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{{#Wiki_filter:Committed to Nuclear Excellence~r" Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
{{#Wiki_filter:Committed to Nuclear Excellence~r" Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
* Welch MN 55089 May 15, 2001 Prairie Island Technical Specifications 6.6.B US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 72-10 SNM-2506 2000 Annual Radiological Environmental Monitoring Report In accordance with the Prairie Island Nuclear Generating Plant Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, and in accordance with the Prairie Island Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License DNM-2506, we are submitting one copy of the Annual Radiological Environmental Monitoring Report covering the period January 1, 2000 through December 31, 2000. Please contact us if you have any questions related to the information we have provided.
* Welch MN 55089 May 15, 2001                                                               Prairie Island Technical Specifications 6.6.B US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306                       DPR-60 72-10                       SNM-2506 2000 Annual Radiological Environmental Monitoring Report In accordance with the Prairie Island Nuclear Generating Plant Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, and in accordance with the Prairie Island Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License DNM-2506, we are submitting one copy of the Annual Radiological Environmental Monitoring Report covering the period January 1, 2000 through December 31, 2000.
J T'oel P. Sorensen Site Vice President Prairie Island Nuclear Generating Plant c: Regional Administrator, III, NRC Region III Attn: Dr. John House NRC Project Manager Director of NMSS Sr. Resident Inspector, NRC State of Minnesota Attn: Tim Donakowski J. Silberg  
Please contact us if you have any questions related to the information we have provided.
J T'oel P. Sorensen Site Vice President Prairie Island Nuclear Generating Plant c:       Regional Administrator, III, NRC Region III Attn: Dr. John House NRC Project Manager Director of NMSS Sr. Resident Inspector, NRC State of Minnesota Attn: Tim Donakowski J. Silberg


==Attachment:==
==Attachment:==
Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1, 2000 through December 31, 2000.


Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1, 2000 through December 31, 2000.
-- *:    Environmental, Inc.
-- Environmental, Inc. Midwest Laboratory 11" an Alleheny Technologies Co. 700 Landwehr Road -Noffý IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2000 Prepared under Contract by ENVIRONMENTAL, Inc. MIDWEST LABORATORY Project No. 8010 Approved: 3b, M.S. Manager Oec.-7ýjoe PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Nuclear Management Company, LLC for Xcel Energy Corporation.
Midwest Laboratory 11"   an Alleheny Technologies Co.
The report was prepared by Environmental, Inc., Midwest Laboratory.
700 Landwehr Road -Noffý IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306                 DPR-60 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2000 Prepared under Contract by ENVIRONMENTAL, Inc.
ii TABLE OF CONTENTS Section Page Preface ..................................................................................................................................
MIDWEST LABORATORY Project No. 8010 Approved:
ii List of Tables .......................................................................................................................
3b, M.S.
iv List of Figures ........................................................................................................................
Manager Oec.-7ýjoe
v  
 
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Nuclear Management Company, LLC for Xcel Energy Corporation. The report was prepared by Environmental, Inc., Midwest Laboratory.
ii
 
TABLE OF CONTENTS Section                                                                                                                                           Page Preface .................................................................................................................................. ii List of Tables .......................................................................................................................       iv List of Figures ........................................................................................................................     v


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
............................................................................... 1 2.0 SUMM ARY ......................................................................................................................                2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ......................... 3 3.1  Program Design and Data Interpretation .................................................................                                3 3.2  Program Description ..............................................................................................                      4 3.3  Program Execution ..............................................................................................                        5 3.4  Laboratory Procedures .............................................................................................                    6 3.5  Program M odifications .............................................................................................                    6 3.6  Land Use Census ...........................................................................................................            6 4.0 RESULTS AND DISCUSSION ..........................................................................................                              7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ........................................ 7 4.2 Summ ary of Preoperational Data ..............................................................................                          7 4.3 Program Findings .................................................................................................                      8 5.0 FIGURES AND TABLES .....................................................................................................                      12


...............................................................................
==6.0 REFERENCES==
1 2.0 SUM M ARY ......................................................................................................................
CITED .........................................................................................................                   25 APPENDICES A    Interlaboratory Comparison Program Results ...............................................................                                 A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Samples ...............................................                                 A-2 B    Data Reporting Conventions ........................................................................................                       B -1 C    Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas .......................................................                                   C-1 D    Sampling Location M aps ..............................................................................................                     D-1 iii
2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) .........................
3 3.1 Program Design and Data Interpretation
.................................................................
3 3.2 Program Description
..............................................................................................
4 3.3 Program Execution
..............................................................................................
5 3.4 Laboratory Procedures
.............................................................................................
6 3.5 Program M odifications
.............................................................................................
6 3.6 Land Use Census ...........................................................................................................
6 4.0 RESULTS AND DISCUSSION
..........................................................................................
7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents
........................................
7 4.2 Summ ary of Preoperational Data ..............................................................................
7 4.3 Program Findings .................................................................................................
8 5.0 FIGURES AND TABLES .....................................................................................................
12


==6.0 REFERENCES==
LIST OF TABLES No.                                                                  Title                                                                Page 5.1  Sample Collection and Analysis Program ............................................................................                  13 5.2  Sampling Locations ................................................................................................................ 14 5.3  Missed Collections and Analyses ........................................................................................              17 5.4  Radiation Environmental Monitoring Program Summary .................................................. 20 In addition, the following tables are in the Appendices:
Appendix A A-1  U.S. Environmental Protection Agency's Crosscheck Program results ................................                                  Al-i A-2 Crosscheck Program Results; (TLDs) ..................................................................................                A2-1 A-3 In-house "Spiked" Samples ............................................................................................                A3-1 A-4 In-house "Blank" Samples ..................................................................................................          A4-1 A-5 In-house "Duplicate" Samples ...........................................................................................              A5-1 A-6 Department of Energy MAPEP comparison results .........................................................                              A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results ...........................................................................................              A7-1 Appendix C C-1  Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ..................................................................                   C-2 iv


CITED .........................................................................................................
LIST OF FIGURES No.                                                     Title                                                                 Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control, 1985-2000 ................................................................................... 18 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i), 1985-2000 ........................................                   19 v
25 APPENDICES A Interlaboratory Comparison Program Results ...............................................................
A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Samples ...............................................
A-2 B Data Reporting Conventions
........................................................................................
B -1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas .......................................................
C-1 D Sampling Location M aps ..............................................................................................
D-1 iii LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ............................................................................
13 5.2 Sampling Locations
................................................................................................................
14 5.3 Missed Collections and Analyses ........................................................................................
17 5.4 Radiation Environmental Monitoring Program Summary ..................................................
20 In addition, the following tables are in the Appendices:
Appendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results ................................
Al-i A-2 Crosscheck Program Results; (TLDs) ..................................................................................
A2-1 A-3 In-house "Spiked" Samples ............................................................................................
A3-1 A-4 In-house "Blank" Samples ..................................................................................................
A4-1 A-5 In-house "Duplicate" Samples ...........................................................................................
A5-1 A-6 Department of Energy MAPEP comparison results .........................................................
A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results ...........................................................................................
A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ..................................................................
C-2 iv LIST OF FIGURES No. Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control, 1985-2000  
...................................................................................
18 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i), 1985-2000  
........................................
19 v  


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January December, 2000. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January December, 2000. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included in this report. These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2001b) available at Prairie Island Nuclear Generating Plant. Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors.
Tabulations of the individual analyses made during the year are not included in this report. These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2001b) available at Prairie Island Nuclear Generating Plant.
Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.1 2.0  
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974.
Commercial operation at full power began on 21 December 1974.
1
 
2.0  


==SUMMARY==
==SUMMARY==
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.
Results for 2000 are summarized and discussed.
Results for 2000 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.
For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs). Sources of environmental radiation include the following:
2
(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.
 
3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1)   Natural background radiation arising from cosmic rays and primordial radionuclides; (2)   Fallout from atmospheric nuclear detonations; (3)   Releases from nuclear power plants; (4)   Industrial and medical radioactive waste; and (5)   Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream).
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.
The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese 54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation 3
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131.
 
Most samples are also analyzed for gamma emitting isotopes with results for the following groups quantified:
3.1   Program Design and Data Interpretation (continued) of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40.
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g.,
The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.
atmospheric nuclear detonations.
Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.
3.2   Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2000).
On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.
Maps of fixed sampling locations are included in Appendix E.
The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine 131. A quarterly composite of the particulate filters from each location is gamma-scanned on an HPGe detector. One of the five locations is a control (P-l), and four are indicators (P 2, P-3, P-4, and P-6).
These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese 54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation 3
Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for the inner ring, outer ring and special interest locations are placed in the field at the same time as regular sets.
3.1 Program Design and Data Interpretation (continued) of corrosion products.
The emergency set is returned to EIML quarterly for annealing and repackaging.
They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational.
Milk samples are collected monthly from five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.
Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at two locations, one 4
3.2 Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate.
 
To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2000). Maps of fixed sampling locations are included in Appendix E. To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations.
3.2   Program Description (continued) upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine 131. A quarterly composite of the particulate filters from each location is gamma-scanned on an HPGe detector.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
One of the five locations is a control (P-l), and four are indicators (P 2, P-3, P-4, and P-6). Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location:
3.3   Program Execution The Program was executed as described in the preceding section with the following exceptions:
ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly.
(1)   No air particulate/air iodine samples were available from location P-3 for the week ending 06-14-00, due to sampler pump failure.
Also, a complete emergency set of TLDs for the inner ring, outer ring and special interest locations are placed in the field at the same time as regular sets. The emergency set is returned to EIML quarterly for annealing and repackaging.
(2)   TLD data was not available from location P-10B for the fourth quarter, 2000.
Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters.
Both the regular and emergency TLDs were lost in the field, due to unusually deep snow.
Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.
Deviations from the program are summarized in Table 5.3.
Milk samples are collected monthly from five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes.
3.4   Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting. All gamma-spectroscopic analyses were performed with an HPGe detector. Levels of airborne iodine-131 in charcoal samples were measured by gamma spectrometry.
The milk is collected biweekly during the growing season (May -October), because the milk animals may be on pasture.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131.
Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes.
Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes.
River water is collected weekly at two locations, one 4 3.2 Program Description (continued) upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments.
Shoreline sediment is collected semi-annually from one location.
All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) No air particulate/air iodine samples were available from location P-3 for the week ending 06-14-00, due to sampler pump failure.
(2) TLD data was not available from location P-10B for the fourth quarter, 2000. Both the regular and emergency TLDs were lost in the field, due to unusually deep snow. Deviations from the program are summarized in Table 5.3. 3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting.
All gamma-spectroscopic analyses were performed with an HPGe detector.
Levels of airborne iodine-131 in charcoal samples were measured by gamma spectrometry.
Levels of iodine-131 in cabbage and were determined by gamma spectrometry.
Levels of iodine-131 in cabbage and were determined by gamma spectrometry.
Tritium levels were determined by liquid scintillation technique.
Tritium levels were determined by liquid scintillation technique.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection. Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984. Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.
Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.5 3.5 Program Modifications Special tritium sampling of ground and well water was monitored from 1989 through 1999 at several locations.
5
Tritium concentrations in that time have dropped to below detection levels. The program has been discontinued for the year 2000. The Suter residence, (P-24) was retained from the program, and added to the REMP in 2000, as a monitored well water location.
 
3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
3.5   Program Modifications Special tritium sampling of ground and well water was monitored from 1989 through 1999 at several locations. Tritium concentrations in that time have dropped to below detection levels. The program has been discontinued for the year 2000. The Suter residence, (P-24) was retained from the program, and added to the REMP in 2000, as a monitored well water location.
This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant. The 2000 Land Use Census was completed in October, 2000. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2000. The critical receptor location did not change in 2000, based on the results of the land use census. No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant. Therefore, no corn samples were collected for analysis.6 4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3. The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations.
3.6   Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
The locations with the highest mean and range are also shown. 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2000. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents at nuclear reactor facilities in 2000. 4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.
This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.
Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m 2 to 1,020 pCi/m 2 , and these declining values are reflected throughout the various media tested. In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3.Average present day levels have stabilized at around 0.025 pCi/m 3.Airborne radioiodine remained below detection levels. In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored.
The 2000 Land Use Census was completed in October, 2000. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2000. The critical receptor location did not change in 2000, based on the results of the land use census.
In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected.
No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.
Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g. The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish , aquatic vegetation and periphyton.
Therefore, no corn samples were collected for analysis.
Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible.
6
However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream.
 
The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively.
4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.
Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.
The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
7 4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 2000. Offsite Ambient Radiation (TLDs) Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 -5 mi distant from the Plant, at special interest areas and at one control location.
4.1   Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2000. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents at nuclear reactor facilities in 2000.
The means ranged from 16.0 mR/91 days at inner ring locations to 17.6 mRI91 days at outer ring locations.
4.2   Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.
The mean at special locations was 15.8 mR/91 days and 17.1 mR/91 days at the control location.
2 Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m 2 , and these declining values are reflected throughout the various media tested.
The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1985. through 1999. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1). Average (Inner Year and Outer Ring-s) Control 1985 14.0 15.3 1986 17.1 17.3 1987 16.9 17.0 1988 15.4 16.0 1989 16.5 16.7 1990 15.9 16.3 1991 14.9 14.5 1992 16.3 14.8 1993 15.9 15.4 1994 15.2 16.0 1995 15.6 16.6 1996 14.8 16.4 1997 15.1 16.0 1998 16.7 17.3 1999 16.6 17.5 2000 17.0 17.1 Ambient gamma radiation as measured by thermoluminescent dosimetry.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 3
Average quarterly dose rates (mR/91 days). ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community.
pCi/m 3 . Average present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.
The mean dose rates measured 70.0 mR/91 days inside the ISFSI earth berm and 19.0 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSI pad in 2000. There were twelve loaded casks on the ISFSI pad during 2000. The higher levels inside the earth berm are expected due to the loaded spent fuel casks being in direct line-of-sight from the TLDs. The ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.8 and 15.4 mR/91 days. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).8 Airborne Particulates The annual gross beta concentration in airborne particulates for both indicator and control locations averaged 0.025 pCi/m 3.These averages were similar to average means reported from 1985 through 1999. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl. (Figure 5-2).Average of Year Indicators Control Concentration (pCi/m 3) 1985 0.025 0.025 1986 0.024 0.029 1987 0.024 0.023 1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 1991 0.025 0.025 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 Average annual gross beta concentrations in airborne particulates.
In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.
A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1985 through 2000. Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation.
The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish , aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible.
In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations.
However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g.
Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Xcel Energy Corp., 2001a). Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.
Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples. All other gamma-emitting isotopes were below their respective LLD limits.9 Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples. There was no indication of a plant effect. Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968). In summary, the milk data for 2000 show no radiological effects of the plant operation.
7
 
4.3   Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 2000.
Offsite Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of the site boundary, at the outer ring 4
    - 5 mi distant from the Plant, at special interest areas and at one control location. The means ranged from 16.0 mR/91 days at inner ring locations to 17.6 mRI91 days at outer ring locations. The mean at special locations was 15.8 mR/91 days and 17.1 mR/91 days at the control location. The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1985. through 1999. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).
Average (Inner Year           and Outer Ring-s)     Control 1985                 14.0               15.3 1986                 17.1               17.3 1987                 16.9               17.0 1988                 15.4               16.0 1989                 16.5               16.7 1990                 15.9               16.3 1991                 14.9               14.5 1992                 16.3               14.8 1993                 15.9               15.4 1994                 15.2               16.0 1995                 15.6               16.6 1996                 14.8               16.4 1997                 15.1               16.0 1998                 16.7               17.3 1999                 16.6             17.5 2000                 17.0             17.1 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates (mR/91 days).
ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 70.0 mR/91 days inside the ISFSI earth berm and 19.0 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSI pad in 2000. There were twelve loaded casks on the ISFSI pad during 2000. The higher levels inside the earth berm are expected due to the loaded spent fuel casks being in direct line-of-sight from the TLDs. The ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.8 and 15.4 mR/91 days. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).
8
 
Airborne Particulates The annual gross beta concentration in airborne particulates for both indicator and control locations averaged 0.025 pCi/m 3 . These averages were similar to average means reported from 1985 through 1999. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl. (Figure 5-2).
Average of Year             Indicators           Control Concentration (pCi/m 3 )
1985               0.025             0.025 1986               0.024             0.029 1987               0.024             0.023 1988               0.030             0.030 1989               0.028             0.027 1990               0.024             0.023 1991               0.025             0.025 1992               0.023             0.021 1993               0.022             0.019 1994               0.022             0.022 1995               0.022             0.022 1996               0.023             0.020 1997               0.021             0.021 1998               0.022             0.018 1999               0.024             0.022 2000               0.025             0.025 Average annual gross beta concentrations in airborne particulates.
A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al.,
1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1985 through 2000.
Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations.
Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Xcel Energy Corp.,
2001a).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples. All other gamma-emitting isotopes were below their respective LLD limits.
9
 
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples. There was no indication of a plant effect.
Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
In summary, the milk data for 2000 show no radiological effects of the plant operation.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCi/L in all samples.
Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCi/L in all samples.
Gross beta measurements remained fairly constant throughout the year and averaged 10.1 pCi/L. These concentrations were slightly higher than levels observed from 1985 through 1999 and are most likely contributed by relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2000 data of any effect of plant operation.
Gross beta measurements remained fairly constant throughout the year and averaged 10.1 pCi/L. These concentrations were slightly higher than levels observed from 1985 through 1999 and are most likely contributed by relatively high levels of naturally-occurring radium.
Gross Beta Yea.r (pCi/L) 1985 7.1 1986 6.8 1987 7.9 1988 8.0 1989 7.0 1990 7.0 1991 8.0 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 1997 5.1 1998 5.4 1999 5.3 2000 10.1 Average annual concentrations; Gross beta in drinking water.10 River Water In one quarterly composite of downstream river water, tritium was measured at a concentration of 297 pCi/L. In all other upstream and downstream collections, quarterly composite tritium levels were below the LLD level of 190 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2000 data of any effect of plant operation.
Gross Beta (pCi/L)
Yea.r 1985                     7.1 1986                     6.8 1987                     7.9 1988                     8.0 1989                     7.0 1990                     7.0 1991                     8.0 1992                     7.6 1993                     7.5 1994                     5.8 1995                     3.9 1996                     6.3 1997                     5.1 1998                     5.4 1999                     5.3 2000                     10.1 Average annual concentrations; Gross beta in drinking water.
10
 
River Water In one quarterly composite of downstream river water, tritium was measured at a concentration of 297 pCi/L. In all other upstream and downstream collections, quarterly composite tritium levels were below the LLD level of 190 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
Well Water At the control well P-41, Huppert Farm and four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 180 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
Well Water At the control well P-41, Huppert Farm and four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 180 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.
In summary, well water data for 2000 show no radiological effects of the plant operation.
In summary, well water data for 2000 show no radiological effects of the plant operation.
Crops Two samples of broadleaf vegetation, cabbage and rutabaga leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131.
Crops Two samples of broadleaf vegetation, cabbage and rutabaga leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.009 pCi/g wet weight in both samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
The 1-131 level was below 0.009 pCi/g wet weight in both samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect. The field sampling personnel conducted an annual land use survey and found that there was no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. No collection and analysis of corn samples was not required.
The field sampling personnel conducted an annual land use survey and found that there was no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. No collection and analysis of corn samples was not required.
Fish Fish samples were collected in April, May and September, 2000 and analyzed for gamma emitting isotopes.
Fish Fish samples were collected in April, May and September, 2000 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.
Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect. Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2000. All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect. Bottom and Shoreline Sediments Sediment collections were made in May and September, 2000 and analyzed for gamma emitting isotopes.
Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2000.
All other gamma-emitting isotopes, excepting naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.
All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect.
11 5.0 FIGURES AND TABLES 12 PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant. Collection Analysis Location Type and Type and Medium No. Codes (and Type)' Frequencyb Frequency' Ambient radiation (TLD's) 54 P-01A -P-10A C/Q Ambient gamma Airborne Particulates Airborne Iodine Milk Milk River water Drinking water P-01B -P-15B P-01S -P-08S P-011A -P-081A P-01IB -P-081B P-0lIX- P-04IX, P-0lC 5 P-I(C), P-2, P-3, P-4, P-6 5 P-I(C), P-2, P-3, P-4, P-6 4 P-14, P-18,P-37, P-41 (C) 1 P-39 2 P-5(C), P-6 1 P-1I C/W C/W G/Md G/M G/W G/W GB, GS (QC of each location) 1-131 1-131, GS 1-13 1, GS GS(MC), H-3(QC) GB(MC), I- 131 (MC) GS (MC), H-3 (QC)Well water Edible cultivated crops leafy green vegetables Fish (one species, edible portion) Periphyton or invertebrates Bottom sediment Shoreline sediment 5 2 2 2 2 1 P-6, P-8, P-9, P-24, P-41 (C) P-38(C), P-24 P-19(C), P-13 P40(C), P-6 P-20(C), P-6 P-12 a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
Bottom and Shoreline Sediments Sediment collections were made in May and September, 2000 and analyzed for gamma emitting isotopes. All other gamma-emitting isotopes, excepting naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.
b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows: W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.   
11
'Analysis type codes: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
 
d Milk is collected biweekly during the grazing season (May -October).13 G/Q G/A G/SA G/SA G/SA G/SA H-3, GS GS (1-131) GS GS GS GS PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant. Distance and Direction from Code Typea Collection Site Sample Typeb Reactor C Air Station P-I Air Station P-2 Air Station P-3 Air Station P-4 C Upstream of Plant Lock and Dam # 3 & Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Gustafson Farm Christiansen Farm C Upstream of Plant C Upstream of Plant Suter Residence Welsch Farm C Cain Residence Born Farm C Upstream of Plant C Huppert Farm AP, AI AP, AI AP, AI AP, Al RW AP, AI, RW WW, BS, BOc WW WW DW SS Fc M M Fc BS VE, WW M VE M BOc M,WW 11.8 mi @ 316°/NNW 0.5 mi @ 294°/WNW 0.8 mi @ 313°/NW 0.4 mi @ 359 0/N 1.8 mi @ 11/N 1.6 mi @ 129°/SE 1.0 mi @ 321°/WNW 0.3 mi @ 306'/NW 3.3 mi @ 158°/SSE 3.0 mi @ 116°/ESE 3.5 mi @ 113°/ESE 2.3 mi @ 1730/S 3.8 mi @ 88°/E 1.3 mi @ 0 0 N 0.9 mi @ 45°/NE 0.6 mi @ 158°/SSE 4.1 mi@ 87°/E 14.2 mi @ 359°/N 2.8 mi @ 239°/WSW 0.4 mi @ 0°/N 13.8 mi @ 354°/N General Area of the Site Boundary Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.4 mi @ 359-/N 0.3 mi @ 10I/N 0.5 mi @ 183-/S 0.4 mi @ 204°/SWW 0.4 mi @ 225°/SW 0.4 mi @ 249 0/WSW 0.4 mi @ 268°/W 0.4 mi @ 291 °/WNW 0.7 mi @ 317°/NW 0.5 mi @ 333°/NNW 14 P-1 P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-11 P-12 P-13 P-14 P-18 P-19 P-20 P-24 P-37 P-38 P-39 P-40 P-41 P-O0A P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-IOA PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
5.0 FIGURES AND TABLES 12
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant Thomas Killian Residence Roy Kimneman Residence Wayne Anderson Farm Nelson Drive (Road) County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 19 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Holst Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 355°/N 4.8 mi @ 17°/NNE 4.9 mi @ 46 0/NE 4.2 mi @ 61°IENE 4.2 mi @ 102°/ESE 4.4 mi @ 112°/ESE 4.7 mi @ 140 0/SE 4.1 mi @ 165°/SSE 4.2 mi @ 187°/S 4.9 mi @ 200°/SSW 4.5 mi @ 221°/SW 4.6 mi @ 251I/WSW 4.4 mi @ 270°/W 4.9 mi @ 306°/NW 3.8 mi @ 345°/NNW Special Interest Locations Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 1.6 mi @ 129°/SE 0.5 mi @ 155°/SSE 2.2 mi @ 1730/S 2.0 mi @ 202°/SSW 2.0 mi @ 270V/W 2.5 mi @ 299°/WNW 0.7 mi @ 271 0/W 0.7 mi @ 287 0/NWW 11.1 mi @ 331°/NNW 15 P-01B P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-103B P- l1B P-12B P-13B P-14B P-15B P-01S P-02S P-03S P-04S P-05S P-06S P-07S P-08S P-01C PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
 
Approximate Type of Distance and Direction Code Typea Collection Site Sampleb from ISFSI Center. ISFSI Area Inside Earth Berm P-01IA ISFSI Nuisance Fence TLD 190' @ 45°/NE P-021A ISFSI Nuisance Fence TLD 360' @ 82°/E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219°/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 28 1°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318 0/NW P-OlIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-03DX ISFSI Nuisance Fence TLD 140' @ 0O/N P-041X ISFSI Nuisance Fence TLD 360' @ 90°/E ISFSI Area Outside Earth Berm P-OlIB ISFSI Berm Area TLD 340' @ 3°/N P-021B ISFSI Berm Area TLD 380' @ 28 0/NNE P-031B ISFSI Berm Area TLD 560' @ 85°/E P-041B ISFSI Berm Area TLD 590' @ 165 0/SSE P-05IB ISFSI Berm Area TLD 690' @ 1860/S P-061B ISFSI Berm Area TLD 720' @ 201°/SSW P-07EB ISFSI Berm Area TLD 610' @ 271°/W P-08EB ISFSI Berm Area TLD 360' @ 332°/NNW a "C" denotes control location.
PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.
All other locations are indicators.
Collection               Analysis Location                       Type and                 Type and Medium                       No. Codes (and Type)'             Frequencyb               Frequency' Ambient radiation (TLD's)           54 P-01A - P-10A                         C/Q             Ambient gamma P-01B - P-15B P-01S - P-08S P-011A - P-081A P-01IB - P-081B P-0lIX- P-04IX, P-0lC Airborne Particulates                5 P-I(C), P-2,                         C/W            GB, GS (QC of P-3, P-4, P-6                                       each location)
b Sample Codes: AP Airborne particulates AI Airborne Iodine BS Bottom (river) sediments BO Bottom organisms (periphyton or macroinvertebrates)
Airborne Iodine                      5 P-I(C), P-2, P-3, P-4, P-6           C/W            1-131 Milk                                  4  P-14, P-18,P-37, P-41 (C)           G/Md            1-131, GS Milk                                  1   P-39                               G/M            1-13 1, GS River water                          2   P-5(C), P-6                         G/W            GS(MC), H-3(QC)
DW Drinking water F M SS SW VE WW Fish Milk Shoreline Sediments Surface Water Vegetation/vegetables Well water C Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.16 Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.All required samples were collected and analyzed as scheduled with the following exceptions:
Drinking water                        1   P-1I                               G/W             GB(MC), I- 131 (MC)
Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, P-03 6/14/00 No power due to open fuse. Replaced fuse and conducted testing.
GS (MC), H-3 (QC)
1-131 All operational testing was satisfactory.
Well water                            5  P-6, P-8, P-9, P-24, P-41 (C)       G/Q            H-3, GS Edible cultivated crops               2  P-38(C), P-24                        G/A            GS (1-131) leafy green vegetables Fish (one species, edible portion)   2   P-19(C), P-13                      G/SA            GS Periphyton or invertebrates          2  P40(C), P-6                         G/SA            GS Bottom sediment                      2  P-20(C), P-6                       G/SA            GS Shoreline sediment                    1  P-12                               G/SA            GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
TLD Ambient P-lOB 4th Qtr. TLD lost in the field due to Isolated incident; no action required.
b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows: W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
Gamma unusually deep snow.17 C> ~ 4-:- C,, -- W 1,0 C 1985 "- 1985 --- , 1986-- 1986 --"'_ --© 1987- 1987--- CD 1988 1988 1989 1989 1990--1990 1- -. -- " o 1992- Z, CL) S1993 1993 I 1994 1994- --- 199 3 1995--19965 1996 -/ -0 19974-------
  'Analysis type codes: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine 131.
1997 -, 1998 1998 5 -- 1999 T 1999 -2000 2000-mR / 91 days mR / 91 days Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.0.031 0.029 S0.027 , 0.025 0.023 0.021 0.019 0.017 0.015 W) ý10 r- 00 a's ý '-4 C14 M~ ýt W) 10 00 00 00 00 00 ON Oa% 01 0\ ON QN a' C* O. O( ON 0) O\ OS ON CN CN ON ON Ox .-4 ---4 -.4 --4 1-4 -4 1-4 1- -00 01% 0 CN 0 O\ 0 01 CN C: 0.0 0.0: 0.0 S0.0: S0.0: 0.0 0.0 0.0 0.0 0.0 0.0-e-- Control (P-l) I 35 33-31-29-- -- --- --- --- 27 25-( 23'17'15-LO C (0 I- O0) 0 .m-- 0 Co) l q U (0 1 "- M0 O0 0 ccO c cc CO C0 60 0)J 0) 0) 0) 0) 0) 0) 0) 0) 0 0') 0') 0) 0') 0) 0) 0) 0') 0) 0") 0) 0) 0") 0) 0 0 19 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota ( County, State)Docket No. 50-282,50-306 Reporting Period January-December, 2000 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)' Mean (F)Y Routine (Units) Analyses' Range' Location" Rangec Range' Results' TLD (Inner Ring, Gamma 40 3.0 16.0 (40/40) P-06A 16.9 (4/4) (See Control 0 Area at Site (12.3-18.4) 0.4 mi @ 249* /WSW (15.1-18.4) below.) Boundary) mR/91 days) TLD (Outer Ring, Gamma 59 3.0 17.6 (59/59) P-02B, Roy Kinneman, 20.5 (4/4) (See Control 0 4-5 mi. distant) (13.1-21.8) 4.8 mi @ 17' /NNE (18.2-21.8) below.) mR/91 days) TLD (Special Gamma 32 3.0 15.8 (32/32) P-03S, Gustafson Farm, 18.4 (4/4) (See Control 0 Interest Areas) (12.3-19.7) 2.2 mi @ 173' /S (16.5-19.7) below.) mR/91 days) TLD (Control)
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
Gamma 4 3.0 None P-01C, R. Kinneman, 17.1 (4/4) 17.1 (4/4) 0 mR/91 days) 11.1 mi @ 331' /NNW (15.1-18.2)
d Milk is collected biweekly during the grazing season (May - October).
(15.1-18.2)
13
Airborne GB 264 0.005 0.025 (211/211)
 
P-04, Air Station 0.026 (53/53) 0.025 (53/53) 0 Particulates (0.009-0.078) 0.4 mi @ 3590 /N (0.009-0.073)
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.
(0.011-0.083) (pCi/my) GS 20 Be-7 0.015 0.061 (16/16) P-06, Air Station 0.064 (4/4) 0.055 (4/4) 0 (0.040-0.075) 1.6 mi @ 129'/SE (0.040-0.070)
Distance and Direction from Code       Typea   Collection Site               Sample Typeb                 Reactor P-1          C     Air Station P-I               AP, AI              11.8 mi @ 316°/NNW P-2                  Air Station P-2                AP, AI              0.5 mi @ 294°/WNW P-3                 Air Station P-3                AP, AI              0.8 mi @ 313°/NW P-4                  Air Station P-4                AP, Al              0.4 mi @ 3590/N P-5          C      Upstream of Plant             RW                  1.8 mi @ 11/N P-6                  Lock and Dam # 3 & Air        AP, AI, RW Station P-6                  WW, BS, BOc         1.6 mi @ 129°/SE P-8                  Community Center              WW                  1.0 mi @ 321°/WNW P-9                  Plant Well #2                  WW                  0.3 mi @ 306'/NW P-11                Red Wing Service Center        DW                  3.3 mi @ 158°/SSE P-12                Downstream of Plant            SS                  3.0 mi @ 116°/ESE P-13                Downstream of Plant            Fc                  3.5 mi @ 113°/ESE P-14                Gustafson Farm                M                  2.3 mi @ 1730/S P-18                Christiansen Farm              M                  3.8 mi @ 88°/E P-19          C      Upstream of Plant              Fc                  1.3 mi @ 00 N P-20          C      Upstream of Plant              BS                  0.9 mi @ 45°/NE P-24                Suter Residence                VE, WW              0.6 mi @ 158°/SSE P-37                Welsch Farm                    M                  4.1 mi@ 87°/E P-38          C      Cain Residence                VE                  14.2 mi @ 359°/N P-39                Born Farm                      M                  2.8 mi @ 239°/WSW P-40          C      Upstream of Plant              BOc                0.4 mi @ 0°/N P-41          C      Huppert Farm                  M,WW                13.8 mi @ 354°/N General Area of the Site Boundary P-O0A                Property Line                  TLD                0.4 mi @ 359-/N P-02A                Property Line                  TLD                0.3 mi @ 10I/N P-03A                Property Line                  TLD                0.5 mi @ 183-/S P-04A                Property Line                  TLD                0.4 mi @ 204°/SWW P-05A                Property Line                  TLD                0.4 mi @ 225°/SW P-06A                Property Line                 TLD                0.4 mi @ 2490/WSW P-07A                Property Line                 TLD                 0.4 mi @ 268°/W P-08A                Property Line                  TLD                0.4 mi @ 291 °/WNW P-09A                Property Line                  TLD                0.7 mi @ 317°/NW P-IOA                Property Line                  TLD                0.5 mi @ 333°/NNW 14
(0.040-0.066)
 
Mn-54 0.0008 < LLD -- < LLD 0 Co-58 0.0011 < LLD --< LLD 0 Co-60 0.0010 < LLD --< LLD 0 Zn-65 0.0013 < LLD --< LLD 0 Zr-Nb-95 0.0011 < LLD --< LLD 0 Ru-103 0.0009 < LLD --< LLD 0 Ru-106 0.0069 < LLD --< LLD 0 Cs-134 0.0006 < LD -< LLD 0 Cs-137 0.0007 <LLD --<LLD 0 Ba-La-140 0.0024 < LLD --< LLD 0 Ce-141 0.0013 < LLD <- < LLD 0 Ce-144 0.0036 < LLD -< LLD 0 Airborne Iodine 1-131 264 0.07 < LLD --< LLD 0 (pG/rft)20 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No. 50-282, 50-306 Reporting Period January-December, 2000 ( County, State ) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)Y Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results' Milk (pCi/L) 1-131 76 1.0 < LLD < LLD 0 GS 76 K-40 200 1481 (57/57) P-14, Gustafson Farm 1524 (19/19) 1481 (19/19) 0 (1276-1756) 2.3 mi @ 173&deg;/S (1367-1632)
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
(1347-1588)
Distance and Direction from Code        Typea  Collection Site                    Sample Typeb            Reactor Approximately 4 to 5 miles Distant from the Plant P-01B                Thomas Killian Residence              TLD        4.7 mi @ 355&deg;/N P-02B                Roy Kimneman Residence                TLD        4.8 mi @ 17&deg;/NNE P-03B                Wayne Anderson Farm                    TLD        4.9 mi @ 460 /NE P-04B                Nelson Drive (Road)                    TLD        4.2 mi @ 61&deg;IENE P-05B                County Road E and Coulee              TLD        4.2 mi @ 102&deg;/ESE P-06B                William Hauschiblt Residence          TLD        4.4 mi @ 112&deg;/ESE P-07B                Red Wing Public Works                  TLD        4.7 mi @ 140 0/SE P-08B                David Wnuk Residence                  TLD        4.1 mi @ 165&deg;/SSE P-09B                Highway 19 South                      TLD        4.2 mi @ 187&deg;/S P-103B                Cannondale Farm                      TLD        4.9 mi @ 200&deg;/SSW P- l1B              Wallace Weberg Farm                    TLD        4.5 mi @ 221&deg;/SW P-12B                Ray Gergen Farm                        TLD        4.6 mi @ 251I/WSW P-13B                Thomas O'Rourke Farm                  TLD        4.4 mi @ 270&deg;/W P-14B                David J. Anderson Farm                TLD        4.9 mi @ 306&deg;/NW P-15B                Holst Farms                            TLD        3.8 mi @ 345&deg;/NNW Special Interest Locations P-01S                Federal Lock & Dam #3                  TLD        1.6 mi @ 129&deg;/SE P-02S                Charles Suter Residence                TLD        0.5 mi @ 155&deg;/SSE P-03S                Carl Gustafson Farm                    TLD        2.2 mi @ 1730/S P-04S                Richard Burt Residence                TLD        2.0 mi @ 202&deg;/SSW P-05S                Kinney Store                          TLD        2.0 mi @ 270V/W P-06S                Earl Flynn Farm                        TLD        2.5 mi @ 299&deg;/WNW P-07S                Indian Community                      TLD        0.7 mi @ 2710 /W P-08S                Indian Community                      TLD        0.7 mi @ 2870/NWW P-01C          C    Robert Kinneman Farm                  TLD        11.1 mi @ 331&deg;/NNW 15
Cs-134 15 < LLD < LLD 0 Cs-137 15 < LLD < LLD 0 Ba-La-140 15 < LLD < LLD 0 River Water H-3 8 179 297(1/4) P-6, Lock and Dam # 3 297(1/4) < LLD 0 (pCi/L) 1.6 mi @ 129'/SE GS 24 Mn-54 15 < LLD -< LLD 0 Fe-59 30 < LLD -< LLD 0 Co-58 15 < LLD -< LLD 0 Co-60 15 < LLD --< LLD 0 Zn-65 30 < LLD -< LLD 0 Zr-Nb-95 15 < LLD -< LLD 0 Cs-134 15 < LLD --< LLD 0 Cs-137 18 < LLD -< LLD 0 Ba-La-140 15 < LLD -< LLD 0 Ce-144 58 < LLD I < LLD 0 21 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No. 50-282, 50-306 Reporting Period January-December, 2000 (County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysese Range' Locationd Range' Range' Results' Drinking Water GB 12 1.0 < LLD P-11, Red Wing S.C. 10.1 (12/12) None 0 (pCi/L) 3.3 mi @ 158' /SSE (5.2-12.9) 1-131 12 1.0 < LLD -None 0 H-3 4 179 < LLD -None 0 GS 12 Mn-54 15 < LLD --None 0 Fe-59 30 < LLD --None 0 Co-58 15 < LLD --None 0 Co-60 15 < LLD --None 0 Zn-65 30 < LLD --None 0 Zr-Nb-95 15 < LLD --None 0 Cs-134 10 < LLD --None 0 Cs-137 10 < LLD --None 0 Ba-La-140 15 < LLD --None 0 Ce-144 59 < LLD --None 0 Well Water H-3 20 180 < LLD --< LLD 0 (pCi/L) GS 20 Mn-54 15 < LLD --< LLD 0 Fe-59 30 < LLD --< LLD 0 Co-58 15 < LLD --< LLD 0 Co-60 15 < LLD --<LLD 0 Zn-65 30 < LLD --< LLD 0 Zr-Nb-95 15 < LLD --< LLD 0 Cs-134 10 < LLD --< LLD 0 Cs-137 18 < LLD --< LLD 0 Ba-La-140 15 < LLD -< LLD 0 Ce-144 56 < LLD -< LLD 0 Crops -Cabbage 1-131 2 0.009 < LLD -< LLD 0 (pCi/gwet) 22 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No. 50-282,50-306 Reporting Period January-December, 2000 (County, State) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDP Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysese Range' Location' Range' Range' Results' Fish GS 4 (pCi/g wet) K-40 0.10 2.85 (2/2) P-19, Upstream 3.58 (2/2) 3.28 (2/2) 0 (2.63-3.06) 1.3 mi. @ 0*&deg;/N (3.42-3.73)
 
(3.07-3.48)
PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).
Mn-54 0.018 < LLD --< LLD 0 Fe-59 0.081 < LLD --< LLD 0 Co-58 0.015 < LLD --< LLD 0 Co-60 0.017 < LLD --< LLD 0 Zn-65 0.029 < LLD --< LLD 0 Zr-Nb-95 0.031 < LLD --< LLD 0 Cs-134 0.013 < LLD --< LLD 0 Cs-137 0.013 < LLD --< LLD 0 Ba-La-140 0.77 < LLD --< LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.55 < LLD --< LLD 0 K-40 1.48 < LLD --< LLD 0 Mn-54 0.063 < LLD --< LLD 0 Co-58 0.10 < LLD --< LLD 0 Co-60 0.069 < LLD --< LLD 0 Zn-65 0.12 < LLD --< LLD 0 Zr-Nb-95 0.13 < LLD --< LLD 0 Ru-103 0.078 < LLD -< LLD 0 Ru-106 0.40 < LLD --< LLD 0 Cs-134 0.071 < LLD --< LLD 0 Cs-137 0.057 < LLD --< LLD 0 Ba-La-140 0.61 < LLD --< LLD 0 Ce-141 0.11 < LLD --< LLD 0 Ce-144 0.24 <LLD --< LLD 0 23 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota Docket No. 50-282, 50-306 Reporting Period January-December, 2000 (County, State) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Location' Range' Range' Results' Bottom and GS 6 Shoreline Be-7 0.30 < LLD < LLD 0 Sediments K-40 0.10 6.94(4/4)
Approximate Type of    Distance and Direction Code         Typea   Collection Site                               Sampleb      from ISFSI Center.
P-20, Upstream 8.79 (4/4) 8.79 (4/4) 0 (pCi/g dry) (6.51-7.46) 0.9 mi. @ 45' /NE (8.64-8.94)
ISFSI Area Inside Earth Berm P-01IA                ISFSI Nuisance  Fence                        TLD      190' @ 45&deg;/NE P-021A                ISFSI Nuisance  Fence                        TLD      360' @ 82&deg;/E P-031A                ISFSI Nuisance  Fence                        TLD      370' @ 100&deg;/E P-041A                ISFSI Nuisance  Fence                        TLD       200' @ 134&deg;/SE P-051A                ISFSI Nuisance  Fence                        TLD      180' @ 219&deg;/SW P-061A                ISFSI Nuisance  Fence                        TLD      320' @ 258&deg;/WSW P-071A                ISFSI Nuisance  Fence                        TLD      320' @ 28 1&deg;/WNW P-081A                ISFSI Nuisance  Fence                        TLD      190' @ 318 0/NW P-OlIX                ISFSI Nuisance  Fence                        TLD      140' @ 1800/S P-021X                ISFSI Nuisance  Fence                        TLD      310' @ 270&deg;/W P-03DX                ISFSI Nuisance  Fence                        TLD      140' @ 0O/N P-041X                ISFSI Nuisance  Fence                        TLD      360' @ 90&deg;/E ISFSI Area Outside Earth Berm P-OlIB                ISFSI Berm Area                                TLD      340' @ 3&deg;/N P-021B                ISFSI Berm Area                                TLD      380' @ 28 0/NNE P-031B                ISFSI Berm Area                                TLD      560' @ 85&deg;/E P-041B                ISFSI Berm Area                                TLD      590' @ 165 0/SSE P-05IB                ISFSI Berm Area                                TLD      690' @ 1860/S P-061B                ISFSI Berm Area                                TLD      720' @ 201&deg;/SSW P-07EB                ISFSI Berm Area                                TLD      610' @ 271&deg;/W P-08EB                ISFSI Berm Area                                TLD      360' @ 332&deg;/NNW a "C" denotes control location. All other locations are indicators.
(8.64-8.94)
b  Sample Codes:
Mn-54 0.021 < LLD --< LLD 0 Co-58 0.030 < LLD --< LLD 0 Co-60 0.016 < LLD --< LLD 0 Zn-65 0.066 < LLD --< LLD 0 Zr-Nb-95 0.030 < LLD --< LLD 0 Ru-103 0.023 < LLD --< LLD 0 Ru-106 0.18 < LLD --< LLD 0 Cs-134 0.030 < LLD --< LLD 0 Cs-137 0.024 < LLD --< LLD 0 Ba-La-140 0.062 < LLD --< LLD 0 Ce-141 0.044 < LLD --< LLD 0 Ce-144 0.10 < LLD --< LLD 0 "GB gross beta, GS = gamma scan.  ' LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.  ' Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). d Locations are specified:
AP      Airborne particulates                            F      Fish AI      Airborne Iodine                                M      Milk BS      Bottom (river) sediments                        SS      Shoreline Sediments BO      Bottom organisms                              SW      Surface Water (periphyton or macroinvertebrates)            VE      Vegetation/vegetables DW      Drinking water                                WW      Well water CDistance  and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.
(1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.  "Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.24  
16
 
Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled with the following exceptions:
Collection        Reason for not Sample    Analysis  Location    Date or        conducting REMP                    Plans for Preventing Type                              Period            as required                          Recurrence AP/AI        Beta,    P-03      6/14/00  No power due to open fuse. Replaced fuse and conducted testing.
1-131                                                        All operational testing was satisfactory.
TLD        Ambient  P-lOB      4th Qtr. TLD lost in the field due to  Isolated incident; no action required.
Gamma                          unusually deep snow.
17
 
mR / 91 days                      mR / 91 days C>  ~          4-:-   C,,  -- W      1,0  C 1985                  "-     1985 ---                                                       ,
1986--                         1986    -   -"'_                        -       -&#xa9; 1987-                         1987---                                                       CD 1988                          1988 1989                          1989 1990--1990                                        1-                       -                   .
                            --                                                            o 1992-*                        1992-                                                  CL)   Z, 1993            S1993                                I 1994                          1994-    -  --
199          3                1995--
1996                              -/     -
19965 0
19974-------                   1997 -,
1998                          1998      5    --
1999 T                        1999                                      -
2000                          2000-
 
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
0.031 0.029 S0.027
  ,    0.025 0.023 0.021 0.019 0.017 0.015 W)    &#xfd;10  r-   00    a's        &#xfd;   '-4  C14  M~    &#xfd;t    W) 10      00  01% 0 00    00  00    00    00      ON      Oa%  01  0\    ON    O* QN a'   CN O\  0'*
O*
0 0
C*    O. O(
ON        0)      O\      OS    ON  CN    CN    ON ON Ox  01  CN  C:
                  . -4      - -      -4      -.4      --4  1-4  -4    1-4  1-      -
                                                                      -e-- Control (P-l)    I 0.0 35 0.0:33-0.0 31-S0.0:29--              --      -    --        -      --      -      --
S0.0:27 0.0 25-(
0.0 23 0.0 0.0 0.0 '17 0.0 '15-                 O0) C0        0      .m--  00)  Co)    l0) q    U  (0 10)
                                                                                        "- M0  O0  00 ccO LO    c (0
C   cc I-   CO    60              0)J        0)            0) 0)      0)  0) 0')  0')  0)    0')  0)      0)      0)      0') 0)      0")  0) 0) 0") 0)  0    0 19
 
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility              Prairie Island Nuclear Power Station                    Docket No.      50-282,50-306 Location of Facility          Goodhue, Minnesota                                      Reporting Period January-December, 2000
( County, State)
Indicator                Location with Highest                Control    Number Sample              Type and                        Locations                      Annual Mean                    Locations    Non Type            Number of          LLDb          Mean (F)c                                    Mean (F)'         Mean (F)Y    Routine (Units)           Analyses'                        Range'              Location"              Rangec            Range'    Results' TLD (Inner Ring, Gamma              40      3.0      16.0 (40/40)               P-06A              16.9 (4/4)      (See Control      0 Area at Site                                          (12.3-18.4)      0.4 mi @ 249* /WSW          (15.1-18.4)        below.)
Boundary) mR/91 days)
TLD (Outer Ring, Gamma              59      3.0       17.6 (59/59)    P-02B, Roy Kinneman,        20.5 (4/4)      (See Control      0 4-5 mi. distant)                                        (13.1-21.8)      4.8 mi @ 17' /NNE          (18.2-21.8)         below.)
mR/91 days)
TLD (Special    Gamma            32      3.0        15.8 (32/32)    P-03S, Gustafson Farm,        18.4 (4/4)     (See Control      0 Interest Areas)                                        (12.3-19.7)         2.2 mi @ 173' /S        (16.5-19.7)         below.)
mR/91 days)
TLD (Control)   Gamma            4      3.0           None          P-01C, R. Kinneman,        17.1 (4/4)       17.1 (4/4)       0 mR/91 days)                                                           11.1 mi @331' /NNW          (15.1-18.2)       (15.1-18.2)
Airborne      GB              264    0.005    0.025 (211/211)       P-04, Air Station      0.026 (53/53)   0.025 (53/53)     0 Particulates                                        (0.009-0.078)       0.4 mi @ 3590 /N        (0.009-0.073)     (0.011-0.083)
(pCi/my)
GS              20 Be-7              0.015      0.061 (16/16)         P-06, Air Station      0.064 (4/4)       0.055 (4/4)     0 (0.040-0.075)       1.6 mi @ 129'/SE        (0.040-0.070)    (0.040-0.066)
Mn-54            0.0008          < LLD                                          --            < LLD        0 Co-58            0.0011          < LLD                    -                    -<              LLD        0 Co-60            0.0010          < LLD                    -                    -              < LLD          0 Zn-65            0.0013          < LLD                    -                    -              < LLD          0 Zr-Nb-95        0.0011          < LLD                    -                    -              < LLD          0 Ru-103          0.0009          < LLD                    -                      -            < LLD          0 Ru-106          0.0069          < LLD                    -                      -            < LLD          0 Cs-134          0.0006          < LD                                            -            < LLD          0 Cs-137            0.0007          <LLD                      -                    -             <LLD          0 Ba-La-140        0.0024          < LLD                      -                    -            < LLD          0 Ce-141            0.0013          < LLD                                                          <<-LLD        0 Ce-144            0.0036          < LLD                                            -<              LLD        0 1-131    264      0.07          < LLD                      -                      -            < LLD          0 Airborne Iodine (pG/rft) 20
 
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility              Prairie Island Nuclear Power Station                    Docket No.       50-282, 50-306 Location of Facility          Goodhue, Minnesota                                      Reporting Period January-December, 2000
( County, State )
Indicator                  Location with Highest                Control    Number Sample            Type and                        Locations                      Annual Mean                    Locations    Non Type              Number of        LLDb          Mean (F)Y                                    Mean (F)'        Mean (F)'   Routine (Units)           Analyses'                        Range'                Locationd              Range'          Range'      Results' Milk (pCi/L)      1-131            76      1.0           < LLD                                                          < LLD        0 GS              76 K-40              200        1481 (57/57)       P-14, Gustafson Farm      1524 (19/19)     1481 (19/19)     0 (1276-1756)           2.3 mi @ 173&deg;/S        (1367-1632)     (1347-1588)
Cs-134              15            < LLD                                                          < LLD        0 Cs-137              15            < LLD                                                          < LLD        0 Ba-La-140          15            < LLD                                                          < LLD        0 River Water    H-3              8      179          297(1/4)       P-6, Lock and Dam # 3        297(1/4)           < LLD          0 (pCi/L)                                                           1.6 mi @ 129'/SE GS                24 Mn-54              15          < LLD                                          -<                LLD        0 Fe-59              30          < LLD                                           -<               LLD         0 Co-58               15          < LLD                                           -<               LLD         0 Co-60               15          < LLD                     -                     -             < LLD         0 Zn-65               30          < LLD                                           -<               LLD         0 Zr-Nb-95           15            < LLD                                           -<               LLD         0 Cs-134              15            < LLD                     -                     -             < LLD         0 Cs-137             18            < LLD                                           -<               LLD         0 Ba-La-140           15            < LLD                                           -<               LLD         0 Ce-144              58            < LLD                                                 I      < LLD         0 21
 
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility               Prairie Island Nuclear Power Station                 Docket No.       50-282, 50-306 Location of Facility          Goodhue, Minnesota                                  Reporting Period January-December, 2000 (County, State)
Indicator               Location with Highest               Control     Number Sample             Type and                       Locations                     Annual Mean                 Locations     Non Type             Number of         LLD"        Mean (F)'                                Mean (F)'       Mean (F)'     Routine (Units)           Analysese                      Range'               Locationd             Range'           Range'     Results' Drinking Water GB                12      1.0         < LLD         P-11, Red Wing S.C.      10.1 (12/12)       None          0 (pCi/L)                                                           3.3 mi @ 158' /SSE        (5.2-12.9) 1-131            12      1.0          < LLD                                       -            None          0 H-3              4      179          < LLD                   -                                  None          0 GS                12 Mn-54              15           < LLD                   -                    -            None          0 Fe-59              30          < LLD                   -                    -            None          0 Co-58              15           < LLD                   -                    -            None          0 Co-60              15          < LLD                   -                    -            None          0 Zn-65              30          < LLD                   -                    -            None          0 Zr-Nb-95            15           < LLD                   -                    -            None            0 Cs-134              10          < LLD                   -                    -            None            0 Cs-137              10          < LLD                   -                   -            None            0 Ba-La-140          15           < LLD                   -                   -            None            0 Ce-144              59          < LLD                   -                    -            None          0 Well Water      H-3            20      180          < LLD                   -                     -           < LLD           0 (pCi/L)
GS              20 Mn-54                15          < LLD                   -                    -           < LLD           0 Fe-59                30          < LLD                   -                    -<             LLD         0 Co-58                15         < LLD                   -                     -<             LLD         0 Co-60                15          < LLD                    -                    -          <LLD            0 Zn-65                30          < LLD                    -                    -<            LLD          0 Zr-Nb-95            15          < LLD                    -                    -          < LLD          0 Cs-134              10          < LLD                    -                    -          < LLD          0 Cs-137             18         < LLD                     -                   -          < LLD           0 Ba-La-140           15         < LLD                                         -           < LLD         0 Ce-144             56          < LLD                    -                                < LLD          0 Crops - Cabbage 1-131              2    0.009        < LLD                     -                                < LLD           0 (pCi/gwet) 22
 
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility           Prairie Island Nuclear Power Station                   Docket No.       50-282,50-306 Location of Facility        Goodhue, Minnesota                                    Reporting Period January-December, 2000 (County, State)
Indicator               Location with Highest               Control     Number Sample             Type and                   Locations                       Annual Mean                 Locations     Non Type             Number of       LLDP        Mean (F)'                                   Mean (F)'       Mean (F)'     Routine (Units)           Analysese                     Range'             Location'              Range'           Range'     Results' Fish        GS              4 (pCi/g wet)          K-40            0.10       2.85 (2/2)         P-19, Upstream          3.58 (2/2)       3.28 (2/2)      0 (2.63-3.06)       1.3 mi. @ 0*&deg;/N          (3.42-3.73)      (3.07-3.48)
Mn-54         0.018          < LLD                   -                     -             < LLD          0 Fe-59         0.081          < LLD                     -                   -             < LLD          0 Co-58         0.015          < LLD                     -                   -             < LLD          0 Co-60         0.017          < LLD                     -                   -             < LLD          0 Zn-65         0.029          < LLD                     -                   -             < LLD          0 Zr-Nb-95       0.031          < LLD                     -                   -             < LLD          0 Cs-134         0.013          < LLD                     -                   -             < LLD          0 Cs-137         0.013          < LLD                     -                   -             < LLD          0 Ba-La-140       0.77          < LLD                     -                     -             < LLD         0 Invertebrates    GS              4 (pCi/g wet)          Be-7            0.55          < LLD                     -                     -             < LLD         0 K-40            1.48          < LLD                     -                     -             < LLD         0 Mn-54          0.063          < LLD                   -                     -<             LLD         0 Co-58           0.10          < LLD                   -                     -<             LLD         0 Co-60         0.069          < LLD                     -                   -<             LLD         0 Zn-65         0.12          < LLD                     -                   -             < LLD         0 Zr-Nb-95       0.13          < LLD                    -                    -            < LLD          0 Ru-103        0.078          < LLD                                          -            < LLD          0 Ru-106          0.40          < LLD                     -                   -             < LLD         0 Cs-134       0.071          < LLD                     -                   -             < LLD         0 Cs-137       0.057          < LLD                     -                     -           < LLD         0 Ba-La-140       0.61          < LLD                     -                     -            < LLD         0 Ce-141          0.11          < LLD                     -                    -           < LLD           0 Ce-144          0.24          <LLD                       -                   -            < LLD           0 23
 
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility               Prairie Island Nuclear Power Station                   Docket No.       50-282, 50-306 Location of Facility          Goodhue, Minnesota                                    Reporting Period January-December, 2000 (County, State)
Indicator                 Location with Highest               Control       Number Sample               Type and                       Locations                     Annual Mean                     Locations       Non Type             Number of         LLDb        Mean (F)'                                   Mean (F)'         Mean (F)'       Routine (Units)             Analyses'                        Range'             Location'               Range'           Range'       Results' Bottom and        GS             6 Shoreline            Be-7              0.30          < LLD                                                        < LLD            0 Sediments            K-40               0.10       6.94(4/4)         P-20, Upstream           8.79 (4/4)       8.79 (4/4)         0 (pCi/g dry)                                          (6.51-7.46)       0.9 mi. @ 45' /NE        (8.64-8.94)       (8.64-8.94)
Mn-54             0.021          < LLD                   -                     -             < LLD           0 Co-58            0.030          < LLD                   -                     -             < LLD           0 Co-60            0.016          < LLD                   -                     -             < LLD           0 Zn-65            0.066          < LLD                   -                     -             < LLD           0 Zr-Nb-95          0.030          < LLD                   -                     -             < LLD           0 Ru-103            0.023          < LLD                    -                      -             < LLD            0 Ru-106            0.18          < LLD                   -                     -             < LLD           0 Cs-134           0.030          < LLD                   -                     -             < LLD           0 Cs-137           0.024          < LLD                   -                     -             < LLD           0 Ba-La-140         0.062          < LLD                   -                     -             < LLD           0 Ce-141            0.044          < LLD                   -                     -             < LLD           0 Ce-144            0.10          < LLD                   -                     -             < LLD           0 "GB gross beta, GS = gamma scan.
' LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
' Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
dLocations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.
"Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.
24


==6.0 REFERENCES==
==6.0 REFERENCES==
 
CITED Arnold, J. R. and H. A. A1-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
CITED Arnold, J. R. and H. A. A1-Salih.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.
1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Environmental, Inc., Midwest Laboratory. 2001a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276. Environmental, Inc., Midwest Laboratory.
_           2001b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.
2001a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 2000. _ 2001b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 2000. 2000. Quality Assurance Program Manual, Rev. 0, 11 October 2000. 2000. Quality Control Procedures Manual, Rev. 0, 21 September 2000. 2000. Quality Control Program, Rev. 0, 12 October 2000. Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
2000.     Quality Assurance Program Manual, Rev. 0, 11 October 2000.
Hazleton Environmental Sciences Corporation.
2000.     Quality Control Procedures Manual, Rev. 0, 21 September 2000.
1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December 1978 through 1982. Hazleton Environmental Sciences Corporation.
2000.     Quality Control Program, Rev. 0, 12 October 2000.
1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December 1978 through 1982. Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.
Hazleton Environmental Sciences Corporation. 1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hazleton Environmental Sciences Corporation. 1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.       1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, No. 12, 730-746.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, No. 12, 730-746.
Northern States Power Company. 1972. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971. Minneapolis, Minnesota.
Northern States Power Company. 1972. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971. Minneapolis, Minnesota.
1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1972 to December 31, 1972. Minneapolis, Minnesota.
1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1972 to December 31, 1972. Minneapolis, Minnesota.
1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1, 1973 to December 31, 1973. Minneapolis, Minnesota.
1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1, 1973 to December 31, 1973. Minneapolis, Minnesota.
1979 to 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 1982 (prepared by Hazleton Environmental Sciences).
1979 to 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
Minneapolis, Minnesota.
1984 to 2000. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Minneapolis, Minnesota.
1984 to 2000. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory).
25
Minneapolis, Minnesota.
25  


==6.0 REFERENCES==
==6.0 REFERENCES==
CITED (continued)
Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
_    1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
U.S. Environmental Protection Agency . 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984.      Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p. 125.
Xcel Energy Corporation. 2001. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26
- "-.-.. Environmental, Inc.
      """Midwest Laboratory an Allegheny Technologies Co.
700 Landwetr Road
* Norbhbrook, IL 60062-2310 (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS studies administered by NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison serves as a replacement  for studies  conducted previously Environmental Resources Associates, and Laboratory,  Las Vegas,  Nevada. Results are by the U.S. EPA Environmental Monitoring Systems results,  in-house  spikes,  blanks, duplicates and reported in Appendix A. TLD Intercomparison results are  also reported. Appendix  A is updated mixed analyte performance evaluation program in  March,  June, September  and  December four times a year; the complete Appendix is included monthly progress reports only.
January, 2000 through December, 2000


CITED (continued)
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the by agencies formulation of it's quality control program in December 1971. These programs are operated samples (e.g., milk or water) containing concentrations   of radionuclides which supply environmental type program is to known to the issuing agency but not to participant laboratories. The purpose of such a any possible provide an independent check on a laboratory's analytical procedures and to alert it of problems.
Teledyne Brown Engineering Environmental Services, Midwest Laboratory.
them to the Participant laboratories measure the concentration of specified radionuclides and report reports  the  known  values  to the participant    laboratories issuing agency. Several months later, the agency higher  or  lower  than  the known   values   or  outside the and specifies control limits. Results consistently control limits indicate a need to check the instruments   or procedures   used.
1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1983 through 1999. _ 1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1983 through 1999. U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY. U.S. Environmental Protection Agency .1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
crosscheck The results in Table A-1 were obtained through participation in the environmental sample the past twelve months. Data for previous     years is program for milk, water and air filters during available upon request.
1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
Office of Research and This program was conducted by the U.S. Environmental Protection Agency Division-Las Vegas, Development National Exposure Research Laboratory Characterization Research Nevada.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p. 125. Xcel Energy Corporation.
(TLDs), via various The results in Table A-2 were obtained for Thermoluminescent Dosimeters listed in Table A-2.
2001. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 (prepared by Environmental, Inc., Midwest Laboratory).
International Intercomparisons of Environmental Dosimeters under the sponsorships Results of crosscheck testing with Teledyne Brown Engineering are also listed.
Northbrook, Illinois 26
past twelve months. All Table A-3 lists results of the analyses on in-house "spiked" samples for the upon request.
......-.:.: * .....:...  -"-.-.. Environmental, Inc.  """Midwest Laboratory an Allegheny Technologies Co. 700 Landwetr Road
samples are prepared using NIST traceable sources. Data for previous years available twelve months. Data for Table A-4 lists results of the analyses on in-house "blank" samples for the past previous years available upon request.
* Norbhbrook, IL 60062-2310 (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported.
months. Acceptance is based Table A-5 list results of the in-house "duplicate" program for the past twelve for previous years available on the difference of the results being less than the sum of the errors. Data upon request.
Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.January, 2000 through December, 2000 Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
Analyte Performance The results in Table A-6 were obtained through participation in the Mixed Evaluation Program.
The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
the Environmental Measurement The results in Table A-7 were obtained through participation in Laboratory Quality Assessment Program.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.
This program was conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada. The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of crosscheck testing with Teledyne Brown Engineering are also listed. Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for "spiked" samples.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.Al 12-31-00 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION:
Out-of-limit results are explained directly below the result.
ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter  
Al
>100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter  
 
>50 pCi/liter or kg 10% of known value Strontium_90b 2 to 30 pCi/liter or kg 5.0 pCi/liter  
12-31-00 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis                       Level                                   for single determinations Gamma Emitters             5 to 100 pCi/liter or kg                         5.0 pCi/liter
>30 pCi/liter or kg 10% of known value Potassium-40
                              >100 pCi/liter or kg                         5% of known value Strontium-89b               5 to 50 pCi/liter or kg                         5.0 pCi/liter
>0.1 g/liter or kg 5% of known value Gross alpha <_20 pCi/liter 5.0 pCi/liter  
                              >50 pCi/liter or kg                           10% of known value 2 to 30 pCi/liter or kg                         5.0 pCi/liter Strontium_90b
>20 pCi/liter 25% of known value Gross beta <100 pCi/liter 5.0 pCi/liter  
                              >30 pCi/liter or kg                         10% of known value
>100 pCi/liter 5% of known value Tritium 4,000 pCi/liter is = (pCi/liter)  
                            >0.1 g/liter or kg                             5% of known value Potassium-40
= 169.85 x (known)&deg;9  
                            <_20 pCi/liter                                 5.0 pCi/liter Gross alpha
>4,000 pCi/liter 10% of known value Radium-226,-228  
                            >20 pCi/liter                                   25% of known value
<0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, <55 pCi/liter 6.0 pCi/liter iodine_129b
                            <100 pCi/liter                                   5.0 pCi/liter Gross beta                                                                  5% of known value
>55 pCi/liter 10% of known value Uranium-238, <_35 pCi/liter 6.0 pCi/liter  
                            >100 pCi/liter
-35 0-C&#xa2;' Ilter 15% of known value Nickel-63  
                            *4,000 pCi/liter                                 is = (pCi/liter) =
.. '-- .. Technetium-99b 50 to 100 pCi/liter 10 pCi/liter Iron-55b >100 pCi/liter 10% of known value Others" 20% of known value "a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
Tritium                                                                        169.85 x (known)&deg;9
b Laboratory limit. A2 I Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a. Concentration in pCi/L Lab Sample Date Laboratory results ERA Resultd Control Code Type Collected Analysis +/-2 Sigmac Is, N=1 Limits STW-863 WATER Jan, 2000 Gr. Alpha 39.3 +/- 5.2 25.4 +/- 6.4 14.5 -36.3 The analysis was repeated and recalculated with Am-241 efficiency; result of reanalysis 29.32 +/- 5.79 pCi/L. Internal spike program results do not indicate a problem.
                            >4,000 pCi/liter                               10% of known value Radium-226,-228             <0.1 pCi/liter                                 15% of known value Plutonium                   0.1 pCi/liter, gram, or sample                 10% of known value
STW-863 WATER Jan, 2000 Gr. Beta 40.7 +/-1 .2 42.1 +/-4.2 33.4 -50.8 STW-866 WATER Jan, 2000 Sr-89 17.1 +/- 2.2 22.5 +/- 5.0 13.8 -31.2 STW-866 WATER Jan, 2000 Sr-90 8.1 +/- 0.6 9.6 +/- 5.0 0.9 -18.3 STW-868 WATER Feb, 2000 Ra-226 7.6 +/- 0.5 8.3 +/- 1.2 6.1 -10.4 STW-868 WATER Feb, 2000 Ra-228 5.6 +/- 1.0 2.3 +/- 0.6 1.3 -3.2 Result of reanalysis:
                            <55 pCi/liter                                   6.0 pCi/liter         I Iodine-131,
6.34 +/- 0.94. Activity confirmed by gamma spectroscopy (6.00 +/- 1.42 pCi/L ). STW-868 WATER Feb, 2000 Uranium 5.4+/-0.2 6.1+/-3.0 0.9- 11.3 STW-869 WATER Mar, 2000 H-3 23,500.0 +/- 306.0 23,800.0 +- 2,380.0 19,800.0 -27,800.0 STW-867 WATER Mar, 2000 Gr. Alpha 83.6 +/- 5.8 58.4 +/- 5.8 33.3 -83.5 Results were recalculated with Am-241 efficiency; 57.80 --+ 5.73 pCi/L. Refer to STW-863.
                            >55 pCi/liter                                   10% of known value iodine_129b
STW-867 WATER Mar, 2000 Gr. Beta 15.4+/-0.9 16.8+/-1.7 8.1 -25.5 STW-876 WATER Mar, 2000 1-131 18.7+/--0.6 19.9 -+/- 2.0 14.7- 25.1 STW-877 WATER Apr, 2000 Gr. Alpha 52.3 +/- 2.3 54.0 +/- 13.5 30.8 -77.2 STW-877 WATER Apr, 2000 Ra-226 17.5 +/- 1.1 18.6 +/- 2.8 13.8 -23.4 STW-877 WATER Apr, 2000 Ra-228 3.7 +/- 0.4 3.6 +/- 0.9 2.0 -5.1 STW-878 WATER Apr, 2000 Co-60 19.2 +/- 0.6 16.9 +/- 5.0 8.2 -25.6 STW-878 WATER Apr, 2000 Cs-134 81.0 +/- 1.3 86.4 +/- 5.0 77.7 -95.1 STW-878 WATER Apr, 2000 Cs-137 119.0 +/- 2.6 123.0 +/- 6.2 112.0 -134.0 STW-878 WATER Apr, 2000 Gr. Beta 276.0 +/- 9.6 289.0 +/- 43.4 214.0 -364.0 STW-878 WATER Apr, 2000 Sr-89 32.3 +/- 3.3 50.7 +/-5.0 42.0 -59.4 STW-878 WATER Apr, 2000 Sr-90 11.3 +/- 1.0 32.8 +/- 5.0 24.1 -41.5 An error was found in calculation.
                            <_35 pCi/liter                                   6.0 pCi/liter Uranium-238,              -35       Ilter 0-C&#xa2;'                                     15% of known value Nickel-63 ..'--                     ..
Result of recalculation:
Technetium-99b 50 to 100 pCi/liter                             10 pCi/liter Iron-55b                   >100 pCi/liter                                   10% of known value Others"                                                                   20% of known value "aFrom EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
Sr-89, 55.5+/- 7.2 pCi/L / Sr-90, 30.7 +/- 3.0 pCi/L. Results of reanalysis:
b Laboratory limit.
Sr-89, 47.4 +/- 14.5 pCi/L / Sr-90, 33.0 +/- 1.35 pCi/L. Both results are within limits. STW-879 WATER Jun, 2000 Ba-133 22.4 +/- 2.1 25.5 +/- 5.0 16.8 -34.2 STW-879 WATER Jun, 2000 Co-60 69.9 +/- 3.7 65.6 +/- 5.0 56.9 -74.3 STW-879 WATER Jun, 2000 Cs-134 13.5 +/- 0.8 13.8 +/-5.0 5.1 -22.5 STW-879 WATER Jun, 2000 Cs-137 232.0 +/- 7.8 238.0 +/- 11.9 217.0 -259.0 STW-879 WATER Jun, 2000 Zn-65 50.9 +/- 3.8 54.6 +/- 5.5 45.3 -63.9 STW-880 WATER Jun, 2000 Ra-226 2.8 +/-0.2 3.0 +/-0.5 2.2- 3.8 STW-880 WATER Jun, 2000 Ra-228 10.0 +/- 0.9 13.0 +/- 3.3 7.4 -18.6 STW-880 WATER Jun, 2000 Uranium 57.0 +/- 4.4 63.4 +/- 6.3 52.6 -74.2 STW-883 WATER Jul, 2000 Gr. Alpha 6.9 +/- 1.1 7.2 +/- 5.0 0.0 -15.9 STW-883 WATER Jul, 2000 Gr. Beta 88.8 +/- 9.8 87.5 +/- 10.0 70.2 -105.0 STW-884 WATER Aug, 2000 H-3 8,740.0 +/- 174.0 8,320.0 +/- 832.0 6,910.0 -9,730.0 STW-891 WATER Sep, 2000 Ra-226 17.9 +/- 1.3 18.9 +/- 2.8 14.0 -23.8 STW-891 WATER Sep,20 0 0 Ra-228 5.7 +/-0.5 6.2 +/-1.6 3.5-8.8 Al-1 Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a. Concentration in pCi/Lb Lab Sample Date Laboratory results ERA Resultd Control Code Type Collected Analysis +/-2 Sigmac 1s, N=1 Limits Uranium 1-131 1-131(g) Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-134 Cs-137 Gr. Beta Sr-89 Sr-90 Gr. Alpha Gr. Beta Ba-133 Co-60 Cs-134 10.3 +/- 0.1 16.9 +/- 0.3 17.1 +/-5.4 66.3 +/- 5.3 10.1+/- 1.0 21.2 +/- 0.5 41.4+/-1.9 93.4 +/- 1.6 54.8 +/- 0.3 45.5 +/-2.3 209.0 +/- 7.9 32.8 +/- 3.0 16.0 +/- 2.4 50.3 +/- 2.6 28.6 +/- 1.3 78.0 +/- 2.0 30.8+/-k 1.7 67.2 +/- 3.3 11.9 +/-3.0 15.9 +/- 1.6 15.9 +/-1.6 74.4 +/- 18.6 10.5 +/- 1.6 19.4+/-4.9 44.5 +/- 4.5 91.1 +/-5.0 59.8 +/- 5.0 45.0 +/-5.0 256.0 +/- 38.4 41.3 +/- 5.0 18.0 +/- 5.0 60.3 +/- 15.1 25.5 +/-5.0 82.2 +/- 8.2 27.8 +/-5.0 76.0 +/-5.0 6.7- 17.1 10.7- 21.1 10.7- 21.1 42.2- 107.0 7.8- 13.2 11.0- 27.8 36.8 -52.2 82.4- 99.8 51.1 -68.5 36.3 -53.7 189.0 -323.0 32.6- 50.0 9.3 -26.7 34.4- 86.2 16.8 -34.2 68.0- 96.4 19.1 -36.5 67.3 -84.7 The mean value for Cs-134 of all participating laboratories was 70.7 pCi/L. Other gamma emitters are within limits, the counting efficiency is not suspect. Library values were reviewed and found to be correct.WATER Nov, 2000 Cs-137 WATER Nov. 2000 Zn-65 109.0 +/- 1.0 81.5 +/- 7.4 106.0 +/-5.3 79.0 + 7.9 96.8- 115.0 65.3 -92.7 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA). b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.
A2
 
Associates (ERA)a.
Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Concentration in pCi/L Laboratory results           ERA Resultd             Control Lab            Sample          Date
                                                                +/-2 Sigmac                 Is, N=1               Limits Code              Type        Collected    Analysis 39.3 +/- 5.2               25.4 +/- 6.4           14.5 - 36.3 STW-863            WATER        Jan, 2000 Gr. Alpha efficiency; result of reanalysis   29.32 +/- 5.79 pCi/L.
The analysis was repeated and recalculated with Am-241 Internal spike program results do not indicate a problem.
40.7 +/-1 .2             42.1 +/-4.2             33.4 - 50.8 STW-863            WATER         Jan, 2000 Gr. Beta 17.1 +/- 2.2               22.5 +/- 5.0           13.8 - 31.2 STW-866             WATER         Jan, 2000 Sr-89 8.1 +/- 0.6               9.6 +/- 5.0           0.9 - 18.3 STW-866            WATER         Jan, 2000 Sr-90 7.6 +/- 0.5               8.3 +/- 1.2           6.1 - 10.4 STW-868             WATER         Feb, 2000 Ra-226 5.6 +/- 1.0               2.3 +/- 0.6           1.3 - 3.2 STW-868            WATER        Feb, 2000 Ra-228 gamma spectroscopy (6.00 +/- 1.42 pCi/L ).
Result of reanalysis: 6.34 +/- 0.94. Activity confirmed by                                                  0.9- 11.3 5.4+/-0.2                 6.1+/-3.0 STW-868            WATER         Feb, 2000 Uranium Mar, 2000 H-3               23,500.0 +/- 306.0         23,800.0 +-2,380.0 19,800.0 - 27,800.0 STW-869            WATER 83.6 +/- 5.8             58.4 +/- 5.8           33.3 - 83.5 STW-867            WATER        Mar, 2000 Gr. Alpha 57.80 --+ 5.73 pCi/L. Refer to STW-863.
Results were recalculated with Am-241 efficiency;                                                          8.1 -25.5 15.4+/-0.9                 16.8+/-1.7 STW-867            WATER       Mar, 2000 Gr. Beta 18.7+/--0.6               19.9 -+/-2.0           14.7-   25.1 STW-876            WATER       Mar, 2000 1-131 52.3 +/- 2.3               54.0 +/- 13.5         30.8 - 77.2 STW-877             WATER         Apr, 2000 Gr. Alpha 17.5 +/- 1.1               18.6 +/- 2.8           13.8 - 23.4 STW-877             WATER         Apr, 2000 Ra-226 3.7 +/- 0.4               3.6 +/- 0.9           2.0 - 5.1 STW-877            WATER         Apr, 2000 Ra-228 19.2 +/- 0.6             16.9 +/- 5.0             8.2 - 25.6 STW-878           WATER         Apr, 2000 Co-60 81.0 +/- 1.3             86.4 +/- 5.0           77.7 - 95.1 STW-878           WATER         Apr, 2000 Cs-134 119.0 +/- 2.6             123.0 +/- 6.2         112.0 - 134.0 STW-878           WATER         Apr, 2000 Cs-137 276.0 +/- 9.6             289.0 +/- 43.4         214.0 - 364.0 STW-878             WATER         Apr, 2000 Gr. Beta 32.3 +/- 3.3               50.7 +/-5.0           42.0 - 59.4 STW-878             WATER         Apr, 2000 Sr-89 11.3 +/- 1.0               32.8 +/- 5.0           24.1 - 41.5 STW-878            WATER        Apr, 2000 Sr-90 Sr-89, 55.5+/- 7.2 pCi/L / Sr-90, 30.7 +/- 3.0 pCi/L.
An error was found in calculation. Result of recalculation:                                                 limits.
Sr-90, 33.0 +/- 1.35 pCi/L. Both results are within Results of reanalysis: Sr-89, 47.4 +/- 14.5 pCi/L /                                                        16.8  - 34.2 22.4 +/- 2.1               25.5 +/- 5.0 STW-879             WATER         Jun, 2000 Ba-133 69.9 +/- 3.7             65.6 +/- 5.0           56.9 - 74.3 STW-879           WATER         Jun, 2000 Co-60 13.5 +/- 0.8               13.8 +/-5.0             5.1 - 22.5 STW-879           WATER         Jun, 2000 Cs-134 232.0 +/- 7.8             238.0 +/- 11.9         217.0 - 259.0 STW-879           WATER         Jun, 2000 Cs-137 50.9 +/- 3.8               54.6 +/- 5.5           45.3 - 63.9 STW-879            WATER         Jun, 2000 Zn-65 2.8 +/-0.2                 3.0 +/-0.5             2.2- 3.8 STW-880           WATER         Jun, 2000 Ra-226 10.0 +/- 0.9               13.0 +/- 3.3           7.4 - 18.6 STW-880           WATER         Jun, 2000 Ra-228 57.0 +/- 4.4               63.4 +/- 6.3           52.6 - 74.2 STW-880            WATER         Jun, 2000 Uranium 6.9 +/- 1.1               7.2 +/- 5.0           0.0 - 15.9 STW-883           WATER           Jul, 2000 Gr. Alpha 88.8 +/- 9.8               87.5 +/- 10.0           70.2 - 105.0 WATER         Jul, 2000 Gr. Beta STW-883                                                                              8,320.0 +/- 832.0       6,910.0 - 9,730.0 WATER         Aug, 2000 H-3              8,740.0 +/- 174.0 STW-884                                                                                    18.9 +/- 2.8           14.0 - 23.8 Sep,  2000  Ra-226              17.9 +/- 1.3 STW-891           WATER                                                                                         3.5-8.8 5.7 +/-0.5                 6.2 +/-1.6 STW-891            WATER        Sep,200 0 Ra-228 Al-1
 
Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration in pCi/Lb Lab             Sample         Date                     Laboratory results     ERA Resultd         Control Code               Type       Collected     Analysis       +/-2 Sigmac             1s, N=1           Limits STW-891            WATER        Sep, 2000 Uranium               10.3 +/- 0.1           11.9 +/-3.0          6.7- 17.1 WATER        Oct, 2000 1-131                  16.9 +/- 0.3          15.9 +/- 1.6      10.7-   21.1 STW-892 STW-892            WATER        Oct, 2000 1-131(g)              17.1 +/-5.4           15.9 +/-1.6        10.7- 21.1 WATER        Oct, 2000 Gr. Alpha              66.3 +/- 5.3          74.4 +/- 18.6     42.2- 107.0 STW-893 WATER        Oct, 2000 Ra-226                10.1+/- 1.0           10.5 +/- 1.6        7.8- 13.2 STW-893 WATER        Oct, 2000 Ra-228                21.2 +/- 0.5          19.4+/-4.9        11.0-  27.8 STW-893 WATER        Oct, 2000 Uranium                41.4+/-1.9            44.5 +/- 4.5      36.8 - 52.2 STW-893 WATER        Oct, 2000 Co-60                  93.4 +/- 1.6           91.1 +/-5.0        82.4- 99.8 STW-894 WATER        Oct, 2000 Cs-134                54.8 +/- 0.3          59.8 +/- 5.0      51.1 - 68.5 STW-894 WATER        Oct, 2000 Cs-137                45.5 +/-2.3            45.0 +/-5.0       36.3 - 53.7 STW-894 WATER        Oct, 2000 Gr. Beta              209.0 +/- 7.9        256.0 +/- 38.4      189.0 - 323.0 STW-894 WATER        Oct, 2000 Sr-89                  32.8 +/- 3.0           41.3 +/- 5.0       32.6- 50.0 STW-894 Oct, 2000 Sr-90                  16.0 +/- 2.4          18.0 +/- 5.0         9.3 - 26.7 STW-894            WATER Nov, 2000 Gr. Alpha              50.3 +/- 2.6          60.3 +/- 15.1      34.4- 86.2 STW-895            WATER Nov, 2000 Gr. Beta              28.6 +/- 1.3          25.5 +/-5.0       16.8 - 34.2 STW-895            WATER Nov, 2000 Ba-133                78.0 +/- 2.0          82.2 +/- 8.2       68.0- 96.4 STW-896            WATER Nov, 2000 Co-60                  30.8+/-k 1.7           27.8 +/-5.0        19.1 - 36.5 STW-896            WATER WATER        Nov, 2000 Cs-134                 67.2 +/- 3.3          76.0 +/-5.0        67.3 - 84.7 STW-896 The mean value for Cs-134 of all participating laboratories was 70.7 pCi/L. Other gamma emitters are within limits, the counting efficiency is not suspect. Library values were reviewed and found to be correct.
STW-896            WATER        Nov, 2000    Cs-137            109.0 +/- 1.0          106.0 +/-5.3        96.8- 115.0 STW-896            WATER        Nov. 2000    Zn-65             81.5 +/- 7.4           79.0 + 7.9       65.3 - 92.7 STW-896 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.
Unless otherwise indicated, the laboratory results are given as the mean +/- 2 standard deviations for three determinations.
Unless otherwise indicated, the laboratory results are given as the mean +/- 2 standard deviations for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.A1-2 STW-891 STW-892 STW-892 STW-893 STW-893 STW-893 STW-893 STW-894 STW-894 STW-894 STW-894 STW-894 STW-894 STW-895 STW-895 STW-896 STW-896 STW-896 WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Sep, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Oct, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 Nov, 2000 STW-896 STW-896 STW-896 Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Laboratory results Known Average +/- 2 Sigma Code TLD Type Date Measurement  
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
+/-2 Sigma Value (All Participants)
A1-2
Environmental.
 
Inc. 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #1 14.5 +/- 0.5 15.4 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #2 29.3 +/- 1.0 31.8 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #3 60.0_L0.2 59.1 Environmental, Inc. 1999-2 CaSO 4: Dy Cards Mar, 1999 Reader 1, #1 18.3 +/- 0.5 15.4 1999-2 CaSO 4: Dy Cards Mar, 1999 Reader 1, #2 35.9+/- 1.3 31.8 1999-2 CaSO 4: Dy Cards Mar, 1999 Reader 1, #3 66.5 +/- 4.4 59.1 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 1999. Environmental, Inc. 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #1 14.4+/- 0.2 17.8 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #2 32.4_+/- 0.1 35.5 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #3 61.8 +/- 0.9 62.2 Environmental, Inc. 2000-2 CaSO 4: Dy Cards Mar, 2000 Reader 1, #1 21.3 +/- 0.3 17.8 2000-2 CaSO 4: Dy Cards Mar, 2000 Reader 1, #2 40.1 +/- 1.9 35.5 2000-2 CaSO 4: Dy Cards Mar, 2000 Reader 1, #3 69.9 +/-3.5 62.2 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 2000.A2-1 Table A-3. In-house "spike" samples.
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
Concentration in pCi/La Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s, n=lb Activity Limits SPW-271 WATER Jan, 2000 Ra-226 14.81 +/- 0.44 SPW-271 WATER Jan, 2000 Ra-228 16.97 +/- 2.12 SPW-272 WATER Jan, 2000 Gr. Alpha 44.35 +/- 1.95 SPW-272 WATER Jan, 2000 Gr. Beta 31.19 +/- 5.02 SPW-756 WATER Jan, 2000 H-3 56339.00 +/- 666.00 5 SPW-480 WATER Jan, 2000 Co-60 32.33 +/- 2.87 SPW-480 WATER Jan, 2000 Cs-137 35.58 +/- 4.20 SPMI-482 MILK Jan, 2000 Sr-90 16.93 +/- 1.07 SPAP-484 AIR FILTER Jan, 2000 Cs-137 1.84 +/- 0.01 SPW-917 WATER Feb, 2000 Gr. Alpha 16.59 +/- 1.90 An insufficient amount of Am-241 spike was available for an accurate test. SPW-917 WATER Feb, 2000 Gr. Beta 32.61 +/- 2.06 SPW-918 WATER Feb, 2000 Ra-226 21.15 +/- 0.49 SPW-918 WATER Feb, 2000 Ra-228 14.24+/- 1.64 SPVE-1262 VEGETATION Mar, 2000 1-131(g) 1.17+/- 0.07 SPCH-1264 CHARCOAL Mar, 2000 1-131(g) 0.56 +/- 0.02 CANISTER SPMI-1274 MILK Mar, 2000 1-131 47.02 +/-3.36 SPW-1301 WATER Mar, 2000 1-131 66.03 +/-1.06 SPW-1301 WATER Mar, 2000 1-131(g) 80.31 +/- 6.28 SPW-1477 WATER Mar, 2000 Gr. Alpha 32.09 +/- 1.82 SPW-1477 WATER Mar, 2000 Gr. Beta 29.20+/-1.56 SPW-1478 WATER Mar, 2000 Ra-226 21.78+/- 0.47 SPW-1478 WATER Mar, 2000 Ra-228 14.41 +/- 1.70 SPMI-2275 MILK Apr, 2000 Cs-134 33.53 +/- 2.82 SPMI-2275 MILK Apr, 2000 Cs-137 36.38 +/-4.94 SPMI-2275 MILK Apr, 2000 1-131 46.06 +/- 0.82 SPW-2277 WATER Apr, 2000 Ra-226 20.51 +/- 0.44 SPW-2278 WATER Apr, 2000 Gr. Alpha 40.22 +/-2.50 SPW-2278 WATER Apr, 2000 Gr. Beta 32.63 +/- 1.81 SPW-2278 WATER Apr, 2000 Ra-228 14.91 +/- 1.70 SPW-2279 WATER Apr, 2000 Co-60 37.12_+/- 3.86 SPW-2279 WATER Apr, 2000 Cs-134 34.70+/- 3.32 SPW-2279 WATER Apr, 2000 Cs-137 39.60+/- 5.12 SPW-2279 WATER Apr, 2000 1-131 49.92 +/- 0.67 SPW-2279 WATER Apr, 2000 1-131(g) 60.63 +/- 6.58 SPW-2281 WATER Apr, 2000 H-3 58829.00 +/-682.00 SPAP-3097 AIR FILTER Apr, 2000 Cs-137 1.81 +/- 0.02 SPW-3093 WATER May, 2000 1-131 83.39 +/- 1.06 SPW-3094 WATER May, 2000 Ra-226 20.86-+/- 0.42 SPW-3094 WATER May, 2000 Ra-228 14.17+/- 1.59 qPW-3f95 WATER Mav. 2000 Gr. Aloha 38.99 +/- 2.09 13.76 14.68 41.14 29.50 7667.00 28.36 36.83 14.10 1.72 41.10 29.43 20.68 14.51 1.12 0.53 48.00 76.84 76.84 41.13 29.38 20.69 14.39 32.12 36.66 55.50 20.68 38.44 29.30 14.25 34.54 32.12 36.66 55.50 55.50 56996.00 1.71 85.38 20.68 14.12 38.44 9.63 -17.89 10.28 -19.08 20.57 -61.71 19.50 -39.50 46133.60 -69200.40 18.36 -38.36 26.83 -46.83 4.10 -24.10 1.03 -2.41 20.55 -61.65 19.43 -39.43 14.48 -26.88 10.16 -18.86 0.67- 1.57 0.32 -0.74 36.00 -60.00 61.47 -92.21 66.84 -86.84 20.57 -61.70 19.38 -39.38 14.48 -26.90 10.07 -18.71 22.12 -42.12 26.66 -46.66 44.40 -66.60 14.48 -26.88 19.22 -57.66 19.30 -39.30 9.98- 18.53 24.54 -44.54 22.12 -42.12 26.66 -46.66 44.40 -66.60 45.50 -65.50 45596.80 -68395.20 1.03- 2.39 68.30 -102.46 14.48 -26.88 9.88- 18.36 19.22 -57.66 A3-1, ,
mR Lab                                                 Laboratory results   Known     Average +/- 2 Sigma Code         TLD Type       Date     Measurement       +/-2 Sigma         Value     (All Participants)
Environmental. Inc.
LiF-100 Chips     Mar, 1999 Reader 1, #1       14.5 +/- 0.5     15.4 1999-1 1999-1    LiF-100 Chips     Mar, 1999 Reader 1, #2       29.3 +/- 1.0     31.8 LiF-100 Chips     Mar, 1999   Reader 1, #3     60.0_L0.2     59.1 1999-1 Environmental, Inc.
Mar, 1999   Reader 1, #1     18.3 +/- 0.5     15.4 1999-2 CaSO 4: Dy Cards CaSO 4: Dy Cards  Mar, 1999   Reader 1, #2     35.9+/- 1.3       31.8 1999-2 CaSO 4: Dy Cards   Mar, 1999   Reader 1, #3     66.5 +/- 4.4     59.1 1999-2 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 1999.
Environmental, Inc.
Mar, 2000   Reader 1, #1       14.4+/- 0.2     17.8 2000-1   LiF-100 Chips Mar, 2000   Reader 1, #2       32.4_+/- 0.1     35.5 2000-1   LiF-100 Chips Mar, 2000   Reader 1, #3       61.8 +/- 0.9     62.2 2000-1    LiF-100 Chips Environmental, Inc.
Mar, 2000   Reader 1, #1       21.3 +/- 0.3     17.8 2000-2 CaSO4 : Dy Cards Mar, 2000   Reader 1, #2       40.1 +/- 1.9     35.5 2000-2 CaSO 4: Dy Cards Mar, 2000   Reader 1, #3       69.9 +/-3.5     62.2 2000-2  CaSO 4: Dy Cards Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 2000.
A2-1
 
Table A-3. In-house "spike" samples.
Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3095 SPAP-274 SPMI-3138 SPF-3180 SPF-3180 SPAP-3902
Concentration in pCi/La Lab              Sample        Date                    Laboratory results Known                  Control' Code              Type      Collected Analysis                2s, n=lb      Activity            Limits SPW-271              WATER      Jan, 2000 Ra-226              14.81 +/- 0.44        13.76            9.63 - 17.89 16.97  +/- 2.12      14.68          10.28  - 19.08 SPW-271              WATER      Jan, 2000 Ra-228 44.35 +/- 1.95        41.14          20.57  - 61.71 SPW-272              WATER
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5 In rounding off, the following rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged.
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
As an example, 11.443 is rounded off to 11.44. 4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.B-2 APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1 Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa. Air (pCi/m 3) Water (pCi/L) Gross alpha I x 10-3 Strontium-89 8,000 Gross beta 1 Strontium-90 500 Iodine-131b 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x 10 6 a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.
Concentrations may be averaged over a period not greater than one year. b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
B-2
 
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
 
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCi/m 3 )                                                       Water (pCi/L)
Gross alpha       I x 10- 3                                                 Strontium-89               8,000 Gross beta         1                                                         Strontium-90                   500 Iodine-131b       2.8 x 10- 1                                               Cesium-137                 1,000 Barium-140                 8,000 Iodine-131                 1,000 Potassium-40c               4,000 Gross alpha                     2 Gross beta                     10 Tritium                   1 x 106 a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
c A natural radionuclide.
C-2 APPENDIX D Sampling Location Maps D-1 TLD LOCATIONS ONE MILE RADIUS J PLANT AREA ENLARGED PLAN[1.00 MILE RADIUS][NO SCALE]MONITORING LEGEND: C) N.S.P. TLD POINTS D-2 TLD0LOGN D-2 TLDOI.DGN TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND: 0 N.S.P. TLD POINTS D-3 TLD02.DGN TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND: 0 N.S.P. TLD POINTS D-4 TLD03.DGN ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS] [NO SCALE]MONITORING LEGEND <$> MILK SAMPLING POINT IM NUMBERS P-14. P-18. P-37. P-41 AIR SAMPLING POINT ID NUMBERS P-1, P-2. P-3, P-4, P-S WATER SAMPLING POINT ID NUMBERS P-5, P-B, P-8. P-9. P-11, P-24, P-41 El VEGETATION
C-2
/ VEGETABLES ID NUMBERS P-24. P-38 e]FISH SAMPLING POINT ID NUMBERS P-13, P-19 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT ID NUMBERS P-f. P-12, P-20 D-5 SAMPOI.DGN ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS 4.7 MONITORING LEGEND S>MILK SAMPLING POINT ID NUMBERS P-14. P-18. P-37, P-41 AIR SAMPLING POINT ID NUMBERS P-i, P-2, P-3, P-4, P-6 S)WATER SAMPLING POINT ID NUMBERS P-5. P-6. P-B, P-9. P-11, P-24, P-41 VEGETATION
 
/ VEGETABLES ID NUMBERS P-24, P-38 FISH SAMPLING POINT ID NUMBERS P-13o P-i9 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT ID NUMBERS P-S. P-12, P-20 D-6 SAMP03.DGN ENVIRONMENTAL SAMPLING POINTS CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND 4. MILK SAMPLING POINT ID NUMBERS P-14, P-18, P-37, P-41 A AIR SAMPLING POINT ID NUMBERS P-i. P-2, P-3. P-4. P-6 0 WATER SAMPLING POINT ID NUMBERS P-5, P-6,, P-8, P-% P-11. P-41 n VEGETATION  
APPENDIX D Sampling Location Maps D-1
/ VEGETABLES ID NUMBERS P-24, P-38 D-7 SAMP02.DGN P-1 ()<) HUPPERT FARM. W 1430 ST RD 29, FRVER FALLS, WL E] CAIN RESIDENCE, N73%5 % ST. RIVER FALLS, D-7 SAMP02.DGN}}
 
TLD LOCATIONS ONE MILE RADIUS J
PLANT AREA ENLARGED PLAN     [1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEGEND:
C) N.S.P. TLD POINTS D-2                               TLDOI.DGN D-2                               TLD0LOGN
 
TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:
0 N.S.P. TLD POINTS D-3                           TLD02.DGN
 
TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:
0 N.S.P. TLD POINTS D-4                             TLD03.DGN
 
ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J
PLANT AREA ENLARGED PLAN                 [1.00 MILE RADIUS]
[NO SCALE]
MONITORING LEGEND
<$>                                                 FISH SAMPLING POINT ID NUMBERS MILK SAMPLING POINT IM NUMBERS P-14. P-18. P-37. P-41                   e]  P-13, P-19 A*    AIR SAMPLING POINT ID NUMBERS P-1, P-2. P-3, P-4, P-S INVERTEBRATES POINT ID NUMBERS P-6. P-40 WATER SAMPLING POINT ID NUMBERS P-5, P-B, P-8. P-9. P-11, P-24, P-41 SEDIMENT SAMPLING POINT ID NUMBERS P-f. P-12, P-20 El  VEGETATION / VEGETABLES ID NUMBERS P-24. P-38 D-5                                 SAMPOI.DGN
 
ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS 4.7 MONITORING LEGEND SAMPLING POINT ID NUMBERS                    FISH SAMPLING POINT ID NUMBERS P-14. P-18. P-37, P-41                             P-13o P-i9 A*    AIR SAMPLING POINT ID NUMBERS P-i, P-2, P-3, P-4, P-6 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SAMPLING POINT ID NUMBERS                  SEDIMENT SAMPLING POINT ID NUMBERS P-5. P-6. P-B, P-9. P-11, P-24, P-41               P-S. P-12, P-20 r*    VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 D-6 SAMP03.DGN
 
ENVIRONMENTAL SAMPLING POINTS P-1
()<)    HUPPERT FARM. W 1430 ST RD 29, FRVER FALLS, WL E] CAIN RESIDENCE, N73%5 %  ST. RIVER FALLS, W*.
CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND
: 4. MILK SAMPLING POINT ID NUMBERS P-14, P-18, P-37, P-41 A     AIR SAMPLING POINT ID NUMBERS P-i. P-2, P-3. P-4. P-6 0     WATER SAMPLING POINT ID NUMBERS P-5, P-6,, P-8, P-% P-11. P-41 n VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 D-7                                       SAMP02.DGN D-7                                       SAMP02.DGN}}

Latest revision as of 10:36, 28 March 2020

2000 Annual Radiological Environmental Monitoring Report
ML011380003
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/15/2001
From: Sorensen J
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, -RFPFR
Download: ML011380003 (68)


Text

Committed to Nuclear Excellence~r" Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East

  • Welch MN 55089 May 15, 2001 Prairie Island Technical Specifications 6.6.B US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 72-10 SNM-2506 2000 Annual Radiological Environmental Monitoring Report In accordance with the Prairie Island Nuclear Generating Plant Technical Specifications, Appendix A to Operating License DPR-42 and DPR-60, and in accordance with the Prairie Island Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License DNM-2506, we are submitting one copy of the Annual Radiological Environmental Monitoring Report covering the period January 1, 2000 through December 31, 2000.

Please contact us if you have any questions related to the information we have provided.

J T'oel P. Sorensen Site Vice President Prairie Island Nuclear Generating Plant c: Regional Administrator, III, NRC Region III Attn: Dr. John House NRC Project Manager Director of NMSS Sr. Resident Inspector, NRC State of Minnesota Attn: Tim Donakowski J. Silberg

Attachment:

Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1, 2000 through December 31, 2000.

-- *: Environmental, Inc.

Midwest Laboratory 11" an Alleheny Technologies Co.

700 Landwehr Road -Noffý IL 60062-2310 ph. (847) 564-0700 fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2000 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

3b, M.S.

Manager Oec.-7ýjoe

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, operated by Nuclear Management Company, LLC for Xcel Energy Corporation. The report was prepared by Environmental, Inc., Midwest Laboratory.

ii

TABLE OF CONTENTS Section Page Preface .................................................................................................................................. ii List of Tables ....................................................................................................................... iv List of Figures ........................................................................................................................ v

1.0 INTRODUCTION

............................................................................... 1 2.0 SUMM ARY ...................................................................................................................... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ......................... 3 3.1 Program Design and Data Interpretation ................................................................. 3 3.2 Program Description .............................................................................................. 4 3.3 Program Execution .............................................................................................. 5 3.4 Laboratory Procedures ............................................................................................. 6 3.5 Program M odifications ............................................................................................. 6 3.6 Land Use Census ........................................................................................................... 6 4.0 RESULTS AND DISCUSSION .......................................................................................... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ........................................ 7 4.2 Summ ary of Preoperational Data .............................................................................. 7 4.3 Program Findings ................................................................................................. 8 5.0 FIGURES AND TABLES ..................................................................................................... 12

6.0 REFERENCES

CITED ......................................................................................................... 25 APPENDICES A Interlaboratory Comparison Program Results ............................................................... A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Samples ............................................... A-2 B Data Reporting Conventions ........................................................................................ B -1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ....................................................... C-1 D Sampling Location M aps .............................................................................................. D-1 iii

LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ............................................................................ 13 5.2 Sampling Locations ................................................................................................................ 14 5.3 Missed Collections and Analyses ........................................................................................ 17 5.4 Radiation Environmental Monitoring Program Summary .................................................. 20 In addition, the following tables are in the Appendices:

Appendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results ................................ Al-i A-2 Crosscheck Program Results; (TLDs) .................................................................................. A2-1 A-3 In-house "Spiked" Samples ............................................................................................ A3-1 A-4 In-house "Blank" Samples .................................................................................................. A4-1 A-5 In-house "Duplicate" Samples ........................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ......................................................... A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results ........................................................................................... A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas .................................................................. C-2 iv

LIST OF FIGURES No. Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control, 1985-2000 ................................................................................... 18 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i), 1985-2000 ........................................ 19 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January December, 2000. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.

Tabulations of the individual analyses made during the year are not included in this report. These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2001b) available at Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974.

Commercial operation at full power began on 21 December 1974.

1

2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.

Results for 2000 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.

2

3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

In interpreting the data, effects due to the plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese 54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation 3

3.1 Program Design and Data Interpretation (continued) of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g.,

atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2000).

Maps of fixed sampling locations are included in Appendix E.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine 131. A quarterly composite of the particulate filters from each location is gamma-scanned on an HPGe detector. One of the five locations is a control (P-l), and four are indicators (P 2, P-3, P-4, and P-6).

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for the inner ring, outer ring and special interest locations are placed in the field at the same time as regular sets.

The emergency set is returned to EIML quarterly for annealing and repackaging.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

Milk samples are collected monthly from five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at two locations, one 4

3.2 Program Description (continued) upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.

3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:

(1) No air particulate/air iodine samples were available from location P-3 for the week ending 06-14-00, due to sampler pump failure.

(2) TLD data was not available from location P-10B for the fourth quarter, 2000.

Both the regular and emergency TLDs were lost in the field, due to unusually deep snow.

Deviations from the program are summarized in Table 5.3.

3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting. All gamma-spectroscopic analyses were performed with an HPGe detector. Levels of airborne iodine-131 in charcoal samples were measured by gamma spectrometry.

Levels of iodine-131 in cabbage and were determined by gamma spectrometry.

Tritium levels were determined by liquid scintillation technique.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection. Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.

5

3.5 Program Modifications Special tritium sampling of ground and well water was monitored from 1989 through 1999 at several locations. Tritium concentrations in that time have dropped to below detection levels. The program has been discontinued for the year 2000. The Suter residence, (P-24) was retained from the program, and added to the REMP in 2000, as a monitored well water location.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The 2000 Land Use Census was completed in October, 2000. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2000. The critical receptor location did not change in 2000, based on the results of the land use census.

No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.

Therefore, no corn samples were collected for analysis.

6

4.0 RESULTS AND DISCUSSION All scheduled collections and analyses were made except those listed in Table 5.3.

The results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2000. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents at nuclear reactor facilities in 2000.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.

2 Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m 2 , and these declining values are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 3

pCi/m 3 . Average present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.

The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish , aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible.

However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g.

Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.

7

4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 2000.

Offsite Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of the site boundary, at the outer ring 4

- 5 mi distant from the Plant, at special interest areas and at one control location. The means ranged from 16.0 mR/91 days at inner ring locations to 17.6 mRI91 days at outer ring locations. The mean at special locations was 15.8 mR/91 days and 17.1 mR/91 days at the control location. The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1985. through 1999. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).

Average (Inner Year and Outer Ring-s) Control 1985 14.0 15.3 1986 17.1 17.3 1987 16.9 17.0 1988 15.4 16.0 1989 16.5 16.7 1990 15.9 16.3 1991 14.9 14.5 1992 16.3 14.8 1993 15.9 15.4 1994 15.2 16.0 1995 15.6 16.6 1996 14.8 16.4 1997 15.1 16.0 1998 16.7 17.3 1999 16.6 17.5 2000 17.0 17.1 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 70.0 mR/91 days inside the ISFSI earth berm and 19.0 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSI pad in 2000. There were twelve loaded casks on the ISFSI pad during 2000. The higher levels inside the earth berm are expected due to the loaded spent fuel casks being in direct line-of-sight from the TLDs. The ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 15.8 and 15.4 mR/91 days. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

8

Airborne Particulates The annual gross beta concentration in airborne particulates for both indicator and control locations averaged 0.025 pCi/m 3 . These averages were similar to average means reported from 1985 through 1999. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl. (Figure 5-2).

Average of Year Indicators Control Concentration (pCi/m 3 )

1985 0.025 0.025 1986 0.024 0.029 1987 0.024 0.023 1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 1991 0.025 0.025 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 Average annual gross beta concentrations in airborne particulates.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al.,

1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1985 through 2000.

Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations.

Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Xcel Energy Corp.,

2001a).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples. All other gamma-emitting isotopes were below their respective LLD limits.

9

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples. There was no indication of a plant effect.

Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

In summary, the milk data for 2000 show no radiological effects of the plant operation.

Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 179 pCi/L in all samples.

Gross beta measurements remained fairly constant throughout the year and averaged 10.1 pCi/L. These concentrations were slightly higher than levels observed from 1985 through 1999 and are most likely contributed by relatively high levels of naturally-occurring radium.

Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2000 data of any effect of plant operation.

Gross Beta (pCi/L)

Yea.r 1985 7.1 1986 6.8 1987 7.9 1988 8.0 1989 7.0 1990 7.0 1991 8.0 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 1997 5.1 1998 5.4 1999 5.3 2000 10.1 Average annual concentrations; Gross beta in drinking water.

10

River Water In one quarterly composite of downstream river water, tritium was measured at a concentration of 297 pCi/L. In all other upstream and downstream collections, quarterly composite tritium levels were below the LLD level of 190 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

Well Water At the control well P-41, Huppert Farm and four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 180 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2000 show no radiological effects of the plant operation.

Crops Two samples of broadleaf vegetation, cabbage and rutabaga leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.009 pCi/g wet weight in both samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

The field sampling personnel conducted an annual land use survey and found that there was no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. No collection and analysis of corn samples was not required.

Fish Fish samples were collected in April, May and September, 2000 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2000.

All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect.

Bottom and Shoreline Sediments Sediment collections were made in May and September, 2000 and analyzed for gamma emitting isotopes. All other gamma-emitting isotopes, excepting naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.

11

5.0 FIGURES AND TABLES 12

PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)' Frequencyb Frequency' Ambient radiation (TLD's) 54 P-01A - P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-011A - P-081A P-01IB - P-081B P-0lIX- P-04IX, P-0lC Airborne Particulates 5 P-I(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6 each location)

Airborne Iodine 5 P-I(C), P-2, P-3, P-4, P-6 C/W 1-131 Milk 4 P-14, P-18,P-37, P-41 (C) G/Md 1-131, GS Milk 1 P-39 G/M 1-13 1, GS River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)

Drinking water 1 P-1I G/W GB(MC), I- 131 (MC)

GS (MC), H-3 (QC)

Well water 5 P-6, P-8, P-9, P-24, P-41 (C) G/Q H-3, GS Edible cultivated crops 2 P-38(C), P-24 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2 P40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.

b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows: W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.

'Analysis type codes: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine 131.

Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (May - October).

13

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 C Air Station P-I AP, AI 11.8 mi @ 316°/NNW P-2 Air Station P-2 AP, AI 0.5 mi @ 294°/WNW P-3 Air Station P-3 AP, AI 0.8 mi @ 313°/NW P-4 Air Station P-4 AP, Al 0.4 mi @ 3590/N P-5 C Upstream of Plant RW 1.8 mi @ 11/N P-6 Lock and Dam # 3 & Air AP, AI, RW Station P-6 WW, BS, BOc 1.6 mi @ 129°/SE P-8 Community Center WW 1.0 mi @ 321°/WNW P-9 Plant Well #2 WW 0.3 mi @ 306'/NW P-11 Red Wing Service Center DW 3.3 mi @ 158°/SSE P-12 Downstream of Plant SS 3.0 mi @ 116°/ESE P-13 Downstream of Plant Fc 3.5 mi @ 113°/ESE P-14 Gustafson Farm M 2.3 mi @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 88°/E P-19 C Upstream of Plant Fc 1.3 mi @ 00 N P-20 C Upstream of Plant BS 0.9 mi @ 45°/NE P-24 Suter Residence VE, WW 0.6 mi @ 158°/SSE P-37 Welsch Farm M 4.1 mi@ 87°/E P-38 C Cain Residence VE 14.2 mi @ 359°/N P-39 Born Farm M 2.8 mi @ 239°/WSW P-40 C Upstream of Plant BOc 0.4 mi @ 0°/N P-41 C Huppert Farm M,WW 13.8 mi @ 354°/N General Area of the Site Boundary P-O0A Property Line TLD 0.4 mi @ 359-/N P-02A Property Line TLD 0.3 mi @ 10I/N P-03A Property Line TLD 0.5 mi @ 183-/S P-04A Property Line TLD 0.4 mi @ 204°/SWW P-05A Property Line TLD 0.4 mi @ 225°/SW P-06A Property Line TLD 0.4 mi @ 2490/WSW P-07A Property Line TLD 0.4 mi @ 268°/W P-08A Property Line TLD 0.4 mi @ 291 °/WNW P-09A Property Line TLD 0.7 mi @ 317°/NW P-IOA Property Line TLD 0.5 mi @ 333°/NNW 14

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-01B Thomas Killian Residence TLD 4.7 mi @ 355°/N P-02B Roy Kimneman Residence TLD 4.8 mi @ 17°/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 460 /NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 61°IENE P-05B County Road E and Coulee TLD 4.2 mi @ 102°/ESE P-06B William Hauschiblt Residence TLD 4.4 mi @ 112°/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140 0/SE P-08B David Wnuk Residence TLD 4.1 mi @ 165°/SSE P-09B Highway 19 South TLD 4.2 mi @ 187°/S P-103B Cannondale Farm TLD 4.9 mi @ 200°/SSW P- l1B Wallace Weberg Farm TLD 4.5 mi @ 221°/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251I/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270°/W P-14B David J. Anderson Farm TLD 4.9 mi @ 306°/NW P-15B Holst Farms TLD 3.8 mi @ 345°/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 129°/SE P-02S Charles Suter Residence TLD 0.5 mi @ 155°/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 202°/SSW P-05S Kinney Store TLD 2.0 mi @ 270V/W P-06S Earl Flynn Farm TLD 2.5 mi @ 299°/WNW P-07S Indian Community TLD 0.7 mi @ 2710 /W P-08S Indian Community TLD 0.7 mi @ 2870/NWW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331°/NNW 15

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).

Approximate Type of Distance and Direction Code Typea Collection Site Sampleb from ISFSI Center.

ISFSI Area Inside Earth Berm P-01IA ISFSI Nuisance Fence TLD 190' @ 45°/NE P-021A ISFSI Nuisance Fence TLD 360' @ 82°/E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219°/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 28 1°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318 0/NW P-OlIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-03DX ISFSI Nuisance Fence TLD 140' @ 0O/N P-041X ISFSI Nuisance Fence TLD 360' @ 90°/E ISFSI Area Outside Earth Berm P-OlIB ISFSI Berm Area TLD 340' @ 3°/N P-021B ISFSI Berm Area TLD 380' @ 28 0/NNE P-031B ISFSI Berm Area TLD 560' @ 85°/E P-041B ISFSI Berm Area TLD 590' @ 165 0/SSE P-05IB ISFSI Berm Area TLD 690' @ 1860/S P-061B ISFSI Berm Area TLD 720' @ 201°/SSW P-07EB ISFSI Berm Area TLD 610' @ 271°/W P-08EB ISFSI Berm Area TLD 360' @ 332°/NNW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F Fish AI Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water CDistance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

16

Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.

All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, P-03 6/14/00 No power due to open fuse. Replaced fuse and conducted testing.

1-131 All operational testing was satisfactory.

TLD Ambient P-lOB 4th Qtr. TLD lost in the field due to Isolated incident; no action required.

Gamma unusually deep snow.

17

mR / 91 days mR / 91 days C> ~ 4-:- C,, -- W 1,0 C 1985 "- 1985 --- ,

1986-- 1986 - -"'_ - -© 1987- 1987--- CD 1988 1988 1989 1989 1990--1990 1- - .

-- o 1992-* 1992- CL) Z, 1993 S1993 I 1994 1994- - --

199 3 1995--

1996 -/ -

19965 0

19974------- 1997 -,

1998 1998 5 --

1999 T 1999 -

2000 2000-

Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.

0.031 0.029 S0.027

, 0.025 0.023 0.021 0.019 0.017 0.015 W) ý10 r- 00 a's ý '-4 C14 M~ ýt W) 10 00 01% 0 00 00 00 00 00 ON Oa% 01 0\ ON O* QN a' CN O\ 0'*

O*

0 0

C* O. O(

ON 0) O\ OS ON CN CN ON ON Ox 01 CN C:

. -4 - - -4 -.4 --4 1-4 -4 1-4 1- -

-e-- Control (P-l) I 0.0 35 0.0:33-0.0 31-S0.0:29-- -- - -- - -- - --

S0.0:27 0.0 25-(

0.0 23 0.0 0.0 0.0 '17 0.0 '15- O0) C0 0 .m-- 00) Co) l0) q U (0 10)

"- M0 O0 00 ccO LO c (0

C cc I- CO 60 0)J 0) 0) 0) 0) 0) 0') 0') 0) 0') 0) 0) 0) 0') 0) 0") 0) 0) 0") 0) 0 0 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282,50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2000

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)' Mean (F)Y Routine (Units) Analyses' Range' Location" Rangec Range' Results' TLD (Inner Ring, Gamma 40 3.0 16.0 (40/40) P-06A 16.9 (4/4) (See Control 0 Area at Site (12.3-18.4) 0.4 mi @ 249* /WSW (15.1-18.4) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 59 3.0 17.6 (59/59) P-02B, Roy Kinneman, 20.5 (4/4) (See Control 0 4-5 mi. distant) (13.1-21.8) 4.8 mi @ 17' /NNE (18.2-21.8) below.)

mR/91 days)

TLD (Special Gamma 32 3.0 15.8 (32/32) P-03S, Gustafson Farm, 18.4 (4/4) (See Control 0 Interest Areas) (12.3-19.7) 2.2 mi @ 173' /S (16.5-19.7) below.)

mR/91 days)

TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 17.1 (4/4) 17.1 (4/4) 0 mR/91 days) 11.1 mi @331' /NNW (15.1-18.2) (15.1-18.2)

Airborne GB 264 0.005 0.025 (211/211) P-04, Air Station 0.026 (53/53) 0.025 (53/53) 0 Particulates (0.009-0.078) 0.4 mi @ 3590 /N (0.009-0.073) (0.011-0.083)

(pCi/my)

GS 20 Be-7 0.015 0.061 (16/16) P-06, Air Station 0.064 (4/4) 0.055 (4/4) 0 (0.040-0.075) 1.6 mi @ 129'/SE (0.040-0.070) (0.040-0.066)

Mn-54 0.0008 < LLD -- < LLD 0 Co-58 0.0011 < LLD - -< LLD 0 Co-60 0.0010 < LLD - - < LLD 0 Zn-65 0.0013 < LLD - - < LLD 0 Zr-Nb-95 0.0011 < LLD - - < LLD 0 Ru-103 0.0009 < LLD - - < LLD 0 Ru-106 0.0069 < LLD - - < LLD 0 Cs-134 0.0006 < LD - < LLD 0 Cs-137 0.0007 <LLD - - <LLD 0 Ba-La-140 0.0024 < LLD - - < LLD 0 Ce-141 0.0013 < LLD <<-LLD 0 Ce-144 0.0036 < LLD -< LLD 0 1-131 264 0.07 < LLD - - < LLD 0 Airborne Iodine (pG/rft) 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2000

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)Y Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results' Milk (pCi/L) 1-131 76 1.0 < LLD < LLD 0 GS 76 K-40 200 1481 (57/57) P-14, Gustafson Farm 1524 (19/19) 1481 (19/19) 0 (1276-1756) 2.3 mi @ 173°/S (1367-1632) (1347-1588)

Cs-134 15 < LLD < LLD 0 Cs-137 15 < LLD < LLD 0 Ba-La-140 15 < LLD < LLD 0 River Water H-3 8 179 297(1/4) P-6, Lock and Dam # 3 297(1/4) < LLD 0 (pCi/L) 1.6 mi @ 129'/SE GS 24 Mn-54 15 < LLD -< LLD 0 Fe-59 30 < LLD -< LLD 0 Co-58 15 < LLD -< LLD 0 Co-60 15 < LLD - - < LLD 0 Zn-65 30 < LLD -< LLD 0 Zr-Nb-95 15 < LLD -< LLD 0 Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD -< LLD 0 Ba-La-140 15 < LLD -< LLD 0 Ce-144 58 < LLD I < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2000 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysese Range' Locationd Range' Range' Results' Drinking Water GB 12 1.0 < LLD P-11, Red Wing S.C. 10.1 (12/12) None 0 (pCi/L) 3.3 mi @ 158' /SSE (5.2-12.9) 1-131 12 1.0 < LLD - None 0 H-3 4 179 < LLD - None 0 GS 12 Mn-54 15 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 15 < LLD - - None 0 Co-60 15 < LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 59 < LLD - - None 0 Well Water H-3 20 180 < LLD - - < LLD 0 (pCi/L)

GS 20 Mn-54 15 < LLD - - < LLD 0 Fe-59 30 < LLD - -< LLD 0 Co-58 15 < LLD - -< LLD 0 Co-60 15 < LLD - - <LLD 0 Zn-65 30 < LLD - -< LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Ce-144 56 < LLD - < LLD 0 Crops - Cabbage 1-131 2 0.009 < LLD - < LLD 0 (pCi/gwet) 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282,50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2000 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDP Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analysese Range' Location' Range' Range' Results' Fish GS 4 (pCi/g wet) K-40 0.10 2.85 (2/2) P-19, Upstream 3.58 (2/2) 3.28 (2/2) 0 (2.63-3.06) 1.3 mi. @ 0*°/N (3.42-3.73) (3.07-3.48)

Mn-54 0.018 < LLD - - < LLD 0 Fe-59 0.081 < LLD - - < LLD 0 Co-58 0.015 < LLD - - < LLD 0 Co-60 0.017 < LLD - - < LLD 0 Zn-65 0.029 < LLD - - < LLD 0 Zr-Nb-95 0.031 < LLD - - < LLD 0 Cs-134 0.013 < LLD - - < LLD 0 Cs-137 0.013 < LLD - - < LLD 0 Ba-La-140 0.77 < LLD - - < LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.55 < LLD - - < LLD 0 K-40 1.48 < LLD - - < LLD 0 Mn-54 0.063 < LLD - -< LLD 0 Co-58 0.10 < LLD - -< LLD 0 Co-60 0.069 < LLD - -< LLD 0 Zn-65 0.12 < LLD - - < LLD 0 Zr-Nb-95 0.13 < LLD - - < LLD 0 Ru-103 0.078 < LLD - < LLD 0 Ru-106 0.40 < LLD - - < LLD 0 Cs-134 0.071 < LLD - - < LLD 0 Cs-137 0.057 < LLD - - < LLD 0 Ba-La-140 0.61 < LLD - - < LLD 0 Ce-141 0.11 < LLD - - < LLD 0 Ce-144 0.24 <LLD - - < LLD 0 23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2000 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Location' Range' Range' Results' Bottom and GS 6 Shoreline Be-7 0.30 < LLD < LLD 0 Sediments K-40 0.10 6.94(4/4) P-20, Upstream 8.79 (4/4) 8.79 (4/4) 0 (pCi/g dry) (6.51-7.46) 0.9 mi. @ 45' /NE (8.64-8.94) (8.64-8.94)

Mn-54 0.021 < LLD - - < LLD 0 Co-58 0.030 < LLD - - < LLD 0 Co-60 0.016 < LLD - - < LLD 0 Zn-65 0.066 < LLD - - < LLD 0 Zr-Nb-95 0.030 < LLD - - < LLD 0 Ru-103 0.023 < LLD - - < LLD 0 Ru-106 0.18 < LLD - - < LLD 0 Cs-134 0.030 < LLD - - < LLD 0 Cs-137 0.024 < LLD - - < LLD 0 Ba-La-140 0.062 < LLD - - < LLD 0 Ce-141 0.044 < LLD - - < LLD 0 Ce-144 0.10 < LLD - - < LLD 0 "GB gross beta, GS = gamma scan.

' LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

' Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

dLocations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.

"Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.

24

6.0 REFERENCES

CITED Arnold, J. R. and H. A. A1-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.

Environmental, Inc., Midwest Laboratory. 2001a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.

_ 2001b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000.

2000. Quality Assurance Program Manual, Rev. 0, 11 October 2000.

2000. Quality Control Procedures Manual, Rev. 0, 21 September 2000.

2000. Quality Control Program, Rev. 0, 12 October 2000.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.

Hazleton Environmental Sciences Corporation. 1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hazleton Environmental Sciences Corporation. 1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, No. 12, 730-746.

Northern States Power Company. 1972. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971. Minneapolis, Minnesota.

1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1972 to December 31, 1972. Minneapolis, Minnesota.

1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1, 1973 to December 31, 1973. Minneapolis, Minnesota.

1979 to 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984 to 2000. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Minneapolis, Minnesota.

25

6.0 REFERENCES

CITED (continued)

Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

_ 1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.

U.S. Environmental Protection Agency . 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).

1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p. 125.

Xcel Energy Corporation. 2001. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

- "-.-.. Environmental, Inc.

"""Midwest Laboratory an Allegheny Technologies Co.

700 Landwetr Road

  • Norbhbrook, IL 60062-2310 (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS studies administered by NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison serves as a replacement for studies conducted previously Environmental Resources Associates, and Laboratory, Las Vegas, Nevada. Results are by the U.S. EPA Environmental Monitoring Systems results, in-house spikes, blanks, duplicates and reported in Appendix A. TLD Intercomparison results are also reported. Appendix A is updated mixed analyte performance evaluation program in March, June, September and December four times a year; the complete Appendix is included monthly progress reports only.

January, 2000 through December, 2000

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the by agencies formulation of it's quality control program in December 1971. These programs are operated samples (e.g., milk or water) containing concentrations of radionuclides which supply environmental type program is to known to the issuing agency but not to participant laboratories. The purpose of such a any possible provide an independent check on a laboratory's analytical procedures and to alert it of problems.

them to the Participant laboratories measure the concentration of specified radionuclides and report reports the known values to the participant laboratories issuing agency. Several months later, the agency higher or lower than the known values or outside the and specifies control limits. Results consistently control limits indicate a need to check the instruments or procedures used.

crosscheck The results in Table A-1 were obtained through participation in the environmental sample the past twelve months. Data for previous years is program for milk, water and air filters during available upon request.

Office of Research and This program was conducted by the U.S. Environmental Protection Agency Division-Las Vegas, Development National Exposure Research Laboratory Characterization Research Nevada.

(TLDs), via various The results in Table A-2 were obtained for Thermoluminescent Dosimeters listed in Table A-2.

International Intercomparisons of Environmental Dosimeters under the sponsorships Results of crosscheck testing with Teledyne Brown Engineering are also listed.

past twelve months. All Table A-3 lists results of the analyses on in-house "spiked" samples for the upon request.

samples are prepared using NIST traceable sources. Data for previous years available twelve months. Data for Table A-4 lists results of the analyses on in-house "blank" samples for the past previous years available upon request.

months. Acceptance is based Table A-5 list results of the in-house "duplicate" program for the past twelve for previous years available on the difference of the results being less than the sum of the errors. Data upon request.

Analyte Performance The results in Table A-6 were obtained through participation in the Mixed Evaluation Program.

the Environmental Measurement The results in Table A-7 were obtained through participation in Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for "spiked" samples.

Out-of-limit results are explained directly below the result.

Al

12-31-00 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

>100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

>50 pCi/liter or kg 10% of known value 2 to 30 pCi/liter or kg 5.0 pCi/liter Strontium_90b

>30 pCi/liter or kg 10% of known value

>0.1 g/liter or kg 5% of known value Potassium-40

<_20 pCi/liter 5.0 pCi/liter Gross alpha

>20 pCi/liter 25% of known value

<100 pCi/liter 5.0 pCi/liter Gross beta 5% of known value

>100 pCi/liter

  • 4,000 pCi/liter is = (pCi/liter) =

Tritium 169.85 x (known)°9

>4,000 pCi/liter 10% of known value Radium-226,-228 <0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value

<55 pCi/liter 6.0 pCi/liter I Iodine-131,

>55 pCi/liter 10% of known value iodine_129b

<_35 pCi/liter 6.0 pCi/liter Uranium-238, -35 Ilter 0-C¢' 15% of known value Nickel-63 ..'-- ..

Technetium-99b 50 to 100 pCi/liter 10 pCi/liter Iron-55b >100 pCi/liter 10% of known value Others" 20% of known value "aFrom EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

Associates (ERA)a.

Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Concentration in pCi/L Laboratory results ERA Resultd Control Lab Sample Date

+/-2 Sigmac Is, N=1 Limits Code Type Collected Analysis 39.3 +/- 5.2 25.4 +/- 6.4 14.5 - 36.3 STW-863 WATER Jan, 2000 Gr. Alpha efficiency; result of reanalysis 29.32 +/- 5.79 pCi/L.

The analysis was repeated and recalculated with Am-241 Internal spike program results do not indicate a problem.

40.7 +/-1 .2 42.1 +/-4.2 33.4 - 50.8 STW-863 WATER Jan, 2000 Gr. Beta 17.1 +/- 2.2 22.5 +/- 5.0 13.8 - 31.2 STW-866 WATER Jan, 2000 Sr-89 8.1 +/- 0.6 9.6 +/- 5.0 0.9 - 18.3 STW-866 WATER Jan, 2000 Sr-90 7.6 +/- 0.5 8.3 +/- 1.2 6.1 - 10.4 STW-868 WATER Feb, 2000 Ra-226 5.6 +/- 1.0 2.3 +/- 0.6 1.3 - 3.2 STW-868 WATER Feb, 2000 Ra-228 gamma spectroscopy (6.00 +/- 1.42 pCi/L ).

Result of reanalysis: 6.34 +/- 0.94. Activity confirmed by 0.9- 11.3 5.4+/-0.2 6.1+/-3.0 STW-868 WATER Feb, 2000 Uranium Mar, 2000 H-3 23,500.0 +/- 306.0 23,800.0 +-2,380.0 19,800.0 - 27,800.0 STW-869 WATER 83.6 +/- 5.8 58.4 +/- 5.8 33.3 - 83.5 STW-867 WATER Mar, 2000 Gr. Alpha 57.80 --+ 5.73 pCi/L. Refer to STW-863.

Results were recalculated with Am-241 efficiency; 8.1 -25.5 15.4+/-0.9 16.8+/-1.7 STW-867 WATER Mar, 2000 Gr. Beta 18.7+/--0.6 19.9 -+/-2.0 14.7- 25.1 STW-876 WATER Mar, 2000 1-131 52.3 +/- 2.3 54.0 +/- 13.5 30.8 - 77.2 STW-877 WATER Apr, 2000 Gr. Alpha 17.5 +/- 1.1 18.6 +/- 2.8 13.8 - 23.4 STW-877 WATER Apr, 2000 Ra-226 3.7 +/- 0.4 3.6 +/- 0.9 2.0 - 5.1 STW-877 WATER Apr, 2000 Ra-228 19.2 +/- 0.6 16.9 +/- 5.0 8.2 - 25.6 STW-878 WATER Apr, 2000 Co-60 81.0 +/- 1.3 86.4 +/- 5.0 77.7 - 95.1 STW-878 WATER Apr, 2000 Cs-134 119.0 +/- 2.6 123.0 +/- 6.2 112.0 - 134.0 STW-878 WATER Apr, 2000 Cs-137 276.0 +/- 9.6 289.0 +/- 43.4 214.0 - 364.0 STW-878 WATER Apr, 2000 Gr. Beta 32.3 +/- 3.3 50.7 +/-5.0 42.0 - 59.4 STW-878 WATER Apr, 2000 Sr-89 11.3 +/- 1.0 32.8 +/- 5.0 24.1 - 41.5 STW-878 WATER Apr, 2000 Sr-90 Sr-89, 55.5+/- 7.2 pCi/L / Sr-90, 30.7 +/- 3.0 pCi/L.

An error was found in calculation. Result of recalculation: limits.

Sr-90, 33.0 +/- 1.35 pCi/L. Both results are within Results of reanalysis: Sr-89, 47.4 +/- 14.5 pCi/L / 16.8 - 34.2 22.4 +/- 2.1 25.5 +/- 5.0 STW-879 WATER Jun, 2000 Ba-133 69.9 +/- 3.7 65.6 +/- 5.0 56.9 - 74.3 STW-879 WATER Jun, 2000 Co-60 13.5 +/- 0.8 13.8 +/-5.0 5.1 - 22.5 STW-879 WATER Jun, 2000 Cs-134 232.0 +/- 7.8 238.0 +/- 11.9 217.0 - 259.0 STW-879 WATER Jun, 2000 Cs-137 50.9 +/- 3.8 54.6 +/- 5.5 45.3 - 63.9 STW-879 WATER Jun, 2000 Zn-65 2.8 +/-0.2 3.0 +/-0.5 2.2- 3.8 STW-880 WATER Jun, 2000 Ra-226 10.0 +/- 0.9 13.0 +/- 3.3 7.4 - 18.6 STW-880 WATER Jun, 2000 Ra-228 57.0 +/- 4.4 63.4 +/- 6.3 52.6 - 74.2 STW-880 WATER Jun, 2000 Uranium 6.9 +/- 1.1 7.2 +/- 5.0 0.0 - 15.9 STW-883 WATER Jul, 2000 Gr. Alpha 88.8 +/- 9.8 87.5 +/- 10.0 70.2 - 105.0 WATER Jul, 2000 Gr. Beta STW-883 8,320.0 +/- 832.0 6,910.0 - 9,730.0 WATER Aug, 2000 H-3 8,740.0 +/- 174.0 STW-884 18.9 +/- 2.8 14.0 - 23.8 Sep, 2000 Ra-226 17.9 +/- 1.3 STW-891 WATER 3.5-8.8 5.7 +/-0.5 6.2 +/-1.6 STW-891 WATER Sep,200 0 Ra-228 Al-1

Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration in pCi/Lb Lab Sample Date Laboratory results ERA Resultd Control Code Type Collected Analysis +/-2 Sigmac 1s, N=1 Limits STW-891 WATER Sep, 2000 Uranium 10.3 +/- 0.1 11.9 +/-3.0 6.7- 17.1 WATER Oct, 2000 1-131 16.9 +/- 0.3 15.9 +/- 1.6 10.7- 21.1 STW-892 STW-892 WATER Oct, 2000 1-131(g) 17.1 +/-5.4 15.9 +/-1.6 10.7- 21.1 WATER Oct, 2000 Gr. Alpha 66.3 +/- 5.3 74.4 +/- 18.6 42.2- 107.0 STW-893 WATER Oct, 2000 Ra-226 10.1+/- 1.0 10.5 +/- 1.6 7.8- 13.2 STW-893 WATER Oct, 2000 Ra-228 21.2 +/- 0.5 19.4+/-4.9 11.0- 27.8 STW-893 WATER Oct, 2000 Uranium 41.4+/-1.9 44.5 +/- 4.5 36.8 - 52.2 STW-893 WATER Oct, 2000 Co-60 93.4 +/- 1.6 91.1 +/-5.0 82.4- 99.8 STW-894 WATER Oct, 2000 Cs-134 54.8 +/- 0.3 59.8 +/- 5.0 51.1 - 68.5 STW-894 WATER Oct, 2000 Cs-137 45.5 +/-2.3 45.0 +/-5.0 36.3 - 53.7 STW-894 WATER Oct, 2000 Gr. Beta 209.0 +/- 7.9 256.0 +/- 38.4 189.0 - 323.0 STW-894 WATER Oct, 2000 Sr-89 32.8 +/- 3.0 41.3 +/- 5.0 32.6- 50.0 STW-894 Oct, 2000 Sr-90 16.0 +/- 2.4 18.0 +/- 5.0 9.3 - 26.7 STW-894 WATER Nov, 2000 Gr. Alpha 50.3 +/- 2.6 60.3 +/- 15.1 34.4- 86.2 STW-895 WATER Nov, 2000 Gr. Beta 28.6 +/- 1.3 25.5 +/-5.0 16.8 - 34.2 STW-895 WATER Nov, 2000 Ba-133 78.0 +/- 2.0 82.2 +/- 8.2 68.0- 96.4 STW-896 WATER Nov, 2000 Co-60 30.8+/-k 1.7 27.8 +/-5.0 19.1 - 36.5 STW-896 WATER WATER Nov, 2000 Cs-134 67.2 +/- 3.3 76.0 +/-5.0 67.3 - 84.7 STW-896 The mean value for Cs-134 of all participating laboratories was 70.7 pCi/L. Other gamma emitters are within limits, the counting efficiency is not suspect. Library values were reviewed and found to be correct.

STW-896 WATER Nov, 2000 Cs-137 109.0 +/- 1.0 106.0 +/-5.3 96.8- 115.0 STW-896 WATER Nov. 2000 Zn-65 81.5 +/- 7.4 79.0 + 7.9 65.3 - 92.7 STW-896 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.

Unless otherwise indicated, the laboratory results are given as the mean +/- 2 standard deviations for three determinations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

A1-2

Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).

mR Lab Laboratory results Known Average +/- 2 Sigma Code TLD Type Date Measurement +/-2 Sigma Value (All Participants)

Environmental. Inc.

LiF-100 Chips Mar, 1999 Reader 1, #1 14.5 +/- 0.5 15.4 1999-1 1999-1 LiF-100 Chips Mar, 1999 Reader 1, #2 29.3 +/- 1.0 31.8 LiF-100 Chips Mar, 1999 Reader 1, #3 60.0_L0.2 59.1 1999-1 Environmental, Inc.

Mar, 1999 Reader 1, #1 18.3 +/- 0.5 15.4 1999-2 CaSO 4: Dy Cards CaSO 4: Dy Cards Mar, 1999 Reader 1, #2 35.9+/- 1.3 31.8 1999-2 CaSO 4: Dy Cards Mar, 1999 Reader 1, #3 66.5 +/- 4.4 59.1 1999-2 Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 1999.

Environmental, Inc.

Mar, 2000 Reader 1, #1 14.4+/- 0.2 17.8 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #2 32.4_+/- 0.1 35.5 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #3 61.8 +/- 0.9 62.2 2000-1 LiF-100 Chips Environmental, Inc.

Mar, 2000 Reader 1, #1 21.3 +/- 0.3 17.8 2000-2 CaSO4 : Dy Cards Mar, 2000 Reader 1, #2 40.1 +/- 1.9 35.5 2000-2 CaSO 4: Dy Cards Mar, 2000 Reader 1, #3 69.9 +/-3.5 62.2 2000-2 CaSO 4: Dy Cards Chips and Cards were irradiated by Teledyne Brown Engineering, Westwood, New Jersey, in March, 2000.

A2-1

Table A-3. In-house "spike" samples.

Concentration in pCi/La Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s, n=lb Activity Limits SPW-271 WATER Jan, 2000 Ra-226 14.81 +/- 0.44 13.76 9.63 - 17.89 16.97 +/- 2.12 14.68 10.28 - 19.08 SPW-271 WATER Jan, 2000 Ra-228 44.35 +/- 1.95 41.14 20.57 - 61.71 SPW-272 WATER Jan, 2000 Gr. Alpha 31.19 +/- 5.02 29.50 19.50 - 39.50 SPW-272 WATER Jan, 2000 Gr. Beta 56339.00 +/- 666.00 5 7667.00 46133.60 - 69200.40 SPW-756 WATER Jan, 2000 H-3 32.33 +/- 2.87 28.36 18.36 - 38.36 SPW-480 WATER Jan, 2000 Co-60 36.83 26.83 - 46.83 SPW-480 WATER Jan, 2000 Cs-137 35.58 +/- 4.20 14.10 4.10 - 24.10 SPMI-482 MILK Jan, 2000 Sr-90 16.93 +/- 1.07 1.72 1.03 - 2.41 SPAP-484 AIR FILTER Jan, 2000 Cs-137 1.84 +/- 0.01 16.59 +/- 1.90 41.10 20.55 - 61.65 SPW-917 WATER Feb, 2000 Gr. Alpha An insufficient amount of Am-241 spike was available for an accurate test.

32.61 +/- 2.06 29.43 19.43 - 39.43 SPW-917 WATER Feb, 2000 Gr. Beta 21.15 +/- 0.49 20.68 14.48 - 26.88 SPW-918 WATER Feb, 2000 Ra-226 14.24+/- 1.64 14.51 10.16 - 18.86 SPW-918 WATER Feb, 2000 Ra-228 1.17+/- 0.07 1.12 0.67- 1.57 SPVE-1262 VEGETATION Mar, 2000 1-131(g) 0.53 0.32 - 0.74 SPCH-1264 CHARCOAL Mar, 2000 1-131(g) 0.56 +/- 0.02 CANISTER 47.02 +/-3.36 48.00 36.00 - 60.00 SPMI-1274 MILK Mar, 2000 1-131 66.03 +/-1.06 76.84 61.47 - 92.21 SPW-1301 WATER Mar, 2000 1-131 80.31 +/- 6.28 76.84 66.84 - 86.84 SPW-1301 WATER Mar, 2000 1-131(g) 32.09 +/- 1.82 41.13 20.57 - 61.70 SPW-1477 WATER Mar, 2000 Gr. Alpha 29.38 19.38 - 39.38 SPW-1477 WATER Mar, 2000 Gr. Beta 29.20+/-1.56 21.78+/- 0.47 20.69 14.48 - 26.90 SPW-1478 WATER Mar, 2000 Ra-226 14.41 +/- 1.70 14.39 10.07 - 18.71 SPW-1478 WATER Mar, 2000 Ra-228 32.12 22.12 - 42.12 SPMI-2275 MILK Apr, 2000 Cs-134 33.53 +/- 2.82 36.66 26.66 - 46.66 SPMI-2275 MILK Apr, 2000 Cs-137 36.38 +/-4.94 55.50 44.40 - 66.60 SPMI-2275 MILK Apr, 2000 1-131 46.06 +/- 0.82 20.68 14.48 - 26.88 SPW-2277 WATER Apr, 2000 Ra-226 20.51 +/- 0.44 38.44 19.22 - 57.66 SPW-2278 WATER Apr, 2000 Gr. Alpha 40.22 +/-2.50 29.30 19.30 - 39.30 SPW-2278 WATER Apr, 2000 Gr. Beta 32.63 +/- 1.81 14.25 9.98- 18.53 SPW-2278 WATER Apr, 2000 Ra-228 14.91 +/- 1.70 34.54 24.54 - 44.54 SPW-2279 WATER Apr, 2000 Co-60 37.12_+/- 3.86 32.12 22.12 - 42.12 SPW-2279 WATER Apr, 2000 Cs-134 34.70+/- 3.32 36.66 26.66 - 46.66 SPW-2279 WATER Apr, 2000 Cs-137 39.60+/- 5.12 55.50 44.40 - 66.60 SPW-2279 WATER Apr, 2000 1-131 49.92 +/- 0.67 55.50 45.50 - 65.50 SPW-2279 WATER Apr, 2000 1-131(g) 60.63 +/- 6.58 56996.00 45596.80 - 68395.20 SPW-2281 WATER Apr, 2000 H-3 58829.00 +/-682.00 1.71 1.03- 2.39 SPAP-3097 AIR FILTER Apr, 2000 Cs-137 1.81 +/- 0.02 85.38 68.30 - 102.46 SPW-3093 WATER May, 2000 1-131 83.39 +/- 1.06 20.68 14.48 - 26.88 SPW-3094 WATER May, 2000 Ra-226 20.86-+/- 0.42 14.12 9.88- 18.36 SPW-3094 WATER May, 2000 Ra-228 14.17+/- 1.59 38.99 +/- 2.09 38.44 19.22 - 57.66 qPW-3f95 WATER Mav. 2000 Gr. Aloha

,.,* , , *viv A3-1

Table A-3. In-house "spike" samples.

Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3095 WATER May, 2000 Gr. Beta 30.65 . 1.53 29.30 19.30 - 39.30 AIR FILTER May, 2000 Gr. Beta 5.08 _0.03 5.97 -4.03 - 15.97 SPAP-274 1-131 85.08 +/- 1.05 85.38 68.30 - 102.46 SPMI-3138 MILK May, 2000 0.52 +/- 0.02 0.50 0.30 - 0.70 SPF-3180 FISH May, 2000 Cs-134 0.65 +/- 0.04 0.59 0.35 - 0.82 SPF-3180 FISH May, 2000 Cs-137 Gr. Beta 5.81 +/- 0.03 5.35 -4.65 - 15.35 SPAP-3902 AIR FILTER Jun, 2000 0.60 +/- 0.04 0.59 0.35 - 0.83 SPF-5182 FISH Jun, 2000 Cs-134 FISH Jun, 2000 Cs-137 0.60 +/- 0.05 0.58 0.35- 0.81 SPF-5182 WATER Jun, 2000 Ra-226 23.73 +/- 0.85 20.68 14.48 - 26.88 SPW-3911 WATER Jun, 2000 Ra-228 20.43 +/- 1.77 20.75 14.53 - 26.98 SPW-3911 Gr. Alpha 38.28 +/- 2.12 38.44 19.22 - 57.66 SPW-3910 WATER Jun, 2000 WATER Jun, 2000 Gr. Beta 35.14 +/- 1.74 29.22 19.22 - 39.22 SPW-3910 Sr-89 73.70 +/- 4.77 81.00 64.80 - 97.20 SPW-4342 WATER Jun, 2000 Sr-90 58.13 +/- 2.17 55.90 44.72 - 67.08 SPW-4342 WATER Jun, 2000 Ra-226 21.07 +/- 0.56 20.68 14.48 - 26.88 SPW-4687 WATER Jul, 2000 Ra-228 16.35 +/- 1.70 20.75 14.53 - 26.98 SPW-4687 WATER Jul, 2000 WATER Jul, 2000 H-3 56205.00 +/- 663.00 56228.00 44982.40 - 67473.60 SPW-4688 Gr. Beta 6.07 +/- 0.02 5.96 -4.04 - 15.96 SPAP-4807 AIR FILTER Jul, 2000 Cs-137 1.82 +/- 0.02 1.71 1.03 - 2.39 SPAP-4809 AIR FILTER Jul, 2000 Cs-134 33.24 +/- 3.74 29.56 19.56 - 39.56 SPMI-4856 MILK Jul, 2000 Cs-137 39.80 +/- 6.77 36.45 26.45 - 46.45 SPMI-4856 MILK Jul, 2000 Sr-89 46.35 +/- 5.10 56.34 45.07 - 67.61 SPMI-4856 MILK Jul, 2000 Sr-90 70.47 +/- 2.06 69.73 55.78 - 83.68 SPMI-4856 MILK Jul, 2000 Co-60 33.31 +/- 4.61 33.24 23.24 - 43.24 SPW-5372 WATER Jul, 2000 Cs-134 59.70 +/- 4.57 58.26 48.26 - 68.26 SPW-5372 WATER Jul, 2000 Cs-137 40.00 +/- 5.58 36.42 26.42 - 46.42 SPW-5372 WATER Jul, 2000 Gr. Alpha 34.12 _ 1.71 38.43 19.22 - 57.65 SPW-4686 WATER Aug, 2000 Gr. Beta 35.42 +/- 1.51 29.21 19.21 - 39.21 SPW-4686 WATER Aug 2000 Sr-89 62.97 +/- 4.73 67.61 54.09 - 81.13 SPW-5564 WATER Aug 2000 Sr-90 65.40 +/- 2.47 55.70 44.56 - 66.84 SPW-5564 WATER Aug 2000 Ra-226 12.82 +/- 0.30 13.79 9.65 - 17.93 SPW-5792 WATER Aug 2000 Ra-228 15.00 +/- 1.21 13.69 9.58-17.80 SPW-5792 WATER Aug 2000 Ra-228 22.20+/-2.20 20.32 14.22 - 26:42 SPW-6631 WATER Sep, 2000 Ra-226 13.58 +/- 0.29 13.79 9.65- 17.93 SPW-6632 WATER Sep, 2000 18.84 +/- 2.59 20.32 14.22 - 26.42 SPW-6632 WATER Sep, 2000 Ra-228 Fe-55 1757.00 +/- 674.00 1852.00 1481.60 - 2222.40 SPW-6633 WATER Sep, 2000 52.28 +/- 9.41 69.00 34.50 - 103.50 SPW-5791 WATER Sep, 2000 Gr. Alpha Gr. Beta 34.60 +/- 4.71 29.10 19.10 - 39.10 SPW-5791 WATER Sep, 2000 Gr. Alpha 71.54 +/- 7.15 69.14 34.57 - 103.71 SPW-6630 WATER Sep, 2000 37.78 +/- 1.62 29.04 19.04 - 39.04 SPW-6630 WATER Sep, 2000 Gr. Beta 12.36 +/- 0.25 13.79 9.65- 17.93 SPW-7744 WATER Oct, 2000 Ra-226 A3-2

Table A-3. In-house "spike" samples.

Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, nrlb Activity Limits SPW-7744 WATER Oct, 2000 Ra-228 10.37+/- 1.15 13.40 9.38 - 17.42 SPW-7745 WATER Oct, 2000 H-3 54650.00_+/- 643.00 55391.00 44312.80 - 66469.20 SPAP-7764 AIR FILTER Oct, 2000 Gr. Beta 6.14 +/- 0.03 5.91 -4.09 - 15.91 SPAP-7766 AIR FILTER Oct, 2000 Cs-137 1.84 +/- 0.01 1.69 1.01 - 2.37 SPMI-8347 MILK Oct, 2000 Cs-134 29.18 +/- 6.51 26.83 16.83 - 36.83 SPMI-8347 MILK Oct, 2000 Cs-134 29.37 +/-3.63 26.83 16.83 - 36.83 SPMI-8347 MILK Oct, 2000 Cs-137 39.04 +/- 8.76 36.20 26.20 - 46.20 SPMI-8347 MILK Oct, 2000 Cs-137 34.89 +/- 5.71 36.20 26.20 - 46.20 SPF-8349 FISH Oct, 2000 Cs-134 0.56_+/- 0.02 0.54 0.32 - 0.75 SPF-8349 FISH Oct, 2000 Cs-137 0.92 +/- 0.04 0.87 0.52 - 1.22 SPW-8369 WATER Oct, 2000 Co-60 32.49 +/- 1.86 32.19 22.19 - 42.19 SPW-8369 WATER Oct, 2000 Cs-134 55.87 +/- 1.71 53.66 43.66 - 63.66 SPW-8369 WATER Oct, 2000 Cs-137 36.46 +/- 2.73 36.21 26.21 - 46.21 SPW-7743 WATER Oct, 2000 Gr. Alpha 51.28 +/-2.28 69.10 34.55 - 103.65 SPW-7743 WATER Oct, 2000 Gr. Beta 36.86 +/- 1.66 29.00 19.00 - 39.00 SPW-9101 WATER Nov, 2000 Ra-226 14.35 +/- 0.24 13.79 9.65 - 17.93 SPW-9101 WATER Nov, 2000 Ra-228 22.14+/- 1.56 20.09 14.06 - 26.12 SPW-9102 WATER Dec, 2000 Gr. Alpha 77.76 +/- 3.02 69.14 34.57 - 103.71 SPW-9102 WATER Dec, 2000 Gr. Beta 36.71 +/- 1.65 28.99 18.99 - 38.99 SPW-9726 WATER Dec, 2000 Gr. Alpha 43.03 +/- 2.18 69.14 34.57 - 103.71 SPW-9726 WATER Dec, 2000 Gr. Beta 32.17+/- 1.55 28.89 18.89 - 38.89 SPW-9727 WATER Dec, 2000 Ra-226 13.35 +/-0.29 13.79 9.65 - 17.93 SPW-9727 WATER Dec, 2000 Ra-228 15.44 +/- 1.23 19.75 13.83 - 25.68 SPCH-10228 CHARCOAL Dec, 2000 Ba-133 1.80 +/- 0.05 2.11 1.26 - 2.95 CANISTER "All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/Filter; and food products, which are in mg/kg.

bAll samples are the results of single determinations.

'Control limits are based on Attachment A, page A2 of this report.

NOTE: For fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike matrix.

A3-3

Table A-4. In-house "blank" samples.

Concentration pCi/La.

Laboratory results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)

SPW-270 WATER Jan 2000 Gr. Alpha < 0.50 0.52 +/- 0.41 < 1.0 SPW-270 WATER Jan 2000 Gr. Beta < 1.50 -0.34 +/-_1.11 <3.2 SPW-270 WATER Jan 2000 Ra-226 0.06 +/- 0.01 < 1.0 SPW-270 WATER Jan 2000 Ra-228 < 0.94 0.14 +/- 0.45 < 2.0 SPW-447 WATER Jan 2000 H-3 < 184.00 -54.70 +/- 88.60 < 200.0 SPW-481 WATER Jan 2000 Co-60 < 2.42 < 10.0 SPW-481 WATER Jan 2000 Cs-134 < 3.99 < 10.0 SPW-481 WATER Jan 2000 Cs-137 < 2.90 < 10.0 SPMI-483 MILK Jan 2000 Cs-137 < 2.73 < 10.0 SPMI-483 MILK Jan 2000 Sr-90 1.03 +/- 0.40 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPAP-485 AIR FILTER Jan 2000 Cs-137 < 1.64 < 100.0 Gr. Alpha < 0.80 0.56 +/- 0.61 <1.0 SPW-919 WATER Feb 2000 Gr. Beta < 1.65 0.11 +/- 1.16 <3.2 SPW-919 WATER Feb 2000 Ra-226 < 0.02 0.02 t 0.01 <1.0 SPW-919 WATER Feb 2000 Ra-228 < 0.60 0.02 +/- 0.01 <2.0 SPW-919 WATER Feb 2000 Cs-134 < 11.48 < 100.0 SPVE-1263 VEGETATION Mar 2000 Cs-137 < 24.82 < 100.0 SPVE-1263 VEGETATION Mar 2000 CHARCOAL Mar 2000 1-131(g) < 7.00 <9.6 SPCH-1265 CANISTER MILK Mar 2000 1-131 < 0.32 0.05 +/- 0.18 <0.5 SPMI-1292 MILK Mar 2000 1-131(g) < 4.60 < 20.0 SPMI-1292 WATER Mar 2000 1-131 < 0.30 0.01 +/- 0.14 <0.5 SPW-1302 WATER Mar 2000 Gr. Alpha < 0.84 -0.32 +/- 0.53 <1.0 SPW-1479 Mar 2000 Gr. Beta < 1.86 -1.39 +/- 1.19 <3.2 SPW-1479 WATER Mar 2000 Ra-226 < 0.01 0.06

  • 0.01 <1.0 SPW-1479 WATER Mar 2000 Ra-228 < 1.00 1.17 +/- 0.60 <2.0 SPW-1479 WATER Apr 2000 Cs-134 < 4.20 < 10.0 SPMI-2276 MILK Apr 2000 Cs-137 < 3.33 < 10.0 SPMI-2276 MILK Apr 2000 1-131 < 0.50 0.32 +/- 0.30 <0.5 SPMI-2276 MILK Apr 2000 Co-60 < 2.78 < 10.0 SPW-2280 WATER Apr 2000 Cs-134 < 3.56 < 10.0 SPW-2280 WATER A4-1

Table A-4. In-house "blank" samples.

Concentration pCi/La.

Laboratory results Acceptance Sample Sample (4.66 Sigma) Criteria Lab Code Date Analysis LLD Activityb (4.66 Sigma)

Type ate SPW-2280 WATER Apr 2000 Cs-137 < 2.81 < 10.0 SPW-2280 WATER Apr 2000 Gr. Alpha < 0.60 0.55 + 0.45 < 1.0 SPW-2280 WATER Apr 2000 Gr. Beta < 1.66 0.62 +/- 1.11 < 3.2 SPW-2280 WATER Apr 2000 1-131 < 0.29 -0.16 +/- 0.19 < 0.5 SPW-2280 WATER Apr 2000 1-131(g) < 3.42 < 20.0 SPW-2280 WATER Apr 2000 Ra-226 0.03 +/- 0.01 < 1.0 SPW-2280 WATER Apr 2000 Ra-228 < 0.87 0.65 +/- 0.47 < 2.0 SPW-2282 WATER Apr 2000 H-3 < 151.60 -5.40 +/-74.90 < 200.0 SPAP-3098 AIR FILTER Apr 2000 Cs-137 < 1.37 < 100.0 SPW-3096 WATER May 2000 Gr. Alpha < 0.68 < 1.0 SPW-3096 WATER May 2000 Gr. Beta < 1.62 < 3.2 SPW-3096 WATER May 2000 Ra-226 0.05 +/- 0.01 < 1.0 SPW-3096 WATER May 2000 Ra-228 < 0.90 0.05 +/-0.01 < 2.0 SPAP-273 AIR FILTER May 2000 Gr. Beta < 0.54 0.90 +/- 0.32 < 3.2 SPMI-3139 MILK May 2000 1-131 < 0.33 < 0.5 SPF-3181 FISH May 2000 Cs-134 < 3.02 < 100.0 SPF-3181 FISH May 2000 Cs-137 < 4.99 < 100.0 SPAP-3903 AIR FILTER Jun 2000 Gr. Beta < 0.48 < 3.2 SPW-3912 WATER Jun 2000 Gr. Alpha < 0.35 0.28 +/- 0.28 < 1.0 SPW-3912 WATER Jun 2000 Gr. Beta < 1.22 0.54 +/- 0.86 < 3.2 SPW-3912 WATER Jun2000 Ra-226 0.04 +/- 0.02 < 1.0 SPW-3912 WATER Jun2000 Ra-228 < 0.65 < 2.0 SPMI-4343 MILK Jun 2000 Sr-89 < 0.73 < 5.0 SPMI-4343 MILK Jun 2000 Sr-90 < 0.56 < 1.0 WATER Jul2000 Ra-226 0.03 +/- 0.01 < 1.0 SPW-4689 SPW-4689 WATER Jul2000 Ra-228 < 0.93 1.11 +/- 0.55 < 2.0 SPW-4690 WATER Jul 2000 H-3 < 178.00 18.57 +/- 89.13 < 200.0 SPW-4808 WATER Jul 2000 Gr. Alpha < 0.45 < 1.0 SPAP-4810 AIR FILTER Jul 2000 Cs-137 < 2.18 < 100.0 SPMI-4857 MILK Jul 2000 Cs-137 < 6.13 < 10.0 SPMI-4857 MILK Jul 2000 1-131(g) < 7.19 < 20.0 A4-2

Table A-4. In-house "blank" samples.

Concentration pCi/La.

Laboratory results Acceptance Lab (4.66 Sigma) Criteria Lab Sample Sample Code Type Date Analysis LLD Activityb (4.66 Sigma)

< 0.66 <5.0 SPMI-4857 MILK Jul 2000 Sr-89 Sr-90 1.15 +/- 0.32 <1.0 SPMI-4857 MILK Jul2000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPF-5183 FISH Jul2000 Cs-134 < 17.71 < 100.0 Cs-137 < 12.81 < 100.0 SPF-5183 FISH Jul2000 Gr. Alpha < 0.50 <1.0 SPW-4689 WATER Jul2000

< 1.20 <3.2 SPW-4689 WATER Jul2000 Gr. Beta

< 5.20 < 10.0 SPW-5373 WATER Jul 2000 Co-60

< 4.80 < 10.0 SPW-5373 WATER Jul2000 Cs-134

< 4.00 < 10.0 SPW-5373 WATER Jul2000 Cs-137

< 1.56 -0.64 +/-1.11 <5.0 SPW-5565 WATER Aug 2000 Sr-89

< 0.59 0.17 +/- 0.30 <1.0 SPW-5565 WATER Aug 2000 Sr-90

< 0.51 0.02 +/- 0.36 < 1.0 SPW-5793 WATER Aug 2000 Gr. Alpha 0.05 +/- 0.02 <1.0 SPW-5793 WATER Aug 2000 Ra-226

< 0.95 0.26 +/- 0.47 <2.0 SPW-5793 WATER Aug 2000 Ra-228

< 1.40 -0.13 +/- 1.01 <3.2 SPW-5793 WATER Aug 2000 Gr. Beta

< 617.00 -105.90 +/-453.40 < 1000.0 SPW-6634 WATER Sep 2000 Fe-55

< 0.01 0.03 +/- 0.01 <1.0 SPW-6634 WATER Sep 2000 Ra-226 Ra-228 < 0.99 0.36 +/-0.51 <2.0 SPW-6634 WATER Sep 2000

< 0.67 -0.22 +/- 0.45 <1.0 SPW-6634 WATER Sep 2000 Gr. Alpha

< 1.60 -0.20 +/- 1.12 <3.2 SPW-6634 WATER Sep 2000 Gr. Beta

< 16.87 < 100.0 SPSO-10595 SOIL Oct 2000 Cs-134 Cs-137 < 9.40 < 100.0 SPSO-10595 SOIL Oct 2000

< 0.03 0.04 +/- 0.02 <1.0 SPW-7746 WATER Oct 2000 Ra-226

< 1.08 0.00 +/-_0.87 <2.0 SPW-7746 WATER Oct 2000 Ra-228 H-3 < 158.00 -38.00 +/- 77.00 < 200.0 SPW-7747 WATER Oct 2000

< 0.64 0.00 +/- 0.00 <3.2 SPAP-7765 AIR FILTER Oct 2000 Gr. Beta

< 0.19 < 100.0 SPAP-7767 AIR FILTER Oct 2000 Co-60

< 0.32 < 100.0 SPAP-7767 AIR FILTER Oct 2000 Cs-134

< 2.32 < 100.0 SPAP-7767 AIR FILTER Oct 2000 Cs-137

< 3.35 < 10.0 SPMI-8348 MILK Oct 2000 Cs-134

< 3.07 < 10.0 SPMI-8348 MILK Oct 2000 Cs-137 A4-3

Table A-4. In-house "blank" samples.

Concentration pCi/La.

Laboratory results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)

SPF-8350 FISH Oct 2000 Cs-134 < 10.26 < 100.0 SPF-8350 FISH Oct 2000 Cs-137 < 10.51 < 100.0 SPW-8370 WATER Oct 2000 Co-60 < 4.67 < 10.0 SPW-8370 WATER Oct 2000 Cs-134 < 5.28 < 10.0 SPW-8370 WATER Oct 2000 Cs-137 < 4.93 < 10.0 SPW-7746 WATER Oct 2000 Gr. Alpha < 0.46 0.06 + 0.33 < 1.0 SPW-7746 WATER Oct 2000 Gr. Beta < 1.24 0.00 + 0.87 < 3.2 SPW-9103 WATER Nov 2000 Ra-226 < 0.01 0.02 _0.01 < 1.0 SPW-9103 WATER Nov 2000 Ra-228 < 1.00 0.14 +/- 0.48 < 2.0 SPW-9729 WATER Dec 2000 Gr. Alpha < 0.46 0.23 + 0.36 < 1.0 SPW-9729 WATER Dec 2000 Gr. Beta < 1.33 -0.46 +/- 0.98 < 3.2 SPW-9729 WATER Dec 2000 Ra-226 < 0.02 0.05 +/- 0.01 < 1.0 WATER Dec 2000 Ra-228 < 0.70 0.22 +/- 0.35 < 2.0 SPW-9729 WATER Dec 2000 Gr. Alpha < 0.51 -0.11 +/- 0.37 < 1.0 SPW-9103 WATER Dec 2000 Gr. Beta < 1.21 0.55 +/- 0.91 < 3.2 SPW-9103 SPCH-10583 CHARCOAL Dec 2000 1-131(g) < 1.49 <9.6 CANISTER aLiquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in pCi/charcoal, and solid sample results are in pCi/kilogram.

b The activity reported is the net activity result.

A4-4

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result CF-23, 24 Jan, 2000 Gr. Beta 13.05 +/- 0.39 12.46 +/- 0.36 12.75 +/- 0.26 CF-23, 24 Jan, 2000 K-40 13.00 + 0.90 11.73++/-0.79 12.36 +/- 0.60 CF-23, 24 Jan, 2000 Sr-90 0.01 +/- 0.00 0.01 +/- 0.00 0.01 - 0.00 WW-65, 66 Jan, 2000 Co-60 -0.53 +/- 1.62 0.44 +/- 2.11 -0.04 + 1.33 WW-65, 66 Jan, 2000 Cs-137 -2.13 +/- 1.70 0.41 +/- 2.35 -0.86 - 1.45 WW-65, 66 Jan, 2000 H-3 131.62 +/- 84.13 182.81 +/- 86.33 157.22+/- 60.27 WW-686, 687 Jan, 2000 Gr. Beta 4.76 +/- 1.22 4.59 +/-1.27 4.67 - 0.88 AP-1204, 1205 Jan, 2000 Be-7 0.19 +/- 0.09 0.10 + 0.07 0.14 : 0.06 SW-68, 69 Jan, 2000 K-40 (FP) 1.30 +/- 0.13 1.30 +/- 0.13 1.30 . 0.09 Jan, 2000 1-131 -0.08 +/- 0.27 -0.00 +/- 0.26 -0.04 +/--0.19 MI-277, 278 MI-277, 278 Jan, 2000 K-40 1,664.70 +/- 113.20 1,431.30 t 90.30 1,548.00 - 72.40 MI-277, 278 Jan, 2000 Sr-90 0.63 +/- 0.42 0.51 +/- 0.40 0.57 - 0.29 SW-728, 729 Jan, 2000 Co-60 0.39 +/- 1.79 1.04 +/- 1.53 0.72

  • 1.18 SW-728, 729 Jan, 2000 Cs-137 -0.67+/- 1.86 1.22 +/- 1.38 0.27 +/- 1.16 SW-403, 404 Jan, 2000 H-3 795.21 +/- 109.04 857.22 +/- 111.09 826.22 .- 77.83 SWT-437, 438 Jan, 2000 Gr. Beta 1.73 +/- 0.57 2.60 - 0.58 2.16 - 0.41 PW-637, 638 Jan, 2000 Co-60 4.90 +/- 2.92 -2.56 +/- 2.80 1.17 - 2.02 PW-637, 638 Jan, 2000 Cs-137 2.73 +/- 2.51 -1.68 +/- 2.71 0.53 - 1.85 PW-637, 638 Jan, 2000 Gr. Beta 1.67 +/- 1.31 4.00 +/- 1.59 2.83 . 1.03 SW-587, 588 Jan, 2000 Co-60 -1.24 +/--1.86 -0.27+/- 1.79 -0.76 . 1.29 Jan, 2000 Cs-137 1.35 - 1.94 0.23 +/- 1.80 0.79 . 1.32 SW-587, 588 SW-587, 588 Jan, 2000 Gr. Beta 3.80 +/- 1.56 6.76 +/- 1.75 5.28 +/- 1.17 SW-611, 612 Jan, 2000 H-3 2,229.26 +/-158.61 2,115.19 +/-155.80 2,172.23 - 111.16 SW-459, 460 Feb, 2000 Gr. Beta 2.15 +/- 0.94 2.79 +/- 0.94 2.47 +/- 0.66 Feb, 2000 Co-60 4.26 +/- 3.48 1.61 +/- 4.46 2.93 - 2.83 WW-774, 775 Feb, 2000 Cs-137 -1.19 +/- 3.78 2.37 + 4.65 0.59 __2.99 WW-774, 775 Feb, 2000 H-3 2,841.35 +/- 174.48 2,566.76+/-168.19 2,704.05 - 121.17 WW-774, 775 Feb, 2000 Gr. Alpha 2.20 +/- 1.73 0.16 +/- 1.29 1.18 - 1.08 SW-707, 708 Feb, 2000 Gr. Beta 7.90 +/- 1.70 7.70-+/-1.70 7.80 +/- 1.20 SW-707, 708 Feb, 2000 H-3 117.00
  • 92.00 69.00 +/- 90.00 93.00 +/- 64.35 SW-707, 708 Feb, 2000 Gr. Beta 2.13 +/- 1.36 1.34 +/- 1.25 1.74 - 0.93 CW-854, 855 SW-881, 882 Feb, 2000 H-3 1,794.91 +/- 145.81 1,762.31 +/- 144.95 1,778.61 +/-102.80 SW-959, 960 Feb, 2000 Gr. Alpha 1.04 +/- 1.00 0.92 +/- 0.67 0.98 +/- 0.60 Gr. Beta 1.24 +/- 0.89 1.79 +/- 0.90 1.51 +/-t 0.63 SW-959, 960 Feb, 2000 Feb, 2000 Co-60 -0.72 +/- 3.18 1.73 +/- 1.89 0.51 - 1.85 PW-1055, 1056 Feb, 2000 Cs-137 0.55 +/- 2.81 0.90 +/- 1.86 0.72 . 1.69 PW-1055, 1056 Feb, 2000 Gr. Beta 2.40 +/- 1.52 2.20 - 1.50 2.30 -t 1.07 PW-1055, 1056 A5-1

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result MI-1079, 1080 Mar, 2000 Calcium 0.79 +/- 0.08 0.78 +/- 0.08 0.79 + 0.06 MI-1079, 1080 Mar, 2000 K-40 1,229.00 +/- 138.00 1,387.00 +/- 162.00 1,308.00 + 106.40 MI-1079, 1080 Mar, 2000 Sr-90 0.90 +/- 0.40 1.70 +/- 0.50 1.30 +/- 0.32 CW-1156, 1157 Mar, 2000 H-3 1,994.51 +/- 143.09 2,012.54 +/- 143.55 2,003.53 +/- 101.34 SW-1967, 1968 Mar, 2000 Gr. Beta 11.96 +/- 1.31 12.57+/-1.31 12.27 + 0.93 SW-2468, 2469 Mar, 2000 Sr-90 0.93 +/- 0.45 0.50 +/- 0.29 0.72 +/- 0.27 WW-1402, 1403 Mar, 2000 H-3 93.34 +/- 97.05 60.63 +/- 95.75 76.98 +/- 68.17 LW-1269, 1270 Mar, 2000 Gr. Beta 1.97 +/- 0.57 3.22 +/- 0.69 2.60 +/- 0.45 MI-1541, 1542 Mar, 2000 K-40 1,380.00 +/- 122.00 1,476.00 +/- 158.00 1,428.00 +/- 99.81 AP-2113, 2114 Mar, 2000 Be-7 0.06 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 CW-1571, 1572 Mar, 2000 Gr. Beta 2.29 +/- 1.48 1.35 +/- 1.27 1.82 +/- 0.98 CW-1693, 1694 Mar, 2000 Gr. Beta 0.56 +/- 1.18 1.91 +/- 1.49 1.24 +/- 0.95 SWT-1821, 1822 Mar, 2000 Gr. Beta 2.36 +/- 0.65 2.01 +/- 0.57 2.19 +/- 0.43 WW-1916, 1917 Mar, 2000 H-3 25.37 +/- 90.21 3.90 +/- 89.27 14.63 +/- 63.46 AP-2155, 2156 Mar, 2000 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 + 0.01 SWU-2547, 2548 Mar, 2000 Sr-90 0.57 +/- 0.24 0.55 +/- 0.24 0.56 +/- 0.17 CW-1798, 1799 Mar, 2000 Gr. Beta 2.73 +/- 1.85 0.76 +/- 1.71 1.75 +/- 1.26 AP-2176, 2177 Mar, 2000 Be-7 0.06 +/- 0.01 0.08 +/- 0.02 0.07 +/- 0.01 WW-2046, 2047 Mar, 2000 H-3 221.85 +/- 101.64 185.19 +/- 100.24 203.52 +/- 71.38 SW-1967, 1968 Apr, 2000 K-40 9.20 +/- 0.90 9.10 +/- 0.90 9.15 +/- 0.64 SW-2241, 2242 Apr, 2000 Gr. Alpha 2.49 +/-1.44 3.15 +/- 1.53 2.82 _+1.05 SW-2241, 2242 Apr, 2000 Gr. Beta 8.37 +/- 1.36 7.20 +/- 1.29 7.79 +/- 0.94 WW-2342, 2343 Apr, 2000 Gr. Beta 4.20 +/-0.64 4.68 +/- 0.73 4.44 +/- 0.49 WW-2711, 2712 Apr, 2000 Cs-137 -0.76 +/-2.19 1.43 +/- 3.63 0.34 +/- 2.12 WW-2711, 2712 Apr, 2000 H-3 3,877.05 +/- 192.54 3,951.88 +/- 193.99 3,914.46 +/- 136.66 WW-2511, 2512 Apr, 2000 H-3 108.10 +/- 79.80 127.80 +/-80.70 117.95 +/- 56.75 SO-2435, 2436 Apr, 2000 K-40 4.73 +/- 0.38 4.83 +/- 0.53 4.78 +/- 0.33 SS-2669, 2670 Apr, 2000 K-40 8.60 +/- 0.55 9.18 +/- 0.45 8.89 +/- 0.36 SWU-2732, 2733 Apr, 2000 Gr. Beta 3.33 +/- 0.68 3.19 +/- 0.69 3.26 +/- 0.48 PW-2605, 2606 Apr, 2000 Co-60 0.36 +/- 1.10 1.05 +/- 2.03 0.71 +/- 1.16 PW-2605, 2606 Apr, 2000 Cs-137 -0.07 +/- 0.93 -0.98 +/- 2.37 -0.53 +/- 1.27 PW-2605, 2606 Apr, 2000 Gr. Beta 1.51 +/- 1.31 2.91 +/- 1.39 2.21 +/- 0.96 WW-2711, 2712 Apr, 2000 H-3 3,877.00 +/- 192.50 3,951.90 +/- 194.00 3,914.45 - 136.65 WW-2711, 2712 Apr, 2000 Co-60 0.97 +/- 1.93 0.82 +/- 3.64 0.90 +/- 2.06 BS-3212, 3213 Apr, 2000 Gr. Beta 7.90 +/- 1.97 7.57+/- 1.88 7.74 +/- 1.36 MI-2810, 2811 May, 2000 K-40 1,285.00 +/- 111.00 1,338.00 +/- 127.00 1,311.50 +/- 84.34 SW-3003, 3004 May, 2000 Gr. Beta 5.06 +/- 0.73 5.27+/-0.73 5.17 +/- 0.52 A5-2

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result SW-3003, 3004 May, 2000 K-40 1.30 + 0.13 1.20 +/- 0.12 1.25 +/- 0.09 F-2831, 2832 May, 2000 Co-60 0.01 +/- 0.01 0.00 +/- 0.01 0.01 +/- 0.01 F-2831, 2832 May, 2000 Cs-137 -0.00 + 0.01 0.00 +/- 0.01 0.00 +/- 0.01 WW-3128, 3129 May, 2000 Gr. Beta 5.41 +/- 1.35 4.43 +/- 1.22 4.92 +/- 0.91 BS-3411, 3412 May, 2000 Co-60 -0.00 +/- 0.01 0.01 +/- 0.01 0.00 +/- 0.01 BS-3411, 3412 May, 2000 Cs-137 0.01 +/- 0.01 0.00 +/- 0.01 0.00 +/- 0.00 F-3436, 3437 May, 2000 Co-60 0.01 +/- 0.01 0.00 +/- 0.01 0.01 +/- 0.00 F-3436, 3437 May, 2000 Cs-137 0.00 +/- 0.01 -0.00 +/- 0.00 -0.00 +/- 0.00 F-2978, 2979 May, 2000 K-40 2.72 +/- 0.26 2.14 +/- 0.30 2.43 +/- 0.20 SS-3482, 3483 May, 2000 Cs-137 0.11 +/-0.03 0.12 +/- 0.03 0.12 +/- 0.02 SS-3482, 3483 May, 2000 K-40 11.26 +/- 0.57 11.37 +/- 0.54 11.32 +/- 0.39 BS-3458, 3459 May, 2000 Co-60 0.01 +/- 0.01 0.02 +/- 0.01 0.01 +/- 0.01 BS-3458, 3459 May, 2000 Cs-137 0.04 +/- 0.01 0.03 +/- 0.02 0.03 +/- 0.01 MI-3510, 3511 May, 2000 Co-60 0.48 +/-3.05 -0.80 +/- 2.74 -0.16 +/- 2.05 MI-3510, 3511 May, 2000 Cs-137 1.17 +/- 2.96 0.38 +/- 2.60 0.77 +/- 1.97 MI-3510, 3511 May, 2000 1-131 -0.06 +/- 0.25 -0.04 +/- 0.24 -0.05 +/- 0.17 SO-3629, 3630 May, 2000 Cs-137 0.23 +/-0.03 0.20 +/-0.03 0.22 +/- 0.02 SO-3629, 3630 May, 2000 Gr. Beta 20.49 +/- 2.82 19.14 +/- 2.73 19.82 +/- 1.96 SO-3629, 3630 May, 2000 K-40 13.03 +/- 0.61 12.25 +/- 0.57 12.64 +/- 0.42 SW-3904, 3905 May, 2000 Gr. Beta 6.27 +/- 1.83 7.02 +/- 1.90 6.65 +/- 1.32 SW-3904, 3905 May, 2000 Co-60 -0.65 +/- 1.54 1.32 _ 1.77 0.33 +/- 1.17 SW-3904, 3905 May, 2000 Cs-137 0.19 +/-1.22 -0.16 +/- 1.15 0.01 +/- 0.84 SW-3904, 3905 May, 2000 Gr. Beta 6.27 +/- 1.83 7.02 +/- 1.90 6.64 +/-1.32 SP-3833, 3834 May, 2000 Gr. Alpha 4.19 +/- 1.34 3.22 +/- 1.20 3.71 +/- 0.90 MI-3105, 3106 May, 2000 K-40 1,460.00 +/- 173.00 1,452.00 +/- 110.00 1,456.00 +/- 102.50 VE-3191, 3192 May, 2000 Be-7 0.42 +/-0.23 0.39 +/- 0.16 0.40 +/- 0.14 VE-3191, 3192 May, 2000 Gr. Alpha 0.15 +/- 0.06 0.28 +/- 0.07 0.22 +/- 0.05 VE-3191, 3192 May, 2000 Gr. Beta 3.76 +/- 0.13 3.88 +/- 0.14 3.82 +/- 0.10 VE-3191, 3192 May, 2000 K-40 3.58 +/- 0.43 3.47 +/- 0.72 3.53 +/- 0.42 MI-3718, 3719 May, 2000 K-40 1,447.00 +/- 165.00 1,444.00 +/- 177.00 1,445.50+/- 120.99 DW-3770, 3771 May, 2000 Gr. Beta 5.92 +/- 1.32 4.54 +/- 1.10 5.23 +/- 0.86 MI-3653, 3654 Jun, 2000 K-40 1,407.00 +/- 170.00 1,388.00 +/- 102.00 1,397.50 +/- 99.13 SW-4614, 4615 Jun, 2000 Sr-90 0.50 +/- 0.27 0.55 +/- 0.27 0.53 +/- 0.19 WW-3883, 3884 Jun, 2000 H-3 4,401.80 +/- 204.60 4,298.00 +/- 202.70 4,349.90 +/- 144.00 WW-3883, 3884 Jun, 2000 Co-60 0.91 +/-3.01 -0.28 +/- 1.52 0.32 +/- 1.69 WW-3883, 3884 Jun, 2000 Cs-137 0.49 +/- 2.16 0.66 +/- 1.82 0.57 +/- 1.41 WW-3883, 3884 Jun, 2000 H-3 4,401.78 +/-204.63 4,297.96 +/- 202.67 4,349.87+/- 144.00 A5-3

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result BS-3980, 3981 Jun, 2000 Cs-137 0.07 +/- 0.02 0.08 +/- 0.02 0.08 +/- 0.01 BS-3980, 3981 Jun, 2000 Cs-137 0.06 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 BS-3980, 3981 Jun, 2000 K-40 1,458.60 +/- 69.40 1,421.90 +/- 52.20 1,440.25 +/- 43.42 VE-4065, 4066 Jun, 2000 K-40 6.37 +/- 0.54 6.34 +/- 0.51 6.36 +/- 0.37 WW-4252, 4253 Jun, 2000 H-3 705.40 +/- 114.10 718.90 +/- 114.60 712.15 +/- 80.86 TSWU-4283, 4284 Jun, 2000 Gr. Beta 3.24 + 0.63 3.11 +/-0.62 3.18 +/- 0.44 F-4438, 4439 Jun, 2000 Gr. Beta 2.25 + 0.06 2.13 +/- 0.06 2.19 +/- 0.04 SW-4459, 4460 Jun, 2000 H-3 532.20 +/- 108.10 670.50 +/- 112.90 601.35 +/- 78.15 WW-4480, 4481 Jun, 2000 H-3 601.50 +/- 99.50 573.10 +/- 108.50 587.30 +/- 73.61 SW-4375, 4376 Jun, 2000 Gr. Beta 4.53 +/- 1.59 4.43+/-1.54 4.48 +/- 1.11 SW-4375, 4376 Jun, 2000 Cs-137 -0.09 +/- 1.61 -0.43 +/- 1.39 -0.26 +/- 1.06 AP-4712, 4713 Jun, 2000 Be-7 0.07.-t+/-0.02 0.09 +/- 0.02 0.08 +/- 0.01 AP-4754, 4755 Jun, 2000 Be-7 0.06 +/- 0.02 0.07 +/- 0.01 0.07 +/- 0.01 SW-4537, 4538 Jun, 2000 H-3 584.10 +/- 108.80 599.20 +/- 109.30 591.65 +/- 77.11 SL-4636, 4637 Jul, 2000 Be-7 0.93 +/- 0.18 0.56 +/- 0.12 0.75 +/- 0.11 SL-4636, 4637 Jul, 2000 Gr. Beta 2.41 +/- 0.32 2.69 +/- 0.32 2.55 +/- 0.23 SL-4636, 4637 Jul, 2000 K-40 1.25 +/- 0.24 1.13 +/- 0.30 1.19 +/- 0.19 SL-4636, 4637 Jul, 2000 Sr-90 0.04 +/- 0.02 0.05 +/- 0.03 0.05 +/- 0.02 G-4667, 4668 Jul, 2000 Be-7 0.93 +/- 0.20 0.98 +/- 0.31 0.96 +/- 0.18 G-4667, 4668 Jul, 2000 Gr. Beta 6.16 +/- 0.13 6.68 +/- 0.14 6.42 +/- 0.10 G-4667, 4668 Jul, 2000 K-40 7.72 +/- 0.51 8.43 +/- 0.83 8.08 +/- 0.49 WW-4818, 4819 Jul, 2000 H-3 13.30 +/- 77.10 29.70 +/- 77.90 21.50 +/- 54.80 MI-4839, 4840 Jul, 2000 K-40 1,313.00 +/- 173.00 1,398.00 +/- 161.00 1,355.50 +/- 118.16 MI-4949, 4950 Jul, 2000 K-40 1,307.00 +/- 56.00 1,346.00 +/- 58.00 1,326.50 +/- 40.31 LW4991, 4992 Jul, 2000 Gr. Beta 2.78 +/- 0.66 2.22 +/- 0.55 2.50 +/- 0.43 MI-4903, 4904 Jul, 2000 K-40 1,383.10 +/- 193.20 1,328.00 +/- 153.10 1,355.55 +/- 123.25 MI-4881, 4882 Jul, 2000 K-40 1,538.40 +/- 103.00 1,438.00 +/-125.30 1,488.20 +/- 81.10 MI-4881, 4882 Jul, 2000 Sr-90 1.01 +/- 0.37 1.38 +/-+0.42 1.19 +/- 0.28 G-5388, 5389 Jul, 2000 Be-7 1.64 +/-0.16 1.52 +/- 0.21 1.58 +/- 0.13 G-5388, 5389 Jul, 2000 K-40 5.51 +/- 0.33 5.86 +/- 0.49 5.69 +/- 0.30 G-5388, 5389 Jul, 2000 Gr. Beta 5.64 +/- 0.15 5.81 +/-0.15 5.73 +/-0.11 SWU-5473, 5474 Jul, 2000 Gr. Beta 3.50 +/- 0.67 3.17 +/- 0.61 3.34 +/-0.45 SW-5410, 5411 Jul, 2000 Gr. Beta 1.95 +/- 0.81 1.89 +/- 1.04 1.92 +/- 0.66 PW-5550, 5551 Jul, 2000 Gr. Beta 0.71 +/- 1.15 2.50 +/- 1.49 1.61 +/- 0.94 WW-5623, 5624 Jul, 2000 H-3 "22,713.90+/- 429.00 22,265.50 +/- 424.90 22,489.70 +/- 301.90 MI-5529, 5530 Aug, 2000 K-40 1,396.80 +/- 103.80 1,278.20 +/- 117.50 1,337.50 +/- 78.39 VE-5745, 5746 Aug 2000 K-40 1.66 +/- 0.32 1.93 +/- 0.33 1.80 +/- 0.23 A5-4

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result MI-5808, 5809 Aug, 2000 K-40 1,261.90 + 124.40 1,234.40 +/- 152.80 1,248.15 +/- 98.52 CW-6514, 6515 Aug, 2000 Gr. Beta 1.42 + 0.37 1.44 +/- 0.41 1.43 +/- 0.28 MI-5933, 5934 Aug, 2000 Calcium 0.88 +/- 0.09 0.89 +/- 0.09 0.89 +/- 0.06 MI-5933, 5934 Aug 2000 Sr-90 3.29 +/- 0.51 1.72 +/- 0.47 2.51 +/- 0.35 VE-6002, 6003 Aug 2000 Sr-90 0.00 +0.00 0.00 +/- 0.00 0.00 +/- 0.00 VE-6002, 6003 Aug, 2000 K-40 1.44+/-0.23 1.78 +/- 0.18 1.61+/- 0.14 PW-6209, 6210 Aug, 2000 H-3 528.20 +/- 112.70 578.50+/-114.50 553.35 +/- 80.33 SW-6291, 6292 Aug&2000 Gr. Beta 4.14 +/- 1.58 1.95 +/- 1.32 3.05 +/- 1.03 WW-6312, 6313 Aug, 2000 H-3 7,804.20 +/- 262.70 7,221.70 +/-253.80 7,512.95 +/- 182.64 WW-5981, 5982 Aug, 2000 Gr. Beta 4.85 +/- 0.78 5.87 +/- 0.79 5.36 +/- 0.56 PW-6341, 6342 Aug 2000 Gr. Beta 2.45 +/- 1.42 2.63 +/- 1.37 2.54 +/- 0.99 CW-6514, 6515 Aug, 2000 H-3 5,600.10 +/- 226.80 5,434.30 +/- 223.90 5,517.20 +/- 159.35 MI-6409, 6410 Sep, 2000 1-131 -0.04 +/- 0.23 0.19 +/- 0.24 0.08 +/- 0.17 MI-6409, 6410 Sep, 2000 K-40 1,367.80 +/- 111.40 1,368.60 +/- 107.50 1,368.20+/- 77.41 MI-6409, 6410 Sep, 2000 Sr-90 1.19 +/- 0.35 0.80 +/- 0.30 1.00 +/- 0.23 MI-6542, 6543 Sep,2000 K-40 1,298.00 +/- 140.10 1,470.60 +/- 139.70 1,384.30 +/- 98.92 MI-6450, 6451 Sep, 2000 K-40 1,237.20 +/- 102.10 1,328.10 +/- 108.30 1,282.65 +/- 74.42 MI-7102, 7103 Sep, 2000 1-131 -0.11 +/- 0.23 -0.02 +/- 0.25 -0.07 +/- 0.17 MI-7102, 7103 Sep, 2000 K-40 1,473.10 +/- 101.40 1,400.70+/-168.60 1,436.90 +/- 98.37 Sep, 2000 Gr. Beta 3.45 +/- 0.66 2.32 +/- 0.57 2.89 +/- 0.44 SWT-7262, 7263 SWU-7283, 7284 Sep, 2000 Gr. Beta 2.75 +/- 0.55 2.87 +/- 0.56 2.81 +/- 0.39 SWU-7283, 7284 Sep, 2000 H-3 197.76 +/- 94.07 172.31 +/- 93.00 185.04 +/- 66.14 SW-7081, 7082 Sep, 2000 H-3 89.32 +/- 92.99 42.38 +/-90.37 65.85 +/- 64.83 AP-7685, 7686 Sep, 2000 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 AP-7706, 7707 Sep, 2000 Be-7 0.06 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 SW-7482, 7483 Sep, 2000 Gr. Beta 5.31 +/- 1.75 6.70 +/- 1.85 6.01 +/- 1.27 SP-7347, 7348 Sep, 2000 Gr. Alpha 6.12 +/- 1.54 5.68 +/- 1.49 5.90 +/- 1.07 SW-7436, 7437 Sep, 2000 H-3 40.60 +/- 79.90 72.00 +/- 81.40 56.30 +/- 57.03 CW-7748, 7749 Sep, 2000 Gr. Alpha 0.47 +/- 0.28 0.65 +/- 0.36 0.56 +/- 0.23 CW-7748, 7749 Sep, 2000 Gr. Beta 2.35 +/- 0.39 2.02 +/- 0.38 2.19 +/- 0.27 BS-7512, 7513 Oct, 2000 Cs-137 0.84 +/- 0.06 0.79 +/- 0.06 0.81 +/- 0.04 BS-7512, 7513 Oct, 2000 Gr. Beta 13.52 +/- 1.61 14.88 +/- 1.80 14.20.+/- 1.21 SL-7304, 7305 Oct, 2000 Gr. Beta 2.94 +/-0.23 2.90 +/- 0.23 2.92 +/- 0.17 SL-7304, 7305 Oct, 2000 K-40 1.14 +/- 0.36 1.73 +/- 0.58 1.44 +/- 0.34 BS-7369, 7370 Oct, 2000 Cs-137 10.79 +/- 4.96 20.04 +/--9.40 15.41 +/- 5.31 SO-7950, 7951 Oct, 2000 Ac-228 0.66 +/- 0.10 0.77 +/- 0.10 0.72 +/- 0.07 SO-7950, 7951 Oct, 2000 Bi-214 0.42 +/- 0.06 0.57+/-0.07 0.49 +/- 0.05 A5-5

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result SO-7950, 7951 Oct, 2000 Cs-137 0.20 +/- 0.31 0.21 +/- 0.04 0.20 +/- 0.16 SO-7950, 7951 Oct, 2000 Gr. Beta 29.22 +/- 1.98 28.02 +/- 1.98 28.62 + 1.40 SO-7950, 7951 Oct, 2000 K-40 21.36 +/- 0.93 21.77 +/- 0.89 21.56 + 0.64 SO-7950, 7951 Oct, 2000 Pb-212 0.72+/-0.12 0.92 +/- 0.12 0.82 +/-0.09 SO-7950, 7951 Oct, 2000 Ra-226 1.21 +/- 0.33 1.30 +/- 0.31 1.26 +/- 0.22 SO-7950, 7951 Oct, 2000 T1-208 0.21 +/- 0.04 0.25 +/- 0.03 0.23 +/- 0.02 VE-7554, 7555 Oct, 2000 Gr. Beta 0.73 +/- 0.02 0.74+/-0.02 0.74 +/- 0.01 MI-7622, 7623 Oct, 2000 K-40 1,505.90 +/-142.70 1,453.60+/-172.00 1,479.75 +/- 111.74 F-8219, 8220 Oct, 2000 K-40 2.94 +/- 0.22 3.39 +/- 0.38 3.16+/- 0.22 WW-7844, 7845 Oct, 2000 H-3 -68.13 +/- 74.09 84.23 +/- 81.38 8.05 +/- 55.03 WW-8240, 8241 Oct, 2000 Gr. Beta 0.35 +/-1.89 1.61 +/- 2.28 0.98 +/- 1.48 WW-8240, 8241 Oct, 2000 H-3 72.46 +/- 92.95 38.87 +/- 91.51 55.66 +/- 65.22 BS-8170, 8171 Oct, 2000 Gr. Beta 11.96 +/- 2.55 11.30 +/- 2.39 11.63 + 1.75 BS-8170, 8171 Oct, 2000 K-40 8.36 +/- 0.46 8.76 +/- 0.47 8.56 +/- 0.33 MI-8085, 8086 Oct, 2000 Calcium 0.94 0.94 0.94 MI-8085, 8086 Oct, 2000 Sr-90 1.04 +/- 0.35 0.75 +/- 0.31 0.90 +/- 0.24 MI-8149, 8150 Oct, 2000 K-40 1,358.10 +/- 95.81 1,341.80 +/- 178.00 1,349.95 +/- 101.07 SO-8967, 8968 Oct, 2000 Be-7 1.25 +/- 0.37 1.27 +/- 0.35 1.26 +/- 0.26 SO-8967, 8968 Oct, 2000 Cs-137 0.05 +/- 0.02 0.05 +/-0.02 0.05 +/- 0.02 SO-8967, 8968 Oct, 2000 K-40 4.53 +/- 0.66 4.46 +/- 0.58 4.50 +/- 0.44 MI-8522, 8523 Oct, 2000 1-131 -0.05 +/- 0.23 0.18 +/- 0.25 0.07 +/- 0.17 RW-8623, 8624 Oct, 2000 Ag-110M 99.79 +/-18.18 118.64 +/- 21.79 109.21 +/- 14.19 RW-8623, 8624 Oct, 2000 Co-60 2.47 +/- 0.10 2.56 +/- 0.10 2.51 +/- 0.07 RW-8623, 8624 Oct, 2000 Cs-134 228.46 +/- 17.29 229.75 +/-13.39 229.11 +/- 10.93 RW-8623, 8624 Oct, 2000 Cs-137 3.59 +/- 0.20 3.79 +/-0.20 3.69 +/- 0.14 RW-8623, 8624 Oct, 2000 Gr. Alpha 14.57 +/- 5.86 8.07 +/- 4.74 11.32 +/- 3.77 RW-8623, 8624 Oct, 2000 H-3 785.70 +/- 5.98 786.80 +/- 5.97 786.25 +/- 4.22 RW-8623, 8624 Oct, 2000 Mn-54 1.06 +/- 0.20 1.31 +/- 0.20 1.19 +/- 0.14 RW-8623, 8624 Oct, 2000 Pu-238 1.24 +/- 0.54 1.11+/-0.47 1.17 +/- 0.36 RW-8623, 8624 Oct, 2000 Pu-239/40 3.45 +/- 0.88 3.42 +/- 0.81 3.44 +/- 0.60 RW-8623, 8624 Oct, 2000 Sr-90 0.92 +/- 0.08 0.95 +/- 0.10 0.94 +/- 0.06 RW-8623, 8624 Oct, 2000 Zn-65 86.33 +/- 46.77 137.07 +/- 46.07 111.70 +/- 32.82 SWU-8894, 8895 Oct, 2000 Gr. Beta 3.63 +/-0.62 2.45 +/- 0.61 3.04 +/- 0.43 MI-8802, 8803 Nov, 2000 1-131 -0.22 +/- 0.24 -0.25 +/- 0.26 -0.24 +/- 0.18 MI-8802, 8803 Nov, 2000 K-40 1,340.50 +/- 113.80 1,453.50+/-100.50 1,397.00 +/- 75.91 MI-8802, 8803 Nov, 2000 Sr-89 0.19 - 1.31 0.61+/- 1.34 0.40 +/- 0.94 MI-8802, 8803 Nov, 2000 Sr-90 1.10 +/- 0.39 0.90 +/- 0.38 1.00 +/- 0.27 A5-6

Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result LW-8823, 8824 Nov, 2000 Gr. Beta 2.13 k 0.55 1.59 . 0.52 1.86 + 0.38 VE-9014, 9015 Nov, 2000 Gr. Alpha 0.10 _-0.06 0.15 +/- 0.07 0.12 +/- 0.05 VE-9014, 9015 Nov, 2000 Gr. Beta 5.59 +/- 0.17 5.90 +/- 0.19 5.74 +/- 0.13 F-9469, 9470 Nov, 2000 Gr. Beta 5.51+/-1.34 5.16 +/- 1.12 5.34 +/- 0.87 PW-9991, 9992 Nov, 2000 Gr. Beta 2.50 +/- 0.01 3.49 +/- 1.18 3.00 +/- 0.59 SW-9991, 9992 Nov, 2000 Co-60 1.16 +/-1.70 -2.94 +/- 3.39 -0.89 +/- 1.89 SW-9991, 9992 Nov, 2000 Cs-134 -0.07 +/- 1.85 2.27 +/- 3.73 1.10 +/- 2.08 SW-9991, 9992 Nov, 2000 Cs-137 -0.88 +/- 1.67 3.84 +/- 3.45 1.48 +/- 1.92 DW-9682, 9683 Dec, 2000 Gr. Beta 1.61 +/- 1.02 2.10 +/- 0.94 1.86 +/- 0.69 MI-9749, 9750 Dec, 2000 K-40 1,562.40+/-118.70 1,495.90 +/- 168.30 1,529.15 +/- 102.97 MIv-9776, 9777 Dec, 2000 K-40 1,185.90 +/- 88.05 1,409.60 +/- 175.80 1,297.75 _ 98.31 PW-10234, 10235 Dec, 2000 H-3 104.66 +/- 93.36 110.62 +/- 93.61 107.64 +/- 66.11 DW-10302, 10303 Dec, 2000 Gr. Beta 2.23 +/- 1.62 2.08 +/- 1.62 2.16 +/- 1.15 AP-10845, 10846 Dec, 2000 Co-60 -0.00 +/- 0.00 0.00 +/- 0.00 -0.00 +/- 0.00 AP-10845, 10846 Dec, 2000 Cs-134 0.00 +/- 0.00 0.00 +/- 0.00 0.00 + 0.00 AP-10845, 10846 Dec, 2000 Cs-137 0.00 +/- 0.00 -0.00 +/- 0.00 0.00 +/- 0.00 AP-10782, 10783 Dec, 2000 Be-7 0.21 +/- 0.10 0.31 +/- 0.14 0.26 +/- 0.09 AP-10824, 10825 Dec, 2000 Be-7 0.06 +/- 0.02 0.07 +/- 0.01 0.06 +/- 0.01 AP-10866, 10867 Dec, 2000 Co-60 0.00 +/- 0.00 -0.00 +/- 0.00 0.00 h 0.00 AP-10866, 10867 Dec, 2000 Cs-134 -0.00 +/- 0.00 0.00 +/- 0.00 -0.00 k 0.00 AP-10866, 10867 Dec, 2000 Cs-137 0.00 +/- 0.00 0.00 +/- 0.00 0.00 +/- 0.00 WW-10424, 10425 Dec, 2000 H-3 1,690.87 +/- 137.81 1,551.48 +/- 1,339.42 1,621.18 +/- 673.25 SW-10596, 10597 Dec, 2000 H-3 445.47 +/- 106.70 423.46 +/- 105.87 434.47 +/- 75.16 LW-10529, 10530 Dec, 2000 Gr. Beta 2.21 +/- 0.45 2.06 +/- 0.40 2.14 +/- 0.30 aAll results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/Filter; and food products, which are in mg/kg.

A5-7

Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentrationb Lab Sample Date MAPEP Resulte Control Code Type Collected Analysis Laboratory resultc Is, N=1 Limits STSO-882 SOIL Jan, 2000 Am-241 64.90 +/- 6.49 61.10 42.77 - 79.43 949.00 664.30 - 1,233.70 STSO-882 SOIL Jan, 2000 Co-57 721.10 +/- 83.80 geometry. The The MAPEP soil sample (STSO-882), as received, did not closely match a standard gamma results for gamma-emitting isotopes are reanalyses, with a reduced sample size.

1,264.40 +/- 78.60 1,180.00 826.00 - 1,534.00 STSO-882 SOIL Jan, 2000 Co-60 969.30 +/- 76.90 1,047.00 732.90 - 1,361.10 STSO-882 SOIL Jan, 2000 Cs-134 944.00 +/- 92.00 930.00 651.00 - 1,209.00 STSO-882 SOIL Jan, 2000 Cs-137 811.70 +/- 79.90 652.00 456.40 - 847.60 STSO-882 SOIL Jan, 2000 K-40 1,023.00 716.10 - 1,329.90 STSO-882 SOIL Jan, 2000 Mn-54 1,103.30 +/- 64.20 960.00 672.00 - 1,248.00 STSO-882 SOIL Jan, 2000 Ni-63 711.00 +/- 71.10 74.40 52.08 - 96.72 STSO-882 SOIL Jan, 2000 Pu-239/40 67.90 +/- 6.79 304.00 212.80 - 395.20 STSO-882 SOIL Jan, 2000 Sr-90 345.00 +/- 34.50 90.00 63.00 - 117.00 STSO-882 SOIL Jan, 2000 U-233/4 62.90 +/- 6.29 Incomplete dissolution of the sample is suspected.

Results of reanalysis: U-233/234 67.3 +/- 3.3 pCi/g, U-238 68.1 +/- 8.9 pCi/g.

93.00 65.10 - 120.90 STSO-882 SOIL Jan, 2000 U-238 63.20 + 6.32 1,540.00 1,078.00 - 2,002.00 STSO-882 SOIL Jan, 2000 Zn-65 1,544.30 +/- 61.50 aResults obtained by Environmental Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b All results are in Bq/kg or Bq/L as requested by the Department of Energy.

Unless otherwise indicated, laboratory results are given as the mean t 1 standard deviations for three determinations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination),

and control limits as defined by the MAPEP.

A6-1

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)a.

b Concentration Lab Saihple Date Control Code Type Collected Analysis Laboratory resultc EML Result Limitse STSO-870 SOIL Mar, 2000 Ac-228 98.300 +/- 7.100 97.600 0.79- 1.75 STSO-870 SOIL Mar, 2000 Bi-212 98.500 +/- 15.100 106.000 0.42- 1.22 STSO-870 SOIL Mar, 2000 Bi-214 88.000 +/-3.800 86.700 0.75- 1.42 STSO-870 SOIL Mar, 2000 Cs-137 324.000 +/- 5.000 339.000 0.83- 1.32 STSO-870 SOIL Mar, 2000 K-40 872.000 +/- 34.000 811.000 0.78- 1.53 STSO-870 SOIL Mar, 2000 Pb-212 93.700 +/-2.700 97.300 0.74- 1.33 STSO-870 SOIL Mar, 2000 Pb-214 100.100 +/- 3.700 86.500 0.65- 1.45 STSO-870 SOIL Mar, 2000 Pu-238 19.800 +/- 3.000 18.600 0.52- 2.84 STSO-870 SOIL Mar, 2000 Pu-239/40 8.100 +/- 1.700 7.000 0.69- 1.74 STSO-870 SOIL Mar, 2000 Sr-90 13.600 +/- 3.100 20.200 0.60- 3.66 STVE-871 VEGETATION Mar, 2000 Am-241 9.800 +/- 0.900 10.400 0.68 - 2.70 STVE-871 VEGETATION Mar, 2000 Co-60 46.500 +/-2.100 52.800 0.69- 1.46 STVE-871 VEGETATION Mar, 2000 Cs-137 1,872.000 +/- 46.000 1,380.000 0.80- 1.40 STVE-871 VEGETATION Mar, 2000 K-40 506.400 +/- 28.000 521.000 0.79- 1.42 STVE-871 VEGETATION Mar, 2000 Pu-239/40 14.300 +/- 1.500 15.500 0.68- 1.59 STVE-871 VEGETATION Mar, 2000 Sr-90 1,198.000+/-85.000 1,780.000 0.50- 1.33 STAP-872 AIR FILTER Mar, 2000 Co-57 5.900 +/- 0.100 5.310 0.65- 1.39 STAP-872 AIR FILTER Mar, 2000 Co-60 5.900 +/- 0.100 5.320 0.75- 1.32 STAP-872 AIR FILTER Mar, 2000 Cs-137 7.500 +/- 0.100 6.100 0.73- 1.37 STAP-872 AIR FILTER Mar, 2000 Gr. Alpha 3.300 +/- 0.100 3.020 0.50- 1.55 STAP-872 AIR FILTER Mar, 2000 Gr. Beta 2.700 +/- 0.100 2.420 0.72- 1.67 AIR FILTER Mar, 2000 Mn-54 31.800 +/- 0.300 27.200 0.76- 1.33 STAP-872 AIR FILTER Mar, 2000 Pu-238 0.060 +/- 0.030 0.080 0.74- 1.40 STAP-872 AIR FILTER Mar, 2000 Pu-239/40 0.090 +/- 0.010 0.089 0.76- 1.44 STAP-872 STAP-872 AIR FILTER Mar, 2000 Ru-106 3.500 +/- 1.000 2.010 0.59- 1.30 Result within activity -herror margin.

AIR FILTER Mar, 2000 Sr-90 0.310 +/- 0.160 0.242 0.61 - 1.93 STAP-872 AIR FILTER Mar, 2000 Uranium 0.120 _ 0.010 0.126 0.80 - 3.35 STAP-872 Mar, 2000 Am-241 1.700 +/- 0.220 1.950 0.75- 1.49 STW-874 WATER Mar, 2000 Co-60 51.000 +/- 1.200 48.900 0.80- 1.20 STW-874 WATER A7-1

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)a.

Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory resultc EML Resultd Limitse STW-874 WATER Mar, 2000 Cs-137 108.600 _ 1.800 103.000 0.80- 1.26 STW-874 WATER Mar, 2000 Fe-55 33.000

  • 1.200 33.100 0.44- 1.53 Mar, 2000 Gr. Alpha 1,217.000 + 35.000 1,700.000 0.61 - 1.32 STW-874 WATER STW-874 WATER Mar, 2000 Gr. Beta 792.000 + 25.000 690.000 0.55- 1.54 WATER Mar, 2000 H-3 147.000 + 26.000 79.400 0.71 - 1.79 STW-874 Analysis was repeated; result of reanalysis; 97.5 + 11.6 Bq/1.

WATER Mar, 2000 Ni-63 101.000 +/- 6.000 112.000 0.25 - 1.75 STW-874 Mar, 2000 Pu-238 0.750 +/- 0.170 0.944 0.78 - 1.25 STW-874 WATER WATER Mar, 2000 Pu-239/40 0.990 +/- 0.090 0.918 0.80- 1.39 STW-874 Mar, 2000 Sr-90 4.460 +/- 0.990 3.390 0.75- 1.50 STW-874 WATER WATER Mar, 2000 Uranium 0.270 +/- 0.020 0.995 0.67- 1.42 STW-874 Result r*!ported was for U-234. Result for U (total); 0.58 +/- 0.02 pCi/L.

Sep, 2000 Ac-228 78.000 +/- 1.500 80.200 0.80- 1.50 STSO-885 SOIL Bi-212 73.000 +/- 3.300 80.500 0.45 - 1.23 STSO-885 SOIL Sep, 2000 Sep, 2000 Bi-214 91.000 +/- 4.000 83.300 0.78 - 1.50 STSO-885 SOIL Cs-137 925.700 +/- 14.200 1,020.000 0.80 - 1.29 STSO-885 SOIL Sep, 2000 K-40 713.600 +/- 7.100 713.000 0.80 - 1.37 STSO-885 SOIL Sep, 2000 Sep, 2000 Pb-212 66.100 +/- 4.300 79.300 0.74- 1.36 STSO-885 SOIL Pb-214 100.100 + 3.700 86.300 0.76- 1.53 STSO-885 SOIL Sep, 2000 18.400 +/- 0.400 16.800 0.71 - 1.33 STSO-885 SOIL Sep, 2000 Pu-239/40 Sep, 2000 Sr-90 39.900 +/- 5.300 50.400 0.61 - 3.91 STSO-885 SOIL 154.700 :t 9.300 148.000 0.68 - 2.36 STSO-885 SOIL Sep, 2000 Th-234 254.300 +/- 13.000 327.000 0.62- 1.35 STSO-885 SOIL Sep, 2000 Uranium 1.300 +/- 0.200 1.190 0.76 - 1.48 STW-886 WATER Sep, 2000 Am-241 Co-60 71.900 +/- 7.200 73.700 0.80- 1.20 STW-886 WATER Sep, 2000 Cs-137 62.700 +/- 6.300 67.000 0.80 - 1.24 STW-886 WATER Sep, 2000 91.300 0.74 - 2.29 STW-886 WATER Sep, 2000 H-3 92.300 +/- 8.900 0.786 0.74 - 1.22 STW-886 WATER Sep, 2000 Pu-238 0.700 +/- 0.100 0.600 +/-0.100 0.591 0.75- 1.26 STW-886 WATER Sep, 2000 Pu-239/40 4.530 0.64- 1.50 STW-886 WATER Sep, 2000 Sr-90 4.600 +/- 0.400 A7-2

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)a.

Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result' EML Result" Limits' STW-886 WATER Sep, 2000 Uranium 0.800 +/- 0.100 0.916 0.73- 1.37 STW-887 WATER Sep, 2000 Gr. Alpha 1,113.700 +/- 17.900 1,070.000 0.58- 1.26 STW-887 WATER Sep, 2000 Gr. Beta 1,129.400 +/- 16.700 950.000 0.56- 1.50 STAP-888 AIR FILTER Sep, 2000 Am-241 0.060 +/- 0.010 0.032 0.69 - 2.40 STAP-888 AIR FILTER Sep, 2000 Co-57 16.500 +/- 0.600 14.500 0.69- 1.37 STAP-888 AIR FILTER Sep, 2000 Co-60 9.200 +/- 0.400 8.430 0.79- 1.30 STAP-888 AIR FILTER Sep, 2000 Cs-137 8.800 +/- 0.500 7.410 0.78- 1.35 STAP-888 AIR FILTER Sep, 2000 Mn-54 50.200 +/- 2.300 43.200 0.80- 1.36 STAP-888 AIR FILTER Sep, 2000 Pu-238 0.033 +/-0.010 0.045 0.66- 1.35 STAP-888 AIR FILTER Sep, 2000 Pu-239/40 0.080 +/- 0.010 0.074 0.69- 1.29 STAP-888 AIR FILTER Sep, 2000 Sr-90 3.300 +/- 0.100 1.640 0.55- 2.05 STAP-888 AIR FILTER Sep, 2000 U-233/4 0.034 +/- 0.001 0.040 0.80- 1.92 STAP-888 AIR FILTER Sep, 2000 U-238 0.032 + 0.010 0.041 0.80- 1.59 Result within activity -t error margin.

STAP-888 AIR FILTER Sep, 2000 Uranium 0.070 +/- 0.010 0.083 0.80- 2.54 STAP-889 AIR FILTER Sep, 2000 Gr. Alpha 2.840 +/- 0.010 2.350 0.57- 1.47 AIR FILTER Sep, 2000 Gr. Beta 2.080 +/- 0.020 1.520 0.76- 1.52 STAP-889 VEGETATIOI', I Sep, 2000 Am-241 5.900 . 1.200 5.600 0.72- 2.34 STVE-890 STVE-890 VEGETATIOINJ Sep, 2000 Cm-244 3.200 +/- 0.100 3.600 0.61- 1.61 VEGETATIO1N4 Sep, 2000 Co-60 29.400 +/- 0.400 32.800 0.75- 1.51 STVE-890 STVE-890 VEGETATIOb' J Sep, 2000 Cs-137 739.300 +/- 23.000 867.000 0.80- 1.37 VEGETATIOI' 4 Sep, 2000 K-40 597.500 +/- 49.300 639.000 0.78 - 1.43 STVE-890 VEGETATIOIP .4 Sep, 2000 Pu-239/40 4.500 +/- 0.200 9.600 0.67- 1.49 STVE-890 Bq/kg.

No reason for deviation was found with original result. The result of reanalysis; 12.1 +/-k1.1 Sr-90 1,201.500 + 117.300 1,150.000 0.52- 1.23 STVE-890 VEGETATION Sep, 2000 A7-3

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)a.

b Concentration Lab Sample Date Control Code Type Collected Analysis Laboratory result' EML Resultd Limitse a The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Vegetation and Water.

b Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported intBq/Kg.

C Laboratory results are reported as the mean of three determinations +/- standard deviation.

d The EML result listed is the mean of replicate determinations for each nuclide+/-the standard error of the mean.

" The control limits are reported by EML as the ratio of Reported Value / EML value.

A7-4

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x +/-s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; Xl +/- Sl and X2 +/- s2 s2 .2 Reported result: x +/- s; where x = (1/2) (xI + x2) and s = (1/2) s1+2 3.2. Individual results: <Li, <L2 Reported result: <L, where L = lower of Li and L2 3.3. Individual results: x +/- s, <L Reported result: x 4- s if x > L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x 1 , x 2 ... xn are defined as follows:

-1x-Y-n x s=

)2_

n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.

B-2

APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.

Air (pCi/m 3 ) Water (pCi/L)

Gross alpha I x 10- 3 Strontium-89 8,000 Gross beta 1 Strontium-90 500 Iodine-131b 2.8 x 10- 1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x 106 a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

c A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps D-1

TLD LOCATIONS ONE MILE RADIUS J

PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]

[NO SCALE]

MONITORING LEGEND:

C) N.S.P. TLD POINTS D-2 TLDOI.DGN D-2 TLD0LOGN

TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLD LOCATIONS MONITORING LEGEND:

0 N.S.P. TLD POINTS D-3 TLD02.DGN

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

0 N.S.P. TLD POINTS D-4 TLD03.DGN

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J

PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]

[NO SCALE]

MONITORING LEGEND

<$> FISH SAMPLING POINT ID NUMBERS MILK SAMPLING POINT IM NUMBERS P-14. P-18. P-37. P-41 e] P-13, P-19 A* AIR SAMPLING POINT ID NUMBERS P-1, P-2. P-3, P-4, P-S INVERTEBRATES POINT ID NUMBERS P-6. P-40 WATER SAMPLING POINT ID NUMBERS P-5, P-B, P-8. P-9. P-11, P-24, P-41 SEDIMENT SAMPLING POINT ID NUMBERS P-f. P-12, P-20 El VEGETATION / VEGETABLES ID NUMBERS P-24. P-38 D-5 SAMPOI.DGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS 4.7 MONITORING LEGEND SAMPLING POINT ID NUMBERS FISH SAMPLING POINT ID NUMBERS P-14. P-18. P-37, P-41 P-13o P-i9 A* AIR SAMPLING POINT ID NUMBERS P-i, P-2, P-3, P-4, P-6 INVERTEBRATES POINT ID NUMBERS P-6. P-40 SAMPLING POINT ID NUMBERS SEDIMENT SAMPLING POINT ID NUMBERS P-5. P-6. P-B, P-9. P-11, P-24, P-41 P-S. P-12, P-20 r* VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 D-6 SAMP03.DGN

ENVIRONMENTAL SAMPLING POINTS P-1

()<) HUPPERT FARM. W 1430 ST RD 29, FRVER FALLS, WL E] CAIN RESIDENCE, N73%5 % ST. RIVER FALLS, W*.

CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

4. MILK SAMPLING POINT ID NUMBERS P-14, P-18, P-37, P-41 A AIR SAMPLING POINT ID NUMBERS P-i. P-2, P-3. P-4. P-6 0 WATER SAMPLING POINT ID NUMBERS P-5, P-6,, P-8, P-% P-11. P-41 n VEGETATION / VEGETABLES ID NUMBERS P-24, P-38 D-7 SAMP02.DGN D-7 SAMP02.DGN