,;,to-control-average dose ratios (re:) for control locations. The expected ranges of fe for each coni,rol location for each calendar quarter during the 1980-81 preoperational period have been calculated. The highest expected re, for all the preope~tional co~tr~lloca~i~ms is 1.22.
. (
~.
Ratios for indicator locations greater. than 1.22, are,flagged for possible SSES direct radiation dose contributions.
{ *** j 2003 Radiological Environmental Monitoring Report E-8
itppendix E DETERMINATION OF GAMMA EMITTING RADIOISOTOPES TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES &
FRAMA TOME ANP ENVIRONMENTAL LABORATORY Gamma emitting radionuclides are detennined with the use of a lithium-drifted gennanium (Ge(Li>>
and high purity gennanium detectors with high resolution spectrometry in specific media. such as, air particulate filters, charcoal filters, milk, water, vegetation, soil/sediments. biological media, etc. Each sample is prepared and counted in standard geometries such as one liter or four liter wrap-around Marinelli containers, 300 m] or 150 m] bottles, two-inch filter paper source geometries, etc.
The analysis of each sample consists of calculating the specific activities of all detected radionucHdes as well as the minimum detectable concentration for a standard Hst of nuclides. The gennanium detection systems are calibrated for each standard geometry using certified radionuclide standards traceable to the National Institute of Standards and Technology.
CALCULATION OF THE SAMPLE ACTIVITY
[C-B]
+
2.JC+B Net pCi / vol or mass = ---=----=----
2.22(V)(E)(GA)DF)(t) 2.22(V)(E)(GA)(DF)(t) where:
c B
net activity random uncertainty
=
area, in counts, of a spectral region containing a gamma emission of the nuclide of interest Note (l): If the detector exhibits a peak in this region when counting a blank, the counts from that peak are subtracted from C before using the above equation.
Note (2): If no peaks are exhibited, the counts in the channels where the predominant peaks for gammas from selected radionuclides would be expected are summed for C and used in the calculation of "net" activity.
=
background counts in the region of interest, calculated by fitting a straight line across the region connecting the two adjacent regions.
2003 Radiological Environmental Monitoring Report I
I itppendix E DETERMINATION OF GAMMA EMITTING RADIOISOTOPES TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES &
. FRAMA TOME ANP.
ENVIRONMENTAL LABORATORY Gamma emitting radionuclides are detennined with the use of a lithium-drifted gennanium (Ge(Li>>
and high purity gennanium detectors with high resolution spectrometry in specific media. such as, air particulate filters, charcoal filters, milk, water, vegetation, soil/sediments. biological media, etc. Each sample is prepared and counted in standard geometries such as one liter or four liter wrap-around Marinelli containers, 300 m] or 150 m] bottles, two-inch filter paper source geometries, etc.
The analysis of each sample consists of calculating the specific activities of all detected radionucHdes as well as the minimum detectable concentration for a standard Hst of nuclides. The gennanium detection systems are calibrated for each standard geometry using certified radionuclide standards traceable to the National Institute of Standards and Technology.
CALCULATION OF THE SAMPLE ACTIVITY
[C-B]
+
2.JC+B Net pCi / vol or mass = ---=----=----
2.22(V)(E)(GA)DF)(t) 2.22(V)(E)(GA)(DF)(t) where:
c B
net activity random uncertainty
=
area, in counts, of a spectral region containing a gamma emission of the nuclide of interest Note (l): If the detector exhibits a peak in this region when counting a blank, the counts from that peak are subtracted from C before using the above equation.
Note (2): If no peaks are exhibited, the counts in the channels where the predominant peaks for gammas from selected radionuclides would be expected are summed for C and used in the calculation of "net" activity.
=
background counts in the region of interest, calculated by fitting a straight line across the region connecting the two adjacent regions.
2003 Radiological Environmental Monitoring Report E*18 I
I
\\J
Appendix E Note:
t
=
2.22
=
V
=
E
=
GA
=
If no peak exists in a region from which a "net" activity is being calculated, background is represented by the average of the counts in one channel from each side of that region.
counting interval of sample (minutes) dpmJpCi volume or mass of sample analyzed efficiency of counter at the energy region of interest gamma abundance of the nuclide at the gamma emission energy under consideration DF
=
decay factor from sample collection time or midpoint of sample collection (air 1-131) to midpoint of the counting interval Calculation of the MDC MDC( pCi / vol or mass )= 2 22(V I( ~~;::X DF X I
t The width of the region around the energy where an emission is expected is calculated differently for MDCs than it is for the width of a peak that is actually identified.
Consequently, the value of B used in the two equations may differ.
2003 Radiological Environmental Monitoring Report Appendix E Note:
t
=
2.22
=
V
=
E
=
GA
=
If no peak exists in a region from which a "net" activity is being calculated, background is represented by the average of the counts in one channel from each side of that region.
counting interval of sample (minutes) dpmJpCi volume or mass of sample analyzed efficiency of counter at the energy region of interest gamma abundance of the nuclide at the gamma emission energy under consideration DF
=
decay factor from sample collection time or midpoint of sample collection (air 1-131) to midpoint of the counting interval Calculation of the MDC MDC( pCi / vol or mass )= 2 22(V I( ~~;::X DF X I
t The width of the region around the energy where an emission is expected is calculated differently for MDCs than it is for the width of a peak that is actually identified.
Consequently, the value of B used in the two equations may differ.
E*19 2003 Radiological Environmental Monitoring Report
,F-I' APPENDIXF 2~03 R,adiological Environmental Monitoring Rep~rt
,F-I' I.:,
APPENDIXF
~. ;
.. ;J 1
~
~ I.'
.,,1
) ;,
2~03 R,adiological Environmental Monitoring Rep~rt
Appendix F Exceptions to the SSES Technical Requirements occurred in the monitoring of the following ~edia: drinking water, surface water, air, and ambient radiation monitoring.
These exceptions involved sample collections that did not take place for the required periods due to sampling equipment problems and various environmental conditions (rain) that impacted sample col1ection or analysis.
These exceptions are discussed in this appendix and specifically documented in the tables of Appendix I.
Drinking Water Sampling at the Danville Municipal Water Facility, monitoring location 12H2, proceeded flawlessly during most of 2003, with only one exception. The only exception during 2003 occurred when the sample collectors incorrectly mixed the drinking water sample for week 1 of the April monthly composite period with the week 1 sample of the April monthly composite period from Surface Water monitoring location 6S5. The April monthly composite for monitoring location 12H2 sent for analysis contained only weeks 2-4 for April 2003.
There were no malfunctions of the ACS at monitoring location 12H2 during 2003.
Sampling at this location was routine (as expected) for 100% of the year.
Surface Water Monitoring at. control lOCation 6S6,. the. SSES River Water Intake Structure, and indicator.1ocation 2S7 or its alternate location 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) to the Susquehanna River, are the only environmental surveillance's of surface water required by SSES Technical Specifications. The other SSES REMP routine indicator surface water monitoring location on the Susquehanna River, which is downstream from the SSES discharge to the river, and the monitoring location at LTAW are not required. They have been monitored to provide added assurance that the environment is not being compromised by radiological releases resulting from the SSES operation.
SampJing at locations 6S6 and 2S7 or 6S7 is required to be performed by the collection of aliquots at time intervals that are small compared to the compositing period.
Composite samples from these locations are required to be analyzed monthly and are expected to be representative of the streams from which they are collected.
Problems occurred in 2003 with the automatic composite sampler (ACS) at sampling location 6S6 during portions of the following collection periods: March 17, through March 24, 2003 and June 23, through June 26, 2003. Sample collectors discovered low flow through the ACS due to rising river level causing debris and silt build-up on intake screens. Initially, the ACS sample flow rate was adjusted to insure sufficient volume was collected. Preventive maintenance was performed on the ACS (cleaned lines) and the sample flow rates were reset to 1.5 gpm.
2003 Radiological Environmental Monitoring Report F-2 I I
"\\.J Appendix F Exceptions to the SSES Technical Requirements occurred in the monitoring of the following ~edia: drinking water, surface water, air, and ambient radiation monitoring.
These exceptions involved sample collections that did not take place for the required periods due to sampling equipment problems and various environmental conditions (rain) that impacted sample col1ection or analysis.
These exceptions are discussed in this appendix and specifically documented in the tables of Appendix I.
Drinking Water Sampling at the Danville Municipal Water Facility, monitoring location 12H2, proceeded flawlessly during most of 2003, with only one exception. The only exception during 2003 occurred when the sample collectors incorrectly mixed the drinking water sample for week 1 of the April monthly composite period with the week 1 sample of the April monthly composite period from Surface Water monitoring location 6S5. The April monthly composite for monitoring location 12H2 sent for analysis contained only weeks 2-4 for April 2003.
There were no malfunctions of the ACS at monitoring location 12H2 during 2003.
Sampling at this location was routine (as expected) for 100% of the year.
Surface Water Monitoring at. control lOCation 6S6,. the. SSES River Water Intake Structure, and indicator.1ocation 2S7 or its alternate location 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) to the Susquehanna River, are the only environmental surveillance's of surface water required by SSES Technical Specifications. The other SSES REMP routine indicator surface water monitoring location on the Susquehanna River, which is downstream from the SSES discharge to the river, and the monitoring location at LTAW are not required. They have been monitored to provide added assurance that the environment is not being compromised by radiological releases resulting from the SSES operation.
SampJing at locations 6S6 and 2S7 or 6S7 is required to be performed by the collection of aliquots at time intervals that are small compared to the compositing period.
Composite samples from these locations are required to be analyzed monthly and are expected to be representative of the streams from which they are collected.
Problems occurred in 2003 with the automatic composite sampler (ACS) at sampling location 6S6 during portions of the following collection periods: March 17, through March 24, 2003 and June 23, through June 26, 2003. Sample collectors discovered low flow through the ACS due to rising river level causing debris and silt build-up on intake screens. Initially, the ACS sample flow rate was adjusted to insure sufficient volume was collected. Preventive maintenance was performed on the ACS (cleaned lines) and the sample flow rates were reset to 1.5 gpm.
2003 Radiological Environmental Monitoring Report F-2 I I
"\\.J
Appendix F The ACS at monitoring location 6S6,operated routinely, (as,expected) for approximately 97% of' 2003~,No malf~,nc~ons, of.'th( AC~. at ID,?nitoring l#ation 6S6 required th,e colleCtion of grab samples during 2003.
~
~
~
Surface'water,samples could ~ot be'i~en :8t :ACS'l~ation 2S7 from,October 3~t 1011 through october 4 at 0541 due to 'pMver failure~ Power'was restored to the sampler on October 4, 2003 at 0541. There was adequate volume for sample requirements. The ACS at monitoring location 2S7 operated routinely (as expected) for approximately 99% of 2003.
Reasons for exceptions to REMP air sampling during 2003 included the following: loss of electrical power to air sampling stations and air sample equipment problems (pump malfunctions).
Electrical power to the air sampling stations at monitoring locations 3S2, 13S6, 13S6Q, 12S1, and 12El was interrupted for about 3-4 hours on'September 19, 2003, during the monitoring period from September 17 through September 24,2003. There was a wide area power outage during the referenced time period due to Tropical Storm Isabel.
Power was restored to the air sampling equipment and adequate sample volume was achieved for the monitoring period.
The sample pump at monitoring station 12El experienced a pump motor failure during the monitoring period from October 1 through October 8,2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.
The sample pump failed at monitoring station 6G 1 during the monitoring period from June 4 through June 11, 2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.
Collectively, the air sampling equipment at the six air monitoring locations operated routinely (as expected) for more than 99% of 2003 in spite of the exceptions noted above.
2003 Radiological Environmental Monitoring Report Appendix F
'-...J" The ACS at monitoring location 6S6,operated routinely, (as,expected) for approximately 97% of' 2003~,No malf~,nc~ons, of.'th( AC~. at ID,?nitoring l#ation 6S6 required th,e colleCtion of grab samples during 2003.. 0c
. I
".:,.; ~
~
~
Surface'water,samples could ~ot be'i~en :8t :ACS'l~ation 2S7 from,October 3~t 1011 through october 4 at 0541 due to 'pMver failure~ Power'was restored to the sampler on October 4, 2003 at 0541. There was adequate volume for sample requirements. The ACS at monitoring location 2S7 operated routinely (as expected) for approximately 99% of 2003.
Reasons for exceptions to REMP air sampling during 2003 included the following: loss of electrical power to air sampling stations and air sample equipment problems (pump malfunctions).
Electrical power to the air sampling stations at monitoring locations 3S2, 13S6, 13S6Q, 12S1, and 12El was interrupted for about 3-4 hours on'September 19, 2003, during the monitoring period from September 17 through September 24,2003. There was a wide area power outage during the referenced time period due to Tropical Storm Isabel.
Power was restored to the air sampling equipment and adequate sample volume was achieved for the monitoring period.
The sample pump at monitoring station 12El experienced a pump motor failure during the monitoring period from October 1 through October 8,2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.
The sample pump failed at monitoring station 6G 1 during the monitoring period from June 4 through June 11, 2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.
Collectively, the air sampling equipment at the six air monitoring locations operated routinely (as expected) for more than 99% of 2003 in spite of the exceptions noted above.
2003 Radiological Environmental Monitoring Report F*3
Appendix F Ambient Radiation Monitoring EXceptions Occurred to the monitoring of ambient radiation during' the second and fourth quarterly monitoring periOds of 2003~ The second quarterly monitoring period was April 29 through July 24,2003. The TLD's at location' 3S4 were wet and unable to process for the referen~ed monitoring period. The fourth quarterly monitoring period was October 21, 2003 through January 30,2004. The TLD's at location 14B3 were wet and unable to process.
2003 Radiological Environmental Monitoring Report F4 I I Appendix F Ambient Radiation Monitoring EXceptions Occurred to the monitoring of ambient radiation during' the second and fourth quarterly monitoring periOds of 2003~ The second quarterly monitoring period was April 29 through July 24,2003. The TLD's at location' 3S4 were wet and unable to process for the referen~ed monitoring period. The fourth quarterly monitoring period was October 21, 2003 through January 30,2004. The TLD's at location 14B3 were wet and unable to process..
2003 Radiological Environmental Monitoring Report F4 I I
i",
APPEN"pIX G" 2003 Radiological Environmental Monitoring Report
.~
. J:
,I
. ; ~ ~'.
~,.
i",
APPEN"pIX G"
.:; )
t
. " 1 '.
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- ~ -'.,.
- 1 f -.;~ : : ".' '":.':- "'.'" ~ ':' ;
2003 Radiological Environmental Monitoring Report -:
.I,...
.~
- G*l
AppendixG The averages for indicator and control locations reported in the Summary of Data Table, which summarizes the entire year's results for the SSES REMP, were calculated using all measured values, when available, whether or not they were reported in Appendix. I tables. Values below the MDCs, even zeroes and negatives, were part of the averaging process for these analysis results. When no measured results are available in these cases, "LLO" is reported.
Preferably, the averages reported in the Summary of Data table for sample media that are normally collected continuously are determined using only results from continuously collected samples. Occasionally, grab samples are taken for these media when equipment malfunctions or other anomalies preclude or otherwise perturb routine continuous sampling. These grab samples are taken to minimize the time periods when no sampling is being performed, or, in some instances, when continuous sampling is considered to be nonrepresentative.
Because grab samples are snapshots of the media over brief periods, it is preferable not to average the analysis results of these samples with those for continuously collected composite samples. However, when equipment malfunctions are protracted, relatively large periods of time could be entirely unrepresented by averages if the results from grab sample analyses are not considered.
Allowing analysis results for grab samples to be weighted equally with those representing relatively large periods of time would tend to bias the resulting averages unjustifiably towards the conditions at the times that the grabs are obtained. Averages obtained in this way might less accurately reflect the conditions for the combined period of continuous sampling and grab simlpHng than if only the results from continuous sampling were used. On the other hand. using weighting factors for the analysis results of grab samples derived from the actual time it takes to collect those samples would lead to the grab sample analysis results having a negligible effect on the overall average and not justifying the effort involved.
Grab samples collected in lieu of normal continuous sampling are typically obtained at regular intervals corresponding to the intervals (weekly) at which the continuously collected samples would usually be retrieved for eventual compositing. For example.
grab samples are collected once a week but may be composited monthly in place of continuously collected samples that would normally be retrieved weekly and composited monthly. Since each grab sample is used to represent an entire week, albeit imperfect, it is reasonable to weight the analysis results the same. Thus, the results of one weekly grab are given approximately one-fourth the weight of the results for a monthly composite sample collected continuously for each of the four weeks in a month. Similarly, the analysis results of a composite of four weekly grab samples would cany the same weight as the analysis results for a composite of four weeks of continuously col1ected sample.
2003 Radiological Environmental Monitoring Report I I AppendixG The averages for indicator and control locations reported in the Summary of Data Table, which summarizes the entire year's results for the SSES REMP, were calculated using
- "y all measured values, when available, whether or not they were reported in Appendix. I tables. Values below the MDCs, even zeroes and negatives, were part of the averaging process for these analysis results. When no measured results are available in these cases, "LLO" is reported.
Preferably, the averages reported in the Summary of Data table for sample media that are normally collected continuously are determined using only results from continuously collected samples. Occasionally, grab samples are taken for these media when equipment malfunctions or other anomalies preclude or otherwise perturb routine continuous sampling. These grab samples are taken to minimize the time periods when no sampling is being performed, or, in some instances, when continuous sampling is considered to be nonrepresentative.
Because grab samples are snapshots of the media over brief periods, it is preferable not to average the analysis results of these samples with those for continuously collected composite samples. However, when equipment malfunctions are protracted, relatively large periods of time could be entirely unrepresented by averages if the results from grab sample analyses are not considered.
Allowing analysis results for grab samples to be weighted equally with those representing relatively large periods of time would tend to bias the resulting averages unjustifiably towards the conditions at the times that the grabs are obtained. Averages obtained in this way might less accurately reflect the conditions for the combined period of continuous sampling and grab simlpHng than if only the results from continuous sampling were used. On the other hand. using weighting factors for the analysis results of grab samples derived from the actual time it takes to collect those samples would lead to the grab sample analysis results having a negligible effect on the overall average and not justifying the effort involved.
Grab samples collected in lieu of normal continuous sampling are typically obtained at regular intervals corresponding to the intervals (weekly) at which the continuously.
collected samples would usually be retrieved for eventual compositing. For example.
grab samples are collected once a week but may be composited monthly in place of continuously collected samples that would normally be retrieved weekly and composited monthly. Since each grab sample is used to represent an entire week, albeit imperfect, it is reasonable to weight the analysis results the same. Thus, the results of one weekly grab are given approximately one-fourth the weight of the results for a monthly composite sample collected continuously for each of the four weeks in a month. Similarly, the analysis results of a composite of four weekly grab samples would cany the same weight as the analysis results for a composite of four weeks of continuously col1ected sample.
2003 Radiological Environmental Monitoring Report G*2
c C'
(
1 TABLEG
SUMMARY
OF DATA FOR SSF.S OPERATIONAL RADIOLOGICAL ENVlRONMENTAL MONITORING PROGRAM.1003 NAMEOFFACILITY: SUSQUEIIANNASTEAMELECTRICSTATION LOCATION OFFACIUTY: LUZERNE COUNTY, PENNSYLV ANlA Reporting Period:
December 30, 2001 to J mua" 30, 2004 Paget ort',
ANALYSIS AND LOWERUMIT NUMBEROP MnDIUMORPATIlWAY TOTAL NUMBER OF ALLINDICATOR LOCATIONS tocAllONwrmmGHBSTMllAN CONIROLLOCATION NONROUllNB SAMPI..ED OFANALYSBS DBTl!CTION MllAN(3)
NAME MI!AN(3)
MBAN(3)
REPOR'I1ID (UNITOFMEASUREMENT)
PHRFORMIID~ll (llD)!22 RANGll DISTANCE AND DIRECTION RANGll RANGE MBASUREMENTS!~
Amblmt Radiation TLD 333 2.02£+01 (301 1301) 9S2 4.06B+Ol (4/4) 1.90£+01 (32/32) 0 (mRlstd. qu.)
(1.27£+01
- 4.47E+Ol) 0.2 mi S
(3.17£+01 -
4.47£+01)
(1.4tE+01 -
2.36E+01)
Surface Water OrossBeta 48 4
6.06B+OO (36/36) 2S7 1.t0E+OI (12/12) 2.37E+OO (12/12) 0 (pCiIl)
(2.42E+00 1.59£+01) 0.1 mi NNI!
(7.08£+00 1.59£+01)
(6.08£.01 4.32£+00)
Tritium 48 2000 1.57E+03 (36/36) 2S7 4.42E+03 (12/12) 3.18£+01 (12' 12) 0
(-3.54£+01 1.66E+04) 0.1 mi NNI!
(1.13£+02 1.66E+04)
(-4.98£+01 1.37£+02)
Iodine-13 I 90 3.6SE-OI (64 164) 2S7 7.7'7E-Ol (26/26) 2.58£.01 (26/26) 0
(-1.10£.01 1.9tE+00) 0.1 mi NNI!
(-1.10£.01 1.91£+00)
(-I.00E-02 7.20£.(1)
~"
OammaSpec 3.s8E~OOl (36/36)
- J ('
(12112)
K40' '
48' 6SS 4.7SE+00 tiOB-Oi (12/12) 0
(-3.ooE+01 S.ooE+OI) 0.9:
mi ',:ESB::
(-2.40£+01' 4.10£+01)
(-1.70£+01 ~
2.40E+OI)
M:n:54 '
48 15'
~ "
I
~ ~.
(i2/ll)
.8.31E-02 (36/36) 6S6 tSSE-02' (12/12) 2.5SE-02 0
(-1.90E+00.
1.50E+00) 0.8 mi" ESE
(.I.ooE+OO 2.IOE+OO)
(.1.00£+00 2.10£+00)
Co-58 48 15
-2.0SE-Ol (36/36) 6SS 1.83E-Ol (12' 12)
.8.09£.01 (12/12) 0
(-3.300+00 -
3.60E+00) 0.9 mi ESE
(.2.40E+00 2.50E+00) 2.00£.(1)
Pc-59 48 30 1.49£-01 (36/36) 6SS 1.23£+00 (12/12) 4.85£.01 (12/12) 0
(-6.00£+00. 4.70E+00) 0.9' mi ESE
(.2.10E+00 4.70E+00) 5.80£+00)
<:0-60 48 15 2.96E-Ol (36/36) 2S7 3.90£.01 (12/12) 2.63£.01 (12/12) 0
(-I.tOE+oo -
1.90E+00) 0.1 mi NNI!
(-8.00£-01
- 1.90£+00)
(-8.00£.01 3.00£+00)
Zn-6S 48 30
-4,8iMI (36/36) 6SS 7,92.E-OI (12/12)
.2.91£.01 (12/12) 0.,
(-1.07E+Ol ' -
7.70£+00) 0.9 mi ESE
(-5.50£+00.
6.00E+00) c C'
(
1 TABLEG
SUMMARY
OF DATA FOR SSF.S OPERATIONAL RADIOLOGICAL ENVlRONMENTAL MONITORING PROGRAM.1003 NAMEOFFACILITY: SUSQUEIIANNASTEAMELECTRICSTATION LOCATION OFFACIUTY: LUZERNE COUNTY, PENNSYLV ANlA Reporting Period:
December 30, 2001 to J mua" 30, 2004 Paget ort',
ANALYSIS AND LOWERUMIT NUMBEROP MnDIUMORPATIlWAY TOTAL NUMBER OF ALLINDICATOR LOCATIONS tocAllONwrmmGHBSTMllAN CONIROLLOCATION NONROUllNB SAMPI..ED OFANALYSBS DBTl!CTION MllAN(3)
NAME MI!AN(3)
MBAN(3)
REPOR'I1ID (UNITOFMEASUREMENT)
PHRFORMIID~ll (llD)!22 RANGll DISTANCE AND DIRECTION RANGll RANGE MBASUREMENTS!~
Amblmt Radiation TLD 333 2.02£+01 (301 1301) 9S2 4.06B+Ol (4/4) 1.90£+01 (32/32) 0 (mRlstd. qu.)
(1.27£+01
- 4.47E+Ol) 0.2 mi S
(3.17£+01 -
4.47£+01)
(1.4tE+01 -
2.36E+01)
Surface Water OrossBeta 48 4
6.06B+OO (36/36) 2S7 1.t0E+OI (12/12) 2.37E+OO (12/12) 0 (pCiIl)
(2.42E+00 1.59£+01) 0.1 mi NNI!
(7.08£+00 1.59£+01)
(6.08£.01 4.32£+00)
Tritium 48 2000 1.57E+03 (36/36) 2S7 4.42E+03 (12/12) 3.18£+01 (12' 12) 0
(-3.54£+01 1.66E+04) 0.1 mi NNI!
(1.13£+02 1.66E+04)
(-4.98£+01 1.37£+02)
Iodine-13 I 90 3.6SE-OI (64 164) 2S7 7.7'7E-Ol (26/26) 2.58£.01 (26/26) 0
(-1.10£.01 1.9tE+00) 0.1 mi NNI!
(-1.10£.01 1.91£+00)
(-I.00E-02 7.20£.(1)
I.! -
~';-'. r\\'
r:,.. :' ;' ~, ~
- 1. 1 " ":'Y':
~".... tl :",'j'l OammaSpec 3.s8E~OOl (36/36)
- J ('
,,' :', (12112)
......... "1
, : -J
\\ r',"
K40' '
48' 6SS 4.7SE+00 tiOB-Oi (12/12) 0
(-3.ooE+01 S.ooE+OI) 0.9:
mi ',:ESB::
(-2.40£+01' 4.10£+01)
(-1.70£+01 ~
- 2.40E+OI)
M:n:54 '
48 15' r*. '-. "
~ "
I l
0
~ ~.
(i2/ll)
.8.31E-02 (36/36) 6S6 tSSE-02' (12/12) 2.5SE-02 0
(-1.90E+00.
1.50E+00) 0.8 mi" ESE
(.I.ooE+OO 2.IOE+OO)
(.1.00£+00 2.10£+00)
Co-58 48 15
-2.0SE-Ol (36/36) 6SS 1.83E-Ol (12' 12)
.8.09£.01 (12/12) 0
(-3.300+00 -
3.60E+00) 0.9 mi ESE
(.2.40E+00 2.50E+00)
(*2.10£+00 2.00£.(1)
Pc-59 48 30 1.49£-01 (36/36) 6SS 1.23£+00 (12/12) 4.85£.01 (12/12) 0
(-6.00£+00. 4.70E+00) 0.9' mi ESE
(.2.10E+00 4.70E+00)
(.1.40£+00..
5.80£+00)
<:0-60 48 15 2.96E-Ol (36/36) 2S7 3.90£.01 (12/12) 2.63£.01 (12/12) 0
(-I.tOE+oo -
1.90E+00) 0.1 mi NNI!
(-8.00£-01
- 1.90£+00)
(-8.00£.01 3.00£+00)
Zn-6S 48 30
-4,8iMI (36/36) 6SS 7,92.E-OI (12/12)
.2.91£.01 (12/12) 0.,
(-1.07E+Ol ' -
7.70£+00) 0.9 mi ESE
(-5.50£+00.
6.00E+00)
(-4.40£+00
- 7.00£+00)
~.
"0#' t.
't "0 ~ \\! '
'. '.',1
TABLEG
SUMMARY
OFDATAFORSSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORlNG 2003 NAMEOFFAClUTY: SUSQUEIIANNASTEAMELECTRlCSTATION LOCATION OFFACIUTY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2002 to January 30, 2004 Pa,c%o(13 ANALYSIS AND LOWERI1MlT MEDIUM OR PA11lWAY TOfALNUMBER OF ALL INDICATOR LOCATIONS LOCATIONwrrnmGllP.ST MIlAN SAMPI.lID OFANALYSBS DB1'ECTION MIlAN(3}
NAME M.EAN(3}
~UNIT OFMRAS\\lRE.}.i\\1Nr) PERFORMED !l}
!Ul>lPl RANGB DISI' ANCB AND DlRF..cI1ON RANGE Sud ace WJlter (oonL) 48 30
-6.20E-Ol (36/36) 6SS (12/12)
(pCiIl)
(oS.80B+00 3.70B+00)
(9.ooE-OI mi ES£ 1.70£+00)
Nb-9S 48 15
-S.60R-02 (36/36) 686 2.96R-Ol (12/12)
(-3.~0£+OO 3.40£+00)
(S.ooE-Ol mi RSE
(-2.2OR+00 -
4.40£+00)
C&-134 48 IS 3.83R-Ol (36/36) 2S1 4.73E-Ol (12/12)
(-1.70£+00 2.80£+00)
(l.ooE-Ol mi NNE 1.40E+00) c&-131 48 18 S.97R-02 (36/36)
LTAW 6.08E-OI (12/12)
(-1.40£+00 3.70£+00) on site NE-RS£
(-1.20B+00 -
3.1OR+00) 48 60 8.91E-Ol (36/36)
LTAW 1.36£+00 (12/12)
(-3.40£+00 5.70£+00) on site NE-RSB
(-1.50B+OO 5.10B+00) 48 15 1.03B+OO (36/36)
LTAW 1.57B+00 (12/12)
(-3.90B+00 6.50B+00) on site NE-ES£ 6.5OR+00)
NUMBER OF CONTROLl.OCATION NONROtmNB M.EAN(3)
REPORTP.D RANGB MBASURBMl!NTS~4l 4.02&01 (12/12) 0
-(3.00£+00 1.50£+00) 2.96R-Ol (12/12) 0
-(2.2OR+00 4.40£+00) 3.13E-Ol (12/12) 0
-(2.10R-Ol I.5OR+OO) 4.50R-OI (12/12) 0
-(1.60£+00 4.70E-(1)
(12/12) 0 2.7OR+OO)
.2.81R-OI (12/12) 0 3.1OR+00)
TABLEG
SUMMARY
OFDATAFORSSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORlNG PROGRAM* 2003 NAMEOFFAClUTY: SUSQUEIIANNASTEAMELECTRlCSTATION LOCATION OFFACIUTY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2002 to January 30, 2004 Pa,c%o(13 ANALYSIS AND LOWERI1MlT MEDIUM OR PA11lWAY TOfALNUMBER OF ALL INDICATOR LOCATIONS LOCATIONwrrnmGllP.ST MIlAN SAMPI.lID OFANALYSBS DB1'ECTION MIlAN(3}
NAME M.EAN(3}
~UNIT OFMRAS\\lRE.}.i\\1Nr) PERFORMED !l}
!Ul>lPl RANGB DISI' ANCB AND DlRF..cI1ON RANGE Sud ace WJlter (oonL)
Zr*9S 48 30
-6.20E-Ol (36/36) 6SS
- 2.92&01 (12/12)
(pCiIl)
(oS.80B+00 -
3.70B+00)
(9.ooE-OI mi ES£
(-2.90£+00 1.70£+00)
Nb-9S 48 15
-S.60R-02 (36/36) 686 2.96R-Ol (12/12)
(-3.~0£+OO 3.40£+00)
(S.ooE-Ol mi RSE
(-2.2OR+00 -
4.40£+00)
C&-134 48 IS 3.83R-Ol (36/36) 2S1 4.73E-Ol (12/12)
(-1.70£+00 -
2.80£+00)
(l.ooE-Ol mi NNE
(*9.00E-Ol -
1.40E+00) c&-131 48 18 S.97R-02 (36/36)
LTAW 6.08E-OI (12/12)
(-1.40£+00 -
3.70£+00) on site NE-RS£
(-1.20B+00 -
3.1OR+00)
Ba*140 48 60 8.91E-Ol (36/36)
LTAW 1.36£+00 (12/12)
(-3.40£+00. 5.70£+00) on site NE-RSB
(-1.50B+OO. 5.10B+00)
La*140 48 15 1.03B+OO (36/36)
LTAW 1.57B+00 (12/12)
(-3.90B+00 -
6.50B+00) on site NE-ES£
(*1.80E+OO -
6.5OR+00) c:
(
NUMBER OF CONTROLl.OCATION NONROtmNB M.EAN(3)
REPORTP.D RANGB MBASURBMl!NTS~4l 4.02&01 (12/12) 0
-(3.00£+00 1.50£+00) 2.96R-Ol (12/12) 0
-(2.2OR+00 -
4.40£+00) 3.13E-Ol (12/12) 0
-(2.10R-Ol I.5OR+OO) 4.50R-OI (12/12) 0
-(1.60£+00. 4.70E-(1)
- 2.S4E-OI (12/12) 0
-(5.00£+00 -
2.7OR+OO)
.2.81R-OI (12/12) 0
-(5.80£+00. 3.1OR+00)
('
c'
(
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MOmTORING 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY. PENNSYLVANIA Reporting Period:
December 30, 2001 to January 30,2004 Page30ftl ANALYsts AND LOWERUMlT NUMBBROF MEDlUMORPATIlWAY TOrALNUMBER OF AlL INDICATOR LOCATIONS LOCATIONwmUI[OUESTMEAN CONIROLLOCATION NONROUI'INB SAMPLED OF ANALYSES DETECTION Ml!AN(3)
NAME MEAN (3)
MEAN (3)
REPORTED
~UNlT OF MBAStJREMENT) PI!RFORMI!D ~ll (U.Dl~2~
RANOB DISTANCB AND DIRECTION RANOB RANOB MBAS1.lRBMBNl'S'~
Potable Water OrossAlpha 12 (12/12) 12H2 t.69B-OI (12/12)
Only indicator 0
(pCiIl) t.37E+OO) 26 ml wsw
(-6.S4B l.37E+OO) stations sampled for this medium.
OrossBeta 12 4
12112 0
26 ml WSW Iodine-13 I 26 12H2 0
26 ml WSW Tritium 12 2000 12H2 0
26 ml WSW OammaSpec K-40 12 12H2
~
0 26'"
ml WSW Mn-S4 12 IS 12H2 0
26 ml WSW Co-S8 12 IS 12112 0
26 ml WSW F~S9 12 30 12112 0
26 ml WSW Co-60 12 IS 12U2 0
26 ml WSW Zn-6S 12 30 12H2 0
26 ml WSW 12 30 t2H2 0
26 ml WSW
('
c'
(
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MOmTORING PROGRAM* 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY. PENNSYLVANIA Reporting Period:
December 30, 2001 to January 30,2004 Page30ftl ANALYsts AND LOWERUMlT NUMBBROF MEDlUMORPATIlWAY TOrALNUMBER OF AlL INDICATOR LOCATIONS LOCATIONwmUI[OUESTMEAN CONIROLLOCATION NONROUI'INB SAMPLED OF ANALYSES DETECTION Ml!AN(3)
NAME MEAN (3)
MEAN (3)
REPORTED
~UNlT OF MBAStJREMENT) PI!RFORMI!D ~ll (U.Dl~2~
RANOB DISTANCB AND DIRECTION RANOB RANOB MBAS1.lRBMBNl'S'~
Potable Water OrossAlpha 12 1.69E*OI (12/12) 12H2 t.69B-OI (12/12)
Only indicator 0
(pCiIl)
(*6.S4E*Ol.
t.37E+OO) 26 ml wsw
(-6.S4B l.37E+OO) stations sampled for this medium.
OrossBeta 12 4
2.26E+OO (12/12) 12112 2.26E+OO (t2/12) 0 (8.98B 4.26E+OO) 26 ml WSW (8.98B-Ol -
4.26E+OO)
Iodine-13 I 26 1.78E*Ol 0.(/26) 12H2 1.7gB-Ol 0.(/26) 0
(.1.60B-Ol -
S.SOE*OI) 26 ml WSW
(-1.60B-Ot -
S.SOE*OI)
Tritium 12 2000 6.43B+OI (12/12) 12H2 6.43B+Ol (12/12) 0
(-7.67E+OO l.93B+02) 26 ml WSW
(*7.67E+OO l.93B+02)
OammaSpec K-40 12 4.04E+OO. (12112).
12H2
': ~
4.04E+OO* (12112) : ';
0
(*2.00E+Ol
~. 4.IOB+0l) 26'"
ml WSW
(.2.00B+Ot:
.", 4.10B+Ol)
Mn-S4 12 IS
- S.36E*02 (12/12) "
I 12H2
- S.36E*02 (12112)' ".
0
(*1.40E+OO
- . 9.00E*Ol) 26 '
ml WSW
(.1.40E+OO 9.00B-Ol)
Co-S8 12 IS
-4.26E-Ol (12/12) 12112
-4,26E-OI (12/12) 0
(-1.20B+OO 6.00E*Ol) 26 ml WSW
(.1.20B+OO
'. 6.00B-Ol)
F~S9 12 30
-3.69B-Ol (12/12) 12112
-3.69E-0l (12/12) 0
(*3.60B+OO -
3.00B+OO) 26 ml WSW
(*3.6OE+OO. 3.00B+OO)
Co-60 12 IS I.SSB*OI (12112) 12U2 USB*Ol (12/12) 0
(-7.00B-Ol -,8.00B*Ot) 26 ml WSW
(.7.00E*OI
., 8.00B*Ol)
, Zn-6S 12 30
--1.21E+OO. (12 112),
12H2
-t.21E+OO (12/12) 0
(.9.80E+OO "-
,6.IOB+OO) 26 ml WSW
(*9.S0B+OO -
6.10B+OO)
Zr*9S
. 12 30., _ -S.llB-OI. (12/12),
t2H2
-S.nE*Ot (12112) 0
(-2.60B+OO -
4,OOB-Ol) 26 ml WSW
(*2.60B+OO -
4.00B-Ol)
TABLEG
SUMMARY
OF DATA FORSSES OPERATIONAL RADIOLOGICAL.ENVIRONMENTAL MONITOlUNG Z003 NAME OF FACILITY: SUSQUHlIANNA STRAM ELECTlUC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December JO. 1002 to January 30,lOO4 Page40flJ ANALYSIS AND LO'WERUMlT MEDIUM OR PAllIWAY TOrALNUMBBR OF AlLlNDlCATOR LOCATIONS LOCATION WmUIIGIIBSr MEAN SAMPLED OFANALYSBS DBI'ECllON MBAN(3)
NA:b.tn MEAN (3)
~UNITOPMBASURHMt!NT) Pl!RFORMED~il
!UD~~l!
RANGE DlST ANCB AND DlRECl10N RANGE
(
NUMBBROP CONfROLLOCATION NONROUTINB ME.AN(3) lU!PORIED RANGE MEASURJl.MBNTS(4!
TABLEG
SUMMARY
OF DATA FORSSES OPERATIONAL RADIOLOGICAL.ENVIRONMENTAL MONITOlUNG PROGRAM* Z003 NAME OF FACILITY: SUSQUHlIANNA STRAM ELECTlUC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December JO. 1002 to January 30,lOO4 Page40flJ ANALYSIS AND LO'WERUMlT MEDIUM OR PAllIWAY TOrALNUMBBR OF AlLlNDlCATOR LOCATIONS LOCATION WmUIIGIIBSr MEAN SAMPLED OFANALYSBS DBI'ECllON MBAN(3)
NA:b.tn MEAN (3)
~UNITOPMBASURHMt!NT) Pl!RFORMED~il
!UD~~l!
RANGE DlST ANCB AND DlRECl10N RANGE Potable Water (con)
Nb-9S 12 IS 1.8SE-OI (12/12) 12H2 1.8SE-Ol (12/12)
(pCiIl)
(-I.IOE+OO -
1.IOE+(0) 26 mi WSW
(-I.IOE+OO -
I. 1 OE+OO)
Cs-I34 12 15 9.23E..Q2 (12/12) 12112 9.23E-02 (12/12)
(-S.70B-Ol -
I.ZOE+OO) 26 mi WSW
(-S.70E-Ol 1.20E+(0)
Cs-137 12 18
-1.4IE-Ol (12/12) 12112
-1.41E-Ol (12/12)
(-2.40B+00 -
1.60E+(0) 26 mi WSW
(-2.40E+00 -. 1.60E+(0)
Ba-140 12 60 3.OSE-Ot (12 I 12) 12H2 3.0SE-Ol (12/12)
(-2.80E+00. 7.20E+(0) 26 mi WSW
(-2.80E+00 -
7.20E+(0)
La-140 12 15 3.72E-DI (12/12) 12H2 3.72E-0l (12/12)
(-3.20B+00 -
8.30E+(0) 26 mi WSW
(-3.20E+00 -
8.30E+00)
(
NUMBBROP CONfROLLOCATION NONROUTINB ME.AN(3) lU!PORIED RANGE MEASURJl.MBNTS(4!
Onlyindk:ator 0
stations sampled for this medium.
0 0
0 0
c ANALysts AND MEDIUM ORPATIIWAY TOTAL NUMBER SAMPLED OF ANALYSES
~UNIT OFMBAS'UREMi!.Nn PERFORMED [tl Fish TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAl\\m OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNsYLVANIA Reporting Period:
D<<ember 30, 2002 to PageSor13 January 30,1004 LOWERUMIT OF AlL INDICATOR LOCATIONS NAMP;'
LOCATIONWrll1InGlmsTMEAN DETEcrrON MBAN(3)
MEAN (3)
(Ul)~~1~
RANGB DTSTANCB AND nnmcrrON, RANGB NUMBBROF CONI'ROLLOCATION NONROUI1NB MEAN (3)
REl'ORTIID RANGB MBAStJRBMP.NTS~
c ANALysts AND MEDIUM ORPATIIWAY TOTAL NUMBER SAMPLED OF ANALYSES
~UNIT OFMBAS'UREMi!.Nn PERFORMED [tl Fish OammaSpec (pCi/kg wet)
K-40 13 Mn-S4 13 Co-5S 13 Fe-59 13 Co-60 13 zn.6S 13 Zr*9S 13 Nb-9S 13 Cs*l34 13 Cs-137 13 Ba-140 13 La*140 13 TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 2003 NAl\\m OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNsYLVANIA Reporting Period:,
D<<ember 30, 2002 to PageSor13 January 30,1004 LOWERUMIT OF AlL INDICATOR LOCATIONS NAMP;'
LOCATIONWrll1InGlmsTMEAN DETEcrrON MBAN(3)
MEAN (3)
(Ul)~~1~
RANGB DTSTANCB AND nnmcrrON, RANGB 3.S8E+03
\\1/7)
LTAW 3.67B+03 (I II),
(1.30E+D3.
4.~9E+03) on site NE*ESE (3.67B+?3. -
3.67B+03) 130 1.9SE+00 (1/7)
LTAW S.74E+00 (t / t)
(.9.19E+OO, -
9.69E+OO) on site NE*ESE (S.74E+00 -
5.74E+00) 130
- t.67B+00.. \\1/7)
LTAW
- 9.80E-Ot (11 I) \\'
(-9.09E+OO'* *
,6.3.~+(6) on site NE-EsE
(.9.~OE~?1. ".9.~OE.OI)
.. i
-~ ~
260
- 9.S1E+00
\\1 /7)
LTAW t06E+OI. (Ill)! ;., " ;
(-4.40B+of" * : I.S7E+Ot)'
onsitC NE-ESE (I.06E+Ol " *," 1.000+Ot)
- ~r*~'~'
~..... '. -
~.
t30
-1.S9B+00
\\1 /7) 211 1.31E*Ot (6/6),.,,
(-7.97E+oO: -, 4.40B.f.00),
30 m1 NNE
(.8.69E+00, - ' 9.99E+OO)
'j 260
-3.99E+OI
\\1/7) 211
-3.26E+00 (616)." "I **
(.S.6mtOl'; -
2.8SE+00) 30 m1 NNE
(*2.9SB+Ot -
9.28E+00) 1.68E*Dl (1/7) 21I 3.B4E+OO (616)
('l.SOB+O~,., ~.36E+Dt)*
3D mi NNE
(*3.2SE+00 -
1.38B+Ol)
O.OOE+OO (1/7) 2H O.OOE+OO (616)
(O.OOE+oo*'.
O.OOE+OO) 30 mi NNE (O.OOE+OO -
O.OOE+OO) 130
- 1.86E+Ol (117)
LTAW 3.39E+OO. (Ill)
(-4.3SB+0~ -
3.39E+OO) on site NE*ESE (3.39E+OO. 3.39B+OO)
ISO 4.S3E+00
\\1/7)
IND S.I9E+OO (616)
(*7.78B*Ot
- -, J.22E+Ol).
0.9-1.4, ' -mi ESE
(-7.7m*OJ -
1.22E+Ol) 4.8SE+Ol
\\1/7). ",
LTAW
" 1.S0B+02 ' (I 11)
,,(.S.44E+Ol " ';.
1.8SE+02) on site NE*ESE (J.SOE+02 -
I.S0E+02)
T
~_
~
.. ~
- 6.S7B+00
\\1/7)
IND.
- 6.2SB+00 (616)
(-S.2SE+Dl. -
3.3lE+Ol),,. 0.9-1.4 mi ESB
(*S.2SE+Ot 3.31E+0l)
. ~. ~,
)'
NUMBBROF CONI'ROLLOCATION NONROUI1NB MEAN (3)
REl'ORTIID RANGB
' MBAStJRBMP.NTS~
3.16E+03 (6/6) 0 (1.30E+03 -
3.92E+03) 3.ISE+00 (616),
.0
(.6.18E+00 -, I.34E+Ol)
- 2.S3E+00 (6/6) 0
(-6.l4E+00* *. t.2lE+OO)
-1.6~+00. (616).;,
0
(.2.84E+Ot /' * '2 l.88E+OI) 1.31E-OI,; (616) 0
(.8.69E+OO,; - '" 9.99E+00)
- 3.26E+00. (616) : "...
0
(.2.9sE+01.
! " 9.28E+00) 3.B4E+OO (616) 0
(*3.2SE+00 1.38E+Ot)
O.ooE+OO (616) 0 (O.OOE+OO -
O.OOE+OO)
- l.47B+Dl (616),
0
(*6.66E+OI.. 1.19E+OO)
-t.78E+00 (616) 0
(.8.29E+00 -
3.14E+OO)
- 3.49E+Ot (616),
0
(.2.26E";.02 -
4.39E+Ol)
- 7.2SE+OO (616) 0
(-1.94E+Ol -
7A2E*Dt) 0*7
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVlROl'tl'MENTAL MONITORING NAMEOFFAClLlTY: SUSQUEllANNASTEAMELECTRlCSTATION LOCATIONOFFACILlTY: LUZERNECOUNTY,PENNSYLVA.NIA Reporting Period:
De~er3O,2002 to JanlUll)' 30, 2004 Page 6 of 13 ANALYSIS AND LOWER IDUT NUMBnROF MEDIUM ORPAnlWAY TOfALMJMBER OF A1J.INDJCATOR LOCATIONS LOCATION WmUIIGUBST MEAN CONIROLLOCATION NONROUllNB SAMl'lllD OFANALYSns DlITBCTION MEAN (3)
NAME MEAN (3)
MEAN (3)
RBPORTED lUNlTOPMBASUREMENr) PERFORMED!I}
~UDH2!
RANGE DISTANCE AND DlRBC110N RANGB RANGB Ml!A<;UREMEN1'S!"2 Sediment (pCiIkg TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVlROl'tl'MENTAL MONITORING PROGRAM *2003 NAMEOFFAClLlTY: SUSQUEllANNASTEAMELECTRlCSTATION LOCATIONOFFACILlTY: LUZERNECOUNTY,PENNSYLVA.NIA Reporting Period:
De~er3O,2002 to JanlUll)' 30, 2004 Page 6 of 13 ANALYSIS AND LOWER IDUT NUMBnROF MEDIUM ORPAnlWAY TOfALMJMBER OF A1J.INDJCATOR LOCATIONS LOCATION WmUIIGUBST MEAN CONIROLLOCATION NONROUllNB SAMl'lllD OFANALYSns DlITBCTION MEAN (3)
NAME MEAN (3)
MEAN (3)
RBPORTED lUNlTOPMBASUREMENr) PERFORMED!I}
~UDH2!
RANGE DISTANCE AND DlRBC110N RANGB RANGB Ml!A<;UREMEN1'S!"2 Sediment Gamma Spec (pCiIkg dry)
Be-1 8
3.30E+02 (6/6) 12P 6.99E+02 (2/2) 2.91E+02 (2/2) 0
(-2.53E+Ol
- 7.26E+02) 6.9 mi WSW (6.7IE+02
- 1.268+02)
(2.58E+02
- 3.25E+02)
K-40 8
1.318+04 (6/6)
LTAW 1.528+04 (2/2) 1.23E+04 (2/2) 0 (1.04E+04
- 1.58E+04) ons.iJ.c NE-ESI! (1.47E+04
- 1.58E+04)
(1.23E+03
- 1.73E+04)
Mn-54 8
9.58E+00 (6/6)
LTAW 1.368+01 (2/2) 3.11E+00 (2/2) 0 (1.78E+00 -
2.55E+OI) onsile NE*ESE (1.78E+00
- 2.55E+Ol)
(-3.54E+00. -
9:7SE+00)
Co-58 8
- l.07E+Ol (6/6) 12P
- 1.79E-Ol (212)
- 1.94E+Ol (2/2) 0
(-2.57E+Ol
- 2.4IE+00) 6.9 mi WSW (1.78E+00
- 2.4IE+00)
(-2.828+01 *
-1.05E+Ol)
Fe-59 8
-6.29E+00 (6/6) 2B 2.58E+Ol (2/2) 2.58E+Ol (2/2) 0
(-2.98E+Ol -
4.928+01) 1.6 mi NNE (2.3IE+00
- 4.928+01)
(2.31E+00
- 4.928+01)
Co-60 8
4.578+00 (6/6) 78 7.79B+00 (2/2)
.2.50E+00 (2/2) 0
(-9.06E+00 -
1.128+01) 1.2 mi SE (4.428+00 1.128+01)
(-1.2OE+Ol
- 7.04E+00)
Zn-6S 8
7.53E+00 (6/6)
LTAW 2.57E+Ol (2/2)
- 3.328+01 (2/2) 0
(*2.05B+Ol -
4.05B+Ol) ons.iJ.c NE-ESB (1.08B:,:01 4.05E+01)
(-6.23E+Ol * -4.07E+OO)
Zr-95 8
1.95E+Ol (6/6) 78 3.60E+Ol (2/2) 1.38B+Ol (2/2) 0 (1.20E+00
- 4.37E+Ol) 1.2 mi SE (2.83E+Ol
- 4.37E+Ol)
(5.34E+OO -
2.228+01)
Nb-95 8
0.008+00 (6/6) 2B O.ooE+oo (2/2)
O.ooE+oo (2/2) 0 (O.ooE+oo
- O.OOE+OO) 1.6 mi NNE (0.008+00
- O.ooE+OO)
(O.OOE+OO
- O.OOE+OO)
Cs-l34 8
150
-2.28E+oo (6/6)
LTAW 4.96E+00 (2/2)
-6.59E+00 (2/2) 0
(-8.528+00
- 7.96B+OO) onsile NE*ESE (1.978+00
- 7.96E+00)
(-l.07E+Ol *.2.538+00)
Cs-137 8
180 5.2OE+Ol (6/6) 78 8.928+01 (2/2) 7.56E+01 (2/2) 0 (6.91E+00 -
l.ooE+02) 1.2 mi SE (7.8 1E+0 1 l.ooE+02)
(4. 14E+Ol 1.IOE+02)
Ba*l40 8
-2.30E+Ol (6/6) 12F
-4.68E+00 (2/2)
-4.79E+Ol (2/2) 0
(*9.928+01
- 7.40E+Ol) 6.9 mi WSW
(.7. llE+OO * *2.25E+oo) (*I.IOE+02 1.428+01)
c MEDWMORPAntWAY SAMPLED roNIT DFMEASUREMl!N'I1 ANALYSIS AND Tal'ALNUMBER OF ANALYSES PI!RFORMED ~tl c'
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Perlo!l:
December 3D, 2002 to January 30, 2004 Page 7 or 13 LOWERUMIT OF AlL INDICATORLOCAlIONS LOCAlIONWITHInGIIESTMBAN DETECITON MBAN(3)
NMm MEAN (3)
~l(2!
RANGB DISTANCB AND DJRl!C1l0N KANGB
(
NUMBER OF CONTROLLOCAlION NONROUI'INB MBAN(3)
REl'OR11ID KANGB MJ!ASUREMF.NTS~~
c MEDWMORPAntWAY SAMPLED roNIT DFMEASUREMl!N'I1 Sediment (COI1l)
(pCi/kg dry)
, Ground Water (PC:III) t....I, *.
'~"
ANALYSIS AND Tal'ALNUMBER OF ANALYSES PI!RFORMED ~tl La-140 8
';"1,t Ra-226 8
Th-228 8
'Oammaspec K-40' 36 c'
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Perlo!l:
December 3D, 2002 to January 30, 2004 Page 7 or 13 LOWERUMIT OF AlL INDICATORLOCAlIONS LOCAlIONWITHInGIIESTMBAN DETECITON MBAN(3)
NMm MEAN (3)
~l(2!
RANGB DISTANCB AND DJRl!C1l0N KANGB
-9.83E+00 (6/6) 7B 2.81E+OI (2/2)
(-9.79HtOl '
- 4.89E+Ol) 1.2 mi SE (7.3SE+00 - 4.89E+Ol) 2.27E+03 (6/6) 7D 2.6tE+03 (2/2)
(1.96E+03',
- 2. 86E.f.03) 1.2 mi SE (2.36E+03. 2.86E+03) 3.21E+03 (6/6) 7D 3.SIE+03 (2/2)
(2.46E+03
- 3.S6E+03) 1.2 mi SE (3.47E+03 -
3,S6E+03)
-l.SSE+oo (24/24) 252 2.49E+00 (12/12)
(
NUMBER OF CONTROLLOCAlION NONROUI'INB MBAN(3)
REl'OR11ID KANGB MJ!ASUREMF.NTS~~
1.91E+Ot (2 J 2) 0 (1.78E+01. 2.0SE+01) t.60E+03. (212) 0 (7.S0E+02,. 2.4SE+03) 3.01E+03 (2/2) 0 (1.28E+D,3 -
4.74E+03) 2.33E+OO (12/12) 0
(-5.100+011 -
2.70E+OI)
O.9~
mi"'NNE: (-1.9OE+OI ;\\!. '2.70E+Ol) *:"*(-3.30E:tOlf'* -
5.3oE+Olj',:'.'l
~ 'j.
'-;;;',,..-;- "j -
I:' :'
':"~ :;~~.:~ \\
~~
~/"~,\\
1Mn:.S4
~.. '
- 36 15
-1.18E*0t' (24/24) lID 1.92E*01 (12/12) l.92E-Ol (12/12) 0
(-2.90E+oo
- 2.10E+OO),
5.2:
mi WSW: (.1.40Efoo ;,, * '2.00EfOO)
(-1.40E+oif'.'
2.ooE+OO)'::,
!,-, : ~:..
~:
~,.
_. I
'" ~ (
.,\\,-
!C0:58
-1.57E-Ol' (24/24)
\\
36 IS 12F3
-5.ooE-02 (12/12)
- 5.ooE-02 (12/12) 0
(-2.70E+00
- t.70E+OO) 5.2" mi WSW:; (-1.70E+00 1.200+00)
(-1.70E+00 1.20E+OO)' ' :
Fe-59 36 30 S.B3E-OI (24'/24) 252 6.42E-OI (12112) 3.7SE-Ol (12/12) 0
(-S.30E+00 -
6.10E+00) 0.9 mi NNE
(*S.30E+00. 6.10Efoo). (-4.20E+00
- 8.50E+00) i Co-60 36 15
- t:2BE-01 (24/24) 4S4 3.33E*02 (12/12)
- 1.0BE*01 (12/12) 0
(*2.40E+00 -
2.ooE+OO) 0.5 mi ENE
(.I.S0E+00. 2.ooE+OO)
(-2.BOE+oo
- 1.9OE+OO),.
Zn-6S 36 30
-1.32E+oO (24/24) 4S4
-1.20E+00 '(12/12)
-4.43E+00 (12/12) 0
(*9.40E+00
- 8.S0E+OO) 0.5 mi ENE
(*9.40E+OO -
8.500+00)
(-2.BOE+oo
'. 2.80E+OO)
, Zr*9S 36 30
-6.54E-OI (24"24) 12F3' 1.1sE+oo '(12/12) 1.1SE+00 '(12/12) 0
(-S.70E+00
- '3.30Efoo) 5.2 mi WSW
(-2.70E+00 -
5.40E+00)
(-2.70E+00 -
5.400+00)
Nb-9S
'36 is
~2.46E-02 '(24124), :
4S4 3.83E-Ol (l~ 112)
.2.42E-01 (12112) 0
(-2.90Efoo -
3.ooE+OOj 0.5 mi ENE
(-2.70E+00 -
3.ooE+00)
(-2.40E+00
- 2.10E+00)
. ~-
~. *...,..,
Cs-l34 36 15 1.74E-Ol (24/24) 4S4, '
4.42E-Ol (12/12)
-3.67E-Ot (12 112) 0
(.2.40E+00
- 2.80E+OO) 0.5 '
mi ENE
(-9.ooE-OI'
,,2.80E+00)
(*1.70E+00 1.20E+00)
"w.'
().IJ
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAME OF FACILITY: SUSQUEIIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30. 2002 to J anulll')' 30. 2004 Page 8 or 13 ANALYSIS AND LOWERUMIT NUMBER OF MEDIUM OR PATIlWAY TOTAL NUMBER OF AU. INDICATOR LOCAnONS LOCAnON WmllllGllEST MEAN CONTROL LqCAnON NONROUT1NE SAMPLED OF ANALYSES DETECI10N MEAN (3)
NAME MEAN (3)
MEAN(l}
REFORTfl>
~UNIT OF MEASUREMENTI PERroRMED ~1 ~
(LlDl!2~
RANGB DISTANCE AND DmECTION RANGE RANGB MEASUREMENTS!41 TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 2003 NAME OF FACILITY: SUSQUEIIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30. 2002 to J anulll')' 30. 2004 Page 8 or 13 ANALYSIS AND LOWERUMIT NUMBER OF MEDIUM OR PATIlWAY TOTAL NUMBER OF AU. INDICATOR LOCAnONS LOCAnON WmllllGllEST MEAN CONTROL LqCAnON NONROUT1NE SAMPLED OF ANALYSES DETECI10N MEAN (3)
NAME MEAN (3)
MEAN(l}
REFORTfl>
~UNIT OF MEASUREMENTI PERroRMED ~1 ~
(LlDl!2~
RANGB DISTANCE AND DmECTION RANGE RANGB MEASUREMENTS!41 Ground Water (COOl)
Cs*137 36 18
-1.28B-OI (24/24) 252
-1.14B-OI (12/12)
-3.75&01 (12/12) 0 (pCi/I)
(-1.70E+OO 1.40E+OO) 0.9 mi NNE
(*1.70E-+OO -
1.40E+oo)
(-2.20E-tOO
- I.20E-+OO)
Ba440 36 60
- 2.67B-Ol (24/24) 454 6.08B-Ol (12/12) t.08B-OI (12/12) 0
(*5.20B+OO 3.ooE+OO) 05 mi ENE
(-1.80E+OO -
2.60B-+OO)
(-4.80E+OO -
5.IOE-tOO)
La-I40 36 IS
-2.96B-Ol (24/24) 454 7.ooB-OI (12/12)
I.2SB-OI (12/12) 0
(-6.ooE+OO 3.40B+OO) 05 mi ENB
(*2.10B-+OO
- 3.ooE-tOO)
(*550E-+OO
- S.80E-tOO)
H*3 36 2000 5.44B+OI (24/24) 454 8.43E+Ol (12/12) 1.74E+Ol (12/12) 0
(-6.74B+Ol 1.93E+(2) 05 mi ENE
(*2.46E-tOO
- 1.93E+(2). (-8.84B+OI
- 8.86B+Ol)
Air Particulates Gross Beta 312 10 I.46E+Ol (208 I 208) 3S2 1.51E+OI (52/53) l.34B+Ol (104 I 104) 0 (E*03 pCi/ml)
(359E+OO
- 3.17E+Ol) 05 mi NE (5.30E+Ol
- 4.91E-tOO)
(3.16E+OO
- 3.10E+Ol)
Air Iodine 1-131 312 70 6.01B-04 (208 1208) 3S2 8.29B-04 (52/52)
-6.44E-OS (104 1104) 0 (B-03 pCi/m3)
(*S.27B-03
- S.97B-03) 05 mi NB (S.20B+OI *.2.79B-OJ)
(.3.74B-OJ
- 6.30B-OJ)
Air Particulates GammaSpcc Quarterly Composite Be-7 24 9.06E+Ol (16/16) 1251 9.10B+OI (4/4) 8.2 1 E+OI (8/8) 0 (E-03 pCilml)
(6.70E+Ol 1.11B+(2) 0.4 mi WSW (7.6SB+Ol 1.06E+(2)
(6.63B+Ol 9.34E+OI)
K-40 24 1.29B-+OO (16/16) 3S2 2.2IB-+OO (4/4) 9.20B-Ol (8/8) 0
(-4.94E+OO
- 4.04E+OO) 05 mi NB (2.27B-Ol
- 4.04E+oo)
(-5.79E+OO
- 4.66B+oo)
Mn-54 24 3.63B-02 (16/16) 601 1.10B-Ol (4/4) 9.2JB-02 (8/8) 0
(-6.98B-02
- 2.2JB-Ol) 135 mi ESE
(-5.7SB-Ol
- 3.29B-OI)
(*S.75B-Ol 3.29E-Ol)
L
(;,10
(
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAMEOFFACILITY: SUSQUEIJANNASTEAMELECTRlCSTATlON LOCATION OF FACILITY: L~ZERNE COUNTY, PENNSYLVANIA,.'
Reporting Period:,
DfCember 30, 2001 to ','
",Paie9orl3
~.
January 30, 2004 -"
ANALYSISAND LOWERUMIT
.' ;. I.
MEDIUMORPAntWAY TOTALNUMBER OF Au.tNDlCATOR LOCATIONS
. MEm(3),
RANGB t:.aCATIONv.TnllRGHF.STMEAN CONl'ROLlOCATION MBAN(3) "
RANGB SAMPU!D OF ANALYSES DB1"I!C1lON (UNIT OFMBASlJR.EMEND 1'l!RFORMBD (l)
(W)(1)
, NAMe MEm(3),
DtSTANCB ANDDnmC1lON RANGB NUMBER OF NONltOUl'INP.
REPORTED MBAmREMJ!NTS(4)
(
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 2003 NAMEOFFACILITY: SUSQUEIJANNASTEAMELECTRlCSTATlON LOCATION OF FACILITY: L~ZERNE COUNTY, PENNSYLVANIA,.'
Reporting Period:,
DfCember 30, 2001 to ','
",Paie9orl3
~.
January 30, 2004 -"
ANALYSISAND LOWERUMIT
.' ;. I.
MEDIUMORPAntWAY TOTALNUMBER OF Au.tNDlCATOR LOCATIONS
. MEm(3),
RANGB t:.aCATIONv.TnllRGHF.STMEAN CONl'ROLlOCATION MBAN(3) "
RANGB SAMPU!D OF ANALYSES DB1"I!C1lON (UNIT OFMBASlJR.EMEND 1'l!RFORMBD (l)
(W)(1)
Afr PartrculatH (cont)
Quartedy Composite (E*Ol pCiIm3)
,~.
~...
Co-58 PC:S9 r ',(. L' ~
2'J'*9S '
Nb-9S' 24 24 24 24 24 t,
- 1.76E*02 (16 I 16)
(-:3.02E.Ol "-
4.75E*Ol)
- 9.55E*02 (16 I 16)
(*I.ISE+OO t.OgE+OO) 2.3gE*02 (16 i 16)
, (-I.4SE-OI' 1.76E*OI)*
- 2.8gE-Ol (16 116)
(.I.34E+OO" 6.2SE-Ol)'
- ~, ~:.. I_
- r!:' J" 1.78E-02 (16 116)
(-S.13~~(!: * : ~.??E.o15'::
f O.OOE+OO (16 116)
((i.OOE+OO ".: O.OOE+oO)'
Cs*l34 24 50 O.OOE+OO (161 16)
(.S.96E-Ol
" ' 8.9tE*0l)
Cs-137 24 60 4.15E*02,(16 116)
(.9.46E*02 J.6lE-Ol)
Ba-140
.24
-4.S9E+OO (16/16)
(-2.38E+?I,,'
1.74E+0l),
La-140 24"
- 2.94E+OO ' (16 / 16)
, (-2.42E+Ol.' 4.8IE+OO)
-<, \\
~,
, NAMe MEm(3),
DtSTANCB ANDDnmC1lON RANGB 3S2 O.S 1251 0.4 Sot 12 '
1251 0.4' 13S6 0.4 601 13.S 1.3SE*Ol (4 14) mi NE"
(-6.89E*02 4.7SE*Ol)
S.03E-OI (4 14) mi 'WSW (1.0SE-OI I) 8.38E-02 (4 I 4) mi SSE"
(.3A4E.Ol
~,, 2.13E-Ol)
,,0:,.:
, I'
- 9.0lE-02 (8 I S)
(*3.SSE*Ol 4.g6E-02)
\\'
4.0SE-Ol (8 I 8)
(.8.34E-Ol 1.27E+oo) 5.70E-02 (8/8)
(-3. 17E-02 ~ *,2.i3E-Ol)
-7.97E-Ol (4 14)
,~2.46E-Ol, (8 18) " "";
mi"'wSW
(~S.~Ot,:'. 6.~1),J (.l.Ol~:*OO, -" 2.?3E-0l)*
8.62E-02 (414)...,
- 7.31E-02 (8/8) mi W
(.3.07E.Ot', -,4.77E-01)
(-2.42E-Ol, -" 9.69E-0l)
O.OOE+OO * (4/4) ';
,;~,.,
O,OOE+OO, (8/8) "',
mi' ESE (o.oOE+OO' ':
O.OOE+OO)
(O.OOE+OO'
,O.oOE+oO) 1281
- 3,46E-02 (414)
-3.00E-Ol (8 18), l 0.4 mi WSW
(-9.70E-0l 4.42E-0l)
(-'S.09E-Ot, -
2.49E-02) 13S6 1.19&01, (414) 2.07E-02 (8/8) 0.4 mi W
(6.29&02 1.6 IE-O 1)
(.6.S2E-02 t.OlE-ot) 12EI 4.7 1251 0.4 5.S4E+OO (4 14) mi WSW, (-4.OlE+OO
-t.74E+01) 1.97E+oO (4 /4) mi WSW, (-4.43E-01
-4.8lE+OO)
'j
~.,,.
- 2. 12E*Ot (8 IS)
(.1.19E+OI
-, S.l7E+OO) 4.77E-Ol ' (8 /8)
(-S.49E+OO l.2SE+OI)
NUMBER OF NONltOUl'INP.
REPORTED MBAmREMJ!NTS(4) o o
o o
o o
o o
o o
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAME OF FACIUTY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACIUTY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2002 to January 30, 2004 Page 10 ot13 ANALYSIS AND LOWERUMlT NUMBBROP M1IDItJM ORl'ATIlWAY TOTALNUMBER OF ALL INDICATOR LOCATIONS LOCATION MlllmGImsT MEAN CONrROLLOCATION NONROtmNB SAMl'llID OPANALYSES DEl"ECIlON MBAN{3)
NAME MEAN (3)
MBAN(3)
REPORTED
~UNIT OFMBASUREMBNI1 PHRFORMED ~I~
~IlJ)lP!
RANOB DISTANCE AND DIREmlON RANOB RANGE MBASUREMF..Nl'S~4!
Milk 1-131 76 5.32B-02 (57/57) 1001 9.0SE-02 (19/19) 9.0SB-02 (19/19) 0 (pC'JJ1)
(-1.70E-OI -
4.40E-Ol) 14 mi SSW
(-S.ooE 4.50E-Ol)
(-8.ooE 4.50B-0l)
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRA¥. 2003 NAME OF FACIUTY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACIUTY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2002 to January 30, 2004 Page 10 ot13 ANALYSIS AND LOWERUMlT NUMBBROP M1IDItJM ORl'ATIlWAY TOTALNUMBER OF ALL INDICATOR LOCATIONS LOCATION MlllmGImsT MEAN CONrROLLOCATION NONROtmNB SAMl'llID OPANALYSES DEl"ECIlON MBAN{3)
NAME MEAN (3)
MBAN(3)
REPORTED
~UNIT OFMBASUREMBNI1 PHRFORMED ~I~
~IlJ)lP!
RANOB DISTANCE AND DIREmlON RANOB RANGE MBASUREMF..Nl'S~4!
Milk 1-131 76 5.32B-02 (57/57) 1001 9.0SE-02 (19/19) 9.0SB-02 (19/19) 0 (pC'JJ1)
(-1.70E-OI -
4.40E-Ol) 14 mi SSW
(-S.ooE 4.50E-Ol)
(-8.ooE 4.50B-0l)
OammaSpcc K-40 76 1.38E+03 (57/57) 1001 1.41E+03 (19/19) 1.4IE+03 (19 119) 0 (9.4~E+02 1.55E+03) 14 mi SSW (S.19E+02 -
1.53E+03)
(8.19E+02 ' -
1.53E+03)
Mtr54 76
-1.8SB-Ol (57/57) 10DZ
-5.268-02 (19/19)
-4.428-01 (19/19) 0
(-4.30E+OO -
2.50E+00) 3.1 mi SSW
(-2.60E+oo -
2.50E+00)
(-3.IOE+OO -
1.60E+OO)
Co-58 76
-4.ooE-OI (57/57) 1001
-7.S9E-02 (19/19)
-7.898-02 (19119) 0
(-4.10E+00 -
3.30E+00) 14 mi SSW
(-3.70E+00 -
2.30E+00)
(*3.70E+00 -
2.30E+00)
Fe-59 76 4.60E-Ol (571 S7)
IOD2 8.32E-Ol (19/19) 1.42B-OI (19/19) 0
(-1.20E+Ol 1.228+01) 3.1 nu SSW
(-4.ooE+OO -.8.ooE+OO)
(-4.60E+OO -
7.30E+00)
Co-60 76 2.41E-Ol (57/57) 1001
- 6. 11E-Ol (19/19) 2.21£*01 (19/19) 0
(-4.70E+00 -
5.40E+00) 3 mi SSW
(-3.00£+00. 3.30E+00)
(-2.9OE+00. 2.9OE+00)
Zn-65 76
-2.77E+00 (57/57) 1002
-9.2IE-Ol (19/19)
-2.928+00 (19/19) 0
(-I.60E+Ol. 7.00E+00) 3.1 nIi SSW
(-I.60E+Ol -
7.00E+OO)
(-I.34E+Ol -
4.20E+00)
Zr*95 76
-2.63E-02 (57 J 57) 12H2 3.58£.01 (19/19)
-2.5gB-01 (19119) 0
(-7.20E+00 -
3.60E+00) 1.7 mi WSW
(-4.30E+OO -
3.60E+00)
(-4.30E+00 -
7.50£+00)
Nb-95 76 2.56E-Ol (57/57) 1001 4.31E-Ol (19/19) 4.31E-Ol (19/19) 0
(-2.80£+00 -
4.70£+00) 14 mi SSW
(-2.00£+00 -
2.70E+00)
(-2.00£+00 -
2.70E+00)
Cs-l34 76 15
-S.71E-03 (57/57) 1002 4.11B-01 (19/19)
- 2.21&01 (19/19) 0
(-4.00E+OO. 4. 1 OE+OO) 3.1 mi SSW
(-1.70£+09 -
2.80£+00)
(-2.80E+00 -
2.6OE+00)
Cs*137 76 18
-S.71E-03 (57/57) 1001 S.58E-Ol (19/19) 5.58B-01 (19/19) 0
(-3.20£+00 -
3.S0E+00) 14 mi SSW
(-1.20E+OO* -
2.60E+OO)
(-1.20E+00 -
2.60E+OO)
Ba-140 76 60
-2.49B-Ol (57/57) 1001 1.89£-01 (19/19) 1.89E*OI (19/19) 0
(-4.80£+00 -
5.00E+00) 14 nIi SSW
(-2.70E+OO -
3.90£+00)
(-2.70E+00 -
3.9OE+00)
La-l40 76 15
- 2.8SB-Ol (571 S7).
1001 2.16.6-01 (19119)
- 2. 16E-Ol (19/19) 0
(-5.50E+00 -.5.80E+00) 14 nIi SSW
(-3.10E+OO. 4.40E+00)
(-3.10E+00 -
4.40E+00)
(
(~
(
MEDIUMORPA111WAY SAMPI.J!l)
(UNlT OPMBAS1.lREMEN"O son TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
'Detember 30, 2002 to
' Ianuary 30, 2004 ',
- ': Page 11 olll
~ '. -I" I
ANALYSIS AND LOWERUMIT TOfALNUMBER OF AIL INDICATOR LOCATIONS LOCATIONwmJlnGHBSTMEAN,
OP ANALYSES Dm:nCTION M1lAN(3)
NA}.m MEAN (3)
PERFORMED ~Sl (lll))(Zl RANGB DISTANCE AND DIRECTION,.'
, RANGE ',',
Gamma Spec NUMBER OF CONTROL LOCATION NONROtmNB MEAN (3)
REI'OImID RANGE MEAStJREMENTS~4!
MEDIUMORPA111WAY SAMPI.J!l)
(UNlT OPMBAS1.lREMEN"O son (pCiIkg chy)
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
'Detember 30, 2002 to
' Ianuary 30, 2004 ',
- ': Page 11 olll
~ '. -I" I
ANALYSIS AND LOWERUMIT TOfALNUMBER OF AIL INDICATOR LOCATIONS LOCATIONwmJlnGHBSTMEAN,
OP ANALYSES Dm:nCTION M1lAN(3)
NA}.m MEAN (3)
PERFORMED ~Sl (lll))(Zl RANGB DISTANCE AND DIRECTION,.'
, RANGE ',',
Gamma Spec K-40 8
l.44E+04 (6/6) 13S6 1.62E+04 (2/2)
(l.03E+04 1.82E+04) 0.4 mi W
(l.43E+04
- 1.82E+04)
Mn-S4 8
- 1.S0E+00 (6/6),
13S6
- S.ooE-OI (2/2)
(.9:ooE+00 * '4.00E+OO) 0.4 mi W
(.S.ooE+oo
- 4.00E+OO)
Co-58 8
- 6.33E+00 (6/6) 3S2 l.OOE+OO (2/2) "
(-1:8OB+01 *,9'OOE+OO) 0.5 mi NE
(:7.00~+OO
- 9.00E+OO)
Pc-59 8
-6.17B+OO (6/6), '
1356
, 4.00B+OO (2/2);.,.,:'
, (~2.80E+61 -
3.60B+0l) 0.4 tid W
(-2.8~+.01
- 3.60E+Ol)
,I J. ~,~
'1'
- :.' ~ ~. r
... ~
"CO-:60 8
4.00B+00 (6 1,6)".,'
3S2,_
7.00E+OO (2'.2),
, f1.80E+01
-1.2QE+01) 0.5 mi,'rm (2.00E+OO -
1.20B+Ol)
~ 1.,.....
Zn-6S 8
- l.87B+O I (6/6) "
1251
~..
,9.00E+00 (2/2),
(-1. 1 OE+02
- 6.ooB+Ol) 0:4 mi WSW
(-3.2OB+01 -
- S.ooB+01)
Zr-9S 8
-1.15B+03 (6 /6) 801 4.80B+Ol (2/2).'
(-6.70B+03
- 3.00B+01) 12 mi SSE (4.70B+(Jt
- 4.90E+01)
~95 8
4.67B+00 (616) 801 1.70E+Ol (212)
(4.30E+Ol
- l.60E+Ol) 12 mi SSE
(.S.OOE+OO
- 3.90E+01)
Cs*l34 8
3.83B+00 (6/6) 801 3.30E+Ol (212)
(-7.00E+OO -
2.40E+Ol) 12 mi SSE (l.40E+Ol -
S.20E+Ol)
,Cs-137 8
4.28B+Ol (6/6) 1281 8.60E+Ol (2/2)
(*2.10E+Ol * " 9.60B+Ol) 0.4-mi:*WSW
. (7.60E+Ol 9.60B+Ol)
Ba*140 8
6.67B-Ol (6/6) 3S2 2.S0E+01,. (212)
(.S:OOE+Ol" 8.00E+0I)
O.S
'IDi NE
' (1.ooE+Ol
- 4.00B+Ol)
. La-l40 8
-1.13B+Ol (6 /6) 3S2 l.05B+Ol (212)
-(4.90B+Ol -
1.40E+0l).
0.5 ini NE (7.00E+oo,.-
1.40B+OI)
~
~... :',',
- t ' **,,:,I
- f,r '" ***
I NUMBER OF CONTROL LOCATION NONROtmNB MEAN (3)
REI'OImID RANGE MEAStJREMENTS~4!
1.06E+04 (2/2) 0 (1.02E+04
- 1.10E+04)
- 1.20E+Ol (2/2) 0
(-I.90B+Ol -
-S.OOE+OO)
O.OOE+OO (2/2) 0
(-S.OOE+OO
- S.OOB+OO) 4.05B+Ol (2/2) 0
(.7.2OB+01 -
- 9.00E+OO)
.1.OOB+Ol (2/2) 0
(.1.80B+Ol -
-2.00E+OO)
S.OOB+OO (2/2) 0
(.3.00E+Ol
- 4.00B+Ol) 4.80B+Ol (2/2) 0 (4.70B+Ol
- 4.90B+Ol) 1.70B+Ol (2/2) 0
(.S.OOE+oo -
3.90B+OI) 3.30E+Ol (2/2) 0 (1.40E+Ol
- 5.20E+Ol) 7.45B+Ol (2/2) 0 (S.20B+Ol
- 9.70E+Ol)
-1.80B+O'l (2/2) 0
(.2.S0E+Ol -
-1.IOE+Ol)
.2.0SB+Ol (2/2) 0
-(2.80E+Ol -
-1.30E+Ol)
(].13
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING 2003 NAME OF FACILITY: SUSQUEHANNASTEAMELECTRICSTATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 1001 to January 30, 1004 Page 11 or 13 ANALYSIS AND LOWERllMIT NUMBER OF MEDIUMORPAnlWAY TarALNUMBER OF AILlNDlCATOR LOCAnONS LOCAnONWnllInGUBSl'MEAN CONrROLLOCAnON NONROUIlNB SAMPLED OPANALYSIlS DBTBCllON MEAN (3)
NAME MEAN (3)
MEAN (3)
REPORTED
!UNITOFMBASUREMENT) PERFORMED!!}
!un~p~
RANGB DlST ANa! AND DIRECIlON RANGB RANGB MBAWRE.MENTS(4!
Soil (com)
&a-226 0
0 (pCiJkg dIy)
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 2003 NAME OF FACILITY: SUSQUEHANNASTEAMELECTRICSTATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 1001 to January 30, 1004 Page 11 or 13 ANALYSIS AND LOWERllMIT NUMBER OF MEDIUMORPAnlWAY TarALNUMBER OF AILlNDlCATOR LOCAnONS LOCAnONWnllInGUBSl'MEAN CONrROLLOCAnON NONROUIlNB SAMPLED OPANALYSIlS DBTBCllON MEAN (3)
NAME MEAN (3)
MEAN (3)
REPORTED
!UNITOFMBASUREMENT) PERFORMED!!}
!un~p~
RANGB DlST ANa! AND DIRECIlON RANGB RANGB MBAWRE.MENTS(4!
Soil (com)
&a-226 0
0 (pCiJkg dIy) nl.-228 8
7.89E+02 (6/6) 382 1.02E+03 (2/2)
- 8. 15E+02 (2/2) 0
(-2.00&00 1.00E+03) 0.5 mi NE (UlOE+03 -
I.04E+03)
(7.30E+02 -
9.00E+02)
Food/Garden Crops OammaSpcx:
(pC'1Ikg wet)
Be-7 2
8.43E+00 (2/2)
UP2 1.39E+Ol (1
I) 0 (2.95E+OO 1.39E+Ol) 5.5 mi SW (1.39E+Ol
- 1.39E+Ol)
K-40 2
4.S6E+03 (2/2) 1102 4.66E+03 (111) 0 (4.47E+03 -
4.66E+03) 3.5 mi SW (4.66E+03 -
4.66E+03)
Mn-S4 2
-4.75E-Ol (2/2)
UD2 1.36E+00 (111) 0
(-2.31E+00 -
1.36E+OO) 3.5 mi SW (1.36E+00 -
1.36E+00)
Co-58 2
-1.28E+OO (2/2) 1102
-1.07E+00 (111) 0
(-1.48E+00 -
.1.07E+00) 3.5 mi sW
(-1.07E+00 -
-1.07E+00)
Fe-59 2
- 3.75E-Ol (2/2) llF2 1.97E+OO (111) 0
(-2.72E+00
- 1.97E+00) 5.5 mi sW (1.97E+00 -
1.97E+00)
Co-60 2
3.48E+00 (2/2) llF2 5.53E+OO (111) 0 (1.42E+00 -
5.53E+00) 5.5 mi SW (5.53E+00
- 5.53E+00)
Zn-6S 2
-2.01E+Ol (2/2) llF2
- I.69E+O 1 (1/1) 0
(-2.33E+Ol -
.1.69E+Ol) 5.5 mi SW
(*1.69E+Ol * *1.69E+0l)
Zr-95 2
7.40E-Ol (2/2) 1IP2 5.73E+OO (1/1) 0
(-4.25E+OO
- 5.73E+00) 5.5 mi Sw (5.73E+00
- . 5.73E+00)
~95 2
O.OOE+OO (2/2)
UD2 O.OOE+OO (1/1) 0 (O.OOE+OO
- O.OOE+OO) 3.5 mi SW (O.OOE+OO
- O.OOE+OO) 1-131 2
-6.32E+00 (2/2) 1IP2
-6.01E+OO (111) 0
(-6.63E+00 -
-6.01E+OO) 5.5
'mi SW
(-6.01E+00 * -6.01E+00)
(
co.
ANALYSlSAND MEDIUM OR PATIlWAY TOl'ALNUMBER SAMPlED OF ANALYSES (UN!TOFMBASUREMENl) PERFORMED Cll TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATIONOFFACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2001 to January 30, 1004 Page13ort3 LOWERUMIT OF AIL INDICATOR LOCATIONS LOCATIONwmlIDGHEST MEAN DETECTION MBAN(3)
NAME MEAN (3)
(llD) (1)
RANGE DISTANc:B AND DIRECTION RANGE I. The total nnmber of analysis does not include duplicates, splits, or tepealed analyses.
- 2. The Teclmica1 Requirement LtO's are shown when applicable.
- 3. The means are based on an available measured results. When possible, this includes those below the MDCs as wen as those above them.
- 4. USNRC reporting levels are specified in the Teclmica1Requiremcnts.
(
NUMBBROP CONI'ROL LOCATION NONROUl1NB MEAN (3)
REPORTIID RANGE M1!ASU1U!MENTS(4) co.
ANALYSlSAND MEDIUM OR PATIlWAY TOl'ALNUMBER SAMPlED OF ANALYSES (UN!TOFMBASUREMENl) PERFORMED Cll Food/Garden Crops (conl)
(pCiIkg wet)
Cs-I34 2
Cs-137 2
Ba-140 2
La-140 2
TABLEG
SUMMARY
OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *1003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATIONOFFACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:
December 30, 2001 to January 30, 1004 Page13ort3 LOWERUMIT OF AIL INDICATOR LOCATIONS LOCATIONwmlIDGHEST MEAN DETECTION MBAN(3)
NAME MEAN (3)
(llD) (1)
RANGE DISTANc:B AND DIRECTION RANGE
-t.9lE+OI (2/2) llF2
-1.S2E+Ol (1 fl)
(-2.00E+Ol
-1.82E+Ot) 5.5 mi SW
(-1.82E+Ol. -1.82E+OJ)
-3.S4E+OO (2/2) 1100
-1.07E+OO (Ill)
(-6.00E+OO -
-1.07E+OO) 3.S mi SW
(-t.07E+OO -
-1.07E+OO) 1.89E+01 (212) llF2 4.4lE+Ol (1fl)
(-6.32E+OO.
4.4lE+Ol)
S.S mi SW (4.41E+Ot. 4.4tE+Ol)
-l.B4E+OO (2f2) 1100 5.5SB-Ot (1ft)
(-4.24E+OO -
S.5gB-Ol) 3.5 ml SW (5.5gB-Ot -
5.5SB-Ot)
I. The total nnmber of analysis does not include duplicates, splits, or tepealed analyses.
- 2. The Teclmica1 Requirement LtO's are shown when applicable.
- 3. The means are based on an available measured results. When possible, this includes those below the MDCs as wen as those above them.
- 4. USNRC reporting levels are specified in the Teclmica1Requiremcnts.
(
NUMBBROP CONI'ROL LOCATION NONROUl1NB MEAN (3)
REPORTIID RANGE M1!ASU1U!MENTS(4) 0 0
0 0
0*15
2003 Radiological Environmental Monitoring Report APPENDIX*H
[:;; ;,
2003 Radiological Environmental Monitoring Report H-1
I I AppendixH The data presented in the following tables were included if specific analysis results routinely exceeded the applicable MDCs in 2003 andlor routinely may have done so in previous years. The comparisons may be useful for observing any step changes that may occur in the. environment over a wide area. However, the importance attached to these comparisons shouid' be tempered by 'the understanding' that' changes, in methods. of analysis, typical MDCs achieved by the analyses, and averaging methods over the years may tend to blur the picture in sOIl1~ cases.
2003 Radiological En~jronmentall\\lonitorlng Report H-2 I I AppendixH
.) ::::".~--,
.~.;
.'
- j".~,
The data presented in the following tables were included if specific analysis results routinely exceeded the applicable MDCs in 2003 andlor routinely may have done so in previous years. The comparisons may be useful for observing any step changes that may occur in the. environment over a wide area. However, the importance attached to these comparisons shouid' be tempered by 'the understanding' that' changes, in methods. of I
analysis, typical MDCs achieved by the analyses, and averaging methods over the years
\\.......J may tend to blur the picture in sOIl1~ cases.
2003 Radiological En~jronmentall\\lonitorlng Report H-2
, A,;,iendiX H AMBIENT RADIATION MONITORING', l; TABLEHI AMBIENT RADIA nON LEVELS AS MEASURED BY TLDS (mRlSTD QTR)
Location
,-*-~~Control~~
.:-~
Period Ran2e Mean AQUATIC PATHWAY MONITORING ~'
" '"TABLE H 2 SURFACE 'NATER GROISS BETAACTIVITJES (pCiJI)
Location
-~--.
~
Indicator'
~
-~. 'Control Period Range
,Mean TABLE H3 SURFACE WATERJODINE-131 ACTIVITIES Location Period Range Mean
~\\TABLE*H
~
'-SURFACE WATER TRITIUM ACTIVITIES (pCiJI) rjl~~:
"Period
~.
Mean
- 1990 results were not averaged with 1982-01 data because the validity ofthe 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the 1990 Annual Report.
H-3 Radiological Environmental Monitoring Report
, A,;,iendiX H AMBIENT RADIATION MONITORING', l;
.: ;;: ~
TABLEHI AMBIENT RADIA nON LEVELS AS MEASURED BY TLDS (mRlSTD QTR).
--Location -,- -, -
, " "-. ~Indicator:':"':"""::-'.-r..,-,-*-~~Control~~
.:-~
Period Pre-Op.. :
Operational Pre-Op Operational 1978-81 1982-02 2003 1978-81 1982-02
'2003 Ran2e 18.5-19.2 14.7-20.8 15.0-17.9 14.8-20.8 Mean 18.9 18.2 20.2 16.3 17.9 19.0
~. :.,,~.. ~, \\
- o. ~~, ~
- AQUATIC PATHWAY MONITORING ~'.:
" '"TABLE H 2 SURFACE 'NATER GROISS BETAACTIVITJES (pCiJI),
Location
-~--.
~
Indicator'
. ~..-~.-"'-
~ -
-~. 'Control ~'
...w
~
Period Pre-Op Operational "
Pre-Op
, Operational' 1978-81 1982-02 2003 1978-81 1982-02 2003 Range 3.2-4.9 3.0-7.7 2.9-5.2 2.8-6.7
,Mean 3.8 5.6. "
- .:.~6:1;:~
4.0 3.8 2.4
" : TABLE H3 SURFACE WATERJODINE-131 ACTIVITIES (pCiJI)
Location
"
- Indicator I Coritrol Period
- Pre-Op Operational Pre-Op Operational 1979-81 1982-02 2003 1979-81 1982-02 2003 Range 0.24-0.37 0.06-0.61 0.29-0.43 0.03-1.0 Mean 0.29 0.32 0.36 0.36 0.32 0.26 "t
I
, ;: : j;' ~\\TABLE*H 4
~ "'
~
'-SURFACE WATER TRITIUM ACTIVITIES (pCiJI)
Location* '
Indicator I i: rjl~~:
.,Control i
, "Period Pre-Op
- -"', Operational' 1
' :'Pre-Op'
\\.".. Op.erational
- .. ~.
1978-81
',', 1982.:02*
-~003
..,1978-81,
,:1982-02*
2003
- -:Ran2e..
'101-122 126-1363" 119-319
-239 - +212 Mean 109 573 1,576 171 52 32
- 1990 results were not averaged with 1982-01 data because the validity ofthe 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the 1990 Annual Report.
- 2003 Radiological Environmental Monitoring Report
I I AppendixH TABLEH5- "
DRINKING WATER GROSS ALPHA ACTIVITIES (pCiJI)
Period
' Preoperational-"
Operational 1980- 81 '
' 1982 -02 2003 "
Ran2e' 0.1 -10.0 Mean-1.3 1.4 0.18 TABLEH6 DRINKING WATER GROSS UETA ACTIVITIES (pCiJI)
Period Preopera tional Operational 1977 - 81' 1982 - 02, 2003 Ranee 2.2 - 3~2 2.1.. 5.4' Mean
, 2.7
'3:1 2.1
~
TABLEH7 DRINKING,WATER TRITIUM ACTIVITIES (pCiJI)
Period Preoperational',
Ran2e' Mean TABLEHS' FISH POTASSIUM-40 ACTIVITIES (pCi/g wet)
- Location Control Period Pre-Op Operational Pre-:-Op Operational 1977-81 1982-02~
2003:
1977-81 1982-02 2003 Ram~e 2.7 - 3.5
',3~1 '-5.3 2.8 - 3.6 3.1 -4.2 Mean 3.2
,3.8 3.6 3.2 3.5 3.2 2003 Radiological Enyironmental Monitoring Report H-4 I I AppendixH TABLEH5- "
DRINKING WATER GROSS ALPHA ACTIVITIES (pCiJI)
Period
' Preoperational-"
Operational 1980- 81 '. '
' 1982 -02 2003 "
Ran2e'
' : 0.1 -10.0 Mean-
."*1
,, 1.3 1.4 0.18 TABLEH6 DRINKING WATER GROSS UETA ACTIVITIES (pCiJI)
Period Preopera tional Operational 1977 - 81' 1982 - 02, 2003 Ranee 2.2 - 3~2 2.1.. 5.4' Mean
, 2.7
'3:1 2.1
~
TABLEH7 DRINKING,WATER TRITIUM ACTIVITIES (pCiJI)
Period Preoperational',
Operational 1977"": 81' 1982 - 02 2003 Ran2e' 101 -194
'-247 :.. +220 Mean 132 62 62 TABLEHS' FISH POTASSIUM-40 ACTIVITIES (pCi/g wet)
- Location
- . ", '. Iridicator;* -:
J,",
~J Control Period
- Pre-Op Operational
. Pre-:-Op Operational :
1977-81 1982-02~
2003:
1977-81 1982-02 2003 Ram~e 2.7 - 3.5
' ',3~1 '-5.3 2.8 - 3.6 3.1 -4.2 Mean 3.2
,3.8 3.6 3.2 3.5 3.2 2003 Radiological Enyironmental Monitoring Report H-4
\\. Armendix SEDIMENT POTASSIUM-40 ACTIVITIES (pCi/~ dD'l
. Location Indicator Control Period Ran2e"
, 'Mean SEDIME:ST RADIUM-226 ACTIVITIES (pCi/2 dry)
Location Indicator Control Period Ran2e Mean
~
SEDIMENT THORIUM-228 ACTIVITIES (pCi/g dry),
, Location 1.
Period Range Mean r~
- Th-232 was reported instead ofTh-228 CESIUM-137 ACTIVITIES (pCilg dry)
Period Range Mean H-S
~'." 2003 Radiological Environmental Monitoring Report
\\. Armendix H**.
SEDIMENT POTASSIUM-40 ACTIVITIES (pCi/~ dD'l
. Location Indicator Control 7~"
- Period
,Pre--Op, :'. Operational
, Prc-Op
. Operational
"'1978*81 1982-02 2003
"'1978-81 1982-02
.*.*2003 Ran2e". 8.6-10.4 7.4';13.6 7.5-11.0
- ',6.2-13.0
~
- t
, 'Mean
> '9.3
"': 10.8 l
'12.3
~
'7.7 '
10.5 12.9 SEDIME:ST RADIUM-226 ACTIVITIES (pCi/2 dry)
Location Indicator Control Period
- Pre--Op Operational'
.Pre--Op Operational
,:1978-81 " : ~1982-02 ".
'2003 : "1978-81 c 1982-02 2003 Ran2e
- '0.5-0.7 0.5-2.0:
,0.6-1.9 0.4-2.1 '.
Mean 0.6
'15 ',"
",2.4',,
0.7 1.5 1.6
~-,-
~.'..
i ':TABLEHll-:
. SEDIMENT THORIUM-228 ACTIVITIES (pCi/g dry),
, Location
' Indicator' 1. ': :
Control Period
. 1984': 02* ,'f
." ' '2003
- 1984 ~ 02*
2003 Range 0.9 - 1.7 0.8-2.F*
Mean 1.1 3.2 1.1 3.0
...... '\\.,:.. l',- "
r~ * "
- Th-232 was reported instead ofTh-228 in:*1990..
~,:: :. I!'
'( ~
~:. ":.: ~',,:
- ~<
J"
,f;;.
,;,,\\; ;':':rtABLEHii*: '
.. :.*:SEDIMENT CESIUM-137 ACTIVITIES (pCilg dry)
. Location"
..,'.., Indicator.. I
.,............ ~
1 ~.
~,
- 'Control
- . ~ "'"
Period
.. 'Pre--Op',. " <", Operational
- Pre:"Op.,: ':
". Operational
....-.
- I ~.1978-81*
'.. :1982~2 __ ~2003...
,11978-81
' 1982-02
" 2003 Range 0.08-0.15*. I
. 0.04-0.17
..*. ! __ f
- "0.08-0.21 0.06-0.21 Mean 0.10 0.09 0.07 0.11 0.11 0.08 H-S
~'." 2003 Radiological Environmental Monitoring Report
AppendixH ATl\\10SPHERIC PATHWAY MONITORING
. TABLEH13" AiR PARTICULATE GROSS BETA ACTIVITIES (E-3 ilCilm3),
Location
~ -..
Control Period Range Mean TABLEH14 AIR I~ARTICUL)~TE BERYLI..IUM-7ACTivriiiS(E-fpCilmJ.,
. Location Period Ranee Mean
- 1990 results were not averaged with 1982-01 data because the validity of the 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the'1990 'Annual Report.
TERRESTRIAL PATHWAY MONITORING TABLE HIS SOIL POTASSIUM-40 ACTiVITIES (pCil2 dry)
Location Period..
.: Ran2e c'
Mean 2003 Radiological Environmental Monitoring Report
'. H-6 I I AppendixH ATl\\10SPHERIC PATHWAY MONITORING
. ': ','1'
. TABLEH13" AiR PARTICULATE GROSS BETA ACTIVITIES (E-3 ilCilm3),
Location
~ -..
- Indicator, Control Period Pre-Op ; i' Operational "Pre-Op Operational 1978-81
" 1982-02
. 2003
.. 1978-81 1982-02 2003 Range 24-97 13 - 29 24 -102 12-28 Mean 61 16 15 62 16 13 TABLEH14 AIR I~ARTICUL)~TE BERYLI..IUM-7ACTivriiiS(E-fpCilmJ.,
. Location Indicator' Control
- Period
. Pre-Op*
Operational Pre-OU..
' Operational 1978-81 1982-02*
2003 1978-81 1982-02*
2003 Ranee 69 - 81 50 - 137 59 - 85 49 -126 Mean 76
- 95 91 72 88.
82.
- 1990 results were not averaged with 1982-01 data because the validity of the 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the'1990 'Annual Report.
TERRESTRIAL PATHWAY MONITORING TABLE HIS SOIL POTASSIUM-40 ACTiVITIES (pCil2 dry)
Location Indicator'. -, -;.'.
.****Control Period Pre-Op Operational Pre-Op.
Operational. ':
1979&81
- .1984-02 2003
. 1979&81 1984-02.
2003'
.: Ran2e c'
. 9.2 - 9.7 9.4-15.3 9.1'-1 [0 7.4-14.1 Mean 9.5 11.7 14.4 10.1 10.5 10.6.
2003 Radiological Environmental Monitoring Report
'. H-6 I I
- Appendix H
"~TABLEH 16
':':~ '::>;'~i',,!~~SOILRADIUM-226ACTIVITIES '(pCilg di'y)'~:!"
Location Indicator Control Period
.**.~1984*02
-Range, 1 Mean
- Radium-226 was not measured in 2002 or 2003.
TABLEH 17
,, SOIL THORIUM~228 :ACTIVITIES (pCi/g dry)
Location Indicator Control Period Range Mean TABLEH 18
- SOIL CESIUM~137,ACTIVITIES (pCi/g (lIj)
Location Period Range Mean TABLEH 19
'.' MILK POTASSIUM~40 ACTIVITIES JJ)CiII).
Location Indicator Control Period Range Mean
,.,'2003 Radiological Environmental Monitoring Report
- Appendix H
"~TABLEH 16
,".. ':':~ '::>;'~i',,!~~SOILRADIUM-226ACTIVITIES '(pCilg di'y)'~:!".. '
Location I
Indicator Control Period
' Pre-Op,:
- ';Operational,
- ', :.. Pre-Op
, Operational 1979&81, ~~1984*02* ;: 2003*', 1979&81
.**.~1984*02 2003 "
-...... *~:*.;..... t.
-Range,
.0
'0.8 -1.3
,0.8 - 2.5 o' i....
0.8 - 1.2' 1.0 - 2.2.'
1 Mean 1.1 1.6 i'
- 0 1.0 1.7
- o.
- Radium-226 was not measured in 2002 or 2003.
TABLEH 17
,, SOIL THORIUM~228 :ACTIVITIES (pCi/g dry)
Location Indicator Control Period Pre-Op Operational Pre-Op Operational 1979&81 1984*02 2003 1979&81 1984*02 2003 I
Range 0.9 -1.3 0.8-2.0 0.7 -2.4 I
Mean 1.1 1.0 0.8 1.0 1.0 UJS TABLEH 18
.'. :SOIL CESIUM~137,ACTIVITIES (pCi/g (lIj)
Location Indicator Control Period Pre*Op Operational Pre-Op Operational 1979&81 1982*02 2003 1979&81 1982-02 2!2L1 Range 0.5 -0.7 0.02 - 0.5 0.2 -1.2 0.09 -1.2 Mean 0.6 0.2 0.04 0.7 0.4 V.VI TABLEH 19
_i
'.' MILK POTASSIUM~40 ACTIVITIES JJ)CiII).. ;'
Location Indicator Control Period Pre-Op Operational Pre-Op Operational 1978*81 1985*02 2003 1978*81 1985-02 2003 Range 1222-1500 1241-1422 1273-1500 1247-1472 Mean 1325 1333 1383 1390 1331 1406
,.,'2003 Radiological Environmental Monitoring Report
I I AopendixH
',TABLE H20 GROUND WATER TRITIUM ACTIVITIES (pCiII)
Location Indicator Control Period
'Pre-Op'
, Operational:
. Pre-Op.',. '.. Operational 1980-81 1982-02 2003
. 1980-81
', 1982-02 2003',
. Range'. -., 9~109". ~206 '~'+ 180, 117-119
- .206~+260 Mean 101 59 54 118 67 17 2003 Radiological Environmental Monitoring Report H-8 I I AopendixH
',TABLE H20 GROUND WATER TRITIUM ACTIVITIES (pCiII)
Location Indicator Control Period
'Pre-Op'
, Operational:
. Pre-Op.',. '.. Operational 1980-81 1982-02 2003
. 1980-81
', 1982-02 2003',
. Range'. -., 9~109". ~206 '~'+ 180, 117-119
- .206~+260 Mean 101 59 54 118 67 17 2003 Radiological Environmental Monitoring Report H-8
'f I
/'
I'
'J;,
APPENDIX I I\\....,.../"
I, J.;;
~ !.
'2003 Radiological Environmental Monitoring Report
'f I
/'
I'
'J;,
APPENDIX I I\\....,.../"
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'2003 Radiological Environmental Monitoring Report 1-1
APDendixl Results of analyses are generally reported in the following tables to two significant figures. Random uncertainties of counting are reported to the same decimal place as the result.
Calculated values for analysis results are reported with the random uncertainty of counting at two standard deviations (28), determined by considering both the sample and background count rates. The uncertainty of an activity is influenced by the volume or mass of the sample, the background count rate, the count times, the method used to round otT the value obtained to reflect its degree of significance, and other factors. The uncertainties of activities determined by gamma spectrometric analyses are also influenced by the relative concentrations of the radionuclides in the sample, the energies and intensities of the gammas emitted by those radionuclides, and the assumptions used in selecting the radionuclides to be quantitatively determined.
Results reported as less than <<) in these tables are below the minimum detectable concentrations (MDCs). The MDC is an estimate of the detection capabilities of the overall measurement method, taking into account not only the counting system, but also the characteristics of the sample being courited. When the MDC is used as the level to decide whether or not to enter a measured value into a table, there is a 50% chance that the value will be entered when the actual sample activity is equivalent to the MDC.
There is only a five percent chance that a value representing a fluctuation in background activity will be entered as sample activity in such an instance.
Measured values for the activities of specific radionuclides, such as the man-made gamma-emitting radionuclides beryllium-7 and cesium-137, only appear in the following tables for each specific medium when the levels that are measured exceed the MDC values for those measurements and those radionuclides are actually identified as present in the samples. Measured values for the analyses that are not radionuclide specific, such as gross alpha and beta analyses, also are presented in the tables for specific media only when the levels that are measured actually exceed the MDCs.
2003 Radiological Environmental Monitoring Report 1-2 I I APDendixl Results of analyses are generally reported in the following tables to two significant figures. Random uncertainties of counting are reported to the same decimal place as the result.
Calculated values for analysis results are reported with the random uncertainty of counting at two standard deviations (28), determined by considering both the sample and background count rates. The uncertainty of an activity is influenced by the volume or mass of the sample, the background count rate, the count times, the method used to round otT the value obtained to reflect its degree of significance, and other factors. The uncertainties of activities determined by gamma spectrometric analyses are also influenced by the relative concentrations of the radionuclides in the sample, the energies and intensities of the gammas emitted by those radionuclides, and the assumptions used in selecting the radionuclides to be quantitatively determined.
Results reported as less than <<) in these tables are below the minimum detectable concentrations (MDCs). The MDC is an estimate of the detection capabilities of the overall measurement method, taking into account not only the counting system, but also the characteristics of the sample being courited. When the MDC is used as the level to decide whether or not to enter a measured value into a table, there is a 50% chance that the value will be entered when the actual sample activity is equivalent to the MDC.
There is only a five percent chance that a value representing a fluctuation in background activity will be entered as sample activity in such an instance.
Measured values for the activities of specific radionuclides, such as the man-made gamma-emitting radionuclides beryllium-7 and cesium-137, only appear in the following tables for each specific medium when the levels that are measured exceed the MDC values for those measurements and those radionuclides are actually identified as present in the samples. Measured values for the analyses that are not radionuclide specific, such as gross alpha and beta analyses, also are presented in the tables for specific media only when the levels that are measured actually exceed the MDCs.
2003 Radiological Environmental Monitoring Report 1-2 I I
c TABLE 1-1 ENVIRONMENTAL TIIERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECfRIC STATION - 2003 :
Results (I) are in mRlstd. qtr (2) +/- 2S (3)
Flnt Quarter 01129103 to 05101/03 Second Quarter 04129/03 to 07124103 Third Quarter 07121103 to 10123103 Location ONSITE Fourth Quarter 10121103 to 01130104 c
1-3 c
(.
TABLE 1-1 ENVIRONMENTAL TIIERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECfRIC STATION - 2003 :
Results (I) are in mRlstd. qtr (2) +/- 2S (3)
Flnt Quarter 01129103 to 05101/03 Second Quarter 04129/03 to 07124103 Third Quarter 07121103 to 10123103 Location ONSITE IS2 23.6 +/- 1.4 24.3 +/- 1.9 23.6 +/- 1.2 2S2 17.5 +/- 1.8 15.8 +/- 1.3 20.5 +/- 0.8 2S3 20.4+/- 0.8 20.5 +/- 1.5 23.6 +/- 0.4 3S2 17.6 +/- 1.4 16.0 +/- 1.1 19.5 +/- 1.2 3S3 17.0 +/- 1.6 15.0 +/- 1.3 19.1 +/- 2.6 3S4 17.2 +/- 1.4 (4) 19.4 +/- 1.8 4S3 22.0 +/- 1.2 21.0 +/- 1.1 24.2 +/- 1.0 4S6" "..
j I,
17.8 +/- 1.6 16.9 +/- 1.3 20.8 +/- 1.2
.. --.... 5S4-.-.........
16.1"+/-*1.0 14.9 -+/- 1.3' "18.4 +/- 1.6' 5'Si'j 1iJf"+/- '1.8"-
16:6' +/- '1.1.
19.6"::1: '1.4 6S4';
23.8':;: '1.2';"
2~Lf*+/-2.1 27:9 +/-"1.2'*
6S9" 22.6'10.6*
23.2:;: '1.'1 r:
27:6 +/- 1.S" 7S6 22.9+/- '1.8" 23.3 +/- 1.3
,26.7 +/-1.2 7S7 1i.3+/-"1.0" 15.9'+/- '1.5 19.9:::1: 1.2 8S2' 22.9 ::I: 1.4 22.5 +/- 1.7.
27.4 +/- 3.0' 9S2 31.7 +/- 1.8 "
41.9 +/- 6.4 44.7 +/- 2.6 lOSt 17.1 '+/- '1.8 15.9 +/- 1.7 19.1 +/- 2.4 10S2 26.6 +/-1.2 29.2 +/- 1.1 33.3 +/- 2.4 10S3 16.3 +/-'O.6 15.1 +/- 1.3 18.6 +/- 1.4 I1S3 24.8 +/- 1.6 24.6 +/- 1.1 28.1 +/- 1.4 lis7 18.0 '+/- 1:2 16.9 '+/- 1.1 20.8 +/- 2.4 Fourth Quarter 10121103 to 01130104 26.5 +/- 2.1 17.9 +/- 1.1 23.2 +/- 2.3 18.4 +/- 1.5 18.1 +/- 0.9 18.3 ::I: 1.1 23.5 +/- 1.9 18.4 +/- 1.3
'17.2"+/- 0.9' 1s::f +/- '1.5:
26.,3' +/-' 0.9 25.i'+/- 0.8 '
25.S +/- 1.3 '
19:1 +/- 0.9 '
25.5 ::1:0.9 44.1 +/- 3.0 18.1 +/- 1.1 31.6 +/- 1.9 16.8+/- 0.9 27.4 +/- 0.9 20.1 +/- 1.3 c
1-3
ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 First Quarter 01129/03 to 05101/03 Results (1) arc in mRistd. qtr (2) +/- 2S (3)
Second Quarter 04/29/03 to 07124/03 Third Quarter 07122103 to 10123/03 Fourth Quarter 10121103 to 0]130/04 1-4 Location 12S1 12S3 1254 12S5 12S6 12S7 13S2 13S4 13S5 13S6 14S5 14S6 15S5 16S1 16S2 TABLE 1*1 ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 First Quarter 01129/03 to 05101/03 19.0 :l: 1.2 24.2 :l: 1.2 24.9 :l: 1.0 21.0 ':l: 0.6 21.4 :l: 1.0 16.S :l: 1.2 23.4 :l: 1.2 22.9 :l: 1.6 24.5 :l: 2.4 22.5 :l: 2.. 0 21.4 :l: 1.2 19.9 :l: 1.0 19.5 :I: 1.0 22.3 :l: 1.S 23.3 :I: 1.2 Results (1) arc in mRistd. qtr (2) +/- 2S (3)
Second Quarter 04/29/03 to 07124/03 17.4 :I: 1.1 22.8 :I: 1.5 23.0 :I: 2.1 20.3 :I: 1.3 19.9 ;/; 1.7 14.9 ;/; 0.9 21.7 ;/; 1.7 20.7 :I: 1.1 22.4 :I: 2.6 21.1 ;/; 1.3 20.6 ;/; 1.7 19.1 :I: 1.5 17.8 :I: 0.6 22.2 :I: 1.1 21.1 :I: 1.5 Third Quarter 07122103 to 10123/03 21.5 :I: 1.4 25.9 :I: 0.8 26.5 :I: 2.0 22.6 ;/; 1.6 23.6 :I: 1.4 17.7 ;/; 1.S 26.1 ;/; 1.4 25.9 :I: 1.6 27.1 ;/; 1.4 24.2 :I: 1.8 23.5 :I: 1.4 22.7 :I: 0.4 21.8 :I: 1.0 24.4 :I: 1.0 25.3 ;/; 1.4 See the comments at the end of this table.
Fourth Quarter 10121103 to 0]130/04 19.6 ;/; 1.3 24.3 :I: 1.7 24.9 ;/; 0.9 21.S ;/; 0.9 21.8 :I: 1.7 17.2 :I: 0.6 24.3 :I: O.S 22.S*:!: 0.6 25.4 ;/; 1.7 23.0 ;/; 1.5 21.2 ;/; 1.5 20.3 ;/; 1.5 21.2 :I: 4.5 23.S :I: 1.3 23.9 :I: 1.5 1-4
(
TABLE ENVIRONMENTAL Til ERMOLUMI NESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003
--t' '. ; I' First Quarter
- 01129/03 _ to_ 05101103 Location Results (l) are in mRlstd. qtr (2) +/- 2S (3)
Second Quarter 04129103 to. 07124/03 Third Quarter 07122/03
,to. 10123103, Fourth Quarter 10121103 to 01130104 1-5
(
TABLE I*!
ENVIRONMENTAL Til ERMOLUMI NESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003
--t' '. ; I' First Quarter
- 01129/03 _ to_ 05101103 Location 0-1 MILE OFFSITE 6A4.
20.7 :I: 1.6 8A3 17.5 :I: 0.8 15A3 '
18.9:1: 2.0
- ,16A2,,.
16.4 :I: 1.6 1-2 MILES OFFSITE lBI' 17.7 +/- 1.8 2B3 IS.9 :I: 0.8.
2B4 17.5':1: 0.2 5B3!
16.2::1: 1.4 7B2 :
17.3 ;:1:' 0.8 '
8B2 16.9 :I: '1.2" 9BI ~
16.7 :1:'0.6,
- 10B2 14.8 :I: 1.6 lOB3 17.5 :I: 1.2 10B4 '
18.0 :I: 1.6 12B4 18.3 :I: 1.0, 13Bl 18.4:1: 1.6 14B3 IS.7 :I: 1.8 15Bl 17.1 :1:*1.8 16B2:
16.1,*:1:*0.8 t*.*
. i 2-3 MILES OFFSITE Hel 21.2 :I: 1.6 See the comments at the end of this table.
Results (l) are in mRlstd. qtr (2) +/- 2S (3)
Second Quarter 04129103 to. 07124/03 18.7:1: 1.3 15.4 :I: 1.7 '
17.7 :I: 1.9 14.3 :I: 1.3 16.1 :1:1.1 16.6 :I: 0.9 '
16.4 :I: 0.9' 14.6 ::1:'1.1 "
15.7 :I: 0.9 15.1 :I: 1.1 15.6 :I: 1.3 12.7 :I: 1.3 15.2 :I: 0.4 18.0 :I: 1.5 17.0 :I: 1.5 16.4 :I: 1.5 16.4 :I: 1.5 16.0 :I: 1.1 15.4 :I: 1.9, 19.4 :I: 0.9 Third Quarter 07122/03
,to. 10123103, 22.7 :I: 1.2 19.2 :I: 1.6 '
20.9 :I: 1.4 18.6 :I: 1.2 21.3 :I: 1.4 20.S :I: 0.4 2f.4 +/- 1.8' 17.5 '+/- 1.2"
- 18.7'+/- 1.0 ;
18.1 ~:I: :1.4' 18.9:1: '1.6 16.7 :I: 0.8 19.2 :I: 1.0 20.4 :I: 1.0 20.1 :I: 1.0 19.1 :I: 1.6 19.9 :I: 1.0 18.9 :I: 1.4 19.2 :I: 0.4 22.4 :I: 1.0 Fourth Quarter 10121103 to 01130104 21.1 :I: 0.9 18.3 :I: 0.7 19.4 :I: 1.7 17.1 :I: 0.9 19.0 ':I: 1.1 18.8 :I: 0.6 19.1 :I: 1.1 16.5 :1:2.2 "
17.4";: cO:6 17.3 :1:'0.7' 17.8':1:"1.5 14.9 :I: 1.5 (4) 20.4 :I: 1.1 '
18.6 :I: 0.7 18.3 :1:,1.7' (4) 18.0 :I: 2.4 17.3:1: 0.7 21.7 :I: 0.7 1-5
Location 3-4 MILES OFFSITE 105 601 803 904 1001 1+02 1401 4-5 MILES OFFSITE 3EI 4E2 5E2 6El 7Et llEt 12El 13E4 5-10 MILES OFFSITE 2Fl 8F2 12F2 15Ft 16Fl TABLE ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECIRIC STATION - 2003 Flnt Quarter 01119/0J to OSlO 1103 19.9 :!: 0.8 18.9 :!: 1.4 18.6 :!: 1.2 18.4 :!: 1.6 18.5 :!: 1.2 21.2 :!: 1.8 19.9.:!: 1.2 15.7 :!: 0.6 19.2 :!: 1.6 18.0 :!: 1.4 20.5 :!: 2.2 18.7 :!: 2.0 16.0 :!: 0.8 17.4 :!: 1.8 20.5 :!: 1.6 17.0 +/- 1.6 17.4 +/- 0.8 19.1 :!: 1.2 19.1 :!: 1.2 20.8 +/- 0.6 Results (I) are in mR/std. qtr (2) +/- 2S (3)
Second Quarter 04119/03 to 07124/03 18.6 :!: 0.9 17.9 :!: 1.3 17.3 :!: 0.6 17.7 :!: 1.1 16.7 :!: 1.3 19.9 :!: 1.1 17.9 :!: 1.5 14.9 +/- 1.7 18.8 +/- 0.6 16.3' +/- 1.5 20.1 +/- 0.6 17.5 :!: 0.6 14.3 +/- 0.9 16.1 +/- 1.3 20.1 :!: 1.1 17.0 :!: 1.5 16.4 +/- 1.1 17.9 +/- 1.1 lS.7 :!: 1.3 19.8 +/- 1.5 Third Quarter 0711210J to 101lJ/03 22.5 :!: 0.0 21.3 :!: 1.2 19.1 :!: 0.8 20.4 :!: 2.6 19.9 :!: 1.2 22.0 :!: 2.4 20.7 :!: 2.4 18.6 :!: 1.5 21.7 +/- 1.4 20.9 +/- 2.0 21.6 :!: 1.0 20.5 +/- 1.0 17.4 +/- 1.0 IS.6 +/- 0.6 22.9 +/- 1.6 20.2 :!: 0.4 18.6 :!: 1.0 20.8 :!: 1.2 21.9 :!: ~.O 22.2 +/- 1.8 Sec the comments at the end of this table.
Fourtb Quarter 101ll/OJ to 01130104 20.3 :!: l.1 19.8 :!: '0.6 18.1 :!: 1.1 18.8 :!: 1.3 18.3 :!: 2.4 21.5 :!: 0.9 1.7 16.2 +/- 0.6
, 19.6 +/- 0.7 18.9 +/- 0.7 20.7 :!: 1.7 IS.9 :!: 1.3 16.1 :!: 0.7 17.8 :!: 1.1 22.3 :!: 1.1 18.4 +/- 1.7 17.5 :!: 0.7 20.4 :!: 0.7 20.9 +/- 1.7 20.9 :!: 1.9 1-6 1-1 Location 3-4 MILES OFFSITE 105 601 803 904 1001 1+02 1401 4-5 MILES OFFSITE 3EI 4E2 5E2 6El 7Et llEt 12El 13E4 5-10 MILES OFFSITE 2Fl 8F2 12F2 15Ft 16Fl TABLE 1*1 ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECIRIC STATION - 2003 Flnt Quarter 01119/0J to OSlO 1103 19.9 :!: 0.8 18.9 :!: 1.4 18.6 :!: 1.2 18.4 :!: 1.6 18.5 :!: 1.2 21.2 :!: 1.8 19.9.:!: 1.2 15.7 :!: 0.6 19.2 :!: 1.6 18.0 :!: 1.4 20.5 :!: 2.2 18.7 :!: 2.0 16.0 :!: 0.8 17.4 :!: 1.8 20.5 :!: 1.6 17.0 +/- 1.6 17.4 +/- 0.8 19.1 :!: 1.2 19.1 :!: 1.2 20.8 +/- 0.6 Results (I) are in mR/std. qtr (2) +/- 2S (3)
Second Quarter 04119/03 to 07124/03 18.6 :!: 0.9 17.9 :!: 1.3 17.3 :!: 0.6 17.7 :!: 1.1 16.7 :!: 1.3 19.9 :!: 1.1 17.9 :!: 1.5 14.9 +/- 1.7 18.8 +/- 0.6 16.3' +/- 1.5 20.1 +/- 0.6 17.5 :!: 0.6 14.3 +/- 0.9 16.1 +/- 1.3 20.1 :!: 1.1 17.0 :!: 1.5 16.4 +/- 1.1 17.9 +/- 1.1 lS.7 :!: 1.3 19.8 +/- 1.5 Third Quarter.
0711210J to 101lJ/03 22.5 :!: 0.0 21.3 :!: 1.2 19.1 :!: 0.8 20.4 :!: 2.6 19.9 :!: 1.2 22.0 :!: 2.4 20.7 :!: 2.4 18.6 :!: 1.5 21.7 +/- 1.4 20.9 +/- 2.0 21.6 :!: 1.0 20.5 +/- 1.0 17.4 +/- 1.0 IS.6 +/- 0.6 22.9 +/- 1.6 20.2 :!: 0.4 18.6 :!: 1.0 20.8 :!: 1.2 21.9 :!: ~.O 22.2 +/- 1.8 Sec the comments at the end of this table.
Fourtb Quarter 101ll/OJ to 01130104 20.3 :!: l.1 19.8 :!: '0.6 18.1 :!: 1.1 18.8 :!: 1.3 18.3 :!: 2.4 21.5 :!: 0.9 20.3*:!: 1.7 16.2 +/- 0.6
, 19.6 +/- 0.7 18.9 +/- 0.7 20.7 :!: 1.7 IS.9 :!: 1.3 16.1 :!: 0.7 17.8 :!: 1.1 22.3 :!: 1.1 18.4 +/- 1.7 17.5 :!: 0.7 20.4 :!: 0.7 20.9 +/- 1.7 20.9 :!: 1.9 1-6
c Location 1';,..
10-20 MILES 3G4-4Gl:
6Gl 7G1.
7Gi 8Gl 12GI 12G4 TABLEI-I I
ENVIRONMENTAL TIIERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 20031 Results (1) are in mRlstd. qtr (2) +/- 2S (3)
Fint Quarter 01129103 to 05/01103 Second Quarter 04129103 to 07124103 ThIrd Quarter 07122103 to 10113103 21.2 :f: 0.6 21.7 :f: 1.8 23.6 :f: 1.0 19.1 :f: 1.0 20.2 :f: 0.7 17.3 :f: 1.8 17.8 :f: 0.8 1.4 Fourth Quarter Ii; 10121103 to 01130/04 21.2 :f: 0.0 21.3 :f: 0.6 21.9 :f: 0.6 18.5 :f: 0.6 18.8 :f: 1.9 16.9 :f: 0.7 18.0 :f: 0.7 20.4 :f: 0.4 c
Location l
1';,..
10-20 MILES 3G4-4Gl:
6Gl 7G1.
7Gi 8Gl 12GI 12G4
('.
TABLEI-I I
ENVIRONMENTAL TIIERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 20031 Results (1) are in mRlstd. qtr (2) +/- 2S (3)
Fint Quarter 01129103 to 05/01103 19.9 :f: '1.2 20.0 :f: *1.4 19.5 :f: 2.0 17.L:f: 1.2 t:7.3~ +/-,1.0 15.9 :f: *1.0 17.2 :f: 2.0 20.3 :f: 1.4 Second Quarter 04129103 to 07124103 19.7 :f: 1.7 19.9 :f: 0.6.
20.2 :f: 1.7 16.5 :f: 0.9 16.9 :f: 0.4 14.1 :f: 1.1 15.2 :f: 1.1 17.8 +/-*0.9 ThIrd Quarter I 07122103 to 10113103 21.2 :f: 0.6 21.7 :f: 1.8 23.6 :f: 1.0 19.1 :f: 1.0 20.2 :f: 0.7 17.3 :f: 1.8 17.8 :f: 0.8 21.3*:f: 1.4
, : See the comments at the end ofthis table. U !
'I.,: ~
i'~ J',:1 !' !.:.~:
~ "..
Location
. : Indicator
,. 'Average (5)
- i9
- 6'+/-' 11.8
, t. ~ if
' ".:,~;
18.6 :f:' 12.9.
21.9 :f: 12.9
. Control
, Average (5) 18.4 :f: 4.1 17.5 :f:. 3.2 20.3 :f: 3.5 Fourth Quarter Ii; 10121103 to 01130/04 21.2 :f: 0.0 21.3 :f: 0.6 21.9 :f: 0.6 18.5 :f: 0.6 18.8 :f: 1.9 16.9 :f: 0.7 18.0 :f: 0.7 20.4 :f: 0.4 20.7 :f: 12.2 19.6 :f: 2.4 COMMENTS ".
I (I) Individual mtmitor loCation resitt~'~re nonnallythe average of the elementai:d~ses of six calcium elements from the two liDs assigned to each monitoring loCation. '.
~ f i
(2) A standard (std.) quarter (qtr.) is considered to be 91.25 days. Results obtained fOT monitoring periods of other durations ate nonnalized by mUltiplying them
. by 91.25/](, \\Vheie x is the actual dumtion in days ofthe period.
I (3) Uncertainties 'fori~diVidual fu6nfioring location results are two standard deviations of the elemental doses of silt calcium elements from the two TLOs assigned to each monitoring location; representing the variability between the elemental doses of each of the six TLO eleml:nts.
I (5) Uncertainties assoCiated with quarterly indicator and control avemgeS are two standard deviations, representing the variability between the results of
. - the individual monitoring locations.
1-7
TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE W~T~R SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pC~itcr +/- 2S LOCATION COLLECTION DATE TRITIUM GR-BETA OTHER ACTIVITY COMMENTS 6S6 12130/02 01127/03
<129 1.9 +/- 1.2 2S7 12130/02 01127/03 170+/- 87.3 15.9 +/- 2.9 6S5 01106/03 01/27/03
<126 3.2 +/- 1.4 LTAW' 01l2qJ03
<149 4.6 +/- 1.6 6S6 01127/03 03/03/03
<135
<2.01 2S7 01127103 03/03/03 4770+/- 177 8.3 +/- 2.4 685 03/03/03 1310 +/- 114 4.5 +/- 1.8 LTAWt 02118103 246+/-90.1 3.7 +/- 1.6 6S6 03/03/03 03/31103
<146 4.3 +/- 1.5 287 03/03/03 03/31103 16600 +/-307 9.9 +/- 2.2 685 03110/03 03/31103
< 149 3.2 +/- 1.4 LTAW 03117/03
<147 4.0 +/- 1.4 686 03/31103 04128/03
<134
<1.87 687 03/31103 04128/03 293 +/-91.7 7.2 +/- 2.1 685' 04/07/03 04/28/03
<123 2.6 +/- 1.4 LTAW 04/14/03 244 +/- 87.5 2.6 +/- 1.4 6S6 04/28/03 06/02103
<141
<1.76 287 04/28/03 06/02103 261 +/- 95.3 10.9 +/- 2.4 685 05/05/03 06/02103
<142 3.9.+/- 1.4 LTAW 05112/03 225 +/- 92.7 3.7 +/- 1.6 6S6 06/02103 06130/03
<134
<1.88 2S7 06/02103 06/30/03 3790 +/- 166 7.1 +/- 2.1 6SS 06/09/03 06/30/03
<140 3.1 +/- 1.4 LTAW 06/09/03 192 +/- 95.7 3.6 +/- 1.6 Comments:
- Rer~
j Appendix F of this report for additional details regarding except( to SSES Technical Requirements for sampling and analyses. C 1-8 TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE W~T~R SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pC~itcr +/- 2S LOCATION COLLECTION DATE TRITIUM GR-BETA OTHER ACTIVITY COMMENTS 6S6 12130/02 01127/03
<129 1.9 +/- 1.2 2S7 12130/02 01127/03 170+/- 87.3 15.9 +/- 2.9 6S5 01106/03 '
01/27/03
<126 3.2 +/- 1.4 LTAW' 01l2qJ03.
<149 4.6 +/- 1.6 6S6 01127/03 03/03/03
<135
<2.01 2S7 01127103 03/03/03 4770+/- 177 8.3 +/- 2.4 685 02103/03*
03/03/03 1310 +/- 114 4.5 +/- 1.8 LTAWt 02118103 246+/-90.1 3.7 +/- 1.6 6S6.
03/03/03 03/31103
<146 4.3 +/- 1.5 287 03/03/03 03/31103 16600 +/-307 9.9 +/- 2.2 685 03110/03 03/31103
< 149 3.2 +/- 1.4 LTAW 03117/03
<147 4.0 +/- 1.4 686 03/31103 04128/03
<134
<1.87 687,
03/31103 04128/03 293 +/-91.7 7.2 +/- 2.1 685' 04/07/03 04/28/03
<123 2.6 +/- 1.4 LTAW 04/14/03 244 +/- 87.5 2.6 +/- 1.4 6S6 04/28/03 06/02103
<141
<1.76 287 04/28/03 06/02103 261 +/- 95.3 10.9 +/- 2.4 685 05/05/03 06/02103
<142 3.9.+/- 1.4 LTAW 05112/03 225 +/- 92.7 3.7 +/- 1.6 6S6 06/02103 06130/03
<134
<1.88 2S7 06/02103 06/30/03 3790 +/- 166 7.1 +/- 2.1 6SS 06/09/03 06/30/03
<140 3.1 +/- 1.4 LTAW 06/09/03 192 +/- 95.7 3.6 +/- 1.6 Comments:
- Rer~
j Appendix F of this report for additional details regarding except( to SSES Technical Requirements for sampling and analyses. C 1-8
C-
~,
(
LOCATION 6S6 2S7 6SS LTAW 6S6 2S7 6SS
- LTAW, 6S6 2S7 6S5 6S6 2S7 6S5 LTAW 6S6 2S7 6S5 6S6 2S7 6S5 LTAW Comments:
TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELEcrRiC STATION - 2003 i Results in pCilliter +/- 2S COLLECTION DATE TRITIUM GR-BETA OTHER ACTIVITY 06130/03 07128103 3.0 +/- 1.5 06/30/03 07128103 11.8 +/- 2.5 07/07/03
. 07128103 2.8 +/- 1.5 07114/03
-'I J 2.8 +/- 1.3 07128/03 08125103
<132 4.2 +/- 1.6 07/28/03 9800 +/-257 11.8 +/-.2.S 08/04/03 08125103 4.2 +/- 1.6 081l 1/03 4.1,+/- 1.6 08/25/03 2.8 +/- 1.3 08125103
] 1.9 +/- 2.3 09/02103 3.8 +/- 1.4 09/08/03
'4.7 +/- 1.5 09129/03 11103/03
<122
~.2 +/- 1.4 11103/03' 09129/03
'~ 15800 +/- 268 13.7 +/- 2.6 10/06/03 11103/03
<114 4.2+/- 1.5 10/13/03 147+/-82.8 3.9 +/- 1.5 11103/03 12101103
<124 2.7 +/- 1.3 t tl03/03 12101103 231 +/- 89.3
] 1.8 +/- 2.4 11110/03 12101103
<123 3.1 +/- 1.3 11110/03 293 +/- 86.7 3.9 +/- 1.3 12101103 12129/03
<132 2.2 +/- 1.2 1210tl03 12129/03
<128 12.2 +/- 2.4 12108/03 12129103
<134 2.4 +/- 1.3 12115103
<120 3.3 +/- 1.4 COMMENTS "Refer to Appendix F of this report for additional details regarding exception~'to SSES TechnIcal Requlr~ments for sampling and analyses.
(
1-9 C-j
~,
~..:
(
LOCATION 6S6 2S7 6SS LTAW 6S6 2S7 6SS
- LTAW, 6S6 2S7 6S5 LTAW,'. I' 6S6 I;:
2S7 6S5 LTAW 6S6 2S7 6S5 LTAW*
6S6 2S7 6S5 LTAW Comments:
TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELEcrRiC STATION - 2003 i Results in pCilliter +/- 2S COLLECTION DATE '
TRITIUM GR-BETA OTHER ACTIVITY 06130/03 07128103
<146 3.0 +/- 1.5 06/30/03 07128103 182 +/-97.6 11.8 +/- 2.5 07/07/03
. 07128103
,: <150 2.8 +/- 1.5 07114/03
-'I J
' :. <129 2.8 +/- 1.3 07128/03 08125103
<132 4.2 +/- 1.6 07/28/03 08125103*
9800 +/-257 11.8 +/-.2.S 08/04/03 08125103
<128*
4.2 +/- 1.6 081l 1/03
- .! 'i 163 +/- 94.2 4.1,+/- 1.6
'. t' J.'"
1 08/25/03
' 09129103 '.!.': J 137 +/- 71.2 2.8 +/- 1.3 08125103
_ 09129/03
,,135 +/- 72.2
] 1.9 +/- 2.3 09/02103 ir,~ '09i2'9/03.,::,': 'J <:114 3.8 +/- 1.4
- I
- i _. ~ -
(,/,
09/08/03 213+/-94.2
'4.7 +/- 1.5
'" *. J.'
09129/03 11103/03
<122
~.2 +/- 1.4 11103/03' 09129/03
'~ 15800 +/- 268 13.7 +/- 2.6 10/06/03 11103/03
<114 4.2+/- 1.5 10/13/03 147+/-82.8 3.9 +/- 1.5 11103/03 12101103
<124 2.7 +/- 1.3 t tl03/03 12101103 231 +/- 89.3
] 1.8 +/- 2.4 11110/03 12101103
<123 3.1 +/- 1.3 11110/03 293 +/- 86.7 3.9 +/- 1.3 12101103 12129/03
<132 2.2 +/- 1.2 1210tl03 12129/03
<128 12.2 +/- 2.4 12108/03 12129103
<134 2.4 +/- 1.3 12115103
<120 3.3 +/- 1.4
. I COMMENTS "Refer to Appendix F of this report for additional details regarding exception~'to SSES TechnIcal Requlr~ments for sampling and analyses.
(
1-9
LOCATION COLLECTION DATE 6S6 12/30/02 - 01113/03 2S7 12130/02 - 01113/03 6S5 01106/03 & 01/13/03 6S6 01113/03 - 01127/03 2S7 01113/03 - 01127/03 6S5 01/20/03 & 01127/0J LTAW 1120/2003 6S6 01/27/03 - 02110103 2S7 01127/03 - 02110/03 6S5 02l0J/03 & 02110/03 LTAW 211812003 6S6 02110/03 - 02124/03 2S7 02110/03 - 02124/03 6S5 02118/03 & 02124/0J 6S6 02124/03 - 03/1 O/OJ 2S7 02124/03 - 03/10/03 6S5 03/0J/03. & 03/10/03 LTAW 3/17/2003 6S6 03/10/03 - 03/24/03 2S7 03/10103 - 03/24/03 6S5 03/17/03 & 03/24/03 6S6 03/24/03 - 04107103 6S7 03124/03 - 04107/03 04/07i03 LTAW 4/14/2003 Comments:
TABLE 1-3 IODlNE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter +/- 2S 1-131 COMMENTS
.01 :i:.15
.21 :i:.29
.24:i:.25
.33 :i:.31
.21 :i:.29
.25:i:.23
-.01 :i:.ll
.11 :i:.21 1.33:i:.58
.J9:i:.33
.1O:i:.12
.72:i:.30 1.61 :i:.46
.31 :i:.29
.64:i:.41 1.24:i:.53
.80:i:.39
<0.18
.16:i:.21
.77:i:.42
.30:i:.29
.05:i:.12
.52:i:.32
<0.43
.05:i:.15
- Re('1 Appendix F of this report for additional details regarding exceptr-to SSES Technical Requirements for sampling and analyses.
(
1-10 LOCATION COLLECTION DATE 6S6 12/30/02 - 01113/03 2S7 12130/02 - 01113/03 6S5 01106/03 & 01/13/03 6S6 01113/03 - 01127/03 2S7 01113/03 - 01127/03 6S5 01/20/03 & 01127/0J LTAW 1120/2003 6S6 01/27/03 - 02110103 2S7 01127/03 - 02110/03 6S5 02l0J/03 & 02110/03 LTAW 211812003 6S6 02110/03 - 02124/03 2S7 02110/03 - 02124/03 6S5 02118/03 & 02124/0J 6S6 02124/03 - 03/1 O/OJ 2S7 02124/03 - 03/10/03 6S5 03/0J/03. & 03/10/03 LTAW 3/17/2003 6S6 03/10/03 - 03/24/03 2S7 03/10103 - 03/24/03 6S5 03/17/03 & 03/24/03 6S6 03/24/03 - 04107103 6S7 03124/03 - 04107/03 6S5*
03/31/03*'& 04/07i03 LTAW 4/14/2003 Comments:
TABLE 1-3 IODlNE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter +/- 2S 1-131 COMMENTS
.01 :i:.15
.21 :i:.29
.24:i:.25
.33 :i:.31
.21 :i:.29
.25:i:.23
-.01 :i:.ll
.11 :i:.21 1.33:i:.58
.J9:i:.33
.1O:i:.12
.72:i:.30 1.61 :i:.46
.31 :i:.29
.64:i:.41 1.24:i:.53
.80:i:.39
<0.18
.16:i:.21
.77:i:.42
.30:i:.29
.05:i:.12
.52:i:.32
<0.43
.05:i:.15
. I
- Re('1 Appendix F of this report for additional details regarding exceptr-to SSES Technical Requirements for sampling and analyses.
(
1-10
LOCATION 6S6 2S7'"
6S5 6S6 2ST 6S5 LTAW
~.
6S6 2S7 6S6' 2S7:
6S5 6S6 6S7 6S5 LTAW 6S6 2S7' 6S5 6S6 2S7 6S5 LTAW Comments:
COLLECTION DATE 04/07/03 - 04/21103 04/07/03 - 04121103 '
04114/03 & 0412 1103.
04/21103 - 05105103 04/21103 - 05/05/03 04128103 & 05/05/03
, '511212003 05105103- 05119103 05/05/03 - 05119103 05112103 '&:05119/03 05/19/03'- 06/02103' 05/19103;. 06/02/03 05127/03 & 06/02103 06/02/03- 06/16103; 06/02/03 - 06/16/03 '
06/09/03 & 06/16/03 61912003',
06/16/03 - 06130103 :
06/16/03 '. 06130103 06123/03 &. 06/30/03 06/30/03 07/07/03 &,07114/03 711412003 TABLE 1-3 IODlNE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECfruC 2003 Results in pCilliter +/- 2S 1-131
.06:1:.17
.59:1:.36
.1 0:1:.21
.32:1:.32
.53 +/-,41.
.14:1:.20 O.OO:l:.t 1
.50:1:.39 1.19:1:.60
.06 :1:'.20
.61':1:.38" Un'+/-.50
.30:1:.24
.18 :1:.26 '
.48 +/-.38
.28+/-.28
.16:1:.25
.47:1:.36 Lt8 +/-.53
.15:1:.19
.39:1:.33
.91 :I:.50
.16:1:.23
.to+/-.22 COMMENTS "Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requlr~ments for sampling and analyses.
1-11 c
LOCATION 6S6 2S7'"
6S5 6S6 2ST 6S5 LTAW
~. :
6S6 2S7 6S5,',,',.,
6S6' 2S7:
6S5 6S6 6S7 6S5 LTAW 6S6 2S7' 6S5 6S6 2S7 6S5 LTAW Comments:
COLLECTION DATE 04/07/03 - 04/21103 04/07/03 - 04121103 '
04114/03 & 0412 1103.
04/21103 - 05105103 04/21103 - 05/05/03 04128103 & 05/05/03
, '511212003 05105103- 05119103 05/05/03 - 05119103 05112103 '&:05119/03 05/19/03'- 06/02103' 05/19103;. 06/02/03 05127/03 & 06/02103 06/02/03- 06/16103; 06/02/03 - 06/16/03 '
06/09/03 & 06/16/03 61912003',
06/16/03 - 06130103 :
06/16/03 '. 06130103 06123/03 &. 06/30/03 06/30/03 '*07/14/03 06/30/03*07114/03 07/07/03 &,07114/03 711412003
.C',)
TABLE 1-3 IODlNE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECfruC STATION* 2003 Results in pCilliter +/- 2S 1-131
.06:1:.17
.59:1:.36
.1 0:1:.21
.32:1:.32
.53 +/-,41.
.14:1:.20 O.OO:l:.t 1
.50:1:.39 1.19:1:.60
.06 :1:'.20
.61':1:.38" Un'+/-.50
.30:1:.24
.18 :1:.26 '
.48 +/-.38
.28+/-.28
.16:1:.25
.47:1:.36 Lt8 +/-.53
.15:1:.19
.39:1:.33
.91 :I:.50
.16:1:.23
.to+/-.22 COMMENTS
, i
, I "Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requlr~ments for sampling and analyses.
1-11
TABLE IODlN~131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter +/- 2S LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 07/14/03 - 07128103
.27+/-.26 2S7 1.15 +/-.51 6S5 07/21103 & 07/28/03
.9S+/-.52 6S6 07128103 - 08/11103
.19+/-.23 2S7 07/28/03 - 08111103
.40+/-.32 6S5 08/04/03 & 08/11103
.19 +/-.19 LTAW 8/1112003
.12 +/-.23 656 08/11103 - 08/25/03
.04 +/-.19 257 08111103 - 08/25/03
.63 +/-.38 655 08/18/03 & 08125103
.09+/-.23 656 08/25103 - 09/08/03
.26+/-.29 2S7 08/25/03 - 09/08/03 1.42+/-.62 6S5 09/02103 & 09/08/03
.24+/-.24 LTAW 91812003
<0.24 656 09/08103 - 09/21J03
.31 +/-.29 257 09/08/03 - 09/21J03
.13 +/-.25 655" 09/15/03 & 09/21J03
.07 +/-.lS 6S6 09/21J03 - 10/06/03
.15 +/-.25 2S7 09121J03 - 10/06103
<0.45 685 09/29/03 & 10/06103
.02+/-.l6 6S6 10/6/03 - J0/20/03
<0.34 257 JO/06/03 - JO/20/03
.05+/-.22 655 10113/03 & 10120/03
<0040 LTAW 10/13/2003
.19 +/-.27 comments:
- Retr t~ Appendix F of this report for additional details regarding exceptigpQ to SSES Technical Requirements for sampling and analyses.
~
L 1-12 TABLE 1*3 IODlN~131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter +/- 2S LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 07/14/03 - 07128103
.27+/-.26 2S7 07/14/03*07/28/03 1.15 +/-.51 6S5 07/21103 & 07/28/03
.9S+/-.52 6S6 07128103 - 08/11103
.19+/-.23 2S7 07/28/03 - 08111103
.40+/-.32 6S5 08/04/03 & 08/11103
.19 +/-.19 LTAW 8/1112003
.12 +/-.23 656 08/11103 - 08/25/03
.04 +/-.19 257 08111103 - 08/25/03
.63 +/-.38 655 08/18/03 & 08125103
.09+/-.23 656 08/25103 - 09/08/03
.26+/-.29 2S7 08/25/03 - 09/08/03 1.42+/-.62 6S5 09/02103 & 09/08/03
.24+/-.24 LTAW 91812003
<0.24 656 09/08103 - 09/21J03
.31 +/-.29 257 09/08/03 - 09/21J03
.13 +/-.25 655" 09/15/03 & 09/21J03
.07 +/-.lS 6S6 09/21J03 - 10/06/03
.15 +/-.25 2S7 09121J03 - 10/06103
<0.45 685 09/29/03 & 10/06103
.02+/-.l6 6S6 10/6/03 - J0/20/03
<0.34 257 JO/06/03 - JO/20/03
.05+/-.22 655 10113/03 & 10120/03
<0040 LTAW 10/13/2003
.19 +/-.27 comments:
- Retr t~ Appendix F of this report for additional details regarding exceptigpQ to SSES Technical Requirements for sampling and analyses.
~
L 1-12
LOCATION 6S6 2S7 6SS LTAW 6S6 2S7 6SS 6S6 2S7 6SS 6S6 2S7 6SS LTAW 6S6 2S7 6S5 Comments:
COLLECTION DATE 10/20/03 - 11103/03 10/20/03 - t 1103103 10127/03 & 11103/03 1111012003 11/03/03 - 11/17/03 11103103 - 11117/03 11110/03. & 11117103 1111'7/03 - 12101103 1111 7/03 - 12101103 11124/03\\ & 12101103 TABLE 1-3 IODINE-Ill ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003
.' Rcsuhs in pCilliter +/- 2S 1-131
.15 :!:.27 1.91 :!:.70
.26:!:.23
<OAI
.31 :!:.51
.68:!:.60
.24:!: 044
.14:!:.26
.23:!:.29
.01 :!:.IS COMMENTS
- 1'2101/03-12115/03
.21 :!:.50 1.02+/-.64.
.32:!: AS
.33:!: AS 12101103 - 12115/03 12108/03 & 12115/03 1211512003
. 12115/03 - 12129/03 12115103 - 12129/03 12122103 & 12129/03
.15:!: 046
.92:!:.78
.27:!:.45
"'Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses.
1-13 LOCATION 6S6 2S7 6SS LTAW 6S6 2S7 6SS 6S6 2S7 6SS t '/'
6S6 2S7 6SS LTAW 6S6 2S7 6S5 Comments:
COLLECTION DATE 10/20/03 - 11103/03 10/20/03 - t 1103103 10127/03 & 11103/03 1111012003 11/03/03 - 11/17/03 11103103 - 11117/03 11110/03. & 11117103
- 1111'7/03 - 12101103 '
1111 7/03 - 12101103.
" - 11124/03\\ & 12101103.
TABLE 1-3 IODINE-Ill ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003
.' Rcsuhs in pCilliter +/- 2S 1.
1-131
.15 :!:.27 1.91 :!:.70
.26:!:.23
<OAI
.31 :!:.51
.68:!:.60
.24:!: 044
.14:!:.26
.23:!:.29
.01 :!:.IS COMMENTS J: - 1'2101/03-12115/03
.21 :!:.50 1.02+/-.64.
.32:!: AS
.33:!: AS 12101103 - 12115/03 12108/03 & 12115/03 1211512003
. 12115/03 - 12129/03 12115103 - 12129/03 12122103 & 12129/03
.15:!: 046
.92:!:.78
.27:!:.45
"'Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses.
1-13
TABLE 1-4 GROSS ALPHA, GROSS BETA, TRITIUM, IODlNE-t31 GAMMA* SPECTROSCOPIC ANALYSES OF D.,.RINKING WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter ::I:: 2S LOCATION COLLECTION DATE GR-ALPIIA GR-BETA TRITIUM OTHER ACTIVITY COMMENTS 12H2 12/30/02 - 01127103
<1.24 1.86 +/-.9
<127 12H2 01/27/03 - 03/03/03
<1.62 2.7:i: 1.4
<135 12H2 03/03/03 - 03/31103
<1.30 2.19:i: 1.3
<142 12H2 04/07/03 - 04128103
<1.74
<1.87
<130 12H2 04/28/03 - 06/02103
<1.87
<1.90
<141 12H2 06/02/03 - 06/30/03
<1.53 2.04:i: 1.3
<134 12H2 06/30/03 - 07/28/03
<1.90
<2.01
<133 12H2 07/28/03 - 08/28/03
<1.06 3.54+/- 1.4
<146 12H2 08/25/03 - 09/29/03
<1.07 2.29:i: 1.3 193 +/-72 12H2 09/29/03 - 11103103
<1.78 4.26 +/- 1.4
<119 12H2 11103/03 - 12101103
<1.55
<1.57 149 :i: 76 12H2 12101103 - 12129/03
<1.68 2.01 +/- 1.2
<128 Comments:
- Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses.
1-14 TABLE 1-4 GROSS ALPHA, GROSS BETA, TRITIUM, IODlNE-t31 GAMMA* SPECTROSCOPIC ANALYSES OF D.,.RINKING WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiIliter ::I:: 2S LOCATION COLLECTION DATE GR-ALPIIA GR-BETA TRITIUM OTHER ACTIVITY j' COMMENTS 12H2 12/30/02 - 01127103
<1.24 1.86 +/-.9
<127 12H2 01/27/03 - 03/03/03
<1.62 2.7:i: 1.4
<135 12H2 03/03/03 - 03/31103.
<1.30 2.19:i: 1.3
<142 12H2 04/07/03 - 04128103
<1.74
<1.87
<130 12H2 04/28/03 - 06/02103
<1.87
<1.90
<141 12H2 06/02/03 - 06/30/03
<1.53 2.04:i: 1.3
<134 12H2 06/30/03 - 07/28/03
<1.90
<2.01
<133 12H2 07/28/03 - 08/28/03
<1.06 3.54+/- 1.4
<146 12H2 08/25/03 - 09/29/03
<1.07 2.29:i: 1.3 193 +/-72 12H2 09/29/03 - 11103103
<1.78 4.26 +/- 1.4
<119 12H2 11103/03 - 12101103
<1.55
<1.57 149 :i: 76 12H2 12101103 - 12129/03
<1.68 2.01 +/- 1.2
<128 Comments:
- Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses.
1-14
LOCATION IND IND IND 2H 2H 2H
,IND IND IND 2H 2H 2H
, LTAW TABLE 1-5 GROSS BETA AND GAMMA 1r SPECTROSCOPIC ANALYSES OF FISH SUSQUEHANNA STEAM ELECTRIC STATION - 2003 SAMPLE TYPE Smallmouth Bass Shorthead Redhorse Channel Catfish Smallmouth Bass Shorthead Redhorse Channel Catfish Channel Catfish Smallmouth Bass White Sucker, Channel Catfish Smallmouth Bass White Sucker L~rge~outh Bass Results in pCi/gm (wet) +/- 2S COLLECTION DATE 04/28/03 - 04128103 04/28/03 - 04/28/03 04/29/03 - 04/30/03 05/12/03 - 05112103 05/12103 - 05/12103 05112/03 - 05/13/03 10/07/03 - 10108/03 10/08/03 - 10/08/03 10/08/03 - 10/08/03 10115/03 - 10116/03 10116/03 - 10116/03 10116/03 - 10116/03 10/20/03 - 10/20/03 K-40 4.lS::!:.37
~.39::!:.43 3.89:1:.33 3.92:1:.28 3.20:1:.26 3.49:1:.25 3.69:1:.33 3.99:1:.37
'1.30::!:.14 3.44:1:.37 1.30::!:.24 3.58::!:.24 3.67::!:.30 -'
COMMENTS 1-15 LOCATION IND IND '
IND 2H 2H 2H
,IND IND IND 2H 2H 2H
, LTAW
)
(
TABLE 1-5 GROSS BETA AND GAMMA 1r SPECTROSCOPIC ANALYSES OF FISH SUSQUEHANNA STEAM ELECTRIC STATION - 2003 SAMPLE TYPE Smallmouth Bass Shorthead Redhorse Channel Catfish Smallmouth Bass Shorthead Redhorse Channel Catfish Channel Catfish Smallmouth Bass White Sucker, Channel Catfish Smallmouth Bass White Sucker
, L~rge~outh Bass Results in pCi/gm (wet) +/- 2S COLLECTION DATE 04/28/03 - 04128103 04/28/03 - 04/28/03 04/29/03 - 04/30/03 05/12/03 - 05112103 05/12103 - 05/12103 05112/03 - 05/13/03 10/07/03 - 10108/03 10/08/03 - 10/08/03 10/08/03 - 10/08/03 10115/03 - 10116/03 10116/03 - 10116/03 10116/03 - 10116/03 10/20/03 - 10/20/03 I' ;!
K-40 4.lS::!:.37
~.39::!:.43 3.89:1:.33 3.92:1:.28 3.20:1:.26 3.49:1:.25 3.69:1:.33 3.99:1:.37
'1.30::!:.14 3.44:1:.37 1.30::!:.24 3.58::!:.24 3.67::!:.30 -'
COMMENTS 1-15
TABLE 1-6 GAMMA
- SPECTROSCOPIC ANALYSES OF SHORELINE SEDIMENT SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-4O Cs-137 Ra-226 TH-228 OTHER ACTIVITY 2B 5/2012003 17.3 :!:.8
.11 :!:.03 2.45:!:.65 4.74:!:.67 7B 5/2012003 15.8:!:.5
.1O:!:.02 2.86+/-.59 3.56:!:.54 12F 5/20/2003 11.8 +/-.8
.09+/-.04 2.12+/-.85 3.34 +/-.82 LTAW 512012003 15.8:!:.8
<.03 1.96:!:.61 3.21 +/-.60 2B 10/27/2003 7.22+/-.24
.04 +/-.01
.75+/-.16 1.28:!:.18 7B 10127/2003 13.6:!:.5
.07:!:.02 2.36+/-.46 3.47:!:.43 12F 10/27/2003 lOA +/-.4
<.02 2.17+/-.40 2A6:!:.38 LTAW 10127/2003.
14.7:!: A
<.ot 2.18+/-.37 3.23 +/-.41 1-16 TABLE 1-6 GAMMA
- SPECTROSCOPIC ANALYSES OF SHORELINE SEDIMENT SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-4O Cs-137 Ra-226 TH-228 OTHER ACTIVITY 2B 5/2012003 17.3 :!:.8
.11 :!:.03 2.45:!:.65 4.74:!:.67 7B 5/2012003 15.8:!:.5
.1O:!:.02 2.86+/-.59 3.56:!:.54 12F 5/20/2003 11.8 +/-.8
.09+/-.04 2.12+/-.85 3.34 +/-.82 LTAW 512012003 15.8:!:.8
<.03 1.96:!:.61 3.21 +/-.60 2B 10/27/2003 7.22+/-.24
.04 +/-.01
.75+/-.16 1.28:!:.18 7B 10127/2003 13.6:!:.5
.07:!:.02 2.36+/-.46 3.47:!:.43 12F 10/27/2003 lOA +/-.4
<.02 2.17+/-.40 2A6:!:.38 LTAW 10127/2003.
14.7:!: A
<.ot 2.18+/-.37 3.23 +/-.41 1-16
LOCATION 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484 Treated
~
12F3 282 '
484 Treated 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484;Treated -
TABLEI-7 TRITIUM AND GAMMA
- SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECfRlC STATION - 2003 Results in pCiniter +/- 28 COLLECTION DATE TRITIUM OTHER ACTIVITY 1/2012003
<145 112012003
<149 1120/2003
<140 2118/2003
<135 2/18/2003
<137 2/18/2003 178 +/- 87.3 311712003
<143 311712003
<141 3/17/2003
<143 4/14/2003
<131 411412003 167 +/- 83.1 4114/2003 142+/-83.2
,<136 :
5/1212003 '
<136' 511212003
<137 6/9/2003 :~
<146 6/9/2003 '.
<145 6/9/2003
<146 711412003
<147 7114/2003.
<137 7/14/2003
<143 811112003
<138 8/1112003
<140 811112003
<139 1-17 LOCATION 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484 Treated i"t
~ ;..'
\\
12F3 282 '
484 Treated 12F3 282 484 Treated 12F3 282 484 Treated 12F3 282 484;Treated -
c TABLEI-7 TRITIUM AND GAMMA
- SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECfRlC STATION - 2003 Results in pCiniter +/- 28 COLLECTION DATE TRITIUM OTHER ACTIVITY 1/2012003
<145 112012003
<149 1120/2003
<140 2118/2003
<135 2/18/2003
<137 2/18/2003 178 +/- 87.3 311712003
<143 311712003
<141 3/17/2003
<143 4/14/2003
<131 411412003 167 +/- 83.1 4114/2003 142+/-83.2
., \\.
5/12i2003 '
,<136 :
5/1212003 '
<136' 511212003
<137 6/9/2003 :~
<146 6/9/2003 '.
<145 6/9/2003
<146 711412003
<147 7114/2003.
<137 7/14/2003
<143 811112003
<138 8/1112003
<140 811112003
<139
(
1-17
LOCATION 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated
(~
TABLE 1-7 TRITIUM AND SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiltitcr +/- 2S COLLECTION DATE TRITIUM OTHER ACTIVITY 9/8/2003
<139 91812003
<138 9/8/2003 193 +/- 89.6 101 13i2003
<125 10113/2003
<124 10/13/2003
<122 1111012003
<127 11110/2003
<122 11110/2003
<125 12/15/2003
<121 1211512003
<120 12115/2003
<126
(~
1-18 LOCATION 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated
(~
TABLE 1-7 TRITIUM AND GAMMA* SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCiltitcr +/- 2S COLLECTION DATE TRITIUM OTHER ACTIVITY 9/8/2003
<139 91812003
<138 9/8/2003 193 +/- 89.6
'. ~ "
101 13i2003
<125 10113/2003
<124 10/13/2003
<122 1111012003
<127 11110/2003
<122 11110/2003
<125 12/15/2003
<121 1211512003
<120 12115/2003
<126
(
(~
1-18
COLLECTION MONTH DATE 1'1"':
'6Gl Comments:
TABLE I~8 GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 2003:
Results in E-03 pCilCu. M. +/- 2S I
8Gl 3S2 12El 12S1 i
'13S6 COMMENTS to Appendix F of this report for additional details regarding exceptions to SSES Technical Requir~ments for sampling and analyses.
COLLECTION MONTH DATE 1'1"':
'6Gl JAN 112103 ~ 'tl8/03 "
12.8 +/- 2.2 118/03 - tl15/03 14.3 +/- 2.1 1IIS/03'~ i/22103 14 +/- 2.2 1122103 ',: 1129/03 14:1 +/-2.3
. I; FEB 1129/03 ~'21si03 13:8 :!: 2.3 ' :
215/03 - 2/12103 :'
14.8 '+/- 2.2 2/12/03 - 2119/03 9.9 +/- 2.0 2119/03 - 2126103 '"
12~6 +/- 2,3,
MAR 2126/03.; 3/5103.
14:5 '+/- 2.3 '
\\ : ',3/5/03 - 3/12103'"
2 1'.6 '+/- 2.7.
3112103 - 3/19/03 18.3 +/- 2.5 3/19/03\\.2 3/26/03' ~
100.4'+/- 2.1 3126/03.: 4/2103, ' '
9:5 '+/- 2.0:.'
APR" 412103 - 4/9/03.~ 1 7.6"+/- 1.9 "
4/9/03 - 4116/03 13.0 +/- 2.2 4/16/03:' 4/23/03 10.5' +/- 2.0 4123/03 - 4/30/03 :
11.3 +/- 2.0 MAY 4/30/03..: 517/03 9:4,.:!: 2.1 :
517/03 '.,; 5114i03 9.3: +/- 2~1 :
5/]4/03 - 5/21103 7.9 +/- 2.0 5/21103.: 5128/03 '
3.2 +/- I.S JUN 5128103 - 6/4ior 7.0' :!: 2.1 6/4/03 ;. 6/1 tl03 5.8 ':l: 2.2:
6/11103 - 6118/03 7.0 +/- 2.1
, 6/18/03,- 6125103
,10.5 +/- 2.1 6fi.S103 ~ 712103 16.9 +/- 2.6 Comments:
(
i
-, /'
' I TABLE I~8 GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 2003:
Results in E-03 pCilCu. M. +/- 2S I
8Gl 3S2 12El 12S1 i
'13S6 1l~1' +/- 2.3 14.6 +/- 2.8 13.6 +/- 2.5 1
' 13J +/-2.6 10.8 +/- 2.3 14.2 +/- 2.2 13.8 +/- 2.3 15.9 +/- 2.2 13.7 +/- 2.2 16.0 +/- 2.3 18.6.:l: 2.5 20.6 +/- 2.8 18.7 +/- 2.5 17:6 :!: 2.5 16.3 d:: 2.4 14.6:l: 2.3 17.3 +/- 2.6' 15.7 ~+/- 2.3 18.2 ':!: 2.5 17.1 +/- 2.4 16.2 +/- 2.4 15.7 +/- 2.3 15.2 +/- 2.4 16.7 :!: 2~6 15.2 :!: 2.3 16.2 :!: 2.4 17.8' ':!: 2.4 17.5 :!: 2.3 17.8 +/- 2.4 18.1 +/- 2.4 12.2 +/- 2.1 14.2 +/- 2.2 14.2 +/- 2.2 14.9 +/- 2.2 14.1 +/- 2.2 17.7 '+/- 2.5 19:2 +/- 2.3 16.0 +/- 2.4 14:9 :!: 2.4
- 16. I :!: 2.4 18.8 '+/- 2.6 19.7 +/- 2.6 17.9 +/- 2.5 18.1 +/- 2.5 19.5 +/- 2.6 19.4 '+/- 2.5 25.9' '+/- 2.8 18.2 +/- 2.5'
. i 18.6 +/- 2.5 23~6+/- 2.8 : I 17.8 +/- 2.4 17.6 :!: 2.4 17.9 +/-2.4 18.4 :!: 2.6 18.4 :!: 2.5 10'.5 :l: 2.0 "
12.6 +/- 2.S" 9:8 ' *+/-2.0' 11.8 ':+/- 2.2 ) 11:' +/- 2.1 '
If.!> '+/- 2.0' 10.5 -+/- 2.0 10.4 '+/- 2.0 10:7.. +/- 2.~ II 12.6+/- 2.1'"
i
,1 9:6 ':l: 2.0,:
9:5 +/- t() 1 10.0. +/- 2.0 9.9
- !: 2.1 i 9.6 +/- 2.0 15.9 +/- 2.3 14.3 +/- 2.1 14.7 :!: 2.2 12.7 :!: 2.1 14.3 :!: 2.2 13.6 +/- 2.1 IS.0+/- 2.3 12.8 +/- 2.1 14,3 +/- 2.2 13.3 +/- 2.1 14.7 '+/- 2.2 15.3 :!: 2.3 11.4 +/- 2.0 13.3 +/- 2.2 12.8 :l: 2.1 10.5 :!: '2.1 13.5+/- 2.4 10.5 +/- 2.2 11.1 :!: 2.3 I
11.2 +/- 2.2 7.3 +/-'1.9 11.2 +/- 2.2 8.9 +/- 2.0 9.3 +/- 2.1 7.5 '+/- 1.9 '
9.1 +/- 2.0 6.6 +/- 1.9 6.7
- !: 1.9 7.0
- !: 2.0 8.4 :!: 2.0 4.l+/- 1.5 4.9 +/- 1.7' 3.6 +/- I.S 5.2
- !: 1.7 4.9 +/- 1.6 8.5 +/- 2.3' 10.6 :l: 2.3 8.7 +/- 2.1 9.2
- l: 2.2 8.5 +/- 2.1' 10.5 +/- 2.2 10.0 :!: 2.1 7.1
- !: 1.8 8.5
- !: 2.0.,
7.9 +/- 1.9 9.4 +/- 2.1 12.5 :!: 2.2 9.3 +/- 2.0 11.0 +/- 2.2 !
10.3 +/- 2.0 11.4 +/-.2.2 9.7 +/- 2.1 10.6 :!: 2.1 10.4 :l: 2.1 11.7 +/- 2.2 23.5 +/- 3.0 17.3 +/- 2.6 18.1 +/- 2.8 21.9 +/- 2.8 21.9 +/- 2.8
~.... -.~.
I COMMENTS I
- Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requir~ments for sampling and analyses.
1*19
TABLE GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELEcrRIC 2003 Results in pCilCu. M. +/- 2S COLLECTION MONTH DATE 6Gl 8Gl 3S2 12El 12S1 13S6 COMMENTS Comments:
'Re(' '0 Appendix F of this report for additional details regarding to SSES Technical Requirements for sampling and analyses. '-
1-20 TABLE 1*8 GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELEcrRIC STATION* 2003 Results in E*03 pCilCu. M. +/- 2S COLLECTION I
MONTH DATE 6Gl 8Gl 3S2 12El 12S1 13S6 COMMENTS JUL 712103 -7/9/03 17.4 :+/- 2.6 17.7 :+/- 2.6 21.4 :+/- 2.7 20.8 :+/- 2.7 23.1 :+/- 2.9 20.4 :+/- 2.7 7/9103 -7116/03 9.2 +/-2.0 11.6 :+/- 2.1 11.5 :+/- 2.1 12.0 :+/- 2.1 10.1 :+/- 2.0.
10.4 :+/- 2.0 7/16103 -7123/03 13.3 :+/- 2.5 8.4 :+/- 2.0 12.0 :+/- 2.3 13.6 :+/- 2.4 12.1 :+/- 2.5 :
11.5 :+/- 2.3 7/23103 ~ 7/30/03 12.4 +/- 2.4.
12.1 :+/- 2.2 14.9 :+/- 2.4 14.5 :I: 2.4 14.9 :I: 2.5 13.5 :I: 2.4 AUG 7/30/03 - 8/6103 9.3
~ 2.1 8.9 :+/- 2.0 11.7 :+/- 2.2 9.4
- I: 2.1 12.4 :+/- 2.3 11.3 :+/- 2.2 8/6/03*8/13/03 10.8 :I: 2.3 H.8 :I: 2.3
. 12.4 :I: 2.3 13.2 :I: 2.3 11.2 :I: 2.6,
11.2 ;.I: 2.3 S/13/03 - 8/20/03 15.3 :I: 2.4 19.4 +/- 2.6 16.7 ;.I: 2.4 17.9 ;.I: 2.5 16.8 :I: 2.5 '
16.4 ;.I: 2.5 8120103 - 8127/03
. 19.9 +/- 2.7 20.7 +/- 2.8 22.8 :I: 2.8 21.9 ;.I: 2.7 20.4 +/- 2.9 '
20.4 ;.I: 2.8 8/27/03 - 9/3103 10.2 :+/- 2.1 11.4 :I: 2.2 11.9 +/- 2.1 10.9 :I: 2.1 10.7 +/- 2.1 11.7 +/- 2.2 SEP 9/3/03 - 9/10/03 13.4 +/- 2.2 12.6 :I: 2.2 12.8 :I: 2.1 13.5 :I: 2.2 15.2 :I: 2.3 13.4 ;.I: 2.2 9/10/03 - 9/17/03 J 1.9 +/- 2.20 J 1.0 :I: 2.1 15.4 :I: 2.2 U.S :I: 2. J 12.5 ;.I: 2.2.
13.2 ;.I: 2.2 9/17/03 - 9/24/03 16.7 +/- 2.8 16.7 +/- 2.7 13.2 +/- 2.5 17.4 :+/- 2.7 13.4 +/- 2.5 16.0 :I: 2.7 9/24/03 - 1011103 12.2 +/- 2.8 J 1.2 +/- 2.7 12.3 :+/- 2.7 13.3 :I: 2.7 12.9 :I: 2.7 13.2 +/- 2.8 ocr 10l1J03 - 10/8/03 13.3 +/- 2.4 12.0 +/- 2.2 12.1 :+/- 2.3 10.2 +/- 5.4 12.7 +/- 2.3 12.2 +/- 2.3 1018103 - 10115/03 30.9 :I: 3.6 31.0 +/- 3.5 30.2 +/- 3.4 29.9 +/- 3.3 31.7 :I: 3.5 26.6 ;.I: 3.3 10/15103 - 10122103 16.3 +/- 2.6 16.8 +/- 2.5 18.0 :I: 2.6 17.3 :I: 2.5 19.1 :I: 2.6 '
20.7 ;.I: 2.8 10122103
- 10/29/03 12.6 +/- 2.2 10.0 ;.I: 2.0 11.9 :1:2.1 14.6 :I: 2.5 14.5 +/- 2.2 14.3 ;.I: 2.3 NOV 10/29/03 - 1115103 21.1 +/- 2.8 23.3 +/- 2.8 30.0 +/- 3.'
24.6 :I: 2.8 22.0 :+/- 2.7.
24.1 :+/- 2.9 1115/03 - 11112103 10.7 :+/- 2.2 14.1 +/- 2.4 15.3 +/- 2.2 15.3 :I: 2.3 16.3 +/- 2.4 15.1 ;.1:2.4 11112103 - 11119/03 13.2 +/- 2.4 21.1 :I: 2.7 19.0 :I: 2.5 16.1
- I: 2.4 17.2 :I: 2.6 17.2 :I: 2.5 1 1119103 - 1 1/26/03 19.3 +/- 2.8 18.9 :I: 2.7 24.1 +/- 2.8 23.3 :I: 2.7 25.0 +/- 2.9 22.4 +/- 2.9 11126/03 ~ 1213/03 11.1 :I: 2.3 12.S +/- 2.3 13.4 :I: 2.5 14.3 +/- 2.3 12.8 :I: 2.3 12.8 :I: 2.4 DEC 1213/03 - 12110/03 10.1 :+/- 2.1 12.1 :I: 2.1 11.3 :I: 2.1 11.7 :+/- 2.0 12.4 ;.I: 2.1 10.1 :I: 2.0 12110/03* 12116/03 9.1
- +/- 2.3 9.0 +/- 2.1
)).0 +/- 2.3 9.3
- I: 2.1 9.5
- I: 2.3 '
9.5 +/- 2.2 12116/03:. 12123/03 13.7 '+/- 2.3 13.0 ':I: 2.2 13.5 ;.I: 2.3 13.6 :I: 2.2 14.9 :I: 2.3 15.8 :I: 2.4 12123103 - 12130/03 14.1 +/- 2.3 13.4 +/- 2.1 IS.5 :I: 2.5 16.8 :I: 2.3 16.9 :I: 2.3 !
18.3 :I: 2.4 Comments:
'Re(' '0 Appendix F of this report for additional details regarding exceptic* to SSES Technical Requirements for sampling and analyses. '-
1-20
LOCATION 601 Sal 3S2 12EI 12S1 13S6 601 SOl 3S2 12E1 12S1 1356 601 801 3S2 12El 12S1 13S6 601 SOl 3S2 12EI 12S1 13S6 TABLE GAMMA
- SPECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC 2003 Results in E-03 pCUCu. M. +/- 2S COLLECTION DATE OTHER ACTIVITY 01/02103 - 04/02103 91.1 +/-1O.3
<5.01 01102103 - 04102103 93.4+/- 7.03 '
<1.97 01102103 - 04102103 106+/- 8.29
<3.05 01102103.. 04;62103 109+/- 8.69
<1.78 01102103 - 04102103 106 +/- 7.54
<6.66 01102103 - 04;02103 99.1 +/- 7.15
<6.30 04/02103 - 07m03 74.7 +/- 9.41 4.16 +/- 2.31 04/02103 - 07 m03 88.5 +/-9.42
<1.78 04/02103 - 07 m03 86.6+/- 10.4
<3.40 04/02103. ~ '07'o/~3 91.4 +/- 8.50
<2.03 04/02103,- 0712103 83.2+/- 12.2'
<1.99 04/02103 - Oii2i03
'UI+/-11.l
<5.17 07/02103 ~ 10/01103 89.2+/- 8.23:
<2.81 07/02103 -10/01103 83.8 +/- 7.33
<7.31 07/02103 - 10/01103 101 +/- 2.47
<.794 07/02103 - 10101103 86.7+/-9.03
<3.27 07/02103 - 10/01103 97.7 +/- 8.28
<2.22 07/02103 - 10/01103 85.5 +/-9.95
<S.26 10/01103 - 12130/03 70.3 +/- 6.57'
<2.80 10/01103 -;12130/03 66.3+/-7.22
<7.83 10/01103 - 12130/03 69.3 +/- 5.85 '
<2.02 10/01103 - 12130/03 74.9 +/-7.l0
<2.60 10/01103 - 12130/03 76.5 +/-4.33
<1.38 10/01103 - 12130/03 67.0 +/-6.96
<1.60 c
LOCATION 601 Sal 3S2 12EI 12S1 13S6 601 SOl 3S2 12E1 12S1 '
1356 601 801 3S2 12El 12S1 13S6 601 SOl 3S2 12EI 12S1 13S6 TABLE 1*9 GAMMA
- SPECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION* 2003 Results in E-03 pCUCu. M. +/- 2S COLLECTION DATE Be*7 K*40 OTHER ACTIVITY 01/02103 - 04/02103 91.1 +/-1O.3
<5.01 01102103 - 04102103 93.4+/- 7.03 '
<1.97 01102103 - 04102103 106+/- 8.29
<3.05 01102103.. 04;62103 109+/- 8.69
<1.78 01102103 - 04102103 106 +/- 7.54
<6.66 01102103 - 04;02103 99.1 +/- 7.15
<6.30
~,:'
,',,'. t 04/02103 - 07m03 74.7 +/- 9.41 4.16 +/- 2.31 04/02103 - 07 m03 88.5 +/-9.42
<1.78 04/02103 - 07 m03 86.6+/- 10.4
<3.40 04/02103. ~ '07'o/~3 91.4 +/- 8.50
<2.03 04/02103,- 0712103 83.2+/- 12.2'
<1.99 04/02103 - Oii2i03
'UI+/-11.l
<5.17
- "fl.l
'*"t 07/02103 ~ 10/01103 89.2+/- 8.23:
<2.81 07/02103 -10/01103 83.8 +/- 7.33
<7.31 07/02103 - 10/01103 101 +/- 2.47
<.794 07/02103 - 10101103 86.7+/-9.03
<3.27 07/02103 - 10/01103 97.7 +/- 8.28
<2.22 07/02103 - 10/01103 85.5 +/-9.95
<S.26 I,';
10/01103 - 12130/03 70.3 +/- 6.57'
<2.80 10/01103 -;12130/03 66.3+/-7.22
<7.83 10/01103 - 12130/03 69.3 +/- 5.85 '
<2.02 10/01103 - 12130/03 74.9 +/-7.l0
<2.60 10/01103 - 12130/03 76.5 +/-4.33
<1.38 10/01103 - 12130/03 67.0 +/-6.96
<1.60 1*21
LOCATION 10Gl 1001 1002 12B2 10Gl 1001 1002 12B2 10G1 1001 1002 12B2 10Gl 1001 1002 12B2 10Gl 1001 1002 12B2 10GI 1001 1002 12B2 10Gl 1001 TABLE IODlN~131, AND GAMMA* SPECfROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECfRIC 2003 Results in pCiIliter +/- 2S COLLECTION DATE K-40 OTHER ACfIVITY 01107/03 1480+/- 120 01106/03 1470 +/- 120 01106/03 1410+/- 120 01106/03 1390 +/- 130 02103/03 IS20+/- 110 02103/03.
1540 +/- 130 02103/03 1280+/- 140 02l03i03 1400 +/- ISO 03/03/03 1390+/- 110 03/03/03 1330 +/- 130 03/03/03 1420 +/- 110 03/03/03 1400+/- 110 04/07/03 1530+/- 110 04/07/03 1360+/- 130 04/07103 1220 +/- 140 04/07/03 1330 +/- 150 04121/03 1480 +/- 110 04/21103 1350+/- 130 04/21103 1440+/- 160 04/21103 1360 +/- 150 05/05/03 1470+/- 110 05/0S/03 1430+/- 160 05105/03 13IO+/- 110 OS/05/03 1530 +/- 140 05119103 1470+/- 130 05/19/03 1460 +/- 110 COMMENTS 1-21 LOCATION 10Gl 1001 1002 12B2 10Gl 1001 1002 12B2 10G1 1001 1002 12B2 10Gl 1001 1002 12B2 10Gl 1001 1002 12B2 10GI 1001 1002 12B2
. 10Gl 1001 TABLE 1*10 IODlN~131, AND GAMMA* SPECfROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECfRIC STATION* 2003 Results in pCiIliter +/- 2S COLLECTION DATE K-40 OTHER ACfIVITY 01107/03 1480+/- 120 01106/03 1470 +/- 120 01106/03 1410+/- 120 01106/03 1390 +/- 130 02103/03 IS20+/- 110 02103/03.
1540 +/- 130 02103/03 1280+/- 140 02l03i03 1400 +/- ISO 03/03/03 1390+/- 110 03/03/03 1330 +/- 130 03/03/03 1420 +/- 110 03/03/03 1400+/- 110 04/07/03 1530+/- 110 04/07/03 1360+/- 130 04/07103 1220 +/- 140 04/07/03 1330 +/- 150 04121/03 1480 +/- 110 04/21103 1350+/- 130 04/21103 1440+/- 160 04/21103 1360 +/- 150 05/05/03 1470+/- 110 05/0S/03 1430+/- 160 05105/03 13IO+/- 110 OS/05/03 1530 +/- 140 05119103 1470+/- 130 05/19/03 1460 +/- 110
(.
COMMENTS 1-21
LOCATION 1002 1282 10GI lOot 1002 12B2 10Gl 1001 1002 12B2' 10Gl -
- 1001, 1002 12B2 10Gl 1001 1002 12B2 TABLE 1-10 IODINE-131, AND GAMMA"" SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECfRIC STATION - 2003 Results in pCilIiter +/- 2S COLLECTION DATE K-40 OTHER ACTIVITY 05/19/03 05/19/03 06/04/03 06/04/03 06/04103' 06/04/03, 06/J9/03 06/19/03" 06lt9/03' '
06/1'9/03'.:
n 07/06/03';
07/06/03 07/66103 :
0?~06/~3-!
07121103 07121103 07/21103, 07/21103 i
,I 1480+/- 110 1350+/- 110 1340+/- ltO 1390+/- 140 t190+/- 160 1390+/- 120 1400+/- 160 1460+/- 160 1400+/- 150 1350 d:: 150,~
~ ~
~
1350+/- 130 1340:!:: 130, J420+/- J 10,\\
1500+/- 1 ~O:,
1470:!:: 110 1340 +/- 150 1550+/- 160 IS20:!:: 170 COMMENTS 1-23 LOCATION 1002 1282 10GI lOot 1002 '
12B2 10Gl 1001 1002 12B2'
,,*i
'f'-/'
- 10Gl -
- 1001, 1002 12B2 10Gl 1001 1002 12B2
(,
TABLE 1-10 IODINE-131, AND GAMMA"" SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECfRIC STATION - 2003 Results in pCilIiter +/- 2S COLLECTION DATE K-40 OTHER ACTIVITY 05/19/03 05/19/03 06/04/03 06/04/03 "
06/04103' 06/04/03, 06/J9/03 06/19/03" 06lt9/03' '
06/1'9/03'.:
dq "
n
.. r'; ""'.
07/06/03';
07/06/03 07/66103 :
0?~06/~3-!
07121103 07121103 07/21103, 07/21103 i
,I 1480+/- 110 1350+/- 110 1340+/- ltO 1390+/- 140 t190+/- 160 1390+/- 120 1400+/- 160 1460+/- 160 1400+/- 150 1350 d:: 150,~
J
,,;. ~ ~
~,
1 :n -- ! II, 1350+/- 130 1340:!:: 130, J420+/- J 10,\\
1500+/- 1 ~O:,
1470:!:: 110 1340 +/- 150 1550+/- 160 IS20:!:: 170 i
I '
I.
COMMENTS 1-23
LOCATION lOG I 1001 1002 12B2 10Gl 1001 1002 12B2 10GI 100) 1002 12B2 10GI 1001 1002 12B2 1001 1001 1002 12B2 c
TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCilliter +/- 2S COLLECTION DATE K-4O OTHER ACTIVITY 08/04/03 1360:1: 180 08/04/03 1330:1: 110 08104103 1500:1: 120 08/04/03 1410:1: 170 08/18/03
)420:1: 160 08118103 1340:1: 150 08118/03 1410:1: 110 08118103 1330:1: 1'10 09/03/03 1484:1: 94 09/03/03 1380:1: 160 09/03/03 1380:1: 110 09/03/03 1471 :I: 95 09/18/03 1490 ~ 110 09/18/03 1410:1: 14Q 09/18/03 1390:1: 110 09118103 1370:1: 110 10/05103 1470:1: 110 10/05/03 1330:1: 130 10/05/03 1350:1: 150 10/05/03 1200:1: 150 COMMENTS 1-24 LOCATION lOG I 1001 1002 12B2 10Gl 1001 1002 12B2 10GI 100) 1002 12B2 10GI 1001 1002 12B2 1001 1001 1002 12B2 c
TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCilliter +/- 2S COLLECTION DATE K-4O OTHER ACTIVITY 08/04/03 1360:1: 180 08/04/03 1330:1: 110 08104103 1500:1: 120 08/04/03 1410:1: 170 08/18/03
)420:1: 160 08118103 1340:1: 150 08118/03 1410:1: 110 08118103 1330:1: 1'10 09/03/03 1484:1: 94 09/03/03 1380:1: 160 09/03/03 1380:1: 110 09/03/03 1471 :I: 95 09/18/03 1490 ~ 110 09/18/03 1410:1: 14Q 09/18/03 1390:1: 110 09118103 1370:1: 110 10/05103 1470:1: 110 10/05/03 1330:1: 130 10/05/03 1350:1: 150 10/05/03 1200:1: 150 COMMENTS 1-24
c:
LOCATION 10G1 1001 1002 12B2 10Gt 1001 1002 12B2 10Gl" 1001 1002 12B2 TABLE IODINE-t31, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK COLLECTION DATE 10120/03 10120/03 10120/03 10120/03 11103/03 11103/03 11103/03 11103/03 12108/03 12108/03 12108/03 12108/03 SUSQUEHANNA STEAM ELECTRIC STATION - 2003 K-40 1420:1: 120 1450:1: 140 1380:1: 160 1250:1: 150 1350:1: 110 1550:1: 160 1360:1: 150 1380:1: 150 819:1: 86 1361 :1:58 1452:1: 62 940:1: 94 Results in pCiIliter +/- 2S OTHER ACTIVITY COMMENTS c:
LOCATION 10G1 1001 1002 12B2 10Gt 1001 1002 12B2 10Gl" 1001 1002 12B2
. I,'
TABLE I*tO IODINE-t31, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK COLLECTION DATE 10120/03 10120/03 10120/03 10120/03 11103/03 11103/03 11103/03 11103/03 12108/03 12108/03 "
12108/03 12108/03 SUSQUEHANNA STEAM ELECTRIC STATION - 2003 K-40 1420:1: 120 1450:1: 140 1380:1: 160 1250:1: 150 1350:1: 110 1550:1: 160 1360:1: 150 1380:1: 150 819:1: 86 1361 :1:58 1452:1: 62 940:1: 94 Results in pCiIliter +/- 2S 1
t y
~
I I OTHER ACTIVITY
"[
I,
i I" COMMENTS 1*25
TABLE 1-11 GAMMA
- SPECTROSCOPIC ANALYSES OF SOIL SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-40 Cs-137 Th-228 801 TOP 9115/2003 11.0 +/- 1.1 0.17 +/-.OS 0.90 +/-.14 801 BOT 9/15/2003 10.2+/- 1.1 0.097+/-.053 0.73 +/-.13 3S2TOP 9/1512003 14.7 +/- 1.1 0.030+/-.035
. 1.04 +/-.13 3S2BOT 9/15/2003 16.2 +/- 1.2 0.049+/-.039 1.00+/-.13 12S1 TOP 9/15/2003 10.3 +/- 1.0 0.096+/-.047 0.82+/-.12 12S1 BOT 9/1512003 12.5 +/-0.8 0.076+/-.029
. 0.84 :I:.85 13S6TOP 9/15/2003 18.2:1: 0.9
<0.042 1.04+/-.95 13S6 BOT 9/15/2003 14.3 +/- 1.0 0.027 :I:.024 0.95:1:.11
(~
c 1-26 TABLE 1-11 GAMMA
- SPECTROSCOPIC ANALYSES OF SOIL SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-40 Cs-137 Th-228 801 TOP 9115/2003 11.0 +/- 1.1 0.17 +/-.OS 0.90 +/-.14 801 BOT 9/15/2003 10.2+/- 1.1 0.097+/-.053 0.73 +/-.13 3S2TOP 9/1512003 14.7 +/- 1.1 0.030+/-.035
. 1.04 +/-.13 3S2BOT 9/15/2003 16.2 +/- 1.2 0.049+/-.039 1.00+/-.13 12S1 TOP 9/15/2003 10.3 +/- 1.0 0.096+/-.047 0.82+/-.12 12S1 BOT 9/1512003 12.5 +/-0.8 0.076+/-.029
. 0.84 :I:.85 13S6TOP 9/15/2003 18.2:1: 0.9
<0.042 1.04+/-.95 13S6 BOT 9/15/2003 14.3 +/- 1.0 0.027 :I:.024 0.95:1:.11
(~
c 1-26
TABLE 1-11 GAMMA
- SPECTROSCOPIC ANALYSES OF SOIL SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-40 Cs-137 Th-228 801 TOP 9115/2003 11.0 +/- 1.1 0.17 +/-.OS 0.90 +/-.14 801 BOT 9/15/2003 10.2+/- 1.1 0.097+/-.053 0.73 +/-.13 3S2TOP 9/1512003 14.7 +/- 1.1 0.030+/-.035
. 1.04 +/-.13 3S2BOT 9/15/2003 16.2 +/- 1.2 0.049+/-.039 1.00+/-.13 12S1 TOP 9/15/2003 10.3 +/- 1.0 0.096+/-.047 0.82+/-.12 12S1 BOT 9/1512003 12.5 +/-0.8 0.076+/-.029
. 0.84 :I:.85 13S6TOP 9/15/2003 18.2:1: 0.9
<0.042 1.04+/-.95 13S6 BOT 9/15/2003 14.3 +/- 1.0 0.027 :I:.024 0.95:1:.11
(~
c 1-26 TABLE 1-11 GAMMA
- SPECTROSCOPIC ANALYSES OF SOIL SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-40 Cs-137 Th-228 801 TOP 9115/2003 11.0 +/- 1.1 0.17 +/-.OS 0.90 +/-.14 801 BOT 9/15/2003 10.2+/- 1.1 0.097+/-.053 0.73 +/-.13 3S2TOP 9/1512003 14.7 +/- 1.1 0.030+/-.035
. 1.04 +/-.13 3S2BOT 9/15/2003 16.2 +/- 1.2 0.049+/-.039 1.00+/-.13 12S1 TOP 9/15/2003 10.3 +/- 1.0 0.096+/-.047 0.82+/-.12 12S1 BOT 9/1512003 12.5 +/-0.8 0.076+/-.029
. 0.84 :I:.85 13S6TOP 9/15/2003 18.2:1: 0.9
<0.042 1.04+/-.95 13S6 BOT 9/15/2003 14.3 +/- 1.0 0.027 :I:.024 0.95:1:.11
(~
c 1-26
c TA~r;I-ll GAMMA
- SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS AND VEGETABLES)
SUSQUEHANNA STEAM ELECTRIC 2003' Results in pCi/gm (wet) +/- 2S LOCATION SAMPLE TYPE COLLECTION DATE K-40 OTHER ACTIVITY Potato 08/21103 4.66:1:.19 1IF2 Potato 09/04/03 4.47:1:.29 Comments:
- Refer to ~ppendix F of this report for, additional details regarding exceptions to SSES TechnlcCi' Requirements for. sampling and analyses.
(
1-27 c
TA~r;I-ll GAMMA
- SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS AND VEGETABLES)
SUSQUEHANNA STEAM ELECTRIC STATION* 2003' Results in pCi/gm (wet) +/- 2S
- .i LOCATION SAMPLE TYPE COLLECTION DATE K-40 OTHER ACTIVITY Potato 08/21103 4.66
- 1:.19 1IF2 Potato 09/04/03 4.47:1:.29 I: *
-:{.
Comments:
- Refer to ~ppendix F of this report for, additional details regarding exceptions to SSES TechnlcCi' Requirements for. sampling and analyses.
(
1-27
TABLE 1-)3 TYPICAL" MINIMUM DETECTABLE CONCENTRATIONS OF NUCLIDES SEARCHED FOR BUT NOT FOUND BY G¥lMA SPECTROMETRY IN TIlE VICINITY OF SUSQUEHANNA STEAM ELECTRIC STATION, 2003 Fish Sediment Surface Water Ground Water Potable Water Nuclide (pCilg wet)
(pCilg dry)
(pC ill)
(pCiJI)
(pCill)
Mn-54 0.019 0.028 2.9 4.1 1.7 Co-58 0.023 0.035 2.1 4.6 1.8 Fe-59 0.050 0.110 5.1 10.2 8.3 Co-60 0.015 0.028 3.3 5.3 2.5 Zo-65 0.028 0.071 7.8 14.4 6.7 Zr-95 0.020 0.070 6.4 7.8 5.4 Nb-95 N/A N/A 4.3 5.8 3.2 Ru-103 N/A N/A 4.9 5.3 2.6 1-131 0.100 0.173 15.4 8.1 13.2 Cs-134 0.010 0.032 2.3 5.2 2.6 Cs-137 0.015 0.033 2.4 4.S 2.5 Ba-140 0.300 0.310 7.8 9.0 9.2 La-I40 0.040 0.100 12.1 10.1 10.2 Ce-141 N/A N/A 6.8 7.8 6.8 Air Particulate Milk Fruit/Veg.
Soil Nuclide (10-3 pCilm3)
(pCiJI)
(pCilg wet)
(pCilg dry)
Mn-54 0.33 5.5 0.008 0.037 Co-58 0.51 5.1 0.008 0.039 Fc-59 2.31 12.4 0.032 0.993 Co-60 0.28 5.7 0.009 0.055 Zo-65 0.75 13.4 0.025 0.176 Zr-95 0.88 7.7 0.016 0.995 Nb-95 N/A 6.1 N/A 0.071 Ru-I03 N/A 5.2 N/A 0.051 1-131 70.3 8.2 0.019 0.097 Cs-134 0.27 4.8 0.007 0.057 Cs-137 0.29 4.4 O.OOS 0.047 36.2 6.7 0.055 0.255 La-I 40 11.5 7.8 0.016 0.11 Ce-141 N/A 8.1 N/A 0.078
(-'.
1-28 TABLE 1-)3 TYPICAL" MINIMUM DETECTABLE CONCENTRATIONS OF NUCLIDES SEARCHED FOR BUT NOT FOUND BY G¥lMA SPECTROMETRY IN TIlE VICINITY OF SUSQUEHANNA STEAM ELECTRIC STATION, 2003 Fish Sediment Surface Water Ground Water Potable Water Nuclide (pCilg wet)
(pCilg dry)
(pC ill)
(pCiJI)
(pCill)
Mn-54 0.019 0.028 2.9 4.1 1.7 Co-58 0.023 0.035 2.1 4.6 1.8 Fe-59 0.050 0.110 5.1 10.2 8.3 Co-60 0.015 0.028 3.3 5.3 2.5 Zo-65 0.028 0.071 7.8 14.4 6.7 Zr-95 0.020 0.070 6.4 7.8 5.4 Nb-95 N/A N/A 4.3 5.8 3.2 Ru-103 N/A N/A 4.9 5.3 2.6 1-131 0.100 0.173 15.4 8.1 13.2 Cs-134 0.010 0.032 2.3 5.2 2.6 Cs-137 0.015 0.033 2.4 4.S 2.5 Ba-140 0.300 0.310 7.8 9.0 9.2 La-I40 0.040 0.100 12.1 10.1 10.2 Ce-141 N/A N/A 6.8 7.8 6.8 Air Particulate Milk Fruit/Veg.
Soil Nuclide (10-3 pCilm3)
(pCiJI)
(pCilg wet)
(pCilg dry)
Mn-54 0.33 5.5 0.008 0.037 Co-58 0.51 5.1 0.008 0.039 Fc-59 2.31 12.4 0.032 0.993 Co-60 0.28 5.7 0.009 0.055 Zo-65 0.75 13.4 0.025 0.176 Zr-95 0.88 7.7 0.016 0.995 Nb-95 N/A 6.1 N/A 0.071 Ru-I03 N/A 5.2 N/A 0.051 1-131 70.3 8.2 0.019 0.097 Cs-134 0.27 4.8 0.007 0.057 Cs-137 0.29 4.4 O.OOS 0.047 Ba-140*
36.2 6.7 0.055 0.255 La-I 40 11.5 7.8 0.016 0.11 Ce-141 N/A 8.1 N/A 0.078
(-'.
1-28
APPENDIX>J 2003 Radiological Environmental Monitoring Report"
, J-l
-,.-. )'
I;' (".
APPENDIX>J 2003 Radiological Environmental Monitoring Report"
, J-l
I I AppendixJ The data in the tables that follow show how wen Framatome ANP Environmental Laboratory and Teledyne Brown Engineering Environmental Services (TBE) performed in the analysis of
"~J
. radioactively spiked media. Tables through provide the performance results for.
Framatome ANP. Tables 1-6 through 1-10 provide the performance results for TBE. In addition to the Analytics' spikes analyzed as part ofPPL's REMP Laboratory Spike Program (Tables 1-3 and 1-8), Framatome ANP and TBE analyzed spikes procured independently from Analytics as part of their respective Quality Control Spike Programs (Tables 1-2 and 1-7), as well as spikes prepared as part of the following programs:
- 1. The Proficiency Testing Program of Environmental Resource Associates (Tables I-I and 1-6)
- 2. The Quality Assessment Program ofDDE's Environmental Measurements Laboratory (EML)
(Tables 1-4 and 1-9)
-.. '~'fiie Mixed Analyte-Performance Evaliiation Pfogmm:-(MAPEPr of the DOE (Tables-J.;.5 and-',_.
1-10)
It should be noted that program #1 above oilly provides spiked water for analyses. No other media are included in the spikes provided by this program. Also, it should be noted that the levels of activity in spikes of different media prepared for program #2 tend to be relatively high.
They are relatively high compared to the levels of activity in the spikes prepared by Analytics as part of its EnvironmentarCross Check Prognim and for PPL's REMP Laboratory Spike Program.
The following characteristics are impo~t for the spiked enviro~ental media:
- 1. When practical, the level of activity in, at least,' some of the spiked environmental media should be within the range between required analysis sensitivities for the SSES REMP and the Reporting Levels, if applicable, o~ the NRC.
- 2. The spikes should be preserved in a manner as similar as possible to the way that actual samples of those media are prepared.
- 3. The variety of radio nuclides with which environmental media are spiked should be as extensive as practical, including as many as of the activation and fission products that could be detected in the vicinity of the SSES as reasonable.
The spiked environmental media prepared by Analytics according to the requirements ofPPL's REMP Laboratory Spike Program are intended to incorporate characteristics # 1, #2, and #3 to the greatest degree that is practical.
2003 Radiological Environmental Monitoring Report I I AppendixJ The data in the tables that follow show how wen Framatome ANP Environmental Laboratory and Teledyne Brown Engineering Environmental Services (TBE) performed in the analysis of
"~J
. radioactively spiked media. Tables J*l through 1*5 provide the performance results for.
Framatome ANP. Tables 1-6 through 1-10 provide the performance results for TBE. In addition to the Analytics' spikes analyzed as part ofPPL's REMP Laboratory Spike Program (Tables 1-3 and 1-8), Framatome ANP and TBE analyzed spikes procured independently from Analytics as part of their respective Quality Control Spike Programs (Tables 1-2 and 1-7), as well as spikes prepared as part of the following programs:
- 1. The Proficiency Testing Program of Environmental Resource Associates (Tables I-I and 1-6)
- 2. The Quality Assessment Program ofDDE's Environmental Measurements Laboratory (EML)
(Tables 1-4 and 1-9)
-.. '~'fiie Mixed Analyte-Performance Evaliiation Pfogmm:-(MAPEPr of the DOE (Tables-J.;.5 and-',_.
1-10)
It should be noted that program #1 above oilly provides spiked water for analyses. No other media are included in the spikes provided by this program. Also, it should be noted that the levels of activity in spikes of different media prepared for program #2 tend to be relatively high.
They are relatively high compared to the levels of activity in the spikes prepared by Analytics as part of its EnvironmentarCross Check Prognim and for PPL's REMP Laboratory Spike Program.
The following characteristics are impo~t for the spiked enviro~ental media:
- 1. When practical, the level of activity in, at least,' some of the spiked environmental media should be within the range between required analysis sensitivities for the SSES REMP and the Reporting Levels, if applicable, o~ the NRC.
- 2. The spikes should be preserved in a manner as similar as possible to the way that actual samples of those media are prepared.
- 3. The variety of radio nuclides with which environmental media are spiked should be as extensive as practical, including as many as of the activation and fission products that could be detected in the vicinity of the SSES as reasonable.
The spiked environmental media prepared by Analytics according to the requirements ofPPL's REMP Laboratory Spike Program are intended to incorporate characteristics # 1, #2, and #3 to the greatest degree that is practical.
2003 Radiological Environmental Monitoring Report
Appendix!
\\.../
The criteria for the acceptability of the analyses results for the spikes prepared as part of the PPL REMP Laboratory Spike Program (Tables 1-3 & 1-8) have been established by PPL. They are based on criteria that were originally developed by the NRC. The NRC bases these criteria on an empirical relationship that combines prior experience and accuracy needs. As the resolution of the measurement process improves (relative measurement uncertainty becomes smaller), the criteria for detennining acceptability become tighter. Conversely, as the resolution of the process qecomes poorer (relative measurement uncertainty becomes bigger), the criteria are widened.
The criteria for acceptability of DOE programs (EML's and MAPEP's programs - Tables 1-4, 1-5,1-9 and 1-10) are based on control limits based on percentiles of historic data distributions.
Note that comment numbers at the extreme right side of the tables denote unacceptable results in Tables I-I through 1-10. Discussions relevant to these comment numbers follow the presentations of the-data;-as -applicable.
~~------- ---------~~---
Radionuclide concentration results not available (due to loss of spectrum by Analytics) and therefore not included in Tables 1-3 and I-S for the following:
Analytics Sample Numbers: E39S0-1S6 and E3976-1S6 (spiked milk).
J-3 2003 Radiological Environmental Monitoring Report Appendix!
\\.../
The criteria for the acceptability of the analyses results for the spikes prepared as part of the PPL REMP Laboratory Spike Program (Tables 1-3 & 1-8) have been established by PPL. They are based on criteria that were originally developed by the NRC. The NRC bases these criteria on an empirical relationship that combines prior experience and accuracy needs. As the resolution of the measurement process improves (relative measurement uncertainty becomes smaller), the criteria for detennining acceptability become tighter. Conversely, as the resolution of the process qecomes poorer (relative measurement uncertainty becomes bigger), the criteria are widened.
The criteria for acceptability of DOE programs (EML's and MAPEP's programs - Tables 1-4, 1-5,1-9 and 1-10) are based on control limits based on percentiles of historic data distributions.
Note that comment numbers at the extreme right side of the tables denote unacceptable results in Tables I-I through 1-10. Discussions relevant to these comment numbers follow the presentations of the-data;-as -applicable.
~~------- ---------~~---
Radionuclide concentration results not available (due to loss of spectrum by Analytics) and therefore not included in Tables 1-3 and I-S for the following:
Analytics Sample Numbers: E39S0-1S6 and E3976-1S6 (spiked milk).
J-3 2003 Radiological Environmental Monitoring Report
Identlncatlon No.
Rad-52 Rad-S3 Rad-54 MedIum Water Water Water Water, "
Untl'l pCiII pCiII pCiII pCiII pCtII pCiII pCiII pCtII pCiII pCtII pCtII pCiII pCtII pCtII pCiII pCtII
, pCiII
. pCtII'
- pC-t11.
pCiII pC:t11 pCiII pCtII pCiII TA(~J-1 I
ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) I PROFICIENCY TESTING PROGRAM - 2003 I
FRAMATOME ANP ENVIRONMENTAL SERVICES LABORATORY (page 1 of2)
NuclIde Gross Alpha Gross Deta Sr-90 Ba-133 Co-6O Cs-134 Zn-65 Nat. Uranium H-3 Gross Alpha Gross Beta 5r-9O Da-133
,,co-6O Zn-65..
Nat. Uranium Triiium ERA Known Resu1t(a) 37.6 8.55 15.9 9.03 19.5 37.4 17.8 44.2 60.3 53.7 1250.0 20.8 65.1 31.6 58.8 20.6 20.7 37.4.
32.6
.44.3 60.2 11.4 28.2 "
14300 Framatome Resull'l (a) 28 8.97 13 8.74 17.9 36.6 17.9 45.4 60 56 1080.0 21.4 70.4 31.9 5S.S 18.7
, 19.9
- 37.4..
31.0 47.0 61.3 1I.S 28':.
14800 FramatomtlERA Ratio 0.74 I.OS 0.82 0.97 0.92 0.98 1.01 l.oJ 1.00 1.04 0.86 t.03 1.08 1.01 0.94 0.91
" 0.96 1.00 0.95
., 'co t.()6 1.02 1.01 0.99 1.03 ERA Control LimIts (b) 1.3-53.9 0.00-17.2 7.24-24.6 0.37-17.7 1'0.S-28.2 28.7-46.1 9.14-26.5 1 35.5-52.9 49.9-70.7 44.4-63.0 I
678-1820 I 15.6-26.0 I
36.9-93.3 22.9-40.3 50.1-67.5 1'1.9.29.3 12.0-29.4',
28.7-46.1 23.9-41.3 35.6-53.0.
49.8.70.6
~20-16.6 10-33.4' 11800-16800 I
(a) Results are the average of three measurements, reported in units of pCiIJ. '
(b) Per guidelines of the EPA'S National Standards for Water Proficiency Testing Criteria D~ument. December 1998.
u.\\
I I
I I
I Evaluation Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable
. ACctptable ACceptable Acceptable Acceptable Acceptable
. Acceptable Acceptable Acceptable J-4 Identlncatlon No.
Rad-52 Rad-S3 Rad-54 Rad*55 MedIum Water Water Water
.... ;' I Water, "
Untl'l pCiII pCiII pCiII pCiII pCtII pCiII pCiII pCtII pCiII pCtII pCtII pCiII pCtII pCtII pCiII pCtII
, pCiII
. pCtII'
- pC-t11.
pCiII pC:t11 pCiII pCtII pCiII TA(~J-1 I
ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) I PROFICIENCY TESTING PROGRAM - 2003 I
FRAMATOME ANP ENVIRONMENTAL SERVICES LABORATORY (page 1 of2)
NuclIde Gross Alpha Gross Deta St*89 Sr-90 Ba-133 Co-6O Cs-134 Cs*t37 Zn-65 Nat. Uranium H-3 1*131 Gross Alpha Gross Beta St*89 5r-9O Da-133
,,co-6O Cr*134 Cs*137 Zn-65..
Nat. Uranium
- 1-131 '
Triiium ERA Known Resu1t(a) 37.6 8.55 15.9 9.03 19.5 37.4 17.8 44.2 60.3 53.7 1250.0 20.8 65.1 31.6 58.8 20.6 20.7 37.4.
32.6
.44.3 60.2 11.4 28.2 "
14300 Framatome Resull'l (a) 28 8.97 13 8.74 17.9 36.6 17.9 45.4 60 56 1080.0 21.4 70.4 31.9 5S.S 18.7
, 19.9
- 37.4..
31.0 47.0 61.3 1I.S 28':.
14800 FramatomtlERA Ratio 0.74 I.OS 0.82 0.97 0.92 0.98 1.01 l.oJ 1.00 1.04 0.86 t.03 1.08 1.01 0.94 0.91
" 0.96 1.00 0.95
., 'co t.()6 1.02 1.01 0.99 1.03 ERA Control LimIts (b) 1.3-53.9 0.00-17.2 7.24-24.6 0.37-17.7 1'0.S-28.2 28.7-46.1 9.14-26.5 1 35.5-52.9 49.9-70.7 44.4-63.0 I
678-1820 I 15.6-26.0 I
36.9-93.3 22.9-40.3 50.1-67.5 1'1.9.29.3 12.0-29.4',
28.7-46.1 23.9-41.3 35.6-53.0.
49.8.70.6
~20-16.6 10-33.4' 11800-16800 I
(a) Results are the average of three measurements, reported in units of pCiIJ. '
(b) Per guidelines of the EPA'S National Standards for Water Proficiency Testing Criteria D~ument. December 1998.
u.\\
I I
I I
I Evaluation Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable
. ACctptable ACceptable Acceptable Acceptable Acceptable
. Acceptable Acceptable Acceptable J-4
2 3
! i,
TABLEJ-l i
ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) \\
PROFICIENCY TESTING PROGRAM - 2003 I
FRAMATOME ANP ENVIRONMENT~ SERVICES LABO~TORY (Page 2 of 2) i I
1 COMMENTS The equations used t~ calculate the sample activity were all independently verified to be correct. No problems were!ideillified with sample documentation. The chemists were trained to process strontium samples expeditiously and 10 utilize the full IS-day )1trium-90 period.
I Equipment problem with iodide probe identified. When sample was re-analyu:d with new iodide probe, ~
resu1i w~ 14.5 pCiIL, a bias of -1.4%.
No problems identifed via test data evaluation using internal calibrations. The grand mean of the test comp'ared favorably (1 % bias) with the Framatome ANP result yet indicated a signifi~ant bias from the ERA stated known. No actions were taken based on the favorable QC history
~~m C._
c.-
2 3
! i,
TABLEJ-l i
ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) \\
PROFICIENCY TESTING PROGRAM - 2003 I
FRAMATOME ANP ENVIRONMENT~ SERVICES LABO~TORY (Page 2 of 2) i I
1 COMMENTS The equations used t~ calculate the sample activity were all independently verified to be correct. No problems were!ideillified with sample documentation. The chemists were trained to process strontium samples expeditiously and 10 utilize the full IS-day )1trium-90 in*growth period.
I Equipment problem with iodide probe identified. When sample was re-analyu:d with new iodide probe, ~
resu1i w~ 14.5 pCiIL, a bias of -1.4%.
No problems identifed via test data evaluation using internal calibrations. The grand mean of the RAD*50 test comp'ared favorably (1 % bias) with the Framatome ANP result yet indicated a signifi~ant bias from the ERA stated known. No actions were taken based on the favorable QC history
~~m C._
c.-
J-5
(
TA(~J.Z I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOMEANPENVIRONMENTALLABORATORY (Page 1 of 4)
I I"
I Analytlcs I
JdentincaUon Calculated Framatome FramatomelAnalytlcs MonthlYear No.
Medium Units Nuclide Results I Results Ratio 83600-162 Milk pCiII pCiII pCiII pCiII pCiII pCiII pCiII pCill 1.:~.
pCiIi pCiII p~iII
~ "'J,i Marcb-03 83597-162 Water pCiII
- '> ~;
83597-162 Water pCiII 83598-162 Water pCiII pCiII pCiII pCiIl pCiII pCiIl pCill pCiIl pCiIl pCiIl pCiIl analysis 74 74 173 246 90 200 47 64' 47 93,
162 53 186 '
70 70 16S 238 88 195 42 63 46 90 157.
i' I
i 72.S 0.98 73 0.99 170 0.98 244 0.99 86 0.96 196 0.98 44 0.94 61 o.9S.
47' too' 96 1.03 162 l~oo' 1.04 146 0.78' 67.7 0.97 68 0.97 163 0.97 243 1.02 83 0.94 188 0.96 44 1.05 61 0.97 48 1.04 88 0.98 156 0.99
(
(
TA(~J.Z I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOMEANPENVIRONMENTALLABORATORY (Page 1 of 4)
I I"
I Analytlcs I
JdentincaUon Calculated Framatome FramatomelAnalytlcs MonthlYear No.
Medium Units Nuclide Results I Results Ratio Marcb*03 83600-162 Milk pCiII 1*131U.*
pCiII j.t31 pCiII Ce~t41 pCiII Cr*SI pCiII Cs*134 pCiII Cs~137 pCiII Co-58' pCill Mo*54 1.:~.
pCiIi Ft-59 i pCiII Zn*6S p~iII Co-60
~ "'J,i Marcb-03 83597-162 Water pCiII Or.Alpba
- '> ~;
83597-162 Water pCiII Or. Beta 83598-162 Water pCiII 1*131LV pCiII 1*131' pCiII Ce-141 pCiIl Cr*SI pCiII Cs-134 pCiIl Cs*t37 pCill Co-SS pCiIl Mn*S4 '
pCiIl Pe-59 pCiIl Zn*6S pCiIl Co-60
- r* t:n u. = radicx:hemicalscparation analysis 74 74 173 246 90 200 47 64' 47 93,
162 53 186 '
70 70 16S 238 88 195 42 63 46 90 157.
i' I
i 72.S 0.98 73 0.99 170 0.98 244 0.99 86 0.96 196 0.98 44 0.94 61 o.9S.
47' too' 96 1.03 162 l~oo' SS 1.04 146 0.78' 67.7 0.97 68 0.97 163 0.97 243 1.02 83 0.94 188 0.96 44 1.05 61 0.97 48 1.04 88 0.98 156 0.99 J*6
(
TABLEJ-2 ANAL YTlCS ENVmONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROG¥M FRAMATOME ANP ENVmONMENTAL LABORATORY (Page 2 of 4)
Analyllcs JdentUkaUon Calculated l<'ramatome FramatomtlAnalylics MonthlVear No.
Medium Units Nuclide Results Results Ratio March.oJ AP filter pCi Gr. Alpha 49 52 1.06 pCi Gr. Beta 148 IS1 1.06 March.o3 Milk pCiIJ 133 121 0.91 pCill 12 13 1.08 March.oJ Water pCill Sr-89 114 104 0.91 pCiIJ Sr-90 10 1.10 Junc.o3 El704-162 Waler pCiIJ 11953 10643 0.89 Junc.oJ El705-162 AP filter pCi Gr. Alpha 21 20 0.95 pCi liS 1.01 Junc.oJ El706-162 AP filter pCi l54 149 0.97 pCi er-Sl 130 134 1.03 pCi Cs-I34 S6 54 0.96 pCi 115 13S 1.08 pCi Co-5S 50 53 1.06 pCi 101 110 1.09 pCi Fe-59 54 60 1.11 pCi Zn-65 99 110 1.11 pCi 72 71 0.99 JUDe-OJ El707-162 APfilter pCi S,-89 81 78 0.90 pCi Sr-90 24 24 1.00 J.'
TABLEJ-2 I
ANAL YTlCS ENVmONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 I
FRAMATOME ANP QUALITY CONTROL SPIKE PROG¥M FRAMATOME ANP ENVmONMENTAL LABORATORY (Page 2 of 4)
I I
Analyllcs JdentUkaUon Calculated l<'ramatome FramatomtlAnalylics MonthlVear No.
Medium Units Nuclide Results I Results Ratio March.oJ ElS!}9*162 AP filter pCi Gr. Alpha 49 52 1.06 pCi Gr. Beta 148 IS1 1.06 March.o3 El60I*162 Milk pCiIJ 5r*89 133 121 0.91 pCill Sr*90 12 13 1.08 March.oJ El60S*162 Water pCill Sr-89 114 104 0.91 pCiIJ Sr-90 10 II 1.10 Junc.o3 El704-162 Waler pCiIJ H*3 11953 10643 0.89 Junc.oJ El705-162 AP filter pCi Gr. Alpha 21 20 0.95 pCi Gr. Beta liS 116 1.01 Junc.oJ El706-162 AP filter pCi Cc*141 l54 149 0.97 pCi er-Sl 130 134 1.03 pCi Cs-I34 S6 54 0.96 pCi Cs*137 115 13S 1.08 pCi Co-5S 50 53 1.06 pCi MD*54 101 110 1.09 pCi Fe-59 54 60 1.11 pCi Zn-65 99 110 1.11 pCi Co-6O 72 71 0.99 JUDe-OJ El707-162 APfilter pCi S,-89 81 78 0.90 pCi Sr-90 24 24 1.00 J.'
(.
c
(
TABLEJ-2 I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONfROL SPIKE PROGRAM FRAMATOMEANPENVIRONMENTALLABORATORY (Page 3 of 4)
I I
I Analytl(S I
IdentlncatIon Calculated Framatome FramatomelAnalytl(S MonthlYtar No.
Medium Unlts Nuclide Results I Results Ratio Milt pCiII 103 109 1.06 pCiII 103 104 J.OI pCiII 283 283 1.00 pClII 239 239 1.00 pCiII 103 98 0.9S pCiII 230 232 J.OI pCiII 93 92 0.99 pC-III 186 186 1.00 pCiII 99 100 1.01
, pCiII 181 181 1.00 pCiII :
132 134 1.02:
September-03 Water pCiII '
36 37 1:03, pCiII' 246' 242 0.98 Water pCiII 76 69 0.91 pCiII,
76 78 1.03 pCiII 81 78 0.96, pCiII,
221 198 0.90 pCiII 113 108 0.96
- pCiII, 84, 85 1.01 pCiII 94 92 0.98 pCiII 88 93, 1.06, pCiII 75 74' 0.99 pCiII 166 170 1.02 pCiII
.117 118 1.01 APFilter pCi 28 30 1.07 pCI 189 197 1.04 I
- ,. J 3 I lL = radiocbemical separation analysis
! I I
\\
c
(
TABLEJ-2 I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONfROL SPIKE PROGRAM FRAMATOMEANPENVIRONMENTALLABORATORY (Page 3 of 4)
I I
I Analytl(S I
IdentlncatIon Calculated Framatome FramatomelAnalytl(S MonthlYtar No.
Medium Unlts Nuclide Results I Results Ratio June*03 El153*162 Milt pCiII 1*131 103 109 1.06 pCiII 1*13IlL*
103 104 J.OI pCiII Ce*141 283 283 1.00 pClII er*sl 239 239 1.00 pCiII Cs*134 103 98 0.9S pCiII Cs*137 230 232 J.OI pCiII Co-58 93 92 0.99 pC-III Mn*54 186 186 1.00 pCiII Fe-S9 99 100 1.01
, pCiII Zn-6S 181 181 1.00 pCiII :
cQ:.6O' 132 134 1.02:
September-03 El866-t62 Water pCiII '
OrossAlpba 36 37 1:03, pCiII' OrossBeta 246' 242 0.98 September*03 El867*162 Water pCiII 1*131'J 76 69 0.91 pCiII,
1*I3ILL*
76 78 1.03 pCiII Ce*14t 81 78 0.96, pCiII,
Cr*SI 221 198 0.90 pCiII Cs*134 113 108 0.96
- pCiII, Cs~137 84, 85 1.01 pCiII Co-58 94 92 0.98 pCiII Mn*S4 88 93, 1.06, pCiII Fe*59 75 74' 0.99 pCiII Zn*65 166 170 1.02 pCiII Co-60
.117 118 1.01 September*03 El868*162 APFilter pCi Or. Alpha 28 30 1.07 pCI Or. Beta 189 197 1.04 I
- ,. J 3 I lL = radiocbemical separation analysis J*8 I
I
\\
(-
TABLEJ-2 ANALYTICS ENVmONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 4)
Analytla Identification Calculated Framatome FramatomdAnalyUa MonthlYear No.
Medium Units Nuclide Results
- Results Ratio Seplember'()3 Milk pCill 74 66 0.89 pCiII 74 74 1.00 pCill 86 90 1.05 pCiIl 233 228 0.98 pCill 119 123 1.03 pCiII 88 94 1.07 pCiIl 99 99 1.00 pCill 93 101 1.09 pCill 79 84 1.06 pCill 176 178 1.01 pCiIl 123 129 1.05 E387()'162 Milk pCill 100 80 0.80 pCiIl 14 II 0.79 LL= radiocbemicalseparauoo analysis J.g c
(-
TABLEJ-2 ANALYTICS ENVmONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 4)
Analytla Identification Calculated Framatome FramatomdAnalyUa MonthlYear No.
Medium Units Nuclide Results
- Results Ratio Seplember'()3 E3869*162 Milk pCill 1*131 74 66 0.89 pCiII 1*13ILL*
74 74 1.00 pCill Ce*141 86 90 1.05 pCiIl er*St 233 228 0.98 pCill Cs*I34 119 123 1.03 pCiII Cs*137 88 94 1.07 pCiIl Co-58 99 99 1.00 pCill Mn*S4 93 101 1.09 pCill Fe*S9 79 84 1.06 pCill
- zn.{jS 176 178 1.01 pCiIl Co-GO 123 129 1.05 September*03 E387()'162 Milk pCill Sr*89 100 80 0.80 pCiIl Sr*90 14 II 0.79
- 1*131 LL= radiocbemicalseparauoo analysis J.g c
(
MonthIYtar Marcll-03 Marcll-03 Marcll-03
('
TABt~J*3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACI1VITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 1 of5)
Identification Analytlcs Framatome No.
Medium Units Nuc:Ude Calc:nl.ted Results (a)
Results (a)
Sedimt:l1t pC.1I:g 358 :I: 18 351 :!: 14 pC1I\\g 508 :t 2S 511 :t: 41 pC1I\\g 186 :t 9 189 :t 6 '
pC1I\\g 497 :t 2S 536 :t 9 pCiltg 96 :1:5 97 :!:
pCiltg 133 :t 65 132 :t II pC1I\\g 98:5-104 :t: 7 pC1I\\g 192 ;: I 197 :tl0 pCiltg 335 :t 17 340: 6 Mill:
pCiIl,
75:1:3' 73 :t 9.
pCiIl 188 ':1:17 pCiIl' 261:t: 35 193' +/- 7 244' :t:n pan' 98 :t pCiIl 211 :t 22 pC'II1' 51 '+/-'2 '
9S ::I: 4 221:6 50 +/- 3 pan 70 :t 3 ;
70 :1:4 pCt/I 51 :I: 2 51 :I:
pCiIl 101 :t 5 101 : 8 pCt/I 176 :t 16
.79:1: 4 APFilter pCi 160:!: 6 143 :2 pCi 227:!: 8 219 :I: 11 pCi 83 :!: 3 pCi 185 :!: 6 78 :I: 2 179 ': 3 pCi 4j ':!: 2 41 :I: 2 pCi S9 :t 2 '
S9:1: 2 pCi 44 :t: 2 4S :I: 2 pCi' 86 :t: 3 87 :t:4 pCi 149 :t S 133 :t: 2
.t (a) Counting error is two standard deviations.
(
FramatomrlAnalytlcs Ratio 0.98, 1.01 1.02 1.08 1.01 0.99,
1.06 1.03 1.01 0.91.
1.03.
0.91 "
0.971,:
1.02 0.98 1.00 1.00 1.00 1.02, 0.89 0.96 0.94 0.97 0.96 0.99
" 1.01 1.01 0.89
(
MonthIYtar Marcll-03 Marcll-03 Marcll-03
('
TABt~J*3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACI1VITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 1 of5)
Identification Analytlcs Framatome No.
Medium Units Nuc:Ude Calc:nl.ted Results (a)
Results (a)
IDS7)*J86 Sedimt:l1t pC.1I:g Ce-J41 358 :I: 18 351 :!: 14 pC1I\\g Cr*SI 508 :t 2S 511 :t: 41 pC1I\\g Cs-134 186 :t 9 189 :t 6 '
pC1I\\g Cs-131 497 :t 2S 536 :t 9 pCiltg Co.S8 96 :1:5 97 :!: S pCiltg Mn-54 '
133 :t 65 132 :t II pC1I\\g Fe-59 98:5-104 :t: 7 pC1I\\g Zn-65 192 ;: I 197 :tl0 pCiltg Co-60 335 :t 17 340: 6 B3575*186 Mill:
pCiIl,
1*131 75:1:3' 73 :t 9.
pCiIl Cc-141.,
188 ':1:17 pCiIl' Cr.51 261:t: 35 193' +/- 7 244' :t:n pan' Cs-134 '
98 :t S pCiIl Cs-137 '
211 :t 22 pC'II1' Co.58 51 '+/-'2 '
9S ::I: 4 221:6 50 +/- 3 pan Mn-54 70 :t 3 ;
70 :1:4 pCt/I Fe-59 51 :I: 2 51 :I: S pCiIl Zn-65 101 :t 5 101 : 8 pCt/I Co-60 176 :t 16
.79:1: 4
£3576*186 APFilter pCi Ce-141 160:!: 6 143 :2 pCi Cr.SI; 227:!: 8 219 :I: 11 pCi CsJ34 83 :!: 3 pCi Cs-137 185 :!: 6 78 :I: 2 179 ': 3 pCi Co.S8 4j':!: 2 41 :I: 2 pCi Mn*S4 S9 :t 2 '
S9:1: 2 pCi Fe-S9 44 :t: 2 4S :I: 2 pCi' Zn-65 86 :t: 3 87 :t:4 pCi C0-60 149 :t S 133 :t: 2
- J, '.
.t (a) Counting error is two standard deviations.
(
FramatomrlAnalytlcs Ratio 0.98, 1.01 1.02 1.08 1.01 0.99,
1.06 1.03 1.01 0.91.
1.03.
0.91 "
0.971,:
1.02 0.98 1.00 1.00 1.00 1.02, 0.89 0.96 0.94 0.97 0.96 0.99
" 1.01 1.01 0.89 J*I0
PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOAcrIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of5)
IdenUDeaUon Analyuc:s Framatome Fnnu.tonltl AlIal)'Uc:s MonthlVear No.
Mediunl Units NUclide Calculated Results !al Results <al RaUo APFll!.c.r pCi Ce.141 133 S
121 2
0.91 pCi 189 :t 7 172 :t 9 0.91 pCi CsI34 69 :t 2 62;t 1 0.89 pCi Cs-137 154 :t 5 153 ;t 3 0.99 pCi
<:0.58 36 1
36 2
0.99 Mn-54 50 :t 2 50 :t 2 1.01 Po-59 36 :t 1 40 :2 1.11 pCi Zn-65 72 :t 3 71 :t 4 0.98 pCi
<:0.60 125 :t 4 113' ;t 2 0.90 APFJl!.c.r
<:0.141 171 :t 6 162: 2 0.95 pCi 242 :t 8 235 :t 11 0.97 pCi CsI34 89 :t 3 82 :t 2 0.93 Cs-137 197 :t 7 200 3
1.02 pCi
<:0.58 46 ;t 2 44 :t 2 0.96 pCi Mn-S4 63 :t 2 68 :t 2 1.08 Po-59 41 :t 2 53 :t 2 1.12 pCi Zn.6S 91 : 3 95:1: 4 1.05 pCi
<:0.60 159 : 6 148:1: 2 0.93 APFllter Ce.141 230:8 209:1: 2 0.91 194 1
190 : 11 0.98 pCi CsI34 84 :t 3 78 :t 2 0.93 pCi Cs-137 188:7 191 : 3 1.02 pCi
<:0.58 76 : 3 74 2
0.98 pel lSI :t; 5 157 :t; 3 pCi Fo-59 81 :t; 3 85 :t; 3 pCi Zn.65 148 :t; 5 157 :t 5 1.06 pCi
<:0.60 108 :t; 4 100 :t 2 0.92 (a) e.rroris two standard deviations.
TABLEJ*3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOAcrIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of5)
IdenUDeaUon Analyuc:s Framatome Fnnu.tonltl AlIal)'Uc:s MonthlVear No.
Mediunl Units NUclide Calculated Results !al Results <al RaUo M.arch-OJ E.3S17*186 APFll!.c.r pCi Ce.141 133 ::t S 121 ::t 2 0.91 pCi Cr*S1 189 :t 7 172 :t 9 0.91 pCi CsI34 69 :t 2 62;t 1 0.89 pCi Cs-137 154 :t 5 153 ;t 3 0.99 pCi
<:0.58 36 ::t 1 36 :t 2 0.99 pel Mn-54 50 :t 2 50 :t 2 1.01 pel Po-59 36 :t 1 40 :2 1.11 pCi Zn-65 72 :t 3 71 :t 4 0.98 pCi
<:0.60 125 :t 4 113' ;t 2 0.90 M.arch-03 E3578*186 APFJl!.c.r pel
<:0.141 171 :t 6 162: 2 0.95 pCi Cr*51 242 :t 8 235 :t 11 0.97 pCi CsI34 89 :t 3 82 :t 2 0.93 pel Cs-137 197 :t 7 200 :t 3 1.02 pCi
<:0.58 46 ;t 2 44 :t 2 0.96 pCi Mn-S4 63 :t 2 68 :t 2 1.08 pel Po-59 41 :t 2 53 :t 2 1.12 pCi Zn.6S 91 : 3 95:1: 4 1.05 pCi
<:0.60 159 : 6 148:1: 2 0.93 Juno-03 E3770-186 APFllter pel Ce.141 230:8 209:1: 2 0.91 pel Cr*Sl 194 :I: 1 190 : 11 0.98 pCi CsI34 84 :t 3 78 :t 2 0.93 pCi Cs-137 188:7 191 : 3 1.02 pCi
<:0.58 76 : 3 74 :t 2 0.98 pel MIl*54 lSI :t; 5 157 :t; 3 1.04 pCi Fo-59 81 :t; 3 85 :t; 3 1.04 pCi Zn.65 148 :t; 5 157 :t 5 1.06 pCi
<:0.60 108 :t; 4 100 :t 2 0.92 1*11 (a) Counting e.rroris two standard deviations.
C
c, TAnCr..J-3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 -
FRAMATOME ANP ENVIRONMENTAL LABORATORY (pnge30f5)
I.'entmcation Analytlc::9 Fnmltome Fnmatome! Anllytla MonO,/Yell" No.
Mrdlum Units Nuclide C.lrnJattd RfSIllts CI)
RfSIlIts Ca)
Ratio J.ll (8) Counting error is two staOOard deviatiOf'L'l.
c c,
TAnCr..J-3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 -
FRAMATOME ANP ENVIRONMENTAL LABORATORY (pnge30f5)
I.'entmcation Analytlc::9 Fnmltome Fnmatome! Anllytla MonO,/Yell" No.
Mrdlum Units Nuclide C.lrnJattd RfSIllts CI)
RfSIlIts Ca)
Ratio lunc-03 BJ77t*l86 APFiItet' pCi Ce-14 I 203 % 7 189 :t 2 0.93 pCi Cr*SI 171 % 6 170 % 10 0.99 pCi Csl34 74:3: 3 69:t 2 0.94 pCi Cs-137 1605 :t 6 170 :t 3 l.oo pCi Co.58 67:1: 2 66 :t 2 0.99 pCi MrrS4 133 +/-.5 142 % 3 1.06 pCi Pe-59 71 :t 2 78 = 3 1.09 pCi Zn-6S 130:1: S 138 = S 1.06 pe;:i Co-60 95:1: 3 89 +/- 2 0.94 J~:',I \\.' ~.
~ ~,
lune-03 BJ77Z*186 APPi1tet'
- pCi, Ce-141 225 :I: 8 203 :1:,2 0.90
~ '" l,',.~ "
Po er.s'l' 190':!; t' 177:1: 10 0.93 pCi Cs134 82:1: 3 76'= 2 0.93 pCi Cs-137 183 % 6 186 = 3 1.02
- pCi, Co.5!
74:1: 3 71:1: 2 0.96 pCi Mn.54 148 :t S 152 = 3.
1.03 pCi Pe-59 79.+/- 3 84:1: 3 1.06 pCi Zn-6"S 144 :t S 154 +/- S.
1.07' pO Co-60 105 % 4 97 +/-.2 0.92 June-02 BJ713*186 Ol3rcoal Filtet' pel 1*131 66:1: 2 80:1: 7 1.22 BJ774*186 Ol3rcoal Filler fa 1*131 51 +/- 2.
(1)
BJ71S:is6 Ol3rcoal Filter pCi 1*131 59:t 2 68:t 6 1.15 J.ll J.'
I (8) Counting error is two staOOard deviatiOf'L'l.
c
PPL REMP LABORATORY SPIKE PROGRAM ANAL mcs ENVIRONMENTAL RADIOACflVITY CROSS CHECK P~OGRAM
- 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 5)
Idenllftc:aUon AnalyUaI Frllll1&tomt FramatomtiAnalyUaI (n) Counlinq etrOf is two stanJanl deviations.
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TABLEJ*3 PPL REMP LABORATORY SPIKE PROGRAM ANAL mcs ENVIRONMENTAL RADIOACflVITY CROSS CHECK P~OGRAM
- 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 5)
Idenllftc:aUon AnalyUaI Frllll1&tomt FramatomtiAnalyUaI MOIIUlIYear No.
Medium Units NucUde Calculated Results (a)
Results (a)
RaUo Septc.mbe.r-03 83891*186 Milk pCiIl 1*131 7S ;t 2 83 ;t 8 1.10 pCiIl a,.141 188 :t 11 191 :I: 6 1.01 pCiIl Cr*SI SIO ;t 87 S43 ;t: 3S 1.06 pCiIl Cf.134 261 ;t: 23 24S:l:6 0.94 pCiIl Crl37 193 ;t 12 196:1: 5 1.02 pCiIl COOSS 216 :I: 15 I
214 ;t: 6 0.99 pCiIl M.n-.54 203 ;t 14 187 :t S 0.92 pCiIl Fc>S9 173:1: 10 173 :t 7 1.00 pCiIl Zn-6S 385:1: SO I
39S :I: 12 1.03 pCiIl
<=0-60 270 :t 24 283.:1:5 1.0S Deeember-03 83977*186 Cwtoal Fllte.r pCi 1*131 76:1: 2.5 85 :t 6 1.12 83978*186 Cwtoal Fllla' pCi 1*131 68;t 2.3 78;t: 6 US E3979*186 Cwtoal Fllte.r pCi 1-131 86 ;t: 2.9 94:1: 6 1.09 J*13 (n) Counlinq etrOf is two stanJanl deviations.
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c TA(~~J.3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (page 5 of 5)
COMMENTS Framatome ANP unable to a~alyze sample. Charcoal cartridge damaged during shipment from Analytlcs.
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c TA(~~J.3 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (page 5 of 5)
COMMENTS Framatome ANP unable to a~alyze sample. Charcoal cartridge damaged during shipment from Analytlcs.
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J*14 I..
TABLEJ-4 DOE - ENVlRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
~TOMEANPENVlRONMENTALLABORATO~Y (Page 1 of 4)
Identification EMLKnown Fnunatome FnunatomdEML MonthIYear No.
Medium Units Nuclide Results Results Rallo QAP58 AP Filler Dq Mn-S4 43.8 43.2 0.99 Bq Co-60 33.5 33.5 1.00 Dq 5r-90 2.8 23 0.83 Dq Cs-137 99.7 102.7 1.03 Dq U-234 0.2 0.2 0.93 Dq 0.5 0.5 0.99 Dq U-238 0.2 0.2 0.92 Dq Pu-239 03 0.3 1.00 8q Am-241 03 0.3 0.98 Dq Gross Alpha 1.2 1.1 0.93 Bq Gross Beta 1.5 1.4 0.94 March.Ql QAP58 Soil Dqlkg K-40 636.0 65l.0 1.03 Bqlkg Cs-137 1450.0 1497.6 1.03 Bqlkg Ae-228 51.6 54.9 0.95 Bqlkg U-234 120.0 IIS.7 0.96 Bqlkg Pu-238 21.9 23.5 1.07 Bqlkg U-238 125.0 122.9 0.98 Bqlkg Pu-239 23.4 24.4 1.04 Bqlkg Am-24 1 IS.6 12.4 0.79 (1)
March-OJ QAP58 Vegetati~
Dqlkg.
K-40 1120 1172 1.05 Bqlkg Co-6O 12.1 13.02 1.08 Bqlkg Sr-90 650 545.3 0.84 Bqlkg 444 469.1 1.06 Dqlkg Pu-239 5.17 5.05 0.98 Dqlkg Am-241 3.51 3.487 0.99 Bqlkg Cm-244 2.01 1.02 I-IS
(
TABLEJ-4 DOE - ENVlRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
~TOMEANPENVlRONMENTALLABORATO~Y (Page 1 of 4)
Identification EMLKnown Fnunatome FnunatomdEML MonthIYear No.
Medium Units Nuclide Results Results Rallo March*03 QAP58 AP Filler Dq Mn-S4 43.8 43.2 0.99 Bq Co-60 33.5 33.5 1.00 Dq 5r-90 2.8 23 0.83 Dq Cs-137 99.7 102.7 1.03 Dq U-234 0.2 0.2 0.93 Dq Pu*238 0.5 0.5 0.99 Dq U-238 0.2 0.2 0.92 Dq Pu-239 03 0.3 1.00 8q Am-241 03 0.3 0.98 Dq Gross Alpha 1.2 1.1 0.93 Bq Gross Beta 1.5 1.4 0.94 March.Ql QAP58 Soil Dqlkg K-40 636.0 65l.0 1.03 Bqlkg Cs-137 1450.0 1497.6 1.03 Bqlkg Ae-228 51.6 54.9 0.95 Bqlkg U-234 120.0 IIS.7 0.96 Bqlkg Pu-238 21.9 23.5 1.07 Bqlkg U-238 125.0 122.9 0.98 Bqlkg Pu-239 23.4 24.4 1.04 Bqlkg Am-24 1 IS.6 12.4 0.79 (1)
March-OJ QAP58 Vegetati~
Dqlkg.
K-40 1120 1172 1.05 Bqlkg Co-6O 12.1 13.02 1.08 Bqlkg Sr-90 650 545.3 0.84 Bqlkg Cs*137 444 469.1 1.06 Dqlkg Pu-239 5.17 5.05 0.98 Dqlkg Am-241 3.51 3.487 0.99 Bqlkg Cm-244 2.01 2.0S 1.02 I-IS
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TA(~J.4
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DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
FRAMATOMEANPENVmONMENTALLABORATORY (Page 2 of 4)
Identincation EMLKnown
~ Framatome Framatom<<1EML MonthlYear No.
Medium Units Nucllde Results Results Ratio QAP58 Water BqII H-3 426.0 390.0 0.92 BqII Co-60 219.0 234.0 1.07 BqII 4.1 4.3 1.07 DqII Cs-134 29.4 30.5 1.04 BqII Cs-137 59.6 63.8 1.07 BqII U-234 2.3 2.'
0.90 DqII Pu238 3.7 3.3 0.91 BqII U-238 2.1 2.2 1.02 BqII 4.2 3.9 0.92 BqII Am-24 I 2.2 2.1 0.99 BqII Or. Alpha 418.1 0.90 BqII Gr. Dela 682.4 627.5 0.92 September-03 QAP59 AP filters Bq Co-60 55.1 56.0 1.02 Dq Cs-137 54.8 57.1 1.04 Bq Or. Alpha 3.1 2.8 0.88 Bq Gr. Beta 3.9 3.1 0.80 (2)
Dq 58.0 58.3 1.01 Sepiembei'-03 QAP59 Soli.
nqlkg AcTh-228 50.8 51.7 1.02 Bqlkg Cs-137 1973.0 2269.0 Bqlkg K-40 488.0 547.0 1.12 J-lti I
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TA(~J.4
(_
DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
FRAMATOMEANPENVmONMENTALLABORATORY (Page 2 of 4)
Identincation EMLKnown
~ Framatome Framatom<<1EML MonthlYear No.
Medium Units Nucllde Results Results Ratio March*03 QAP58 Water BqII H-3 426.0 390.0 0.92 BqII Co-60 219.0 234.0 1.07 BqII Sr*9O 4.1 4.3 1.07 DqII Cs-134 29.4 30.5 1.04 BqII Cs-137 59.6 63.8 1.07 BqII U-234 2.3 2.'
0.90 DqII Pu238 3.7 3.3 0.91 BqII U-238 2.1 2.2 1.02 BqII Pu*239 4.2 3.9 0.92 BqII Am-24 I 2.2 2.1 0.99 BqII Or. Alpha 418.1 3n.5 0.90 BqII Gr. Dela 682.4 627.5 0.92 September-03 QAP59 AP filters Bq Co-60 55.1 56.0 1.02 Dq Cs-137 54.8 57.1 1.04 Bq Or. Alpha 3.1 2.8 0.88 Bq Gr. Beta 3.9 3.1 0.80 (2)
Dq Mn*S4 58.0 58.3 1.01 Sepiembei'-03 QAP59 Soli.
nqlkg AcTh-228 50.8 51.7 1.02 Bqlkg Cs-137 1973.0 2269.0 I.lS Bqlkg K-40 488.0 547.0 1.12 J-lti I
TABLEJ4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 3 of 4)
Identification El\\lLKnown Framatome Framatomc:lEML MonlhIYear No.
Medium Units Nuclide Results Results Ratio September"()3 QAP59 Water 8qIJ Co-60 469.4 513.0 1.09 Bqll 60.1 63.0 1.05 Bqll 73.9 80.3 1.09 Dqll Gross Alpha 531.0 622.0 1.17 DqII Gross Beta 1790.0 1948.0 1.09 Scptember"()3 QAP59 Vegetation Bqlkg (3)
(3)
(3)
(3)
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TABLEJ4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 3 of 4)
Identification El\\lLKnown Framatome Framatomc:lEML MonlhIYear No.
Medium Units Nuclide Results Results Ratio September"()3 QAP59 Water 8qIJ Co-60 469.4 513.0 1.09 Bqll Cs*J34 60.1 63.0 1.05 Bqll Cs*137 73.9 80.3 1.09 Dqll Gross Alpha 531.0 622.0 1.17 DqII Gross Beta 1790.0 1948.0 1.09 Scptember"()3 QAP59 Vegetation Bqlkg (3)
(3)
(3)
(3)
J*17
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TABLEJ.. 4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATQRY (EML)
QUALITY ASSESSMENT PROGRAM (QAP) i FRAMATOME ANP ENVIRONMENTAL LABORAT9RY,
(page 4 of 4)
COMMENTS 1
Low bias identified. Condition Report (~ No. 03-20) generated by" Framatome Env. Lab to: investigate Low Bias.
2 Low bias identified. Condition Report (CR No. 04-03) generated by Framatome Env. Lab to investigate Low Bias..,
I 3
,i':;' No vegetation s~triple was provided by DOEQAP for this test period:.
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TABLEJ.. 4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATQRY (EML)
QUALITY ASSESSMENT PROGRAM (QAP) i FRAMATOME ANP ENVIRONMENTAL LABORAT9RY,
(page 4 of 4)
COMMENTS 1
Low bias identified. Condition Report (~ No. 03-20) generated by" Framatome Env. Lab to: investigate Low Bias.
2 Low bias identified. Condition Report (CR No. 04-03) generated by Framatome Env. Lab to investigate Low Bias..,
I 3
,i':;' No vegetation s~triple was provided by DOEQAP for this test period:.
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Identification MonthIYear No.
03-S10 TABLEJ.. 5 DOE.. MAPEP N.UXEDANALYTEPERFORMANCEEVALUATIONPROq~
FRAMATOME ANP ENVIRONMENTAL LABORATO~Y (Page 1 of 2)
MAPEP Known Framatome Framatome/MAPEP Medium Units Nuclide Results Results Ratio Water BqIL 0.58 0.58 1.00 BqIL 421.00 398.12 0.95 BqIL 329.00 301.31 0.92 BqIL 51.00 52.44 0.92 8qIL 38.20 36.54 0.96 BqIL 96.00 81.00 0.91 BqIL 32.90 31.53 0.96 BqIL 136.50 126.00 0.92 BqIL 0.83 0.85 1.03 BqIL 0.03 BqIL 12.31 11.09 0.90 DqIL 1.54 1.63 1.06 BqIL 1.60 1.63 1.02 DqIL 516.00 509.10 0.99 Soil DqlKg 238.00 248.60 1.04 8q1Kg 832.00 848.80 1.02 8q1Kg 530.00 544.40 1.03 BqlKg 420.00 439.20 1.05 BqlKg 131.00 143.10 1.05 BqlKg 714.00 626.60 0.88 8q1Kg 652.00 613.70 1.03 BqlKg 490.00 516.50 1.05 c
Evaluation Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement False Positive (I)
Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Identification MonthIYear No.
March-03 02*WIO March*03 03-S10 TABLEJ.. 5 DOE.. MAPEP N.UXEDANALYTEPERFORMANCEEVALUATIONPROq~
FRAMATOME ANP ENVIRONMENTAL LABORATO~Y (Page 1 of 2)
MAPEP Known Framatome Framatome/MAPEP Medium Units Nuclide Results Results Ratio Water BqIL Am-24 1 0.58 0.58 1.00 BqIL Cs*134 421.00 398.12 0.95 BqIL Cs*U1 329.00 301.31 0.92 BqIL Co-51 51.00 52.44 0.92 8qIL Co-60 38.20 36.54 0.96 BqIL Fe-55 96.00 81.00 0.91 BqIL Mn*S4 32.90 31.53 0.96 BqIL Ni-63 136.50 126.00 0.92 BqIL Pu-238 0.83 0.85 1.03 BqIL Pu-239/40 0.03 BqIL Sr-90 12.31 11.09 0.90 DqIL U*233/234 1.54 1.63 1.06 BqIL U*238 1.60 1.63 1.02 DqIL Zn-65 516.00 509.10 0.99 Soil DqlKg Cs*134 238.00 248.60 1.04 8q1Kg Cs*131 832.00 848.80 1.02 8q1Kg Co-51 530.00 544.40 1.03 BqlKg Co-6O 420.00 439.20 1.05 BqlKg Mn*S4 131.00 143.10 1.05 BqlKg Sr*90 714.00 626.60 0.88 8q1Kg K40 652.00 613.70 1.03 BqlKg Zn-65 490.00 516.50 1.05 c
Evaluation Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement False Positive (I)
Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement J*19
c TA[.... J.S DOE-MAPEP MIXED ANALYfE PERFORMANCE (page 2 of 2)
COMMENTS I
False positive. Condition Report (CR No. CR 03-14) generated by Framatome Env Lab to investigate and verify MDC of sample with MAPEP.
c TA[.... J.S DOE-MAPEP MIXED ANALYfE PERFORMANCE (page 2 of 2)
COMMENTS I
False positive. Condition Report (CR No. CR 03-14) generated by Framatome Env Lab to investigate and verify MDC of sample with MAPEP.
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TABLEJ-6 ENVIRONMENTAL RESOURCE ASSOCIATES (E~)
PROFICIENCY TESTING PROGRAM - 2003 j
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERYICES (TBE)
(Page 1 of2)
Identification ERA KoOWD THE
' THFJERA ERA MonthlYear No.
Medium Units Nuclide Result (a)
Results (a)
Ratio Control Limits (b)
EvaluatioD May-03 Rad-S3 Water pCiIl l-l3I 20.8 13.6 0.65 15.6-26.0 (1) pCiIl H-3 1200 0.96 678 - J820 Acceptable pCiIl Co-ro 63.8 69.9 1.10 55.1-72.5 Acceptable pCiIl Cs-l34 75.7 73.5 0.97 67.0-84.4 Acceptable pCiIl Cs-137 ISO 165 1.10 141 - 159 (2) pCiIl Sr-89 31.3 37.0 1.18 22.6-40.0 Acceptable pCiIl Sf-90 27.4 23.5 0.86 18.7 - 36.1 Acccptable November.Q3 Rad-5S Water pCiIl 1-131 28.2 22.2 0.79 23.0-33.4 (3) pCiIl H-3 14300 1630 0.11 (4) pCiIl co-ro 27.7 28.4 1.03 19.0-36.4 Acceptable pCiIl Cs-134 23.4 21.7 0.93 14.7 - 32.1 Acceptable pCiIl Cs-137 64.2 63.6 0.99 55.S - 72.9 Acceptable pCiIl Sr-89 50.4 47.9 0.95 41.7-59.1 Acceptable pCiIl Sr-9O 10.2 9.23 0.90 1.54 - 18.9 Acceptable pCiIl Or-Beta 168 161 0.96 124 -212 Acceptable (a) Results are the average of three measurements, reported in units of pCiIl.
(b) Per guidelines of the EPA'S National Standards for Water Proficiency Testing Criteria Document, December 1998.
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c TAl~J.6 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)
PROFICIENCY TESTING PROGRAM - 2003 !
I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)
(Page 2 of2)
COMMENTS
~
1 The stable iodine carrier in the sample was unaccounted for in the calculation. When recalculated, the correct result of 20.0 pCiIL was within acc~ptance criteria. NCR 03~ 11 generated by Teledyne to investigate: condition. '.:
'I-2 Although Cs-137 is evaluated as N, the TBElERA ratio of 1.10 faits within limits of 0.80 - It20 and is considered by TBE as acceptable.
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3 The decay correction did not take into account the extended count time. When recalculated,i,the correct result of 23.2 was within
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acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition.
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Due to recalculating H-3 to required reporting units, it decimal place was dropped. The co~~ct result of 16300 is within acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition.
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TAl~J.6 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)
PROFICIENCY TESTING PROGRAM - 2003 !
I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)
(Page 2 of2)
COMMENTS
~
1 The stable iodine carrier in the sample was unaccounted for in the calculation. When recalculated, the correct result of 20.0 pCiIL was within acc~ptance criteria. NCR 03~ 11 generated by Teledyne to investigate: condition. '.:
'I-2 Although Cs-137 is evaluated as N, the TBElERA ratio of 1.10 faits within limits of 0.80 - It20 and is considered by TBE as acceptable.
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3 The decay correction did not take into account the extended count time. When recalculated,i,the correct result of 23.2 was within
~
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acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition.
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Due to recalculating H-3 to required reporting units, it decimal place was dropped. The co~~ct result of 16300 is within acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition.
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I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL S~RVICES (Page 1 o(5)
Analytles Identification Calculated TBE TBFJ Analyties MonthlYear No.
Medium Units Nuclide Results Results Ratio March-OJ Milk pCill Sr-89 133 80:
0.60 (I) pCiJI 11.8 11.2 0.95 March-03 Milk pCill 74 75 1.01 pCill 173
- 168, 0.91 pCill 246 243 0.99 pCiJI 90 83~
0.92 pCiJI 200 201 1.04 pCill 47 49:
1.04 pCiJI 64 65 :
1.02 pCiIl 47 53 1.13 pCill 93 114 1.23 (4) pCiJI 162 169 1.04 March-OJ pCi 224 239 1.01 pCi 318 348 1.09 pCi 117 JOI 0.86 pCi 259 217 1.01 pCi 60 t
66 1.10 pCi 83 97 1.11 pCi 61 80j 1.31.
(2) pCi 120 l52 1.21 pCi 209 223 1.07 pCi 106 138 l.lO (4)
March-Ol Charcoal Filler pCi 74 68 0.92
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TABLEJ*7 ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL S~RVICES (Page 1 o(5)
Analytles Identification Calculated TBE TBFJ Analyties MonthlYear No.
Medium Units Nuclide Results Results Ratio March-OJ
£3585*396 Milk pCill Sr-89 133 80:
0.60 (I) pCiJI Sr-90 11.8 11.2 0.95 March-03
£3586-396 Milk pCill J-131 74 75 1.01 pCill Ce-141 173
- 168, 0.91 pCill Cr*Sl 246 243 0.99 pCiJI Cs*134 90 83~
0.92 pCiJI Cs*131 200 201 1.04 pCill Co-58 47 49:
1.04 pCiJI Mn-S4 64 65 :
1.02 pCiIl Fc-59 47 53 1.13 pCill Zn-65 93 114 1.23 (4) pCiJI Co-6O 162 169 1.04 March-OJ
£3588*J96 APFilter pCi Ce-141 224 239 1.01 pCi Cr-51 318 348 1.09 pCi Cs*134 117 JOI 0.86 pCi Cs*137 259 217 1.01 pCi Co-5S 60 t
66 1.10 pCi Mn-S4 83 97 1.11 pCi Fc-59 61 80j 1.31.
(2) pCi Zn-65 120 l52 1.21 pCi Co-60 209 223 1.07 pCi Fe*55 106 138 l.lO (4)
March-Ol
£3587*396 Charcoal Filler pCi I-Ill 74 68 0.92 J*23
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ANAL YTICS ENVmONMENT AL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM
" TELEDYNE BROWN ENGINEERING ENVmONMENTAL SERVICES (page 2 of5)
Analytlcs Identification
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Calculated THE TBFiAnaJytlcs MonthlYear No.
Medium Units' Nuclide Results Resul'ts Ratto June-03 B3747-396 Milk pClII Sr-89 85 89j 1.05 pCiII Sr-90 23 20:
0.87 June-03 B3748-396 Milk pC'1II 1-131 103 liS 1.12 pClIi 283 285 1.01 pCiII 239 266 l.ll pClII 103 0.96
' 99; pClII 230 236 1.03 pClII CO-58 93 106 1.14 pCui Mn.S4 186 1.02 190 Fe-59' I
pClII 99' 108 1.09.
pClII Zn~6S 181 208 I.IS:
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pClII 132 142 1.08 Ce-14'1
" i June-03 B37So.396 APFilter
" pCi' 248 238 0.96 pCi' Cr-SI 209 239 1~14 pCi Cs.t34 91 79:
0.87 pCi Cs-137 202 189 0.94 pCi Co-58 81 71 :
0.88 I
pCi Mn-54 163 164 1.01 pCi Fe-59 87 91 :
1.05 I
pCi Zn-6S 159 ISS 0.91 pCi Co-60 116 109 0.94 pCi Fe-55 97 160 1.65 (3)
June-03 Charcoal Filter pCi 62 78' 1.26 (4)
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TABLr.;J-7 ANAL YTICS ENVmONMENT AL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM
" TELEDYNE BROWN ENGINEERING ENVmONMENTAL SERVICES (page 2 of5)
Analytlcs Identification
- ( ',f 1
Calculated THE TBFiAnaJytlcs MonthlYear No.
Medium Units' Nuclide Results Resul'ts Ratto June-03 B3747-396 Milk pClII Sr-89 85 89j 1.05 pCiII Sr-90 23 20:
0.87 I*
June-03 B3748-396 Milk pC'1II 1-131 103 liS 1.12 pClIi Ce*141 283 285 1.01 pCiII Cr*SI 239 266 l.ll pClII Cs*134 103 0.96
' 99; pClII Cs*137 230 236 1.03 pClII CO-58 93 106 1.14 pCui Mn.S4 186 1.02 190 Fe-59' I
pClII 99' 108 1.09.
pClII Zn~6S 181 208 I.IS:
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pClII 132 142 1.08 Ce-14'1
" i June-03 B37So.396 APFilter
" pCi' 248 238 0.96 pCi' Cr-SI 209 239 1~14 pCi Cs.t34 91 79:
0.87 pCi Cs-137 202 189 0.94 pCi Co-58 81 71 :
0.88 I
pCi Mn-54 163 164 1.01 pCi Fe-59 87 91 :
1.05 I
pCi Zn-6S 159 ISS 0.91 pCi Co-60 116 109 0.94 pCi Fe-55 97 160 1.65 (3)
June-03 B3749*396 Charcoal Filter pCi 1*131 62 78' 1.26 (4)
"'i" J*24 j,
ANAL YTICS ENVIRONMENTAL RADIOACfIVITY CROSS CHECK 2003 TELEDYNE QUALITY CONTROL SPIKE PROG~
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES t
(Page 3 of5)
Analyties Identification Calculated TB~
TBFlAnalyUcs Month/Year No.
Medium Units Nuclide Results Results Ratio September-03 Milk pCiJI 100 45:
0.45 (l) pCill 14 13 :
0.93 September-03 Milk pCiJI 74 73 0.99 pCill 86 85' 0.99 pCill 233 220 0.94 pCill 119 l06 i
0.89 pCiJI 88 90!
1.02 pCiJI 99 96:
0.97 pCiJI 93 95:
1.02 pCiJI 79 84' 1.06 pCiJI 176
- 187, 1.06 pCiJI 123 132 1.07 APFiller pCi 77 79:
1.03 pCi 210 227 1.08 pCi 108 93 0.86 pCi 79 70 0.89 pCi 89 80i 0.90 pCi 84 73 0.87 pCi 71 74, 1.04 pCi 158 143 0.91 pCi III 93' 0.84 pCi 112 144 1.29 (4)
September.03 Charcoal Filter pCi 86 74 0.86 November-03 Milk pCill 168 185 1.10 pCill 17 19 1.12 J.2S c
TABLEJ*7 ANAL YTICS ENVIRONMENTAL RADIOACfIVITY CROSS CHECK :pROGRAM* 2003 TELEDYNE QUALITY CONTROL SPIKE PROG~
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES t
(Page 3 of5)
Analyties Identification Calculated TB~
TBFlAnalyUcs Month/Year No.
Medium Units Nuclide Results Results Ratio September-03 E3898*396 Milk pCiJI Sr*89 100 45:
0.45 (l) pCill Sr*90 14 13 :
0.93 September-03 E3899*396 Milk pCiJI I-13l 74 73 0.99 pCill Ce-141 86 85' 0.99 pCill er*Sl 233 220 0.94 pCill Cs*l34 119 l06 i
0.89 pCiJI Cs*137 88 90!
1.02 pCiJI Co-S8 99 96:
0.97 pCiJI Mn*54 93 95:
1.02 pCiJI Fe*59 79 84' 1.06 pCiJI ZO-6S 176
- 187, 1.06 pCiJI Co-60 123 132 1.07 September*03 E3901*396 APFiller pCi Ce-141 77 79:
1.03 pCi er*51 210 227 1.08 pCi Cs*134 108 93 0.86 pCi Cs*137 79 70 0.89 pCi Co-S8 89 80i 0.90 pCi Mn-54 84 73 0.87 pCi Fe-59 71 74, 1.04 pCi Zn-65 158 143 0.91 pCi Co-60 III 93' 0.84 pCi Fe-55 112 144 1.29 (4)
September.03 E3900-396 Charcoal Filter pCi 1*131 86 74 0.86 November-03 E3790-396 Milk pCill Sr*89 168 185 1.10 pCill Sr-90 17 19 1.12 J.2S c
MonthIVear
,",1;" *
.... \\'
c;, I November-03.;:
~ :
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ANAL YTICS ENVIRONMENTAL RADIOACl1VITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES i
(Page 4 of 5)
AnalyUa I
I Identification Caltulated THE THFJ Analytlcs No.
Medium Units Nudlde Results Resuits Ratio Milk pCi/1 90 871 0.97 pCi/1 202 186 0.92
- pCi/1; 280 281 1.03 pCi/1 t3S
,119 0.88 pCi/1 129 116 0.90 pCi/1 III III 1.00
, 'pCiI1" 173 17(;
1.02
.t 7 ". ~ **
. pC"JII Fe-S9
" 102 941
'0.92
,". '~: ' (,
,I" pCi/1 197 190
,'0.96 pCi/1 C0-60 ISS 140 0.90 I
",)':.') Ce-14f' r' p,,! E3973-396 ",,'<;:1 :,"APFilter.
pCi',
142 144 1.01 pCI Cr-SI 198 203 1.03 pCi Cs-l34 96 9O!
0.94 pCi" Cs-137 "0,91,,.., '( ','
8Sj
",0.93
.. : {-,,'...-. ;' :~;, : " 0 pCi'
- y Co-S8" ;
78'"
I
' 8O,'
1.03 I
pCI Mn-S4 122 11S 0.94
,pCI Fe-59 72 72:
1.00 Zn-6S pCI
- 139, 121 0.87 k (+
pCI 102 Co-60 pCI Fe-55 November-03 Charcoal Filter pCI' 1-131 109 96 77
',\\,
62:
67:
, i 1
0.94 0.65 (5) 0.87
(
i J-26 MonthIVear November*03
,",1;" *
.... \\'
c;, I November-03.;:
~ :
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TAUa..&lIJ*7 ANAL YTICS ENVIRONMENTAL RADIOACl1VITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES i
(Page 4 of 5)
AnalyUa I
I Identification Caltulated THE THFJ Analytlcs No.
Medium Units Nudlde Results Resuits Ratio E3971*396 Milk pCi/1 1*131 90 871 0.97 pCi/1 Ce-141 202 186 0.92
- pCi/1; Cr*SI 280 281 1.03 pCi/1 Cs-134 t3S
,119 0.88 pCi/1 Cs-137 129 116 0.90 pCi/1 Co-58 III III 1.00
, 'pCiI1" Mn-S4 173 17(;
1.02
.t 7 ". ~ **
. pC"JII Fe-S9
" 102 941
'0.92
,". '~: ' (,
,I" pCi/1 Zn-6S*
197 190
,'0.96 pCi/1 C0-60 ISS 140 0.90 I
",)':.') Ce-14f' r' p,,! E3973-396 ",,'<;:1 :,"APFilter.
pCi',
142 144 1.01 pCI Cr-SI 198 203 1.03 pCi Cs-l34 96 9O!
0.94 pCi" Cs-137 "0,91,,.., '( ','
8Sj
",0.93
.. : {-,,'...-. ;' :~;, : " 0 pCi'
- y Co-S8" ;
78'"
I
' 8O,'
1.03 I
pCI Mn-S4 122 11S 0.94
,pCI Fe-59 72 72:
1.00 Zn-6S pCI
- 139, 121 0.87 k (+
pCI 102 Co-60 pCI Fe-55 November-03 E3972*396 Charcoal Filter pCI' 1-131 109 96 77
',\\,
62:
67:
, i 1
0.94 0.65 (5) 0.87
(
i J-26
ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5)
COMMENTS 1
Incorrectly calculated. The recalculated March & September results of 138 & 95.8 pCUL. respectively, are acceptable.
The efficiency required for these samples is different than the efficiency for regular samples.
NCR 04-02 generated by Teledyne to investigate conditon.
2 Using only the results from'the 1099.2 keY photon, the Fe-59 would ~e 71 pCi. which is acceptab~e. Coincidental summing occurs only with significant Fe-59 activity levels. Therefore, there is no impact on environmental samples.
NCR 04-02 generated by Teledyne to investigate condition.
3 Reprocessed to separate Fe-55 peak. Reprocessed result of 103 total pCi is acceptable. NCR 04-Q2 generated by Teledyne to investigate the condition.
4 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.
5 NCR 04-07 generated by Teledyne to investigate condition. The mylar film (not a filter) from Analytics is not typical of samples received from Teledyne clients. Since the analytics sample was mylar, the laboratory tried to adjust to the new matrix by ashing the filter before analysis.
Analytics thought Teledyne was performing a direct count of the mylar (no preparation or chemical separation).
Teledyne believes that some of the Fe-55 was lost during ashing.
Teledyne has changed their request to Analytics and will now receive glass fiber filters for analysis.
In addition, Teledyne has also verified the validity of their Fe-55 efficiencies by comparing to a standard from a different standards lot.
(~
c J-21 TABLEJ*7 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5)
COMMENTS 1
Incorrectly calculated. The recalculated March & September Sr*89 results of 138 & 95.8 pCUL. respectively, are acceptable.
The efficiency required for these samples is different than the efficiency for regular samples.
NCR 04-02 generated by Teledyne to investigate conditon.
2 Using only the results from'the 1099.2 keY photon, the Fe-59 would ~e 71 pCi. which is acceptab~e. Coincidental summing occurs only with significant Fe-59 activity levels. Therefore, there is no impact on environmental samples.
NCR 04-02 generated by Teledyne to investigate condition.
3 Reprocessed to separate Fe-55 peak. Reprocessed result of 103 total pCi is acceptable. NCR 04-Q2 generated by Teledyne to investigate the condition.
4 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.
5 NCR 04-07 generated by Teledyne to investigate condition. The mylar film (not a filter) from Analytics is not typical of samples received from Teledyne clients. Since the analytics sample was mylar, the laboratory tried to adjust to the new matrix by ashing the filter before analysis.
Analytics thought Teledyne was performing a direct count of the mylar (no preparation or chemical separation).
Teledyne believes that some of the Fe-55 was lost during ashing.
Teledyne has changed their request to Analytics and will now receive glass fiber filters for analysis.
In addition, Teledyne has also verified the validity of their Fe-55 efficiencies by comparing to a standard from a different standards lot.
(~
c J-21
C TA(~J-8
(
\\ :'
PPL REMP LABORATORY SPIKE PROGRAM i ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (page 10f5) 1'-,
i Identlncatlon Analytic!
- TBE, TBFJAnalytlcs MonthIYear No.
Medium Units Nuclide Calculated Results (a)
I Results (a)
Ratio 83573-186 Sediment pCiJkg Ce-141 358 :!: 18 409:!: 17 1.14 "
pCiJkg Cr-SI 508 :!: 25 576 :!: 99 1.13 pcilkg CS-134' 186 :!: 9 180 :!: 9 0.97 pCineg Cs~lj7 497 :!: 2S 598 :!: 19 1.20 pCiJkg Co-58 96:!: S 116 :!: 13 1.21 pCiJkg Mn-54 133 :!: 65 157 :!: 13,
1.18 pCiJkg Pe-S9
'98 :!:5 120 :!: 17 1.22 pCiJkg 192 :!: I 271 :!: 23 1.41, (I) pCiJkg Co-GO 33S:!: 17 408 :!: 13 1.22
. ~.' ",'
83569-186
,~
1~131:
Mille pCiII 75:!: 3
,67.:!:-7,:
0.89; pCiIi Ce~141; 188 +/- 17 188::t: 8, 1.00:
pCin' Cr-SI 26?I':!: 3~
262= 37 0.98:
pCiIi 98:t: S 86 :!: 3, 0.88, pCW Cs-i37' 217 :!: 22 214 :!: 7.
0.99.
pCiti
,. \\ -.
C~~8 51:!: 2 SO :t:4 0.98,'
pCiIi Mn-54 70:!: 3 74 :t: 5 l.O5 pCiII 51 :!: 2 56 :!:6 1.10 pCiII Zn-65 101,:!: S' 110 :t: 9 1.09 pCi/I Co-GO 176 = 16 173 :t: 5 0.98 March-03 83570-186 APFilter pCi 151.:!: 5 153 = 7 1.01 pC(
er-sl 215 :!: 8 241 :!: 38 1.12, pCi CS-134 79::t:3 67 :t:4.
0.84 pCi Cs~137 175 :!: 6 180 = 9 1.03 pCi' C~S8 41 :!: I 4S:!: 6 1.09 pCi:
Mn~54 '
56:!: 2 59.s:t: 7 1.06
.pCL...
_. Pe-59 41:!:
52.9:t: 8
- 1.29 '
(I) pCi.
81 +/- 3 96.3:t: 13 1.19
- i ~,
pCi Co-GO 141 :!:' S 148:!: 7 1.05 i!
~ :: t
/,
.., l' '
I ~.
IT,
~
(.~.~*.~~i (a) Counting error is two standard deviations.
C TA(~J-8
(
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PPL REMP LABORATORY SPIKE PROGRAM i ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (page 10f5) 1'-,
i Identlncatlon Analytic!
- TBE, TBFJAnalytlcs MonthIYear No.
Medium Units Nuclide Calculated Results (a)
I Results (a)
Ratio Marcb*03 83573-186 Sediment pCiJkg Ce-141 358 :!: 18 409:!: 17 1.14 "
pCiJkg Cr-SI 508 :!: 25 576 :!: 99 1.13 pcilkg CS-134' 186 :!: 9 180 :!: 9 0.97 pCineg Cs~lj7 497 :!: 2S 598 :!: 19 1.20 pCiJkg Co-58 96:!: S 116 :!: 13 1.21 pCiJkg Mn-54 133 :!: 65 157 :!: 13,
1.18 pCiJkg Pe-S9
'98 :!:5 120 :!: 17 1.22 pCiJkg Zn*65 192 :!: I 271 :!: 23 1.41, (I) pCiJkg Co-GO 33S:!: 17 408 :!: 13 1.22
. ~.' ",'
March*03 83569-186
,~
1~131:
Mille pCiII 75:!: 3
,67.:!:-7,:
0.89; pCiIi Ce~141; 188 +/- 17 188::t: 8, 1.00:
pCin' Cr-SI 26?I':!: 3~
262= 37 0.98:
pCiIi Cs*134' 98:t: S 86 :!: 3, 0.88, pCW Cs-i37' 217 :!: 22 214 :!: 7.
0.99.
pCiti
,. \\ -.
C~~8 51:!: 2 SO :t:4 0.98,'
pCiIi Mn-54 70:!: 3 74 :t: 5 l.O5 pCiII Pe*59 51 :!: 2 56 :!:6 1.10 pCiII Zn-65 101,:!: S' 110 :t: 9 1.09 pCi/I Co-GO 176 = 16 173 :t: 5 0.98 March-03 83570-186 APFilter pCi Ce*141 151.:!: 5 153 = 7 1.01 pC(
er-sl 215 :!: 8 241 :!: 38 1.12, pCi CS-134 79::t:3 67 :t:4.
0.84 pCi Cs~137 175 :!: 6 180 = 9 1.03 pCi' C~S8 41 :!: I 4S:!: 6 1.09 pCi:
Mn~54 '
56:!: 2 59.s:t: 7 1.06
.pCL...
_. Pe-59 41:!: I*
52.9:t: 8
- 1.29 '
(I) pCi.
Zn*6S 81 +/- 3 96.3:t: 13 1.19
- i ~,
pCi Co-GO 141 :!:' S 148:!: 7 1.05 i!
J*28
~ :: t
/,
.., l' '
I ~.
IT,
~
(.~.~*.~~i (a) Counting error is two standard deviations.
PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHEC~ PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 5)
IdentificaUon Aoalytics TDE TDFJ AoalyUcs MonlblYear No.
Medium Units Nuclide Calculated Results (_)
Results (II)
Ratio AP Filter pCi 156 +/- 5 170 +/- 8 1.09 pCi 221 +/- 8 255 +/- 46 US pCi 81 +/- 3 65.3 +/-.5 0.81 pCi 180 +/- 6 187 +/- 9 1.04 pCi 42 +/- 1 39.5 +/- 8 0.94 pCi 58 +/- 2 59.1 +/- 7 1.02 pCi 43 +/- 2 51 +/- 9 1.19 pCi 84+/- 3 110 +/- 13 1.31 (I) pCi 146 +/- 5 148 +/- 1 1.01 AP Filter pCi 182 +/- 6 IBO +/- 1 0.99 pCi 259 +/- 9 240+/- 40 0.93 pCi 9S +/- 3 76.3 +/- 4 0.80 pCi 211 :t 7 217 +/- 9 1.03 pCi 49 +/- 2 SIS:t 7 1.05 pCi 68:t 2 75.5 +/- 7 1.11 pCi 50:t 2 60.3:t 9 1.21 pCi 98 +/- 3 IIS:t 14 1.17 pCi 170:t 6 173:t,7 1.02 Water pCiIL 4463:t 230 4840:t 176 1.08 AP Filter pCi 152 +/- 5 157:t 17 1.03 pq 128:t 4 142 +/- 102 1.11 pCi 55 +/- 2 58.3 +/- 8 1.06 pCi 123 :t 4 147 +/- 14 1.20 pCi 50 +/- 2 46.5:t 14 0.93 pCi 99:t 3 105:t 14 1.06 pCi 53 +/- 2 63 +/- 19 1.19 pCi 97:t 3 IIS:t 18 1.19 pCi 71 :t 2 87.9:t 10 1.24 (a) Counting error is two standard deviations.
C.
TABLEJ*8 PPL REMP LABORATORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHEC~ PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 5)
IdentificaUon Aoalytics TDE TDFJ AoalyUcs MonlblYear No.
Medium Units Nuclide Calculated Results (_)
Results (II)
Ratio March*03 El571*IB6 AP Filter pCi Cc-141 156 +/- 5 170 +/- 8 1.09 pCi Cr*51 221 +/- 8 255 +/- 46 US pCi Cs*134 81 +/- 3 65.3 +/-.5 0.81 pCi Cs-137 180 +/- 6 187 +/- 9 1.04 pCi Co-58 42 +/- 1 39.5 +/- 8 0.94 pCi Mn*S4 58 +/- 2 59.1 +/- 7 1.02 pCi Fe-59 43 +/- 2 51 +/- 9 1.19 pCi Zn*65 84+/- 3 110 +/- 13 1.31 (I) pCi Co-60 146 +/- 5 148 +/- 1 1.01 March*03 E3572*186 AP Filter pCi Ce*141 182 +/- 6 IBO +/- 1 0.99 pCi Cr*51 259 +/- 9 240+/- 40 0.93 pCi Cs*134 9S +/- 3 76.3 +/- 4 0.80 pCi Cs*137 211 :t 7 217 +/- 9 1.03 pCi Co-58 49 +/- 2 SIS:t 7 1.05 pCi Mn*S4 68:t 2 75.5 +/- 7 1.11 pCi Fe*59 50:t 2 60.3:t 9 1.21 pCi Zn*65 98 +/- 3 IIS:t 14 1.17 pCi Co-6O 170:t 6 173:t,7 1.02 March*03 El574*186 Water pCiIL H*3 4463:t 230 4840:t 176 1.08 June*03 El776*186 AP Filter pCi Ce*141 152 +/- 5 157:t 17 1.03 pq Cr-SI 128:t 4 142 +/- 102 1.11 pCi Cs-134 55 +/- 2 58.3 +/- 8 1.06 pCi Cs-137 123 :t 4 147 +/- 14 1.20 pCi CO-58 50 +/- 2 46.5:t 14 0.93 pCi Mn*54 99:t 3 105:t 14 1.06 pCi Fe*59 53 +/- 2 63 +/- 19 1.19 pCi Zn-65 97:t 3 IIS:t 18 1.19 pCi Co-60 71 :t 2 87.9:t 10 1.24 J*29 (a) Counting error is two standard deviations.
C.
(
TAl.. J-8
(
PPL REMP LADORA TORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE DROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of5)
IdenUntation AnalyUcs TBE TBFJAnalytlcs MonthIVear No.
Medlom Unlts Nuclide Calc:uJated ResultS (a)
Results (a)
Ratio June-03 E3777A-186 AP Filter pCi 238:!: 8 267:!: 20 1.12 pCi 201 :!: 7 176:!: 112 0.88 pCi 87:!: 3 91 :!: 8 1.05 pCi 194 % 7 219 % 17 1.13 pCi 78:!: 3 84.3:!: 13 1.08 pCi 156 % 5 172:!: 17 1.10 pCi 83:!: 3 107 % 20 1.29 (1) pCi IS3:!: 5 179:!: 23 1.17 pCi III % 4 127:!: II 1.14
. "I:'
~. I c.',. : ~
E3778A.i86 APFilter pCi 140:!: 5 I
128 % 20 0.91 122'%; 89
",t"
- T" -~', :..,;.,'
- pCi, 118 £4:
'I 1.03' pCi 51:!: 2 i
53.7:!: 6 1.05, pCi 1t4 % '4' 1
112~'12 0.98
,~' ':
pCi 46:!: 2 3S:!: 10 0.76 96.2 :~/I'I 92:!:3
'LOS' 49:!: 2 42.4:!: 18 0:87, 89:!:'3 74.1 % 18 0.83, 65% 2 69.6:!: 7 1.07 E3779-186 Charcoal Filter pCi 73.9:!: 3 l.12 E3780-186 Charcoal Filter pCi 59:!: 2 68.6% 3 1.16 Charcoal Filter.
pCi' 51 %2 61.6:!: 4 1.21
. /'
~,t (a) Counting error is two standard deviations.
(
TAl.. J-8
(
PPL REMP LADORA TORY SPIKE PROGRAM ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE DROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of5)
IdenUntation AnalyUcs TBE TBFJAnalytlcs MonthIVear No.
Medlom Unlts Nuclide Calc:uJated ResultS (a)
Results (a)
Ratio June-03 E3777A-186 AP Filter pCi Ce-141, 238:!: 8 267:!: 20 1.12 pCi er*51 201 :!: 7 176:!: 112 0.88 pCi Cs*134 87:!: 3 91 :!: 8 1.05 pCi Cs-137 194 % 7 219 % 17 1.13 pCi Co-58 78:!: 3 84.3:!: 13 1.08 pCi Mn-S4 156 % 5 172:!: 17 1.10 pCi Fe*S9 83:!: 3 107 % 20 1.29 (1) pCi Zn*65 IS3:!: 5 179:!: 23 1.17 pCi Co-60 III % 4 127:!: II 1.14
. "I:'
~. I c.',. : ~
June*03 '
E3778A.i86 APFilter pCi Q-141 140:!: 5 I
128 % 20 0.91 122'%; 89
",t"
- T" -~', :..,;.,'
- pCi, Cr-Sl:
118 £4:
'I 1.03' pCi Cs-134 51:!: 2 i
53.7:!: 6 1.05, pCi Cs*137 1t4 % '4' 1
112~'12 0.98
,~.
,~' ':
pCi Co-58 46:!: 2 3S:!: 10 0.76 96.2 :~/I'I pCL*
Mn-S4 92:!:3
'LOS' pCi Fe-59 49:!: 2 42.4:!: 18 0:87,
- pCL, Zn-65 89:!:'3 74.1 % 18 0.83, pCi:
Co-60 65% 2 69.6:!: 7 1.07 June-03 E3779-186 Charcoal Filter pCi 1*131 66:!: 2;*
73.9:!: 3 l.12 June-03 E3780-186 Charcoal Filter pCi I-131 59:!: 2 68.6% 3 1.16 June*03 E3781*186 Charcoal Filter.
pCi' 1*131 '
51 %2 61.6:!: 4 1.21
. /'
~,t J*30 (a) Counting error is two standard deviations.
PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOAcnvITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL ~ERVICES (Page 4 of5)
IdenUfication AnalyUcs THE TBFJ Analytics MontblYear No.
Medium Units Nuclide Calculated Results (a)
Results (a)
Ratio Milk pCiIl 75:t: 2 65.9 +/- 8 0.88 pCill 188 +/- 11 171 +/- 11 0.91 pCiIl 510 +/- 87 429 +/- 48 0.84 pCiIl 261 +/- 23 212 +/- 5 O.SI pCiIl 193 +/- 12 181+/- 8 0.94 pCiIl 216 +/- IS 197 +/- 8 0.91 pCi/l 203 +/- 14 202+/- 9 1.00 pCi/I 173 +/- 10 177 +/- IO 1.02 pCill 385 +/- SO 368 +/- 16 0.96 pCi/l 270 +/- 24 264 +/- 7 0.98 Water pCill SOOO+/- 300 8240 +/- 222 1.03 Charcoal Filter pCi 77 +/-. 3 83 +/- 3 1.07 Charcoal Filter pCi 68 +/- 2 73 +/- 2 1.07 Charcoal Filter pCi 86+/- 3 92:t 5 1.07 (a) Counting error is two standard deviations.
(:
TABLEJ*8 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOAcnvITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL ~ERVICES (Page 4 of5)
IdenUfication AnalyUcs THE TBFJ Analytics MontblYear No.
Medium Units Nuclide Calculated Results (a)
Results (a)
Ratio September-03 E3889*186 Milk pCiIl 1-131 75:t: 2 65.9 +/- 8 0.88 pCill Ce*141 188 +/- 11 171 +/- 11 0.91 pCiIl Cr-51 510 +/- 87 429 +/- 48 0.84 pCiIl Cs-I34 261 +/- 23 212 +/- 5 O.SI pCiIl Cs*137 193 +/- 12 181+/- 8 0.94 pCiIl Co-58 216 +/- IS 197 +/- 8 0.91 pCi/l Mn-54 203 +/- 14 202+/- 9 1.00 pCi/I Fe*59 173 +/- 10 177 +/- IO 1.02 pCill Zn*6S 385 +/- SO 368 +/- 16 0.96 pCi/l Co-60 270 +/- 24 264 +/- 7 0.98 September*03 E3890*186 Water pCill H-3 SOOO+/- 300 8240 +/- 222 1.03 December-Ol E3981*186 Charcoal Filter pCi l*ll1 77 +/-. 3 83 +/- 3 1.07 December*03 E3982*186 Charcoal Filter pCi 1*131 68 +/- 2 73 +/- 2 1.07 December-03 E398l*186 Charcoal Filter pCi 1*131 86+/- 3 92:t 5 1.07
)*31 (a) Counting error is two standard deviations.
(:
('
TABLEJ-8 PPL REMP LABORATORY SPIKE PROGRAMi I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2Q03 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5)
COMMENTS 1
High Bias identified. Evaluation of results requested by PPL via email on April 19, 2004.
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to
~
I
- I"t t !, '/",",
(
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TABLEJ-8 PPL REMP LABORATORY SPIKE PROGRAMi I
ANAL YTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2Q03 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5)
COMMENTS 1
High Bias identified. Evaluation of results requested by PPL via email on April 19, 2004.
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to
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I
- I"t t !, '/",",
j
" I
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I',
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i '
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J*32
TABLEJ-9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL S;ERVICES (Page 1 of 4)
I Identification EMLKnown THE TBEJEML MonthlYear No.
Medium Units Nuclide Result Results Ratio QAP-S8 AP Filter Bq 0.34 0.~4 1.00 Bq 33.S 35:9 1.01 Bq 99.1 lQ.1 1.14 Bq 1.2 0.9 0.73 (I)
I Bq 2
1.6 1.01 Bq 43.8 49.4 1.13 Bq 0.52 0.59 1.13 Bq 0.3 I
0.4 1.06 8q 2.8 2.4 0.86 QAP-58 Soil Bqlkg 57 70 1.23 (4)
Bqlkg 16 16 0.99 Bqlkg 61 73 1.20 (4)
Bqlkg 67 76 1.14 Bqlkg 1450 1883 1.30 (2) 8q1kg 636 80,6 1.27 (4)
Bqlkg 58 75 l.29 (4)
Bqlkg 71 79 1.11 Bqlkg 23 2S 1.09 Bqlkg 64 5t 0.83 8q1kg 127 169 1.33 March-03 QAP-S8 Vegetation Bqlkg 12 It 1.19 Bqlkg 444 522 1.18 Bqlkg 1120 1360 1.21 Bqlkg 650 498 0.77 TABLEJ-9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL S;ERVICES (Page 1 of 4)
I Identification EMLKnown THE TBEJEML MonthlYear No.
Medium Units Nuclide Result Results Ratio March*03 QAP-S8 AP Filter Bq Am*24 1 0.34 0.~4 1.00 Bq Co-60 33.S 35:9 1.01 Bq Cs*131 99.1 lQ.1 1.14 Bq Or-Alpha 1.2 0.9 0.73 (I)
I Bq Or-Beta 2
1.6 1.01 Bq Mn-54 43.8 49.4 1.13 Bq Pu*238 0.52 0.59 1.13 Bq Pu*239 0.3 I
0.4 1.06 8q Sr-90 2.8 2.4 0.86 March*OJ QAP-58 Soil Bqlkg Ac-228 57 70 1.23 (4)
Bqlkg Am-241 16 16 0.99 Bqlkg Bi*212 61 73 1.20 (4)
Bqlkg Bi*214 67 76 1.14 Bqlkg Cs-137 1450 1883 1.30 (2) 8q1kg K-40 636 80,6 1.27 (4)
Bqlkg Ph-212 58 75 l.29 (4)
Bqlkg Pb*214 71 79 1.11 Bqlkg Pu*239 23 2S 1.09 Bqlkg Sr-90 64 5t 0.83 8q1kg Th-234 127 169 1.33 March-03 QAP-S8 Vegetation Bqlkg Co-60 12 It 1.19 Bqlkg Cs-1"37 444 522 1.18 Bqlkg K-40 1120 1360 1.21 Bqlkg Sr-90 650 498 0.77 J*33
c
(
(
TABL~J*9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of4)
I IdenllflcntJon EMLKnown TBE TBFJEML MonthlYear No.
Medium Units Nuclide Result Reshlts Ratio Marcb-03 Water BqIl 2.13 i
2.4 1.13 BqIl 234 252 1.08 BqIl 31 31 1.02 '
BqIl 64 72 1.12 BqIl 378 484 1.28 (4)
BqIl 628 821 1.31 '
(4)
- BqIl, 390 418.
1.07,
BqIl 3.3 4:0 1.20, I
BqIl 3.9 4.6 1.16 BqII.
4.3, 3.6, 0,,84;.
~ 'I"r~'ir_""~.",,
~.. ~
~-, \\~
J.'
f,:
58' Sq,teinbei.03.
QAP59 APFilter Bq 4
0.93 Bq "
5S.l,
53.3, 0.97.
Sq,,,:
2.1 :
1:7.
Bq~
S4.8 si.2.
0.93",
Bq 0.4 0.4 0.92 B,q 0.2 0.2 1.00.,
Bq 0.4 0.4 0.93 Bq 0.4 0.4 1.00 Bq,
0.4 0.4 0.90 Bq 3.1 3.1 1.00 Bq 3.9 3.4 0.87
- 1"-
- l. *
.' j.'
\\.'.
~., { :
c
(
(
TABL~J*9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP)
I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of4)
I IdenllflcntJon EMLKnown TBE TBFJEML MonthlYear No.
Medium Units Nuclide Result Reshlts Ratio Marcb-03 QAP*58 Water BqIl Am-24 I 2.13 i
2.4 1.13 BqIl Co-60 234 252 1.08 BqIl Cs.134,
31 31 1.02 '
BqIl Cs.137 64 72 1.12 BqIl Or*Alpha 378 484 1.28 (4)
BqIl Or-Beta '
628 821 1.31 '
(4)
- BqIl, H*3, 390 418.
1.07,
BqIl Pu~238.
3.3 4:0 1.20, (3)
I BqIl Pu*239 3.9 4.6 1.16 BqII.
Sr-90 4.3, 3.6, 0,,84;.
~ 'I"r~'ir_""~.",,
~.. ~
~-, \\~
.;. J J.'
f,:
58' Sq,teinbei.03.
QAP59 APFilter Bq Mn*S4 4
0.93 Bq "
Co-60 J 5S.l,
53.3, 0.97.
Sq,,,:
Sr-gO,'.
2.1 :
1:7.
0.81*
Bq~
Cs*137,
S4.8 si.2.
0.93",
Bq U.234.
0.4 0.4 0.92 B,q Pii*238 0.2 0.2 1.00.,
Bq U-238 0.4 0.4 0.93 Bq Pu*239 0.4 0.4 1.00 Bq,
Am-241 0.4 0.4 0.90 Bq Or-Alpha 3.1 3.1 1.00 Bq Or-Beta 3.9 3.4 0.87 J*34
- 1"-
- l. *
.' j.'
\\.'.
~., { :
DOE - ENVIRONMENTAL MEASUREMENTS LABORATO~Y (EML)
QUAUTY ASSESSMENT PROGRAM (QAP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of4)
Identification EMLKnowD TOE TBElEML MonthlYear No.
Medium Units Nuclide Result Resiaits Ratio Soil Bqlkg 488 511 1.06 Bqlkg 80 10 0.81 Bqlkg 1973 2127 1.08 Bqlkg S4 56 1.04 Bqlkg 51 5~
1.04 Bqlkg 34 36 1.06 Bqlkg 3S 4~
1.18 Bqlkg 51 5~
1.11 Bqlkg 116 145 1.2S Bqlkg 127 1~5 0.91 B.qlkg IS 1~
0.92 Bqlkg 127.1 q4 0.90 Bqlkg 30.4 28.3 0.93 Bqlkg 18.4 16.S 0.90 Water BqI1 446 511 1.14 BqI1 513 4~1 0.96 BqI1 7
~
0.84 BqI1 63 62 0.99 8q11 80 7~
0.93 BqI1 2.79 2~7 0.97 BqI1 2.07 2.2 1.06 Bqll 2.8 2.6 0.93 Bqll 4.99 5.4 J.08 8q11 8.76 9~2 1.05 BqI1 622 612 0.98 8q11 1948 1663 0.85 TABLEJ*9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATO~Y (EML)
QUAUTY ASSESSMENT PROGRAM (QAP)
TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of4)
Identification EMLKnowD TOE TBElEML MonthlYear No.
Medium Units Nuclide Result Resiaits Ratio September-03 QAP59 Soil Bqlkg K-40 488 511 1.06 Bqlkg Sf-90 80 10 0.81 Bqlkg Cs*137 1973 2127 1.08 Bqlkg Hi-212 S4 56 1.04 Bqlkg Pb-212 51 5~
1.04 Bqlkg Bi-214 34 36 1.06 Bqlkg Pb-214 3S 4~
1.18 Bqlkg Ac-228 51 5~
1.11 Bqlkg Th*234 116 145 1.2S Bqlkg U-234 127 1~5 0.91 B.qlkg Pu-238 IS 1~
0.92 Bqlkg U*238 127.1 q4 0.90 Bqlkg Pu*239 30.4 28.3 0.93 Bqlkg Am*241 18.4 16.S 0.90 September.03 QAP59 Water BqI1 H*3 446 511 1.14 BqI1 Co-60 513 4~1 0.96 BqI1 Sr-90 7
~
0.84 BqI1 Cs*134 63 62 0.99 8q11 Cs*137 80 7~
0.93 BqI1 U-234 2.79 2~7 0.97 BqI1 Pu*238 2.07 2.2 1.06 Bqll U*238 2.8 2.6 0.93 Bqll Pu*239 4.99 5.4 J.08 8q11 Am-241 8.76 9~2 1.05 BqI1 Or-Alpha 622 612 0.98 8q11 Or*Beta 1948 1663 0.85 J*35
c 1
2 3
4 I
TABCu J-9 I
ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP) I TELEDYNE BROWN ENGINEERING ENVIRONMENT ALSERVICES (page 4 of 4)
I I
I I
'I I
COMMENTS' I
I Gas flow Proportional efficienci~s are established using Am-241, industry standard for clieni samples.'
I EML requires an efficiency based on Th-230., : Using Th-230 efficiency t the result of 1.18 is acceptable.
NCR 03"()7 generated by Teledyne ~o investigate condition. ", '
, I
~,
'I
. 'i:
Incorrect bottle size used. Sample was placed into a smaller container and recounted. All recount results were acceptable
~
\\
I except Bi:-212 which was acceptable with warning. Previously analyzed samples were examined and no other incorrect container sizes ~Jrei rioted. NCR 03"()7 generated by Tel~dyne to inv~stigate condition.
- ~....
1; * "
~
~
- ' \\
- f t
The electroplating cell was determined to have trace amounts of plutonium, causing an elevated activity.,The electroplating cell has been taken out of service. ""
':l
- 1 Acceptable with warning. Reported result falls within 0.70~,.80 or 1.20-1.30.
i
-I I, I i
i i
i !
I I I
I
'f
- 1,
'if' I
I i
I I
c c
1 2
3 4
I TABCu J-9 I
DOE* ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)
QUALITY ASSESSMENT PROGRAM (QAP) I TELEDYNE BROWN ENGINEERING ENVIRONMENT ALSERVICES (page 4 of 4)
I I
I I
'I I
COMMENTS' I
I Gas flow Proportional efficienci~s are established using Am-241, industry standard for clieni samples.'
I EML requires an efficiency based on Th-230., : Using Th-230 efficiency t the result of 1.18 is acceptable.
NCR 03"()7 generated by Teledyne ~o investigate condition. ", '
, I
~,
'I
. 'i:
Incorrect bottle size used. Sample was placed into a smaller container and recounted. All recount results were acceptable
~
\\
I except Bi:-212 which was acceptable with warning. Previously analyzed samples were examined and no other incorrect container sizes ~Jrei rioted. NCR 03"()7 generated by Tel~dyne to inv~stigate condition.
- ~....
1; * "
~
~
- ' \\
- f t
,. r**, :.
The electroplating cell was determined to have trace amounts of plutonium, causing an elevated activity.,The electroplating cell has been taken out of service. ""
':l
- 1 Acceptable with warning. Reported result falls within 0.70~,.80 or 1.20-1.30.
i
-I I, I i
i i
i !
I I I
I
'f
- 1,
'if' I
I i
I I
c J*36
\\
TABLEJ-1O DOE-MAPEP MIXED ANAL YTE PERFORMANCE EVALUATION PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)
(Page lof2)
Identification MAPEPKnown THE TBEIMAPEP No.
Medium Units NucUde Result Results Ratio Evaluation 02-WlO Water pCi/I 0.578 0.61 1.06 Agreement pCi/I 421 382.7 0.91 Agreement pCi/I 329 329.3 1.00 Agreement pCiIJ 57 58.17 1.02 Agreement pCi/I 38.2 41.2 1.08 Agreemcot pCi/I 96 97.7 1.02 Agreement pCi/I 32.9 35.01 1.01 Agreement pCiIJ 136.5 151.3 1.11 Agreement pCi/I 0.83 0.91 1.10 Agreement pCi/I 12.31 11.70 0.95 Agreement pCi/I 132 84.00 0.64 Low Bias (I) pCi/I 1.54 1.49 0.97 Agreement.
pCi/I 1.6 1.61 1.01 Agreement pCi/I 516 566 1.10 Agreement 03-S10 Soil pCilkg 238 204 0.86 Agreement pCilkg 832 803.
0.91 Agreement pCilkg 530 499 0.94 Agreement pCilkg 420.
427 1.02 Agreement pCilkg 1020 892 0.87 Agreement pCilkg 137 136.
0.99 Agreement pCilkg 770 803 1.04 Agreement
. pCilkg 66.9 69 1.03 Agreement pCi/kg 52.7 51.7 1.09 Agreement pCilkg 652 686 1.05 Agreement pCilkg 714 651 0.91 Agreement pCilkg 89 70.2 0.79 Agreement (2) pCilkg 421 394 0.94 Agreement pCilkg 490 528 1.08 Agreement c
c
\\
TABLEJ-1O DOE-MAPEP MIXED ANAL YTE PERFORMANCE EVALUATION PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)
(Page lof2)
Identification MAPEPKnown THE TBEIMAPEP No.
Medium Units NucUde Result Results Ratio Evaluation 02-WlO Water pCi/I Am*24 I 0.578 0.61 1.06 Agreement pCi/I Cs*134 421 382.7 0.91 Agreement pCi/I Cs*137 329 329.3 1.00 Agreement pCiIJ Co-S1 57 58.17 1.02 Agreement pCi/I Co-60 38.2 41.2 1.08 Agreemcot pCi/I Fe-55 96 97.7 1.02 Agreement pCi/I Mn-S4 32.9 35.01 1.01 Agreement pCiIJ Ni-63 136.5 151.3 1.11 Agreement pCi/I Pu*238 0.83 0.91 1.10 Agreement pCi/I Sr-9O 12.31 11.70 0.95 Agreement pCi/I Tc-99 132 84.00 0.64 Low Bias (I) pCi/I U-2341233 1.54 1.49 0.97 Agreement.
pCi/I U-238 1.6 1.61 1.01 Agreement pCi/I Zn*65 516 566 1.10 Agreement 03-S10 Soil pCilkg Cs-134 238 204 0.86 Agreement pCilkg Cs*137 832 803.
0.91 Agreement pCilkg CooS7 530 499 0.94 Agreement pCilkg Co-60 420.
427 1.02 Agreement pCilkg fe.55 1020 892 0.87 Agreement pCilkg Mn-54 137 136.
0.99 Agreement pCilkg Ni-63 770 803 1.04 Agreement
. pCilkg Pu-238 66.9 69 1.03 Agreement pCi/kg Pu-239f240 52.7 51.7 1.09 Agreement pCilkg K-40 652 686 1.05 Agreement pCilkg Sr*9O 714 651 0.91 Agreement pCilkg U-2341233 89 70.2 0.79 Agreement (2) pCilkg U-238 421 394 0.94 Agreement pCilkg Zn-65 490 528 1.08 Agreement J*37 c
c
(
TABCJ-IO DOE-MAPEP i
MIXED ANAL YTE PERFORMANCE EV ALUA TION PRbGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SE~VICES (TBE)
(page 2 of 2) l COMMENTS 1
Teledyne lab technician read the pipette incorrectly. delivering a 20 mt aliquot rather than th~ 30 mt aliquot used to calculate the result. The re-analyzed Tc-99 result of 127 Bq/L is acceptable.
NCR 03-05 generated by Teledyne to document/investigate the event.
2 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.
(
TABCJ-IO DOE-MAPEP i
MIXED ANAL YTE PERFORMANCE EV ALUA TION PRbGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SE~VICES (TBE)
(page 2 of 2) l COMMENTS 1
Teledyne lab technician read the pipette incorrectly. delivering a 20 mt aliquot rather than th~ 30 mt aliquot used to calculate the result. The re-analyzed Tc-99 result of 127 Bq/L is acceptable.
NCR 03-05 generated by Teledyne to document/investigate the event.
2 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.
J*38