L-MT-16-030, Transmittal of 2015 Annual Radiological Environmental Operating Report: Difference between revisions

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| issue date = 05/12/2016
| issue date = 05/12/2016
| title = Transmittal of 2015 Annual Radiological Environmental Operating Report
| title = Transmittal of 2015 Annual Radiological Environmental Operating Report
| author name = Gardner P A
| author name = Gardner P
| author affiliation = Northern States Power Co, Xcel Energy
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:(l JCcel Energy" May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2015 Annual Radiological Environmental Operating Report Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT-16-030 10 CFR 50, Appendix I Pursuant to 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3, IV.C and, in accordance with Monticello Nuclear Generating Plant (MNGP) Technical Specifications 5.6.1, the Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, is submitting the Annual Radiological Environmental Operating Report, under MNGP's "Radiological Environmental Monitoring Program," for year 2015. Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company -Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, Resident Inspector, Monticello Minnesota Department of Commerce ENCLOSURE 1 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1 -DECEMBER 31, 2015 100 Pages to Follow I Environmental, Inc. Midwest Laboratory 700 landw*hr Road
{{#Wiki_filter:(l JCcel Energy"                                                       Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 May 12, 2016                                                                               L-MT-16-030 10 CFR 50, Appendix I ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2015 Annual Radiological Environmental Operating Report Pursuant to 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3, IV.C and, in accordance with Monticello Nuclear Generating Plant (MNGP) Technical Specifications 5.6.1, the Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, is submitting the Annual Radiological Environmental Operating Report, under MNGP's "Radiological Environmental Monitoring Program," for year 2015.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
  ~~
Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc:   Administrator, Region Ill, USNRC Project Manager, Monticello, Resident Inspector, Monticello Minnesota Department of Commerce
 
ENCLOSURE 1 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1 - DECEMBER 31, 2015 100 Pages to Follow
 
Environmental, Inc.
Midwest Laboratory 700 landw*hr Road
* Northbroak,ll60061-1310 phone (847) 564-0700
* Northbroak,ll60061-1310 phone (847) 564-0700
* fax (847) 564-4517 Approved:
* fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc.
XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc. Midwest Laboratory Project No. 8010 PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation.
Midwest Laboratory Project No. 8010 Approved:
This report was prepared by Environmental, Inc., Midwest Laboratory.
 
ii TABLE OF CONTENTS Preface .......................................................................................................................................
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.
ii List ofT abies .......................................................................................................................
ii
iv List of Figures ......................................................................................................................
v


==1.0 INTRODUCTION==
TABLE OF CONTENTS Preface ....................................................................................................................................... ii List ofT abies ....................................................................................................................... iv List of Figures ...................................................................................................................... v


...........................................................................................................
==1.0    INTRODUCTION==
: ...........
...........................................................................................................:........... 1 2.0  
1 2.0  


==SUMMARY==
==SUMMARY==
  .............................................................................................  
  ..............................................................................................' ................................... 2 3.1   RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) ......................... 3 3.2       Program Design and Data Interpretation ................................................................ 3 3.3       Program Description ............................................................................................... 4 3.4       Program Execution ................................................................................................. 5 3.5       Program Modifications ............................................................................................ 5 3.6       Laboratory Procedures ........................................................................................... 6 3.7       Land Use Census ................................................................................................... 6 4.1   RESULTS AND DISCUSSION ............................................................................................ 7 4.2       Atmospheric Nuclear Detonations and Nuclear AcCidents ...................................... 7 4.3       Summary of Preoperational Data ........................................................................... 7 4.4       Program Findings ................................................................................................... 8 5.0   FIGURES AND TABLES ..................................................................................................... 12
.' ...................................
2 3.1 RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) .........................
3 3.2 Program Design and Data Interpretation  
................................................................
3 3.3 Program Description  
...............................................................................................
4 3.4 Program Execution  
.................................................................................................
5 3.5 Program Modifications  
............................................................................................
5 3.6 Laboratory Procedures  
...........................................................................................
6 3.7 Land Use Census ...................................................................................................
6 4.1 RESULTS AND DISCUSSION  
............................................................................................
7 4.2 Atmospheric Nuclear Detonations and Nuclear AcCidents  
......................................
7 4.3 Summary of Preoperational Data ...........................................................................
7 4.4 Program Findings ...................................................................................................
8 5.0 FIGURES AND TABLES .....................................................................................................
12  


==6.0 REFERENCES==
==6.0   REFERENCES==
...........................................................................................................................24 APPENDICES A    Interlaboratory Comparison Program Results .................................................................... A-1 B    Data Reporting Conventions ............................................................................................. B-1 C    Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .................................. :.......................... C-1 D    Sampling Location Maps ................................................................................................... D-1 E    Ground Water Monitoring Well Samples ................................... ;.. , .... :............................... E-1 3
 
LIST OF TABLES 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 The following tables are in the Appendices:
Appendix A A-1        Interlaboratory Comparison Program Results ................................................................A1-1 A-2        Thermoluminescentdosimeters (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    Resources Associates, Crosscheck Program Results (EML study replacement) ...................................................................................A7-1 Attachment A: Acceptance criteria for spiked samples .................................................... A2 Appendix C C-1        Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ..................................................................... C-2 Appendix E E-1      Sample Collection and Analysis Program, Ground Water, ............................................. E-6 E-2      Sampling Locations for Ground Water Monitoring Wells ................................................ E-6 E-3      Ground Water Monitoring Program Summary .................................................. ,............. E-7 E-4      Results of Analyses, Ground Water Monitoring Program ............................................... E-9 4


...........................................................................................................................
LIST OF FIGURES No.
24 APPENDICES A Interlaboratory Comparison Program Results ....................................................................
5-1      Offsite Ambient Radiation (TLDs), inner versus outer ring locations .......................................... 18 5-2      Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location .............................................................................................. 19 The following figures are located in the Appendices:
A-1 B Data Reporting Conventions
Appendix D D-1      Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................D-2 D-2      Sample collection and analysis program: TLD locations, OuterRing ..............................................................................................................................D-3 D-3      Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................D-4 D-4      Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations .......................................................................... D-5 D-5      Sample collection and analysis program: TLD locations,
.............................................................................................
        . ISFSI TLD Locations ................................................................................................................D-6 Appendix E E-1      Sample collection and analysis program:
B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area ..................................
Ground water, On-site monitoring well locations ..................................................................... E-8 5
: ..........................
C-1 D Sampling Location Maps ...................................................................................................
D-1 E Ground Water Monitoring Well Samples ...................................  
; .. , .... : ...............................
E-1 3 LIST OF TABLES 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 The following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results ................................................................
A1-1 A-2 Thermoluminescentdosimeters (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 Resources Associates, Crosscheck Program Results (EML study replacement)
...................................................................................
A 7-1 Attachment A: Acceptance criteria for spiked samples ....................................................
A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas .....................................................................
C-2 Appendix E E-1 Sample Collection and Analysis Program, Ground Water, .............................................
E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ................................................
E-6 E-3 Ground Water Monitoring Program Summary .................................................. , .............
E-7 E-4 Results of Analyses, Ground Water Monitoring Program ...............................................
E-9 4 LIST OF FIGURES No. 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations
..........................................
18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location ..............................................................................................
19 The following figures are located in the Appendices:
Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................
D-2 D-2 Sample collection and analysis program: TLD locations, OuterRing
..............................................................................................................................
D-3 D-3 Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................
D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations
..........................................................................
D-5 D-5 Sample collection and analysis program: TLD locations, . ISFSI TLD Locations
................................................................................................................
D-6 Appendix E E-1 Sample collection and analysis program: Ground water, On-site monitoring well locations  
.....................................................................
E-8 5


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


This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January -December, 2015. 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 Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2015.
Tabulations of the individual analyses made during the year are included in Part II of this report. The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota.
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.
Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971. 1 2.0  
Tabulations of the individual analyses made during the year are included in Part II of this report.
The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.
1
 
2.0  


==SUMMARY==
==SUMMARY==
The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant. Results for the year 2015 are summarized and discussed.
 
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant. 2 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment.
The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello 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 (TLD's). Sources of environmental radiation include the following:
Results for the year 2015 are summarized and discussed.
(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.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.
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 Monticello 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).
2
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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131.
3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello 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 (TLD's).
Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified:
Sources of environmental radiation include the following:
zirconium-95, cesium-137, cerium-144,  
(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.
?, and potassium-40.
In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.
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.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello 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.
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.
An additional interpretive technique involves analyses for specific radionuclides present in 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-
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-?
    ?, 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.
is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators.
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-? is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-1 03 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 of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
The other group quantified consists of niobium-95, ruthenium-1 03 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
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.
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 of corrosion products.
3
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.
3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.
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.
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.
3 3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision).
Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).
Maps of sampling locations are included in Appendix D. To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations.
Ambient gamma radiation is monitored at forty locations, using CaS0 4 :Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.
Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.
As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C).
Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131.
The samples are analyzed for iodine-131 and other gamma emitting isotopes.
Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.
Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged. Analysis is done for gamma-emitting isotopes.
One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector). Ambient gamma radiation is monitored at forty locations, using CaS0 4:Dy dosimeters with four sensitive areas at each location:
Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes. The Ground Water Monitoring Program is further described in Appendix E.
fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.
Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.
As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C). The samples are analyzed for iodine-131 and other gamma emitting isotopes.
Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged.
Analysis is done for gamma-emitting isotopes.
Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes.
The Ground Water Monitoring Program is further described in Appendix E. Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant and one downstream.
River water is collected weekly at two locations, one upstream of the plant and one downstream.
Monthly composites are analyzed for gamma-emitting isotopes.
Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Quarterly composites are analyzed for tritium. Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Quarterly composites are analyzed for tritium. The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.
Shoreline sediment is also collected from one downstream recreational location.
4
All samples are analyzed for gamma-emitting isotopes.
 
4 3.4 Program Execution The Program was executed as described in the preceding section with the following exceptions:
3.4 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Air Particulates I Air Iodine: M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station. M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
(1) Air Particulates I Air Iodine:
M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station.
M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report. M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015. The GFCI was tripped. The GFCI was reset. (2) Surface Water: Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.
M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report.
One TLD samples was found missing for the second quarter at Outer Ring location M-06B. Deviations from the program are summarized in Table 5.3. 3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015. 3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015.
The GFCI was tripped. The GFCI was reset.
(2) Surface Water:
Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.
One TLD samples was found missing for the second quarter at Outer Ring location M-06B.
Deviations from the program are summarized in Table 5.3.
3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015.
3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
5 Tritium concentrations are determined by liquid scintillation.
5
 
Tritium concentrations are determined by liquid scintillation.
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. Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.
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.
Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck)
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.
Programs.
: 3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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.
Results obtained in the crosscheck programs are presented in Appendix A. 3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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 2015 land use census was conducted between September 14 and September 24, 2015.
The 2015 land use census was conducted between September 14 and September 24, 2015. This is the third year using improved GPS software.
This is the third year using improved GPS software. The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.
The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.
There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.
There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.
The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways).
The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways). Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
6
6 4.1 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3. All 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. 4.2 Atmospheric Nuclear Detonations and Nuclear Accidents  
4.1 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.
' There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011. There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China. 4.3 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.
All 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.
Gross beta measurements in fallout averaged 20,600 pCi/m 3 in 1969 and 12,000 pCi/m 3 in 1970. These levels are reflected throughout the various media tested. In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 pCi/m 3. Present day levels have stabilized at around 0.025 pCi/m 3. Airborne radioiodine remained below detection levels of 0.03 pCi/m 3 In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored.
4.2       Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
In milk samples, low levels of Cs-137 and Sr-90 were detected.
There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
Cs-137 levels averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops. The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton.
4.3       Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 3                            3 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.
Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible.
In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3
However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.
pCi/m 3 . Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained 3
7 4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015. Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples. Ambient Radiation (TLD's) Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 -5 mi. distant from the Plant, at special interest areas and at four control locations.
below detection levels of 0.03 pCi/m In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.
The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively).
Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.
The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1). Year Inner Outer Rino Dose rate (mRem/91 davs) 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 2011 14.8 14.3 2012 16.2 15.5 2013 14.4 14.0 2014 13.5 12.9 2015 14.8 14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.
The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.
7
 
4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015.
Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples.
Ambient Radiation (TLD's)
Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.
distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively). The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).
Year                 Inner Rin~q            Outer Rino Dose rate (mRem/91 davs) 1999                   15.1                   14.3 2000                   15.1                   14.5 2001                   14.3                   13.7 2002                   15.9                   14.8 2003                   15.6                   15.0 2004                   16.0                   15.4 2005                   15.6                   15.2 2006                   16.5                   15.6 2007                   16.1                   15.1 2008                   15.2                   14.6 2009                   14.9                   14.4 2010                   14.7                   14.3 2011                   14.8                   14.3 2012                   16.2                   15.5 2013                   14.4                   14.0 2014                   13.5                   12.9 2015                   14.8                   14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates, Inner vs. Outer Ring locations 8
Average quarterly dose rates, Inner vs. Outer Ring locations 8
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at both indicator and control locations (0.030 and 0.028 pCi/m 3 ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below. Year Indicators Control Concentration (QCi/m 3) 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 2011 0.029 0.027 2012 0.032 0.031 2013 0.029 0.032 2014 0.027 0.028 2015 0.030 0.028 Average annual gross beta concentrations in airborne particulates.
 
Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015. Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at 3
Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.070 pCilm 3 for the indicator locations and 0.066 pCilm 3 for the control locations.
both indicator and control locations (0.030 and 0.028 pCi/m ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below.
All other gamma-emitting isotopes were below their respective LLD limits. Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples. 9 River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.
Year             Indicators           Control 3
Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1999 2.2 2008 2.1 2000 2.5 2009 2.3 2001 2.5 2010 2.9 2002 2.9 2011 2.2 2003 3.0 2012 2.4 2004 2.7 2013 2.6 2005 2.8 2014 2.8 2006 2.1 2015 2.3 2007 2.8 Average annual concentrations; Gross beta in drinking water. Well Water At the four indicator and control locations, tritium was below the detection limit for all samples. Gamma isotopic results were also below detection limits. The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.
Concentration (QCi/m   )
Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available.
1999                 0.023               0.025 2000                 0.027               0.026 2001                 0.027               0.026 2002                 0.028               0.028 2003                 0.027               0.027 2004                 0.024               0.024 2005                 0.025               0.025 2006                 0.024               0.025 2007                 0.027               0.028 2008                 0.028               0.029 2009                 0.029               0.030 2010                 0.026               0.026 2011                 0.029               0.027 2012                 0.032               0.031 2013                 0.029               0.032 2014                 0.027               0.028 2015                 0.030               0.028 Average annual gross beta concentrations in airborne particulates.
With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.
Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015.
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 AI-Salih, 1955) was detected in all samples, 3                                          3 with an average activity of 0.070 pCilm for the indicator locations and 0.066 pCilm for the control locations. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples.
9
 
River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.
Year             Gross Beta (pCi/L)                   Year             Gross Beta (pCi/L) 1999                     2.2                         2008                     2.1 2000                     2.5                         2009                     2.3 2001                     2.5                         2010                     2.9 2002                     2.9                         2011                     2.2 2003                     3.0                         2012                     2.4 2004                     2.7                         2013                     2.6 2005                     2.8                         2014                     2.8 2006                     2.1                         2015                     2.3 2007                     2.8 Average annual concentrations; Gross beta in drinking water.
Well Water At the four indicator and control locations, tritium was below the detection limit for all samples.
Gamma isotopic results were also below detection limits.
The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.
Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.
A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.
A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.
Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September.
Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September. Flesh was separated from the bones and analyzed by gamma spectroscopy. Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits.
Flesh was separated from the bones and analyzed by gamma spectroscopy.
There was no indication of a plant effect.
Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits. There was no indication of a plant effect. 10 Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy.
10
All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect. Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes.
 
Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition.
Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy. All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect.
Naturally-occurring beryllium-?
Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition. Naturally-occurring beryllium-? and potassium-40 were also detected. There was no indication of a plant effect.
and potassium-40 were also detected.
Groundwater Monitoring Program (On-site monitoring wells)
There was no indication of a plant effect. Groundwater Monitoring Program (On-site monitoring wells) Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite. See Appendix E for full Groundwater monitoring well results and discussion.
Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite.
Gamma isotopic measurements were below detection limits. Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.
See Appendix E for full Groundwater monitoring well results and discussion.
Gamma isotopic measurements were below detection limits.
Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.
Storm Water Run-off (on-site)
Storm Water Run-off (on-site)
One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015. ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations.
One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015.
Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected.
ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations. Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected. Neutron dosimetry uses the different responses from two lithium 6      10 borate TLDs, one depleted of Li and 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive). The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016.
Neutron dosimetry uses the different responses from two lithium borate TLDs, one depleted of 6 Li and 10 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive).
11
The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016. 11 5.0 FIGURES AND TABLES 12 Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant. Collection Location Type and Medium No. Codes (and Type) a Frequency b REMP Ambient radiation(TLDs) 40 M-01A-M-14A, M-018-M-168 C/Q M-01 S -M-06S, M-01 C -M-04C ISFSI Ambient radiation (TLDs) 20 ISFSI-1 to ISFSI-16, C/Q Neutron Control A, 8, C, D C/Q 13 1-01 to 1-13 C/Q Airborne Particulates 5 M-1 (C), M-2, M-3, M-4, M-5 crw Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 crw Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year Surface water 2 M-S(C), M-9 Gf\N Drinking water M-14 Gf\N Well water 4 M-11, M-12, M-55, M-43(C) GIQ Fish 2 M-S(C), M-9 G/SA (two species, edible portion) Periphyton or invertebrates 2 M-S(C), M-9 G/SA Shoreline sediment 3 M-S(C), M-9, M-15 G/SA a Location codes are defined in Table 5.2. 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.
5.0 FIGURES AND TABLES 12
 
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.
Collection   Analysis Location                           Type and    Type and Medium                                   No.               Codes (and Type)     a                 Frequency   b Frequency  c REMP Ambient radiation(TLDs)                 40     M-01A- M-14A, M-018- M-168                             C/Q       Ambient gamma M-01 S - M-06S, M-01 C - M-04C ISFSI Ambient radiation (TLDs)               20   ISFSI-1 to ISFSI-16,                                     C/Q       Neutron Dose Neutron Control A, 8, C, D                               C/Q 13   1-01 to 1-13                                             C/Q       Ambient Gamma Airborne Particulates                         5     M-1 (C), M-2, M-3, M-4, M-5                             crw       G8, GS (QC of each location)
Airborne Iodine                               5     M-1(C), M-2, M-3, M-4, M-5                             crw       1-131 Pasture grass, Vegetation       d             3     M-41, M-42, M-43(C)                                   3x/year     GS Surface water                                 2     M-S(C), M-9                                             Gf\N     GS(MC), H-3(QC)
Drinking water                                       M-14                                                   Gf\N     G8(MC), I-131(MC)
GS (MC), H-3 (QC)
Well water                                     4     M-11, M-12, M-55, M-43(C)                               GIQ       H-3, GS Fish                                           2     M-S(C), M-9                                           G/SA       GS (two species, edible portion)
Periphyton or invertebrates                   2     M-S(C), M-9                                           G/SA       GS Shoreline sediment                             3     M-S(C), M-9, M-15                                     G/SA       GS a Location codes are defined in Table 5.2. 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.
c Analysis type is coded as follows: GB =gross beta, GS =gamma spectroscopy, H-3 =tritium, 1-131 = iodine-131.
c Analysis type is coded as follows: 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.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Pasture grass and vegetation collections added to supplement dairy sampling.
d Pasture grass and vegetation collections added to supplement dairy sampling.
13 Analysis Type and Frequency c Ambient gamma Neutron Dose Ambient Gamma G8, GS (QC of each location) 1-131 GS GS(MC), H-3(QC) G8(MC), I-131(MC)
13
GS (MC), H-3 (QC) H-3, GS GS GS GS Table 5.2. Sampling locations, Monticello Nuclear Generating Plant. Distance and Direction Code Type a Collection Site Sample Type b from Reactor M-1 c Air Station M-1 AP,AI 11.0 mi@ 307"/NW M-2 Air Station M-2 AP,AI 0.8 mi@ 140&deg;/SE M-3 Air Station M-3 AP,AI 0.6 mi@ 104&deg;/ESE M-4 Air Station M-4 AP,AI 0.8 mi@ 147"/SSE M-5 Air Station M-5 AP,AI 2.6 mi@ 134&deg;/SE M-8 c Upstream of Plant Intake SW, SS, BO, F < 1 000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1 000' downstream M-11 City of Monticello ww 3.3 mi@ 127"/SE M-12 Plant Well #11 ww 0.26 mi@ 252&deg;/WSW M-14 City of Minneapolis ow 37.0 mi@ 132&deg;/SE M-15 Montissippi Park ss 1.27 mi@ 114&deg;/ESE M-27 Highest 0/Q garden 1.15 mi@ 148&deg;/SSE M-41 Training Center VE 0.8 mi@ 151&deg;/SSE M-42 Biology Station Road VE 0.6 mi@ 134&deg;/SE M-43 c lmholte Farm VE,WW 12.3 mi@ 313&deg;/NW M-55 Hasbrouck Residence ww 1.60 mi@ 255&deg;/WSW 14 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant. Distance and Code Type* Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi@ 353&deg;/N M-02A Sherburne Ave. So. TLD 0.79 mi@ 23&deg;/NNE M-03A Sherburne Ave. So. TLD 1.29 mi@ 56&deg;/NE M-04A Biology Station Road TLD 0.5 mi@ 92&deg;/E M-05A Biology Station Road TLD 0.48 mi @ 122&deg; /ESE M-06A Biology Station Road TLD 0.54 mi@ 138&deg;/SE M-07A County Road 75 TLD 0.47 mi@ 158&deg;/SSE M-08A County Road 75 TLD 0.45 mi@ 175&deg;/S M-09A County Road 75 TLD 0.38 mi@ 206&deg;/SSW M-10A County Road 75 J'LD 0.38 mi@ 224&deg;/SW M-11A County Road 75 TLD 0.4 mi@ 237"/WSW M-12A County Road 75 TLD 0.5 mi@ 262&deg;/W M-13A North Boundary Road TLD 0.89 mi@ 322&deg;/NW M-14A North Boundary Road TLD 0.78 mi@ 335&deg;/NNW Approximately 4 to 5 miles Distant from the Plant M-01B 11?'h Street TLD 4.65 mi@ 01&deg;/N M-02B County Road 11 TLD 4.4 mi@ 18"/NNE M-03B County Road 73 & 81 TLD 4.3 mi@ 51&deg;/NE M-04B County Road 73 (196th St.) TLO 4.2 mi@ 67"/ENE M-05B City of Big Lake TLD 4.3 mi@ 89&deg;/E M-06B County Road 14 and 1 96th St. TLD 4.3 mi@ 117"/ESE M-07B Monticello Industrial Drive TLD 4.3 mi@ 136&deg;/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi@ 162&deg;/SSE M-09B Weinand Farm TLD 4.7 mi@ 178&deg;/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi@ 204&deg;/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi@ 228&deg;/SW M-12B Lake Maria State Park TLD 4.2 mi@ 254&deg;/WSW M-13B Bridgewater Station TLD 4.1 mi@ 270&deg;/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi@ 289&deg;/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi@ 309&deg;/NW M-16B Sand Plain Research Farm TLD 4.4 mi@ 341&deg;/NNW 15 Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant. Code Type a Collection Site Special Interest Locations M-01S M-02S M-03S M-04S M-OSS M-06S M-01C c M-02C c M-03C c M-04C c ISFSI TLD Locations ISFSI-1 ISFSI-2 ISFSI-3 ISFSI-4 ISFSI-5 ISFSI-6 ISFSI-7 ISFSI-8 ISFSI-9 ISFSI-10 ISFSI-11 ISFSI-12 ISFSI-13 ISFSI-14 ISFSI-15 ISFSI-16 Neutron Control A Neutron Control B Neutron Control C Neutron Control D c c c c Osowski Fun Market Krone Residence Big Oaks Park Pinewood School Rivercrest Christian Academy Monticello Public Works Kirchenbauer Farm County Roads 4 and 15 County Rd 19 and Jason Ave. Maple Lake Water Tower ISFSI-1 (neutron) and 1-01 (gamma) ISFSI-2 (neutron) and 1-02 (gamma) ISFSI-3 (neutron) and 1-03 (gamma) ISFSI-4 (neutron) and 1-04 (gamma) ISFSI-5 (neutron) and 1-05 (gamma) ISFSI-6 (neutron) and 1-06 (gamma) ISFSI-7 (neutron) and 1-07 (gamma) ISFSI-8 (neutron) and 1-08 (gamma) ISFSI-9 (neutron) and 1-09 (gamma) ISFSI-10 (neutron) and 1-10 (gamma) ISFSI-11 (neutron) and 1-11 (gamma) ISFSI-12 (neutron) and 1-12 (gamma) ISFSI-13 (neutron) and 1-13 (gamma) ISFSI-14 (neutron)
 
ISFSI-15 (neutron)
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
ISFSI-16 (neutron) a "C" denotes control location.
Distance and Direction Code        Type a      Collection Site                          Sample Type b from Reactor M-1           c          Air Station M-1                          AP,AI              11.0 mi@ 307"/NW M-2                      Air Station M-2                          AP,AI                  0.8 mi@ 140&deg;/SE M-3                      Air Station M-3                           AP,AI                0.6 mi@ 104&deg;/ESE M-4                      Air Station M-4                          AP,AI                0.8 mi@ 147"/SSE M-5                      Air Station M-5                          AP,AI                 2.6 mi@ 134&deg;/SE M-8            c          Upstream of Plant Intake                  SW, SS, BO, F          < 1000' upstream M-9                      Downstream of Plant Discharge            SW, SS, BO, F      < 1000' downstream M-11                      City of Monticello                        ww                    3.3 mi@ 127"/SE M-12                      Plant Well #11                            ww                0.26 mi@ 252&deg;/WSW M-14                      City of Minneapolis                      ow                  37.0 mi@ 132&deg;/SE M-15                    Montissippi Park                          ss                1.27 mi@ 114&deg;/ESE M-27                    Highest 0/Q garden                                            1.15 mi@ 148&deg;/SSE M-41                      Training Center                          VE                  0.8 mi@ 151&deg;/SSE M-42                      Biology Station Road                      VE                    0.6 mi@ 134&deg;/SE M-43          c          lmholte Farm                            VE,WW              12.3 mi@ 313&deg;/NW M-55                      Hasbrouck Residence                      ww                1.60 mi@ 255&deg;/WSW 14
All other locations are indicators.
 
b Sample Codes: AP Airborne particulates AI Airborne Iodine BS Bottom (river) sediments BO Bottom organisms OW Drinking Water Distance and Sample Typeb Direction from Reactor TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD F sw ss TLD VE ww 0.66 mi@ 241WvSW 0.5 mi@ 220&deg;/SW 1.53 mi@ 103&deg;/ESE 2.3 mi@ 131 &deg;/SE 3.0 mi@ 118&deg;/ESE 2.6 mi@ 134&deg;/SE 11.5 mi@ 323&deg;/NW 11.2 mi @4r/NE 11.6 mi@ 130&deg;/SE 10.3 mi@ 226&deg;/ SW NE corner of ISFSI North side of ISFSI, center NW corner of ISFSI West side of ISFSI, middle West side of ISFSI, at center of array SW corner of ISFSI South side of ISFSI, center SE corner of ISFSI East side of ISFSI, at center of array East side of ISFSI, middle OCA fence south, on exit road OCA fence middle, on exit road OCA fence north, on exit road Posted with TLD M12A Posted with TLD M1 OA Posted with TLD M02S Posted with TLD M03C Posted with TLD M04C Posted with TLD M02C Posted with TLD M01 C Fish River Water Shoreline Sediments Thermoluminescent Dosimeter Vegetation I vegetables Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields. 16 Table 5.3 Missed Collections and Analyses.
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
Distance and Code          Type*        Collection Site                        Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A                        Sherburne Ave. So.                    TLD                    0.75 mi@ 353&deg;/N M-02A                        Sherburne Ave. So.                     TLD                  0.79 mi@ 23&deg;/NNE M-03A                        Sherburne Ave. So.                     TLD                   1.29 mi@ 56&deg;/NE M-04A                        Biology Station Road                  TLD                       0.5 mi@ 92&deg;/E M-05A                        Biology Station Road                  TLD               0.48 mi @ 122&deg; /ESE M-06A                        Biology Station Road                   TLD                 0.54 mi@ 138&deg;/SE M-07A                        County Road 75                        TLD               0.47 mi@ 158&deg;/SSE M-08A                        County Road 75                        TLD                   0.45 mi@ 175&deg;/S M-09A                        County Road 75                         TLD               0.38 mi@ 206&deg;/SSW M-10A                        County Road 75                         J'LD                0.38 mi@ 224&deg;/SW M-11A                        County Road 75                         TLD               0.4 mi@ 237"/WSW M-12A                        County Road 75                         TLD                    0.5 mi@ 262&deg;/W M-13A                        North Boundary Road                   TLD                 0.89 mi@ 322&deg;/NW M-14A                        North Boundary Road                   TLD               0.78 mi@ 335&deg;/NNW Approximately 4 to 5 miles Distant from the Plant M-01B                       11?'h Street                           TLD                     4.65 mi@ 01&deg;/N M-02B                       County Road 11                         TLD                   4.4 mi@ 18"/NNE M-03B                       County Road 73 & 81                   TLD                     4.3 mi@ 51&deg;/NE M-04B                       County Road 73 (196th St.)             TLO                   4.2 mi@ 67"/ENE M-05B                       City of Big Lake                       TLD                       4.3 mi@ 89&deg;/E M-06B                       County Road 14 and 196th St.           TLD                 4.3 mi@ 117"/ESE M-07B                       Monticello Industrial Drive           TLD                   4.3 mi@ 136&deg;/SE M-08B                       Residence, Hwy 25 & Davidson Ave.     TLD                 4.6 mi@ 162&deg;/SSE M-09B                       Weinand Farm                           TLD                     4.7 mi@ 178&deg;/S M-10B                       Reisewitz Farm, Acacia Ave.           TLD                 4.2 mi@ 204&deg;/SSW M-11B                       Vanlith Farm, 97th Ave.               TLD                   4.0 mi@ 228&deg;/SW M-12B                       Lake Maria State Park                 TLD               4.2 mi@ 254&deg;/WSW M-13B                       Bridgewater Station                   TLD                     4.1 mi@ 270&deg;/W M-14B                       Anderson Residence, Cty Rd. 111       TLD               4.3 mi@ 289&deg;/WNW M-15B                       Red Oak Wild Bird Farm                 TLD                   4.3 mi@ 309&deg;/NW M-16B                       Sand Plain Research Farm               TLD                 4.4 mi@ 341&deg;/NNW 15
 
Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant.
Distance and Code             Type a         Collection Site                                 Sample Typeb            Direction from Reactor Special Interest Locations M-01S                             Osowski Fun Market                              TLD                          0.66 mi@ 241WvSW M-02S                             Krone Residence                                  TLD                              0.5 mi@ 220&deg;/SW M-03S                            Big Oaks Park                                    TLD                            1.53 mi@ 103&deg;/ESE M-04S                            Pinewood School                                  TLD                                2.3 mi@ 131 &deg;/SE M-OSS                            Rivercrest Christian Academy                    TLD                              3.0 mi@ 118&deg;/ESE M-06S                            Monticello Public Works                          TLD                               2.6 mi@ 134&deg;/SE M-01C                c          Kirchenbauer Farm                                TLD                            11.5 mi@ 323&deg;/NW M-02C                c          County Roads 4 and 15                           TLD                                11.2 mi @4r/NE M-03C                c          County Rd 19 and Jason Ave.                      TLD                              11.6 mi@ 130&deg;/SE M-04C                c           Maple Lake Water Tower                          TLD                            10.3 mi@ 226&deg;/ SW ISFSI TLD Locations ISFSI-1                        ISFSI-1 (neutron) and 1-01 (gamma)               TLD                              NE corner of ISFSI ISFSI-2                        ISFSI-2 (neutron) and 1-02 (gamma)               TLD                    North side of ISFSI, center ISFSI-3                        ISFSI-3 (neutron) and 1-03 (gamma)               TLD                            NW corner of ISFSI ISFSI-4                        ISFSI-4 (neutron) and 1-04 (gamma)               TLD                    West side of ISFSI, middle ISFSI-5                        ISFSI-5 (neutron) and 1-05 (gamma)               TLD        West side of ISFSI, at center of array ISFSI-6                        ISFSI-6 (neutron) and 1-06 (gamma)               TLD                            SW corner of ISFSI ISFSI-7                        ISFSI-7 (neutron) and 1-07 (gamma)               TLD                    South side of ISFSI, center ISFSI-8                        ISFSI-8 (neutron) and 1-08 (gamma)               TLD                              SE corner of ISFSI ISFSI-9                        ISFSI-9 (neutron) and 1-09 (gamma)               TLD        East side of ISFSI, at center of array ISFSI-10                        ISFSI-10 (neutron) and 1-10 (gamma)             TLD                      East side of ISFSI, middle ISFSI-11                        ISFSI-11 (neutron) and 1-11 (gamma)             TLD                OCA fence south, on exit road ISFSI-12                        ISFSI-12 (neutron) and 1-12 (gamma)             TLD              OCA fence middle, on exit road ISFSI-13                       ISFSI-13 (neutron) and 1-13 (gamma)             TLD                  OCA fence north, on exit road ISFSI-14                        ISFSI-14 (neutron)                               TLD                        Posted with TLD M12A ISFSI-15                       ISFSI-15 (neutron)                               TLD                        Posted with TLD M1 OA ISFSI-16                        ISFSI-16 (neutron)                              TLD                        Posted with TLD M02S Neutron Control A          c                                                      TLD                        Posted with TLD M03C Neutron Control B          c                                                      TLD                         Posted with TLD M04C Neutron Control C          c                                                      TLD                         Posted with TLD M02C Neutron Control D          c                                                      TLD                         Posted with TLD M01 C a  "C" denotes control location. All other locations are indicators.
b Sample Codes:            AP  Airborne particulates                                F      Fish AI  Airborne Iodine                                    sw      River Water BS  Bottom (river) sediments                            ss      Shoreline Sediments BO  Bottom organisms                                  TLD      Thermoluminescent Dosimeter OW  Drinking Water                                      VE      Vegetation I vegetables ww      Well Water c  Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.
16
 
Table 5.3 Missed Collections and Analyses.
All required samples were collected and analyzed as scheduled with the following exceptions:
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, 1-131 M-005 1/28/2015 Power loss at sample Power was reset station. sw Gamma M-008 January '15 Water frozen entire month; None no composite.
Collection               Reason for not Sample       Analysis     Location         Date or               conducting REMP           Plans for Preventing Type                                       Period                     as required                 Recurrence AP/AI     Beta, 1-131       M-005       1/28/2015             Power loss at sample           Power was reset station.
AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running due Replaced air sampler. to bad switch. sw Gamma M-008 February '15 Water frozen entire month; None no composite.  
sw         Gamma           M-008       January '15         Water frozen entire month;               None no composite.
*.c sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None APIA I Beta, 1-131 M-002 5/6/2015 Air sampler not running. Replaced air sampler. TLD Gamma M-06B 2nd Qtr '15 TLD missing in field. Replaced TLD APIA I Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped ResetGFCI sw Gamma M-008 12/30/15 Water frozen None 17 Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
AP/AI     Beta, 1-131       M-002         2/4/2015         Air sampler not running due     Replaced air sampler.
20 l -lnnerRing
to bad switch.
--a-Outer Ring 19 18 17 16 15 (/) >> 14 ro "0 0) (i E 13 I 0 I v v \ I/; v r--v 0 r....... 11---1 V; y-""' v 3-1\ \Y 12 11 10 0) 0 N C') """ li) CD 1'-co 0) 0 N (') """ li) 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 0 0 0 N N N N N N N N N N N N N N N N 18 Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
sw         Gamma           M-008       February '15       Water frozen entire month;               None no composite.
0.035 0.033 0.031 0.029 0.027 0.025 :&sect; 0.023 0 D. 0.021 0.019 0.017 0.015 I -Indicators (M-2, 3, 4, 5) -o--Controi(M-1) ly l/l\ /I \ \ \ v/ '\ f/ \ \ I \ /1 I / / \ l) )---1 v Ol Ol Ol I I 0 0 0 N 0 0 N N 0 0 N 1\ I;/ \ v ' I ' (') 0 0 N "<!" 0 0 N I{) (() 0 0 0 0 N N 19 D 0 N (() 0 0 N Ol 0 0 N v 0 0 N (') 0 N I I I I{) 0 N Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*
                                                                                          *.c sw         Gamma           M-008           3/4/15                   Water frozen                   None sw         Gamma           M-008         3/11/15                   Water frozen                   None APIA I     Beta, 1-131       M-002         5/6/2015           Air sampler not running.       Replaced air sampler.
TLD (Inner Ring, Gamma 56 General Area at Site Boundary) mRem/91 days) TLD (Outer Ring, Gamma 63 4-5 mi. distant) mRem/91 days) TLD (Special Gamma 24 Interest Areas) mRem/91 days) TLD (Control)
TLD       Gamma           M-06B       2nd Qtr '15           TLD missing in field.           Replaced TLD APIA I     Beta, 1-131       M-004         6/10/15                   GFCI tripped                 Reset GFCI AP/AI     Beta, 1-131       M-004       6/24/2015                   GFCI tripped               ResetGFCI sw         Gamma           M-008         12/30/15                   Water frozen                   None 17
Gamma 16 mRem/91 days) Airborne GB 256 Particulates (pCi/rn 3) GS 20 Be-7 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-141 Ce-144 Airborne Iodine 1-131 256 (pCi/m 3) Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) Docket No. 50-263 ------------------
 
Reporting Period January-December, 2015 Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean(F)" Mean (F)0 Mean (F)0 Routine Ran gee Locationd Rangec Rangec Results* Direct Radiation 3.0 14.8 (56/56) M-11A, County Rd 75, 17.1 (4/4) (See Control 0 ( 9.6-19.6) 0.4 mi @ 250&deg;/WSW (15.8-19.6) below.) 3.0 14.2 (63/63) M-148 16.6 (4/4) (See Control 0 ( 11.0-19.6) 4.5 mi@ 228&deg;/NW (14.7-19.6) below.) 3.0 14.7 (24/24) M-04S 16.4 (4/4) (See Control 0 ( 9.4-18.8) 2.3 mi@ 132&deg;/SE (14.4-17.6) below.) 3.0 None M-02C 17.5 (4/4) 15.3 (16/16) 0 11.2 mi@ 47"/NE (15.9-20.3) ( 11.8-20.3)
Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
Airborne Pathway 0.002 0.030 (204/204)
20                                                                   l -
M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 (0.007-0.088) 2.6 rni@ 134&deg;/SE (0.009-0.088)
                                                                              --a-lnnerRing Outer Ring 19 18 17 I 0 16
(0.008-0.062) 0.015 0.070 (16/16) M-5, Air Station 0.073 (4/4) 0.066 (4/4) 0 (0.049-0.087) 2.6 rni@ 134&deg;/SE (0.049-0.087)
                          ~    v     ~    v                                 I/;I~
(0.043-0.077) 0.0008 < LLD --< LLD 0 0.0008 < LLD --< LLD 0 0.0009 < LLD --< LLD 0 0.0019 < LLD --< LLD 0 0.0014 < LLD --< LLD 0 0.0013 < LLD --< LLD 0 0.0085 < LLD --< LLD 0 0.0010 < LLD --< LLD 0 0.0010 < LLD --< LLD 0 0.0026 < LLD --< LLD 0 0.0020 < LLD --< LLD 0 0.0046 < LLD --< LLD 0 0.03 < LLD --< LLD 0 20 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*
I y- v r-- 0 \    v                 r.......
River Water (pCi/L) H-3 8 GS 22 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce'-144 Drinking Water GB 12 (pCi/L) 1-131 12 H-3 4 GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Well Water H-3 16 (pCi/L) GS 16 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) *Docket No. ..;5;..;0-...;2;;.;6;..;3
v~
______ _ Reporting Period January-December,2015 Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean (F)0 Mean (F)" Mean (F)0 Routine Range* Locationd Range* Range* Results* Waterborne Pathway 500 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 15 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 15 < LLD --< LLD 0 39 < LLD --< LLD 0 1.0 2.3 (12112) M-14, Minneapolis 2.3 (12/12) None 0 (1.2-3.5) 37.0 mi.@ 132&deg; /SE (1.2-3.5) 1.0 < LLD --None 0 500 < LLD --None 0 10 < LLD --None 0 30 < LLD --None 0 10 < LLD --None 0 10 < LLD --None 0 30 < LLD --None 0 15 < LLD --None 0 10 < LLD --None 0 10 < LLD --None 0 15 < LLD --None 0 35 < LLD --None 0 500 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 15 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 15 < LLD --< LLD 0 49 < LLD --< LLD 0 21 Table 5.4 Radiological Environmental Monitoring Program Summarw Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses" Invertebrates GS 4 (pCilg wet) Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-144 Shoreline GS 6 Sediments Be-7 (pCi/g dry) K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Docket No. ...;5...;;0...:-2;;.;6...;;3
15  11---1
___ ,_. __ _ Reporting Period January-December, 2 015 Wright, Minnesota ( County, State ) Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLD b Mean (F)' Mean (F)' Mean (F)' Routine Range' Locationd Range' Range' Results" Waterborne Pathway 1.49 < LLD --< LLD 0 1.91 < LLD --< LLD 0 0.088 < LLD --< LLD 0 0.24 < LLD --< LLD 0 0.145 < LLD --< LLD 0 0.085 < LLD --< LLD 0 0.18 < LLD --< LLD 0 0.23 < LLD --< LLD 0 0.217 < LLD --< LLD 0 0.55 < LLD --< LLD 0 0.076 < LLD --< LLD 0 0.085 < LLD --< LLD 0 1.35 < LLD --< LLD 0 0.39 < LLD --< LLD 0 0.33 < LLD --< LLD 0 -0.10 10.24 (4/4) M-08, Upstream 11.55 (2/2) 11.55 (2/2) 0 (9.49-1 0.54) < 1000' of discharge (11.53-11.58)
                  ~\YV;
(11.53-11.58) 0.021 < LLD --< LLD 0 0.076 < LLD --< LLD 0 0.026 < LLD --< LLD 0 0.017 < LLD --< LLD 0 0.044 < LLD --< LLD 0 0.051 < LLD --< LLD 0 0.052 < LLD --< LLD 0 0.041 < LLD --< LLD 0 0.13 < LLD --< LLD 0 0.017 < LLD --< LLD 0 0.021 0.029 (2/4) M-09, Downstream
                                                                      ~
-< LLD 0 (0.024-0.034)
(/)
< 1000' of discharge
ro 14
-0.21 < LLD --< LLD 0 0.13 < LLD --< LLD 0 22 Table 5.4 Radiological Environmental Monitoring Program Summary Monticello Nuclear Generating Plant Docket No. 50-263 Name of Facility Location of Facility Wright, Minnesota
          ~
--,---=-----:---
                                                        ""' ~ 3-1\         ~
Reporting Period January-December, 2015 ( County, State ) Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)" (Units) Analyses*
                                                                                      ~~
Ran gee Locationd Ran gee Rangec Ingestion Pathway Vegetation GS 9 (Pasture Grass, Mn-54 0.014 < LLD --< LlD Weeds, Leaves) Fe-59 0.033 < LLD --< LLD Co-58 0.014 < LLD --< LLD (pCi/gwet)
  "0
Co-60 0.019 < LLD --< LLD Zn-65 0.029 < LLD --< LLD Nb-95 0.020 < LLD --< LLD 1-131 0.043 < LLD --< LLD Cs-134 0.015 < LLD -< LLD Cs-137 0.014 < LLD --< LLD Fish GS 8 (pCi/g wet) K-40 0.10 3.39 (4/4) M-09, Downstream 3.39 (4/4) 3.31 (4/4) -(3.08-3.71)
  ~
< 1000' of discharge (3.08-3.71)
0)
(2.56-3.65)
(i E  13 12 11 10
Mn-54 0.025 < LLD --< LLD Fe-59 0.056 < LLD --< LLD Co-58 0.025 < LLD --< LLD Co-60 0.025 < LLD --< LLD Zn-65 0.070 < LLD --< LLD Zr-Nb-95 0.031 < LLD --< LLD Cs-134 0.025 < LLD --< LLD Cs-137 0.020 < LLD --< LLD Ba-La-140 0.122 < LLD --< LLD Ce-144 0.141 < LLD --< LLD
: 0)     0   ~  N   C')       li)   CD   1'-   co       0) 0 ~    N   (')           li) 0)
* GB =gross beta, GS =gamma scan. b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample. c 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:
0) 0 0   0 0 0 0
(1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
0 0     """
0 0
0 0
0 0
0 0
0 0
0 0 0N 0   ~
0
                                                                                    ~
0       0"""  0N
          ~      N   N   N   N     N   N     N     N     N         N     N   N   N       N 18
 
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
                                                                          -  11- - Indicators (M-2, 3, 4, 5) 0.035 I  - o - - Controi(M-1)
I 0.033 0.031 ly ~
                                                                                              \
0.029                                                         l/l\            /I \        \
I I
                                                              ~    v/                                      \
                                                                        '\~v/ f/I                  \
                          /1 ~                            I    /
                                                                                                        \
                                                                                                          \  ~
0.027 v
0.025 l)
I
                    )---1 1\\ v ' I;/          I I                                  '
0.023
:&sect; 0
D.
0.021 0.019 0.017 0.015 Ol    0        N    (')  "<!"  I{)   (()     I'-  (()  Ol  0                      (')            I{)
Ol     0     0 0
0    0     0     0     0       D    0   0   ~                      ~              ~
Ol    0         0   0     0     0     0       0   0   0   0                      0               0
            ~      N    N  N   N    N    N    N        N    N    N    N                     N               N 19
 
Table 5.4     Radiological Environmental Monitoring Program Summary Name of Facility         Monticello Nuclear Generating Plant                    Docket No.        50-263 Location of Facility    Wright, Minnesota                                      Reporting Period ------------------
January-December, 2015
( County, State )
Indicator                  Location with Highest                  Control  Number Sample            Type and                    Locations                      Annual Mean                      Locations    Non-Type              Number of        LLDb      Mean(F)"                                        Mean (F) 0      Mean (F) 0  Routine (Units)           Analyses*                    Ran gee              Locationd                Rangec            Rangec    Results*
Direct Radiation TLD (Inner Ring, Gamma             56    3.0    14.8 (56/56)     M-11A, County Rd 75,            17.1 (4/4)     (See Control    0 General Area at                                    ( 9.6-19.6)      0.4 mi @ 250&deg;/WSW            (15.8-19.6)        below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma            63    3.0      14.2 (63/63)              M-148                  16.6 (4/4)    (See Control    0 4-5 mi. distant)                                  ( 11.0-19.6)      4.5 mi@ 228&deg;/NW              (14.7-19.6)        below.)
mRem/91 days)
TLD (Special      Gamma          24    3.0      14.7 (24/24)              M-04S                  16.4 (4/4)    (See Control    0 Interest Areas)                                    ( 9.4-18.8)        2.3 mi@ 132&deg;/SE            (14.4-17.6)        below.)
mRem/91 days)
TLD (Control)     Gamma          16    3.0         None                  M-02C                  17.5 (4/4)     15.3 (16/16)    0 mRem/91 days)                                                         11.2 mi@ 47"/NE            (15.9-20.3)     ( 11.8-20.3)
Airborne Pathway Airborne        GB            256  0.002  0.030 (204/204)       M-5, Air Station          0.031 (51/51)   0.028 (52/52)    0 Particulates                                  (0.007-0.088)       2.6 rni@ 134&deg;/SE          (0.009-0.088)   (0.008-0.062)
(pCi/rn 3)
GS            20 Be-7          0.015    0.070 (16/16)         M-5, Air Station          0.073 (4/4)       0.066 (4/4)    0 (0.049-0.087)       2.6 rni@ 134&deg;/SE           (0.049-0.087)   (0.043-0.077)
Mn-54        0.0008          < LLD                    -                      -              < LLD      0 Co-58          0.0008        < LLD                    -                       -               < LLD      0 Co-60          0.0009        < LLD                    -                      -               < LLD      0 Zn-65          0.0019        < LLD                    -                      -              < LLD      0 Zr-Nb-95      0.0014        < LLD                    -                      -               < LLD      0 Ru-103        0.0013        < LLD                    -                      -              < LLD      0 Ru-106        0.0085        < LLD                    -                      -              < LLD      0 Cs-134        0.0010        < LLD                    -                       -              < LLD      0 Cs-137        0.0010        < LLD                    -                      -              < LLD      0 Ba-La-140    0.0026        < LLD                    -                      -              < LLD      0 Ce-141        0.0020        < LLD                    -                      -              < LLD      0 Ce-144        0.0046        < LLD                   -                       -               < LLD       0 Airborne Iodine          1-131    256    0.03        < LLD                   -                       -               < LLD       0 3
(pCi/m )
20
 
Table 5.4    Radiological Environmental Monitoring Program Summary Name of Facility        Monticello Nuclear Generating Plant                    *Docket No.      ..;5;..;0-...;2;;.;6;..;3_ _ _ _ _ __
Location of Facility    Wright, Minnesota                                      Reporting Period    January-December,2015
( County, State )
Indicator                  Location with Highest                            Control      Number Sample             Type and                 Locations                        Annual Mean                              Locations          Non-Type             Number of     LLDb      Mean (F) 0                                      Mean (F)"                Mean (F) 0        Routine (Units)           Analyses*                  Range*                Locationd                Range*                      Range*        Results*
Waterborne Pathway River Water (pCi/L)       H-3           8   500          < LLD                    -                      -                          < LLD          0 GS           22 Mn-54         10        < LLD                      -                      -                          < LLD          0 Fe-59         30        < LLD                      -                      -                          < LLD          0 Co-58         10        < LLD                      -                      -                          < LLD          0 Co-60         10        < LLD                      -                      -                          < LLD          0 Zn-65         30          < LLD                      -                       -                          < LLD          0 Zr-Nb-95       15        < LLD                      -                      -                          < LLD          0 Cs-134         10        < LLD                      -                      -                          < LLD          0 Cs-137         10        < LLD                      -                      -                          < LLD          0 Ba-La-140     15        < LLD                      -                      -                          < LLD          0 Ce'-144       39        < LLD                      -                      -                          < LLD          0 Drinking Water     GB           12   1.0      2.3 (12112)         M-14, Minneapolis            2.3 (12/12)                      None          0 (pCi/L)                                    (1.2-3.5)        37.0 mi.@ 132&deg; /SE            (1.2-3.5) 1-131        12  1.0        < LLD                      -                       -                           None          0 H-3            4  500        < LLD                      -                       -                           None          0 GS           12 Mn-54         10        < LLD                      -                      -                            None          0 Fe-59         30          < LLD                      -                      -                            None          0 Co-58         10        < LLD                      -                      -                            None          0 Co-60         10        < 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         35        < LLD                      -                      -                            None          0 Well Water        H-3          16  500          < LLD                      -                      -                          < LLD          0 (pCi/L)        GS            16 Mn-54          10        < LLD                      -                       -                           < LLD          0 Fe-59        30          < LLD                     -                       -                           < LLD         0 Co-58          10         < LLD                     -                       -                           < LLD         0 Co-60          10        < LLD                     -                       -                           < LLD         0 Zn-65          30          < LLD                     -                       -                         < LLD           0 Zr-Nb-95      15        < LLD                     -                       -                         < LLD           0 Cs-134        10        < LLD                     -                       -                           < LLD         0 Cs-137        10         < LLD                     -                       -                           < LLD         0 Ba-La-140      15         < LLD                     -                       -                           < LLD         0 Ce-144        49          < LLD                     -                       -                         < LLD           0 21
 
Table 5.4    Radiological Environmental Monitoring Program Summarw Name of Facility        Monticello Nuclear Generating Plant                  Docket No.      ...;5...;;0...:-2;;.;6...;;3_ _ _,_._ __
Location of Facility    Wright, Minnesota                                    Reporting Period    January-December, 2 015
( County, State )
Indicator              Location with Highest                              Control        Number Sample            Type and                  Locations                    Annual Mean                                Locations            Non-Type              Number of    LLD   b    Mean (F)'                                    Mean (F)'                  Mean (F)'            Routine (Units)          Analyses"                  Range'            Locationd                Range'                        Range'        Results" Waterborne Pathway Invertebrates      GS          4 (pCilg wet)          Be-7            1.49        < LLD                 -                       -                             < LLD           0 K-40            1.91        < LLD                 -                       -                             < LLD           0 Mn-54        0.088        < LLD                 -                       -                             < LLD           0 Fe-59          0.24        < LLD                 -                       -                             < LLD           0 Co-58        0.145        < LLD                 -                       -                             < LLD           0 Co-60        0.085        < LLD                 -                       -                             < LLD           0 Zn-65          0.18        < LLD                 -                       -                             < LLD           0 Zr-Nb-95        0.23        < LLD                 -                       -                             < LLD           0 Ru-103        0.217        < LLD                 -                       -                             < LLD           0 Ru-106          0.55        < LLD                 -                       -                             < LLD           0 Cs-134        0.076        < LLD                 -                       -                             < LLD           0 Cs-137        0.085        < LLD                 -                       -                             < LLD           0 Ba-La-140      1.35        < LLD                 -                       -                             < LLD           0 Ce-144          0.39        < LLD                 -                       -                             < LLD           0 Shoreline        GS          6 Sediments            Be-7            0.33        < LLD                 -                       -                             < LLD           0 (pCi/g dry)                                                            -
K-40           0.10    10.24 (4/4)      M-08, Upstream            11.55 (2/2)                11.55 (2/2)            0 (9.49-1 0.54)    < 1000' of discharge      (11.53-11.58)          (11.53-11.58)
Mn-54        0.021        < LLD                -                       -                             < LLD          0 Fe-59        0.076        < LLD                -                       -                             < LLD          0 Co-58        0.026        < LLD                -                       -                             < LLD          0 Co-60         0.017        < LLD                -                       -                             < LLD          0 Zn-65        0.044        < LLD                -                       -                             < LLD          0 Nb-95        0.051        < LLD                -                       -                             < LLD          0 Zr-95        0.052        < LLD                -                      -                             < LLD          0 Ru-103        0.041        < LLD                -                      -                            < LLD          0 Ru-106          0.13        < LLD                -                      -                            < LLD          0 Cs-134        0.017        < LLD                -                      -                            < LLD          0 Cs-137        0.021      0.029 (2/4)      M-09, Downstream                -                            < LLD          0 (0.024-0.034)     < 1000' of discharge            -
Ba-La-140      0.21        < LLD                 -                       -                             < LLD           0 Ce-144          0.13        < LLD                 -                       -                             < LLD           0 22
 
Table 5.4      Radiological Environmental Monitoring Program Summary Name of Facility        Monticello Nuclear Generating Plant                      Docket No.         50-263
                                                                                                                  --,---=-----:---
Location of Facility    Wright, Minnesota                                        Reporting Period    January-December, 2015
( County, State )
Indicator                  Location with Highest                    Control    Number Sample            Type and                    Locations                      Annual Mean                          Locations    Non-Type              Number of      LLDb        Mean (F) 0                                     Mean (F) 0         Mean (F)"  Routine (Units)          Analyses*                    Ran gee              Locationd                Ran gee            Rangec    Results*
Ingestion Pathway Vegetation        GS          9 (Pasture Grass,          Mn-54          0.014        < LLD                   -                         -               < LlD        0 Weeds, Leaves)            Fe-59          0.033        < LLD                   -                         -               < LLD       0 Co-58          0.014        < LLD                   -                         -               < LLD       0 (pCi/gwet)           Co-60          0.019        < LLD                    -                        -                < LLD        0 Zn-65          0.029        < LLD                    -                        -               < LLD        0 Nb-95          0.020        < LLD                   -                         -               < LLD       0 1-131          0.043        < LLD                   -                         -               < LLD       0 Cs-134          0.015        < LLD                                             -               < LLD       0 Cs-137          0.014        < LLD                   -                         -               < LLD       0 Fish          GS          8 (pCi/g wet)          K-40          0.10        3.39 (4/4)        M-09, Downstream              3.39 (4/4)          3.31 (4/4)    0
                                  -                 (3.08-3.71)      < 1000' of discharge          (3.08-3.71)        (2.56-3.65)
Mn-54        0.025          < LLD                   -                         -               < LLD       0 Fe-59        0.056          < LLD                   -                         -               < LLD       0 Co-58        0.025          < LLD                    -                        -                < LLD        0 Co-60        0.025          < LLD                    -                         -               < LLD       0 Zn-65        0.070          < LLD                    -                        -                < LLD        0 Zr-Nb-95      0.031          < LLD                   -                         -               < LLD       0 Cs-134        0.025          < LLD                   -                         -               < LLD       0 Cs-137        0.020        < LLD                    -                        -               < LLD        0 Ba-La-140      0.122        < LLD                    -                         -               < LLD        0 Ce-144        0.141        < LLD                    -                         -               < LLD        0
* GB =gross beta, GS =gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c 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: (1) by name, and/or station code 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.
* 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.
23 Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 
23


==6.0 REFERENCES==
==6.0 REFERENCES==
CITED Arnold, J. R. and H. A. AI-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, 276.
ATI Environmental, Inc., Midwest Laboratory.
____2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015.
_ _ _---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 2000 through 2015.
____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 1983 through 1999.
____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
_ _ _..,-1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
_ _ _..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
_ _ _ _.2009.            Quality Assurance Program Manual, Rev. 3, 14 November 2012.
_ _ _ _2009.            Quality Control Procedures Manual, Rev. 2, 08 July 2009.
_ _ _ _.2009.            Quality Control Program, Rev. 2, 12 November 2009.
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, Illinois, 369-382 ..
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46.
Northern States Power Company.
_ _ _..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.
____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.
24


CITED Arnold, J. R. and H. A. AI-Salih.
==6.0 REFERENCES==
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, 276. ATI Environmental, Inc., Midwest Laboratory.
CITED (continued)
____ 2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015. ___ ---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015. ____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Scannell, M. J., J. Giard, J. Raimondi. 2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 1983 through 1999. ____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1983 through 1999. ___ ..,-1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation)
U.S. Environmental Protection Agency.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1978 through 1982. ___ ..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation)
----=1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1978 through 1982. ____ .2009. Quality Assurance Program Manual, Rev. 3, 14 November 2012. ____ 2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009. ____ .2009. Quality Control Program, Rev. 2, 12 November 2009. 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, Illinois, 369-382 .. National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46. Northern States Power Company. ___ ..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.
----:1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual,           Montgomery, Alabama (EPA-520/5-84-006).
____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007. 24 
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.
____2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
____.2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.
Minneapolis, Minnesota.
25


==6.0 REFERENCES==
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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2015 through December, 2015
 
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. 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.
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.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.
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 lists REMP specific analytical results from 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.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
Out-of-limit results are explained directly below the result.
A1
 
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S 8
LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES One standard deviation Analysis                                  Level                                        for single determination Gamma Emitters                            5 to 100 pCi/liter or kg                      5.0 pCi/liter
                                                > 100 pCilliter or kg                    5% of known value Strontium-89b                              5 to 50 pCilliter or kg                      5.0 pCi/liter
                                                > 50 pCi/liter or kg                    10% of known value Stronti um-90b                            2 to 30 pCi/liter or kg                      5.0 pCilliter
                                                > 30 pCi/liter or kg                    10% of known value Potassium-40                              ;::: 0.1 g/liter or kg                        5% of known value Gross alpha                                :5 20 pCi/liter                              5.0 pCi/liter
                                          > 20 pCi/liter                                25% of known value Gross beta                                :5 100 pCilliter                              5.0 pCi/liter
                                          > 100 pCi/liter                              5% of known value Tritium                                    :5 4,000 pCi/liter                            +/- 1o =
169.85 x (known) 0 ' 0933
                                          > 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 lodine-131,                                :5 55 pCilliter                              6 pCilliter lodine-129b                            >55 pCi/liter                                10% of known value Uranium-238,                              :5 35 pCi/liter                              6 pCi/liter Nickel-63b                              > 35 pCi/liter                                15% of known value Technetium-99b lron-55b                                  50 to 100 pCi/liter                          10 pCi/liter
                                          > 100 pCi/liter                              10% of known value Other Analyses b                                                                        20% of known value a  From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b  Laboratory limit.
A2
 
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
Concentration (pCi/L)
Lab Code          Date          Analysis          Laboratory          ERA                  Control Result  b        Result c              Limits            Acceptance ERW-1444          4/6/2015      Sr-89            59.71  +/- 5.44            63.20        51.10 -71.20                Pass ERW-1444          4/6/2015      Sr-90            43.41  +/- 2.43            41.90        30.80 - 48.10              Pass ERW-1448          4/6/2015      Ba-133            77.75  +/- 4.69            82.50        69.30 - 90.80              Pass ERW-1448          4/6/2015      Cs-134            68.82  +/- 3.08            75.70        61.80 - 83.30              Pass ERW-1448          4/6/2015      Cs-137            191.9  +/- 5.9            189.0        170.0 - 210.0              Pass ERW-1448          4/6/2015      Co-60            85.05  +/- 4.59            84.50        76.00 - 95.30              Pass ERW-1448          4/6/2015      Zn-65            196.0  +/- 12.0            203.0        183.0 -238.0                Pass ERW-1450          4/6/2015      Gr. Alpha        34.05  +/- 1.90            42.60        22.10-54.00                Pass ERW-1450          4/6/2015      G. Beta          26.93  +/- 1.12            32.90        21.30 - 40.60              Pass ERW-1453          4/6/2015      1-131            22.47  +/- 0.83            23.80        19.70 -28.30                Pass ERW-1456          4/6/2015      Ra-226              8.20  +/- 0.56            8.43        6.33-9.90                  Pass ERW-1456          4/6/2015      Ra-228              5.00  +/- 0.67            4.39        2.56 -6.01                Pass ERW-1456          4/6/2015      Uranium            5.98 +/- 0.31              6.59        4.99 -7.83                Pass ERW-1461          4/6/2015      H-3              3,254 +/- 180                3280        2,770 -3,620                Pass ERW-5528          10/5/2015      Sr-89            34.76  +/- 0.06            35.70        26.70 -42.50                Pass ERW-5528          10/5/2015      Sr-90            29.23  +/- 0.06            31.10        22.70 -36.10                Pass ERW-5531          10/5/2015      Ba-133            30.91  +/- 0.53            32.50        25.90 - 36.70              Pass ERW-5531          10/5/2015      Cs-134            57.40  +/- 2.57            62.30        50.69 - 68.50              Pass ERW-5531          10/5/2015      Cs-137            163.1  +/-4.8              157.0        141.0 -175.0                Pass ERW-5531          10/5/2015      Co-60            73.41  +/- 1.72            71.10        64.00 - 80.70              Pass ERW-5531          10/5/2015      Zn-65            138.9  +/- 5.7            126.0        113.0 -149.0                Pass ERW-5534          10/5/2015      Gr. Alpha        29.99  +/- 0.08            51.60        26.90 - 64.70              Pass ERW-5534          10/5/2015      G. Beta          27.52  +/- 0.04            36.60        24.10 - 44.20              Pass ERW-5537          10/5/2015      1-131            25.54    +/-0.60            26.30        21.90-31.00                Pass ERW-5540          10/5/2015      Ra-226              7.32  +/- 0.37            7.29        5.49 -8.63                Pass ERW-5540d          10/5/2015      Ra-228              7.80  +/- 0.02            4.25        2.46 -5.85                Fail ERW-5540*          10/5/2015      Ra-228              4.45  +/- 0.96              4.25        2.46 -5.85                Pass ERW-5540          10/5/2015      Uranium          53.30  +/- 0.55            56.20        45.70 - 62.40              Pass ERW-5543          10/5/2015      H-3            21,260    +/- 351          21,300        18,700-23,400                Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
* The result of reanalysis (Compare to original result, footnoted "e" above).
A1-1
 
TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code          Irradiation                  Known                Lab      Control Date    Description      Value              Result      Limits    Acceptance Environmental Inc.
2015-1            6/24/2015      30cm.          98.81        103.67 +/-6.05  69.20-128.50    Pass 2015-1            6/24/2015      30cm.          98.81        111.32+/-15.97  69.20 -128.50    Pass 2015-1            6/24/2015      60cm.          24.70          27.23 +/- 1.33 17.30-32.10      Pass 2015-1            6/24/2015      60cm.          24.70          26.98 +/-4.98  17.30-32.10      Pass 2015-1            6/24/2015    120 em.          6.18          6.71 +/- 1.77  4.30-8.00      Pass 2015-1            6/24/2015    120cm.            6.18          6.78 +/-0.38  4.30-8.00      Pass 2015-1            6/24/2015    120cm.            6.18          6.43 +/-2.00  4.30 -8.00      Pass 2015-1            6/24/2015    150cm.            3.95          4.13 +/-0.72  2.80-5.10      Pass 2015-1            6/24/2015    150cm.            3.95          4.12 +/-1.36  2.80-5.10      Pass 2015-1            6/24/2015    150cm.            3.95          4.50 +/- 1.51  2.80-5.10      Pass 2015-1            6/24/2015    180cm.            2.74          3.27 +/-0.28  1.90-3.60      Pass 2015-1            6/24/2015    180cm.            2.74          3.05 +/-1.11  1.90-3.60      Pass 2015-1            6/24/2015    180 em.          2.74          3.14 +/-0.18  1.90-3.60      Pass A2-1
 
TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards).                b mrem Lab Code            Irradiation                    Delivered          Reported            Performance c Date          Description    Dose                Dose              Quotient (P)        Acceptance  d Environmental, Inc.
2015-2              12/15/2015      Spike 1          138.0          118.5 +/-2.1                  -0.14              Pass 2015-2              12/15/2015      Spike 2          138.0          120.0 +/- 1.6                  -0.13              Pass 2015-2              12/15/2015 Spike 3                138.0          121.9 +/- 1.9                  -0.12              Pass 2015-2              12/15/2015 Spike 4                138.0          124.5 +/- 3.3                  -0.10              Pass 2015-2              12/15/2015 Spike 5                138.0          126.5 +/- 3.2                  -0.08              Pass 2015-2              12/15/2015 Spike 6                138.0          140.0 +/- 4.2                  0.01              Pass 2015-2              12/15/2015 Spike 7                138.0          128.2+/-1.2                    -0.07              Pass 2015-2              12/15/2015 Spike 8                138.0          128.0 +/- 4.0                  -0.07              Pass 2015-2              12/15/2015 Spike 9                138.0          124.9 +/-5.1                  -0.09              Pass 2015-2              12/15/2015 Spike 10              138.0          122.9 +/-3.0                  -0.11              Pass 2015-2              12/15/2015      Spike 11          138.0          123.3 +/- 3.0                  -0.11              Pass 2015-2              12/15/2015 Spike 12              138.0          119.0 +/- 3.4                  -0.14              Pass 2015-2              12/15/2015 Spike 13              138.0          123.0 +/-2.7                  -0.11              Pass 2015-2              12/15/2015 Spike 14              138.0          125.4 +/- 2.0                  -0.09              Pass 2015-2              12/15/2015 Spike 15              138.0          122.0 +/-3.1                  -0.12              Pass 2015-2              12/15/2015      Spike 16          138.0          120.8 +/- 2.0                  -0.12              Pass 2015-2              12/15/2015      Spike 17          138.0          118.8 +/- 1.1                  -0.14              Pass 2015-2              12/15/2015      Spike 18          138.0          117.0 +/-2.3                  -0.15              Pass 2015-2              12/15/2015 Spike 19              138.0          120.8 +/- 2.6                  -0.12              Pass 2015-2              12/15/2015 Spike 20              138.0          122.6 +/- 3.0                 -0.11              Pass Mean (Spike 1-20)                                                    123.4                        0.11              Pass Standard Deviation (Spike 1-20)                                        5.0                        0.04              Pass a  TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b  TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c  Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose.
d  Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
e Tables A2.1 and A2.2 assume 1 roentgen= 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015).
A2-2
 
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b    Date        Analysis  Laboratory results      Known        Control 2s, n=1 c            Activity    Limits d    Acceptance W-020315      2/3/2015    Ra-226      16.19+/-0.42              16.70    13.36-20.04        Pass W-021215      2/12/2015    Gr. Alpha    18.38 +/- 0.39            20.10    16.08-24.12        Pass W-021215      2/12/2015    Gr. Beta    27.98 +/- 0.32            30.90    24.72- 37.08      Pass SPW-687        2/27/2015    Ni-63        239.6 +/- 3.5            202.4    161.9 - 242.9      Pass SPAP-689      3/2/2015    Gr. Beta    42.37 +/- 3.50            43.61    34.89 - 52.33      Pass SPAP-691      3/2/2015    Cs-134        1.77 +/- 0.61            1.90    1.52 - 2.28      Pass SPAP-691      3/2/2015    Cs-137      83.02 +/- 2.60            97.20    77.76-116.64      Pass SPW-693        3/2/2015    Cs-134      44.30 +/- 2.53            53.40    42.72-64.08        Pass SPW-693        3/2/2015    Cs-137      74.82 +/- 3.50            73.80    59.04 - 88.56      Pass SPW-693        3/2/2015    Sr-89        87.45 +/- 3.62            87.48    69.98- 104.98      Pass SPW-693        3/25/2015    Sr-90        37.22 +/- 1.55            38.10    30.48 - 45.72      Pass SPMI-697      3/2/2015    Cs-134      96.67 +/- 7.74          107.00    85.60 - 128.40    Pass SPMI-697      3/2/2015    Cs-137      78.51 +/- 7.02            73.84    59.07 - 88.61      Pass SPMI-697      3/2/2015    Sr-89        72.98 +/- 4.86            87.48    69.98- 104.98      Pass SPMI-697      3/2/2015    Sr-90        39.17+/-1.51              38.10    30.48-45.72        Pass SPW-699        3/2/2015    H-3        59,592 +/- 703            58,445  46,756 -70,134      Pass W-031115      3/11/2015    Ra-226      13.73 +/- 0.35            16.70    13.36-20.04        Pass W-030215      3/2/2015      Ra-228      32.79 +/- 2.31            31.44    25.15-37.73        Pass SPF-1040      3/16/2015    Cs-134      787.5 +/- 9.2            840.0    672.0 - 1,008.0    Pass SPF-1040      3/16/2015    Cs-137      2,599 +/- 24              2,360    1,888 - 2,832      Pass SPW-1036      3/25/2015    Fe-55        1,792 +/- 63              1961    1,569 - 2,353      Pass SPW-1374      4/6/2015    U-238        46.03 +/- 2.25            41.70    25.02 - 58.38      Pass W-040815      4/8/2015    Gr. Alpha    20.18 +/-0.42            20.10    16.08-24.12        Pass W-040815      4/8/2015    Gr. Beta    29.70 +/- 0.33            30.90    24.72 - 37.08      Pass SPW-1038      4/13/2015    C-14        3,497 +/- 9              4,734    2,840 - 6,628      Pass W-2165        4/20/2015    H-3          5550 +/- 226              5,780  3,468 - 8,092      Pass W-2165        4/20/2015    Sr-89        90.70 +/- 8.20          108.70    65.22 -152.18      Pass W-2165        4/20/2015    Sr-90      76.80 +/- 2.00            75.90  45.54 - 106.26    Pass W-2165        4/20/2015    Cs-134      62.40 +/- 6.40            57.30    34.38 - 80.22      Pass W-2165        4/20/2015    Cs-137      91.30 +/- 7.70            84.00    50.40 - 117.60    Pass W-2392        4/13/2015    H-3          5032 +/- 214              5780    3468-8092        Pass W-2392        4/13/2015    Ni-63      222.4 +/- 3.8            202.0    121.2 - 282.8      Pass W-2392        4/13/2015    Cs-134      53.26 +/- 5.01            57.30    34.38 - 80.22      Pass W-2392        4/13/2015    Cs-137      91.90 +/-7.76              84.20  50.52- 117.88      Pass W-042415      4/24/2015    Ra-226      12.52 +/- 0.39            16.70  10.02 - 23.38      Pass W-050715      5n/2015      Gr. Alpha    19.05+/-0.41              20.10  12.06-28.14        Pass W-050715      5n/2015      Gr. Beta    27.30 +/- 0.32            30.90  18.54 - 43.26      Pass W-061215      6/12/2015    Gr. Alpha  20.72 +/- 0.44            20.10  12.06-28.14        Pass W-061215      6/12/2015    Gr. Beta    28.51 +/- 0.33            30.90  18.54-43.26        Pass U-2982        6/9/2015      Gr. Beta    500.1 +/- 5.1              604.0  362.4 - 845.6      Pass U-3200        6/9/2015      H-3          2229 +/- 424              2346    1408 - 3284      Pass W-70915        7/9/2015      Gr. Alpha    18.76 +/- 0.40            20.10    12.1-28.1        Pass W-70915        7/9/2015      Gr. Beta    29.71  +/- 0.33            30.90    18.5 -43.3      Pass SPAP-3859      7/21/2015    Gr. Beta    41.59  +/- 0.12            43.61  26.17-61.05        Pass SPAP-3861      7/21/2015    Cs-134        1.69 +/- 0.60              1.69    1.0-2.4        Pass A3-1


CITED (continued)
T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code    b        Date            Analysis            Laboratory results            Known              Control 2s, n=1 c              Activity            Limits d            Acceptance SPAP-3861            7/21/2015      Cs-137                  93.71 +/- 2.64              96.45          57.87 -135.03                Pass SPMI-3863            7/21/2015      Cs-134                  38.21 +/- 5.12              47.02          28.21 - 65.83                Pass SPMI-3863            7/21/2015      Cs-137                  78.65 +/- 7.94              73.18          43.91 - 102.45                Pass SPMI-3863            7/21/2015      Sr-90                  41.05 +/- 1.62              37.78          22.67 - 52.89                Pass SPW-3871            7/21/2015      Cs-134                  45.59 +/- 6.39              47.02          28.21 - 65.83                Pass SPW-3871            7/21/2015       Cs-137                 78.73 +/- 7.03               73.18         43.91 - 102.45               Pass SPW-3871             7/21/2015       Sr-90                   38.36 +/- 1.58               37.78         22.67 - 52.89                 Pass SPW-3873             7/21/2015       H-3                   60,034 +/- 671               57,199         34,319-80,079                 Pass SPW-3875             7/21/2015       Ni-63                   451.3 +/- 3.3               403.7         242.2 - 565.2                 Pass SPW-3877             7/21/2015       Tc-99                   483.0 +/- 8.3               539.1         323.5 -754.7                 Pass SPMI-3879           7/21/2015       C-14                   4,921 +/- 19                 4,736         2,842 - 6,630                 Pass SPS0-4037           7/21/2015       Ni-63                 42,458 +/- 309               40,370         24,222 -56,518                 Pass SPW-072515           7/17/2015       Ra-228                 35.48 +/- 3                 31.44         18.86 - 44.02                 Pass SPF-4104             7/29/2015       Cs-134                 661.5+/-115.9               740.0         444.0 - 1036.0               Pass SPF-4104             7/29/2015       Cs-137                 2,469 +/-59                 2,340         1 ,404 - 3,276               Pass SPW-81015           8/10/2015       Gr. Alpha               21.59 +/- 0.46               20.10         12.06-28.14                   Pass SPW-81015           8/10/2015       Gr. Beta               27.58 +/- 0.32               30.90         18.54 - 43.26                 Pass SPW-81315           8/13/2015       Ra-226                 15.05 +/- 0.36               16.70         10.02 - 23.38                 Pass SPW-90615           9/6/2015       Gr. Alpha               18.32 +/- 0.40             20.10         12.06-28.14                   Pass SPW-90615           9/6/2015       Gr. Beta               29.43 +/- 0.33             30.90         18.54 - 43.26                 Pass W-091415             9/14/2015       Gr. Alpha               19.35 +/- 0.51             20.10         12.06-28.14                   Pass W-091415             9/14/2015       Gr. Beta               31.53 +/- 0.35             30.90         18.54 - 43.26                 Pass W-100815             10/8/2015       Ra-228                 12.27 +/- 0.33             16.70         10.02 - 23.38                 Pass W-100615             10/6/2015       Gr. Alpha               20.62 +/- 0.43             20.10         12.06-28.14                   Pass W-100615             10/6/2015       Gr. Beta               29.35 +/- 0.33             30.90         18.54 - 43.26                 Pass W-5277               10/16/2015     H-3                     5,224 +/- 218               5,466         3,280 - 7,652                 Pass W-5277               10/16/2015     Cs-134                 99.40 +/- 6.64             99.20         59.52 - 138.88               Pass W-5277               10/16/2015     Cs-137                 89.60 +/- 6.64             83.20         49.92 - 116.48               Pass W-110415             11/4/2015       Ra-226                 12.27 +/- 0.33             16.70         10.02 - 23.38                 Pass W-111115             11/11/2015     Ra-228                 31.78 +/- 2.48             31.44         18.86 - 44.02                 Pass W-6086,6087         11/18/2015     H-3                   10,882   +/- 309             11,231         6,738 - 15,723               Pass W-6086,6087         11/18/2015     Cs-134                 92.98 +/- 7.29             96.25         57.75 - 134.75               Pass W-6086,6087         11/18/2015     Cs-137                 76.65 +/- 7.81             82.94         49.76 - 116.12               Pass W-112515             11/25/2015     Gr. Alpha               20.91 +/- 0.52             20.10         12.06-28.14                   Pass W-112515             11/25/2015     Gr. Beta               31.59 +/- 0.35             30.90         18.54 - 43.26                 Pass W-120715             12/7/2015       Fe-55                   2,431 +/- 97               2,319         1,391 -3,247                 Pass W-120815             12/8/2015       Gr. Alpha               20.72 +/- 0.43             20.10         12.06-28.14                   Pass W-120815             12/8/2015       Gr. Beta               29.50 +/- 0.33             30.90         18.54 - 43.26                 Pass W-121515             12/15/2015     Ra-226                 14.77 +/- 0.42             16.70         10.02 - 23.38                 Pass
Scannell, M. J., J. Giard, J. Raimondi.
2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN. 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.
____ 2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
____ .2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
25 NOTE: APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported.
Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. January, 2015 through December, 2015 Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
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.
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. Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. 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 lists REMP specific analytical results from 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. Complete analytical data for duplicate analyses is available upon request. The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program. Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML). Attachment A lists the laboratory precision at the 1 sigma level for various analyses.
The acceptance criteria in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1 Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S LABORATORY PRECISION:
ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES 8 Analysis Gamma Emitters Strontium-89b Stronti u m-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 to 100 pCi/liter or kg > 100 pCilliter or kg 5 to 50 pCilliter or kg > 50 pCi/liter or kg 2 to 30 pCi/liter or kg > 30 pCi/liter or kg ;::: 0.1 g/liter or kg :5 20 pCi/liter
> 20 pCi/liter
:5 100 pCilliter > 1 00 pCi/liter
:5 4,000 pCi/liter
> 4,000 pCi/liter
;::: 0.1 pCi/liter
;::: 0.1 pCi/liter, gram, or sample :5 55 pCilliter
>55 pCi/liter
:5 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter > 1 00 pCi/liter a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit. A2 One standard deviation for single determination 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCilliter 1 0% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value +/- 1o = 169.85 x (known)0'0933 10% of known value 15% of known value 1 0% of known value 6 pCilliter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22.10-54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 -80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21.90-31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540*
10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700-23,400 Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
* The result of reanalysis (Compare to original result, footnoted "e" above). A1-1 TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental Inc. 2015-1 6/24/2015 30cm. 98.81 103.67 +/-6.05 69.20-128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32+/-15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23 +/- 1.33 17.30-32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30-32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.43 +/-2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.12 +/-1.36 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180cm. 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180cm. 2.74 3.05 +/-1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14 +/-0.18 1.90-3.60 Pass A2-1 TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). b mrem Lab Code Irradiation Delivered Reported Date Description Dose Dose Environmental, Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/-2.1 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 2015-2 12/15/2015 Spike 3 138.0 121.9 +/- 1.9 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 2015-2 12/15/2015 Spike 9 138.0 124.9 +/-5.1 2015-2 12/15/2015 Spike 10 138.0 122.9 +/-3.0 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 2015-2 12/15/2015 Spike 15 138.0 122.0 +/-3.1 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 Mean (Spike 1-20) 123.4 Standard Deviation (Spike 1-20) 5.0 a TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) Performance c Quotient (P) -0.14 -0.13 -0.12 -0.10 -0.08 0.01 -0.07 -0.07 -0.09 -0.11 -0.11 -0.14 -0.11 -0.09
-0.12
-0.12 -0.14
-0.15
-0.12
-0.11 0.11 0.04 Acceptance d Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose-conventially true value) + conventially true value) where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. e Tables A2.1 and A2.2 assume 1 roentgen=
1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20-Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). A2-2 TABLE A-3. In-House "Spiked" Samples Lab Code b W-020315 W-021215 W-021215 SPW-687 SPAP-689 SPAP-691 SPAP-691 SPW-693 SPW-693 SPW-693 SPW-693 SPMI-697 SPMI-697 SPMI-697 SPMI-697 SPW-699 W-031115 W-030215 SPF-1040 SPF-1040 SPW-1036 SPW-1374 W-040815 W-040815 SPW-1038 W-2165 W-2165 W-2165 W-2165 W-2165 W-2392 W-2392 W-2392 W-2392 W-042415 W-050715 W-050715 W-061215 W-061215 U-2982 U-3200 W-70915 W-70915 SPAP-3859 SPAP-3861 Date Analysis 2/3/2015 Ra-226 2/12/2015 Gr. Alpha 2/12/2015 Gr. Beta 2/27/2015 Ni-63 3/2/2015 Gr. Beta 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Sr-89 3/25/2015 Sr-90 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Sr-89 3/2/2015 Sr-90 3/2/2015 H-3 3/11/2015 Ra-226 3/2/2015 Ra-228 3/16/2015 Cs-134 3/16/2015 Cs-137 3/25/2015 F e-55 4/6/2015 U-238 4/8/2015 Gr. Alpha 4/8/2015 Gr. Beta 4/13/2015 C-14 4/20/2015 H-3 4/20/2015 Sr-89 4/20/2015 Sr-90 4/20/2015 Cs-134 4/20/2015 Cs-137 4/13/2015 H-3 4/13/2015 Ni-63 4/13/2015 Cs-134 4/13/2015 Cs-137 4/24/2015 Ra-226 5n/2015 Gr. Alpha 5n/2015 Gr. Beta 6/12/2015 Gr. Alpha 6/12/2015 Gr. Beta 6/9/2015 Gr. Beta 6/9/2015 H-3 7/9/2015 Gr. Alpha 7/9/2015 Gr. Beta 7/21/2015 Gr. Beta 7/21/2015 Cs-134 Concentration (pCi/L)a Laboratory results 2s, n=1 c 16.19+/-0.42 18.38 +/- 0.39 27.98 +/- 0.32 239.6 +/- 3.5 42.37 +/- 3.50 1.77 +/- 0.61 83.02 +/- 2.60 44.30 +/- 2.53 74.82 +/- 3.50 87.45 +/- 3.62 37.22 +/- 1.55 96.67 +/- 7.74 78.51 +/- 7.02 72.98 +/- 4.86 39.17+/-1.51 59,592 +/- 703 13.73 +/- 0.35 32.79 +/- 2.31 787.5 +/- 9.2 2,599 +/- 24 1,792 +/- 63 46.03 +/- 2.25 20.18 +/-0.42 29.70 +/- 0.33 3,497 +/- 9 5550 +/- 226 90.70 +/- 8.20 76.80 +/- 2.00 62.40 +/- 6.40 91.30 +/- 7.70 5032 +/- 214 222.4 +/- 3.8 53.26 +/- 5.01 91.90 +/-7.76 12.52 +/- 0.39 19.05+/-0.41 27.30 +/- 0.32 20.72 +/- 0.44 28.51 +/- 0.33 500.1 +/- 5.1 2229 +/- 424 18.76 +/- 0.40 29.71 +/- 0.33 41.59 +/- 0.12 1.69 +/- 0.60 A3-1 Known Activity 16.70 20.10 30.90 202.4 43.61 1.90 97.20 53.40 73.80 87.48 38.10 107.00 73.84 87.48 38.10 58,445 16.70 31.44 840.0 2,360 1961 41.70 20.10 30.90 4,734 5,780 108.70 75.90 57.30 84.00 5780 202.0 57.30 84.20 16.70 20.10 30.90 20.10 30.90 604.0 2346 20.10 30.90 43.61 1.69 Control Limits d 13.36-20.04 16.08-24.12 24.72-37.08 161.9 -242.9 34.89 -52.33 1.52 -2.28 77.76-116.64 42.72-64.08 59.04 -88.56 69.98-104.98 30.48 -45.72 85.60 -128.40 59.07 -88.61 69.98-104.98 30.48-45.72 46,756 -70,134 13.36-20.04 25.15-37.73 672.0 -1 ,008.0 1,888 -2,832 1,569 -2,353 25.02 -58.38 16.08-24.12 24.72 -37.08 2,840 -6,628 3,468 -8,092 65.22 -152.18 45.54 -106.26 34.38 -80.22 50.40 -117.60 3468-8092 121.2 -282.8 34.38 -80.22 50.52-117.88 10.02 -23.38 12.06-28.14 18.54 -43.26 12.06-28.14 18.54-43.26 362.4 -845.6 1408 -3284 12.1-28.1 18.5 -43.3 26.17-61.05 1.0-2.4 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 -65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 -102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 -52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 -65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 -1 02.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 -52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 -565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 -6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 -44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 -1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1 ,404 -3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06-28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 -43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 -23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass W-091415 9/14/2015 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2015 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-100615 10/6/2015 Gr. Alpha 20.62 +/- 0.43 20.10 12.06-28.14 Pass W-100615 10/6/2015 Gr. Beta 29.35 +/- 0.33 30.90 18.54 -43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 -7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 -138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 -116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 -44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 -15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 -134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 -116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 -43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 -23.38 Pass
* Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
* Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c Results are based on single determinations.
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s. NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-2 TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/-3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/- 5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 1 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5n/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMI-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 1 A4-1 TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc  
c Results are based on single determinations.
.. Criteria (4.66 cr) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/- 0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.
NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.
A3-2
 
TABLE A-4. In-House "Blank" Samples 8
Concentration (pCi/L)
Lab Code     Sample           Date     Analysisb     Laboratory results (4.66a)         Acceptance Type                                     LLD           Activityc         Criteria (4.66 a)
W-020315     Water           2/3/2015 Ra-226         0.03         0.03 +/- 0.02 W-021215     Water           2/12/2015 Gr. Alpha     0.47         -0.37 +/- 0.30                 2 W-021215     Water           2/12/2015 Gr. Beta       0.76         -0.62 +/- 0.51                 4 SPW-686       Water           2/27/2015 Ni-63         2.36         -0.74 +/- 1.42                 20 SPAP-688     Air Particulate 3/2/2015 Gr. Beta     0.003       -0.001   +/- 0.002             0.01 SPAP-690     Air Particulate 3/2/2015 Cs-134       0.006       0.428   +/- 0.927             0.05 SPAP-690     Air Particulate 3/2/2015 Cs-137       0.006       -0.785   +/- 1.146             0.05 W-030215     Water           3/2/2015 Ra-228         0.76         0.22 +/- 0.38                 2 SPW-692       Water           3/2/2015 Cs-134         6.70         -1.57 +/- 3.55                 10 SPW-692       Water           3/2/2015 Cs-137         6.18         -0.15 +/-3.20                 10 SPW-692       Water           3/2/2015 Sr-89         0.61         -0.51 +/- 0.51                 5 SPW-692       Water           3/2/2015 Sr-90         0.60         0.38 +/- 0.33                 1 SPMI-696     Milk             3/2/2015 Cs-134         3.75         -0.25 +/- 2.24                 10 SPMI-696     Milk             3/2/2015 Cs-137         4.36         -0.25 +/- 2.24                 10 SPMI-696     Milk             3/2/2015 Sr-89         0.80         -0.40 +/- 0.84                 5 SPMI-696     Milk             3/2/2015 Sr-90         0.49         0.98 +/- 0.32                 1 SPW-698       Water           3/2/2015 H-3           144.0         28.6 +/- 88.9               200 SPW-1035     Water           3/16/2015 Fe-55         599.7         72.6 +/- 368.1             1000 SPW-1037     Water           3/16/2015 C-14           8.94         2.16 +/- 5.47               200 SPF-1039     Fish             3/16/2015 Cs-134       13.54         -1.00 +/- 6.80               100 SPF-1039     Fish             3/16/2015 Cs-137         9.80         4.87 +/- 7.00               100 W-040615     Water           4/6/2015 Ra-226         0.04         0.01 +/- 0.03                   2 W-1373       Water           4/6/2015 U-238         0.08         0.01 +/- 0.01                   1 W-1375       Water           4/6/2015 Pu-238         0.03         0.00 +/- 0.01 W-050715     Water           5/7/2015 Gr. Alpha     0.38         -0.10 +/- 0.25                 2 W-050715     Water           5n/2015   Gr. Beta       0.74         -0.14 +/- 0.51                 4 W-061215     Water           6/12/2015 Gr. Alpha     0.42         -0.10 +/- 0.29                 2 W-061215     Water           6/12/2015 Gr. Beta       0.75         -0.04 +/- 0.53                 4 SPW-3858     Water           7/21/2015 Gr. Beta     0.003       0.004 +/- 0.002                   2 SPAP-3860     Air Particulate 7/21/2015 Cs-134       0.011       0.010 +/- 0.005               0.05 SPAP-3860     Air Particulate 7/21/2015 Cs-137       0.009       0.000 +/- 0.005               0.05 SPMI-3862     Milk             7/21/2015 Cs-134         3.13         1.56+/-1.74                   10 SPMI-3862     Milk             7/21/2015 Cs-137         3.20         1.69 +/- 1.89                 10 SPMI-3862     Milk             7/21/2015 Sr-89         2.17         -1.30 +/- 2.05                   5 SPMI-3862     Milk             7/21/2015 Sr-90         0.90         0.74 +/- 0.50                   1 SPW-3870     Water           7/21/2015 Cs-134         3.01         0.71 +/- 1.66                 10 SPW-3870     Water           7/21/2015 Cs-137         3.94         0.81 +/- 1.86                 10 SPW-3870     Water           7/21/2015 Sr-89           2.28       -0.42 +/- 1.80                   5 SPW-3870     Water           7/21/2015 Sr-90         0.84         0.25 +/- 0.42                   1 A4-1
 
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code           Sample                 Date           Analysisb           Laboratory results (4.66cr)             Acceptance Type                                                         LLD             Activityc ..         Criteria (4.66 cr)
SPW-3872           Water                   7/21/2015       H-3               142.6           82.7 +/- 79.4                 200 SPW-3874           Water                   7/21/2015       Ni-63               2.98           0.77 +/- 1.82                   20 SPW-3876           Water                   7/21/2015     Tc-99                 5.49         -3.81 +/- 3.26                   10 SPW-3878           Water                   7/21/2015       C-14               17.06           8.52 +/- 10.54                 200 SPS0-4036           Soil                   7/21/2015       Ni-63             135.7           51.3 +/- 83.0               1000 SPF-4103           Fish                   7/29/2015       Cs-134             14.17         -37.70   +/- 9.67                 100 SPF-4103           Fish                   7/29/2015     Cs-137             12.39           1.13 +/-8.06                   100 W-081015           Water                   8/10/2015     Gr. Alpha             0.48         -0.10 +/- 0.33                     2 W-081015           Water                   8/10/2015       Gr. Beta             0.78         -0.18 +/- 0.54                     4 W-081815           Water                   8/18/2015       Ra-226               0.03           0.03 +/- 0.02                     2 W-090615           Water                   9/6/2015       Gr. Alpha           0.40           0.00 +/- 0.28                     2 W-090615           Water                   9/6/2015       Gr. Beta             0.77           0.22 +/- 0.54                     4 W-091415           Water                   9/14/2015       Gr. Alpha           0.41           0.10 +/- 0.30                     2 W-091415           Water                   9/14/2015       Gr. Beta             0.77           0.04 +/- 0.54                     4 W-100615           Water                   10/6/2015       Gr. Alpha           0.41         -0.15 +/- 0.27                     2 W-100615           Water                   10/6/2015       Gr. Beta             0.75         -0.12 +/- 0.52                     4 W-112515           Water                   11/25/2015     Gr. Alpha           0.42           0.05 +/- 0.30                     2 W-112515           Water                   11/25/2015     Gr. Beta             0.78         -0.31 +/- 0.54                     4 W-120815           Water                   12/8/2015       Gr. Alpha           0.42         -0.08 +/- 0.29                     2 W-120815           Water                   12/8/2015       Gr. Beta             0.76           0.17 +/-0.54                       4 W-121515           Water                   12/15/2015     Ra-226               0.01           0.01 +/- 0.01                     2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.
b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity
c Activity reported is a net activity result.
A4-2
 
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 8 Averaged Lab
1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.
1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.
A6-3 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/- 2.2 49.8 30.7-67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2-98.8.
A6-3
Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 -1 '130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 -50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/- 3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 -52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21.3-51.7 Pass ERAP-1091 3/16/2015 U-238 31.0 +/- 1.1 34.0 22.0-47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8-96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/- 0.8 58.4 36.9 -85.1 Pass ERS0-1098 3/16/2015 Am-241 157.1.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474-2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9  
 
+/- 86.9 4,430 2,670 -6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1 ,270 -2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180-7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1,140-1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810-14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806 -1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 -6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 -1 ,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1 '185 +/- 140 1,210 791-1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/- 948 3,890 1,230 -7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 -5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,41 0 -4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 -9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2-184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900-14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/- 266 4,340 2,650 -5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 -2,120 Pass A7-1 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060-2,150 Fail ERVE-1100 r 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060-2,150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/-27 2,650 1, 700 -3,440 Fail ERVE-1100 r 3/16/2015 Cs-134 2,554 +/- 49 2,650 1, 700 -3,440 Pass ERVE-1100&deg; 3/16/2015 Cs-137 1,248 +/- 29 1,810 1 ,310 -2,520 Fail ERVE-1100 r 3/16/2015 Cs-137 2,078 +/- 68 1,810 1 ,310 -2,520 Pass ERVE-11 00 e 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 -43,400 Fail ERVE-1100 r 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 -43,400 Pass ERVE-11 00 e 3/16/2015 Mn-54 <13.8 <300 0.0-300.0 Pass ERVE-1100 r 3/16/2015 Mn-54 <24.4 <300 0.0-300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/- 232 3,680 2,190 -5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570-5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/- 326 6,590 3,760-8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 -3,980 Pass ERVE-11 00 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 r 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0-61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/- 17 1,250 1 ,090 -1 ,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925-1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1 , 150 -1 , 630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 -232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/- 4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 -75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/- 136 1,180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 -1,210.0 Pass
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML). b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation).
Concentration (pCi/L) b Lab Code b   Date         Analysis         Laboratory           ERA         Control Result c         Result d         Limits       Acceptance ERAP-1091     3/16/2015     Am-241           46.8 +/- 2.2           49.8       30.7-67.4           Pass ERAP-1091     3/16/2015     Co-60             85.1 +/- 2.9           79.1       61.2-98.8.         Pass ERAP-1091     3/16/2015     Cs-134         825.6 +/- 34.7         909.0     578.0 - 1'130.0       Pass ERAP-1091     3/16/2015     Cs-137         1,312+/-12             1,170       879 - 1,540       Pass ERAP-1091     3/16/2015     Fe-55           760.6 +/- 48.2         836.0     259.0 - 1630.0       Pass ERAP-1091     3/16/2015     Mn-54             <2.7                 <50         0.0 - 50.0       Pass ERAP-1091     3/16/2015     Pu-238           51.0 +/- 3.9           52.1       35.7-68.5           Pass ERAP-1091     3/16/2015     Pu-239/240       38.3 +/- 1.3           40.3     29.20 - 52.70         Pass ERAP-1091     3/16/2015     Sr-90             95.3 +/- 11.4         96.6       47.2 - 145.0       Pass ERAP-1091     3/16/2015     U-233/234         29.0 +/- 1.2           34.3       21.3-51.7           Pass ERAP-1091     3/16/2015     U-238             31.0 +/- 1.1           34.0       22.0-47.0           Pass ERAP-1091     3/16/2015     Zn-65         1099.3 +/- 146.5         986.0     706.0 - 1360.0       Pass ERAP-1094     3/16/2015     Gr. Alpha         73.7 +/- 0.7           62.2       20.8-96.6           Pass ERAP-1094     3/16/2015     Gr. Beta         69.6 +/- 0.8           58.4       36.9 - 85.1         Pass ERS0-1098     3/16/2015     Am-241         157.1.8 +/- 209.6       1,500       878 - 1,950       Pass ERS0-1098     3/16/2015     Ac-228         1198.8 +/- 140.4       1,250       802 - 1,730       Pass ERS0-1098     3/16/2015     Bi-212         1420.1 +/-455.7         1,780       474-2,620         Pass ERS0-1098     3/16/2015     Bi-214         3466.9 +/- 86.9         4,430     2,670 - 6,380         Pass ERS0-1098     3/16/2015     Co-60         1779.8 +/-41.0           1,880   1,270 - 2,590         Pass ERS0-1098     3/16/2015     Cs-134         5204.6 +/- 64.5         6,390     4,180-7,680           Pass ERS0-1098     3/16/2015     Cs-137         1417.1 +/-41.9           1,490   1,140-1,920           Pass ERS0-1098     3/16/2015     K-40           10,597 +/- 380         10,700   7,810-14,400         Pass ERS0-1098     3/16/2015     Mn-54           <62.2                 < 1000       0.0 - 1,000       Pass ERS0-1098     3/16/2015     Pb-212         1,032 +/- 41           1,230       806 - 1,710       Pass ERS0-1098     3/16/2015   Pb-214         3,629 +/- 93           4,530     2,640 - 6,760         Pass ERS0-1098     3/16/2015     Pu-238         942.9 +/- 128.8       998.0     600.0 - 1,380.0       Pass ERS0-1098     3/16/2015     Pu-239/240     1 '185 +/- 140           1,210       791-1,670         Pass ERS0-1098     3/16/2015     Sr-90           1,724+/-125             1,940       740 - 3,060       Pass ERS0-1098     3/16/2015     Th-234         3,666 +/- 948           3,890   1,230 - 7,320         Pass ERS0-1098     3/16/2015     U-233/234       3,474 +/- 226           3,920   2,400 - 5,020         Pass ERS0-1098     3/16/2015   U-238           3,620 +/- 232           3,890   2,41 0 - 4,930       Pass ERS0-1098     3/16/2015   Zn-65           7,362 +/- 145           7,130   5,680 - 9,470         Pass ERW-1095       3/16/2015   Gr. Alpha         93.4 +/- 11.5         119.0     42.2- 184.0         Pass ERW-1095       3/16/2015   Gr. Beta       145.2 +/- 4.8           158.0     90.5-234.0         Pass ERW-1110       3/16/2015   H-3           10,573 +/- 78           10,300   6,900- 14,700         Pass ERVE-1100     3/16/2015   Am-241         4,537 +/- 266           4,340   2,650 - 5, 770       Pass ERVE-1100     3/16/2015   Cm-244         1,338 +/- 146           1,360       666 - 2,120       Pass A7-1
Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).
 
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
Concentration (pCi/L) b Lab Code     b     Date             Analysis               Laboratory           ERA             Control Result c         Result d           Limits         Acceptance ERVE-1100 e         3/16/2015         Co-60                 1,030 +/- 29           1,540       1,060-2,150             Fail ERVE-1100 r         3/16/2015         Co-60                 1,684 +/- 48           1,540       1,060-2,150             Pass ERVE-1100 e         3/16/2015         Cs-134                 1,615 +/-27           2,650       1, 700 - 3,440           Fail ERVE-1100 r         3/16/2015         Cs-134                 2,554 +/- 49           2,650       1, 700 - 3,440         Pass ERVE-1100&deg;         3/16/2015         Cs-137                 1,248 +/- 29           1,810       1,310 - 2,520           Fail ERVE-1100 r         3/16/2015         Cs-137                 2,078 +/- 68           1,810       1 ,310 - 2,520         Pass ERVE-11 00 e       3/16/2015         K-40                 22,037 +/- 463         30,900       22,300 - 43,400           Fail ERVE-1100 r         3/16/2015         K-40                 34,895 +/- 764         30,900       22,300 - 43,400         Pass ERVE-11 00 e       3/16/2015         Mn-54                 <13.8                 <300             0.0-300.0           Pass ERVE-1100 r         3/16/2015         Mn-54                 <24.4                 <300             0.0- 300.0         Pass ERVE-1100           3/16/2015         Pu-238                 3,232 +/- 232         3,680       2,190 - 5,040           Pass ERVE-1100           3/16/2015         Pu-239/240             3,606 +/- 240         4,180       2,570-5,760             Pass ERVE-1100           3/16/2015         Sr-90                 6,023 +/- 326         6,590       3,760-8,740             Pass ERVE-1100           3/16/2015         U-233/234             2,653 +/- 153           3,150       2,070 -4,050           Pass ERVE-1100           3/16/2015         U-238                 2,717 +/- 163           3,130       2,090 - 3,980           Pass ERVE-11 00 e       3/16/2015         Zn-65                 <94.6                 1,090           786 - 1,530           Fail ERVE-1100 r         3/16/2015         Zn-65                 1,306 +/- 75           1,090           786 - 1,530         Pass ERW-1103           3/16/2015         Am-241                   47.1 +/-4.0           46.0         31.0-61.7             Pass ERW-1103           3/16/2015         Co-60                 1,217 +/- 17           1,250       1,090 - 1,460           Pass ERW-1103           3/16/2015         Cs-134                 1,121 +/- 18           1,260           925- 1,450           Pass ERW-1103           3/16/2015         Cs-137                 1,332 +/- 31           1,360       1,150 - 1,630           Pass ERW-1103           3/16/2015         Mn-54                   <3.7               <100           0.00 - 100.00         Pass ERW-1103           3/16/2015         Pu-238                 54.5 +/- 1.6           72.4         53.6 - 90.1           Pass ERW-1103 9         3/16/2015         Pu-239/240           140.2 +/- 7.8         184.0       143.0 - 232.0           Fail ERW-3742h           9/27/2012         Pu-239/240             89.3 +/- 4.9           97.7         66.6 - 108.0         Pass ERW-1103           3/16/2015         U-233/234               56.5 +/- 6.4           61.8         46.4 - 79.7         Pass ERW-1103           3/16/2015         U-238                   58.4 +/- 5.8           61.3         46.7 - 75.2         Pass ERW-1103           3/16/2015         Zn-65                 1,191 +/- 136           1,180           984 - 1,490         Pass ERW-1103           3/16/2015         Fe-55                 1,149+/-144             1,070           638 - 1,450         Pass ERW-1103           3/16/2015         Sr-90                 860.0 +/- 37.0         912.0       594.0   - 1,210.0       Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).
* Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.
* Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
Control limits are not provided.
* Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).
* Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above). 9 The results of reanalysis were outside the control limits (low). h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range. The results for ERW-37 42 were acceptable.
9 The results of reanalysis were outside the control limits (low).
No reason for the unacceptable results for ERW-37 42 was determined.
h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range.
A7-2 APPENDIX B. DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample. 3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x 1 +/- s 1 and x 2 +/- s 2 Reported result: x +/- s; where x == (1/2) (x 1 + x 2) and s == (1/2) + s; 3.2. Individual results: < L 1 , < L 2 Reported result: < L, where L == lower of L 1 and L 2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x L; < L otherwise.
The results for ERW-37 42 were acceptable. No reason for the unacceptable results for ERW-37 42 was determined.
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 standard deviation would not be the average of quarterly standard deviations.
A7-2
The average x and standard deviation "s" of a set of n numbers x 1 , x 2 ... xn are defined as follows: -1 X =r; LX s-\jnT 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.
 
APPENDIX B.             DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample.
3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. :
3.1       Individual results:   For two analysis results; x 1 +/- s 1 and x2 +/- s 2 Reported result:       x +/- s; where x == (1/2) (x 1 + x2 ) and s == (1/2) ~ s~ + s; 3.2.     Individual results:     < L1 , < L2        Reported result: < L, where L == lower of L1 and L2 3.3.     Individual results:     x +/- s, < L         Reported result:         x +/- 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 ~nnual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1 , x2 . . . xn are defined as follows:
X
                                  -   1
                                      =r; LX               s-
                                                              -A~  \jnT 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.
4.4 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 number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged.
4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers 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 number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45. B-1 APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a background in unrestricted areas . Air (pCi/m 3) Water (pCi/L) -3 Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 c Potassium-40 4,000 Gross alpha 2 Gross beta 10 6 Tritium 1 X 10 a b Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number 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. Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway. c A natural radionuclide.
B-1
C-1 APPENDIX D Sampling Location Maps D-1
 
,---1 I I II I i I I Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2) D-2 Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2) D-3 Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2) D-4
APPENDIX C Table C-1.     Maximum permissible concentrations of radioactivity in air and water above natural a
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background in unrestricted areas .
< z j 0 * / r J I ' I (
3 Air (pCi/m     )                                                   Water (pCi/L)
* J <J) a. E ro (f) -c:: <J) E '6 <J) (f) 0 /:/ " b N b 0 0 .,--Figure D-4, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Well Water and Shoreline sampling locations. (Table 5.2) D-5 Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2) D-6 APPENDIX E Ground Water Monitoring Well Samples E-1
                          -3 Gross alpha         1 X 10                                                   Strontium-89                 8,000 Gross beta         1                                                       Strontium-90                   500 b                 -1 lodine-131         2.8 X 10                                               Cesium-137                   1,000 Barium-140                   8,000 lodine-131                   1,000 c
Potassium-40                 4,000 Gross alpha                       2 Gross beta                       10 6
Tritium                     1 X 10 a
Taken from Table 2 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-1
 
APPENDIX D Sampling Location Maps D-1
 
1 I
I III iI I
Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2)
D-2
 
Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2)
D-3
 
Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2)
D-4
 
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0 Figure D-4, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Well Water and Shoreline sampling locations. (Table 5.2)
D-5
 
Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2)
D-6
 
APPENDIX E Ground Water Monitoring Well Samples E-1


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


This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January -December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.
This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January - December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.
E-2 2.0  
E-2
 
2.0  


==SUMMARY==
==SUMMARY==
Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07. This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater.
 
The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater.
Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07.
Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report. The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8'). Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1. Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.
This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater. The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater. Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or AREOR(REM~ffiports.
Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report.
The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8').
Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1.
Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.
Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.
Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.
The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized.
The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized. In practice, samples were counted to an even lower level, approximately 150 pCi/L.
In practice, samples were counted to an even lower level, approximately 150 pCi/L. Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property.
Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property. Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L.
Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L. Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public. No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015. A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4. E-3 3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.
Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public.
3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program. Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.
No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015.
3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:
A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4.
Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity. Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells. 3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015. E-4 3.5 Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911 +/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1. Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume. Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A. The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank. The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.
E-3
E-5 Table E-1. Sample Collection and Analysis Program, Ground Water. Medium Number Sample Codes Collection type Analysis Type Ground Water 32 MW-1, MW-2, MW-3, MW-4, Grab H-3 Quarterly MW-98, MW-11, MW-12A, MW-128, Ground Water 82 8 MW-9A, MW-10, MW-13A, Grab H-3 Monthly MW-138, MW-14, MW-15A MW-158, Ground Water 4 MW-5, MW-6, MW-7, MW-8 Grab H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well. Table E-2. Sampling locations for Ground Water Monitoring Wells. Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 sw Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9A 0.1 310 NW Ground Water M-51 MW-98 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-11 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-128 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-138 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW Ground Water M-53 MW-15A 0.14 14 NNE Ground Water M-54 MW-158 0.14 14 NNE E-6 Table E-3. Ground Water Monitoring Program Summary. Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses' Groundwater H-3 118 Monitoring Wells (pCi/L) Stormwater H-3 4 Runoff (pCi/L) GS 4 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 Ce-144 Sewer lift H-3 2 Station (pCi/L) GS 2 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) Indicator
 
,. Locations LLDb Mean (F)0 Range* 300 603 (47/118) (144-6493) 300 157(1/4) 10 < LLD 30 < LLD 10 < LLD 10 < LLD 30 < LLD 15 < LLD 30 < LLD 10 < LLD 10 < LLD 15 < LLD 43 < LLD 300 < LLD 10 < LLD 30 < LLD 10 < LLD 10 < LLD 30 < LLD 15 < LLD 30 < LLD 10 < LLD 10 < LLD 15 < LLD 43 < LLD Docket No. ...:5..:0...:-2:..:6...:.3-------,----
3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.
Reporting Period January-December, 2015 Location with Highest Annual Mean Mean (F)" Locationd Range* MW-9A, On-site, 1985 (10/13) 0.1 mi@310"/NW (182-6493)
3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.
SD-006 157(1/4) On-site ----------------------------------------------'GB = gross beta, GS =gamma scan. b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.
* 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:
3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:
(1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity.
Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells.
3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015.
E-4
 
3.5   Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911
    +/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1.
Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume.
Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A.
The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank.
The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.
E-5
 
Table E-1. Sample Collection and Analysis Program, Ground Water.
Medium       Number           Sample Codes               Collection type Analysis Type Ground Water       32       MW-1, MW-2, MW-3, MW-4,               Grab             H-3 Quarterly                 MW-98, MW-11, MW-12A, MW-128, 8
Ground Water       82       MW-9A, MW-10, MW-13A,                 Grab             H-3 Monthly                   MW-138, MW-14, MW-15A MW-158, Ground Water         4       MW-5, MW-6, MW-7, MW-8               Grab             H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well.
Table E-2. Sampling locations for Ground Water Monitoring Wells.
Sample Type       Vendor   Well         Distance from       Compass         Sector Code     Number       Stack (miles)       Heading from Stack Ground Water     M-33     MW-1         0.11                 299             WNW Ground Water     M-34     MW-2         0.14                 301             WNW Ground Water     M-35     MW-3         0.15                 305             NW Ground Water     M-36     MW-4         0.1                 25             NNE Ground Water     M-37     MW-5         0.1                 253             WSW Ground Water     M-38     MW-6         229 Feet             228             sw Ground Water       M-39     MW-7         0.2                 66             ENE Ground Water       M-40     MW-8         0.3                   150           SSE Ground Water       M-44     MW-9A         0.1                 310             NW Ground Water       M-51     MW-98         0.1                   310             NW Ground Water       M-45     MW-10         0.1                   292           WNW Ground Water       M-46     MW-11         0.1                   283           WNW Ground Water       M-47     MW-12A       0.1                   330             NW Ground Water       M-48     MW-128       0.1                   326             NW Ground Water       M-49     MW-13A       0.12                 316             NW Ground Water       M-50     MW-138       0.12                 316             NW Ground Water       M-52     MW-14         0.17                 306             NW Ground Water       M-53     MW-15A       0.14                 14             NNE Ground Water       M-54     MW-158       0.14                 14             NNE E-6
 
Table E-3. Ground Water Monitoring Program Summary.
Name of Facility         Monticello Nuclear Generating Plant                        Docket No.          ...:5..:0...:-2:..:6...:.3-------,----
Location of Facility    Wright, Minnesota                                          Reporting Period    January-December, 2015
( County, State )
Indicator                              Location with Highest Sample            Type and                      ,. Locations                                  Annual Mean 0
Type            Number of            LLDb            Mean (F)                                                      Mean (F)"
(Units)          Analyses'                            Range*                  Locationd                              Range*
Groundwater      H-3          118        300          603 (47/118)          MW-9A, On-site,                        1985 (10/13)
Monitoring Wells                                          (144-6493)          0.1 mi@310"/NW                            (182-6493)
(pCi/L)
Stormwater      H-3            4        300            157(1/4)                SD-006                                157(1/4)
Runoff                                                                          On-site (pCi/L)       GS            4 Mn-54                10              < LLD                     -                                      -
Fe-59                30             < LLD                     -                                      -
Co-58                10             < LLD                     -                                      -
Co-60                10             < LLD                     -                                      -
Zn-65                30             < LLD                       -                                      -
Zr-Nb-95            15              < LLD                       -                                      -
1-131                30             < LLD                     -                                      -
Cs-134              10             < LLD                     -                                      -
Cs-137              10             < LLD                     -                                      -
Ba-La-140            15              < LLD                     -                                      -
Ce-144              43             < LLD                     -                                      -
Sewer lift      H-3            2        300             < LLD                     -                                      -
Station (pCi/L)      GS            2 Mn-54                10             < LLD                       -                                      -
Fe-59                30             < LLD                     -                                      -
Co-58                10              < LLD                     -                                      -
Co-60                10             < LLD                     -                                      -
Zn-65                30              < LLD                     -                                      -
Zr-Nb-95            15             < LLD                       -                                      -
1-131                30              < LLD                       -                                      -
Cs-134              10              < LLD                      -                                      -
Cs-137              10              < LLD                      -                                     -
Ba-La-140            15              < LLD                      -                                     -
Ce-144              43              < LLD                      -                                      -
'GB = gross beta, GS =gamma scan.
b 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: (1) by name, and/or station code 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.
* 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.
E-7 
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* Northbroak,ll60061-1310 phone (847) 564-0700
* Northbroak,ll60061-1310 phone (847) 564-0700
* fax (847) 564-4517 Approved:
* fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc.
XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc. Midwest Laboratory Project No. 8010 PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation.
Midwest Laboratory Project No. 8010 Approved:
This report was prepared by Environmental, Inc., Midwest Laboratory.
 
ii TABLE OF CONTENTS Preface .......................................................................................................................................
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.
ii List ofT abies .......................................................................................................................
ii
iv List of Figures ......................................................................................................................
v


==1.0 INTRODUCTION==
TABLE OF CONTENTS Preface ....................................................................................................................................... ii List ofT abies ....................................................................................................................... iv List of Figures ...................................................................................................................... v


...........................................................................................................
==1.0    INTRODUCTION==
: ...........
...........................................................................................................:........... 1 2.0  
1 2.0  


==SUMMARY==
==SUMMARY==
  .............................................................................................  
  ..............................................................................................' ................................... 2 3.1   RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) ......................... 3 3.2       Program Design and Data Interpretation ................................................................ 3 3.3       Program Description ............................................................................................... 4 3.4       Program Execution ................................................................................................. 5 3.5       Program Modifications ............................................................................................ 5 3.6       Laboratory Procedures ........................................................................................... 6 3.7       Land Use Census ................................................................................................... 6 4.1   RESULTS AND DISCUSSION ............................................................................................ 7 4.2       Atmospheric Nuclear Detonations and Nuclear AcCidents ...................................... 7 4.3       Summary of Preoperational Data ........................................................................... 7 4.4       Program Findings ................................................................................................... 8 5.0   FIGURES AND TABLES ..................................................................................................... 12
.' ...................................
2 3.1 RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) .........................
3 3.2 Program Design and Data Interpretation  
................................................................
3 3.3 Program Description  
...............................................................................................
4 3.4 Program Execution  
.................................................................................................
5 3.5 Program Modifications  
............................................................................................
5 3.6 Laboratory Procedures  
...........................................................................................
6 3.7 Land Use Census ...................................................................................................
6 4.1 RESULTS AND DISCUSSION  
............................................................................................
7 4.2 Atmospheric Nuclear Detonations and Nuclear AcCidents  
......................................
7 4.3 Summary of Preoperational Data ...........................................................................
7 4.4 Program Findings ...................................................................................................
8 5.0 FIGURES AND TABLES .....................................................................................................
12  


==6.0 REFERENCES==
==6.0   REFERENCES==
...........................................................................................................................24 APPENDICES A    Interlaboratory Comparison Program Results .................................................................... A-1 B    Data Reporting Conventions ............................................................................................. B-1 C    Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .................................. :.......................... C-1 D    Sampling Location Maps ................................................................................................... D-1 E    Ground Water Monitoring Well Samples ................................... ;.. , .... :............................... E-1 3
 
LIST OF TABLES 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 The following tables are in the Appendices:
Appendix A A-1        Interlaboratory Comparison Program Results ................................................................A1-1 A-2        Thermoluminescentdosimeters (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    Resources Associates, Crosscheck Program Results (EML study replacement) ...................................................................................A7-1 Attachment A: Acceptance criteria for spiked samples .................................................... A2 Appendix C C-1        Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ..................................................................... C-2 Appendix E E-1      Sample Collection and Analysis Program, Ground Water, ............................................. E-6 E-2      Sampling Locations for Ground Water Monitoring Wells ................................................ E-6 E-3      Ground Water Monitoring Program Summary .................................................. ,............. E-7 E-4      Results of Analyses, Ground Water Monitoring Program ............................................... E-9 4


...........................................................................................................................
LIST OF FIGURES No.
24 APPENDICES A Interlaboratory Comparison Program Results ....................................................................
5-1      Offsite Ambient Radiation (TLDs), inner versus outer ring locations .......................................... 18 5-2      Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location .............................................................................................. 19 The following figures are located in the Appendices:
A-1 B Data Reporting Conventions
Appendix D D-1      Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................D-2 D-2      Sample collection and analysis program: TLD locations, OuterRing ..............................................................................................................................D-3 D-3      Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................D-4 D-4      Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations .......................................................................... D-5 D-5      Sample collection and analysis program: TLD locations,
.............................................................................................
        . ISFSI TLD Locations ................................................................................................................D-6 Appendix E E-1      Sample collection and analysis program:
B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area ..................................
Ground water, On-site monitoring well locations ..................................................................... E-8 5
: ..........................
C-1 D Sampling Location Maps ...................................................................................................
D-1 E Ground Water Monitoring Well Samples ...................................  
; .. , .... : ...............................
E-1 3 LIST OF TABLES 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 The following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results ................................................................
A1-1 A-2 Thermoluminescentdosimeters (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 Resources Associates, Crosscheck Program Results (EML study replacement)
...................................................................................
A 7-1 Attachment A: Acceptance criteria for spiked samples ....................................................
A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas .....................................................................
C-2 Appendix E E-1 Sample Collection and Analysis Program, Ground Water, .............................................
E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ................................................
E-6 E-3 Ground Water Monitoring Program Summary .................................................. , .............
E-7 E-4 Results of Analyses, Ground Water Monitoring Program ...............................................
E-9 4 LIST OF FIGURES No. 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations
..........................................
18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location ..............................................................................................
19 The following figures are located in the Appendices:
Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................
D-2 D-2 Sample collection and analysis program: TLD locations, OuterRing
..............................................................................................................................
D-3 D-3 Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................
D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations
..........................................................................
D-5 D-5 Sample collection and analysis program: TLD locations, . ISFSI TLD Locations
................................................................................................................
D-6 Appendix E E-1 Sample collection and analysis program: Ground water, On-site monitoring well locations  
.....................................................................
E-8 5


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


This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January -December, 2015. 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 Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2015.
Tabulations of the individual analyses made during the year are included in Part II of this report. The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota.
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.
Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971. 1 2.0  
Tabulations of the individual analyses made during the year are included in Part II of this report.
The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.
1
 
2.0  


==SUMMARY==
==SUMMARY==
The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant. Results for the year 2015 are summarized and discussed.
 
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant. 2 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment.
The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello 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 (TLD's). Sources of environmental radiation include the following:
Results for the year 2015 are summarized and discussed.
(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.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.
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 Monticello 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).
2
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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131.
3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello 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 (TLD's).
Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified:
Sources of environmental radiation include the following:
zirconium-95, cesium-137, cerium-144,  
(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.
?, and potassium-40.
In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.
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.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello 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.
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.
An additional interpretive technique involves analyses for specific radionuclides present in 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-
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-?
    ?, 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.
is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators.
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-? is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-1 03 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 of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
The other group quantified consists of niobium-95, ruthenium-1 03 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
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.
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 of corrosion products.
3
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.
3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.
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.
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.
3 3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision).
Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).
Maps of sampling locations are included in Appendix D. To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations.
Ambient gamma radiation is monitored at forty locations, using CaS0 4 :Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.
Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.
As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C).
Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131.
The samples are analyzed for iodine-131 and other gamma emitting isotopes.
Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.
Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged. Analysis is done for gamma-emitting isotopes.
One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector). Ambient gamma radiation is monitored at forty locations, using CaS0 4:Dy dosimeters with four sensitive areas at each location:
Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes. The Ground Water Monitoring Program is further described in Appendix E.
fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.
Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.
As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C). The samples are analyzed for iodine-131 and other gamma emitting isotopes.
Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged.
Analysis is done for gamma-emitting isotopes.
Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes.
The Ground Water Monitoring Program is further described in Appendix E. Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant and one downstream.
River water is collected weekly at two locations, one upstream of the plant and one downstream.
Monthly composites are analyzed for gamma-emitting isotopes.
Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Quarterly composites are analyzed for tritium. Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Quarterly composites are analyzed for tritium. The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.
Shoreline sediment is also collected from one downstream recreational location.
4
All samples are analyzed for gamma-emitting isotopes.
 
4 3.4 Program Execution The Program was executed as described in the preceding section with the following exceptions:
3.4 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Air Particulates I Air Iodine: M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station. M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
(1) Air Particulates I Air Iodine:
M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station.
M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.
M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report. M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015. The GFCI was tripped. The GFCI was reset. (2) Surface Water: Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.
M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report.
One TLD samples was found missing for the second quarter at Outer Ring location M-06B. Deviations from the program are summarized in Table 5.3. 3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015. 3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015.
The GFCI was tripped. The GFCI was reset.
(2) Surface Water:
Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.
One TLD samples was found missing for the second quarter at Outer Ring location M-06B.
Deviations from the program are summarized in Table 5.3.
3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015.
3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
5 Tritium concentrations are determined by liquid scintillation.
5
 
Tritium concentrations are determined by liquid scintillation.
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. Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.
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.
Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck)
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.
Programs.
: 3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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.
Results obtained in the crosscheck programs are presented in Appendix A. 3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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 2015 land use census was conducted between September 14 and September 24, 2015.
The 2015 land use census was conducted between September 14 and September 24, 2015. This is the third year using improved GPS software.
This is the third year using improved GPS software. The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.
The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.
There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.
There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.
The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways).
The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways). Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
6
6 4.1 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3. All 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. 4.2 Atmospheric Nuclear Detonations and Nuclear Accidents  
4.1 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.
' There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011. There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China. 4.3 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.
All 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.
Gross beta measurements in fallout averaged 20,600 pCi/m 3 in 1969 and 12,000 pCi/m 3 in 1970. These levels are reflected throughout the various media tested. In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 pCi/m 3. Present day levels have stabilized at around 0.025 pCi/m 3. Airborne radioiodine remained below detection levels of 0.03 pCi/m 3 In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored.
4.2       Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
In milk samples, low levels of Cs-137 and Sr-90 were detected.
There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
Cs-137 levels averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops. The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton.
4.3       Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 3                            3 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.
Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible.
In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3
However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.
pCi/m 3 . Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained 3
7 4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015. Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples. Ambient Radiation (TLD's) Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 -5 mi. distant from the Plant, at special interest areas and at four control locations.
below detection levels of 0.03 pCi/m In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.
The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively).
Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.
The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1). Year Inner Outer Rino Dose rate (mRem/91 davs) 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 2011 14.8 14.3 2012 16.2 15.5 2013 14.4 14.0 2014 13.5 12.9 2015 14.8 14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.
The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.
7
 
4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015.
Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples.
Ambient Radiation (TLD's)
Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.
distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively). The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).
Year                 Inner Rin~q            Outer Rino Dose rate (mRem/91 davs) 1999                   15.1                   14.3 2000                   15.1                   14.5 2001                   14.3                   13.7 2002                   15.9                   14.8 2003                   15.6                   15.0 2004                   16.0                   15.4 2005                   15.6                   15.2 2006                   16.5                   15.6 2007                   16.1                   15.1 2008                   15.2                   14.6 2009                   14.9                   14.4 2010                   14.7                   14.3 2011                   14.8                   14.3 2012                   16.2                   15.5 2013                   14.4                   14.0 2014                   13.5                   12.9 2015                   14.8                   14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates, Inner vs. Outer Ring locations 8
Average quarterly dose rates, Inner vs. Outer Ring locations 8
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at both indicator and control locations (0.030 and 0.028 pCi/m 3 ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below. Year Indicators Control Concentration (QCi/m 3) 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 2011 0.029 0.027 2012 0.032 0.031 2013 0.029 0.032 2014 0.027 0.028 2015 0.030 0.028 Average annual gross beta concentrations in airborne particulates.
 
Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015. Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at 3
Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.070 pCilm 3 for the indicator locations and 0.066 pCilm 3 for the control locations.
both indicator and control locations (0.030 and 0.028 pCi/m ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below.
All other gamma-emitting isotopes were below their respective LLD limits. Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples. 9 River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.
Year             Indicators           Control 3
Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1999 2.2 2008 2.1 2000 2.5 2009 2.3 2001 2.5 2010 2.9 2002 2.9 2011 2.2 2003 3.0 2012 2.4 2004 2.7 2013 2.6 2005 2.8 2014 2.8 2006 2.1 2015 2.3 2007 2.8 Average annual concentrations; Gross beta in drinking water. Well Water At the four indicator and control locations, tritium was below the detection limit for all samples. Gamma isotopic results were also below detection limits. The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.
Concentration (QCi/m   )
Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available.
1999                 0.023               0.025 2000                 0.027               0.026 2001                 0.027               0.026 2002                 0.028               0.028 2003                 0.027               0.027 2004                 0.024               0.024 2005                 0.025               0.025 2006                 0.024               0.025 2007                 0.027               0.028 2008                 0.028               0.029 2009                 0.029               0.030 2010                 0.026               0.026 2011                 0.029               0.027 2012                 0.032               0.031 2013                 0.029               0.032 2014                 0.027               0.028 2015                 0.030               0.028 Average annual gross beta concentrations in airborne particulates.
With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.
Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015.
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 AI-Salih, 1955) was detected in all samples, 3                                          3 with an average activity of 0.070 pCilm for the indicator locations and 0.066 pCilm for the control locations. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples.
9
 
River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.
Year             Gross Beta (pCi/L)                   Year             Gross Beta (pCi/L) 1999                     2.2                         2008                     2.1 2000                     2.5                         2009                     2.3 2001                     2.5                         2010                     2.9 2002                     2.9                         2011                     2.2 2003                     3.0                         2012                     2.4 2004                     2.7                         2013                     2.6 2005                     2.8                         2014                     2.8 2006                     2.1                         2015                     2.3 2007                     2.8 Average annual concentrations; Gross beta in drinking water.
Well Water At the four indicator and control locations, tritium was below the detection limit for all samples.
Gamma isotopic results were also below detection limits.
The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.
Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.
A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.
A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.
Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September.
Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September. Flesh was separated from the bones and analyzed by gamma spectroscopy. Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits.
Flesh was separated from the bones and analyzed by gamma spectroscopy.
There was no indication of a plant effect.
Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits. There was no indication of a plant effect. 10 Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy.
10
All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect. Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes.
 
Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition.
Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy. All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect.
Naturally-occurring beryllium-?
Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition. Naturally-occurring beryllium-? and potassium-40 were also detected. There was no indication of a plant effect.
and potassium-40 were also detected.
Groundwater Monitoring Program (On-site monitoring wells)
There was no indication of a plant effect. Groundwater Monitoring Program (On-site monitoring wells) Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite. See Appendix E for full Groundwater monitoring well results and discussion.
Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite.
Gamma isotopic measurements were below detection limits. Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.
See Appendix E for full Groundwater monitoring well results and discussion.
Gamma isotopic measurements were below detection limits.
Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.
Storm Water Run-off (on-site)
Storm Water Run-off (on-site)
One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015. ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations.
One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015.
Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected.
ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations. Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected. Neutron dosimetry uses the different responses from two lithium 6      10 borate TLDs, one depleted of Li and 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive). The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016.
Neutron dosimetry uses the different responses from two lithium borate TLDs, one depleted of 6 Li and 10 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive).
11
The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016. 11 5.0 FIGURES AND TABLES 12 Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant. Collection Location Type and Medium No. Codes (and Type) a Frequency b REMP Ambient radiation(TLDs) 40 M-01A-M-14A, M-018-M-168 C/Q M-01 S -M-06S, M-01 C -M-04C ISFSI Ambient radiation (TLDs) 20 ISFSI-1 to ISFSI-16, C/Q Neutron Control A, 8, C, D C/Q 13 1-01 to 1-13 C/Q Airborne Particulates 5 M-1 (C), M-2, M-3, M-4, M-5 crw Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 crw Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year Surface water 2 M-S(C), M-9 Gf\N Drinking water M-14 Gf\N Well water 4 M-11, M-12, M-55, M-43(C) GIQ Fish 2 M-S(C), M-9 G/SA (two species, edible portion) Periphyton or invertebrates 2 M-S(C), M-9 G/SA Shoreline sediment 3 M-S(C), M-9, M-15 G/SA a Location codes are defined in Table 5.2. 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.
5.0 FIGURES AND TABLES 12
 
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.
Collection   Analysis Location                           Type and    Type and Medium                                   No.               Codes (and Type)     a                 Frequency   b Frequency  c REMP Ambient radiation(TLDs)                 40     M-01A- M-14A, M-018- M-168                             C/Q       Ambient gamma M-01 S - M-06S, M-01 C - M-04C ISFSI Ambient radiation (TLDs)               20   ISFSI-1 to ISFSI-16,                                     C/Q       Neutron Dose Neutron Control A, 8, C, D                               C/Q 13   1-01 to 1-13                                             C/Q       Ambient Gamma Airborne Particulates                         5     M-1 (C), M-2, M-3, M-4, M-5                             crw       G8, GS (QC of each location)
Airborne Iodine                               5     M-1(C), M-2, M-3, M-4, M-5                             crw       1-131 Pasture grass, Vegetation       d             3     M-41, M-42, M-43(C)                                   3x/year     GS Surface water                                 2     M-S(C), M-9                                             Gf\N     GS(MC), H-3(QC)
Drinking water                                       M-14                                                   Gf\N     G8(MC), I-131(MC)
GS (MC), H-3 (QC)
Well water                                     4     M-11, M-12, M-55, M-43(C)                               GIQ       H-3, GS Fish                                           2     M-S(C), M-9                                           G/SA       GS (two species, edible portion)
Periphyton or invertebrates                   2     M-S(C), M-9                                           G/SA       GS Shoreline sediment                             3     M-S(C), M-9, M-15                                     G/SA       GS a Location codes are defined in Table 5.2. 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.
c Analysis type is coded as follows: GB =gross beta, GS =gamma spectroscopy, H-3 =tritium, 1-131 = iodine-131.
c Analysis type is coded as follows: 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.
Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Pasture grass and vegetation collections added to supplement dairy sampling.
d Pasture grass and vegetation collections added to supplement dairy sampling.
13 Analysis Type and Frequency c Ambient gamma Neutron Dose Ambient Gamma G8, GS (QC of each location) 1-131 GS GS(MC), H-3(QC) G8(MC), I-131(MC)
13
GS (MC), H-3 (QC) H-3, GS GS GS GS Table 5.2. Sampling locations, Monticello Nuclear Generating Plant. Distance and Direction Code Type a Collection Site Sample Type b from Reactor M-1 c Air Station M-1 AP,AI 11.0 mi@ 307"/NW M-2 Air Station M-2 AP,AI 0.8 mi@ 140&deg;/SE M-3 Air Station M-3 AP,AI 0.6 mi@ 104&deg;/ESE M-4 Air Station M-4 AP,AI 0.8 mi@ 147"/SSE M-5 Air Station M-5 AP,AI 2.6 mi@ 134&deg;/SE M-8 c Upstream of Plant Intake SW, SS, BO, F < 1 000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1 000' downstream M-11 City of Monticello ww 3.3 mi@ 127"/SE M-12 Plant Well #11 ww 0.26 mi@ 252&deg;/WSW M-14 City of Minneapolis ow 37.0 mi@ 132&deg;/SE M-15 Montissippi Park ss 1.27 mi@ 114&deg;/ESE M-27 Highest 0/Q garden 1.15 mi@ 148&deg;/SSE M-41 Training Center VE 0.8 mi@ 151&deg;/SSE M-42 Biology Station Road VE 0.6 mi@ 134&deg;/SE M-43 c lmholte Farm VE,WW 12.3 mi@ 313&deg;/NW M-55 Hasbrouck Residence ww 1.60 mi@ 255&deg;/WSW 14 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant. Distance and Code Type* Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi@ 353&deg;/N M-02A Sherburne Ave. So. TLD 0.79 mi@ 23&deg;/NNE M-03A Sherburne Ave. So. TLD 1.29 mi@ 56&deg;/NE M-04A Biology Station Road TLD 0.5 mi@ 92&deg;/E M-05A Biology Station Road TLD 0.48 mi @ 122&deg; /ESE M-06A Biology Station Road TLD 0.54 mi@ 138&deg;/SE M-07A County Road 75 TLD 0.47 mi@ 158&deg;/SSE M-08A County Road 75 TLD 0.45 mi@ 175&deg;/S M-09A County Road 75 TLD 0.38 mi@ 206&deg;/SSW M-10A County Road 75 J'LD 0.38 mi@ 224&deg;/SW M-11A County Road 75 TLD 0.4 mi@ 237"/WSW M-12A County Road 75 TLD 0.5 mi@ 262&deg;/W M-13A North Boundary Road TLD 0.89 mi@ 322&deg;/NW M-14A North Boundary Road TLD 0.78 mi@ 335&deg;/NNW Approximately 4 to 5 miles Distant from the Plant M-01B 11?'h Street TLD 4.65 mi@ 01&deg;/N M-02B County Road 11 TLD 4.4 mi@ 18"/NNE M-03B County Road 73 & 81 TLD 4.3 mi@ 51&deg;/NE M-04B County Road 73 (196th St.) TLO 4.2 mi@ 67"/ENE M-05B City of Big Lake TLD 4.3 mi@ 89&deg;/E M-06B County Road 14 and 1 96th St. TLD 4.3 mi@ 117"/ESE M-07B Monticello Industrial Drive TLD 4.3 mi@ 136&deg;/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi@ 162&deg;/SSE M-09B Weinand Farm TLD 4.7 mi@ 178&deg;/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi@ 204&deg;/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi@ 228&deg;/SW M-12B Lake Maria State Park TLD 4.2 mi@ 254&deg;/WSW M-13B Bridgewater Station TLD 4.1 mi@ 270&deg;/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi@ 289&deg;/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi@ 309&deg;/NW M-16B Sand Plain Research Farm TLD 4.4 mi@ 341&deg;/NNW 15 Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant. Code Type a Collection Site Special Interest Locations M-01S M-02S M-03S M-04S M-OSS M-06S M-01C c M-02C c M-03C c M-04C c ISFSI TLD Locations ISFSI-1 ISFSI-2 ISFSI-3 ISFSI-4 ISFSI-5 ISFSI-6 ISFSI-7 ISFSI-8 ISFSI-9 ISFSI-10 ISFSI-11 ISFSI-12 ISFSI-13 ISFSI-14 ISFSI-15 ISFSI-16 Neutron Control A Neutron Control B Neutron Control C Neutron Control D c c c c Osowski Fun Market Krone Residence Big Oaks Park Pinewood School Rivercrest Christian Academy Monticello Public Works Kirchenbauer Farm County Roads 4 and 15 County Rd 19 and Jason Ave. Maple Lake Water Tower ISFSI-1 (neutron) and 1-01 (gamma) ISFSI-2 (neutron) and 1-02 (gamma) ISFSI-3 (neutron) and 1-03 (gamma) ISFSI-4 (neutron) and 1-04 (gamma) ISFSI-5 (neutron) and 1-05 (gamma) ISFSI-6 (neutron) and 1-06 (gamma) ISFSI-7 (neutron) and 1-07 (gamma) ISFSI-8 (neutron) and 1-08 (gamma) ISFSI-9 (neutron) and 1-09 (gamma) ISFSI-10 (neutron) and 1-10 (gamma) ISFSI-11 (neutron) and 1-11 (gamma) ISFSI-12 (neutron) and 1-12 (gamma) ISFSI-13 (neutron) and 1-13 (gamma) ISFSI-14 (neutron)
 
ISFSI-15 (neutron)
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
ISFSI-16 (neutron) a "C" denotes control location.
Distance and Direction Code        Type a      Collection Site                          Sample Type b from Reactor M-1           c          Air Station M-1                          AP,AI              11.0 mi@ 307"/NW M-2                      Air Station M-2                          AP,AI                  0.8 mi@ 140&deg;/SE M-3                      Air Station M-3                           AP,AI                0.6 mi@ 104&deg;/ESE M-4                      Air Station M-4                          AP,AI                0.8 mi@ 147"/SSE M-5                      Air Station M-5                          AP,AI                 2.6 mi@ 134&deg;/SE M-8            c          Upstream of Plant Intake                  SW, SS, BO, F          < 1000' upstream M-9                      Downstream of Plant Discharge            SW, SS, BO, F      < 1000' downstream M-11                      City of Monticello                        ww                    3.3 mi@ 127"/SE M-12                      Plant Well #11                            ww                0.26 mi@ 252&deg;/WSW M-14                      City of Minneapolis                      ow                  37.0 mi@ 132&deg;/SE M-15                    Montissippi Park                          ss                1.27 mi@ 114&deg;/ESE M-27                    Highest 0/Q garden                                            1.15 mi@ 148&deg;/SSE M-41                      Training Center                          VE                  0.8 mi@ 151&deg;/SSE M-42                      Biology Station Road                      VE                    0.6 mi@ 134&deg;/SE M-43          c          lmholte Farm                            VE,WW              12.3 mi@ 313&deg;/NW M-55                      Hasbrouck Residence                      ww                1.60 mi@ 255&deg;/WSW 14
All other locations are indicators.
 
b Sample Codes: AP Airborne particulates AI Airborne Iodine BS Bottom (river) sediments BO Bottom organisms OW Drinking Water Distance and Sample Typeb Direction from Reactor TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD F sw ss TLD VE ww 0.66 mi@ 241WvSW 0.5 mi@ 220&deg;/SW 1.53 mi@ 103&deg;/ESE 2.3 mi@ 131 &deg;/SE 3.0 mi@ 118&deg;/ESE 2.6 mi@ 134&deg;/SE 11.5 mi@ 323&deg;/NW 11.2 mi @4r/NE 11.6 mi@ 130&deg;/SE 10.3 mi@ 226&deg;/ SW NE corner of ISFSI North side of ISFSI, center NW corner of ISFSI West side of ISFSI, middle West side of ISFSI, at center of array SW corner of ISFSI South side of ISFSI, center SE corner of ISFSI East side of ISFSI, at center of array East side of ISFSI, middle OCA fence south, on exit road OCA fence middle, on exit road OCA fence north, on exit road Posted with TLD M12A Posted with TLD M1 OA Posted with TLD M02S Posted with TLD M03C Posted with TLD M04C Posted with TLD M02C Posted with TLD M01 C Fish River Water Shoreline Sediments Thermoluminescent Dosimeter Vegetation I vegetables Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields. 16 Table 5.3 Missed Collections and Analyses.
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
Distance and Code          Type*        Collection Site                        Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A                        Sherburne Ave. So.                    TLD                    0.75 mi@ 353&deg;/N M-02A                        Sherburne Ave. So.                     TLD                  0.79 mi@ 23&deg;/NNE M-03A                        Sherburne Ave. So.                     TLD                   1.29 mi@ 56&deg;/NE M-04A                        Biology Station Road                  TLD                       0.5 mi@ 92&deg;/E M-05A                        Biology Station Road                  TLD               0.48 mi @ 122&deg; /ESE M-06A                        Biology Station Road                   TLD                 0.54 mi@ 138&deg;/SE M-07A                        County Road 75                        TLD               0.47 mi@ 158&deg;/SSE M-08A                        County Road 75                        TLD                   0.45 mi@ 175&deg;/S M-09A                        County Road 75                         TLD               0.38 mi@ 206&deg;/SSW M-10A                        County Road 75                         J'LD                0.38 mi@ 224&deg;/SW M-11A                        County Road 75                         TLD               0.4 mi@ 237"/WSW M-12A                        County Road 75                         TLD                    0.5 mi@ 262&deg;/W M-13A                        North Boundary Road                   TLD                 0.89 mi@ 322&deg;/NW M-14A                        North Boundary Road                   TLD               0.78 mi@ 335&deg;/NNW Approximately 4 to 5 miles Distant from the Plant M-01B                       11?'h Street                           TLD                     4.65 mi@ 01&deg;/N M-02B                       County Road 11                         TLD                   4.4 mi@ 18"/NNE M-03B                       County Road 73 & 81                   TLD                     4.3 mi@ 51&deg;/NE M-04B                       County Road 73 (196th St.)             TLO                   4.2 mi@ 67"/ENE M-05B                       City of Big Lake                       TLD                       4.3 mi@ 89&deg;/E M-06B                       County Road 14 and 196th St.           TLD                 4.3 mi@ 117"/ESE M-07B                       Monticello Industrial Drive           TLD                   4.3 mi@ 136&deg;/SE M-08B                       Residence, Hwy 25 & Davidson Ave.     TLD                 4.6 mi@ 162&deg;/SSE M-09B                       Weinand Farm                           TLD                     4.7 mi@ 178&deg;/S M-10B                       Reisewitz Farm, Acacia Ave.           TLD                 4.2 mi@ 204&deg;/SSW M-11B                       Vanlith Farm, 97th Ave.               TLD                   4.0 mi@ 228&deg;/SW M-12B                       Lake Maria State Park                 TLD               4.2 mi@ 254&deg;/WSW M-13B                       Bridgewater Station                   TLD                     4.1 mi@ 270&deg;/W M-14B                       Anderson Residence, Cty Rd. 111       TLD               4.3 mi@ 289&deg;/WNW M-15B                       Red Oak Wild Bird Farm                 TLD                   4.3 mi@ 309&deg;/NW M-16B                       Sand Plain Research Farm               TLD                 4.4 mi@ 341&deg;/NNW 15
 
Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant.
Distance and Code             Type a         Collection Site                                 Sample Typeb            Direction from Reactor Special Interest Locations M-01S                             Osowski Fun Market                              TLD                          0.66 mi@ 241WvSW M-02S                             Krone Residence                                  TLD                              0.5 mi@ 220&deg;/SW M-03S                            Big Oaks Park                                    TLD                            1.53 mi@ 103&deg;/ESE M-04S                            Pinewood School                                  TLD                                2.3 mi@ 131 &deg;/SE M-OSS                            Rivercrest Christian Academy                    TLD                              3.0 mi@ 118&deg;/ESE M-06S                            Monticello Public Works                          TLD                               2.6 mi@ 134&deg;/SE M-01C                c          Kirchenbauer Farm                                TLD                            11.5 mi@ 323&deg;/NW M-02C                c          County Roads 4 and 15                           TLD                                11.2 mi @4r/NE M-03C                c          County Rd 19 and Jason Ave.                      TLD                              11.6 mi@ 130&deg;/SE M-04C                c           Maple Lake Water Tower                          TLD                            10.3 mi@ 226&deg;/ SW ISFSI TLD Locations ISFSI-1                        ISFSI-1 (neutron) and 1-01 (gamma)               TLD                              NE corner of ISFSI ISFSI-2                        ISFSI-2 (neutron) and 1-02 (gamma)               TLD                    North side of ISFSI, center ISFSI-3                        ISFSI-3 (neutron) and 1-03 (gamma)               TLD                            NW corner of ISFSI ISFSI-4                        ISFSI-4 (neutron) and 1-04 (gamma)               TLD                    West side of ISFSI, middle ISFSI-5                        ISFSI-5 (neutron) and 1-05 (gamma)               TLD        West side of ISFSI, at center of array ISFSI-6                        ISFSI-6 (neutron) and 1-06 (gamma)               TLD                            SW corner of ISFSI ISFSI-7                        ISFSI-7 (neutron) and 1-07 (gamma)               TLD                    South side of ISFSI, center ISFSI-8                        ISFSI-8 (neutron) and 1-08 (gamma)               TLD                              SE corner of ISFSI ISFSI-9                        ISFSI-9 (neutron) and 1-09 (gamma)               TLD        East side of ISFSI, at center of array ISFSI-10                        ISFSI-10 (neutron) and 1-10 (gamma)             TLD                      East side of ISFSI, middle ISFSI-11                        ISFSI-11 (neutron) and 1-11 (gamma)             TLD                OCA fence south, on exit road ISFSI-12                        ISFSI-12 (neutron) and 1-12 (gamma)             TLD              OCA fence middle, on exit road ISFSI-13                       ISFSI-13 (neutron) and 1-13 (gamma)             TLD                  OCA fence north, on exit road ISFSI-14                        ISFSI-14 (neutron)                               TLD                        Posted with TLD M12A ISFSI-15                       ISFSI-15 (neutron)                               TLD                        Posted with TLD M1 OA ISFSI-16                        ISFSI-16 (neutron)                              TLD                        Posted with TLD M02S Neutron Control A          c                                                      TLD                        Posted with TLD M03C Neutron Control B          c                                                      TLD                         Posted with TLD M04C Neutron Control C          c                                                      TLD                         Posted with TLD M02C Neutron Control D          c                                                      TLD                         Posted with TLD M01 C a  "C" denotes control location. All other locations are indicators.
b Sample Codes:            AP  Airborne particulates                                F      Fish AI  Airborne Iodine                                    sw      River Water BS  Bottom (river) sediments                            ss      Shoreline Sediments BO  Bottom organisms                                  TLD      Thermoluminescent Dosimeter OW  Drinking Water                                      VE      Vegetation I vegetables ww      Well Water c  Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.
16
 
Table 5.3 Missed Collections and Analyses.
All required samples were collected and analyzed as scheduled with the following exceptions:
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, 1-131 M-005 1/28/2015 Power loss at sample Power was reset station. sw Gamma M-008 January '15 Water frozen entire month; None no composite.
Collection               Reason for not Sample       Analysis     Location         Date or               conducting REMP           Plans for Preventing Type                                       Period                     as required                 Recurrence AP/AI     Beta, 1-131       M-005       1/28/2015             Power loss at sample           Power was reset station.
AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running due Replaced air sampler. to bad switch. sw Gamma M-008 February '15 Water frozen entire month; None no composite.  
sw         Gamma           M-008       January '15         Water frozen entire month;               None no composite.
*.c sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None APIA I Beta, 1-131 M-002 5/6/2015 Air sampler not running. Replaced air sampler. TLD Gamma M-06B 2nd Qtr '15 TLD missing in field. Replaced TLD APIA I Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped ResetGFCI sw Gamma M-008 12/30/15 Water frozen None 17 Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
AP/AI     Beta, 1-131       M-002         2/4/2015         Air sampler not running due     Replaced air sampler.
20 l -lnnerRing
to bad switch.
--a-Outer Ring 19 18 17 16 15 (/) >> 14 ro "0 0) (i E 13 I 0 I v v \ I/; v r--v 0 r....... 11---1 V; y-""' v 3-1\ \Y 12 11 10 0) 0 N C') """ li) CD 1'-co 0) 0 N (') """ li) 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 0 0 0 N N N N N N N N N N N N N N N N 18 Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
sw         Gamma           M-008       February '15       Water frozen entire month;               None no composite.
0.035 0.033 0.031 0.029 0.027 0.025 :&sect; 0.023 0 D. 0.021 0.019 0.017 0.015 I -Indicators (M-2, 3, 4, 5) -o--Controi(M-1) ly l/l\ /I \ \ \ v/ '\ f/ \ \ I \ /1 I / / \ l) )---1 v Ol Ol Ol I I 0 0 0 N 0 0 N N 0 0 N 1\ I;/ \ v ' I ' (') 0 0 N "<!" 0 0 N I{) (() 0 0 0 0 N N 19 D 0 N (() 0 0 N Ol 0 0 N v 0 0 N (') 0 N I I I I{) 0 N Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*
                                                                                          *.c sw         Gamma           M-008           3/4/15                   Water frozen                   None sw         Gamma           M-008         3/11/15                   Water frozen                   None APIA I     Beta, 1-131       M-002         5/6/2015           Air sampler not running.       Replaced air sampler.
TLD (Inner Ring, Gamma 56 General Area at Site Boundary) mRem/91 days) TLD (Outer Ring, Gamma 63 4-5 mi. distant) mRem/91 days) TLD (Special Gamma 24 Interest Areas) mRem/91 days) TLD (Control)
TLD       Gamma           M-06B       2nd Qtr '15           TLD missing in field.           Replaced TLD APIA I     Beta, 1-131       M-004         6/10/15                   GFCI tripped                 Reset GFCI AP/AI     Beta, 1-131       M-004       6/24/2015                   GFCI tripped               ResetGFCI sw         Gamma           M-008         12/30/15                   Water frozen                   None 17
Gamma 16 mRem/91 days) Airborne GB 256 Particulates (pCi/rn 3) GS 20 Be-7 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-141 Ce-144 Airborne Iodine 1-131 256 (pCi/m 3) Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) Docket No. 50-263 ------------------
 
Reporting Period January-December, 2015 Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean(F)" Mean (F)0 Mean (F)0 Routine Ran gee Locationd Rangec Rangec Results* Direct Radiation 3.0 14.8 (56/56) M-11A, County Rd 75, 17.1 (4/4) (See Control 0 ( 9.6-19.6) 0.4 mi @ 250&deg;/WSW (15.8-19.6) below.) 3.0 14.2 (63/63) M-148 16.6 (4/4) (See Control 0 ( 11.0-19.6) 4.5 mi@ 228&deg;/NW (14.7-19.6) below.) 3.0 14.7 (24/24) M-04S 16.4 (4/4) (See Control 0 ( 9.4-18.8) 2.3 mi@ 132&deg;/SE (14.4-17.6) below.) 3.0 None M-02C 17.5 (4/4) 15.3 (16/16) 0 11.2 mi@ 47"/NE (15.9-20.3) ( 11.8-20.3)
Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
Airborne Pathway 0.002 0.030 (204/204)
20                                                                   l -
M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 (0.007-0.088) 2.6 rni@ 134&deg;/SE (0.009-0.088)
                                                                              --a-lnnerRing Outer Ring 19 18 17 I 0 16
(0.008-0.062) 0.015 0.070 (16/16) M-5, Air Station 0.073 (4/4) 0.066 (4/4) 0 (0.049-0.087) 2.6 rni@ 134&deg;/SE (0.049-0.087)
                          ~    v     ~    v                                 I/;I~
(0.043-0.077) 0.0008 < LLD --< LLD 0 0.0008 < LLD --< LLD 0 0.0009 < LLD --< LLD 0 0.0019 < LLD --< LLD 0 0.0014 < LLD --< LLD 0 0.0013 < LLD --< LLD 0 0.0085 < LLD --< LLD 0 0.0010 < LLD --< LLD 0 0.0010 < LLD --< LLD 0 0.0026 < LLD --< LLD 0 0.0020 < LLD --< LLD 0 0.0046 < LLD --< LLD 0 0.03 < LLD --< LLD 0 20 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*
I y- v r-- 0 \    v                 r.......
River Water (pCi/L) H-3 8 GS 22 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce'-144 Drinking Water GB 12 (pCi/L) 1-131 12 H-3 4 GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Well Water H-3 16 (pCi/L) GS 16 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) *Docket No. ..;5;..;0-...;2;;.;6;..;3
v~
______ _ Reporting Period January-December,2015 Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLDb Mean (F)0 Mean (F)" Mean (F)0 Routine Range* Locationd Range* Range* Results* Waterborne Pathway 500 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 15 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 15 < LLD --< LLD 0 39 < LLD --< LLD 0 1.0 2.3 (12112) M-14, Minneapolis 2.3 (12/12) None 0 (1.2-3.5) 37.0 mi.@ 132&deg; /SE (1.2-3.5) 1.0 < LLD --None 0 500 < LLD --None 0 10 < LLD --None 0 30 < LLD --None 0 10 < LLD --None 0 10 < LLD --None 0 30 < LLD --None 0 15 < LLD --None 0 10 < LLD --None 0 10 < LLD --None 0 15 < LLD --None 0 35 < LLD --None 0 500 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 30 < LLD --< LLD 0 15 < LLD --< LLD 0 10 < LLD --< LLD 0 10 < LLD --< LLD 0 15 < LLD --< LLD 0 49 < LLD --< LLD 0 21 Table 5.4 Radiological Environmental Monitoring Program Summarw Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses" Invertebrates GS 4 (pCilg wet) Be-7 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-144 Shoreline GS 6 Sediments Be-7 (pCi/g dry) K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Docket No. ...;5...;;0...:-2;;.;6...;;3
15  11---1
___ ,_. __ _ Reporting Period January-December, 2 015 Wright, Minnesota ( County, State ) Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLD b Mean (F)' Mean (F)' Mean (F)' Routine Range' Locationd Range' Range' Results" Waterborne Pathway 1.49 < LLD --< LLD 0 1.91 < LLD --< LLD 0 0.088 < LLD --< LLD 0 0.24 < LLD --< LLD 0 0.145 < LLD --< LLD 0 0.085 < LLD --< LLD 0 0.18 < LLD --< LLD 0 0.23 < LLD --< LLD 0 0.217 < LLD --< LLD 0 0.55 < LLD --< LLD 0 0.076 < LLD --< LLD 0 0.085 < LLD --< LLD 0 1.35 < LLD --< LLD 0 0.39 < LLD --< LLD 0 0.33 < LLD --< LLD 0 -0.10 10.24 (4/4) M-08, Upstream 11.55 (2/2) 11.55 (2/2) 0 (9.49-1 0.54) < 1000' of discharge (11.53-11.58)
                  ~\YV;
(11.53-11.58) 0.021 < LLD --< LLD 0 0.076 < LLD --< LLD 0 0.026 < LLD --< LLD 0 0.017 < LLD --< LLD 0 0.044 < LLD --< LLD 0 0.051 < LLD --< LLD 0 0.052 < LLD --< LLD 0 0.041 < LLD --< LLD 0 0.13 < LLD --< LLD 0 0.017 < LLD --< LLD 0 0.021 0.029 (2/4) M-09, Downstream
                                                                      ~
-< LLD 0 (0.024-0.034)
(/)
< 1000' of discharge
ro 14
-0.21 < LLD --< LLD 0 0.13 < LLD --< LLD 0 22 Table 5.4 Radiological Environmental Monitoring Program Summary Monticello Nuclear Generating Plant Docket No. 50-263 Name of Facility Location of Facility Wright, Minnesota
          ~
--,---=-----:---
                                                        ""' ~ 3-1\         ~
Reporting Period January-December, 2015 ( County, State ) Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)" (Units) Analyses*
                                                                                      ~~
Ran gee Locationd Ran gee Rangec Ingestion Pathway Vegetation GS 9 (Pasture Grass, Mn-54 0.014 < LLD --< LlD Weeds, Leaves) Fe-59 0.033 < LLD --< LLD Co-58 0.014 < LLD --< LLD (pCi/gwet)
  "0
Co-60 0.019 < LLD --< LLD Zn-65 0.029 < LLD --< LLD Nb-95 0.020 < LLD --< LLD 1-131 0.043 < LLD --< LLD Cs-134 0.015 < LLD -< LLD Cs-137 0.014 < LLD --< LLD Fish GS 8 (pCi/g wet) K-40 0.10 3.39 (4/4) M-09, Downstream 3.39 (4/4) 3.31 (4/4) -(3.08-3.71)
  ~
< 1000' of discharge (3.08-3.71)
0)
(2.56-3.65)
(i E  13 12 11 10
Mn-54 0.025 < LLD --< LLD Fe-59 0.056 < LLD --< LLD Co-58 0.025 < LLD --< LLD Co-60 0.025 < LLD --< LLD Zn-65 0.070 < LLD --< LLD Zr-Nb-95 0.031 < LLD --< LLD Cs-134 0.025 < LLD --< LLD Cs-137 0.020 < LLD --< LLD Ba-La-140 0.122 < LLD --< LLD Ce-144 0.141 < LLD --< LLD
: 0)     0   ~  N   C')       li)   CD   1'-   co       0) 0 ~    N   (')           li) 0)
* GB =gross beta, GS =gamma scan. b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample. c 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:
0) 0 0   0 0 0 0
(1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
0 0     """
0 0
0 0
0 0
0 0
0 0
0 0 0N 0   ~
0
                                                                                    ~
0       0"""  0N
          ~      N   N   N   N     N   N     N     N     N         N     N   N   N       N 18
 
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
                                                                          -  11- - Indicators (M-2, 3, 4, 5) 0.035 I  - o - - Controi(M-1)
I 0.033 0.031 ly ~
                                                                                              \
0.029                                                         l/l\            /I \        \
I I
                                                              ~    v/                                      \
                                                                        '\~v/ f/I                  \
                          /1 ~                            I    /
                                                                                                        \
                                                                                                          \  ~
0.027 v
0.025 l)
I
                    )---1 1\\ v ' I;/          I I                                  '
0.023
:&sect; 0
D.
0.021 0.019 0.017 0.015 Ol    0        N    (')  "<!"  I{)   (()     I'-  (()  Ol  0                      (')            I{)
Ol     0     0 0
0    0     0     0     0       D    0   0   ~                      ~              ~
Ol    0         0   0     0     0     0       0   0   0   0                      0               0
            ~      N    N  N   N    N    N    N        N    N    N    N                     N               N 19
 
Table 5.4     Radiological Environmental Monitoring Program Summary Name of Facility         Monticello Nuclear Generating Plant                    Docket No.        50-263 Location of Facility    Wright, Minnesota                                      Reporting Period ------------------
January-December, 2015
( County, State )
Indicator                  Location with Highest                  Control  Number Sample            Type and                    Locations                      Annual Mean                      Locations    Non-Type              Number of        LLDb      Mean(F)"                                        Mean (F) 0      Mean (F) 0  Routine (Units)           Analyses*                    Ran gee              Locationd                Rangec            Rangec    Results*
Direct Radiation TLD (Inner Ring, Gamma             56    3.0    14.8 (56/56)     M-11A, County Rd 75,            17.1 (4/4)     (See Control    0 General Area at                                    ( 9.6-19.6)      0.4 mi @ 250&deg;/WSW            (15.8-19.6)        below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma            63    3.0      14.2 (63/63)              M-148                  16.6 (4/4)    (See Control    0 4-5 mi. distant)                                  ( 11.0-19.6)      4.5 mi@ 228&deg;/NW              (14.7-19.6)        below.)
mRem/91 days)
TLD (Special      Gamma          24    3.0      14.7 (24/24)              M-04S                  16.4 (4/4)    (See Control    0 Interest Areas)                                    ( 9.4-18.8)        2.3 mi@ 132&deg;/SE            (14.4-17.6)        below.)
mRem/91 days)
TLD (Control)     Gamma          16    3.0         None                  M-02C                  17.5 (4/4)     15.3 (16/16)    0 mRem/91 days)                                                         11.2 mi@ 47"/NE            (15.9-20.3)     ( 11.8-20.3)
Airborne Pathway Airborne        GB            256  0.002  0.030 (204/204)       M-5, Air Station          0.031 (51/51)   0.028 (52/52)    0 Particulates                                  (0.007-0.088)       2.6 rni@ 134&deg;/SE          (0.009-0.088)   (0.008-0.062)
(pCi/rn 3)
GS            20 Be-7          0.015    0.070 (16/16)         M-5, Air Station          0.073 (4/4)       0.066 (4/4)    0 (0.049-0.087)       2.6 rni@ 134&deg;/SE           (0.049-0.087)   (0.043-0.077)
Mn-54        0.0008          < LLD                    -                      -              < LLD      0 Co-58          0.0008        < LLD                    -                       -               < LLD      0 Co-60          0.0009        < LLD                    -                      -               < LLD      0 Zn-65          0.0019        < LLD                    -                      -              < LLD      0 Zr-Nb-95      0.0014        < LLD                    -                      -               < LLD      0 Ru-103        0.0013        < LLD                    -                      -              < LLD      0 Ru-106        0.0085        < LLD                    -                      -              < LLD      0 Cs-134        0.0010        < LLD                    -                       -              < LLD      0 Cs-137        0.0010        < LLD                    -                      -              < LLD      0 Ba-La-140    0.0026        < LLD                    -                      -              < LLD      0 Ce-141        0.0020        < LLD                    -                      -              < LLD      0 Ce-144        0.0046        < LLD                   -                       -               < LLD       0 Airborne Iodine          1-131    256    0.03        < LLD                   -                       -               < LLD       0 3
(pCi/m )
20
 
Table 5.4    Radiological Environmental Monitoring Program Summary Name of Facility        Monticello Nuclear Generating Plant                    *Docket No.      ..;5;..;0-...;2;;.;6;..;3_ _ _ _ _ __
Location of Facility    Wright, Minnesota                                      Reporting Period    January-December,2015
( County, State )
Indicator                  Location with Highest                            Control      Number Sample             Type and                 Locations                        Annual Mean                              Locations          Non-Type             Number of     LLDb      Mean (F) 0                                      Mean (F)"                Mean (F) 0        Routine (Units)           Analyses*                  Range*                Locationd                Range*                      Range*        Results*
Waterborne Pathway River Water (pCi/L)       H-3           8   500          < LLD                    -                      -                          < LLD          0 GS           22 Mn-54         10        < LLD                      -                      -                          < LLD          0 Fe-59         30        < LLD                      -                      -                          < LLD          0 Co-58         10        < LLD                      -                      -                          < LLD          0 Co-60         10        < LLD                      -                      -                          < LLD          0 Zn-65         30          < LLD                      -                       -                          < LLD          0 Zr-Nb-95       15        < LLD                      -                      -                          < LLD          0 Cs-134         10        < LLD                      -                      -                          < LLD          0 Cs-137         10        < LLD                      -                      -                          < LLD          0 Ba-La-140     15        < LLD                      -                      -                          < LLD          0 Ce'-144       39        < LLD                      -                      -                          < LLD          0 Drinking Water     GB           12   1.0      2.3 (12112)         M-14, Minneapolis            2.3 (12/12)                      None          0 (pCi/L)                                    (1.2-3.5)        37.0 mi.@ 132&deg; /SE            (1.2-3.5) 1-131        12  1.0        < LLD                      -                       -                           None          0 H-3            4  500        < LLD                      -                       -                           None          0 GS           12 Mn-54         10        < LLD                      -                      -                            None          0 Fe-59         30          < LLD                      -                      -                            None          0 Co-58         10        < LLD                      -                      -                            None          0 Co-60         10        < 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         35        < LLD                      -                      -                            None          0 Well Water        H-3          16  500          < LLD                      -                      -                          < LLD          0 (pCi/L)        GS            16 Mn-54          10        < LLD                      -                       -                           < LLD          0 Fe-59        30          < LLD                     -                       -                           < LLD         0 Co-58          10         < LLD                     -                       -                           < LLD         0 Co-60          10        < LLD                     -                       -                           < LLD         0 Zn-65          30          < LLD                     -                       -                         < LLD           0 Zr-Nb-95      15        < LLD                     -                       -                         < LLD           0 Cs-134        10        < LLD                     -                       -                           < LLD         0 Cs-137        10         < LLD                     -                       -                           < LLD         0 Ba-La-140      15         < LLD                     -                       -                           < LLD         0 Ce-144        49          < LLD                     -                       -                         < LLD           0 21
 
Table 5.4    Radiological Environmental Monitoring Program Summarw Name of Facility        Monticello Nuclear Generating Plant                  Docket No.      ...;5...;;0...:-2;;.;6...;;3_ _ _,_._ __
Location of Facility    Wright, Minnesota                                    Reporting Period    January-December, 2 015
( County, State )
Indicator              Location with Highest                              Control        Number Sample            Type and                  Locations                    Annual Mean                                Locations            Non-Type              Number of    LLD   b    Mean (F)'                                    Mean (F)'                  Mean (F)'            Routine (Units)          Analyses"                  Range'            Locationd                Range'                        Range'        Results" Waterborne Pathway Invertebrates      GS          4 (pCilg wet)          Be-7            1.49        < LLD                 -                       -                             < LLD           0 K-40            1.91        < LLD                 -                       -                             < LLD           0 Mn-54        0.088        < LLD                 -                       -                             < LLD           0 Fe-59          0.24        < LLD                 -                       -                             < LLD           0 Co-58        0.145        < LLD                 -                       -                             < LLD           0 Co-60        0.085        < LLD                 -                       -                             < LLD           0 Zn-65          0.18        < LLD                 -                       -                             < LLD           0 Zr-Nb-95        0.23        < LLD                 -                       -                             < LLD           0 Ru-103        0.217        < LLD                 -                       -                             < LLD           0 Ru-106          0.55        < LLD                 -                       -                             < LLD           0 Cs-134        0.076        < LLD                 -                       -                             < LLD           0 Cs-137        0.085        < LLD                 -                       -                             < LLD           0 Ba-La-140      1.35        < LLD                 -                       -                             < LLD           0 Ce-144          0.39        < LLD                 -                       -                             < LLD           0 Shoreline        GS          6 Sediments            Be-7            0.33        < LLD                 -                       -                             < LLD           0 (pCi/g dry)                                                            -
K-40           0.10    10.24 (4/4)      M-08, Upstream            11.55 (2/2)                11.55 (2/2)            0 (9.49-1 0.54)    < 1000' of discharge      (11.53-11.58)          (11.53-11.58)
Mn-54        0.021        < LLD                -                       -                             < LLD          0 Fe-59        0.076        < LLD                -                       -                             < LLD          0 Co-58        0.026        < LLD                -                       -                             < LLD          0 Co-60         0.017        < LLD                -                       -                             < LLD          0 Zn-65        0.044        < LLD                -                       -                             < LLD          0 Nb-95        0.051        < LLD                -                       -                             < LLD          0 Zr-95        0.052        < LLD                -                      -                             < LLD          0 Ru-103        0.041        < LLD                -                      -                            < LLD          0 Ru-106          0.13        < LLD                -                      -                            < LLD          0 Cs-134        0.017        < LLD                -                      -                            < LLD          0 Cs-137        0.021      0.029 (2/4)      M-09, Downstream                -                            < LLD          0 (0.024-0.034)     < 1000' of discharge            -
Ba-La-140      0.21        < LLD                 -                       -                             < LLD           0 Ce-144          0.13        < LLD                 -                       -                             < LLD           0 22
 
Table 5.4      Radiological Environmental Monitoring Program Summary Name of Facility        Monticello Nuclear Generating Plant                      Docket No.         50-263
                                                                                                                  --,---=-----:---
Location of Facility    Wright, Minnesota                                        Reporting Period    January-December, 2015
( County, State )
Indicator                  Location with Highest                    Control    Number Sample            Type and                    Locations                      Annual Mean                          Locations    Non-Type              Number of      LLDb        Mean (F) 0                                     Mean (F) 0         Mean (F)"  Routine (Units)          Analyses*                    Ran gee              Locationd                Ran gee            Rangec    Results*
Ingestion Pathway Vegetation        GS          9 (Pasture Grass,          Mn-54          0.014        < LLD                   -                         -               < LlD        0 Weeds, Leaves)            Fe-59          0.033        < LLD                   -                         -               < LLD       0 Co-58          0.014        < LLD                   -                         -               < LLD       0 (pCi/gwet)           Co-60          0.019        < LLD                    -                        -                < LLD        0 Zn-65          0.029        < LLD                    -                        -               < LLD        0 Nb-95          0.020        < LLD                   -                         -               < LLD       0 1-131          0.043        < LLD                   -                         -               < LLD       0 Cs-134          0.015        < LLD                                             -               < LLD       0 Cs-137          0.014        < LLD                   -                         -               < LLD       0 Fish          GS          8 (pCi/g wet)          K-40          0.10        3.39 (4/4)        M-09, Downstream              3.39 (4/4)          3.31 (4/4)    0
                                  -                 (3.08-3.71)      < 1000' of discharge          (3.08-3.71)        (2.56-3.65)
Mn-54        0.025          < LLD                   -                         -               < LLD       0 Fe-59        0.056          < LLD                   -                         -               < LLD       0 Co-58        0.025          < LLD                    -                        -                < LLD        0 Co-60        0.025          < LLD                    -                         -               < LLD       0 Zn-65        0.070          < LLD                    -                        -                < LLD        0 Zr-Nb-95      0.031          < LLD                   -                         -               < LLD       0 Cs-134        0.025          < LLD                   -                         -               < LLD       0 Cs-137        0.020        < LLD                    -                        -               < LLD        0 Ba-La-140      0.122        < LLD                    -                         -               < LLD        0 Ce-144        0.141        < LLD                    -                         -               < LLD        0
* GB =gross beta, GS =gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c 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: (1) by name, and/or station code 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.
* 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.
23 Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 
23


==6.0 REFERENCES==
==6.0 REFERENCES==
CITED Arnold, J. R. and H. A. AI-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, 276.
ATI Environmental, Inc., Midwest Laboratory.
____2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015.
_ _ _---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 2000 through 2015.
____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 1983 through 1999.
____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
_ _ _..,-1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
_ _ _..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
_ _ _ _.2009.            Quality Assurance Program Manual, Rev. 3, 14 November 2012.
_ _ _ _2009.            Quality Control Procedures Manual, Rev. 2, 08 July 2009.
_ _ _ _.2009.            Quality Control Program, Rev. 2, 12 November 2009.
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, Illinois, 369-382 ..
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46.
Northern States Power Company.
_ _ _..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.
____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.
24


CITED Arnold, J. R. and H. A. AI-Salih.
==6.0 REFERENCES==
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, 276. ATI Environmental, Inc., Midwest Laboratory.
CITED (continued)
____ 2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015. ___ ---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015. ____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Scannell, M. J., J. Giard, J. Raimondi. 2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 1983 through 1999. ____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1983 through 1999. ___ ..,-1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation)
U.S. Environmental Protection Agency.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1978 through 1982. ___ ..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation)
----=1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 1978 through 1982. ____ .2009. Quality Assurance Program Manual, Rev. 3, 14 November 2012. ____ 2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009. ____ .2009. Quality Control Program, Rev. 2, 12 November 2009. 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, Illinois, 369-382 .. National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46. Northern States Power Company. ___ ..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.
----:1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual,           Montgomery, Alabama (EPA-520/5-84-006).
____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007. 24 
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.
____2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
____.2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.
Minneapolis, Minnesota.
25


==6.0 REFERENCES==
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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2015 through December, 2015
 
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. 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.
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.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.
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 lists REMP specific analytical results from 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.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
Out-of-limit results are explained directly below the result.
A1
 
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S 8
LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES One standard deviation Analysis                                  Level                                        for single determination Gamma Emitters                            5 to 100 pCi/liter or kg                      5.0 pCi/liter
                                                > 100 pCilliter or kg                    5% of known value Strontium-89b                              5 to 50 pCilliter or kg                      5.0 pCi/liter
                                                > 50 pCi/liter or kg                    10% of known value Stronti um-90b                            2 to 30 pCi/liter or kg                      5.0 pCilliter
                                                > 30 pCi/liter or kg                    10% of known value Potassium-40                              ;::: 0.1 g/liter or kg                        5% of known value Gross alpha                                :5 20 pCi/liter                              5.0 pCi/liter
                                          > 20 pCi/liter                                25% of known value Gross beta                                :5 100 pCilliter                              5.0 pCi/liter
                                          > 100 pCi/liter                              5% of known value Tritium                                    :5 4,000 pCi/liter                            +/- 1o =
169.85 x (known) 0 ' 0933
                                          > 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 lodine-131,                                :5 55 pCilliter                              6 pCilliter lodine-129b                            >55 pCi/liter                                10% of known value Uranium-238,                              :5 35 pCi/liter                              6 pCi/liter Nickel-63b                              > 35 pCi/liter                                15% of known value Technetium-99b lron-55b                                  50 to 100 pCi/liter                          10 pCi/liter
                                          > 100 pCi/liter                              10% of known value Other Analyses b                                                                        20% of known value a  From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b  Laboratory limit.
A2
 
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
Concentration (pCi/L)
Lab Code          Date          Analysis          Laboratory          ERA                  Control Result  b        Result c              Limits            Acceptance ERW-1444          4/6/2015      Sr-89            59.71  +/- 5.44            63.20        51.10 -71.20                Pass ERW-1444          4/6/2015      Sr-90            43.41  +/- 2.43            41.90        30.80 - 48.10              Pass ERW-1448          4/6/2015      Ba-133            77.75  +/- 4.69            82.50        69.30 - 90.80              Pass ERW-1448          4/6/2015      Cs-134            68.82  +/- 3.08            75.70        61.80 - 83.30              Pass ERW-1448          4/6/2015      Cs-137            191.9  +/- 5.9            189.0        170.0 - 210.0              Pass ERW-1448          4/6/2015      Co-60            85.05  +/- 4.59            84.50        76.00 - 95.30              Pass ERW-1448          4/6/2015      Zn-65            196.0  +/- 12.0            203.0        183.0 -238.0                Pass ERW-1450          4/6/2015      Gr. Alpha        34.05  +/- 1.90            42.60        22.10-54.00                Pass ERW-1450          4/6/2015      G. Beta          26.93  +/- 1.12            32.90        21.30 - 40.60              Pass ERW-1453          4/6/2015      1-131            22.47  +/- 0.83            23.80        19.70 -28.30                Pass ERW-1456          4/6/2015      Ra-226              8.20  +/- 0.56            8.43        6.33-9.90                  Pass ERW-1456          4/6/2015      Ra-228              5.00  +/- 0.67            4.39        2.56 -6.01                Pass ERW-1456          4/6/2015      Uranium            5.98 +/- 0.31              6.59        4.99 -7.83                Pass ERW-1461          4/6/2015      H-3              3,254 +/- 180                3280        2,770 -3,620                Pass ERW-5528          10/5/2015      Sr-89            34.76  +/- 0.06            35.70        26.70 -42.50                Pass ERW-5528          10/5/2015      Sr-90            29.23  +/- 0.06            31.10        22.70 -36.10                Pass ERW-5531          10/5/2015      Ba-133            30.91  +/- 0.53            32.50        25.90 - 36.70              Pass ERW-5531          10/5/2015      Cs-134            57.40  +/- 2.57            62.30        50.69 - 68.50              Pass ERW-5531          10/5/2015      Cs-137            163.1  +/-4.8              157.0        141.0 -175.0                Pass ERW-5531          10/5/2015      Co-60            73.41  +/- 1.72            71.10        64.00 - 80.70              Pass ERW-5531          10/5/2015      Zn-65            138.9  +/- 5.7            126.0        113.0 -149.0                Pass ERW-5534          10/5/2015      Gr. Alpha        29.99  +/- 0.08            51.60        26.90 - 64.70              Pass ERW-5534          10/5/2015      G. Beta          27.52  +/- 0.04            36.60        24.10 - 44.20              Pass ERW-5537          10/5/2015      1-131            25.54    +/-0.60            26.30        21.90-31.00                Pass ERW-5540          10/5/2015      Ra-226              7.32  +/- 0.37            7.29        5.49 -8.63                Pass ERW-5540d          10/5/2015      Ra-228              7.80  +/- 0.02            4.25        2.46 -5.85                Fail ERW-5540*          10/5/2015      Ra-228              4.45  +/- 0.96              4.25        2.46 -5.85                Pass ERW-5540          10/5/2015      Uranium          53.30  +/- 0.55            56.20        45.70 - 62.40              Pass ERW-5543          10/5/2015      H-3            21,260    +/- 351          21,300        18,700-23,400                Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
* The result of reanalysis (Compare to original result, footnoted "e" above).
A1-1
 
TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code          Irradiation                  Known                Lab      Control Date    Description      Value              Result      Limits    Acceptance Environmental Inc.
2015-1            6/24/2015      30cm.          98.81        103.67 +/-6.05  69.20-128.50    Pass 2015-1            6/24/2015      30cm.          98.81        111.32+/-15.97  69.20 -128.50    Pass 2015-1            6/24/2015      60cm.          24.70          27.23 +/- 1.33 17.30-32.10      Pass 2015-1            6/24/2015      60cm.          24.70          26.98 +/-4.98  17.30-32.10      Pass 2015-1            6/24/2015    120 em.          6.18          6.71 +/- 1.77  4.30-8.00      Pass 2015-1            6/24/2015    120cm.            6.18          6.78 +/-0.38  4.30-8.00      Pass 2015-1            6/24/2015    120cm.            6.18          6.43 +/-2.00  4.30 -8.00      Pass 2015-1            6/24/2015    150cm.            3.95          4.13 +/-0.72  2.80-5.10      Pass 2015-1            6/24/2015    150cm.            3.95          4.12 +/-1.36  2.80-5.10      Pass 2015-1            6/24/2015    150cm.            3.95          4.50 +/- 1.51  2.80-5.10      Pass 2015-1            6/24/2015    180cm.            2.74          3.27 +/-0.28  1.90-3.60      Pass 2015-1            6/24/2015    180cm.            2.74          3.05 +/-1.11  1.90-3.60      Pass 2015-1            6/24/2015    180 em.          2.74          3.14 +/-0.18  1.90-3.60      Pass A2-1
 
TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards).                b mrem Lab Code            Irradiation                    Delivered          Reported            Performance c Date          Description    Dose                Dose              Quotient (P)        Acceptance  d Environmental, Inc.
2015-2              12/15/2015      Spike 1          138.0          118.5 +/-2.1                  -0.14              Pass 2015-2              12/15/2015      Spike 2          138.0          120.0 +/- 1.6                  -0.13              Pass 2015-2              12/15/2015 Spike 3                138.0          121.9 +/- 1.9                  -0.12              Pass 2015-2              12/15/2015 Spike 4                138.0          124.5 +/- 3.3                  -0.10              Pass 2015-2              12/15/2015 Spike 5                138.0          126.5 +/- 3.2                  -0.08              Pass 2015-2              12/15/2015 Spike 6                138.0          140.0 +/- 4.2                  0.01              Pass 2015-2              12/15/2015 Spike 7                138.0          128.2+/-1.2                    -0.07              Pass 2015-2              12/15/2015 Spike 8                138.0          128.0 +/- 4.0                  -0.07              Pass 2015-2              12/15/2015 Spike 9                138.0          124.9 +/-5.1                  -0.09              Pass 2015-2              12/15/2015 Spike 10              138.0          122.9 +/-3.0                  -0.11              Pass 2015-2              12/15/2015      Spike 11          138.0          123.3 +/- 3.0                  -0.11              Pass 2015-2              12/15/2015 Spike 12              138.0          119.0 +/- 3.4                  -0.14              Pass 2015-2              12/15/2015 Spike 13              138.0          123.0 +/-2.7                  -0.11              Pass 2015-2              12/15/2015 Spike 14              138.0          125.4 +/- 2.0                  -0.09              Pass 2015-2              12/15/2015 Spike 15              138.0          122.0 +/-3.1                  -0.12              Pass 2015-2              12/15/2015      Spike 16          138.0          120.8 +/- 2.0                  -0.12              Pass 2015-2              12/15/2015      Spike 17          138.0          118.8 +/- 1.1                  -0.14              Pass 2015-2              12/15/2015      Spike 18          138.0          117.0 +/-2.3                  -0.15              Pass 2015-2              12/15/2015 Spike 19              138.0          120.8 +/- 2.6                  -0.12              Pass 2015-2              12/15/2015 Spike 20              138.0          122.6 +/- 3.0                 -0.11              Pass Mean (Spike 1-20)                                                    123.4                        0.11              Pass Standard Deviation (Spike 1-20)                                        5.0                        0.04              Pass a  TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b  TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c  Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose.
d  Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
e Tables A2.1 and A2.2 assume 1 roentgen= 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015).
A2-2
 
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b    Date        Analysis  Laboratory results      Known        Control 2s, n=1 c            Activity    Limits d    Acceptance W-020315      2/3/2015    Ra-226      16.19+/-0.42              16.70    13.36-20.04        Pass W-021215      2/12/2015    Gr. Alpha    18.38 +/- 0.39            20.10    16.08-24.12        Pass W-021215      2/12/2015    Gr. Beta    27.98 +/- 0.32            30.90    24.72- 37.08      Pass SPW-687        2/27/2015    Ni-63        239.6 +/- 3.5            202.4    161.9 - 242.9      Pass SPAP-689      3/2/2015    Gr. Beta    42.37 +/- 3.50            43.61    34.89 - 52.33      Pass SPAP-691      3/2/2015    Cs-134        1.77 +/- 0.61            1.90    1.52 - 2.28      Pass SPAP-691      3/2/2015    Cs-137      83.02 +/- 2.60            97.20    77.76-116.64      Pass SPW-693        3/2/2015    Cs-134      44.30 +/- 2.53            53.40    42.72-64.08        Pass SPW-693        3/2/2015    Cs-137      74.82 +/- 3.50            73.80    59.04 - 88.56      Pass SPW-693        3/2/2015    Sr-89        87.45 +/- 3.62            87.48    69.98- 104.98      Pass SPW-693        3/25/2015    Sr-90        37.22 +/- 1.55            38.10    30.48 - 45.72      Pass SPMI-697      3/2/2015    Cs-134      96.67 +/- 7.74          107.00    85.60 - 128.40    Pass SPMI-697      3/2/2015    Cs-137      78.51 +/- 7.02            73.84    59.07 - 88.61      Pass SPMI-697      3/2/2015    Sr-89        72.98 +/- 4.86            87.48    69.98- 104.98      Pass SPMI-697      3/2/2015    Sr-90        39.17+/-1.51              38.10    30.48-45.72        Pass SPW-699        3/2/2015    H-3        59,592 +/- 703            58,445  46,756 -70,134      Pass W-031115      3/11/2015    Ra-226      13.73 +/- 0.35            16.70    13.36-20.04        Pass W-030215      3/2/2015      Ra-228      32.79 +/- 2.31            31.44    25.15-37.73        Pass SPF-1040      3/16/2015    Cs-134      787.5 +/- 9.2            840.0    672.0 - 1,008.0    Pass SPF-1040      3/16/2015    Cs-137      2,599 +/- 24              2,360    1,888 - 2,832      Pass SPW-1036      3/25/2015    Fe-55        1,792 +/- 63              1961    1,569 - 2,353      Pass SPW-1374      4/6/2015    U-238        46.03 +/- 2.25            41.70    25.02 - 58.38      Pass W-040815      4/8/2015    Gr. Alpha    20.18 +/-0.42            20.10    16.08-24.12        Pass W-040815      4/8/2015    Gr. Beta    29.70 +/- 0.33            30.90    24.72 - 37.08      Pass SPW-1038      4/13/2015    C-14        3,497 +/- 9              4,734    2,840 - 6,628      Pass W-2165        4/20/2015    H-3          5550 +/- 226              5,780  3,468 - 8,092      Pass W-2165        4/20/2015    Sr-89        90.70 +/- 8.20          108.70    65.22 -152.18      Pass W-2165        4/20/2015    Sr-90      76.80 +/- 2.00            75.90  45.54 - 106.26    Pass W-2165        4/20/2015    Cs-134      62.40 +/- 6.40            57.30    34.38 - 80.22      Pass W-2165        4/20/2015    Cs-137      91.30 +/- 7.70            84.00    50.40 - 117.60    Pass W-2392        4/13/2015    H-3          5032 +/- 214              5780    3468-8092        Pass W-2392        4/13/2015    Ni-63      222.4 +/- 3.8            202.0    121.2 - 282.8      Pass W-2392        4/13/2015    Cs-134      53.26 +/- 5.01            57.30    34.38 - 80.22      Pass W-2392        4/13/2015    Cs-137      91.90 +/-7.76              84.20  50.52- 117.88      Pass W-042415      4/24/2015    Ra-226      12.52 +/- 0.39            16.70  10.02 - 23.38      Pass W-050715      5n/2015      Gr. Alpha    19.05+/-0.41              20.10  12.06-28.14        Pass W-050715      5n/2015      Gr. Beta    27.30 +/- 0.32            30.90  18.54 - 43.26      Pass W-061215      6/12/2015    Gr. Alpha  20.72 +/- 0.44            20.10  12.06-28.14        Pass W-061215      6/12/2015    Gr. Beta    28.51 +/- 0.33            30.90  18.54-43.26        Pass U-2982        6/9/2015      Gr. Beta    500.1 +/- 5.1              604.0  362.4 - 845.6      Pass U-3200        6/9/2015      H-3          2229 +/- 424              2346    1408 - 3284      Pass W-70915        7/9/2015      Gr. Alpha    18.76 +/- 0.40            20.10    12.1-28.1        Pass W-70915        7/9/2015      Gr. Beta    29.71  +/- 0.33            30.90    18.5 -43.3      Pass SPAP-3859      7/21/2015    Gr. Beta    41.59  +/- 0.12            43.61  26.17-61.05        Pass SPAP-3861      7/21/2015    Cs-134        1.69 +/- 0.60              1.69    1.0-2.4        Pass A3-1


CITED (continued)
T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code    b        Date            Analysis            Laboratory results            Known              Control 2s, n=1 c              Activity            Limits d            Acceptance SPAP-3861            7/21/2015      Cs-137                  93.71 +/- 2.64              96.45          57.87 -135.03                Pass SPMI-3863            7/21/2015      Cs-134                  38.21 +/- 5.12              47.02          28.21 - 65.83                Pass SPMI-3863            7/21/2015      Cs-137                  78.65 +/- 7.94              73.18          43.91 - 102.45                Pass SPMI-3863            7/21/2015      Sr-90                  41.05 +/- 1.62              37.78          22.67 - 52.89                Pass SPW-3871            7/21/2015      Cs-134                  45.59 +/- 6.39              47.02          28.21 - 65.83                Pass SPW-3871            7/21/2015       Cs-137                 78.73 +/- 7.03               73.18         43.91 - 102.45               Pass SPW-3871             7/21/2015       Sr-90                   38.36 +/- 1.58               37.78         22.67 - 52.89                 Pass SPW-3873             7/21/2015       H-3                   60,034 +/- 671               57,199         34,319-80,079                 Pass SPW-3875             7/21/2015       Ni-63                   451.3 +/- 3.3               403.7         242.2 - 565.2                 Pass SPW-3877             7/21/2015       Tc-99                   483.0 +/- 8.3               539.1         323.5 -754.7                 Pass SPMI-3879           7/21/2015       C-14                   4,921 +/- 19                 4,736         2,842 - 6,630                 Pass SPS0-4037           7/21/2015       Ni-63                 42,458 +/- 309               40,370         24,222 -56,518                 Pass SPW-072515           7/17/2015       Ra-228                 35.48 +/- 3                 31.44         18.86 - 44.02                 Pass SPF-4104             7/29/2015       Cs-134                 661.5+/-115.9               740.0         444.0 - 1036.0               Pass SPF-4104             7/29/2015       Cs-137                 2,469 +/-59                 2,340         1 ,404 - 3,276               Pass SPW-81015           8/10/2015       Gr. Alpha               21.59 +/- 0.46               20.10         12.06-28.14                   Pass SPW-81015           8/10/2015       Gr. Beta               27.58 +/- 0.32               30.90         18.54 - 43.26                 Pass SPW-81315           8/13/2015       Ra-226                 15.05 +/- 0.36               16.70         10.02 - 23.38                 Pass SPW-90615           9/6/2015       Gr. Alpha               18.32 +/- 0.40             20.10         12.06-28.14                   Pass SPW-90615           9/6/2015       Gr. Beta               29.43 +/- 0.33             30.90         18.54 - 43.26                 Pass W-091415             9/14/2015       Gr. Alpha               19.35 +/- 0.51             20.10         12.06-28.14                   Pass W-091415             9/14/2015       Gr. Beta               31.53 +/- 0.35             30.90         18.54 - 43.26                 Pass W-100815             10/8/2015       Ra-228                 12.27 +/- 0.33             16.70         10.02 - 23.38                 Pass W-100615             10/6/2015       Gr. Alpha               20.62 +/- 0.43             20.10         12.06-28.14                   Pass W-100615             10/6/2015       Gr. Beta               29.35 +/- 0.33             30.90         18.54 - 43.26                 Pass W-5277               10/16/2015     H-3                     5,224 +/- 218               5,466         3,280 - 7,652                 Pass W-5277               10/16/2015     Cs-134                 99.40 +/- 6.64             99.20         59.52 - 138.88               Pass W-5277               10/16/2015     Cs-137                 89.60 +/- 6.64             83.20         49.92 - 116.48               Pass W-110415             11/4/2015       Ra-226                 12.27 +/- 0.33             16.70         10.02 - 23.38                 Pass W-111115             11/11/2015     Ra-228                 31.78 +/- 2.48             31.44         18.86 - 44.02                 Pass W-6086,6087         11/18/2015     H-3                   10,882   +/- 309             11,231         6,738 - 15,723               Pass W-6086,6087         11/18/2015     Cs-134                 92.98 +/- 7.29             96.25         57.75 - 134.75               Pass W-6086,6087         11/18/2015     Cs-137                 76.65 +/- 7.81             82.94         49.76 - 116.12               Pass W-112515             11/25/2015     Gr. Alpha               20.91 +/- 0.52             20.10         12.06-28.14                   Pass W-112515             11/25/2015     Gr. Beta               31.59 +/- 0.35             30.90         18.54 - 43.26                 Pass W-120715             12/7/2015       Fe-55                   2,431 +/- 97               2,319         1,391 -3,247                 Pass W-120815             12/8/2015       Gr. Alpha               20.72 +/- 0.43             20.10         12.06-28.14                   Pass W-120815             12/8/2015       Gr. Beta               29.50 +/- 0.33             30.90         18.54 - 43.26                 Pass W-121515             12/15/2015     Ra-226                 14.77 +/- 0.42             16.70         10.02 - 23.38                 Pass
Scannell, M. J., J. Giard, J. Raimondi.
2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN. 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.
____ 2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
____ .2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.
25 NOTE: APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS 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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported.
Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. January, 2015 through December, 2015 Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
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.
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. Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. 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 lists REMP specific analytical results from 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. Complete analytical data for duplicate analyses is available upon request. The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program. Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML). Attachment A lists the laboratory precision at the 1 sigma level for various analyses.
The acceptance criteria in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1 Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S LABORATORY PRECISION:
ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES 8 Analysis Gamma Emitters Strontium-89b Stronti u m-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-63b Technetium-99b lron-55b Other Analyses b Level 5 to 100 pCi/liter or kg > 100 pCilliter or kg 5 to 50 pCilliter or kg > 50 pCi/liter or kg 2 to 30 pCi/liter or kg > 30 pCi/liter or kg ;::: 0.1 g/liter or kg :5 20 pCi/liter
> 20 pCi/liter
:5 100 pCilliter > 1 00 pCi/liter
:5 4,000 pCi/liter
> 4,000 pCi/liter
;::: 0.1 pCi/liter
;::: 0.1 pCi/liter, gram, or sample :5 55 pCilliter
>55 pCi/liter
:5 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter > 1 00 pCi/liter a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit. A2 One standard deviation for single determination 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCilliter 1 0% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value +/- 1o = 169.85 x (known)0'0933 10% of known value 15% of known value 1 0% of known value 6 pCilliter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 -48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 -90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 -83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 -210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/- 4.59 84.50 76.00 -95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22.10-54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21.30 -40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 -36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 -68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 -80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 -64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 -44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21.90-31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540*
10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700-23,400 Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.
* The result of reanalysis (Compare to original result, footnoted "e" above). A1-1 TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental Inc. 2015-1 6/24/2015 30cm. 98.81 103.67 +/-6.05 69.20-128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32+/-15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23 +/- 1.33 17.30-32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30-32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.43 +/-2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.12 +/-1.36 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180cm. 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180cm. 2.74 3.05 +/-1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14 +/-0.18 1.90-3.60 Pass A2-1 TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards). b mrem Lab Code Irradiation Delivered Reported Date Description Dose Dose Environmental, Inc. 2015-2 12/15/2015 Spike 1 138.0 118.5 +/-2.1 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 2015-2 12/15/2015 Spike 3 138.0 121.9 +/- 1.9 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 2015-2 12/15/2015 Spike 9 138.0 124.9 +/-5.1 2015-2 12/15/2015 Spike 10 138.0 122.9 +/-3.0 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 2015-2 12/15/2015 Spike 15 138.0 122.0 +/-3.1 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 Mean (Spike 1-20) 123.4 Standard Deviation (Spike 1-20) 5.0 a TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) Performance c Quotient (P) -0.14 -0.13 -0.12 -0.10 -0.08 0.01 -0.07 -0.07 -0.09 -0.11 -0.11 -0.14 -0.11 -0.09
-0.12
-0.12 -0.14
-0.15
-0.12
-0.11 0.11 0.04 Acceptance d Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose-conventially true value) + conventially true value) where the conventially true value is the delivered dose. d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. e Tables A2.1 and A2.2 assume 1 roentgen=
1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20-Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015). A2-2 TABLE A-3. In-House "Spiked" Samples Lab Code b W-020315 W-021215 W-021215 SPW-687 SPAP-689 SPAP-691 SPAP-691 SPW-693 SPW-693 SPW-693 SPW-693 SPMI-697 SPMI-697 SPMI-697 SPMI-697 SPW-699 W-031115 W-030215 SPF-1040 SPF-1040 SPW-1036 SPW-1374 W-040815 W-040815 SPW-1038 W-2165 W-2165 W-2165 W-2165 W-2165 W-2392 W-2392 W-2392 W-2392 W-042415 W-050715 W-050715 W-061215 W-061215 U-2982 U-3200 W-70915 W-70915 SPAP-3859 SPAP-3861 Date Analysis 2/3/2015 Ra-226 2/12/2015 Gr. Alpha 2/12/2015 Gr. Beta 2/27/2015 Ni-63 3/2/2015 Gr. Beta 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Sr-89 3/25/2015 Sr-90 3/2/2015 Cs-134 3/2/2015 Cs-137 3/2/2015 Sr-89 3/2/2015 Sr-90 3/2/2015 H-3 3/11/2015 Ra-226 3/2/2015 Ra-228 3/16/2015 Cs-134 3/16/2015 Cs-137 3/25/2015 F e-55 4/6/2015 U-238 4/8/2015 Gr. Alpha 4/8/2015 Gr. Beta 4/13/2015 C-14 4/20/2015 H-3 4/20/2015 Sr-89 4/20/2015 Sr-90 4/20/2015 Cs-134 4/20/2015 Cs-137 4/13/2015 H-3 4/13/2015 Ni-63 4/13/2015 Cs-134 4/13/2015 Cs-137 4/24/2015 Ra-226 5n/2015 Gr. Alpha 5n/2015 Gr. Beta 6/12/2015 Gr. Alpha 6/12/2015 Gr. Beta 6/9/2015 Gr. Beta 6/9/2015 H-3 7/9/2015 Gr. Alpha 7/9/2015 Gr. Beta 7/21/2015 Gr. Beta 7/21/2015 Cs-134 Concentration (pCi/L)a Laboratory results 2s, n=1 c 16.19+/-0.42 18.38 +/- 0.39 27.98 +/- 0.32 239.6 +/- 3.5 42.37 +/- 3.50 1.77 +/- 0.61 83.02 +/- 2.60 44.30 +/- 2.53 74.82 +/- 3.50 87.45 +/- 3.62 37.22 +/- 1.55 96.67 +/- 7.74 78.51 +/- 7.02 72.98 +/- 4.86 39.17+/-1.51 59,592 +/- 703 13.73 +/- 0.35 32.79 +/- 2.31 787.5 +/- 9.2 2,599 +/- 24 1,792 +/- 63 46.03 +/- 2.25 20.18 +/-0.42 29.70 +/- 0.33 3,497 +/- 9 5550 +/- 226 90.70 +/- 8.20 76.80 +/- 2.00 62.40 +/- 6.40 91.30 +/- 7.70 5032 +/- 214 222.4 +/- 3.8 53.26 +/- 5.01 91.90 +/-7.76 12.52 +/- 0.39 19.05+/-0.41 27.30 +/- 0.32 20.72 +/- 0.44 28.51 +/- 0.33 500.1 +/- 5.1 2229 +/- 424 18.76 +/- 0.40 29.71 +/- 0.33 41.59 +/- 0.12 1.69 +/- 0.60 A3-1 Known Activity 16.70 20.10 30.90 202.4 43.61 1.90 97.20 53.40 73.80 87.48 38.10 107.00 73.84 87.48 38.10 58,445 16.70 31.44 840.0 2,360 1961 41.70 20.10 30.90 4,734 5,780 108.70 75.90 57.30 84.00 5780 202.0 57.30 84.20 16.70 20.10 30.90 20.10 30.90 604.0 2346 20.10 30.90 43.61 1.69 Control Limits d 13.36-20.04 16.08-24.12 24.72-37.08 161.9 -242.9 34.89 -52.33 1.52 -2.28 77.76-116.64 42.72-64.08 59.04 -88.56 69.98-104.98 30.48 -45.72 85.60 -128.40 59.07 -88.61 69.98-104.98 30.48-45.72 46,756 -70,134 13.36-20.04 25.15-37.73 672.0 -1 ,008.0 1,888 -2,832 1,569 -2,353 25.02 -58.38 16.08-24.12 24.72 -37.08 2,840 -6,628 3,468 -8,092 65.22 -152.18 45.54 -106.26 34.38 -80.22 50.40 -117.60 3468-8092 121.2 -282.8 34.38 -80.22 50.52-117.88 10.02 -23.38 12.06-28.14 18.54 -43.26 12.06-28.14 18.54-43.26 362.4 -845.6 1408 -3284 12.1-28.1 18.5 -43.3 26.17-61.05 1.0-2.4 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 -65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 -102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 -52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 -65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 -1 02.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 -52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 -565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 -6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 -44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 -1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1 ,404 -3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06-28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 -43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 -23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 -43.26 Pass W-091415 9/14/2015 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2015 Gr. Beta 31.53 +/- 0.35 30.90 18.54 -43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-100615 10/6/2015 Gr. Alpha 20.62 +/- 0.43 20.10 12.06-28.14 Pass W-100615 10/6/2015 Gr. Beta 29.35 +/- 0.33 30.90 18.54 -43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 -7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 -138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 -116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 -23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 -44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 -15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 -134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 -116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 -43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 -43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 -23.38 Pass
* Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
* Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c Results are based on single determinations.
b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s. NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-2 TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a) W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/-3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/- 5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 1 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5n/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMI-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 1 A4-1 TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc  
c Results are based on single determinations.
.. Criteria (4.66 cr) SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/- 0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.
NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.
A3-2
 
TABLE A-4. In-House "Blank" Samples 8
Concentration (pCi/L)
Lab Code     Sample           Date     Analysisb     Laboratory results (4.66a)         Acceptance Type                                     LLD           Activityc         Criteria (4.66 a)
W-020315     Water           2/3/2015 Ra-226         0.03         0.03 +/- 0.02 W-021215     Water           2/12/2015 Gr. Alpha     0.47         -0.37 +/- 0.30                 2 W-021215     Water           2/12/2015 Gr. Beta       0.76         -0.62 +/- 0.51                 4 SPW-686       Water           2/27/2015 Ni-63         2.36         -0.74 +/- 1.42                 20 SPAP-688     Air Particulate 3/2/2015 Gr. Beta     0.003       -0.001   +/- 0.002             0.01 SPAP-690     Air Particulate 3/2/2015 Cs-134       0.006       0.428   +/- 0.927             0.05 SPAP-690     Air Particulate 3/2/2015 Cs-137       0.006       -0.785   +/- 1.146             0.05 W-030215     Water           3/2/2015 Ra-228         0.76         0.22 +/- 0.38                 2 SPW-692       Water           3/2/2015 Cs-134         6.70         -1.57 +/- 3.55                 10 SPW-692       Water           3/2/2015 Cs-137         6.18         -0.15 +/-3.20                 10 SPW-692       Water           3/2/2015 Sr-89         0.61         -0.51 +/- 0.51                 5 SPW-692       Water           3/2/2015 Sr-90         0.60         0.38 +/- 0.33                 1 SPMI-696     Milk             3/2/2015 Cs-134         3.75         -0.25 +/- 2.24                 10 SPMI-696     Milk             3/2/2015 Cs-137         4.36         -0.25 +/- 2.24                 10 SPMI-696     Milk             3/2/2015 Sr-89         0.80         -0.40 +/- 0.84                 5 SPMI-696     Milk             3/2/2015 Sr-90         0.49         0.98 +/- 0.32                 1 SPW-698       Water           3/2/2015 H-3           144.0         28.6 +/- 88.9               200 SPW-1035     Water           3/16/2015 Fe-55         599.7         72.6 +/- 368.1             1000 SPW-1037     Water           3/16/2015 C-14           8.94         2.16 +/- 5.47               200 SPF-1039     Fish             3/16/2015 Cs-134       13.54         -1.00 +/- 6.80               100 SPF-1039     Fish             3/16/2015 Cs-137         9.80         4.87 +/- 7.00               100 W-040615     Water           4/6/2015 Ra-226         0.04         0.01 +/- 0.03                   2 W-1373       Water           4/6/2015 U-238         0.08         0.01 +/- 0.01                   1 W-1375       Water           4/6/2015 Pu-238         0.03         0.00 +/- 0.01 W-050715     Water           5/7/2015 Gr. Alpha     0.38         -0.10 +/- 0.25                 2 W-050715     Water           5n/2015   Gr. Beta       0.74         -0.14 +/- 0.51                 4 W-061215     Water           6/12/2015 Gr. Alpha     0.42         -0.10 +/- 0.29                 2 W-061215     Water           6/12/2015 Gr. Beta       0.75         -0.04 +/- 0.53                 4 SPW-3858     Water           7/21/2015 Gr. Beta     0.003       0.004 +/- 0.002                   2 SPAP-3860     Air Particulate 7/21/2015 Cs-134       0.011       0.010 +/- 0.005               0.05 SPAP-3860     Air Particulate 7/21/2015 Cs-137       0.009       0.000 +/- 0.005               0.05 SPMI-3862     Milk             7/21/2015 Cs-134         3.13         1.56+/-1.74                   10 SPMI-3862     Milk             7/21/2015 Cs-137         3.20         1.69 +/- 1.89                 10 SPMI-3862     Milk             7/21/2015 Sr-89         2.17         -1.30 +/- 2.05                   5 SPMI-3862     Milk             7/21/2015 Sr-90         0.90         0.74 +/- 0.50                   1 SPW-3870     Water           7/21/2015 Cs-134         3.01         0.71 +/- 1.66                 10 SPW-3870     Water           7/21/2015 Cs-137         3.94         0.81 +/- 1.86                 10 SPW-3870     Water           7/21/2015 Sr-89           2.28       -0.42 +/- 1.80                   5 SPW-3870     Water           7/21/2015 Sr-90         0.84         0.25 +/- 0.42                   1 A4-1
 
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code           Sample                 Date           Analysisb           Laboratory results (4.66cr)             Acceptance Type                                                         LLD             Activityc ..         Criteria (4.66 cr)
SPW-3872           Water                   7/21/2015       H-3               142.6           82.7 +/- 79.4                 200 SPW-3874           Water                   7/21/2015       Ni-63               2.98           0.77 +/- 1.82                   20 SPW-3876           Water                   7/21/2015     Tc-99                 5.49         -3.81 +/- 3.26                   10 SPW-3878           Water                   7/21/2015       C-14               17.06           8.52 +/- 10.54                 200 SPS0-4036           Soil                   7/21/2015       Ni-63             135.7           51.3 +/- 83.0               1000 SPF-4103           Fish                   7/29/2015       Cs-134             14.17         -37.70   +/- 9.67                 100 SPF-4103           Fish                   7/29/2015     Cs-137             12.39           1.13 +/-8.06                   100 W-081015           Water                   8/10/2015     Gr. Alpha             0.48         -0.10 +/- 0.33                     2 W-081015           Water                   8/10/2015       Gr. Beta             0.78         -0.18 +/- 0.54                     4 W-081815           Water                   8/18/2015       Ra-226               0.03           0.03 +/- 0.02                     2 W-090615           Water                   9/6/2015       Gr. Alpha           0.40           0.00 +/- 0.28                     2 W-090615           Water                   9/6/2015       Gr. Beta             0.77           0.22 +/- 0.54                     4 W-091415           Water                   9/14/2015       Gr. Alpha           0.41           0.10 +/- 0.30                     2 W-091415           Water                   9/14/2015       Gr. Beta             0.77           0.04 +/- 0.54                     4 W-100615           Water                   10/6/2015       Gr. Alpha           0.41         -0.15 +/- 0.27                     2 W-100615           Water                   10/6/2015       Gr. Beta             0.75         -0.12 +/- 0.52                     4 W-112515           Water                   11/25/2015     Gr. Alpha           0.42           0.05 +/- 0.30                     2 W-112515           Water                   11/25/2015     Gr. Beta             0.78         -0.31 +/- 0.54                     4 W-120815           Water                   12/8/2015       Gr. Alpha           0.42         -0.08 +/- 0.29                     2 W-120815           Water                   12/8/2015       Gr. Beta             0.76           0.17 +/-0.54                       4 W-121515           Water                   12/15/2015     Ra-226               0.01           0.01 +/- 0.01                     2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).
b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.
b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity
c Activity reported is a net activity result.
A4-2
 
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 8 Averaged Lab
1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.
1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.
A6-3 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/- 2.2 49.8 30.7-67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2-98.8.
A6-3
Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 -1 '130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 -50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/- 3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 -52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21.3-51.7 Pass ERAP-1091 3/16/2015 U-238 31.0 +/- 1.1 34.0 22.0-47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 -1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8-96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/- 0.8 58.4 36.9 -85.1 Pass ERS0-1098 3/16/2015 Am-241 157.1.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474-2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9  
 
+/- 86.9 4,430 2,670 -6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1 ,270 -2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180-7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1,140-1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810-14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806 -1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 -6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 -1 ,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1 '185 +/- 140 1,210 791-1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/- 948 3,890 1,230 -7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 -5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,41 0 -4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 -9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2-184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900-14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/- 266 4,340 2,650 -5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 -2,120 Pass A7-1 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*. Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060-2,150 Fail ERVE-1100 r 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060-2,150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/-27 2,650 1, 700 -3,440 Fail ERVE-1100 r 3/16/2015 Cs-134 2,554 +/- 49 2,650 1, 700 -3,440 Pass ERVE-1100&deg; 3/16/2015 Cs-137 1,248 +/- 29 1,810 1 ,310 -2,520 Fail ERVE-1100 r 3/16/2015 Cs-137 2,078 +/- 68 1,810 1 ,310 -2,520 Pass ERVE-11 00 e 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 -43,400 Fail ERVE-1100 r 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 -43,400 Pass ERVE-11 00 e 3/16/2015 Mn-54 <13.8 <300 0.0-300.0 Pass ERVE-1100 r 3/16/2015 Mn-54 <24.4 <300 0.0-300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/- 232 3,680 2,190 -5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570-5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/- 326 6,590 3,760-8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 -3,980 Pass ERVE-11 00 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 r 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0-61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/- 17 1,250 1 ,090 -1 ,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925-1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1 , 150 -1 , 630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 -100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 -90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 -232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/- 4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 -75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/- 136 1,180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 -1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 -1,210.0 Pass
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML). b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation).
Concentration (pCi/L) b Lab Code b   Date         Analysis         Laboratory           ERA         Control Result c         Result d         Limits       Acceptance ERAP-1091     3/16/2015     Am-241           46.8 +/- 2.2           49.8       30.7-67.4           Pass ERAP-1091     3/16/2015     Co-60             85.1 +/- 2.9           79.1       61.2-98.8.         Pass ERAP-1091     3/16/2015     Cs-134         825.6 +/- 34.7         909.0     578.0 - 1'130.0       Pass ERAP-1091     3/16/2015     Cs-137         1,312+/-12             1,170       879 - 1,540       Pass ERAP-1091     3/16/2015     Fe-55           760.6 +/- 48.2         836.0     259.0 - 1630.0       Pass ERAP-1091     3/16/2015     Mn-54             <2.7                 <50         0.0 - 50.0       Pass ERAP-1091     3/16/2015     Pu-238           51.0 +/- 3.9           52.1       35.7-68.5           Pass ERAP-1091     3/16/2015     Pu-239/240       38.3 +/- 1.3           40.3     29.20 - 52.70         Pass ERAP-1091     3/16/2015     Sr-90             95.3 +/- 11.4         96.6       47.2 - 145.0       Pass ERAP-1091     3/16/2015     U-233/234         29.0 +/- 1.2           34.3       21.3-51.7           Pass ERAP-1091     3/16/2015     U-238             31.0 +/- 1.1           34.0       22.0-47.0           Pass ERAP-1091     3/16/2015     Zn-65         1099.3 +/- 146.5         986.0     706.0 - 1360.0       Pass ERAP-1094     3/16/2015     Gr. Alpha         73.7 +/- 0.7           62.2       20.8-96.6           Pass ERAP-1094     3/16/2015     Gr. Beta         69.6 +/- 0.8           58.4       36.9 - 85.1         Pass ERS0-1098     3/16/2015     Am-241         157.1.8 +/- 209.6       1,500       878 - 1,950       Pass ERS0-1098     3/16/2015     Ac-228         1198.8 +/- 140.4       1,250       802 - 1,730       Pass ERS0-1098     3/16/2015     Bi-212         1420.1 +/-455.7         1,780       474-2,620         Pass ERS0-1098     3/16/2015     Bi-214         3466.9 +/- 86.9         4,430     2,670 - 6,380         Pass ERS0-1098     3/16/2015     Co-60         1779.8 +/-41.0           1,880   1,270 - 2,590         Pass ERS0-1098     3/16/2015     Cs-134         5204.6 +/- 64.5         6,390     4,180-7,680           Pass ERS0-1098     3/16/2015     Cs-137         1417.1 +/-41.9           1,490   1,140-1,920           Pass ERS0-1098     3/16/2015     K-40           10,597 +/- 380         10,700   7,810-14,400         Pass ERS0-1098     3/16/2015     Mn-54           <62.2                 < 1000       0.0 - 1,000       Pass ERS0-1098     3/16/2015     Pb-212         1,032 +/- 41           1,230       806 - 1,710       Pass ERS0-1098     3/16/2015   Pb-214         3,629 +/- 93           4,530     2,640 - 6,760         Pass ERS0-1098     3/16/2015     Pu-238         942.9 +/- 128.8       998.0     600.0 - 1,380.0       Pass ERS0-1098     3/16/2015     Pu-239/240     1 '185 +/- 140           1,210       791-1,670         Pass ERS0-1098     3/16/2015     Sr-90           1,724+/-125             1,940       740 - 3,060       Pass ERS0-1098     3/16/2015     Th-234         3,666 +/- 948           3,890   1,230 - 7,320         Pass ERS0-1098     3/16/2015     U-233/234       3,474 +/- 226           3,920   2,400 - 5,020         Pass ERS0-1098     3/16/2015   U-238           3,620 +/- 232           3,890   2,41 0 - 4,930       Pass ERS0-1098     3/16/2015   Zn-65           7,362 +/- 145           7,130   5,680 - 9,470         Pass ERW-1095       3/16/2015   Gr. Alpha         93.4 +/- 11.5         119.0     42.2- 184.0         Pass ERW-1095       3/16/2015   Gr. Beta       145.2 +/- 4.8           158.0     90.5-234.0         Pass ERW-1110       3/16/2015   H-3           10,573 +/- 78           10,300   6,900- 14,700         Pass ERVE-1100     3/16/2015   Am-241         4,537 +/- 266           4,340   2,650 - 5, 770       Pass ERVE-1100     3/16/2015   Cm-244         1,338 +/- 146           1,360       666 - 2,120       Pass A7-1
Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).
 
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.
Concentration (pCi/L) b Lab Code     b     Date             Analysis               Laboratory           ERA             Control Result c         Result d           Limits         Acceptance ERVE-1100 e         3/16/2015         Co-60                 1,030 +/- 29           1,540       1,060-2,150             Fail ERVE-1100 r         3/16/2015         Co-60                 1,684 +/- 48           1,540       1,060-2,150             Pass ERVE-1100 e         3/16/2015         Cs-134                 1,615 +/-27           2,650       1, 700 - 3,440           Fail ERVE-1100 r         3/16/2015         Cs-134                 2,554 +/- 49           2,650       1, 700 - 3,440         Pass ERVE-1100&deg;         3/16/2015         Cs-137                 1,248 +/- 29           1,810       1,310 - 2,520           Fail ERVE-1100 r         3/16/2015         Cs-137                 2,078 +/- 68           1,810       1 ,310 - 2,520         Pass ERVE-11 00 e       3/16/2015         K-40                 22,037 +/- 463         30,900       22,300 - 43,400           Fail ERVE-1100 r         3/16/2015         K-40                 34,895 +/- 764         30,900       22,300 - 43,400         Pass ERVE-11 00 e       3/16/2015         Mn-54                 <13.8                 <300             0.0-300.0           Pass ERVE-1100 r         3/16/2015         Mn-54                 <24.4                 <300             0.0- 300.0         Pass ERVE-1100           3/16/2015         Pu-238                 3,232 +/- 232         3,680       2,190 - 5,040           Pass ERVE-1100           3/16/2015         Pu-239/240             3,606 +/- 240         4,180       2,570-5,760             Pass ERVE-1100           3/16/2015         Sr-90                 6,023 +/- 326         6,590       3,760-8,740             Pass ERVE-1100           3/16/2015         U-233/234             2,653 +/- 153           3,150       2,070 -4,050           Pass ERVE-1100           3/16/2015         U-238                 2,717 +/- 163           3,130       2,090 - 3,980           Pass ERVE-11 00 e       3/16/2015         Zn-65                 <94.6                 1,090           786 - 1,530           Fail ERVE-1100 r         3/16/2015         Zn-65                 1,306 +/- 75           1,090           786 - 1,530         Pass ERW-1103           3/16/2015         Am-241                   47.1 +/-4.0           46.0         31.0-61.7             Pass ERW-1103           3/16/2015         Co-60                 1,217 +/- 17           1,250       1,090 - 1,460           Pass ERW-1103           3/16/2015         Cs-134                 1,121 +/- 18           1,260           925- 1,450           Pass ERW-1103           3/16/2015         Cs-137                 1,332 +/- 31           1,360       1,150 - 1,630           Pass ERW-1103           3/16/2015         Mn-54                   <3.7               <100           0.00 - 100.00         Pass ERW-1103           3/16/2015         Pu-238                 54.5 +/- 1.6           72.4         53.6 - 90.1           Pass ERW-1103 9         3/16/2015         Pu-239/240           140.2 +/- 7.8         184.0       143.0 - 232.0           Fail ERW-3742h           9/27/2012         Pu-239/240             89.3 +/- 4.9           97.7         66.6 - 108.0         Pass ERW-1103           3/16/2015         U-233/234               56.5 +/- 6.4           61.8         46.4 - 79.7         Pass ERW-1103           3/16/2015         U-238                   58.4 +/- 5.8           61.3         46.7 - 75.2         Pass ERW-1103           3/16/2015         Zn-65                 1,191 +/- 136           1,180           984 - 1,490         Pass ERW-1103           3/16/2015         Fe-55                 1,149+/-144             1,070           638 - 1,450         Pass ERW-1103           3/16/2015         Sr-90                 860.0 +/- 37.0         912.0       594.0   - 1,210.0       Pass
* Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).
* Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.
* Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
Control limits are not provided.
* Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).
* Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above). 9 The results of reanalysis were outside the control limits (low). h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range. The results for ERW-37 42 were acceptable.
9 The results of reanalysis were outside the control limits (low).
No reason for the unacceptable results for ERW-37 42 was determined.
h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range.
A7-2 APPENDIX B. DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample. 3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. : 3.1 Individual results: For two analysis results; x 1 +/- s 1 and x 2 +/- s 2 Reported result: x +/- s; where x == (1/2) (x 1 + x 2) and s == (1/2) + s; 3.2. Individual results: < L 1 , < L 2 Reported result: < L, where L == lower of L 1 and L 2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x L; < L otherwise.
The results for ERW-37 42 were acceptable. No reason for the unacceptable results for ERW-37 42 was determined.
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 standard deviation would not be the average of quarterly standard deviations.
A7-2
The average x and standard deviation "s" of a set of n numbers x 1 , x 2 ... xn are defined as follows: -1 X =r; LX s-\jnT 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.
 
APPENDIX B.             DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample.
3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. :
3.1       Individual results:   For two analysis results; x 1 +/- s 1 and x2 +/- s 2 Reported result:       x +/- s; where x == (1/2) (x 1 + x2 ) and s == (1/2) ~ s~ + s; 3.2.     Individual results:     < L1 , < L2        Reported result: < L, where L == lower of L1 and L2 3.3.     Individual results:     x +/- s, < L         Reported result:         x +/- 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 ~nnual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1 , x2 . . . xn are defined as follows:
X
                                  -   1
                                      =r; LX               s-
                                                              -A~  \jnT 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.
4.4 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 number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged.
4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers 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 number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45. B-1 APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a background in unrestricted areas . Air (pCi/m 3) Water (pCi/L) -3 Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 c Potassium-40 4,000 Gross alpha 2 Gross beta 10 6 Tritium 1 X 10 a b Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number 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. Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway. c A natural radionuclide.
B-1
C-1 APPENDIX D Sampling Location Maps D-1
 
,---1 I I II I i I I Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2) D-2 Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2) D-3 Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2) D-4
APPENDIX C Table C-1.     Maximum permissible concentrations of radioactivity in air and water above natural a
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background in unrestricted areas .
< z j 0 * / r J I ' I (
3 Air (pCi/m     )                                                   Water (pCi/L)
* J <J) a. E ro (f) -c:: <J) E '6 <J) (f) 0 /:/ " b N b 0 0 .,--Figure D-4, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Well Water and Shoreline sampling locations. (Table 5.2) D-5 Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2) D-6 APPENDIX E Ground Water Monitoring Well Samples E-1
                          -3 Gross alpha         1 X 10                                                   Strontium-89                 8,000 Gross beta         1                                                       Strontium-90                   500 b                 -1 lodine-131         2.8 X 10                                               Cesium-137                   1,000 Barium-140                   8,000 lodine-131                   1,000 c
Potassium-40                 4,000 Gross alpha                       2 Gross beta                       10 6
Tritium                     1 X 10 a
Taken from Table 2 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-1
 
APPENDIX D Sampling Location Maps D-1
 
1 I
I III iI I
Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2)
D-2
 
Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2)
D-3
 
Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2)
D-4
 
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0 Figure D-4, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Well Water and Shoreline sampling locations. (Table 5.2)
D-5
 
Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2)
D-6
 
APPENDIX E Ground Water Monitoring Well Samples E-1


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


This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January -December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.
This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January - December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.
E-2 2.0  
E-2
 
2.0  


==SUMMARY==
==SUMMARY==
Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07. This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater.
 
The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater.
Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07.
Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report. The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8'). Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1. Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.
This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater. The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater. Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or AREOR(REM~ffiports.
Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report.
The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8').
Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1.
Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.
Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.
Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.
The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized.
The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized. In practice, samples were counted to an even lower level, approximately 150 pCi/L.
In practice, samples were counted to an even lower level, approximately 150 pCi/L. Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property.
Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property. Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L.
Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L. Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public. No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015. A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4. E-3 3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.
Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public.
3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program. Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.
No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015.
3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:
A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4.
Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity. Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells. 3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015. E-4 3.5 Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911 +/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1. Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume. Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A. The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank. The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.
E-3
E-5 Table E-1. Sample Collection and Analysis Program, Ground Water. Medium Number Sample Codes Collection type Analysis Type Ground Water 32 MW-1, MW-2, MW-3, MW-4, Grab H-3 Quarterly MW-98, MW-11, MW-12A, MW-128, Ground Water 82 8 MW-9A, MW-10, MW-13A, Grab H-3 Monthly MW-138, MW-14, MW-15A MW-158, Ground Water 4 MW-5, MW-6, MW-7, MW-8 Grab H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well. Table E-2. Sampling locations for Ground Water Monitoring Wells. Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 sw Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9A 0.1 310 NW Ground Water M-51 MW-98 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-11 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-128 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-138 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW Ground Water M-53 MW-15A 0.14 14 NNE Ground Water M-54 MW-158 0.14 14 NNE E-6 Table E-3. Ground Water Monitoring Program Summary. Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses' Groundwater H-3 118 Monitoring Wells (pCi/L) Stormwater H-3 4 Runoff (pCi/L) GS 4 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 Ce-144 Sewer lift H-3 2 Station (pCi/L) GS 2 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 Ba-La-140 Ce-144 Monticello Nuclear Generating Plant Wright, Minnesota ( County, State ) Indicator
 
,. Locations LLDb Mean (F)0 Range* 300 603 (47/118) (144-6493) 300 157(1/4) 10 < LLD 30 < LLD 10 < LLD 10 < LLD 30 < LLD 15 < LLD 30 < LLD 10 < LLD 10 < LLD 15 < LLD 43 < LLD 300 < LLD 10 < LLD 30 < LLD 10 < LLD 10 < LLD 30 < LLD 15 < LLD 30 < LLD 10 < LLD 10 < LLD 15 < LLD 43 < LLD Docket No. ...:5..:0...:-2:..:6...:.3-------,----
3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.
Reporting Period January-December, 2015 Location with Highest Annual Mean Mean (F)" Locationd Range* MW-9A, On-site, 1985 (10/13) 0.1 mi@310"/NW (182-6493)
3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.
SD-006 157(1/4) On-site ----------------------------------------------'GB = gross beta, GS =gamma scan. b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.
* 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:
3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:
(1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity.
Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells.
3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015.
E-4
 
3.5   Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911
    +/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1.
Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume.
Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A.
The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank.
The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.
E-5
 
Table E-1. Sample Collection and Analysis Program, Ground Water.
Medium       Number           Sample Codes               Collection type Analysis Type Ground Water       32       MW-1, MW-2, MW-3, MW-4,               Grab             H-3 Quarterly                 MW-98, MW-11, MW-12A, MW-128, 8
Ground Water       82       MW-9A, MW-10, MW-13A,                 Grab             H-3 Monthly                   MW-138, MW-14, MW-15A MW-158, Ground Water         4       MW-5, MW-6, MW-7, MW-8               Grab             H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well.
Table E-2. Sampling locations for Ground Water Monitoring Wells.
Sample Type       Vendor   Well         Distance from       Compass         Sector Code     Number       Stack (miles)       Heading from Stack Ground Water     M-33     MW-1         0.11                 299             WNW Ground Water     M-34     MW-2         0.14                 301             WNW Ground Water     M-35     MW-3         0.15                 305             NW Ground Water     M-36     MW-4         0.1                 25             NNE Ground Water     M-37     MW-5         0.1                 253             WSW Ground Water     M-38     MW-6         229 Feet             228             sw Ground Water       M-39     MW-7         0.2                 66             ENE Ground Water       M-40     MW-8         0.3                   150           SSE Ground Water       M-44     MW-9A         0.1                 310             NW Ground Water       M-51     MW-98         0.1                   310             NW Ground Water       M-45     MW-10         0.1                   292           WNW Ground Water       M-46     MW-11         0.1                   283           WNW Ground Water       M-47     MW-12A       0.1                   330             NW Ground Water       M-48     MW-128       0.1                   326             NW Ground Water       M-49     MW-13A       0.12                 316             NW Ground Water       M-50     MW-138       0.12                 316             NW Ground Water       M-52     MW-14         0.17                 306             NW Ground Water       M-53     MW-15A       0.14                 14             NNE Ground Water       M-54     MW-158       0.14                 14             NNE E-6
 
Table E-3. Ground Water Monitoring Program Summary.
Name of Facility         Monticello Nuclear Generating Plant                        Docket No.          ...:5..:0...:-2:..:6...:.3-------,----
Location of Facility    Wright, Minnesota                                          Reporting Period    January-December, 2015
( County, State )
Indicator                              Location with Highest Sample            Type and                      ,. Locations                                  Annual Mean 0
Type            Number of            LLDb            Mean (F)                                                      Mean (F)"
(Units)          Analyses'                            Range*                  Locationd                              Range*
Groundwater      H-3          118        300          603 (47/118)          MW-9A, On-site,                        1985 (10/13)
Monitoring Wells                                          (144-6493)          0.1 mi@310"/NW                            (182-6493)
(pCi/L)
Stormwater      H-3            4        300            157(1/4)                SD-006                                157(1/4)
Runoff                                                                          On-site (pCi/L)       GS            4 Mn-54                10              < LLD                     -                                      -
Fe-59                30             < LLD                     -                                      -
Co-58                10             < LLD                     -                                      -
Co-60                10             < LLD                     -                                      -
Zn-65                30             < LLD                       -                                      -
Zr-Nb-95            15              < LLD                       -                                      -
1-131                30             < LLD                     -                                      -
Cs-134              10             < LLD                     -                                      -
Cs-137              10             < LLD                     -                                      -
Ba-La-140            15              < LLD                     -                                      -
Ce-144              43             < LLD                     -                                      -
Sewer lift      H-3            2        300             < LLD                     -                                      -
Station (pCi/L)      GS            2 Mn-54                10             < LLD                       -                                      -
Fe-59                30             < LLD                     -                                      -
Co-58                10              < LLD                     -                                      -
Co-60                10             < LLD                     -                                      -
Zn-65                30              < LLD                     -                                      -
Zr-Nb-95            15             < LLD                       -                                      -
1-131                30              < LLD                       -                                      -
Cs-134              10              < LLD                      -                                      -
Cs-137              10              < LLD                      -                                     -
Ba-La-140            15              < LLD                      -                                     -
Ce-144              43              < LLD                      -                                      -
'GB = gross beta, GS =gamma scan.
b 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: (1) by name, and/or station code 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.
* 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.
E-7 
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Latest revision as of 23:07, 24 February 2020

Transmittal of 2015 Annual Radiological Environmental Operating Report
ML16133A383
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/12/2016
From: Gardner P
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-16-030
Download: ML16133A383 (102)


Text

(l JCcel Energy" Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 May 12, 2016 L-MT-16-030 10 CFR 50, Appendix I ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2015 Annual Radiological Environmental Operating Report Pursuant to 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3, IV.C and, in accordance with Monticello Nuclear Generating Plant (MNGP) Technical Specifications 5.6.1, the Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, is submitting the Annual Radiological Environmental Operating Report, under MNGP's "Radiological Environmental Monitoring Program," for year 2015.

Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

~~

Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, Resident Inspector, Monticello Minnesota Department of Commerce

ENCLOSURE 1 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1 - DECEMBER 31, 2015 100 Pages to Follow

Environmental, Inc.

I Midwest Laboratory 700 landw*hr Road

  • Northbroak,ll60061-1310 phone (847) 564-0700
  • fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

ii

TABLE OF CONTENTS Preface ....................................................................................................................................... ii List ofT abies ....................................................................................................................... iv List of Figures ...................................................................................................................... v

1.0 INTRODUCTION

...........................................................................................................:........... 1 2.0

SUMMARY

..............................................................................................' ................................... 2 3.1 RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) ......................... 3 3.2 Program Design and Data Interpretation ................................................................ 3 3.3 Program Description ............................................................................................... 4 3.4 Program Execution ................................................................................................. 5 3.5 Program Modifications ............................................................................................ 5 3.6 Laboratory Procedures ........................................................................................... 6 3.7 Land Use Census ................................................................................................... 6 4.1 RESULTS AND DISCUSSION ............................................................................................ 7 4.2 Atmospheric Nuclear Detonations and Nuclear AcCidents ...................................... 7 4.3 Summary of Preoperational Data ........................................................................... 7 4.4 Program Findings ................................................................................................... 8 5.0 FIGURES AND TABLES ..................................................................................................... 12

6.0 REFERENCES

...........................................................................................................................24 APPENDICES A Interlaboratory Comparison Program Results .................................................................... A-1 B Data Reporting Conventions ............................................................................................. B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .................................. :.......................... C-1 D Sampling Location Maps ................................................................................................... D-1 E Ground Water Monitoring Well Samples ................................... ;.. , .... :............................... E-1 3

LIST OF TABLES 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 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ................................................................A1-1 A-2 Thermoluminescentdosimeters (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 Resources Associates, Crosscheck Program Results (EML study replacement) ...................................................................................A7-1 Attachment A: Acceptance criteria for spiked samples .................................................... A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ..................................................................... C-2 Appendix E E-1 Sample Collection and Analysis Program, Ground Water, ............................................. E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ................................................ E-6 E-3 Ground Water Monitoring Program Summary .................................................. ,............. E-7 E-4 Results of Analyses, Ground Water Monitoring Program ............................................... E-9 4

LIST OF FIGURES No.

5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations .......................................... 18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location .............................................................................................. 19 The following figures are located in the Appendices:

Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................D-2 D-2 Sample collection and analysis program: TLD locations, OuterRing ..............................................................................................................................D-3 D-3 Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations .......................................................................... D-5 D-5 Sample collection and analysis program: TLD locations,

. ISFSI TLD Locations ................................................................................................................D-6 Appendix E E-1 Sample collection and analysis program:

Ground water, On-site monitoring well locations ..................................................................... E-8 5

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2015.

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 included in Part II of this report.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant.

Results for the year 2015 are summarized and discussed.

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

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3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello 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 (TLD's).

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 Monticello 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 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-

?, 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-? is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-1 03 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 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.

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3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.

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. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaS0 4 :Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.

As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C).

The samples are analyzed for iodine-131 and other gamma emitting isotopes.

Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged. Analysis is done for gamma-emitting isotopes.

Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes. The Ground Water Monitoring Program is further described in Appendix E.

Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.

River water is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. 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, invertebrates, and shoreline sediments. Shoreline sediment is also collected from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

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

(1) Air Particulates I Air Iodine:

M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station.

M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.

M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.

M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report.

M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015.

The GFCI was tripped. The GFCI was reset.

(2) Surface Water:

Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.

One TLD samples was found missing for the second quarter at Outer Ring location M-06B.

Deviations from the program are summarized in Table 5.3.

3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015.

3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.

Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

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Tritium concentrations are determined by liquid scintillation.

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 QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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 2015 land use census was conducted between September 14 and September 24, 2015.

This is the third year using improved GPS software. The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.

There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.

The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways). Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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

All 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.

4.2 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China.

4.3 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 3 3 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3

pCi/m 3 . Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained 3

below detection levels of 0.03 pCi/m In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.

Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

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4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015.

Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.

distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively). The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rin~q Outer Rino Dose rate (mRem/91 davs) 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 2011 14.8 14.3 2012 16.2 15.5 2013 14.4 14.0 2014 13.5 12.9 2015 14.8 14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at 3

both indicator and control locations (0.030 and 0.028 pCi/m ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below.

Year Indicators Control 3

Concentration (QCi/m )

1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 2011 0.029 0.027 2012 0.032 0.031 2013 0.029 0.032 2014 0.027 0.028 2015 0.030 0.028 Average annual gross beta concentrations in airborne particulates.

Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015.

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 AI-Salih, 1955) was detected in all samples, 3 3 with an average activity of 0.070 pCilm for the indicator locations and 0.066 pCilm for the control locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples.

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River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.

Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1999 2.2 2008 2.1 2000 2.5 2009 2.3 2001 2.5 2010 2.9 2002 2.9 2011 2.2 2003 3.0 2012 2.4 2004 2.7 2013 2.6 2005 2.8 2014 2.8 2006 2.1 2015 2.3 2007 2.8 Average annual concentrations; Gross beta in drinking water.

Well Water At the four indicator and control locations, tritium was below the detection limit for all samples.

Gamma isotopic results were also below detection limits.

The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.

Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.

Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September. Flesh was separated from the bones and analyzed by gamma spectroscopy. Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits.

There was no indication of a plant effect.

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Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy. All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect.

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition. Naturally-occurring beryllium-? and potassium-40 were also detected. There was no indication of a plant effect.

Groundwater Monitoring Program (On-site monitoring wells)

Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite.

See Appendix E for full Groundwater monitoring well results and discussion.

Gamma isotopic measurements were below detection limits.

Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.

Storm Water Run-off (on-site)

One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015.

ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations. Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected. Neutron dosimetry uses the different responses from two lithium 6 10 borate TLDs, one depleted of Li and 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive). The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016.

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5.0 FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type) a Frequency b Frequency c REMP Ambient radiation(TLDs) 40 M-01A- M-14A, M-018- M-168 C/Q Ambient gamma M-01 S - M-06S, M-01 C - M-04C ISFSI Ambient radiation (TLDs) 20 ISFSI-1 to ISFSI-16, C/Q Neutron Dose Neutron Control A, 8, C, D C/Q 13 1-01 to 1-13 C/Q Ambient Gamma Airborne Particulates 5 M-1 (C), M-2, M-3, M-4, M-5 crw G8, GS (QC of each location)

Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 crw 1-131 Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year GS Surface water 2 M-S(C), M-9 Gf\N GS(MC), H-3(QC)

Drinking water M-14 Gf\N G8(MC), I-131(MC)

GS (MC), H-3 (QC)

Well water 4 M-11, M-12, M-55, M-43(C) GIQ H-3, GS Fish 2 M-S(C), M-9 G/SA GS (two species, edible portion)

Periphyton or invertebrates 2 M-S(C), M-9 G/SA GS Shoreline sediment 3 M-S(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. 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.

c Analysis type is coded as follows: 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 Pasture grass and vegetation collections added to supplement dairy sampling.

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction Code Type a Collection Site Sample Type b from Reactor M-1 c Air Station M-1 AP,AI 11.0 mi@ 307"/NW M-2 Air Station M-2 AP,AI 0.8 mi@ 140°/SE M-3 Air Station M-3 AP,AI 0.6 mi@ 104°/ESE M-4 Air Station M-4 AP,AI 0.8 mi@ 147"/SSE M-5 Air Station M-5 AP,AI 2.6 mi@ 134°/SE M-8 c Upstream of Plant Intake SW, SS, BO, F < 1000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream M-11 City of Monticello ww 3.3 mi@ 127"/SE M-12 Plant Well #11 ww 0.26 mi@ 252°/WSW M-14 City of Minneapolis ow 37.0 mi@ 132°/SE M-15 Montissippi Park ss 1.27 mi@ 114°/ESE M-27 Highest 0/Q garden 1.15 mi@ 148°/SSE M-41 Training Center VE 0.8 mi@ 151°/SSE M-42 Biology Station Road VE 0.6 mi@ 134°/SE M-43 c lmholte Farm VE,WW 12.3 mi@ 313°/NW M-55 Hasbrouck Residence ww 1.60 mi@ 255°/WSW 14

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Code Type* Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi@ 353°/N M-02A Sherburne Ave. So. TLD 0.79 mi@ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi@ 56°/NE M-04A Biology Station Road TLD 0.5 mi@ 92°/E M-05A Biology Station Road TLD 0.48 mi @ 122° /ESE M-06A Biology Station Road TLD 0.54 mi@ 138°/SE M-07A County Road 75 TLD 0.47 mi@ 158°/SSE M-08A County Road 75 TLD 0.45 mi@ 175°/S M-09A County Road 75 TLD 0.38 mi@ 206°/SSW M-10A County Road 75 J'LD 0.38 mi@ 224°/SW M-11A County Road 75 TLD 0.4 mi@ 237"/WSW M-12A County Road 75 TLD 0.5 mi@ 262°/W M-13A North Boundary Road TLD 0.89 mi@ 322°/NW M-14A North Boundary Road TLD 0.78 mi@ 335°/NNW Approximately 4 to 5 miles Distant from the Plant M-01B 11?'h Street TLD 4.65 mi@ 01°/N M-02B County Road 11 TLD 4.4 mi@ 18"/NNE M-03B County Road 73 & 81 TLD 4.3 mi@ 51°/NE M-04B County Road 73 (196th St.) TLO 4.2 mi@ 67"/ENE M-05B City of Big Lake TLD 4.3 mi@ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi@ 117"/ESE M-07B Monticello Industrial Drive TLD 4.3 mi@ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi@ 162°/SSE M-09B Weinand Farm TLD 4.7 mi@ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi@ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi@ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi@ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi@ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi@ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi@ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi@ 341°/NNW 15

Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant.

Distance and Code Type a Collection Site Sample Typeb Direction from Reactor Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi@ 241WvSW M-02S Krone Residence TLD 0.5 mi@ 220°/SW M-03S Big Oaks Park TLD 1.53 mi@ 103°/ESE M-04S Pinewood School TLD 2.3 mi@ 131 °/SE M-OSS Rivercrest Christian Academy TLD 3.0 mi@ 118°/ESE M-06S Monticello Public Works TLD 2.6 mi@ 134°/SE M-01C c Kirchenbauer Farm TLD 11.5 mi@ 323°/NW M-02C c County Roads 4 and 15 TLD 11.2 mi @4r/NE M-03C c County Rd 19 and Jason Ave. TLD 11.6 mi@ 130°/SE M-04C c Maple Lake Water Tower TLD 10.3 mi@ 226°/ SW ISFSI TLD Locations ISFSI-1 ISFSI-1 (neutron) and 1-01 (gamma) TLD NE corner of ISFSI ISFSI-2 ISFSI-2 (neutron) and 1-02 (gamma) TLD North side of ISFSI, center ISFSI-3 ISFSI-3 (neutron) and 1-03 (gamma) TLD NW corner of ISFSI ISFSI-4 ISFSI-4 (neutron) and 1-04 (gamma) TLD West side of ISFSI, middle ISFSI-5 ISFSI-5 (neutron) and 1-05 (gamma) TLD West side of ISFSI, at center of array ISFSI-6 ISFSI-6 (neutron) and 1-06 (gamma) TLD SW corner of ISFSI ISFSI-7 ISFSI-7 (neutron) and 1-07 (gamma) TLD South side of ISFSI, center ISFSI-8 ISFSI-8 (neutron) and 1-08 (gamma) TLD SE corner of ISFSI ISFSI-9 ISFSI-9 (neutron) and 1-09 (gamma) TLD East side of ISFSI, at center of array ISFSI-10 ISFSI-10 (neutron) and 1-10 (gamma) TLD East side of ISFSI, middle ISFSI-11 ISFSI-11 (neutron) and 1-11 (gamma) TLD OCA fence south, on exit road ISFSI-12 ISFSI-12 (neutron) and 1-12 (gamma) TLD OCA fence middle, on exit road ISFSI-13 ISFSI-13 (neutron) and 1-13 (gamma) TLD OCA fence north, on exit road ISFSI-14 ISFSI-14 (neutron) TLD Posted with TLD M12A ISFSI-15 ISFSI-15 (neutron) TLD Posted with TLD M1 OA ISFSI-16 ISFSI-16 (neutron) TLD Posted with TLD M02S Neutron Control A c TLD Posted with TLD M03C Neutron Control B c TLD Posted with TLD M04C Neutron Control C c TLD Posted with TLD M02C Neutron Control D c TLD Posted with TLD M01 C a "C" denotes control location. All other locations are indicators.

b Sample Codes: AP Airborne particulates F Fish AI Airborne Iodine sw River Water BS Bottom (river) sediments ss Shoreline Sediments BO Bottom organisms TLD Thermoluminescent Dosimeter OW Drinking Water VE Vegetation I vegetables ww Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

16

Table 5.3 Missed Collections and Analyses.

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, 1-131 M-005 1/28/2015 Power loss at sample Power was reset station.

sw Gamma M-008 January '15 Water frozen entire month; None no composite.

AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running due Replaced air sampler.

to bad switch.

sw Gamma M-008 February '15 Water frozen entire month; None no composite.

  • .c sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None APIA I Beta, 1-131 M-002 5/6/2015 Air sampler not running. Replaced air sampler.

TLD Gamma M-06B 2nd Qtr '15 TLD missing in field. Replaced TLD APIA I Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped ResetGFCI sw Gamma M-008 12/30/15 Water frozen None 17

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

20 l -

--a-lnnerRing Outer Ring 19 18 17 I 0 16

~ v ~ v I/;I~

I y- v r-- 0 \ v r.......

v~

15 11---1

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ro 14

~

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0) 0 0 0 0 0 0

0 0 """

0 0

0 0

0 0

0 0

0 0

0 0 0N 0 ~

0

~

0 0""" 0N

~ N N N N N N N N N N N N N N 18

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

- 11- - Indicators (M-2, 3, 4, 5) 0.035 I - o - - Controi(M-1)

I 0.033 0.031 ly ~

\

0.029 l/l\ /I \ \

I I

~ v/ \

'\~v/ f/I \

/1 ~ I /

\

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0.021 0.019 0.017 0.015 Ol 0 N (') "<!" I{) (() I'- (() Ol 0 (') I{)

Ol 0 0 0

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~ N N N N N N N N N N N N N 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period ------------------

January-December, 2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean(F)" Mean (F) 0 Mean (F) 0 Routine (Units) Analyses* Ran gee Locationd Rangec Rangec Results*

Direct Radiation TLD (Inner Ring, Gamma 56 3.0 14.8 (56/56) M-11A, County Rd 75, 17.1 (4/4) (See Control 0 General Area at ( 9.6-19.6) 0.4 mi @ 250°/WSW (15.8-19.6) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 63 3.0 14.2 (63/63) M-148 16.6 (4/4) (See Control 0 4-5 mi. distant) ( 11.0-19.6) 4.5 mi@ 228°/NW (14.7-19.6) below.)

mRem/91 days)

TLD (Special Gamma 24 3.0 14.7 (24/24) M-04S 16.4 (4/4) (See Control 0 Interest Areas) ( 9.4-18.8) 2.3 mi@ 132°/SE (14.4-17.6) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-02C 17.5 (4/4) 15.3 (16/16) 0 mRem/91 days) 11.2 mi@ 47"/NE (15.9-20.3) ( 11.8-20.3)

Airborne Pathway Airborne GB 256 0.002 0.030 (204/204) M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 Particulates (0.007-0.088) 2.6 rni@ 134°/SE (0.009-0.088) (0.008-0.062)

(pCi/rn 3)

GS 20 Be-7 0.015 0.070 (16/16) M-5, Air Station 0.073 (4/4) 0.066 (4/4) 0 (0.049-0.087) 2.6 rni@ 134°/SE (0.049-0.087) (0.043-0.077)

Mn-54 0.0008 < LLD - - < LLD 0 Co-58 0.0008 < LLD - - < LLD 0 Co-60 0.0009 < LLD - - < LLD 0 Zn-65 0.0019 < LLD - - < LLD 0 Zr-Nb-95 0.0014 < LLD - - < LLD 0 Ru-103 0.0013 < LLD - - < LLD 0 Ru-106 0.0085 < LLD - - < LLD 0 Cs-134 0.0010 < LLD - - < LLD 0 Cs-137 0.0010 < LLD - - < LLD 0 Ba-La-140 0.0026 < LLD - - < LLD 0 Ce-141 0.0020 < LLD - - < LLD 0 Ce-144 0.0046 < LLD - - < LLD 0 Airborne Iodine 1-131 256 0.03 < LLD - - < LLD 0 3

(pCi/m )

20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant *Docket No. ..;5;..;0-...;2;;.;6;..;3_ _ _ _ _ __

Location of Facility Wright, Minnesota Reporting Period January-December,2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) 0 Mean (F)" Mean (F) 0 Routine (Units) Analyses* Range* Locationd Range* Range* Results*

Waterborne Pathway River Water (pCi/L) H-3 8 500 < LLD - - < LLD 0 GS 22 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce'-144 39 < LLD - - < LLD 0 Drinking Water GB 12 1.0 2.3 (12112) M-14, Minneapolis 2.3 (12/12) None 0 (pCi/L) (1.2-3.5) 37.0 mi.@ 132° /SE (1.2-3.5) 1-131 12 1.0 < LLD - - None 0 H-3 4 500 < LLD - - None 0 GS 12 Mn-54 10 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 10 < LLD - - None 0 Co-60 10 < 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 35 < LLD - - None 0 Well Water H-3 16 500 < LLD - - < LLD 0 (pCi/L) GS 16 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 49 < LLD - - < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summarw Name of Facility Monticello Nuclear Generating Plant Docket No. ...;5...;;0...:-2;;.;6...;;3_ _ _,_._ __

Location of Facility Wright, Minnesota Reporting Period January-December, 2 015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses" Range' Locationd Range' Range' Results" Waterborne Pathway Invertebrates GS 4 (pCilg wet) Be-7 1.49 < LLD - - < LLD 0 K-40 1.91 < LLD - - < LLD 0 Mn-54 0.088 < LLD - - < LLD 0 Fe-59 0.24 < LLD - - < LLD 0 Co-58 0.145 < LLD - - < LLD 0 Co-60 0.085 < LLD - - < LLD 0 Zn-65 0.18 < LLD - - < LLD 0 Zr-Nb-95 0.23 < LLD - - < LLD 0 Ru-103 0.217 < LLD - - < LLD 0 Ru-106 0.55 < LLD - - < LLD 0 Cs-134 0.076 < LLD - - < LLD 0 Cs-137 0.085 < LLD - - < LLD 0 Ba-La-140 1.35 < LLD - - < LLD 0 Ce-144 0.39 < LLD - - < LLD 0 Shoreline GS 6 Sediments Be-7 0.33 < LLD - - < LLD 0 (pCi/g dry) -

K-40 0.10 10.24 (4/4) M-08, Upstream 11.55 (2/2) 11.55 (2/2) 0 (9.49-1 0.54) < 1000' of discharge (11.53-11.58) (11.53-11.58)

Mn-54 0.021 < LLD - - < LLD 0 Fe-59 0.076 < LLD - - < LLD 0 Co-58 0.026 < LLD - - < LLD 0 Co-60 0.017 < LLD - - < LLD 0 Zn-65 0.044 < LLD - - < LLD 0 Nb-95 0.051 < LLD - - < LLD 0 Zr-95 0.052 < LLD - - < LLD 0 Ru-103 0.041 < LLD - - < LLD 0 Ru-106 0.13 < LLD - - < LLD 0 Cs-134 0.017 < LLD - - < LLD 0 Cs-137 0.021 0.029 (2/4) M-09, Downstream - < LLD 0 (0.024-0.034) < 1000' of discharge -

Ba-La-140 0.21 < LLD - - < LLD 0 Ce-144 0.13 < LLD - - < LLD 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263

--,---=-----:---

Location of Facility Wright, Minnesota Reporting Period January-December, 2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) 0 Mean (F) 0 Mean (F)" Routine (Units) Analyses* Ran gee Locationd Ran gee Rangec Results*

Ingestion Pathway Vegetation GS 9 (Pasture Grass, Mn-54 0.014 < LLD - - < LlD 0 Weeds, Leaves) Fe-59 0.033 < LLD - - < LLD 0 Co-58 0.014 < LLD - - < LLD 0 (pCi/gwet) Co-60 0.019 < LLD - - < LLD 0 Zn-65 0.029 < LLD - - < LLD 0 Nb-95 0.020 < LLD - - < LLD 0 1-131 0.043 < LLD - - < LLD 0 Cs-134 0.015 < LLD - < LLD 0 Cs-137 0.014 < LLD - - < LLD 0 Fish GS 8 (pCi/g wet) K-40 0.10 3.39 (4/4) M-09, Downstream 3.39 (4/4) 3.31 (4/4) 0

- (3.08-3.71) < 1000' of discharge (3.08-3.71) (2.56-3.65)

Mn-54 0.025 < LLD - - < LLD 0 Fe-59 0.056 < LLD - - < LLD 0 Co-58 0.025 < LLD - - < LLD 0 Co-60 0.025 < LLD - - < LLD 0 Zn-65 0.070 < LLD - - < LLD 0 Zr-Nb-95 0.031 < LLD - - < LLD 0 Cs-134 0.025 < LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.122 < LLD - - < LLD 0 Ce-144 0.141 < LLD - - < LLD 0

  • GB =gross beta, GS =gamma scan.

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

c 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: (1) by name, and/or station code 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.

23

6.0 REFERENCES

CITED Arnold, J. R. and H. A. AI-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, 276.

ATI Environmental, Inc., Midwest Laboratory.

____2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015.

_ _ _---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 2000 through 2015.

____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 1983 through 1999.

____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

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

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

_ _ _..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December, 1978 through 1982.

_ _ _ _.2009. Quality Assurance Program Manual, Rev. 3, 14 November 2012.

_ _ _ _2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009.

_ _ _ _.2009. Quality Control Program, Rev. 2, 12 November 2009.

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, Illinois, 369-382 ..

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46.

Northern States Power Company.

_ _ _..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.

24

6.0 REFERENCES

CITED (continued)

Scannell, M. J., J. Giard, J. Raimondi. 2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN.

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.

____2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.

____.2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.

Minneapolis, Minnesota.

25

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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2015 through December, 2015

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. 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.

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.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

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 lists REMP specific analytical results from 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.

Complete analytical data for duplicate analyses is available upon request.

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

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

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

A1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S 8

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

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

> 50 pCi/liter or kg 10% of known value Stronti um-90b 2 to 30 pCi/liter or kg 5.0 pCilliter

> 30 pCi/liter or kg 10% of known value Potassium-40  ;::: 0.1 g/liter or kg 5% of known value Gross alpha :5 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta :5 100 pCilliter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium :5 4,000 pCi/liter +/- 1o =

169.85 x (known) 0 ' 0933

> 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 lodine-131, :5 55 pCilliter 6 pCilliter lodine-129b >55 pCi/liter 10% of known value Uranium-238, :5 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b lron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 - 210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22.10-54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21.90-31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540* 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700-23,400 Pass

  • Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.

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

d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.

  • The result of reanalysis (Compare to original result, footnoted "e" above).

A1-1

TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental Inc.

2015-1 6/24/2015 30cm. 98.81 103.67 +/-6.05 69.20-128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32+/-15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23 +/- 1.33 17.30-32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30-32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.43 +/-2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.12 +/-1.36 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180cm. 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180cm. 2.74 3.05 +/-1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14 +/-0.18 1.90-3.60 Pass A2-1

TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental, Inc.

2015-2 12/15/2015 Spike 1 138.0 118.5 +/-2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 12/15/2015 Spike 3 138.0 121.9 +/- 1.9 -0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2 -0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 -0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/-5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/-3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 -0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 -0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/-3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass a TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose.

d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.

e Tables A2.1 and A2.2 assume 1 roentgen= 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015).

A2-2

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance W-020315 2/3/2015 Ra-226 16.19+/-0.42 16.70 13.36-20.04 Pass W-021215 2/12/2015 Gr. Alpha 18.38 +/- 0.39 20.10 16.08-24.12 Pass W-021215 2/12/2015 Gr. Beta 27.98 +/- 0.32 30.90 24.72- 37.08 Pass SPW-687 2/27/2015 Ni-63 239.6 +/- 3.5 202.4 161.9 - 242.9 Pass SPAP-689 3/2/2015 Gr. Beta 42.37 +/- 3.50 43.61 34.89 - 52.33 Pass SPAP-691 3/2/2015 Cs-134 1.77 +/- 0.61 1.90 1.52 - 2.28 Pass SPAP-691 3/2/2015 Cs-137 83.02 +/- 2.60 97.20 77.76-116.64 Pass SPW-693 3/2/2015 Cs-134 44.30 +/- 2.53 53.40 42.72-64.08 Pass SPW-693 3/2/2015 Cs-137 74.82 +/- 3.50 73.80 59.04 - 88.56 Pass SPW-693 3/2/2015 Sr-89 87.45 +/- 3.62 87.48 69.98- 104.98 Pass SPW-693 3/25/2015 Sr-90 37.22 +/- 1.55 38.10 30.48 - 45.72 Pass SPMI-697 3/2/2015 Cs-134 96.67 +/- 7.74 107.00 85.60 - 128.40 Pass SPMI-697 3/2/2015 Cs-137 78.51 +/- 7.02 73.84 59.07 - 88.61 Pass SPMI-697 3/2/2015 Sr-89 72.98 +/- 4.86 87.48 69.98- 104.98 Pass SPMI-697 3/2/2015 Sr-90 39.17+/-1.51 38.10 30.48-45.72 Pass SPW-699 3/2/2015 H-3 59,592 +/- 703 58,445 46,756 -70,134 Pass W-031115 3/11/2015 Ra-226 13.73 +/- 0.35 16.70 13.36-20.04 Pass W-030215 3/2/2015 Ra-228 32.79 +/- 2.31 31.44 25.15-37.73 Pass SPF-1040 3/16/2015 Cs-134 787.5 +/- 9.2 840.0 672.0 - 1,008.0 Pass SPF-1040 3/16/2015 Cs-137 2,599 +/- 24 2,360 1,888 - 2,832 Pass SPW-1036 3/25/2015 Fe-55 1,792 +/- 63 1961 1,569 - 2,353 Pass SPW-1374 4/6/2015 U-238 46.03 +/- 2.25 41.70 25.02 - 58.38 Pass W-040815 4/8/2015 Gr. Alpha 20.18 +/-0.42 20.10 16.08-24.12 Pass W-040815 4/8/2015 Gr. Beta 29.70 +/- 0.33 30.90 24.72 - 37.08 Pass SPW-1038 4/13/2015 C-14 3,497 +/- 9 4,734 2,840 - 6,628 Pass W-2165 4/20/2015 H-3 5550 +/- 226 5,780 3,468 - 8,092 Pass W-2165 4/20/2015 Sr-89 90.70 +/- 8.20 108.70 65.22 -152.18 Pass W-2165 4/20/2015 Sr-90 76.80 +/- 2.00 75.90 45.54 - 106.26 Pass W-2165 4/20/2015 Cs-134 62.40 +/- 6.40 57.30 34.38 - 80.22 Pass W-2165 4/20/2015 Cs-137 91.30 +/- 7.70 84.00 50.40 - 117.60 Pass W-2392 4/13/2015 H-3 5032 +/- 214 5780 3468-8092 Pass W-2392 4/13/2015 Ni-63 222.4 +/- 3.8 202.0 121.2 - 282.8 Pass W-2392 4/13/2015 Cs-134 53.26 +/- 5.01 57.30 34.38 - 80.22 Pass W-2392 4/13/2015 Cs-137 91.90 +/-7.76 84.20 50.52- 117.88 Pass W-042415 4/24/2015 Ra-226 12.52 +/- 0.39 16.70 10.02 - 23.38 Pass W-050715 5n/2015 Gr. Alpha 19.05+/-0.41 20.10 12.06-28.14 Pass W-050715 5n/2015 Gr. Beta 27.30 +/- 0.32 30.90 18.54 - 43.26 Pass W-061215 6/12/2015 Gr. Alpha 20.72 +/- 0.44 20.10 12.06-28.14 Pass W-061215 6/12/2015 Gr. Beta 28.51 +/- 0.33 30.90 18.54-43.26 Pass U-2982 6/9/2015 Gr. Beta 500.1 +/- 5.1 604.0 362.4 - 845.6 Pass U-3200 6/9/2015 H-3 2229 +/- 424 2346 1408 - 3284 Pass W-70915 7/9/2015 Gr. Alpha 18.76 +/- 0.40 20.10 12.1-28.1 Pass W-70915 7/9/2015 Gr. Beta 29.71 +/- 0.33 30.90 18.5 -43.3 Pass SPAP-3859 7/21/2015 Gr. Beta 41.59 +/- 0.12 43.61 26.17-61.05 Pass SPAP-3861 7/21/2015 Cs-134 1.69 +/- 0.60 1.69 1.0-2.4 Pass A3-1

T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 - 65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 - 44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 - 1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1 ,404 - 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06-28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 - 43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 - 23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 - 43.26 Pass W-091415 9/14/2015 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2015 Gr. Beta 31.53 +/- 0.35 30.90 18.54 - 43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-100615 10/6/2015 Gr. Alpha 20.62 +/- 0.43 20.10 12.06-28.14 Pass W-100615 10/6/2015 Gr. Beta 29.35 +/- 0.33 30.90 18.54 - 43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 - 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 - 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 - 44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 - 15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 - 134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 - 116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 - 43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 - 43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 - 23.38 Pass

  • Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).

b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.

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

A3-2

TABLE A-4. In-House "Blank" Samples 8

Concentration (pCi/L)

Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)

W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/-3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/- 5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 1 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5n/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMI-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc .. Criteria (4.66 cr)

SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/- 0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).

b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72+/-0.12 5.78 +/- 0.12 5.75 +/- 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/- 0.135 0.919 +/- 0.102 0.917+/-0.15 Pass CF-62,63 1n/2015 K-40 3.97 +/- 0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 1/7/2015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/12/2015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90 +/- 1.16 Pass SG-83,84 1/12/2015 Tl-208 0.57 +/- 0.07 0.56 +/- 0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73+/-0.10 1.58 +/- 0.09 1.65 +/- 0.13 Pass SG-83,84 1/12/2015 Pb-214 13.33 +/- 0.33 13.88 +/- 0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47 +/- 0.24 Pass SG-83, 84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 1/12/2015 Ac-228 13.33 +/- 0.59 12.86 +/- 0.43 13.09 +/- 0.36 Pass AP-011215NB 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-6001 0,60011 1/28/2015 Ra-226 1.25+/-0.14 1.40 +/- 0.15 1.33 +/- 0.10 Pass DW-60010,60011 1/28/2015 Ra-228 2.00 +/- 0.66 1.39 +/- 0.60 1. 70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-214 6.45 +/- 0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/- 0.24 4.20 +/- 0.58 4.32 +/- 0.31 Pass AP-020415NB 2/4/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115NB 2/11/2015 Gr. Beta 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass DW-60023,60024 2/26/2015 Ra-226 1.52+/-0.15 1.51 +/- 0.15 1.52 +/- 0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/- 0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 2/26/2015 K-40 11.96 +/- 0.98 11.49 +/- 0.82 11.72 +/- 0.64 Pass S-799,800 2/26/2015 Tl-208 0.36 +/- 0.04 0.31 +/- 0.04 0.34 +/- 0.03 Pass S-799,800 2/26/2015 Pb-212 0.92 +/- 0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 2/26/2015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2/26/2015 Ac-228 1.35 +/- 0.22 1.23+/-0.17 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3+/-6.3 117.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 2/2/2015 Gr. Beta 82.27 +/- 2.79 84.33 +/- 2.74 83.30 +/- 1.96 Pass DW-60031 ,60032 3/4/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/- 7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/- 0.34 6.88 +/- 0.32 6.89 +/- 0.23 Pass DW-60036,60037 3/4/2015 Ra-228 4.43 +/- 0.73 4.41 +/-0.72 4.42 +/- 0.51 Pass DW-60048,60049 3/4/2015 Ra-226 0.84 +/- 0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169, 1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/9/2015 Gr. Beta 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 4/13/2015 H-3 1,628 +/- 139 1,695 +/- 141 1,662 +/- 99 Pass SG-1847, 1848 4/20/2015 K-40 3.24 +/- 1.18 1.99+/-0.76 2.62 +/- 0.70 Pass SG-1847, 1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847, 1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/23/2015 H-3 6,584 +/- 244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/27/2015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/- 64.3 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/- 3.63 43.61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/- 2.02 51.40 +/- 1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 +/- 0.62 13.67 +/- 0.40 Pass SG-1868, 1869 4/28/2015 Ra-228 20.10 +/- 0.92 22.10 +/- 1.29 21.10+/-0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087,60088 5/14/2015 Ra-226 1.58 +/- 0.17 1.52 +/- 0.17 1.55+/-0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/- 0.61 47.80 +/- 0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/- 7.9 254.6 +/- 7.6 261.2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10+/-0.92 40.80 +/- 0.83 40.95 +/- 0.62 Pass DW-60095,60096 5/26/2015 Gr. Alpha 1.34 +/- 0.69 0.91 +/- 0.62 1.13 +/- 0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/- 0.14 1.08+/-0.12 0.97 +/- 0.09 Pass S-2627,2628 5/29/2015 Cs-137 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/- 0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11.15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/- 214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/- 658 20,987 +/- 600 21,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-301 07,30108 6/8/2015 Gr. Alpha 1.34 +/- 0.82 1.47 +/- 0.85 1.41 +/- 0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/- 0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841.9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Beta 0.023 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78+/-0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass VE-3300,3301 6/24/2015 K-40 29.12 +/- 0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass AP-062915 6/29/2015 Gr. Beta 0.023 +/- 0.005 0.023 +/- 0.005 0.023 +/- 0.003 Pass WW-3632,3633 6/30/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114+/-158 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-3822, 3823 7/1/2015 Be-7 0.075 +/- 0.011 0.068 +/- 0.012 0.072 +/- 0.008 Pass AP-3969, 3970 7/1/2015 Be-7 0.063 +/- 0.008 0.064 +/- 0.010 0.063 +/- 0.006 Pass WW-3632, 3633 7/6/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114 +/- 159 Pass W-4368, 4369 7/6/2015 Gr. Alpha 26.70 +/- 4.00 24.10 +/- 3.90 25.40 +/- 2.79 Pass W-4368, 4369 7/6/2015 Gr. Beta 34.62 +/- 2.10 33.30 +/- 2.02 33.96 +/- 1.46 Pass DW-60138, 60139 717/2015 Ra-226 0.07 +/- 0.04 0.11 +/- 0.05 0.09 +/- 0.03 Pass DW-60138, 60139 717/2015 Ra-228 1.04+/-0.41 1.15+/-0.47 1.10+/-0.31 Pass WW-4158, 4159 7/9/2015 H-3 138.8 +/- 82.4 174.0 +/- 84.1 156.4 +/- 58.9 Pass Ml-2902, 2903 7/10/2015 K-40 1271 +/- 118 1308 +/- 115 1289 +/- 82 Pass SG-3533, 3534 7/10/2015 Gr. Alpha 238.0 +/- 8.2 249.5 +/- 8.5 243.8 +/- 5.9 Pass DW-60150, 60151 7/10/2015 Ra-226 1.53+/-0.16 1.49 +/- 0.12 1.51 +/- 0.10 Pass DW-60150, 60151 7/10/2015 Ra-228 2.68 +/- 0.68 1.89 +/- 0.62 2.29 +/- 0.46 Pass VE-3716, 3717 7/14/2015 K-40 3.85 +/- 0.33 3.71 +/- 0.31 3.78 +/- 0.23 Pass Ml-3759, 3760 7/15/2015 K-40 1819 +/- 127 1764 +/- 140 1791 +/- 94 Pass Ml-3759, 3760 7/15/2015 Sr-90 1.00 +/- 0.36 0.61 +/- 0.32 0.80 +/- 0.24 Pass AP-072115 7/21/2015 Gr. Beta 0.022 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 Pass VE-4053, 4054 7/21/2015 Be-7 0.52 +/- 0.15 0.49 +/- 0.11 0.50 +/- 0.09 Pass VE-4053, 4054 7/21/2015 K-40 8.00 +/- 0.42 7.61 +/- 0.31 7.81 +/- 0.26 Pass AP-4200, 4201 7/29/2015 Be-7 1.06+/-0.12 0.96 +/- 0.11 1.01 +/- 0.08 Pass AP-4200, 4201 7/29/2015 K-40 5.03 +/- 0.24 4.96 +/- 0.23 4.99 +/- 0.16 Pass W-4137, 4138 7/31/2015 Ra-226 0.58 +/- 0.13 0.45 +/- 0.14 0.52+/-0.10 Pass XWW-4431, 4432 8/5/2015 H-3 4,773 +/-213 4,915 +/- 216 4,844 +/- 152 Pass SG-4305, 4306 8/6/2015 Ra-228 10.34 +/- 0.58 11.46 +/- 0.62 10.90 +/- 0.42 Pass AP-081015 8/10/2015 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 0.004 Pass AP-081115 8/11/2015 Gr. Beta 0.024 +/- 0.004 0.020 +/- 0.004 0.022 0.003 Pass VE-4452, 4453 8/11/2015 K-40 3.77 +/- 0.29 3.78 +/- 0.26 3.77 +/- 0.20 Pass AP-081715 8/17/2015 Gr. Beta 0.030 +/- 0.005 0.030 +/- 0.005 0.030 +/- 0.003 Pass DW-60195, 60196 8/17/2015 Ra-226 0.39+/-0.10 0.37 +/- 0.10 0.38 +/- 0.07 Pass DW-60195, 60196 8/17/2015 Ra-228 1.43 +/- 0.51 1.97 +/- 0.61 1.70 +/- 0.40 Pass DW-60198, 60199 8/17/2015 Gr. Alpha 2.93 +/- 0.94 2.11 +/- 0.96 2.52 +/- 0.67 Pass VE-4578, 4579 8/18/2015 K-40 4.14 +/- 0.25 4.32 +/- 0.24 4.23 +/- 0.17 Pass SW-4662, 4663 8/25/2015 H-3 351.3 +/- 89.8 415.6 +/- 92.8 383.4 +/- 64.6 Pass DW-60212, 60213 8/25/2015 Ra-226 0.09 +/- 0.07 0.10+/-0.08 0.10 +/- 0.05 Pass LW-4788, 4789 8/27/2015 Gr. Beta 0.97 +/- 0.51 1.68 +/- 0.59 1.32 +/- 0.39 Pass AP-083115 8/31/2015 Gr. Beta 0.032 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-4875, 4876 9/3/2015 Be-7 0.294 +/- 0.125 0.202 +/- 0.109 0.248 +/- 0.083 Pass VE-5083, 5084 9/14/2015 Be-7 0.47 +/- 0.23 0.56 +/- 0.19 0.52 +/- 0.15 Pass VE-5083, 5084 9/14/2015 K-40 6.20 +/- 0.51 6.36 +/- 0.50 6.28 +/- 0.36 Pass VE-5167, 5168 9/16/2015 Be-7 0.40 +/- 0.11 0.41 +/-0.10 0.41 +/- 0.07 Pass VE-5167, 5168 9/16/2015 K-40 3.56 +/- 0.27 3.91 +/- 0.24 3.74+/-0.18 Pass BS-5188, 5189 9/16/2015 K-40 9.69 +/- 0.51 10.51 +/- 0.52 10.10 +/- 0.36 Pass F-5419, 5420 9/17/2015 K-40 3.48 +/- 0.47 3.49 +/- 0.56 3.49 +/- 0.36 Pass DW-60238, 60239 9/18/2015 Ra-226 1.93 +/- 0.23 2.31 +/- 0.26. 2.12 +/- 0.17 Pass DW-60238, 60239 9/18/2015 Ra-228 4.44 +/- 0.78 5.61 +/- 0.84 5.03 +/- 0.57 Pass AP-092215NB 9/22/2015 Gr. Beta 0.021 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.00 Pass WW-5398, 5399 9/22/2015 H-3 1,857 +/- 145 1,846 +/- 144 1,852 +/- 102 Pass AP-6007, 6008 9/28/2015 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108+/-211 2,220 +/- 157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461 ,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461 ,2 10/1/2015 K-40 8.77 +/- 0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/- 0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17 +/- 0.73 2.10 +/- 0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318+/-127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 O.D78 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29.80 +/-2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/- 0.29 4.13+/-0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/-0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45 +/-0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16+/-0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08+/-0.15 1.14 +/- 0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/- 0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/- 0.43 2.16 +/- 0.37 2.14 +/-0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28 +/- 1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 170 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/- 0.03 0.19 +/- 0.03 0.18 +/- 0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6 +/- 1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A 5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Pass Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 Pass S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 Pass S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 Pass WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 Pass SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 Pass SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 Pass LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 Pass AP-7351 , 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 Pass AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

' Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil, sediment (pCi/g).

A5-5

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314-582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-97 5 2/1 /2015 Tc-99 614 +/- 12 867 607- 1'127 Pass MAS0-975 2/1/2015 Cs-134 533 +/- 6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5+/-1.0 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 - 1,062 Pass MAS0-975 2/1/2015 Mn-54 1 ,153 +/- 9 1,198 839 - 1,557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 - 1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 - 30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 - 24.8 Pass MAW-969 ct 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 - 38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82-8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 - 23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23-4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104-0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 - 1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04-1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA c Pass MAAP-978 f 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06-1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass

-MAAP-978 2/1/2015 Mn-54 1.11 +/-0.08 1.02 0.71 -1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass A6-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3-61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/-0.12 0.00 NA c Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/-0.12 0.00 NA c Pass MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477-887 Pass 9

MAS0-4903 8/1/2015 Sr-90 231 +/-7 425 298-553 Fail 9

MAS0-4903 8/1/2015 Sr-90 352 +/- 10 425 298 -553 Pass MAS0-4903 h 8/1/2015 Tc-99 411 +/-11 631 442 -820 Fail MAS0~4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 -1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566- 1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 - 1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463 - 861 Pass A6-2

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30.0 Pass MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 NA c Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6-27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0-22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151.0-281.0 Pass MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0-11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 -18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 - 9.35 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 3.36-6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13-0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 - 1.94 Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79-5.17 Pass MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 -1.37 Pass MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78-2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 -7.54 Pass MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/-0.18 6.62 4.63 - 8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/-0.15 4.56 3.19-5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38-9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 -7.10 Pass a Results are reported in units of Bqlkg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of"zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

ct Lab result was 27 .84. Data entry error resulted in a non-acceptable result.

e Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

1 Lab result was 1.58. Data entry error resulted in a non-acceptable result.

9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

h The complex sample matrix is interfering with yield calculations causing a failed low result. An investigation is in process to determine a more reliable yield determination.

1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.

A6-3

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/- 2.2 49.8 30.7-67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2-98.8. Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 - 1'130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12 1,170 879 - 1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 - 1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 - 50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/- 3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 - 52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 - 145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21.3-51.7 Pass ERAP-1091 3/16/2015 U-238 31.0 +/- 1.1 34.0 22.0-47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 - 1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8-96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/- 0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 157.1.8 +/- 209.6 1,500 878 - 1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 - 1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474-2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180-7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1,140-1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810-14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 - 1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806 - 1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 - 6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 - 1,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1 '185 +/- 140 1,210 791-1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 - 3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/- 948 3,890 1,230 - 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,41 0 - 4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 - 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2- 184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900- 14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/- 266 4,340 2,650 - 5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 - 2,120 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060-2,150 Fail ERVE-1100 r 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060-2,150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/-27 2,650 1, 700 - 3,440 Fail ERVE-1100 r 3/16/2015 Cs-134 2,554 +/- 49 2,650 1, 700 - 3,440 Pass ERVE-1100° 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 - 2,520 Fail ERVE-1100 r 3/16/2015 Cs-137 2,078 +/- 68 1,810 1 ,310 - 2,520 Pass ERVE-11 00 e 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 - 43,400 Fail ERVE-1100 r 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass ERVE-11 00 e 3/16/2015 Mn-54 <13.8 <300 0.0-300.0 Pass ERVE-1100 r 3/16/2015 Mn-54 <24.4 <300 0.0- 300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/- 232 3,680 2,190 - 5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570-5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/- 326 6,590 3,760-8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 - 3,980 Pass ERVE-11 00 e 3/16/2015 Zn-65 <94.6 1,090 786 - 1,530 Fail ERVE-1100 r 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 - 1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0-61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/- 17 1,250 1,090 - 1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925- 1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1,150 - 1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 - 100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 - 90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 - 232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/- 4.9 97.7 66.6 - 108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 - 79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 - 75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/- 136 1,180 984 - 1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 - 1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 - 1,210.0 Pass

  • Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).

  • Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

  • Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).

9 The results of reanalysis were outside the control limits (low).

h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range.

The results for ERW-37 42 were acceptable. No reason for the unacceptable results for ERW-37 42 was determined.

A7-2

APPENDIX B. DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample.

3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. :

3.1 Individual results: For two analysis results; x 1 +/- s 1 and x2 +/- s 2 Reported result: x +/- s; where x == (1/2) (x 1 + x2 ) and s == (1/2) ~ s~ + s; 3.2. Individual results: < L1 , < L2 Reported result: < L, where L == lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- 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 ~nnual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1 , x2 . . . xn are defined as follows:

X

- 1

=r; LX s-

-A~ \jnT 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 number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

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

B-1

APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a

background in unrestricted areas .

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

-3 Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 c

Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 X 10 a

Taken from Table 2 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-1

APPENDIX D Sampling Location Maps D-1

1 I

I III iI I

Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2)

D-2

Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2)

D-3

Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2)

D-4

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D-5

Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2)

D-6

APPENDIX E Ground Water Monitoring Well Samples E-1

1.0 INTRODUCTION

This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January - December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.

E-2

2.0

SUMMARY

Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07.

This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater. The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater. Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or AREOR(REM~ffiports.

Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report.

The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8').

Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1.

Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.

Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.

The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized. In practice, samples were counted to an even lower level, approximately 150 pCi/L.

Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property. Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L.

Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public.

No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015.

A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4.

E-3

3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.

3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.

Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.

3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:

Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity.

Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells.

3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015.

E-4

3.5 Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911

+/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1.

Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume.

Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A.

The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank.

The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.

E-5

Table E-1. Sample Collection and Analysis Program, Ground Water.

Medium Number Sample Codes Collection type Analysis Type Ground Water 32 MW-1, MW-2, MW-3, MW-4, Grab H-3 Quarterly MW-98, MW-11, MW-12A, MW-128, 8

Ground Water 82 MW-9A, MW-10, MW-13A, Grab H-3 Monthly MW-138, MW-14, MW-15A MW-158, Ground Water 4 MW-5, MW-6, MW-7, MW-8 Grab H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well.

Table E-2. Sampling locations for Ground Water Monitoring Wells.

Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 sw Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9A 0.1 310 NW Ground Water M-51 MW-98 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-11 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-128 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-138 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW Ground Water M-53 MW-15A 0.14 14 NNE Ground Water M-54 MW-158 0.14 14 NNE E-6

Table E-3. Ground Water Monitoring Program Summary.

Name of Facility Monticello Nuclear Generating Plant Docket No. ...:5..:0...:-2:..:6...:.3-------,----

Location of Facility Wright, Minnesota Reporting Period January-December, 2015

( County, State )

Indicator Location with Highest Sample Type and ,. Locations Annual Mean 0

Type Number of LLDb Mean (F) Mean (F)"

(Units) Analyses' Range* Locationd Range*

Groundwater H-3 118 300 603 (47/118) MW-9A, On-site, 1985 (10/13)

Monitoring Wells (144-6493) 0.1 mi@310"/NW (182-6493)

(pCi/L)

Stormwater H-3 4 300 157(1/4) SD-006 157(1/4)

Runoff On-site (pCi/L) GS 4 Mn-54 10 < LLD - -

Fe-59 30 < LLD - -

Co-58 10 < LLD - -

Co-60 10 < LLD - -

Zn-65 30 < LLD - -

Zr-Nb-95 15 < LLD - -

1-131 30 < LLD - -

Cs-134 10 < LLD - -

Cs-137 10 < LLD - -

Ba-La-140 15 < LLD - -

Ce-144 43 < LLD - -

Sewer lift H-3 2 300 < LLD - -

Station (pCi/L) GS 2 Mn-54 10 < LLD - -

Fe-59 30 < LLD - -

Co-58 10 < LLD - -

Co-60 10 < LLD - -

Zn-65 30 < LLD - -

Zr-Nb-95 15 < LLD - -

1-131 30 < LLD - -

Cs-134 10 < LLD - -

Cs-137 10 < LLD - -

Ba-La-140 15 < LLD - -

Ce-144 43 < LLD - -

'GB = gross beta, GS =gamma scan.

b 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: (1) by name, and/or station code 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.

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Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes.

Collection Concentration (pCi/L)

ZrNb 13<cs 137cs 14oBala 1<<ce 3H s*Mn ssFe ssco so co sszn 95 Lab Code Date Monitoring Well #1 (M-33)

MWW- 705 02/24/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 2562 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 4755 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 26 MWW- 6609 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 15 Monitoring Well #2 (M-34)

MWW- 706 02/24/15 169 +/- 80 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 25 MWW- 2563 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 33 MWW- 4756 08/24/15 < 150 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 6610 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 47 Monitoring Well #3 (M-35)

MWW- 707 02/24/15 218 +/- 82 < 10 < 30 < 10 < 10 < 30 <15 < 10 <10 < 15 < 33 MWW- 2565 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 16 MWW- 4757 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 MWW- 6612 11/18/15 248 +/- 90 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 46 Monitoring Well #4 (M-36)

MWW- 708 02/20/15 < 146 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 37 MWW- 2566 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 34 MWW- 5243 09/23/15 < 144 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 <56 MWW- 6613 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 < 29 Monitoring Well #5 (M-37)

MWW- 4758 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 Monitoring Well #6 (M-38)

MWW- 4759 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 10 Monitoring Well #7 (M-39)

MWW- 4760 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 Monitoring Well #8 (M-40).

MWW- 4761 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 E-9

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCiiL)

Lab Code Date Monitoring Well #9A (M-44)

MWW- 250 01121115 2556 +/- 199 MWW- 709 02120115 667 +/- 103 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 23 MWW- 1199 03117115 282 +/- 85 MWW- 1896 04122115 < 147 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 22 MWW- 2567 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 26 MWW- 3147 06118/15 361 +/- 89 MWW- 4087 07121115 5443 +/- 226 MWW- 4772 08121115 6493 +/- 237 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5398 09122115 1857 +/- 145 MWW- 6096 10120115 353 +/- 95 MWW- 6614 11117115 182 +/- 87 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 7260 12115115 1652 +/- 135 Monitoring Well #98 (M-51)

MWW- 710 02120115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 23 MWW- 2568 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 18 MWW- 4773 08121115 < 173 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 20 MWW- 6615 11117115 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 18 Monitoring Well #1 0 (M-45)

MWW- 252 01121115 251+/-110 MWW- 711 02124115 381 +/- 90 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 1138 03117115 453 +/- 98 MWW- 1897 04122115 283 +/- 88 MWW- 2569 05121115 352 +/- 106 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 20 MWW- 3148 06118115 250 +/- 84 MWW- 4273 07123115 180 +/- 88 MWW- 4762 08124115 236 +/- 100 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5244 09123115 293 +/- 86 MWW- 5938 10120115 270 +/- 90 MWW- 6616 11118115 258 +/- 91 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 34 MWW- 7061 12115115 155 +/- 79 Monitoring Well #11 (M-46)

MWW- 712 02124115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 47 MWW- 2570 05121115 < 151 < 10 < 30 <10 <10 < 30 <15 <10 <10 < 15 < 26 MWW- 4763 08124115 260 +/- 101 < 10 < 30 <10 <10 < 30 <15 <10 <10 <15 < 33 MWW- 6617 11118115 < 149 < 10 < 30 <10 <10 < 30 <15 <10 <10 <15 < 26 Monitoring Well #12A (M-47)

MWW- 713 02120115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 27 MWW- 2571 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 16 MWW- 4764 08125115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 22 MWW- 6618 11117115 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 30 a Station duplicate sent. MWW-251 result= 2523+/-198 pCi/L.

E-10

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)

Lab Code Date Monitoring Well #128 (M-48)

MWW- 714 02/20/15 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 25 MWW- 2572 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 26 MWW- 4765 08/25/15 < 173 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 32 MWW- 6619 11/17/15 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 <28 Monitoring Well #13A (M-49)

MWW- 254 01/21/15 < 182 MWW- 715 02/24/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 1139 03/17/15 < 153 MWW- 1898 04/22/15 < 147 MWW- 2573 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 3149 06/18/15 < 143 MWW- 4274 07/27/15 153 +/- 87 MWW- 4766 08/25/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5245 09/23/15 255 +/- 84 MWW- 5939 10/20/15 161 +/- 85 MWW- 6620 11/18/15 182 +/- 87 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 7062 12/15/15 < 146 Monitoring Well #138 (M-50)

MWW- 255 01/21/15 < 182 MWW- 717 02/24/15 203 +/- 81 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 33 MWW- 1140 03/17/15 220 +/- 87 MWW- 1899 04/22/15 240 +/- 85 MWW- 2574 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 MWW- 3893 06/18/15 215 +/- 88 MWW- 4767 08/25/15 172 +/- 83 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 MWW- 5246 09/23/15 184 +/- 81 MWW- 5940 10/20/15 169 +/- 86 MWW- 6621 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 20 MWW- 7064 12/15/15 < 146 Monitoring Well #14 (M-52)

MWW- 256 01/21/15 < 182 MWW- 718 02/16/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 MWW- 1900 04/21/15 < 147 MWW- 2575 05/19/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 MWW- 3150 06/16/15 < 143 MWW- 4275 07/20/15 < 151 MWW- 4769 08/17/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 5247 09/23/15 < 142 MWW- 5941 10/20/15 < 147 MWW- 6622 11/16/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 7065 12/14/15 < 146 E-11

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L) 54 sgFe sa co so co ZrNb 134cs 137Cs 14oBala 144ce 3H sszn 95 Lab Code Date Mn Monitoring Well #15A (M-53)

MWW- 257 01/21/15 < 182 MWW- 719 02/20/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 32 MWW- 1141 03/17/15 < 153 MWW- 1901 04/22/15 < 147 MWW- 2576 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 3151 06/18/15 < 143 MWW- 4276 07/23/15 < 151 MWW- 4770 08/25/15 < 173 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 5248 09/23/15 < 142 MWW- 5942 10/20/15 < 147 MWW- 6623 11/18/15 < 149 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 MWW- 7066 12/15/15 < 146 Monitoring Well #158 (M-54)

MWW- 258 01/21/15 206 +/- 108 MWW- 720 02/20/15 180 +/- 80 < 10 < 30 < 10 <10 < 30 <15 < 10 <10 < 15 < 21 MWW- 1142 03/17/15 203 +/- 87 MWW- 1902 04/22/15 228 +/- 85 MWW- 2577 05/20/15 < 151 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 3152 06/18/15 144 +/- 79 MWW- 4277 07/24/15 275 +/- 92 MWW- 4771 08/25/15 199 +/- 99 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 MWW- 5249 09/23/15 249 +/- 84 MWW- 5943 '10/20/15 161 +/- 85 MWW- 6624 11/18/15 217 +/- 89 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 28 MWW- 7067 12/15/15 < 146 Storm Water Run-off (SD-006)

MXW- 2384 04/24/15 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 <8 MXW- 2385 04/24/15 < 147 < 10 < 30 < 10 <10 < 30 < 15 <10 <10 < 15 < 10 a MXW- 4163 07/28/15 157 +/- 85 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 17 MXW- 6250 10/23/15 < 143 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 32 Storm Water Run-off (Sewer Lift Station)

MXW- 2091 04/27/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 16 MXW- 6887 12/03/15 < 145 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 15 Station duplicate.

E-12

Table E-4. Ground water, analyses for hard to detect isotopes.

Collection Concentration (pCi/L}

Lab Code Date Location Gross Alpha MWW- 1896 04/22/15 MW-9a < 1.6 < 4.1 < 3.3 < 674 < 101 E-13

Environmental, Inc.

I Midwest laboratory 700 Landwehr Ro'd , Northbrook, ll60062*1310 phone (847) 564.0700. fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO 50-263 LICENSE NO DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PART II Radiological Environmental Monitoring Program Complete Analyses Data Tables January- December, 2015 Prepared under contract by ENVIRONMENTAL, INC MIDWEST LABORATORY PROJECT NO 8010 Reviewed and Approved

MNGP TABLE OF CONTENTS Section Page List of Tables................................................................................................................... iii 10 INTRODUCTION ............................................................................................................. iv 20 LISTING OF MISSED SAMPLES .................................................................................. . v 30 DATA TABLES ................................................................................................................ vi ii

MNGP LIST OF TABLES Ambient radiation as measured by thermoluminescent dosimeters (TLDs) .... ...... ...... ...... ........... 1-1 2 Airborne particulates and iodine collected at Location M-1 (C), analysis for gross beta and iodine-131 ............................................................................................................... 2-1 3 Airborne particulates and iodine collected at Location M-2, analysis for gross beta and iodine-131 ...................................................................................................................... 3-1 4 Airborne particulates and iodine collected at Location M-3, analysis for gross beta and iodine-131 ...................................................................................................................... 4-1 5 Airborne particulates and iodine collected at Location M-4, analysis for gross beta and iodine-131 ...................................................................................................................... 5-1 6 Airborne particulates and iodine collected at Location M-5, analysis for gross beta and iodine-131 ......................................................................... ............................................. 6-1 7 Airborne particulates, analysis for gross beta, monthly averages................................................ 7-1 8 Airborne particulate samples, quarterly composites from each location, analysis for gamma-emitting isotopes.............................................................................................. 8-1 9 Pasture Grass, vegetation, analysis for iodine-131 and gamma emitting isotopes...................... 9-1 10 River water, upstream, M-8 (C) and M-9, analysis of monthly composites for gamma-emitting isotopes............................................................................................................ 10-1 11 Drinking water, City of Minneapolis, M-14, analysis of monthly composites for gross beta, iodine-131 and gamma-emitting isotopes............................................................. 11-1 12 River water and drinking water, analysis of quarterly composites for tritium................................ 12-1 13 Well water, analysis for tritium and gamma-emitting isotopes..................................................... 13-1 14 Fish, analysis of edible portions for gamma-emitting isotopes..................................................... 14-1 15 Aquatic Invertebrates, analysis for gamma-emitting isotopes...................................................... 15-1 16 Shoreline sediments, analysis for gamma-emitting isotopes....................................................... 16-1 iii

MNGP 10 INTRODUCTION The following constitutes the final 2015 report for the Environmental Radiological Monitoring Program conducted at the Monticello Nuclear Generating Plant in Monticello, Minnesota Results of completed analyses are presented in the attached tables All concentrations, except gross beta, are decay corrected to the time of collection All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples iv

MNGP 20 LISTING OF MISSED SAMPLES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting Plans for Preventing Type Period REMP as Recurrence required AP/AI Beta, 1-131 M-005 1/28/2015 Power was reset Power loss at sample station sw Gamma M-008 January '15 Water frozen entire month; None no composite AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running Replaced air sampler due to bad switch sw Gamma M-008 February '15 Water frozen entire month; None no composite sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None AP/AI Beta, 1-131 M-002 5/6/2015 Air sampler not running Replaced air sampler TLD Gamma M-06B 2nd Qtr '15 TLD missing in field Replaced TLD AP/AI Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped Reset GFC sw Gamma M-008 12/30/15 Water frozen None v

MNGP 30 DATA TABLES vi

MNGP Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's).

Previous mRem/91 days Cumulative Annual Location 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average Indicators (Inner Ring, General Area of Site Boundary)

M-01A 15.6 +/- 0.8 14.3 +/- 1.2 16.7 +/- 1.5 16.6+/-2.1 15.8 13.7 M-02A 13.4 +/- 1.2 13.8 +/- 0.5 13.9+/-1.2 15.3+/-1.0 14.1 14.2 M-03A 14.8+/-1.3 13.2 +/- 1.0 13.3+/-1.3 16.4+/-1.7 14.4 13.4 M-04A 9.6 +/- 0.9 15.3 +/- 0.7 10.9 +/- 1.5 17.9+/-1.8 13.4 13.5 M-05A 14.2 +/- 0.6 12.2 +/- 0.5 15.2 +/- 0.8 13.2 +/- 1.0 13.7 12.6 M-06A 15.3 +/- 0.5 16.5 +/- 0.5 15.7+/-1.1 18.9+/-1.1 16.6 14.0 M-07A 9.8 +/- 0.6 13.7 +/- 0.5 11.1 +/-0.9 15.3+/-1.0 12.5 11.6 M-08A 12.1 +/- 0.7 15.1 +/-0.5 14.9 +/- 0.9 17.4 +/- 0.9 14.9 13.4 M-09A 14.3 +/- 0.5 12.4 +/- 0.8 13.7 +/- 0.9 16.0 +/- 1.2 14.1 12.4 M-10A 12.9 +/- 1.0 13.7 +/- 0.6 13.9+/-0.9 16.2+/-1.3 14.2 13.4 M-11A 15.8+/-0.8 16.3 +/- 0.9 16.8 +/- 1.1 19.6 +/- 1.4 17.1 14.5 M-12A 14.7 +/- 0.8 15.9 +/- 0.5 15.7 +/- 1.3 19.3+/-1.0 16.4 13.9 M-13A 13.8 +/- 0.9 14.6 +/- 0.9 15.0+/-1.2 16.8 +/- 1.2 15.1 14.5 M-14A 15.2 +/- 0.8 13.4 +/- 0.5 15.4+/-0.8 15.1 +/- 1.1 14.8 13.7 Mean+/- s.d. 13.7 +/- 2.0 14.3+/-1.4 14.4 +/- 1.8 16.7 +/- 1.8 14.8 13.5 Indicators (Outer Ring, 4-5 Miles Distant)

M-018 12.2 +/- 1.2 14.9 +/- 0.9 15.1 +/- 1.0 16.9 +/- 1.5 14.8 12.2 M-028 11.7 +/- 0.7 15.6 +/- 1.0 13.0 +/- 0.9 16.3+/-1.1 14.2 12.8 M-038 11.1 +/-0.8 11.0 +/- 0.6 11.2 +/- 0.9 13.5 +/- 1.2 11.7 11.1 M-048 12.4+/-0.7 12.1 +/-0.4 15.0 +/- 0.9 14.8 +/- 1.0 13.6 11.9 M-058 11.9 +/- 0.5 12.6 +/- 0.6 12.7 +/- 0.9 14.7+/-1.1 13.0 12.4 M-068 13.0+/-1.2 NDa 15.3 +/- 1.2 17.0+/-0.9 15.1 13.3 M-078 14.2 +/- 0.7 13.0+/-0.7 15.9+/-1.2 16.1+/-1.2 14.8 13.7 M-088 12.5 +/- 0.7 13.3 +/- 0.7 14.2 +/- 1.1 15.6 +/- 1.4 13.9 14.2 M-098 12.4+/-0.7 15.1 +/- 1.1 12.7 +/- 1.2 17.8 +/- 1.1 14.5 13.0 M-108 14.4+/-1.0 13.2 +/- 0.8 16.0 +/- 0.9 15.6 +/- 1.4 14.8 13.6 M-118 14.3+/-1.3 13.9 +/- 0.7 15.2 +/- 1.5 15.7+/-1.2 14.8 13.4 M-128 13.7+/-1.0 14.9 +/- 0.6 15.2 +/- 1.9 17.2 +/- 1.1 15.3 14.2 M-138 11.1 +/- 0.7 11.9 +/- 0.5 12.6 +/- 1.2 13.5+/-1.1 12.3 11.8 M-148 14.7+/-1.3 16.7+/-0.6 15.3 +/- 1.6 19.6+/-1.1 16.6 14.4 M-158 12.2 +/- 0.5 12.7 +/- 0.9 13.5+/-1.0 16.3 +/- 1.3 13.7 12.1 M-168 14.3 +/- 0.6 11.7+/-0.8 14.8 +/- 0.8 13.4 +/- 1.2 13.5 12.2 Mean+/- s.d. 12.9 +/- 1.2 13.5 +/- 1.6 14.2+/-1.4 15.9 +/- 1.7 14.2 12.9 a "NO" = No data; see Table 2.0, Listing of Missed Samples.

1-1

MNGP Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's),

(continued).

Previous mRem/91 days Cumulative Annual Location 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-01C 11.8 +/- 1.5 13.2 +/- 0.8 12.5 +/- 1.5 16.0 +/- 1.3 13.4 14.4 M-02C 15.9 +/- 0.8 16.6 +/- 1.4 17.4 +/- 0.9 20.3+/-1.1 17.5 14.1 M-03C 13.2 +/- 0.4 14.8 +/- 0.6 15.2+/-0.9 17.6+/-1.1 15.2 14.3 M-04C 14.7+/-1.7 14.0 +/- 0.5 15.1 +/-1.6 16.6+/-1.0 15.1 14.2 Mean+/- s.d. 13.9 +/- 1.8 14.6+/-1.5 15.1 +/- 2.0 17.6 +/- 1.9 15.3 14.3 Indicators (Special Interest Areas)

M-01S 10.4 +/- 1.0 12.5 +/- 0.5 9.4 +/- 1.4 13.9 +/- 0.9 11.6 10.3 M-02S 13.5 +/- 1.0 13.2 +/- 0.6 14.5 +/- 1.5 15.9+/-1.1 14.3 11.7 M-03S 12.2 +/- 0.7 14.7 +/- 0.7 13.2 +/- 1.1 17.0+/-1.2 14.3 13.0 M-04S 16.6+/-1.1 14.4 +/- 0.8 17.6 +/- 1.2 17.0+/-1.1 16.4 14.6 M-OSS 14.5 +/- 0.6 14.9 +/- 0.8 15.3+/-1.1 17.9+/-1.3 15.6 14.1 M-06S 15.2 +/- 0.7 15.5 +/- 0.5 15.2+/-1.1 18.8 +/- 1.1 16.2 15.6 Mean+/- s.d. 13.7+/-2.2 14.2 +/- 1.1 14.2 +/- 2.8 16.7 +/- 1.7 14.7 13.2 ISFSI TLDs M-1-01 39.4 +/- 1.2 26.7 +/- 2.0 42.8 +/- 2.0 41.7+/-2.4 37.7 36.1 M-1-02 36.4 +/- 1.2 24.3 +/- 0.6 38.1 +/- 1.2 36.9 +/- 1.1 33.9 29.8 M-1-03 29.6 +/- 1.0 23.2 +/- 1.1 32.4 +/- 1.3 31.9 +/- 1.3 29.3 25.6 M-1-04 36.7 +/- 2.6 34.4 +/- 2.4 29.2 +/- 2.6 37.7 +/- 2.7 34.5 35.6 M-1-05 80.3 +/- 5.0 67.3 +/- 3.1 68.3 +/- 4.6 79.5+/-2.1 73.9 65.9 M-1-06 30.3 +/- 2.4 21.6 +/- 0.8 30.0 +/- 2.2 25.4 +/- 1.3 26.8 25.0 M-1-07 30.3+/-1.4 27.5 +/- 1.7 31.1 +/-2.7 32.8 +/- 1.6 30.4 27.7 M-l-08 28.9 +/- 2.9 24.1+/-0.5 29.6 +/- 3.0 28.7 +/- 2.7 27.9 26.6 M-1-09 234.8 +/- 12.1 220.1 +/- 3.7 70.5 +/-4.1 61.3+/-2.7 146.6 170.5 M-1-10 43.3 +/- 1.7 28.6 +/- 1.3 41.6+/-1.2 35.3 +/- 1.6 37.2 33.2 M-1-11 12.4+/-1.7 15.1 +/- 0.5 13.1 +/- 1.7 16.7+/-1.2 14.3 13.9 M-1-12 14.1+/-0.7 14.3 +/- 0.6 15.2 +/- 0.9 15.4 +/- 1.3 14.7 13.9 M-1-13 17.1 +/- 1.3 12.8 +/- 0.8 15.6 +/- 2.0 16.6 +/- 1.6 15.5 13.5 Mean+/- s.d. 48.7 +/- 58.4 41.5 +/- 55.4 35.2 +/- 17.9 35.4 +/- 18.1 40.2 39.8 1-2

MNGP 3

Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

  • Location: M-1 (C) 3 Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m;;) Gross Beta Collected (mJ) Gross Beta Required LLD 0.010 Required LLD 0.010 01-07-15 319 0.041 +/- 0.004 07-08-15 443 0.022 +/- 0.003 01-14-15 321 0.042 +/- 0.004 07-15-15 443 0.024 +/- 0.003 01-21-15 323 0.036 +/- 0.004 07-22-15 441 0.018 +/- 0.002 01-28-15 315 0.021 +/- 0.003 07-29-15 439 0.026 +/- 0.003 02-04-15 357 0.029 +/- 0.003 08-05-15 440 0.019 +/- 0.003 02-11-15 389 0.033 +/- 0.003 08-12-15 305 0.027 +/- 0.004 02-18-15 354 0.044 +/- 0.004 08-19-15 353 0.031 +/- 0.004 02-25-15 354 0.062 +/- 0.004 08-26-15 337 0.022 +/- 0.003 09-02-15 353 0.038 +/- 0.004 03-04-15 352 0.036 +/- 0.004 03-11-15 353 0.025 +/- 0.004 09-09-15 352 0.028 +/- 0.003 03-18-15 392 0.019 +/- 0.003 09-16-15 302 0.033 +/- 0.004 03-25-15 352 0.024 +/- 0.003 09-23-15 352 0.025 +/- 0.003 04-01-15 354 0.018 +/- 0.003 09-30-15 326 0.039 +/- 0.004 1st Quarter Mean+/- s.d. 0.033 +/- 0.012 3rd Quarter Mean +/- s.d. 0.027 +/- 0.007 04-08-15 357 0.023 +/- 0.003 10-07-15 325 0.023 +/- 0.003 04-15-15 351 0.021 +/- 0.003 10-14-15 324 0.031 +/- 0.004 04-22-15 355 0.014 +/- 0.003 10-21-15 301 0.035 +/- 0.004 04-29-15 355 0.021 +/- 0.003 10-28-15 336 0.022 +/- 0.003 05-06-15 443 0.021 +/- 0.003 11-04-15 397 0.025 +/- 0.003 05-13-15 440 0.008 +/- 0.002 11-11-15 351 0.039 +/- 0.004 05-20-15 447 0.010 +/- 0.002 11-18-15 353 0.033 +/- 0.004 05-27-15 435 0.018 +/- 0.003 11-25-15 387 0.022 +/- 0.003 06-03-15 442 0.018 +/- 0.002 12-02-15 382 0.044 +/- 0.004 06-10-15 441 0.016 +/- 0.002 12-09-15 350 0.061 +/- 0.005 06-17-15 441 0.013 +/- 0.002 12-16-15 353 0.016 +/- 0.003 06-24-15 351 0.021 +/- 0.003 12-23-15 354 0.044 +/- 0.004 07-01-15 441 0.019 +/- 0.003 12-30-15 384 0.040 +/- 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.005 4th Quarter Mean +/- s.d. 0.034 +/- 0.012 Cumulative Average 0.028 Previous Annual Average 0.032 3

a lodine-131 concentrations are< 0.03 pCi/m unless otherwise noted.

2-1

MNGP Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-2 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Reguired LLD 0.010 0.010 01-07-15 352 0.038 +/- 0.004 07-08-15 341 0.025 +/- 0.003 01-14-15 326 0.038 +/- 0.004 07-15-15 341 0.023 +/- 0.003 01-21-15 329 0.031 +/- 0.003 07-22-15 325 0.019 +/- 0.003 01-28-15 321 0.021 +/- 0.003 07-29-15 350 0.024 +/- 0.003 02-04-15 NDb 08-05-15 353 0.017 +/- 0.003 02-11-15 322 0.040 +/- 0.004 08-12-15 330 0.025 +/- 0.003 02-18-15 325 0.048 +/- 0.004 08-19-15 342 0.031 +/- 0.004 02-25-15 326 0.073 +/- 0.005 08-26-15 326 0.025 +/- 0.003 09-02-15 342 0.038 +/- 0.004 03-04-15 324 0.035 +/- 0.004 03-11-15 351 0.027 +/- 0.004 09-09-15 348 0.027 +/- 0.003 03-18-15 328 0.025 +/- 0.004 09-16-15 318 0.033 +/- 0.004 03-25-15 323 0.027 +/- 0.004 09-23-15 337 0.024 +/- 0.003 04-01-15 352 0.019 +/- 0.003 09-30-15 318 0.037 +/- 0.004 1st Quarter Mean+/- s.d. 0.035 +/- 0.015 3rd Quarter Mean+/- s.d. 0.027 +/- 0.006 04-08-15 330 0.023 +/- 0.003 10-07-15 314 0.023 +/- 0.003 04-15-15 349 0.027 +/- 0.003 10-14-15 315 0.027 +/- 0.004 04-22-15 325 0.017 +/- 0.003 10-21-15 314 0.029 +/- 0.004 04-29-15 329 0.021 +/- 0.003 10-28-15 263 0.028 +/- 0.004 05-06-15 NDb 11-04-15 353 0.027 +/- 0.003 05-13-15 351 0.010 +/- 0.002 11-11-15 352 0.045 +/- 0.004 05-20-15 358 0.011 +/- 0.002 11-18-15 326 0.037 +/- 0.004 05-27-15 347 0.019 +/- 0.003 11-25-15 327 0.025 +/- 0.004 06-03-15 351 0.019 +/- 0.003 12-02-15 327 0.051 +/- 0.005 06-10-15 353 0.019 +/- 0.003 12-09-15 328 0.066 +/- 0.005 06-17-15 352 0.014 +/- 0.003 12-16-15 326 0.021 +/- 0.003 06-24-15 354 0.018 +/- 0.003 12-23-15 304 0.051 +/- 0.005 07-01-15 340 0.020 +/- 0.003 12-30-15 324 0.050 +/- 0.005 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.037 +/- 0.014 Cumulative Average 0.029 Previous Annual Average 0.028 3

a lodine-131 concentrations are < 0.03 pCi/m unless otherwise noted.

b "NO" = No data, see Table 2.0, Listing of Missed Samples.

3-1

MNGP Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-3 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Required LLD 0.010 0.010 01-07-15 326 0.041 +/- 0.004 07-08-15 409 0.019 +/- 0.003 01-14-15 353 0.042 +/- 0.004 07-15-15 409 0.019 +/- 0.003 01-21-15 357 0.034 +/- 0.003 07-22-15 380 0.021 +/- 0.003 01-28-15 348 0.020 +/- 0.003 07-29-15 324 0.030 +/- 0.004 02-04-15 357 0.029 +/- 0.003 08-05-15 407 0.021 +/- 0.003 02-11-15 351 0.057 +/- 0.004 08-12-15 369 0.027 +/- 0.003 02-18-15 353 0.048 +/- 0.004 08-19-15 342 0.033 +/- 0.004 02-25-15 353 0.066 +/- 0.004 08-26-15 339 0.022 +/- 0.003 09-02-15 342 0.044 +/- 0.004 03-04-15 378 0.035 +/- 0.004 03-11-15 379 0.024 +/- 0.003 09-09-15 342 0.028 +/- 0.003 03-18-15 383 0.022 +/- 0.003 09-16-15 344 0.031 +/- 0.004 03-25-15 350 0.028 +/- 0.004 09-23-15 337 0.025 +/- 0.003 04-01-15 352 0.020 +/- 0.003 09-30-15 346 0.037 +/- 0.004 1st Quarter Mean+/- s.d. 0.036 +/- 0.015 3rd Quarter Mean +/- s.d. 0.027 +/- 0.007 04-08-15 358 0.023 +/- 0.003 10-07-15 340 0.025 +/- 0.003 04-15-15 349 0.024 +/- 0.003 10-14-15 315 0.035 +/- 0.004 04-22-15 352 0.015 +/- 0.003 10-21-15 314 0.031 +/- 0.004 04-29-15 357 0.020 +/- 0.003 10-28-15 316 0.028 +/- 0.004 05-06-15 350 0.025 +/- 0.003 11-04-15 329 D.030 +/- 0.004 05-13-15 380 0.007 +/- 0.002 11-11-15 329 0.047 +/- 0.004 05-20-15 385 0.012 +/- 0.002 11-18-15 304 0.041 +/- 0.004 05-27-15 400 0.018 +/- 0.003 11-25-15 328 0.025 +/- 0.004 06-03-15 378 0.017 +/- 0.003 12-02-15 328 0.053 +/- 0.005 06-10-15 380 0.019 +/- 0.003 12-09-15 306 0.082 +/- 0.006 06-17-15 352 0.013 +/- 0.003 12-16-15 331 0.019 +/- 0.003 06-24-15 382 0.018 +/- 0.003 12-23-15 387 0.041 +/-0.004 07-01-15 340 0.021 +/- 0.003 12-30-15 301 0.057 +/- 0.005 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.040 +/- 0.017 Cumulative Average 0.030 Previous Annual Average 0.027 a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted.

4-1

MNGP Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-4 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 0.010 01-07-15 352 0.035 +/- 0.003 07-08-15 409 0.021 +/- 0.003 01-14-15 353 0.040 +/- 0.004 07-15-15 406 0.024 +/- 0.003 01-21-15 356 0.033 +/- 0.003 07-22-15 383 0.018 +/- 0.003 01-28-15 347 0.021 +/- 0.003 07-29-15 405 0.027 +/- 0.003 02-04-15 355 0.034 +/- 0.003 08-05-15 407 0.018 +/- 0.003 02-11-15 350 0.042 +/- 0.004 08-12-15 329 0.027 +/- 0.003 02-18-15 326 0.047 +/- 0.004 08-19-15 328 0.039 +/- 0.004 02-25-15 327 0.070 +/- 0.005 08-26-15 326 0.024 +/- 0.003 09-02-15 352 0.044 +/- 0.004 03-04-15 350 0.039 +/- 0.004 03-11-15 350 0.023 +/- 0.003 09-09-15 351 0.030 +/- 0.003 03-18-15 330 0.028 +/- 0.004 09-16-15 331 0.037 +/- 0.004 03-25-15 324 0.029 +/- 0.004 09-23-15 350 0.027 +/- 0.003 04-01-15 326 0.021 +/- 0.003 09-30-15 329 0.044 +/- 0.004 1st Quarter Mean+/- s.d. 0.036 +/- 0.013 3rd Quarter Mean +/- s.d. 0.029 +/- 0.009 04-08-15 331 0.024 +/- 0.003 10-07-15 327 0.026 +/- 0.003 04-15-15 323 0.025 +/- 0.003 10-14-15 327 0.040 +/- 0.004 04-22-15 327 0.014 +/- 0.003 10-21-15 327 0.033 +/- 0.004 04-29-15 329 0.023 +/- 0.003 10-28-15 329 0.031 +/- 0.004 05-06-15 407 0.023 +/- 0.003 11-04-15 356 0.032 +/- 0.004 05-13-15 405 0.009 +/- 0.002 11-11-15 350 0.038 +/- 0.004 05-20-15 413 0.011 +/- 0.002 11-18-15 352 0.039 +/- 0.004 05-27-15 401 0.019 +/- 0.003 11-25-15 352 0.024 +/- 0.003 06-03-15 407 0.018 +/- 0.003 12-02-15 352 0.050 +/- 0.004 06-10-15 391 0.017 +/- 0.003 12-09-15 352 0.068 +/- 0.005 06-17-15 404 0.014 +/- 0.002 12-16-15 351 0.022 +/- 0.003 06-24-15 NOb 12-23-15 328 0.051 +/- 0.005 07-01-15 397 0.019 +/- 0.003 12-30-15 350 0.054 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.039 +/- 0.013 Cumulative Average 0.031 Previous Annual Average 0.028 3

a lodine-131 concentrations are < 0.03 pCi/m unless otherwise noted.

b "NO" No data; see Table 2.0, Listing of Missed Samples.

5-1

MNGP Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-5 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Required LLD 0.010 0.010 01-07-15 323 0.046 +/- 0.004 07-08-15 370 0.023 +/- 0.003 01-14-15 324 0.042 +/- 0.004 07-15-15 370 0.021 +/- 0.003 01-21-15 323 0.038 +/- 0.004 07-22-15 352 0.019 +/- 0.003 01-28-15 NOb 07-29-15 351 0.027 +/- 0.003 02-04-15 356 0.031 +/- 0.003 08-05-15 382 0.021 +/- 0.003 02-11-15 352 0.038 +/- 0.004 08-12-15 341 0.024 +/- 0.003 02-18-15 294 0.054 +/- 0.005 08-19-15 352 0.032 +/- 0.004 02-25-15 324 0.071 +/- 0.005 08-26-15 324 0.022 +/- 0.003 09-02-15 326 0.047 +/- 0.004 03-04-15 351 0.034 +/- 0.004 03-11-15 352 0.023 +/- 0.003 09-09-15 271 0.037 +/- 0.004 03-18-15 326 0.024 +/- 0.004 09-16-15 301 0.035 +/- 0.004 03-25-15 292 0.030 +/- 0.004 09-23-15 325 0.028 +/- 0.004 04-01-15 352 0.018 +/- 0.003 09-30-15 298 0.045 +/- 0.005 1st Quarter Mean+/- s.d. 0.038 +/- 0.015 3rd Quarter Mean +/- s.d. 0.029 +/- 0.009 04-08-15 298 0.024 +/- 0.004 10-07-15 298 0.025 +/- 0.004 04-15-15 291 0.027 +/- 0.004 10-14-15 298 0.039 +/- 0.004 04-22-15 324 0.016 +/- 0.003 10-21-15 297 0.036 +/- 0.004 04-29-15 326 0.022 +/- 0.003 10-28-15 326 0.025 +/- 0.004 05-06-15 384 0.022 +/- 0.003 11-04-15 359 0.029 +/- 0.003 05-13-15 381 0.009 +/- 0.002 11-11-15 367 0.043 +/- 0.004 05-20-15 387 0.011 +/- 0.002 11-18-15 252 0.032 +/- 0.005 05-27-15 378 0.016 +/- 0.003 11-25-15 354 0.025 +/- 0.003 06-03-15 382 0.019 +/- 0.003 12-02-15 323 0.050 +/- 0.005 06-10-15 382 0.017 +/- 0.003 12-09-15 323 0.088 +/- 0.006 06-17-15 380 0.012 +/- 0.002 12-16-15 353 0.015 +/- 0.003 06-24-15 353 0.020 +/- 0.003 12-23-15 295 0.048 +/- 0.005 07-01-15 368 0.019 +/- 0.003 12-30-15 352 0.050 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.039 +/- 0.018 Cumulative Average 0.031 Previous Annual Average 0.031 3

a lodine-131 concentrations are< 0.03 pCi/m unless otherwise noted.

b "NO"= No data, see Table 2.0, Listing of Missed Samples.

6-1

MNGP Table 7. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

January April Location Average Minima Maxima Location Average Minima Maxima Control 0.035 0.021 0.042 Control 0.020 0.014 0.023 M-1 0.035 0.021 0.042 M-1 0.020 0.014 0.023 Indicators 0.035 0.020 0.046 Indicators 0.022 0.014 0.027 M-2 0.032 0.021 0.038 M-2 0.022 0.017 0.027 M-3 0.034 0.020 0.042 M-3 0.020 0.015 0.024 M-4 0.032 0.021 0.040 M-4 0.022 0.014 0.025 M-5 0.042 0.038 0.046 M-5 0.022 0.016 0.027 February May Location Average Minima Maxima Location Average Minima Maxima Control 0.042 0.029 0.062 Control 0.015 0.008 0.021 M-1 0.042 0.029 0.062 M-1 0.015 0.008 0.021 Indicators 0.050 0.029 0.073 Indicators 0.015 0.007 0.025 M-2 0.054 0.040 0.073 M-2 0.015 0.010 0.019 M-3 0.050 0.029 0.066 M-3 0.016 0.007 0.025 M-4 0.048 0.034 0.070 M-4 0.016 0.009 0.023 M-5 0.049 0.031 0.071 M-5 0.016 0.009 0.022 March June Location Average Minima Maxima Location Average Minima Maxima Control 0.024 0.018 0.036 Control 0.017 0.013 0.021 M-1 0.024 0.018 0.036 M-1 0.017 0.013 0.021 Indicators 0.027 0.018 0.039 Indicators 0.017 0.012 0.021 M-2 0.027 0.019 0.035 M-2 0.018 0.014 0.020 M-3 0.026 0.020 0.035 M-3 . 0.018 0.013 0.021 M-4 0.028 0.021 0.039 M-4 0.017 0.014 0.019 M-5 0.026 0.018 0.034 M-5 0.017 0.012 0.020 Note: unless otherwise specified, samples collected on the first, second or third day of the month are grouped with data of the previous month.

7-1

MNGP Table 7. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

July October Location Average Minima Maxima Location Average Minima Maxima Control 0.023 0.018 0.026 Control 0.028 0.022 0.035 M-1 0.023 0.018 0.026 M-1 0.028 0.022 0.035 Indicators 0.022 0.018 0.030 Indicators 0.030 0.023 0.040 M-2 0.023 0.019 0.025 M-2 0.027 0.023 0.029 M-3 0.022 0.019 0.030 M-3 0.030 0.025 0.035 M-4 0.022 0.018 0.027 M-4 0.032 0.026 0.040 M-5 0.022 0.019 0.026 M-5 0.031 0.025 0.039 August November Location Average Minima Maxima Location Average Minima Maxima Control Control 0.033 0.022 0.044 M-1 0.027 0.019 0.038 M-1 0.033 0.022 0.044 Indicators 0.029 0.017 0.047 Indicators 0.037 0.024 0.053 M-2 0.027 0.017 0.038 M-2 0.037 0.025 0.051 M-3 0.029 0.021 0.044 M-3 0.039 0.025 0.053 M-4 0.031 0.018 0.044 M-4 0.037 0.024 0.050 M-5 0.029 0.021 0.047 M-5 0.036 0.025 0.050 September December Location Average Minima Maxima Location Average Minima Maxima Control Control 0.040 0.016 0.061 M-1 0.031 0.025 0.039 M-1 0.040 0.016 0.061 Indicators 0.033 0.024 0.045 Indicators 0.049 0.015 0.088 M-2 0.030 0.024 0.037 M-2 0.048 0.021 0.066 M-3 0.030 0.025 0.037 M-3 0.050 0.019 0.082 M-4 0.034 0.027 0.044 M-4 0.048 0.022 0.068 M-5 0.036 0.028 0.045 M-5 0.050 0.015 0.088 Note: unless otherwise specified, samples collected on the first, second or third day of the month are grouped with data of the previous month.

7-2

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCi/m )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-1 (C)

Lab Code MAP- 1842 MAP- 3819 MAP- 6030 MAP- 7410 3

Volume(m ) 4534 5299 4884 4597 Be-7 0.065 +/- 0.013 0.077 +/- 0.010 0.077 +/- 0.012 0.043 +/- 0.010 0.066 0.068 Mn-54 < 0.0005 < 0.0004 < 0.0005 < 0.0003 <0.0005 <0.0008 Co-58 < 0.0007 < 0.0004 < 0.0005 < 0.0004 <0.0007 <0.0010 Co-60 < 0.0009 < 0.0004 < 0.0005 < 0.0002 <0.0009 <0.0006 Zn-65 < 0.0011 < 0.0005 < 0.0012 < 0.0010 <0.0012 <0.0011 Zr-Nb-95 < 0.0007 < 0.0006 < 0.0008 < 0.0008 <0.0008 <0.0015 Ru-1 03 < 0.0008 < 0.0008 < 0.0008 < 0.0005 <0.0008 <0.0008 Ru-1 06 < 0.0049 < 0.0027 < 0.0036 < 0.0043 <0.0049 <0.0063 Cs-134 < 0.0006 < 0.0006 < 0.0005 < 0.0006 <0.0006 <0.0011 Cs-137 < 0.0006 < 0.0005 < 0.0006 < 0.0004 <0.0006 <0.0007 Ba-La-140 < 0.0017 < 0.0017 < 0.0015 < 0.0014 <0.0017 <0.0021 Ce-141 < 0.0010 < 0.0008 < 0.0015 < 0.0010 <0.0015 <0.0016 Ce-144 < 0.0033 < 0.0034 < 0.0028 < 0.0022 <0.0034 <0.0046 M-2 Lab Code MAP- 1843 MAP- 3820 MAP- 6031 MAP- 7411 3

Volume(m ) 4338 4138 4370 4173 Be-7 0.070 +/- 0.011 0.079 +/- 0.013 0.072 +/- 0.013 0.051 +/- 0.012 0.068 0.064 Mn-54 < 0.0006 < 0.0008 < 0.0008 < 0.0011 <0.0008 <0.0008 Co-58 < 0.0004 < 0.0005 < 0.0008 < 0.0006 <0.0008 <0.0010 Co-60 < 0.0004 < 0.0005 < 0.0007 < 0.0004 <0.0007 <0.0008 Zn-65 < 0.0017 < 0.0007 < 0.0008 < 0.0014 <0.0017 <0.0015 Zr-Nb-95 < 0.0009 < 0.0011 < 0.0007 < 0.0010 <0.0011 <0.0010 Ru-1 03 < 0.0007 < 0.0006 < 0.0012 < 0.0010 <0.0012 <0.0014 Ru-1 06 < 0.0061 < 0.0085 < 0.0074 < 0.0046 <0.0085 <0.0077 Cs-134 < 0.0007 < 0.0009 < 0.0008 < 0.0008 <0.0009 <0.0010 Cs-137 < 0.0006 < 0.0006 < 0.0010 < 0.0005 <0.0010 <0.0008 Ba-La-140 < 0.0015 < 0.0019 < 0.0024 < 0.0021 <0.0024 <0.0042 Ce-141 < 0.0017 < 0.0010 < 0.0018 < 0.0011 <0.0018 <0.0015 Ce-144 < 0.0033 < 0.0026 < 0.0046 < 0.0048 <0.0046 <0.0040 8-1

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCilm )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-3 Lab Code MAP- 1844 MAP- 3821 MAP- 6032 MAP- 7412 3

Volume(m ) 4636 4761 4689 4227 Be-7 0.064 +/- 0.016 0.077 +/- 0.013 0.075 +/- 0.011 0.052 +/- 0.012 0.067 0.065 Mn-54 < 0.0007 < 0.0005 < 0.0004 < 0.0008 <0.0007 <0.0009 Co-58 < 0.0006 < 0.0004 < 0.0004 < 0.0009 <0.0006 <0.0008 Co-60 < 0.0006 < 0.0003 < 0.0005 < 0.0006 <0.0006 <0.0007 Zn-65 < 0.0006 < 0.0006 < 0.0014 < 0.(}01 0 <0.0014 <0.0009 Zr-Nb-95 < 0.0007 < 0.0008 < 0.0010 < 0.0007 <0.001 0 <0.0008 Ru-103 < 0.0004 < 0.0006 < 0.0009 < 0.0009 <0.0009 <0.0011 Ru-1 06 < 0.0061 < 0.0061 < 0.0041 < 0.0082 <0.0061 <0.0068 Cs-134 < 0.0007 < 0.0006 < 0.0006 < 0.0009 <0.0007 <0.0009 Cs-137 < 0.0006 < 0.0004 < 0.0004 < 0.0007 <0.0006 <0.0006 Ba-La-140 < 0.0018 < 0.0012 < 0.0013 < 0.0043 <0.0018 <0.0016 Ce-141 < 0.0010 < 0.0011 < 0.0013 < 0.0018 <0.0013 <0.0018 Ce-144 < 0.0022 < 0.0035 < 0.0025 < 0.0035 <0.0035 <0.0055 M-4 Lab Code MAP- 1845 MAP- 3822 MAP- 6033 MAP- 7413 3

Volume(m ) 4447 4534 4703 4452 Be-7 0.062 +/- 0.013 0.075 +/- 0.011 0.086 +/- 0.011 0.058 +/- 0.012 0.070 0.058 Mn-54 < 0.0007 < 0.0008 < 0.0005 < 0.0006 <0.0008 <0.0008 Co-58 < 0.0008 < 0.0007 < 0.0005 < 0.0005 <0.0008 <0.0011 Co-60 < 0.0006 < 0.0008 < 0.0004 < 0.0005 <0.0008 <0.0008 Zn-65 < 0.0019 < 0.0019 < 0.0005 < 0.0013 <0.0019 <0.0009 Zr-Nb-95 < 0.0014 < 0.0011 < 0.0008 < 0.0012 <0.0014 <0.0010 Ru-1 03 < 0.0013 < 0.0007 < 0.0008 < 0.0008 <0.0013 <0.0009 Ru-106 < 0.0062 < 0.0073 < 0.0026 < 0.0062 <0.0073 <0.0060 Cs-134 < 0.0010 < 0.0007 < 0.0006 < 0.0007 <0.001 0 <0.0008 Cs-137 < 0.0010 < 0.0005 < 0.0005 < 0.0006 <0.001 0 <0.0010 Ba-La-140 < 0.0017 < 0.0026 < 0.0010 < 0.0015 <0.0026 <0.0030 Ce-141 < 0.0013 < 0.0012 < 0.0009 < 0.0015 <0.0013 <0.0017 Ce-144 < 0.0040 < 0.0034 < 0.0019 < 0.0046 <0.0040 <0.0035 8-2

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCi/m )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-5 Lab Code MAP- 1846 MAP- 3824 MAP- 6034 MAP- 7414 3

Volume(m ) 3969 4632 4363 4197 Be-7 0.086 +/- 0.014 0.070 +/- 0.011 0.087 +/- 0.012 0.049 +/- 0.013 0.073 0.072 Mn-54 < 0.0005 < 0.0005 < 0.0008 < 0.0006 <0.0008 <0.0009 Co-58 < 0.0007 < 0.0002 < 0.0006 < 0.0004 <0.0007 <0.0006 Co-60 < 0.0004 < 0.0005 < 0.0005 < 0.0006 <0.0005 <0.0006 Zn-65 < 0.0009 < 0.0007 < 0.0007 < 0.0008 <0.0009 <0.0008 Zr-Nb-95 < 0.0014 < 0.0006 < 0.0007 < 0.0013 <0.0014 <0.0011 Ru-1 03 < 0.0012 < 0.0006 < 0.0009 < 0.0008 <0.0012 <0.0011 Ru-106 < 0.0040 < 0.0042 < 0.0072 < 0.0062 <0.0072 <0.0065 Cs-134 < 0.0009 < 0.0006 < 0.0007 < 0.0008 <0.0009 <0.0008 Cs-137 < 0.0006 < 0.0004 < 0.0007 < 0.0007 <0.0007 <0.0007 Ba-La-140 < 0.0016 < 0.0010 < 0.0023 < 0.0015 <0.0023 <0.0019 Ce-141 < 0.0020 < 0.0013 < 0.0015 < 0.0014 <0.0020 <0.0023 Ce-144 < 0.0038 < 0.0031 < 0.0041 < 0.0026 <0.0041 <0.0047 8-3

MNGP Table 9. Pasture grass, vegetation, analysis for gamma-emitting isotopes.

Collection: 3x per year Previous Sample Description and Concentration (pCi/g wet) Annual Annual Average Average Location: M-41 (Training Center)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3772 MVE- 4464 MVE- 4966 Mn-54 < 0.009 < 0.007 < 0.006 < 0.009 < 0.010 Fe-59 < 0.024 < 0.020 < 0.020 < 0.024 < 0.031 Co-58 < 0.008 < 0.010 < 0.014 < 0.014 < 0.009 Co-60 < 0.010 < 0.008 < 0.006 <0.010 < 0.009 Zn-65 < 0.024 < 0.017 < 0.016 < 0.024 < 0.024 Nb-95 < 0.007 < 0.005 < 0.006 < 0.007 < 0.011 1-131 < 0.026 < 0.021 < 0.025 < 0.026 < 0.038 Cs-134 < 0.013 < 0.010 < 0.010 < 0.013 < 0.011 Cs-137 < 0.009 < 0.014 < 0.010 < 0.014 < 0.011 Location: M-42 (Biology Station Road)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3773 MVE- 4465 MVE- 4967 Mn-54 < 0.009 < 0.014 < 0.009 < 0.014 < 0.008 Fe-59 < 0.017 < 0.026 < 0.023 < 0.026 < 0.022 Co-58 < 0.009 < 0.011 < 0.011 < 0.011 < 0.008 Co-60 < 0.006 < 0.007 < 0.007 < 0.007 < 0.008 Zn-65 < 0.022 < 0.018 < 0.020 < 0.022 < 0.024 Nb-95 < 0.009 < 0.012 < 0.009 < 0.012 < 0.012 1-131 < 0.029 < 0.027 < 0.041 <0.041 < 0.030 Cs-134 < 0.011 < 0.012 < 0.011 < 0.012 < 0.011 Cs-137 < 0.012 < 0.013 < 0.013 <0.013 <0.010 Location: M-43 (lmholte Farm, Control)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3894 MVE- 4466 MVE- 4968 Mn-54 < 0.012 < 0.009 < 0.009 <0.012 < 0.012 Fe-59 < 0.021 < 0.033 < 0.027 < 0.033 < 0.030 Co-58 < 0.008 < 0.012 < 0.006 < 0.012 < 0.013 Co-60 < 0.019 < 0.007 < 0.010 < 0.019 < 0.014 Zn-65 < 0.029 < 0.014 < 0.016 < 0.029 < 0.029 Nb-95 < 0.020 < 0.013 < 0.010 < 0.020 <0.015 1-131 < 0.032 < 0.029 < 0.043 < 0.043 < 0.037 Cs-134 < 0.015 < 0.014 < 0.012 < 0.015 < 0.014 Cs-137 < 0.013 < 0.010 < 0.013 < 0.013 < 0.013 9-1

MNGP Table 10. River water, analysis of monthly composites for gamma-emitting isotopes.

Location: M-8 (C)

Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code NSa NSa MSW-1766 MSW-2440 MSW-2952 Mn-54 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 Co-58 < 10 <10 < 10 Co-60 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 Cs-134 < 10 <10 < 10 Cs-137 < 10 <10 < 10 Ba-La-140 < 15 < 15 < 15 Ce-144 < 10 <10 < 24 Period Collected June July August September October Lab Code MSW-3660 MSW-4496 MSW-5158 MSW-5669 MSW-6328 Mn-54 < 10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 < 10 <10 < 10 <10 < 10 Co-60 < 10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 <10 < 10 Cs-137 < 10 < 10 < 10 <10 < 10 Ba-La-140 < 15 < 15 < 15 <15 < 15 Ce-144 < 22 < 22 < 12 < 39 < 23 Previous b

Period Collected November December Cumulative Annual Lab Code MSW-6947 MSW-7322 Average Average Mn-54 < 10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 < 10 Co-60 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 Ce-144 < 25 < 17 < 39 < 30 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

b Water frozen 12-30-15.

10-1

MNGP Table 10. River water, analysis of monthly composites for gamma-emitting isotopes.

Location: M-9 Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code MSW-326 MSW-1130 MSW-1767 MSW-2441 MSW-2953 Mn-54 <10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 <10 < 10 Co-60 <10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 < 10 <10 < 10 Cs-137 < 10 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 < 15 Ce-144 < 12 < 20 < 11 < 11 < 19 Period Collected June July August September October Lab Code MSW-3661 MSW-4497 MSW-5159 MSW-5670 MSW-6329 Mn-54 <10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 < 10 < 10 <10 < 10 Co-60 <10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 < 15 Ce-144 <23 < 29 < 15 < 30 < 25 Previous Period Collected November December Cumulative Annual Lab Code MSW-6948 MSW-7323 Average Average Mn-54 < 10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 < 10 Co-60 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 <10 < 10 < 10 < 10 Cs-137 <10 < 10 < 10 < 10 Ba-La-140 <15 < 15 < 15 < 15 Ce-144 < 24 < 33 < 33 < 33 10-2

MNGP Table 11. Drinking water, City of Minneapolis, M-14, analysis of monthly composites for gross beta, iodine-131, and gamma-emitting isotopes.

Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code MDW-523 MDW-871 MDW-1502 MDW-2354 MDW-2777 Gross beta 3.2 +/- 1.1 3.3 +/- 1.0 2.5 +/- 0.9 2.3 +/- 0.8 3.5 +/- 0.7 1-131 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 < 10 < 10 < 10 < 10 <10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 <10 < 10 < 10 <10 Co-60 <10 <10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 <10 <10 <10 Cs-137 < 10 <10 < 10 <10 < 10 Ba-La-140 <15 <15 < 15 < 15 < 15 Ce-144 <16 < 29 <9 < 11 < 24 Period Collected June July August September October Lab Code MDW-3662 MDW-4346 MDW-5010 MDW-5678 MDW-6447 Gross beta 1.5 +/- 0.6 1.2 +/- 0.5 1.4 +/- 0.6 1.3+/-0.6 3.2 +/- 1.0 1-131 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 <10 <10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 <10 < 10 < 10 <10 Co-60 < 10 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 < 15 < 15 Cs-134 <10 <10 < 10 < 10 <10 Cs-137 <10 <10 < 10 < 10 <10 Ba-La-140 < 15 <15 < 15 < 15 < 15 Ce-144 < 29 < 23 < 27 < 35 < 14 Period Collected November December Cumulative Previous Lab Code MDW-6946 MDW-7269 Average Average Gross beta 2.2 +/- 0.6 1.4 +/- 0.9 2.3 2.8 1-131 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 <10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 <10 < 10 <10 Co-60 < 10 <10 <10 <10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 <10 < 10 < 10 < 10 Cs-137 < 10 <10 < 10 <10 Ba-La-140 < 15 <15 < 15 <15 Ce-144 < 26 <16 < 35 < 46 11-1

MNGP Table 12. River water and drinking water, analysis of quarterly composites for tritium.

Collection: Quarterly composites of weekly collections.

Sample Type, Location and Concentration (pCi/L)

Collection Period Lab Code H-3 River Water Upstream, M-8 (C) Required LLD 1st Quartera MSW -1770 < 500 < 152 2nd Quarter MSW- 3663 < 500 < 154 3rd Quarter MSW- 5675 < 500 < 152 4th Quarterb MSW -7326 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 165 River Water Downstream, M-9 1st Quarter MSW -1771 < 500 < 152 2nd Quarter MSW- 3664 < 500 < 154 3rd Quarter MSW- 5676 < 500 < 152 4th Quarter MSW -7327 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 157 Drinking Water Minneapolis, M-14 1st Quarter MOW -1768 < 500 < 152 2nd Quarter MOW- 3665 < 500 < 154 3rd Quarter MOW- 5677 < 500 < 152 4th Quarter MOW -7339 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 157 a Composite of two samples for quarter- 03-18 and 03-25-15. Water frozen remainder of quarter.

bWater frozen 12-30-15.

12-1

MNGP Table 13. Well water, analysis for tritium and gamma-emitting isotopes.

Sample Description and Concentration (pCi/L) lO a> ('-.

Date H-3 a> Q) 0 lO '

.0 C0 lO lO

<D (l) z '

<h c'

~

0 0 U)

Collected Lab Code (< 500 pCi/L) l1.. 0 0 N 0 Monticello (M-11) 1/21/2015 MWW-240 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 4/15/2015 MWW-1703 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 29 7/22/2015 MWW-4031 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 34 10/21/2015 MWW-5964 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 Plant Well No. 1 (M-12) 1/21/2015 MWW-241 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 4/15/2015 MWW-1704 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 7/22/2015 MWW-4032 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 10/22/2015 MWW-6097 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 Hasbrouck (M-55) 1/21/2015 MWW-242 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 4/15/2015 MWW-1705 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 7/22/2015 MWW-4034 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 10/21/2015 MWW-5965 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 lmholte (M-43C) 1/21/2015 MWW-243 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 36 4/15/2015 MWW-1706 < 152 < 10 *< 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 39 7/22/2015 MWW-4035 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 49 10/21/2015 MWW-5967 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 <10 <15 <17 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 49 13-1

MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCi!g wet)

Upstream 1000' M-8 (C)

Date Collected 05-26-15 05-26-15 09-22-15 09-22-15 Lab Code MF- 2724 MF- 2725 MF- 5239 MF- 5240 Sample Type Shorthead Smallmouth Shorthead Smallmouth Red horse Bass Red horse Bass K-40 2.56 +/- 0.35 3.46 +/- 0.44 3.58 +/- 0.42 3.65 +/- 0.46 Mn-54 < 0.013 < 0.017 < 0.017 < 0.016 Fe-59 < 0.043 < 0.041 < 0.031 < 0.056 Co-58 < 0.016 < 0.018 < 0.017 < 0.019 Co-60 < 0.012 < 0.018 < 0.011 < 0.010 Zn-65 < 0.029 < 0.026 < 0.018 < 0.033 Nb-95 < 0.022 < 0.031 < 0.027 < 0.030 Zr-95 < 0.024 < 0.025 < 0.043 < 0.043 Cs-134 < 0.015 < 0.016 < 0.014 < 0.020 Cs-137 < 0.015 < 0.018 < 0.011 < 0.017 Ba-La-140 < 0.045 < 0.035 < 0.045 < 0.073 Ce-144 < 0.130 < 0.127 < 0.105 < 0.119 Cumulative Previous Average Average K-40 3.31 2.72 Mn-54 < 0.017 < 0.019 Fe-59 < 0.056 < 0.059 Co-58 < 0.019 < 0.023 Co-60 < 0.018 < 0.020 Zn-65 < 0.033 < 0.034 Nb-95 < 0.031 < 0.057 Zr-95 < 0.043 < 0.055 Cs-134 < 0.020 < 0.019 Cs-137 < 0.018 < 0.020 Ba-La-140 < 0.073 < 0.272 Ce-144 < 0.130 < 0.150 14-1

MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCi!g wet)

Downstream 1000' M-9 Date Collected 05-26-15 05-26-15 09-22-15 09-22-15 Lab Code MF- 2726 MF- 2727 MF- 5241 MF- 5242 Sample Type Shorthead Smallmouth Shorthead Smallmouth Red horse Bass Red horse Bass K-40 3.08 +/- 0.45 3.20 +/- 0.64 3.56 +/- 0.42 3.71 +/- 0.43 Mn-54 < 0.016 < 0.025 < 0.015 < 0.015 Fe-59 < 0.043 < 0.019 < 0.046 < 0.033 Co-58 < 0.020 < 0.025 < 0.013 < 0.021 Co-60 < 0.014 < 0.025 < 0.013 < 0.008 Zn-65 < 0.029 < 0.070 < 0.031 < 0.050 Nb-95 < 0.021 < 0.030 < 0.018 < 0.029 Zr-95 < 0.031 < 0.058 < 0.039 < 0.032 Cs-134 < 0.018 < 0.025 < 0.014 < 0.017 Cs-137 < 0.014 < 0.020 < 0.010 < 0.017 Ba-La-140 < 0.031 < 0.122 < 0.057 < 0.056 Ce-144 < 0.102 < 0.141 < 0.108 < 0.068 Date Collected Cumulative Previous Lab Code Average Average Sample Type K-40 3.39 3.03 Mn-54 < 0.025 < 0.018 Fe-59 < 0.046 < 0.059 Co-58 < 0.025 < 0.028 Co-60 < 0.025 < 0.021 Zn-65 < 0.070 < 0.035 Nb-95 < 0.030 < 0.043 Zr-95 < 0.058 < 0.046 Cs-134 < 0.025 < 0.020 Cs-137 < 0.020 < 0.017 Ba-La-140 < 0.122 < 0.217 Ce-144 < 0.141 < 0.126 14-2

MNGP Table 15. Aquatic invertebrates, analysis for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCilg wet) Cumulative Previous Average Average Upstream 1000' M-8 (C)a Date Collected 08-06-15 10-07-15 Lab Code MBO- 4344 MBO- 5607 Be-7 < 1.49 < 0.36 < 1.49 < 0.57 K-40 < 1.91 < 0.66 < 1.91 < 0.84 Mn-54 < 0.088 < 0.042 < 0.088 < 0.024 Fe-59 < 0.24 < 0.090 < 0.24 < 0.13 Co-58 < 0.15 < 0.031 < 0.15 < 0.068 Co-60 < 0.085 < 0.029 < 0.085 < 0.052 Zn-65 < 0.18 < 0.059 < 0.18 < 0.094 Zr-Nb-95 < 0.23 < 0.062 < 0.23 < 0.064 Ru-103 < 0.22 < 0.072 < 0.22 < 0.075 Ru-106 < 0.55 < 0.30 < 0.55 < 0.39 Cs-134 < 0.076 < 0.033 < 0.076 < 0.040 Cs-137 < 0.085 < 0.023 < 0.085 < 0.049 Ba-La-140 < 1.35 < 0.14 < 1.35 < 0.41 Ce-144 < 0.39 < 0.22 < 0.39 < 0.20 Downstream 1000' M-9 Date Collected 08-06-15 10-07-15 Lab Code MBO- 4345 MBO- 5608 Be-7 < 0.67 < 0.60 < 0.67 < 0.55 K-40 < 0.95 < 1.24 < 1.24 < 0.91 Mn-54 < 0.053 < 0.044 < 0.053 < 0.046 Fe-59 < 0.22 < 0.12 < 0.22 < 0.13 Co-58 < 0.078 < 0.064 < 0.078 < 0.046 Co-60 < 0.039 < 0.047 < 0.047 < 0.041 Zn-65 < 0.079 < 0.097 < 0.097 < 0.077 Zr-Nb-95 < 0.13 < 0.11 < 0.13 < 0.067 Ru-103 < 0.13 < 0.087 < 0.13 < 0.070 Ru-106 < 0.48 < 0.33 < 0.48 < 0:38 Cs-134 < 0.050 < 0.043 < 0.050 < 0.041 Cs-137 < 0.039 < 0.038 < 0.039 < 0.040 Ba-La-140 < 1.15 < 0.32 < 1.15 < 0.22 Ce-144 < 0.25 < 0.23 < 0.25 < 0.24 15-1

MNGP Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCilg dry) Cumulative Previous Average Average Upstream 1000' M-8 (C)

Date Collected 08-06-15 10-07-15 Lab Code MSS- 4416 MSS- 5604 Be-7 < 0.29 < 0.27 < 0.29 < 0.16 K-40 11.58+/-0.54 11.53 +/- 0.51 11.55 9.12 Mn-54 < 0.017 < 0.014 <0.017 < 0.016 Fe-59 < 0.073 < 0.068 < 0.073 < 0.052 Co-58 < 0.022 < 0.011 < 0.022 < 0.016 Co-60 < 0.016 < 0.013 <0.016 <0.014 Zn-65 < 0.044 < 0.032 < 0.044 < 0.034 Nb-95 < 0.024 < 0.035 < 0.035 < 0.015 Zr-95 < 0.048 < O.Q46 < 0.048 < 0.028 Ru-103 < 0.039 < 0.018 < 0.039 < 0.018 Ru-106 < 0.083 < 0.13 < 0.13 < 0.075 Cs-134 < 0.013 < 0.014 < 0.014 < 0.012 Cs-137 < 0.017 < 0.015 <0.017 <0.012 Ba-La-140 < 0.21 < 0.085 <0.21 < 0.081 Ce-144 < 0.12 < 0.092 <0.12 < 0.081 Downstream 1000' M-9 Date Collected 08-06-15 10-07-15 Lab Code MSS- 4417 MSS- 5605 Be-7 < 0.26 < 0.30 < 0.30 < 0.27 K-40 10.51 +/- 0.54 10.41 +/- 0.54 10.46 10.58 Mn-54 < 0.018 < 0.016 <0.018 < 0.018 Fe-59 < 0.041 < 0.076 < 0.076 < 0.068 Co-58 < 0.021 < 0.026 < 0.026 < 0.027 Co-60 < 0.017 < 0.013 < 0.017 < 0.016 Zn-65 < 0.039 < 0.039 < 0.039 < 0.040 Nb-95 < 0.030 < 0.051 < 0.051 < 0.044 Zr-95 < 0.052 < 0.027 < 0.052 < 0.042 Ru-103 < 0.036 < 0.032 < 0.036 < 0.030 Ru-106 < 0.12 < 0.11 < 0.12 < 0.16 Cs-134 < 0.012 < 0.017 <0.017 < 0.015 Cs-137 0.034 +/- 0.016 0.024 +/- 0.014 0.029 0.035 Ba-La-140 < 0.10 < 0.14 < 0.14 < 0.11 Ce-144 < 0.11 < 0.13 < 0.13 < 0.12 16-1

MNGP Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/g dry) Cumulative Previous Average Average Montissippi Park M-15 Date Collected 08-06-15 10-07-15 Lab Code MSS- 4418 MSS- 5606 Be-7 < 0.33 < 0.22 < 0.33 < 0.22 K-40 9.49 +/- 0.51 10.54 +/- 0.54 10.01 10.89 Mn-54 < 0.021 < 0.018 < 0.021 < 0.017 Fe-59 < 0.068 < 0.050 < 0.068 < 0.040 Co-58 < 0.022 < 0.019 < 0.022 < 0.017 Co-60 < 0.014 < 0.011 < 0.014 < 0.013 Zn-65 < 0.041 < 0.038 <0.041 < 0.045 Nb-95 < 0.031 < 0.028 < 0.031 < 0.025 Zr-95 < 0.046 < 0.026 < 0.046 < 0.039 Ru-103 < 0.041 < 0.016 <0.041 < 0.026 Ru-106 < 0.13 < 0.13 < 0.13 < 0.102 Cs-134 < 0.014 < 0.016 < 0.016 < 0.014 Cs-137 < 0.017 < 0.021 < 0.021 0.059 Ba-La-140 < 0.20 < 0.11 < 0.20 < 0.092 Ce-144 < 0.11 < 0.11 < 0.11 < 0.088 16-2

(l JCcel Energy" Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 May 12, 2016 L-MT-16-030 10 CFR 50, Appendix I ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2015 Annual Radiological Environmental Operating Report Pursuant to 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3, IV.C and, in accordance with Monticello Nuclear Generating Plant (MNGP) Technical Specifications 5.6.1, the Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, is submitting the Annual Radiological Environmental Operating Report, under MNGP's "Radiological Environmental Monitoring Program," for year 2015.

Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

~~

Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, Resident Inspector, Monticello Minnesota Department of Commerce

ENCLOSURE 1 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1 - DECEMBER 31, 2015 100 Pages to Follow

Environmental, Inc.

I Midwest Laboratory 700 landw*hr Road

  • Northbroak,ll60061-1310 phone (847) 564-0700
  • fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co., Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS Preface ....................................................................................................................................... ii List ofT abies ....................................................................................................................... iv List of Figures ...................................................................................................................... v

1.0 INTRODUCTION

...........................................................................................................:........... 1 2.0

SUMMARY

..............................................................................................' ................................... 2 3.1 RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM (REMP) ......................... 3 3.2 Program Design and Data Interpretation ................................................................ 3 3.3 Program Description ............................................................................................... 4 3.4 Program Execution ................................................................................................. 5 3.5 Program Modifications ............................................................................................ 5 3.6 Laboratory Procedures ........................................................................................... 6 3.7 Land Use Census ................................................................................................... 6 4.1 RESULTS AND DISCUSSION ............................................................................................ 7 4.2 Atmospheric Nuclear Detonations and Nuclear AcCidents ...................................... 7 4.3 Summary of Preoperational Data ........................................................................... 7 4.4 Program Findings ................................................................................................... 8 5.0 FIGURES AND TABLES ..................................................................................................... 12

6.0 REFERENCES

...........................................................................................................................24 APPENDICES A Interlaboratory Comparison Program Results .................................................................... A-1 B Data Reporting Conventions ............................................................................................. B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .................................. :.......................... C-1 D Sampling Location Maps ................................................................................................... D-1 E Ground Water Monitoring Well Samples ................................... ;.. , .... :............................... E-1 3

LIST OF TABLES 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 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ................................................................A1-1 A-2 Thermoluminescentdosimeters (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 Resources Associates, Crosscheck Program Results (EML study replacement) ...................................................................................A7-1 Attachment A: Acceptance criteria for spiked samples .................................................... A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ..................................................................... C-2 Appendix E E-1 Sample Collection and Analysis Program, Ground Water, ............................................. E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ................................................ E-6 E-3 Ground Water Monitoring Program Summary .................................................. ,............. E-7 E-4 Results of Analyses, Ground Water Monitoring Program ............................................... E-9 4

LIST OF FIGURES No.

5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations .......................................... 18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location .............................................................................................. 19 The following figures are located in the Appendices:

Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring ......................................................................................................................................D-2 D-2 Sample collection and analysis program: TLD locations, OuterRing ..............................................................................................................................D-3 D-3 Sample collection and analysis program: TLD locations, Controls ....................................................................................................................................D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Well water and Shoreline sampling locations .......................................................................... D-5 D-5 Sample collection and analysis program: TLD locations,

. ISFSI TLD Locations ................................................................................................................D-6 Appendix E E-1 Sample collection and analysis program:

Ground water, On-site monitoring well locations ..................................................................... E-8 5

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2015.

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 included in Part II of this report.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 681 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co. Minnesota. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) is described; this program is required by the U.S. Nuclear Regulatory Commission (NRC) as well as Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant.

Results for the year 2015 are summarized and discussed.

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

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3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.2 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello 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 (TLD's).

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 Monticello 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 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-

?, 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-? is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-1 03 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 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.

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3.3 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.

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. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1 ), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaS0 4 :Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.

As substitute for dairy sampling, vegetation is collected from locations M-41, M-42 and M-43 (C).

The samples are analyzed for iodine-131 and other gamma emitting isotopes.

Corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged. Analysis is done for gamma-emitting isotopes.

Well water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To detect possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes. The Ground Water Monitoring Program is further described in Appendix E.

Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also analyzed for tritium and gamma emitting isotopes.

River water is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. 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, invertebrates, and shoreline sediments. Shoreline sediment is also collected from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

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

(1) Air Particulates I Air Iodine:

M-05, No air particulate I air iodine sample was available for the week ending January 28, 2015, there was a power loss at the sample station.

M-02, No air particulate I air iodine sample was available for the week ending February 4, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.

M-02, No air particulate I air iodine sample was available for the week ending May 6, 2015, due to a malfunctioning switch on the air sampler. The air sampler was replaced.

M-04, Air sampler was found with GFCI tripped for the week ending June 10, 2015 and the GFCI was reset; the sample duration was determined to be approximately a full week and the analysis result is included in the Complete Data Analysis Tables for this report.

M-04, No air particulate I air iodine sample was available for the week ending June 24, 2015.

The GFCI was tripped. The GFCI was reset.

(2) Surface Water:

Surface water was not collected at location M-08 for the months of January or February, 2015, or for the weeks of March 4, March 11, and December 30, 2015 due to unsafe ice conditions.

One TLD samples was found missing for the second quarter at Outer Ring location M-06B.

Deviations from the program are summarized in Table 5.3.

3.5 Program Modifications No modifications were made to the MNGP Radiological Environmental Monitoring Program in 2015.

3.6 Laboratory Procedures The iodine-131 analyses in drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.

Levels of iodine-131 in natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

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Tritium concentrations are determined by liquid scintillation.

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 QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3. 7 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fF producing fresh leafy vegetables, in each of the 16 meteorological sectors within a 5 mile radius. The census shall also identify the locations of all milk animals, meat animals and all gardens of greater than 500 fF producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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 2015 land use census was conducted between September 14 and September 24, 2015.

This is the third year using improved GPS software. The GPS software provides more accurate distance and direction plotting for identified locations than previous methodologies.

There were three sectors in which the highest D/Q values for gardens increased by greater than 20%. The change in all three sectors was due to a closer residence planting a garden in 2015 where there was no garden in 2014. There were no sectors where the highest D/Q values for the nearest residence changed by more than 20%. Meat animals were identified during the performance of the 2015 census. There currently are no milking animals within a five mile radius of the plant. Vegetation sampling is currently being performed in lieu of milk sampling.

The Critical Receptor for 2015 remained the same as 2014 (Child, Thyroid located 1.15 mi SSE with exposure to Ground, Plume, Inhalation and Vegetable Pathways). Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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

All 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.

4.2 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2015. The last reported test was conducted on October 16, 1980 by the People's Republic of China.

4.3 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 3 3 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3

pCi/m 3 . Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained 3

below detection levels of 0.03 pCi/m In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.

Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

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4.4 Program Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2015.

Tritium was identified in some groundwater samples collected within the site Protected Area, but not in offsite or domestic well samples.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.

distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (14.8 and 14.2 mRem/91 days, respectively). The mean for special interest locations was 14.7 mRem/91 days and the mean for the control locations was 14.3 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1999 through 2014 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rin~q Outer Rino Dose rate (mRem/91 davs) 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 2011 14.8 14.3 2012 16.2 15.5 2013 14.4 14.0 2014 13.5 12.9 2015 14.8 14.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at 3

both indicator and control locations (0.030 and 0.028 pCi/m ,respectively), similar to levels observed from 1999 through 2014. The results are tabulated below.

Year Indicators Control 3

Concentration (QCi/m )

1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 2011 0.029 0.027 2012 0.032 0.031 2013 0.029 0.032 2014 0.027 0.028 2015 0.030 0.028 Average annual gross beta concentrations in airborne particulates.

Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1999 through 2015.

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 AI-Salih, 1955) was detected in all samples, 3 3 with an average activity of 0.070 pCilm for the indicator locations and 0.066 pCilm for the control locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCilm 3 in all samples.

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River Water and Drinking Water Tritium activity measured below 500 pCi/L in all samples. Gamma isotopic results were all below detection limits. Gross beta activity in Minneapolis drinking water averaged 2.3 pCi/L and was similar to average levels observed from 1998 through 2012. Gross beta averages are tabulated below. No indication plant operational effects were indicated.

Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1999 2.2 2008 2.1 2000 2.5 2009 2.3 2001 2.5 2010 2.9 2002 2.9 2011 2.2 2003 3.0 2012 2.4 2004 2.7 2013 2.6 2005 2.8 2014 2.8 2006 2.1 2015 2.3 2007 2.8 Average annual concentrations; Gross beta in drinking water.

Well Water At the four indicator and control locations, tritium was below the detection limit for all samples.

Gamma isotopic results were also below detection limits.

The data for 2015 were consistent with previous year's results and no plant operational effects were indicated.

Vegetation in lieu of Milk Sampling Vegetation samples were collected in July, August and September, 2015. lodine-131 concentrations measured below 0.043 pCi/g wet weight in all samples. These samples are required when milk samples are not available. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

A vegetation collection was not required for 2015. No crops within five miles of the plant were found using irrigation water from the Mississippi River, and the plant did not discharge radioactive liquid effluents.

Eight fish were analyzed in 2015 consisting of two fish collected from upstream locations and two collected from downstream locations in June and then again in September. Flesh was separated from the bones and analyzed by gamma spectroscopy. Only naturally-occurring potassium-40 was found with an average of 3.31 pCilg wet for four upstream samples and 3.39 pCi/g wet weight for the four downstream samples. Other gamma-emitting isotopes remained below detection limits.

There was no indication of a plant effect.

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Invertebrates Samples were collected in August and October, 2015, and analyzed by gamma spectroscopy. All gamma-emitting isotopes, with the exception of naturally-occurring potassium-40 were below detection limits. There was no indication of any plant effect.

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in August and October, 2015, and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in two downstream samples (M-9), at an average concentration of 0.029 pCilg dry weight. Similar levels of activity have been observed since 1978, and are indicative of the influence of fallout deposition. Naturally-occurring beryllium-? and potassium-40 were also detected. There was no indication of a plant effect.

Groundwater Monitoring Program (On-site monitoring wells)

Measurable tritium was detected in 47 of 118 samples collected from the nineteen on-site monitoring wells. The activities ranged from 144 to 6,493 pCi/L. Only six samples from MW-09A indicated tritium activity greater than 500 pCi/L. The highest level detected (6,493 pCi/1), is comparable to the highest level detected from 2014 (5,911 pCi/L), which also was collected from well MW-09A. The current results are consistent with those from previous years, indicating presence of a tritium plume under the Turbine Building that is considered to be remaining onsite.

See Appendix E for full Groundwater monitoring well results and discussion.

Gamma isotopic measurements were below detection limits.

Starting in 2016, Onsite Groundwater Monitoring Program results will be published only in the Effluent report (ARERR). This is to align with guidelines of NEI 07-07 and industry practice.

Storm Water Run-off (on-site)

One of five storm water runoff samples indicated detectible tritium at 157 pCi/L; the remaining four samples were below detection limits. Gamma isotopic analysis results also measured below detection limits for all five samples analyzed in 2015.

ISFSI TLD Monitoring Gamma and Neutron TLDs are located around the Independent Spent Fuel Storage Installation (ISFSI) to monitor direct radiation from stored fuel. Results for gamma monitoring are included in the Complete Data Analysis Tables. In addition, neutron TLDs are included at certain Special Interest locations and at the Control locations. Neutron TLD results were analyzed according to methodology presented at the 2009 RETS/REMP Workshop by Scannell, Giard, and Raimondi, and it was found that neutron TLDs surrounding the ISFSI do indicate a net signal due to neutron dose, but all neutron dosimeters at or beyond the site boundary do not indicate that neutron dose was detected. Neutron dosimetry uses the different responses from two lithium 6 10 borate TLDs, one depleted of Li and 8 (gamma-sensitive only), with the other at natural abundances (neutron and gamma sensitive). The net response is scaled using a site-specific Neutron Correction Factor (NCF) to determine dose. The NCF is not available for Monticello's ISFSI at this time and it would not be correct, nor prudent, to report the neutron TLD results in the Complete Data Analysis Tables. It is intended that neutron results will be reported starting in 2016.

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5.0 FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type) a Frequency b Frequency c REMP Ambient radiation(TLDs) 40 M-01A- M-14A, M-018- M-168 C/Q Ambient gamma M-01 S - M-06S, M-01 C - M-04C ISFSI Ambient radiation (TLDs) 20 ISFSI-1 to ISFSI-16, C/Q Neutron Dose Neutron Control A, 8, C, D C/Q 13 1-01 to 1-13 C/Q Ambient Gamma Airborne Particulates 5 M-1 (C), M-2, M-3, M-4, M-5 crw G8, GS (QC of each location)

Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 crw 1-131 Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year GS Surface water 2 M-S(C), M-9 Gf\N GS(MC), H-3(QC)

Drinking water M-14 Gf\N G8(MC), I-131(MC)

GS (MC), H-3 (QC)

Well water 4 M-11, M-12, M-55, M-43(C) GIQ H-3, GS Fish 2 M-S(C), M-9 G/SA GS (two species, edible portion)

Periphyton or invertebrates 2 M-S(C), M-9 G/SA GS Shoreline sediment 3 M-S(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. 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.

c Analysis type is coded as follows: 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 Pasture grass and vegetation collections added to supplement dairy sampling.

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction Code Type a Collection Site Sample Type b from Reactor M-1 c Air Station M-1 AP,AI 11.0 mi@ 307"/NW M-2 Air Station M-2 AP,AI 0.8 mi@ 140°/SE M-3 Air Station M-3 AP,AI 0.6 mi@ 104°/ESE M-4 Air Station M-4 AP,AI 0.8 mi@ 147"/SSE M-5 Air Station M-5 AP,AI 2.6 mi@ 134°/SE M-8 c Upstream of Plant Intake SW, SS, BO, F < 1000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream M-11 City of Monticello ww 3.3 mi@ 127"/SE M-12 Plant Well #11 ww 0.26 mi@ 252°/WSW M-14 City of Minneapolis ow 37.0 mi@ 132°/SE M-15 Montissippi Park ss 1.27 mi@ 114°/ESE M-27 Highest 0/Q garden 1.15 mi@ 148°/SSE M-41 Training Center VE 0.8 mi@ 151°/SSE M-42 Biology Station Road VE 0.6 mi@ 134°/SE M-43 c lmholte Farm VE,WW 12.3 mi@ 313°/NW M-55 Hasbrouck Residence ww 1.60 mi@ 255°/WSW 14

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Code Type* Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi@ 353°/N M-02A Sherburne Ave. So. TLD 0.79 mi@ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi@ 56°/NE M-04A Biology Station Road TLD 0.5 mi@ 92°/E M-05A Biology Station Road TLD 0.48 mi @ 122° /ESE M-06A Biology Station Road TLD 0.54 mi@ 138°/SE M-07A County Road 75 TLD 0.47 mi@ 158°/SSE M-08A County Road 75 TLD 0.45 mi@ 175°/S M-09A County Road 75 TLD 0.38 mi@ 206°/SSW M-10A County Road 75 J'LD 0.38 mi@ 224°/SW M-11A County Road 75 TLD 0.4 mi@ 237"/WSW M-12A County Road 75 TLD 0.5 mi@ 262°/W M-13A North Boundary Road TLD 0.89 mi@ 322°/NW M-14A North Boundary Road TLD 0.78 mi@ 335°/NNW Approximately 4 to 5 miles Distant from the Plant M-01B 11?'h Street TLD 4.65 mi@ 01°/N M-02B County Road 11 TLD 4.4 mi@ 18"/NNE M-03B County Road 73 & 81 TLD 4.3 mi@ 51°/NE M-04B County Road 73 (196th St.) TLO 4.2 mi@ 67"/ENE M-05B City of Big Lake TLD 4.3 mi@ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi@ 117"/ESE M-07B Monticello Industrial Drive TLD 4.3 mi@ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi@ 162°/SSE M-09B Weinand Farm TLD 4.7 mi@ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi@ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi@ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi@ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi@ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi@ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi@ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi@ 341°/NNW 15

Table 5.2. Sampling locations, Monticello Nuclear GeQerating Plant.

Distance and Code Type a Collection Site Sample Typeb Direction from Reactor Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi@ 241WvSW M-02S Krone Residence TLD 0.5 mi@ 220°/SW M-03S Big Oaks Park TLD 1.53 mi@ 103°/ESE M-04S Pinewood School TLD 2.3 mi@ 131 °/SE M-OSS Rivercrest Christian Academy TLD 3.0 mi@ 118°/ESE M-06S Monticello Public Works TLD 2.6 mi@ 134°/SE M-01C c Kirchenbauer Farm TLD 11.5 mi@ 323°/NW M-02C c County Roads 4 and 15 TLD 11.2 mi @4r/NE M-03C c County Rd 19 and Jason Ave. TLD 11.6 mi@ 130°/SE M-04C c Maple Lake Water Tower TLD 10.3 mi@ 226°/ SW ISFSI TLD Locations ISFSI-1 ISFSI-1 (neutron) and 1-01 (gamma) TLD NE corner of ISFSI ISFSI-2 ISFSI-2 (neutron) and 1-02 (gamma) TLD North side of ISFSI, center ISFSI-3 ISFSI-3 (neutron) and 1-03 (gamma) TLD NW corner of ISFSI ISFSI-4 ISFSI-4 (neutron) and 1-04 (gamma) TLD West side of ISFSI, middle ISFSI-5 ISFSI-5 (neutron) and 1-05 (gamma) TLD West side of ISFSI, at center of array ISFSI-6 ISFSI-6 (neutron) and 1-06 (gamma) TLD SW corner of ISFSI ISFSI-7 ISFSI-7 (neutron) and 1-07 (gamma) TLD South side of ISFSI, center ISFSI-8 ISFSI-8 (neutron) and 1-08 (gamma) TLD SE corner of ISFSI ISFSI-9 ISFSI-9 (neutron) and 1-09 (gamma) TLD East side of ISFSI, at center of array ISFSI-10 ISFSI-10 (neutron) and 1-10 (gamma) TLD East side of ISFSI, middle ISFSI-11 ISFSI-11 (neutron) and 1-11 (gamma) TLD OCA fence south, on exit road ISFSI-12 ISFSI-12 (neutron) and 1-12 (gamma) TLD OCA fence middle, on exit road ISFSI-13 ISFSI-13 (neutron) and 1-13 (gamma) TLD OCA fence north, on exit road ISFSI-14 ISFSI-14 (neutron) TLD Posted with TLD M12A ISFSI-15 ISFSI-15 (neutron) TLD Posted with TLD M1 OA ISFSI-16 ISFSI-16 (neutron) TLD Posted with TLD M02S Neutron Control A c TLD Posted with TLD M03C Neutron Control B c TLD Posted with TLD M04C Neutron Control C c TLD Posted with TLD M02C Neutron Control D c TLD Posted with TLD M01 C a "C" denotes control location. All other locations are indicators.

b Sample Codes: AP Airborne particulates F Fish AI Airborne Iodine sw River Water BS Bottom (river) sediments ss Shoreline Sediments BO Bottom organisms TLD Thermoluminescent Dosimeter OW Drinking Water VE Vegetation I vegetables ww Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

16

Table 5.3 Missed Collections and Analyses.

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, 1-131 M-005 1/28/2015 Power loss at sample Power was reset station.

sw Gamma M-008 January '15 Water frozen entire month; None no composite.

AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running due Replaced air sampler.

to bad switch.

sw Gamma M-008 February '15 Water frozen entire month; None no composite.

  • .c sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None APIA I Beta, 1-131 M-002 5/6/2015 Air sampler not running. Replaced air sampler.

TLD Gamma M-06B 2nd Qtr '15 TLD missing in field. Replaced TLD APIA I Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped ResetGFCI sw Gamma M-008 12/30/15 Water frozen None 17

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

20 l -

--a-lnnerRing Outer Ring 19 18 17 I 0 16

~ v ~ v I/;I~

I y- v r-- 0 \ v r.......

v~

15 11---1

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0) 0 0 0 0 0 0

0 0 """

0 0

0 0

0 0

0 0

0 0

0 0 0N 0 ~

0

~

0 0""" 0N

~ N N N N N N N N N N N N N N 18

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

- 11- - Indicators (M-2, 3, 4, 5) 0.035 I - o - - Controi(M-1)

I 0.033 0.031 ly ~

\

0.029 l/l\ /I \ \

I I

~ v/ \

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/1 ~ I /

\

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0.021 0.019 0.017 0.015 Ol 0 N (') "<!" I{) (() I'- (() Ol 0 (') I{)

Ol 0 0 0

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~ N N N N N N N N N N N N N 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period ------------------

January-December, 2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean(F)" Mean (F) 0 Mean (F) 0 Routine (Units) Analyses* Ran gee Locationd Rangec Rangec Results*

Direct Radiation TLD (Inner Ring, Gamma 56 3.0 14.8 (56/56) M-11A, County Rd 75, 17.1 (4/4) (See Control 0 General Area at ( 9.6-19.6) 0.4 mi @ 250°/WSW (15.8-19.6) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 63 3.0 14.2 (63/63) M-148 16.6 (4/4) (See Control 0 4-5 mi. distant) ( 11.0-19.6) 4.5 mi@ 228°/NW (14.7-19.6) below.)

mRem/91 days)

TLD (Special Gamma 24 3.0 14.7 (24/24) M-04S 16.4 (4/4) (See Control 0 Interest Areas) ( 9.4-18.8) 2.3 mi@ 132°/SE (14.4-17.6) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-02C 17.5 (4/4) 15.3 (16/16) 0 mRem/91 days) 11.2 mi@ 47"/NE (15.9-20.3) ( 11.8-20.3)

Airborne Pathway Airborne GB 256 0.002 0.030 (204/204) M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 Particulates (0.007-0.088) 2.6 rni@ 134°/SE (0.009-0.088) (0.008-0.062)

(pCi/rn 3)

GS 20 Be-7 0.015 0.070 (16/16) M-5, Air Station 0.073 (4/4) 0.066 (4/4) 0 (0.049-0.087) 2.6 rni@ 134°/SE (0.049-0.087) (0.043-0.077)

Mn-54 0.0008 < LLD - - < LLD 0 Co-58 0.0008 < LLD - - < LLD 0 Co-60 0.0009 < LLD - - < LLD 0 Zn-65 0.0019 < LLD - - < LLD 0 Zr-Nb-95 0.0014 < LLD - - < LLD 0 Ru-103 0.0013 < LLD - - < LLD 0 Ru-106 0.0085 < LLD - - < LLD 0 Cs-134 0.0010 < LLD - - < LLD 0 Cs-137 0.0010 < LLD - - < LLD 0 Ba-La-140 0.0026 < LLD - - < LLD 0 Ce-141 0.0020 < LLD - - < LLD 0 Ce-144 0.0046 < LLD - - < LLD 0 Airborne Iodine 1-131 256 0.03 < LLD - - < LLD 0 3

(pCi/m )

20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant *Docket No. ..;5;..;0-...;2;;.;6;..;3_ _ _ _ _ __

Location of Facility Wright, Minnesota Reporting Period January-December,2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) 0 Mean (F)" Mean (F) 0 Routine (Units) Analyses* Range* Locationd Range* Range* Results*

Waterborne Pathway River Water (pCi/L) H-3 8 500 < LLD - - < LLD 0 GS 22 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce'-144 39 < LLD - - < LLD 0 Drinking Water GB 12 1.0 2.3 (12112) M-14, Minneapolis 2.3 (12/12) None 0 (pCi/L) (1.2-3.5) 37.0 mi.@ 132° /SE (1.2-3.5) 1-131 12 1.0 < LLD - - None 0 H-3 4 500 < LLD - - None 0 GS 12 Mn-54 10 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 10 < LLD - - None 0 Co-60 10 < 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 35 < LLD - - None 0 Well Water H-3 16 500 < LLD - - < LLD 0 (pCi/L) GS 16 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 49 < LLD - - < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summarw Name of Facility Monticello Nuclear Generating Plant Docket No. ...;5...;;0...:-2;;.;6...;;3_ _ _,_._ __

Location of Facility Wright, Minnesota Reporting Period January-December, 2 015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses" Range' Locationd Range' Range' Results" Waterborne Pathway Invertebrates GS 4 (pCilg wet) Be-7 1.49 < LLD - - < LLD 0 K-40 1.91 < LLD - - < LLD 0 Mn-54 0.088 < LLD - - < LLD 0 Fe-59 0.24 < LLD - - < LLD 0 Co-58 0.145 < LLD - - < LLD 0 Co-60 0.085 < LLD - - < LLD 0 Zn-65 0.18 < LLD - - < LLD 0 Zr-Nb-95 0.23 < LLD - - < LLD 0 Ru-103 0.217 < LLD - - < LLD 0 Ru-106 0.55 < LLD - - < LLD 0 Cs-134 0.076 < LLD - - < LLD 0 Cs-137 0.085 < LLD - - < LLD 0 Ba-La-140 1.35 < LLD - - < LLD 0 Ce-144 0.39 < LLD - - < LLD 0 Shoreline GS 6 Sediments Be-7 0.33 < LLD - - < LLD 0 (pCi/g dry) -

K-40 0.10 10.24 (4/4) M-08, Upstream 11.55 (2/2) 11.55 (2/2) 0 (9.49-1 0.54) < 1000' of discharge (11.53-11.58) (11.53-11.58)

Mn-54 0.021 < LLD - - < LLD 0 Fe-59 0.076 < LLD - - < LLD 0 Co-58 0.026 < LLD - - < LLD 0 Co-60 0.017 < LLD - - < LLD 0 Zn-65 0.044 < LLD - - < LLD 0 Nb-95 0.051 < LLD - - < LLD 0 Zr-95 0.052 < LLD - - < LLD 0 Ru-103 0.041 < LLD - - < LLD 0 Ru-106 0.13 < LLD - - < LLD 0 Cs-134 0.017 < LLD - - < LLD 0 Cs-137 0.021 0.029 (2/4) M-09, Downstream - < LLD 0 (0.024-0.034) < 1000' of discharge -

Ba-La-140 0.21 < LLD - - < LLD 0 Ce-144 0.13 < LLD - - < LLD 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263

--,---=-----:---

Location of Facility Wright, Minnesota Reporting Period January-December, 2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) 0 Mean (F) 0 Mean (F)" Routine (Units) Analyses* Ran gee Locationd Ran gee Rangec Results*

Ingestion Pathway Vegetation GS 9 (Pasture Grass, Mn-54 0.014 < LLD - - < LlD 0 Weeds, Leaves) Fe-59 0.033 < LLD - - < LLD 0 Co-58 0.014 < LLD - - < LLD 0 (pCi/gwet) Co-60 0.019 < LLD - - < LLD 0 Zn-65 0.029 < LLD - - < LLD 0 Nb-95 0.020 < LLD - - < LLD 0 1-131 0.043 < LLD - - < LLD 0 Cs-134 0.015 < LLD - < LLD 0 Cs-137 0.014 < LLD - - < LLD 0 Fish GS 8 (pCi/g wet) K-40 0.10 3.39 (4/4) M-09, Downstream 3.39 (4/4) 3.31 (4/4) 0

- (3.08-3.71) < 1000' of discharge (3.08-3.71) (2.56-3.65)

Mn-54 0.025 < LLD - - < LLD 0 Fe-59 0.056 < LLD - - < LLD 0 Co-58 0.025 < LLD - - < LLD 0 Co-60 0.025 < LLD - - < LLD 0 Zn-65 0.070 < LLD - - < LLD 0 Zr-Nb-95 0.031 < LLD - - < LLD 0 Cs-134 0.025 < LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.122 < LLD - - < LLD 0 Ce-144 0.141 < LLD - - < LLD 0

  • GB =gross beta, GS =gamma scan.

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

c 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: (1) by name, and/or station code 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.

23

6.0 REFERENCES

CITED Arnold, J. R. and H. A. AI-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, 276.

ATI Environmental, Inc., Midwest Laboratory.

____2001a through 2015a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2015.

_ _ _---,2001 b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 2000 through 2015.

____ 1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 1983 through 1999.

____ 1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

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

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

_ _ _..,-1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December, 1978 through 1982.

_ _ _ _.2009. Quality Assurance Program Manual, Rev. 3, 14 November 2012.

_ _ _ _2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009.

_ _ _ _.2009. Quality Control Program, Rev. 2, 12 November 2009.

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, Illinois, 369-382 ..

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-7 46.

Northern States Power Company.

_ _ _..,.1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

____ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.

24

6.0 REFERENCES

CITED (continued)

Scannell, M. J., J. Giard, J. Raimondi. 2009. Environmental Neutron TLD Monitoring for ISFSI (Presentation and Report). 2009 RETS/REMP Workshop, South Bend, IN.

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.

____2009 to 2014. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012. Minneapolis, Minnesota.

____.2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2012.

Minneapolis, Minnesota.

25

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 lntercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2015 through December, 2015

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., 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 containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. 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.

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.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

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 lists REMP specific analytical results from 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.

Complete analytical data for duplicate analyses is available upon request.

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

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

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

A1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPU:;S 8

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

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

> 50 pCi/liter or kg 10% of known value Stronti um-90b 2 to 30 pCi/liter or kg 5.0 pCilliter

> 30 pCi/liter or kg 10% of known value Potassium-40  ;::: 0.1 g/liter or kg 5% of known value Gross alpha :5 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta :5 100 pCilliter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium :5 4,000 pCi/liter +/- 1o =

169.85 x (known) 0 ' 0933

> 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 lodine-131, :5 55 pCilliter 6 pCilliter lodine-129b >55 pCi/liter 10% of known value Uranium-238, :5 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b lron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/- 5.9 189.0 170.0 - 210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 -238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22.10-54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21.30 - 40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70 -28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56 -6.01 Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 -7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 -3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 -42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70 -36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/-4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/- 1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 -149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/-0.60 26.30 21.90-31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49 -8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46 -5.85 Fail ERW-5540* 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46 -5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 - 62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700-23,400 Pass

  • Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three determinations.

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

d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.

  • The result of reanalysis (Compare to original result, footnoted "e" above).

A1-1

TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental Inc.

2015-1 6/24/2015 30cm. 98.81 103.67 +/-6.05 69.20-128.50 Pass 2015-1 6/24/2015 30cm. 98.81 111.32+/-15.97 69.20 -128.50 Pass 2015-1 6/24/2015 60cm. 24.70 27.23 +/- 1.33 17.30-32.10 Pass 2015-1 6/24/2015 60cm. 24.70 26.98 +/-4.98 17.30-32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.78 +/-0.38 4.30-8.00 Pass 2015-1 6/24/2015 120cm. 6.18 6.43 +/-2.00 4.30 -8.00 Pass 2015-1 6/24/2015 150cm. 3.95 4.13 +/-0.72 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.12 +/-1.36 2.80-5.10 Pass 2015-1 6/24/2015 150cm. 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180cm. 2.74 3.27 +/-0.28 1.90-3.60 Pass 2015-1 6/24/2015 180cm. 2.74 3.05 +/-1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14 +/-0.18 1.90-3.60 Pass A2-1

TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental, Inc.

2015-2 12/15/2015 Spike 1 138.0 118.5 +/-2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 12/15/2015 Spike 3 138.0 121.9 +/- 1.9 -0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2+/-1.2 -0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 -0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/-5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/-3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 -0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/-2.7 -0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0 +/-3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass a TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose.

d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.

e Tables A2.1 and A2.2 assume 1 roentgen= 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015).

A2-2

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance W-020315 2/3/2015 Ra-226 16.19+/-0.42 16.70 13.36-20.04 Pass W-021215 2/12/2015 Gr. Alpha 18.38 +/- 0.39 20.10 16.08-24.12 Pass W-021215 2/12/2015 Gr. Beta 27.98 +/- 0.32 30.90 24.72- 37.08 Pass SPW-687 2/27/2015 Ni-63 239.6 +/- 3.5 202.4 161.9 - 242.9 Pass SPAP-689 3/2/2015 Gr. Beta 42.37 +/- 3.50 43.61 34.89 - 52.33 Pass SPAP-691 3/2/2015 Cs-134 1.77 +/- 0.61 1.90 1.52 - 2.28 Pass SPAP-691 3/2/2015 Cs-137 83.02 +/- 2.60 97.20 77.76-116.64 Pass SPW-693 3/2/2015 Cs-134 44.30 +/- 2.53 53.40 42.72-64.08 Pass SPW-693 3/2/2015 Cs-137 74.82 +/- 3.50 73.80 59.04 - 88.56 Pass SPW-693 3/2/2015 Sr-89 87.45 +/- 3.62 87.48 69.98- 104.98 Pass SPW-693 3/25/2015 Sr-90 37.22 +/- 1.55 38.10 30.48 - 45.72 Pass SPMI-697 3/2/2015 Cs-134 96.67 +/- 7.74 107.00 85.60 - 128.40 Pass SPMI-697 3/2/2015 Cs-137 78.51 +/- 7.02 73.84 59.07 - 88.61 Pass SPMI-697 3/2/2015 Sr-89 72.98 +/- 4.86 87.48 69.98- 104.98 Pass SPMI-697 3/2/2015 Sr-90 39.17+/-1.51 38.10 30.48-45.72 Pass SPW-699 3/2/2015 H-3 59,592 +/- 703 58,445 46,756 -70,134 Pass W-031115 3/11/2015 Ra-226 13.73 +/- 0.35 16.70 13.36-20.04 Pass W-030215 3/2/2015 Ra-228 32.79 +/- 2.31 31.44 25.15-37.73 Pass SPF-1040 3/16/2015 Cs-134 787.5 +/- 9.2 840.0 672.0 - 1,008.0 Pass SPF-1040 3/16/2015 Cs-137 2,599 +/- 24 2,360 1,888 - 2,832 Pass SPW-1036 3/25/2015 Fe-55 1,792 +/- 63 1961 1,569 - 2,353 Pass SPW-1374 4/6/2015 U-238 46.03 +/- 2.25 41.70 25.02 - 58.38 Pass W-040815 4/8/2015 Gr. Alpha 20.18 +/-0.42 20.10 16.08-24.12 Pass W-040815 4/8/2015 Gr. Beta 29.70 +/- 0.33 30.90 24.72 - 37.08 Pass SPW-1038 4/13/2015 C-14 3,497 +/- 9 4,734 2,840 - 6,628 Pass W-2165 4/20/2015 H-3 5550 +/- 226 5,780 3,468 - 8,092 Pass W-2165 4/20/2015 Sr-89 90.70 +/- 8.20 108.70 65.22 -152.18 Pass W-2165 4/20/2015 Sr-90 76.80 +/- 2.00 75.90 45.54 - 106.26 Pass W-2165 4/20/2015 Cs-134 62.40 +/- 6.40 57.30 34.38 - 80.22 Pass W-2165 4/20/2015 Cs-137 91.30 +/- 7.70 84.00 50.40 - 117.60 Pass W-2392 4/13/2015 H-3 5032 +/- 214 5780 3468-8092 Pass W-2392 4/13/2015 Ni-63 222.4 +/- 3.8 202.0 121.2 - 282.8 Pass W-2392 4/13/2015 Cs-134 53.26 +/- 5.01 57.30 34.38 - 80.22 Pass W-2392 4/13/2015 Cs-137 91.90 +/-7.76 84.20 50.52- 117.88 Pass W-042415 4/24/2015 Ra-226 12.52 +/- 0.39 16.70 10.02 - 23.38 Pass W-050715 5n/2015 Gr. Alpha 19.05+/-0.41 20.10 12.06-28.14 Pass W-050715 5n/2015 Gr. Beta 27.30 +/- 0.32 30.90 18.54 - 43.26 Pass W-061215 6/12/2015 Gr. Alpha 20.72 +/- 0.44 20.10 12.06-28.14 Pass W-061215 6/12/2015 Gr. Beta 28.51 +/- 0.33 30.90 18.54-43.26 Pass U-2982 6/9/2015 Gr. Beta 500.1 +/- 5.1 604.0 362.4 - 845.6 Pass U-3200 6/9/2015 H-3 2229 +/- 424 2346 1408 - 3284 Pass W-70915 7/9/2015 Gr. Alpha 18.76 +/- 0.40 20.10 12.1-28.1 Pass W-70915 7/9/2015 Gr. Beta 29.71 +/- 0.33 30.90 18.5 -43.3 Pass SPAP-3859 7/21/2015 Gr. Beta 41.59 +/- 0.12 43.61 26.17-61.05 Pass SPAP-3861 7/21/2015 Cs-134 1.69 +/- 0.60 1.69 1.0-2.4 Pass A3-1

T ABLEA-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87 -135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 - 65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222 -56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/- 3 31.44 18.86 - 44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5+/-115.9 740.0 444.0 - 1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1 ,404 - 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06-28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54 - 43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02 - 23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06-28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 - 43.26 Pass W-091415 9/14/2015 Gr. Alpha 19.35 +/- 0.51 20.10 12.06-28.14 Pass W-091415 9/14/2015 Gr. Beta 31.53 +/- 0.35 30.90 18.54 - 43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-100615 10/6/2015 Gr. Alpha 20.62 +/- 0.43 20.10 12.06-28.14 Pass W-100615 10/6/2015 Gr. Beta 29.35 +/- 0.33 30.90 18.54 - 43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 - 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52 - 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02 - 23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/- 2.48 31.44 18.86 - 44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738 - 15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 - 134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76 - 116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54 - 43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 -3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 - 43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02 - 23.38 Pass

  • Liquid sample results are reported in pCi/Liter, air filters( pCilm3), charcoal (pCi/charcoal canister), and solid samples (pCilkg).

b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to+/- 2s.

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

A3-2

TABLE A-4. In-House "Blank" Samples 8

Concentration (pCi/L)

Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)

W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/-3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/- 5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 1 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/- 0.25 2 W-050715 Water 5n/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMI-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance Type LLD Activityc .. Criteria (4.66 cr)

SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/-8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/- 0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/-0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2 a Liquid sample results are reported in pCi/Liter, air filters( pCilm\ charcoal (pCi/charcoal canister), and solid samples (pCilkg).

b 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72+/-0.12 5.78 +/- 0.12 5.75 +/- 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/- 0.135 0.919 +/- 0.102 0.917+/-0.15 Pass CF-62,63 1n/2015 K-40 3.97 +/- 0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 1/7/2015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/12/2015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90 +/- 1.16 Pass SG-83,84 1/12/2015 Tl-208 0.57 +/- 0.07 0.56 +/- 0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73+/-0.10 1.58 +/- 0.09 1.65 +/- 0.13 Pass SG-83,84 1/12/2015 Pb-214 13.33 +/- 0.33 13.88 +/- 0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47 +/- 0.24 Pass SG-83, 84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 1/12/2015 Ac-228 13.33 +/- 0.59 12.86 +/- 0.43 13.09 +/- 0.36 Pass AP-011215NB 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-6001 0,60011 1/28/2015 Ra-226 1.25+/-0.14 1.40 +/- 0.15 1.33 +/- 0.10 Pass DW-60010,60011 1/28/2015 Ra-228 2.00 +/- 0.66 1.39 +/- 0.60 1. 70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-214 6.45 +/- 0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/- 0.24 4.20 +/- 0.58 4.32 +/- 0.31 Pass AP-020415NB 2/4/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115NB 2/11/2015 Gr. Beta 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass DW-60023,60024 2/26/2015 Ra-226 1.52+/-0.15 1.51 +/- 0.15 1.52 +/- 0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/- 0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 2/26/2015 K-40 11.96 +/- 0.98 11.49 +/- 0.82 11.72 +/- 0.64 Pass S-799,800 2/26/2015 Tl-208 0.36 +/- 0.04 0.31 +/- 0.04 0.34 +/- 0.03 Pass S-799,800 2/26/2015 Pb-212 0.92 +/- 0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 2/26/2015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2/26/2015 Ac-228 1.35 +/- 0.22 1.23+/-0.17 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3+/-6.3 117.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 2/2/2015 Gr. Beta 82.27 +/- 2.79 84.33 +/- 2.74 83.30 +/- 1.96 Pass DW-60031 ,60032 3/4/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/- 7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/- 0.34 6.88 +/- 0.32 6.89 +/- 0.23 Pass DW-60036,60037 3/4/2015 Ra-228 4.43 +/- 0.73 4.41 +/-0.72 4.42 +/- 0.51 Pass DW-60048,60049 3/4/2015 Ra-226 0.84 +/- 0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169, 1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/9/2015 Gr. Beta 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 4/13/2015 H-3 1,628 +/- 139 1,695 +/- 141 1,662 +/- 99 Pass SG-1847, 1848 4/20/2015 K-40 3.24 +/- 1.18 1.99+/-0.76 2.62 +/- 0.70 Pass SG-1847, 1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847, 1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/23/2015 H-3 6,584 +/- 244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/27/2015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/- 64.3 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/- 3.63 43.61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/- 2.02 51.40 +/- 1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 +/- 0.62 13.67 +/- 0.40 Pass SG-1868, 1869 4/28/2015 Ra-228 20.10 +/- 0.92 22.10 +/- 1.29 21.10+/-0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087,60088 5/14/2015 Ra-226 1.58 +/- 0.17 1.52 +/- 0.17 1.55+/-0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/- 0.61 47.80 +/- 0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/- 7.9 254.6 +/- 7.6 261.2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10+/-0.92 40.80 +/- 0.83 40.95 +/- 0.62 Pass DW-60095,60096 5/26/2015 Gr. Alpha 1.34 +/- 0.69 0.91 +/- 0.62 1.13 +/- 0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/- 0.14 1.08+/-0.12 0.97 +/- 0.09 Pass S-2627,2628 5/29/2015 Cs-137 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/- 0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11.15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/- 214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/- 658 20,987 +/- 600 21,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-301 07,30108 6/8/2015 Gr. Alpha 1.34 +/- 0.82 1.47 +/- 0.85 1.41 +/- 0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/- 0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841.9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Beta 0.023 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78+/-0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass VE-3300,3301 6/24/2015 K-40 29.12 +/- 0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass AP-062915 6/29/2015 Gr. Beta 0.023 +/- 0.005 0.023 +/- 0.005 0.023 +/- 0.003 Pass WW-3632,3633 6/30/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114+/-158 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-3822, 3823 7/1/2015 Be-7 0.075 +/- 0.011 0.068 +/- 0.012 0.072 +/- 0.008 Pass AP-3969, 3970 7/1/2015 Be-7 0.063 +/- 0.008 0.064 +/- 0.010 0.063 +/- 0.006 Pass WW-3632, 3633 7/6/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114 +/- 159 Pass W-4368, 4369 7/6/2015 Gr. Alpha 26.70 +/- 4.00 24.10 +/- 3.90 25.40 +/- 2.79 Pass W-4368, 4369 7/6/2015 Gr. Beta 34.62 +/- 2.10 33.30 +/- 2.02 33.96 +/- 1.46 Pass DW-60138, 60139 717/2015 Ra-226 0.07 +/- 0.04 0.11 +/- 0.05 0.09 +/- 0.03 Pass DW-60138, 60139 717/2015 Ra-228 1.04+/-0.41 1.15+/-0.47 1.10+/-0.31 Pass WW-4158, 4159 7/9/2015 H-3 138.8 +/- 82.4 174.0 +/- 84.1 156.4 +/- 58.9 Pass Ml-2902, 2903 7/10/2015 K-40 1271 +/- 118 1308 +/- 115 1289 +/- 82 Pass SG-3533, 3534 7/10/2015 Gr. Alpha 238.0 +/- 8.2 249.5 +/- 8.5 243.8 +/- 5.9 Pass DW-60150, 60151 7/10/2015 Ra-226 1.53+/-0.16 1.49 +/- 0.12 1.51 +/- 0.10 Pass DW-60150, 60151 7/10/2015 Ra-228 2.68 +/- 0.68 1.89 +/- 0.62 2.29 +/- 0.46 Pass VE-3716, 3717 7/14/2015 K-40 3.85 +/- 0.33 3.71 +/- 0.31 3.78 +/- 0.23 Pass Ml-3759, 3760 7/15/2015 K-40 1819 +/- 127 1764 +/- 140 1791 +/- 94 Pass Ml-3759, 3760 7/15/2015 Sr-90 1.00 +/- 0.36 0.61 +/- 0.32 0.80 +/- 0.24 Pass AP-072115 7/21/2015 Gr. Beta 0.022 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 Pass VE-4053, 4054 7/21/2015 Be-7 0.52 +/- 0.15 0.49 +/- 0.11 0.50 +/- 0.09 Pass VE-4053, 4054 7/21/2015 K-40 8.00 +/- 0.42 7.61 +/- 0.31 7.81 +/- 0.26 Pass AP-4200, 4201 7/29/2015 Be-7 1.06+/-0.12 0.96 +/- 0.11 1.01 +/- 0.08 Pass AP-4200, 4201 7/29/2015 K-40 5.03 +/- 0.24 4.96 +/- 0.23 4.99 +/- 0.16 Pass W-4137, 4138 7/31/2015 Ra-226 0.58 +/- 0.13 0.45 +/- 0.14 0.52+/-0.10 Pass XWW-4431, 4432 8/5/2015 H-3 4,773 +/-213 4,915 +/- 216 4,844 +/- 152 Pass SG-4305, 4306 8/6/2015 Ra-228 10.34 +/- 0.58 11.46 +/- 0.62 10.90 +/- 0.42 Pass AP-081015 8/10/2015 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 0.004 Pass AP-081115 8/11/2015 Gr. Beta 0.024 +/- 0.004 0.020 +/- 0.004 0.022 0.003 Pass VE-4452, 4453 8/11/2015 K-40 3.77 +/- 0.29 3.78 +/- 0.26 3.77 +/- 0.20 Pass AP-081715 8/17/2015 Gr. Beta 0.030 +/- 0.005 0.030 +/- 0.005 0.030 +/- 0.003 Pass DW-60195, 60196 8/17/2015 Ra-226 0.39+/-0.10 0.37 +/- 0.10 0.38 +/- 0.07 Pass DW-60195, 60196 8/17/2015 Ra-228 1.43 +/- 0.51 1.97 +/- 0.61 1.70 +/- 0.40 Pass DW-60198, 60199 8/17/2015 Gr. Alpha 2.93 +/- 0.94 2.11 +/- 0.96 2.52 +/- 0.67 Pass VE-4578, 4579 8/18/2015 K-40 4.14 +/- 0.25 4.32 +/- 0.24 4.23 +/- 0.17 Pass SW-4662, 4663 8/25/2015 H-3 351.3 +/- 89.8 415.6 +/- 92.8 383.4 +/- 64.6 Pass DW-60212, 60213 8/25/2015 Ra-226 0.09 +/- 0.07 0.10+/-0.08 0.10 +/- 0.05 Pass LW-4788, 4789 8/27/2015 Gr. Beta 0.97 +/- 0.51 1.68 +/- 0.59 1.32 +/- 0.39 Pass AP-083115 8/31/2015 Gr. Beta 0.032 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-4875, 4876 9/3/2015 Be-7 0.294 +/- 0.125 0.202 +/- 0.109 0.248 +/- 0.083 Pass VE-5083, 5084 9/14/2015 Be-7 0.47 +/- 0.23 0.56 +/- 0.19 0.52 +/- 0.15 Pass VE-5083, 5084 9/14/2015 K-40 6.20 +/- 0.51 6.36 +/- 0.50 6.28 +/- 0.36 Pass VE-5167, 5168 9/16/2015 Be-7 0.40 +/- 0.11 0.41 +/-0.10 0.41 +/- 0.07 Pass VE-5167, 5168 9/16/2015 K-40 3.56 +/- 0.27 3.91 +/- 0.24 3.74+/-0.18 Pass BS-5188, 5189 9/16/2015 K-40 9.69 +/- 0.51 10.51 +/- 0.52 10.10 +/- 0.36 Pass F-5419, 5420 9/17/2015 K-40 3.48 +/- 0.47 3.49 +/- 0.56 3.49 +/- 0.36 Pass DW-60238, 60239 9/18/2015 Ra-226 1.93 +/- 0.23 2.31 +/- 0.26. 2.12 +/- 0.17 Pass DW-60238, 60239 9/18/2015 Ra-228 4.44 +/- 0.78 5.61 +/- 0.84 5.03 +/- 0.57 Pass AP-092215NB 9/22/2015 Gr. Beta 0.021 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.00 Pass WW-5398, 5399 9/22/2015 H-3 1,857 +/- 145 1,846 +/- 144 1,852 +/- 102 Pass AP-6007, 6008 9/28/2015 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108+/-211 2,220 +/- 157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461 ,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461 ,2 10/1/2015 K-40 8.77 +/- 0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/- 0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17 +/- 0.73 2.10 +/- 0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192+/-123 1,318+/-127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 O.D78 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29.80 +/-2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/- 0.29 4.13+/-0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/-0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45 +/-0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16+/-0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08+/-0.15 1.14 +/- 0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/- 0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/- 0.43 2.16 +/- 0.37 2.14 +/-0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28 +/- 1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 170 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17 +/- 0.03 0.19 +/- 0.03 0.18 +/- 0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6 +/- 1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A 5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)'

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Pass Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 Pass S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 Pass S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 Pass WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 Pass SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 Pass SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 Pass LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 Pass AP-7351 , 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 Pass AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

' Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil, sediment (pCi/g).

A5-5

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314-582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457 - 849 Pass MAS0-97 5 2/1 /2015 Tc-99 614 +/- 12 867 607- 1'127 Pass MAS0-975 2/1/2015 Cs-134 533 +/- 6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5+/-1.0 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 - 1,062 Pass MAS0-975 2/1/2015 Mn-54 1 ,153 +/- 9 1,198 839 - 1,557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 - 1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 - 30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 - 24.8 Pass MAW-969 ct 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9 - 38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82-8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 - 23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23-4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NAe Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104-0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 - 1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 - 12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 - 4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04-1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA c Pass MAAP-978 f 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06-1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass

-MAAP-978 2/1/2015 Mn-54 1.11 +/-0.08 1.02 0.71 -1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass A6-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3-61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/-0.12 0.00 NA c Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 - 0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74 -1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 -3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/- 0.13 7.32 5.12 - 9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass MAVE-972 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass MAVE-972 2/1/2015 Zn-65 0.09 +/-0.12 0.00 NA c Pass MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477-887 Pass 9

MAS0-4903 8/1/2015 Sr-90 231 +/-7 425 298-553 Fail 9

MAS0-4903 8/1/2015 Sr-90 352 +/- 10 425 298 -553 Pass MAS0-4903 h 8/1/2015 Tc-99 411 +/-11 631 442 -820 Fail MAS0~4903 8/1/2015 Cs-134 833 +/- 10 1,010 707 -1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566- 1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 - 1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463 - 861 Pass A6-2

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30.0 Pass MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 NA c Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6-27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 12.0-22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151.0-281.0 Pass MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 9.2 - 17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 - 20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0-11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 -18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03 - 9.35 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 3.36-6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13-0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 - 1.94 Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79-5.17 Pass MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74 -1.37 Pass MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78-2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 -7.54 Pass MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/-0.18 6.62 4.63 - 8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/-0.15 4.56 3.19-5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38-9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 -7.10 Pass a Results are reported in units of Bqlkg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of"zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.

ct Lab result was 27 .84. Data entry error resulted in a non-acceptable result.

e Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

1 Lab result was 1.58. Data entry error resulted in a non-acceptable result.

9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

h The complex sample matrix is interfering with yield calculations causing a failed low result. An investigation is in process to determine a more reliable yield determination.

1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.

A6-3

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/- 2.2 49.8 30.7-67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2-98.8. Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 - 1'130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312+/-12 1,170 879 - 1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 - 1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0 - 50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/- 3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20 - 52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 - 145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21.3-51.7 Pass ERAP-1091 3/16/2015 U-238 31.0 +/- 1.1 34.0 22.0-47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 - 1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8-96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/- 0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 157.1.8 +/- 209.6 1,500 878 - 1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 - 1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474-2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180-7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1,140-1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810-14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 - 1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032 +/- 41 1,230 806 - 1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 - 6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 - 1,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1 '185 +/- 140 1,210 791-1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724+/-125 1,940 740 - 3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/- 948 3,890 1,230 - 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/- 226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,41 0 - 4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 - 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2- 184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900- 14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/- 266 4,340 2,650 - 5, 770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666 - 2,120 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)*.

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060-2,150 Fail ERVE-1100 r 3/16/2015 Co-60 1,684 +/- 48 1,540 1,060-2,150 Pass ERVE-1100 e 3/16/2015 Cs-134 1,615 +/-27 2,650 1, 700 - 3,440 Fail ERVE-1100 r 3/16/2015 Cs-134 2,554 +/- 49 2,650 1, 700 - 3,440 Pass ERVE-1100° 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310 - 2,520 Fail ERVE-1100 r 3/16/2015 Cs-137 2,078 +/- 68 1,810 1 ,310 - 2,520 Pass ERVE-11 00 e 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 - 43,400 Fail ERVE-1100 r 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass ERVE-11 00 e 3/16/2015 Mn-54 <13.8 <300 0.0-300.0 Pass ERVE-1100 r 3/16/2015 Mn-54 <24.4 <300 0.0- 300.0 Pass ERVE-1100 3/16/2015 Pu-238 3,232 +/- 232 3,680 2,190 - 5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570-5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/- 326 6,590 3,760-8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 - 3,980 Pass ERVE-11 00 e 3/16/2015 Zn-65 <94.6 1,090 786 - 1,530 Fail ERVE-1100 r 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 - 1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0-61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/- 17 1,250 1,090 - 1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/- 18 1,260 925- 1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/- 31 1,360 1,150 - 1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 - 100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6 - 90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 - 232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/- 4.9 97.7 66.6 - 108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 - 79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 - 75.2 Pass ERW-1103 3/16/2015 Zn-65 1,191 +/- 136 1,180 984 - 1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 - 1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 - 1,210.0 Pass

  • Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCI/kg).

  • Unless otherwise indicated, the laboratory result is given as the mean+/- standard deviation for three detenminations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and ccntrollimits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

  • Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) r The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).

9 The results of reanalysis were outside the control limits (low).

h Sample ERW-3742 was ordered from ERA to detenmine why ERW-1103 results for Pu-239 were outside the acceptable range.

The results for ERW-37 42 were acceptable. No reason for the unacceptable results for ERW-37 42 was determined.

A7-2

APPENDIX B. DATA REPORTING CONVENTIONS 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 == 2a 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 4.66cr uncertainty for a background sample.

3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows. :

3.1 Individual results: For two analysis results; x 1 +/- s 1 and x2 +/- s 2 Reported result: x +/- s; where x == (1/2) (x 1 + x2 ) and s == (1/2) ~ s~ + s; 3.2. Individual results: < L1 , < L2 Reported result: < L, where L == lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- 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 ~nnual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers x1 , x2 . . . xn are defined as follows:

X

- 1

=r; LX s-

-A~ \jnT 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 number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

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

B-1

APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a

background in unrestricted areas .

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

-3 Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 c

Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 X 10 a

Taken from Table 2 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-1

APPENDIX D Sampling Location Maps D-1

1 I

I III iI I

Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring (Table 5.2)

D-2

Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2)

D-3

Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2)

D-4

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D-5

Figure 0-5, Sample Collection and analysis program: TLD locations, ISFSI TLD Locations. (Table 5.2)

D-6

APPENDIX E Ground Water Monitoring Well Samples E-1

1.0 INTRODUCTION

This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January - December 2015. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.

E-2

2.0

SUMMARY

Onsite groundwater is monitored at MNGP in accordance with the guidance presented in NEI 07-07.

This initiative was developed by the Nuclear Energy Institute (NEI) and nuclear industry stakeholders to address a gap in industry guidance and practices for monitoring groundwater and responding to inadvertent releases of radioactive material with the potential to contaminate groundwater. The initiative sets forth voluntary requirements for evaluating and monitoring Systems, Structures and Components (SSCs) with a high risk of contaminating groundwater. Additionally, the guidance specifies reporting requirements for onsite groundwater sample results that exceed REMP reporting thresholds and that all onsite groundwater results are reported in either the ARERR (Effluent) or AREOR(REM~ffiports.

Previously, all groundwater sample results have been reported in the REMP report. It has been determined that onsite groundwater monitoring results are more appropriately reported in the Effluent report, while the true REMP well water sample results belong in the REMP report. For 2015, the results for onsite groundwater monitoring wells will be reported in both reports. Subsequent reports are planned to include only REMP well water samples in the REMP report and only onsite groundwater monitoring samples in the Effluent report.

The current groundwater monitoring program includes wells at 15 locations with four of those locations in a "nested" configuration, where one sample is taken at the level of the water table (locations ending with an 'A') while a second sample can be taken from deeper water (locations ending with a '8').

Sample Frequency for Groundwater Wells is summarized in Table E-1, locations relative to the plant stack are provided in Table E-2, and a map of monitoring well locations is provided in Figure E-1.

Several wells are considered sentinel wells that would indicate if radioactive material were migrating offsite into the Mississippi River; wells MW-2, -3, -4, -14, -15A & -158 fit into the sentinel well category.

Additional sampling performed under the guidance of the Groundwater Protection Program includes sampling water from storm drains. These samples periodically indicate elevated tritium activities due to recapture of tritium from gaseous effluents.

The GWPP includes an LLD requirement of 300 pCi/L for tritium, which is significantly lower than the REMP LLD of 2000 pCi/L. The LLD was set conservatively lower in order to ensure that any indication of potential leaks or spills would be quickly identified and to ensure that concentrations of tritium are well characterized. In practice, samples were counted to an even lower level, approximately 150 pCi/L.

Program findings for 2015 detected low levels of tritium in monitoring wells located on the plant property. Monitoring well MW-9A results indicate tritium activities ranging from 6,493 pCi/L to less than 147 pCi/L; this peak concentration is comparable to the 2014 peak concentration 5,911 pCi/L.

Monitoring well MW-10 results indicate tritium activities ranging from 453 pCi/L down to 155 pCi/L and is also consistent with 2014 results for this well. All other monitoring well and storm water runoff samples indicated tritium activities that were less than 300 pCi/L. All GWPP tritium results for 2015 were below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public.

No gamma emitting isotopes were identified in groundwater or storm water runoff samples in 2015.

A summation of the 2015 analytical results for groundwater monitoring well and storm water runoff samples is provided in Table E-3, and complete results are available in Table E-4.

E-3

3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to ensure timely detection of inadvertent radiological releases to ground water at MNGP. For this purpose, water samples are collected and analyzed for tritium content and presence of gamma-emitting radionuclides.

3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.

Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.

3.3 Program Execution Groundwater sample results are summarized in Table E-3. Results of individual analyses are reported in Table E-4. The Program was executed as described with the following exceptions:

Two groundwater samples were missed in 2015. The July sample for MW-138 was missed due to a broken sample pump. The March sample for MW-14 was missed due to a frozen column of water blocking the monitoring well cavity.

Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells.

3.4 Program Modifications There were no additional on-site monitoring wells added to the ground water program and no changes to sampling frequency or other GWPP requirements in 2015.

E-4

3.5 Results and Discussions Results for 2015 indicate that no gamma emitting isotopes were identified in groundwater samples. Monitoring well MW-9A results indicate activities ranging from 6,493 +/- 237 pCi/1 to <147 pCi/1; this peak concentration is comparable to the 2014 peak concentration 5,911

+/- 279 pCi/1. Monitoring well MW -10 results indicate tritium activities ranging from 453 +/- 98 pCi/1 to 155 +/- 79 pCi/1 and is also consistent with 2014 results for this well. All other monitoring well and storm water samples indicated activities that were less than 300 pCi/1.

Historically, monitoring Well MW-9A has indicated elevated tritium levels that vary seasonally since 2009. It is understood that there is likely a plume of water containing tritium under the Turbine Building that moves tritium activity into, and out from, the monitoring well depending upon the hydraulic gradient at the time of sampling; the plume is considered to be stagnant under the turbine building, based on results from surrounding wells. Evidence indicates that the activity in the plume originated from process water containing tritium that leached through the turbine building concrete base mat. Potential sources of tritium were thoroughly evaluated in the Corrective Action Program and all identified sources that were potentially contributing tritium to the turbine building base mat were corrected during the 2011 refueling outage. Corrective actions taken included lining sumps and discontinuing use of embedded piping that were identified as potential sources of the tritium found in the plume.

Tritium is also regularly identified in samples from MW-1 0. Levels of tritium activity in this well are more consistent throughout the year and at a significantly lower level than the levels of activity observed in MW-9A.

The Lower Limit of Detection (LLD) for groundwater monitoring of tritium at MNGP during 2015 was less than 300 pCi/1, in accordance with station processes and procedures; this LLD is far below the required REMP LLD (2,000 pCi/1) and very far below the REMP reporting threshold for water samples (20,000 pCi/1). The site has chosen to use this low LLD in order to quickly identify and characterize any potential contamination sources. The LLD as reported represents the activity at which there is a 95% chance that a sample containing that level of activity would be characterized as detected with only a 5% chance that the sample would be characterized as a blank.

The Xcel Energy Groundwater Protection Program has established a Baseline Threshold Level for tritium, defined as the 95% Confidence Level determined using Student's t and a statistical mean of ten or more sample results; at this level the a sample would be considered to be statistically different from background, based on analytical results. For wells that consistently indicate near or below LLD, the Baseline Threshold Level is 400 pCi/1. The program also provides an Action Level of 3-times the Baseline Threshold Level, or 1200 pCi/1 for these wells; at this level, additional action is taken to evaluate the cause of the change in activity and work through the Corrective Action process to address the concern. Note that this Action Level is still below the required REMP LLD of 2000 pCi/1. No statistically significant concentrations of tritium were identified in sentinel wells in 2015; therefore no tritium discharge to ground water is reported.

E-5

Table E-1. Sample Collection and Analysis Program, Ground Water.

Medium Number Sample Codes Collection type Analysis Type Ground Water 32 MW-1, MW-2, MW-3, MW-4, Grab H-3 Quarterly MW-98, MW-11, MW-12A, MW-128, 8

Ground Water 82 MW-9A, MW-10, MW-13A, Grab H-3 Monthly MW-138, MW-14, MW-15A MW-158, Ground Water 4 MW-5, MW-6, MW-7, MW-8 Grab H-3 Annual a Two ground water samples were m1ssed 1n 2015. The July sample for MW-138 was m1ssed due to a broken sampling pump. The March sample for MW-14 was missed due to ice plugging the well.

Table E-2. Sampling locations for Ground Water Monitoring Wells.

Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 sw Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9A 0.1 310 NW Ground Water M-51 MW-98 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-11 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-128 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-138 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW Ground Water M-53 MW-15A 0.14 14 NNE Ground Water M-54 MW-158 0.14 14 NNE E-6

Table E-3. Ground Water Monitoring Program Summary.

Name of Facility Monticello Nuclear Generating Plant Docket No. ...:5..:0...:-2:..:6...:.3-------,----

Location of Facility Wright, Minnesota Reporting Period January-December, 2015

( County, State )

Indicator Location with Highest Sample Type and ,. Locations Annual Mean 0

Type Number of LLDb Mean (F) Mean (F)"

(Units) Analyses' Range* Locationd Range*

Groundwater H-3 118 300 603 (47/118) MW-9A, On-site, 1985 (10/13)

Monitoring Wells (144-6493) 0.1 mi@310"/NW (182-6493)

(pCi/L)

Stormwater H-3 4 300 157(1/4) SD-006 157(1/4)

Runoff On-site (pCi/L) GS 4 Mn-54 10 < LLD - -

Fe-59 30 < LLD - -

Co-58 10 < LLD - -

Co-60 10 < LLD - -

Zn-65 30 < LLD - -

Zr-Nb-95 15 < LLD - -

1-131 30 < LLD - -

Cs-134 10 < LLD - -

Cs-137 10 < LLD - -

Ba-La-140 15 < LLD - -

Ce-144 43 < LLD - -

Sewer lift H-3 2 300 < LLD - -

Station (pCi/L) GS 2 Mn-54 10 < LLD - -

Fe-59 30 < LLD - -

Co-58 10 < LLD - -

Co-60 10 < LLD - -

Zn-65 30 < LLD - -

Zr-Nb-95 15 < LLD - -

1-131 30 < LLD - -

Cs-134 10 < LLD - -

Cs-137 10 < LLD - -

Ba-La-140 15 < LLD - -

Ce-144 43 < LLD - -

'GB = gross beta, GS =gamma scan.

b 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: (1) by name, and/or station code 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.

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Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes.

Collection Concentration (pCi/L)

ZrNb 13<cs 137cs 14oBala 1<<ce 3H s*Mn ssFe ssco so co sszn 95 Lab Code Date Monitoring Well #1 (M-33)

MWW- 705 02/24/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 2562 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 4755 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 26 MWW- 6609 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 15 Monitoring Well #2 (M-34)

MWW- 706 02/24/15 169 +/- 80 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 25 MWW- 2563 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 33 MWW- 4756 08/24/15 < 150 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 6610 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 47 Monitoring Well #3 (M-35)

MWW- 707 02/24/15 218 +/- 82 < 10 < 30 < 10 < 10 < 30 <15 < 10 <10 < 15 < 33 MWW- 2565 05/21/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 16 MWW- 4757 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 MWW- 6612 11/18/15 248 +/- 90 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 46 Monitoring Well #4 (M-36)

MWW- 708 02/20/15 < 146 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 37 MWW- 2566 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 34 MWW- 5243 09/23/15 < 144 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 <56 MWW- 6613 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 < 29 Monitoring Well #5 (M-37)

MWW- 4758 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 Monitoring Well #6 (M-38)

MWW- 4759 08/24/15 < 150 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 10 Monitoring Well #7 (M-39)

MWW- 4760 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 Monitoring Well #8 (M-40).

MWW- 4761 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 E-9

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCiiL)

Lab Code Date Monitoring Well #9A (M-44)

MWW- 250 01121115 2556 +/- 199 MWW- 709 02120115 667 +/- 103 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 23 MWW- 1199 03117115 282 +/- 85 MWW- 1896 04122115 < 147 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 22 MWW- 2567 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 26 MWW- 3147 06118/15 361 +/- 89 MWW- 4087 07121115 5443 +/- 226 MWW- 4772 08121115 6493 +/- 237 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5398 09122115 1857 +/- 145 MWW- 6096 10120115 353 +/- 95 MWW- 6614 11117115 182 +/- 87 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 7260 12115115 1652 +/- 135 Monitoring Well #98 (M-51)

MWW- 710 02120115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 23 MWW- 2568 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 18 MWW- 4773 08121115 < 173 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 20 MWW- 6615 11117115 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 18 Monitoring Well #1 0 (M-45)

MWW- 252 01121115 251+/-110 MWW- 711 02124115 381 +/- 90 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 1138 03117115 453 +/- 98 MWW- 1897 04122115 283 +/- 88 MWW- 2569 05121115 352 +/- 106 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 20 MWW- 3148 06118115 250 +/- 84 MWW- 4273 07123115 180 +/- 88 MWW- 4762 08124115 236 +/- 100 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5244 09123115 293 +/- 86 MWW- 5938 10120115 270 +/- 90 MWW- 6616 11118115 258 +/- 91 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 34 MWW- 7061 12115115 155 +/- 79 Monitoring Well #11 (M-46)

MWW- 712 02124115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 47 MWW- 2570 05121115 < 151 < 10 < 30 <10 <10 < 30 <15 <10 <10 < 15 < 26 MWW- 4763 08124115 260 +/- 101 < 10 < 30 <10 <10 < 30 <15 <10 <10 <15 < 33 MWW- 6617 11118115 < 149 < 10 < 30 <10 <10 < 30 <15 <10 <10 <15 < 26 Monitoring Well #12A (M-47)

MWW- 713 02120115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 27 MWW- 2571 05120115 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 16 MWW- 4764 08125115 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 22 MWW- 6618 11117115 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 30 a Station duplicate sent. MWW-251 result= 2523+/-198 pCi/L.

E-10

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)

Lab Code Date Monitoring Well #128 (M-48)

MWW- 714 02/20/15 < 146 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 25 MWW- 2572 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 26 MWW- 4765 08/25/15 < 173 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 32 MWW- 6619 11/17/15 < 149 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 <28 Monitoring Well #13A (M-49)

MWW- 254 01/21/15 < 182 MWW- 715 02/24/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 1139 03/17/15 < 153 MWW- 1898 04/22/15 < 147 MWW- 2573 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 3149 06/18/15 < 143 MWW- 4274 07/27/15 153 +/- 87 MWW- 4766 08/25/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 MWW- 5245 09/23/15 255 +/- 84 MWW- 5939 10/20/15 161 +/- 85 MWW- 6620 11/18/15 182 +/- 87 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 7062 12/15/15 < 146 Monitoring Well #138 (M-50)

MWW- 255 01/21/15 < 182 MWW- 717 02/24/15 203 +/- 81 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 33 MWW- 1140 03/17/15 220 +/- 87 MWW- 1899 04/22/15 240 +/- 85 MWW- 2574 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 MWW- 3893 06/18/15 215 +/- 88 MWW- 4767 08/25/15 172 +/- 83 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 MWW- 5246 09/23/15 184 +/- 81 MWW- 5940 10/20/15 169 +/- 86 MWW- 6621 11/18/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 20 MWW- 7064 12/15/15 < 146 Monitoring Well #14 (M-52)

MWW- 256 01/21/15 < 182 MWW- 718 02/16/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 MWW- 1900 04/21/15 < 147 MWW- 2575 05/19/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 MWW- 3150 06/16/15 < 143 MWW- 4275 07/20/15 < 151 MWW- 4769 08/17/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 5247 09/23/15 < 142 MWW- 5941 10/20/15 < 147 MWW- 6622 11/16/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 7065 12/14/15 < 146 E-11

Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L) 54 sgFe sa co so co ZrNb 134cs 137Cs 14oBala 144ce 3H sszn 95 Lab Code Date Mn Monitoring Well #15A (M-53)

MWW- 257 01/21/15 < 182 MWW- 719 02/20/15 < 146 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 32 MWW- 1141 03/17/15 < 153 MWW- 1901 04/22/15 < 147 MWW- 2576 05/20/15 < 151 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 MWW- 3151 06/18/15 < 143 MWW- 4276 07/23/15 < 151 MWW- 4770 08/25/15 < 173 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 22 MWW- 5248 09/23/15 < 142 MWW- 5942 10/20/15 < 147 MWW- 6623 11/18/15 < 149 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 MWW- 7066 12/15/15 < 146 Monitoring Well #158 (M-54)

MWW- 258 01/21/15 206 +/- 108 MWW- 720 02/20/15 180 +/- 80 < 10 < 30 < 10 <10 < 30 <15 < 10 <10 < 15 < 21 MWW- 1142 03/17/15 203 +/- 87 MWW- 1902 04/22/15 228 +/- 85 MWW- 2577 05/20/15 < 151 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 27 MWW- 3152 06/18/15 144 +/- 79 MWW- 4277 07/24/15 275 +/- 92 MWW- 4771 08/25/15 199 +/- 99 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 MWW- 5249 09/23/15 249 +/- 84 MWW- 5943 '10/20/15 161 +/- 85 MWW- 6624 11/18/15 217 +/- 89 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 < 15 < 28 MWW- 7067 12/15/15 < 146 Storm Water Run-off (SD-006)

MXW- 2384 04/24/15 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 <10 < 15 <8 MXW- 2385 04/24/15 < 147 < 10 < 30 < 10 <10 < 30 < 15 <10 <10 < 15 < 10 a MXW- 4163 07/28/15 157 +/- 85 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 17 MXW- 6250 10/23/15 < 143 < 10 < 30 <10 < 10 < 30 < 15 < 10 < 10 < 15 < 32 Storm Water Run-off (Sewer Lift Station)

MXW- 2091 04/27/15 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 16 MXW- 6887 12/03/15 < 145 < 10 < 30 < 10 < 10 < 30 < 15 <10 < 10 < 15 < 15 Station duplicate.

E-12

Table E-4. Ground water, analyses for hard to detect isotopes.

Collection Concentration (pCi/L}

Lab Code Date Location Gross Alpha MWW- 1896 04/22/15 MW-9a < 1.6 < 4.1 < 3.3 < 674 < 101 E-13

Environmental, Inc.

I Midwest laboratory 700 Landwehr Ro'd , Northbrook, ll60062*1310 phone (847) 564.0700. fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO 50-263 LICENSE NO DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PART II Radiological Environmental Monitoring Program Complete Analyses Data Tables January- December, 2015 Prepared under contract by ENVIRONMENTAL, INC MIDWEST LABORATORY PROJECT NO 8010 Reviewed and Approved

MNGP TABLE OF CONTENTS Section Page List of Tables................................................................................................................... iii 10 INTRODUCTION ............................................................................................................. iv 20 LISTING OF MISSED SAMPLES .................................................................................. . v 30 DATA TABLES ................................................................................................................ vi ii

MNGP LIST OF TABLES Ambient radiation as measured by thermoluminescent dosimeters (TLDs) .... ...... ...... ...... ........... 1-1 2 Airborne particulates and iodine collected at Location M-1 (C), analysis for gross beta and iodine-131 ............................................................................................................... 2-1 3 Airborne particulates and iodine collected at Location M-2, analysis for gross beta and iodine-131 ...................................................................................................................... 3-1 4 Airborne particulates and iodine collected at Location M-3, analysis for gross beta and iodine-131 ...................................................................................................................... 4-1 5 Airborne particulates and iodine collected at Location M-4, analysis for gross beta and iodine-131 ...................................................................................................................... 5-1 6 Airborne particulates and iodine collected at Location M-5, analysis for gross beta and iodine-131 ......................................................................... ............................................. 6-1 7 Airborne particulates, analysis for gross beta, monthly averages................................................ 7-1 8 Airborne particulate samples, quarterly composites from each location, analysis for gamma-emitting isotopes.............................................................................................. 8-1 9 Pasture Grass, vegetation, analysis for iodine-131 and gamma emitting isotopes...................... 9-1 10 River water, upstream, M-8 (C) and M-9, analysis of monthly composites for gamma-emitting isotopes............................................................................................................ 10-1 11 Drinking water, City of Minneapolis, M-14, analysis of monthly composites for gross beta, iodine-131 and gamma-emitting isotopes............................................................. 11-1 12 River water and drinking water, analysis of quarterly composites for tritium................................ 12-1 13 Well water, analysis for tritium and gamma-emitting isotopes..................................................... 13-1 14 Fish, analysis of edible portions for gamma-emitting isotopes..................................................... 14-1 15 Aquatic Invertebrates, analysis for gamma-emitting isotopes...................................................... 15-1 16 Shoreline sediments, analysis for gamma-emitting isotopes....................................................... 16-1 iii

MNGP 10 INTRODUCTION The following constitutes the final 2015 report for the Environmental Radiological Monitoring Program conducted at the Monticello Nuclear Generating Plant in Monticello, Minnesota Results of completed analyses are presented in the attached tables All concentrations, except gross beta, are decay corrected to the time of collection All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples iv

MNGP 20 LISTING OF MISSED SAMPLES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting Plans for Preventing Type Period REMP as Recurrence required AP/AI Beta, 1-131 M-005 1/28/2015 Power was reset Power loss at sample station sw Gamma M-008 January '15 Water frozen entire month; None no composite AP/AI Beta, 1-131 M-002 2/4/2015 Air sampler not running Replaced air sampler due to bad switch sw Gamma M-008 February '15 Water frozen entire month; None no composite sw Gamma M-008 3/4/15 Water frozen None sw Gamma M-008 3/11/15 Water frozen None AP/AI Beta, 1-131 M-002 5/6/2015 Air sampler not running Replaced air sampler TLD Gamma M-06B 2nd Qtr '15 TLD missing in field Replaced TLD AP/AI Beta, 1-131 M-004 6/10/15 GFCI tripped Reset GFCI AP/AI Beta, 1-131 M-004 6/24/2015 GFCI tripped Reset GFC sw Gamma M-008 12/30/15 Water frozen None v

MNGP 30 DATA TABLES vi

MNGP Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's).

Previous mRem/91 days Cumulative Annual Location 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average Indicators (Inner Ring, General Area of Site Boundary)

M-01A 15.6 +/- 0.8 14.3 +/- 1.2 16.7 +/- 1.5 16.6+/-2.1 15.8 13.7 M-02A 13.4 +/- 1.2 13.8 +/- 0.5 13.9+/-1.2 15.3+/-1.0 14.1 14.2 M-03A 14.8+/-1.3 13.2 +/- 1.0 13.3+/-1.3 16.4+/-1.7 14.4 13.4 M-04A 9.6 +/- 0.9 15.3 +/- 0.7 10.9 +/- 1.5 17.9+/-1.8 13.4 13.5 M-05A 14.2 +/- 0.6 12.2 +/- 0.5 15.2 +/- 0.8 13.2 +/- 1.0 13.7 12.6 M-06A 15.3 +/- 0.5 16.5 +/- 0.5 15.7+/-1.1 18.9+/-1.1 16.6 14.0 M-07A 9.8 +/- 0.6 13.7 +/- 0.5 11.1 +/-0.9 15.3+/-1.0 12.5 11.6 M-08A 12.1 +/- 0.7 15.1 +/-0.5 14.9 +/- 0.9 17.4 +/- 0.9 14.9 13.4 M-09A 14.3 +/- 0.5 12.4 +/- 0.8 13.7 +/- 0.9 16.0 +/- 1.2 14.1 12.4 M-10A 12.9 +/- 1.0 13.7 +/- 0.6 13.9+/-0.9 16.2+/-1.3 14.2 13.4 M-11A 15.8+/-0.8 16.3 +/- 0.9 16.8 +/- 1.1 19.6 +/- 1.4 17.1 14.5 M-12A 14.7 +/- 0.8 15.9 +/- 0.5 15.7 +/- 1.3 19.3+/-1.0 16.4 13.9 M-13A 13.8 +/- 0.9 14.6 +/- 0.9 15.0+/-1.2 16.8 +/- 1.2 15.1 14.5 M-14A 15.2 +/- 0.8 13.4 +/- 0.5 15.4+/-0.8 15.1 +/- 1.1 14.8 13.7 Mean+/- s.d. 13.7 +/- 2.0 14.3+/-1.4 14.4 +/- 1.8 16.7 +/- 1.8 14.8 13.5 Indicators (Outer Ring, 4-5 Miles Distant)

M-018 12.2 +/- 1.2 14.9 +/- 0.9 15.1 +/- 1.0 16.9 +/- 1.5 14.8 12.2 M-028 11.7 +/- 0.7 15.6 +/- 1.0 13.0 +/- 0.9 16.3+/-1.1 14.2 12.8 M-038 11.1 +/-0.8 11.0 +/- 0.6 11.2 +/- 0.9 13.5 +/- 1.2 11.7 11.1 M-048 12.4+/-0.7 12.1 +/-0.4 15.0 +/- 0.9 14.8 +/- 1.0 13.6 11.9 M-058 11.9 +/- 0.5 12.6 +/- 0.6 12.7 +/- 0.9 14.7+/-1.1 13.0 12.4 M-068 13.0+/-1.2 NDa 15.3 +/- 1.2 17.0+/-0.9 15.1 13.3 M-078 14.2 +/- 0.7 13.0+/-0.7 15.9+/-1.2 16.1+/-1.2 14.8 13.7 M-088 12.5 +/- 0.7 13.3 +/- 0.7 14.2 +/- 1.1 15.6 +/- 1.4 13.9 14.2 M-098 12.4+/-0.7 15.1 +/- 1.1 12.7 +/- 1.2 17.8 +/- 1.1 14.5 13.0 M-108 14.4+/-1.0 13.2 +/- 0.8 16.0 +/- 0.9 15.6 +/- 1.4 14.8 13.6 M-118 14.3+/-1.3 13.9 +/- 0.7 15.2 +/- 1.5 15.7+/-1.2 14.8 13.4 M-128 13.7+/-1.0 14.9 +/- 0.6 15.2 +/- 1.9 17.2 +/- 1.1 15.3 14.2 M-138 11.1 +/- 0.7 11.9 +/- 0.5 12.6 +/- 1.2 13.5+/-1.1 12.3 11.8 M-148 14.7+/-1.3 16.7+/-0.6 15.3 +/- 1.6 19.6+/-1.1 16.6 14.4 M-158 12.2 +/- 0.5 12.7 +/- 0.9 13.5+/-1.0 16.3 +/- 1.3 13.7 12.1 M-168 14.3 +/- 0.6 11.7+/-0.8 14.8 +/- 0.8 13.4 +/- 1.2 13.5 12.2 Mean+/- s.d. 12.9 +/- 1.2 13.5 +/- 1.6 14.2+/-1.4 15.9 +/- 1.7 14.2 12.9 a "NO" = No data; see Table 2.0, Listing of Missed Samples.

1-1

MNGP Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's),

(continued).

Previous mRem/91 days Cumulative Annual Location 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-01C 11.8 +/- 1.5 13.2 +/- 0.8 12.5 +/- 1.5 16.0 +/- 1.3 13.4 14.4 M-02C 15.9 +/- 0.8 16.6 +/- 1.4 17.4 +/- 0.9 20.3+/-1.1 17.5 14.1 M-03C 13.2 +/- 0.4 14.8 +/- 0.6 15.2+/-0.9 17.6+/-1.1 15.2 14.3 M-04C 14.7+/-1.7 14.0 +/- 0.5 15.1 +/-1.6 16.6+/-1.0 15.1 14.2 Mean+/- s.d. 13.9 +/- 1.8 14.6+/-1.5 15.1 +/- 2.0 17.6 +/- 1.9 15.3 14.3 Indicators (Special Interest Areas)

M-01S 10.4 +/- 1.0 12.5 +/- 0.5 9.4 +/- 1.4 13.9 +/- 0.9 11.6 10.3 M-02S 13.5 +/- 1.0 13.2 +/- 0.6 14.5 +/- 1.5 15.9+/-1.1 14.3 11.7 M-03S 12.2 +/- 0.7 14.7 +/- 0.7 13.2 +/- 1.1 17.0+/-1.2 14.3 13.0 M-04S 16.6+/-1.1 14.4 +/- 0.8 17.6 +/- 1.2 17.0+/-1.1 16.4 14.6 M-OSS 14.5 +/- 0.6 14.9 +/- 0.8 15.3+/-1.1 17.9+/-1.3 15.6 14.1 M-06S 15.2 +/- 0.7 15.5 +/- 0.5 15.2+/-1.1 18.8 +/- 1.1 16.2 15.6 Mean+/- s.d. 13.7+/-2.2 14.2 +/- 1.1 14.2 +/- 2.8 16.7 +/- 1.7 14.7 13.2 ISFSI TLDs M-1-01 39.4 +/- 1.2 26.7 +/- 2.0 42.8 +/- 2.0 41.7+/-2.4 37.7 36.1 M-1-02 36.4 +/- 1.2 24.3 +/- 0.6 38.1 +/- 1.2 36.9 +/- 1.1 33.9 29.8 M-1-03 29.6 +/- 1.0 23.2 +/- 1.1 32.4 +/- 1.3 31.9 +/- 1.3 29.3 25.6 M-1-04 36.7 +/- 2.6 34.4 +/- 2.4 29.2 +/- 2.6 37.7 +/- 2.7 34.5 35.6 M-1-05 80.3 +/- 5.0 67.3 +/- 3.1 68.3 +/- 4.6 79.5+/-2.1 73.9 65.9 M-1-06 30.3 +/- 2.4 21.6 +/- 0.8 30.0 +/- 2.2 25.4 +/- 1.3 26.8 25.0 M-1-07 30.3+/-1.4 27.5 +/- 1.7 31.1 +/-2.7 32.8 +/- 1.6 30.4 27.7 M-l-08 28.9 +/- 2.9 24.1+/-0.5 29.6 +/- 3.0 28.7 +/- 2.7 27.9 26.6 M-1-09 234.8 +/- 12.1 220.1 +/- 3.7 70.5 +/-4.1 61.3+/-2.7 146.6 170.5 M-1-10 43.3 +/- 1.7 28.6 +/- 1.3 41.6+/-1.2 35.3 +/- 1.6 37.2 33.2 M-1-11 12.4+/-1.7 15.1 +/- 0.5 13.1 +/- 1.7 16.7+/-1.2 14.3 13.9 M-1-12 14.1+/-0.7 14.3 +/- 0.6 15.2 +/- 0.9 15.4 +/- 1.3 14.7 13.9 M-1-13 17.1 +/- 1.3 12.8 +/- 0.8 15.6 +/- 2.0 16.6 +/- 1.6 15.5 13.5 Mean+/- s.d. 48.7 +/- 58.4 41.5 +/- 55.4 35.2 +/- 17.9 35.4 +/- 18.1 40.2 39.8 1-2

MNGP 3

Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

  • Location: M-1 (C) 3 Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m;;) Gross Beta Collected (mJ) Gross Beta Required LLD 0.010 Required LLD 0.010 01-07-15 319 0.041 +/- 0.004 07-08-15 443 0.022 +/- 0.003 01-14-15 321 0.042 +/- 0.004 07-15-15 443 0.024 +/- 0.003 01-21-15 323 0.036 +/- 0.004 07-22-15 441 0.018 +/- 0.002 01-28-15 315 0.021 +/- 0.003 07-29-15 439 0.026 +/- 0.003 02-04-15 357 0.029 +/- 0.003 08-05-15 440 0.019 +/- 0.003 02-11-15 389 0.033 +/- 0.003 08-12-15 305 0.027 +/- 0.004 02-18-15 354 0.044 +/- 0.004 08-19-15 353 0.031 +/- 0.004 02-25-15 354 0.062 +/- 0.004 08-26-15 337 0.022 +/- 0.003 09-02-15 353 0.038 +/- 0.004 03-04-15 352 0.036 +/- 0.004 03-11-15 353 0.025 +/- 0.004 09-09-15 352 0.028 +/- 0.003 03-18-15 392 0.019 +/- 0.003 09-16-15 302 0.033 +/- 0.004 03-25-15 352 0.024 +/- 0.003 09-23-15 352 0.025 +/- 0.003 04-01-15 354 0.018 +/- 0.003 09-30-15 326 0.039 +/- 0.004 1st Quarter Mean+/- s.d. 0.033 +/- 0.012 3rd Quarter Mean +/- s.d. 0.027 +/- 0.007 04-08-15 357 0.023 +/- 0.003 10-07-15 325 0.023 +/- 0.003 04-15-15 351 0.021 +/- 0.003 10-14-15 324 0.031 +/- 0.004 04-22-15 355 0.014 +/- 0.003 10-21-15 301 0.035 +/- 0.004 04-29-15 355 0.021 +/- 0.003 10-28-15 336 0.022 +/- 0.003 05-06-15 443 0.021 +/- 0.003 11-04-15 397 0.025 +/- 0.003 05-13-15 440 0.008 +/- 0.002 11-11-15 351 0.039 +/- 0.004 05-20-15 447 0.010 +/- 0.002 11-18-15 353 0.033 +/- 0.004 05-27-15 435 0.018 +/- 0.003 11-25-15 387 0.022 +/- 0.003 06-03-15 442 0.018 +/- 0.002 12-02-15 382 0.044 +/- 0.004 06-10-15 441 0.016 +/- 0.002 12-09-15 350 0.061 +/- 0.005 06-17-15 441 0.013 +/- 0.002 12-16-15 353 0.016 +/- 0.003 06-24-15 351 0.021 +/- 0.003 12-23-15 354 0.044 +/- 0.004 07-01-15 441 0.019 +/- 0.003 12-30-15 384 0.040 +/- 0.004 2nd Quarter Mean +/- s.d. 0.017 +/- 0.005 4th Quarter Mean +/- s.d. 0.034 +/- 0.012 Cumulative Average 0.028 Previous Annual Average 0.032 3

a lodine-131 concentrations are< 0.03 pCi/m unless otherwise noted.

2-1

MNGP Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-2 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Reguired LLD 0.010 0.010 01-07-15 352 0.038 +/- 0.004 07-08-15 341 0.025 +/- 0.003 01-14-15 326 0.038 +/- 0.004 07-15-15 341 0.023 +/- 0.003 01-21-15 329 0.031 +/- 0.003 07-22-15 325 0.019 +/- 0.003 01-28-15 321 0.021 +/- 0.003 07-29-15 350 0.024 +/- 0.003 02-04-15 NDb 08-05-15 353 0.017 +/- 0.003 02-11-15 322 0.040 +/- 0.004 08-12-15 330 0.025 +/- 0.003 02-18-15 325 0.048 +/- 0.004 08-19-15 342 0.031 +/- 0.004 02-25-15 326 0.073 +/- 0.005 08-26-15 326 0.025 +/- 0.003 09-02-15 342 0.038 +/- 0.004 03-04-15 324 0.035 +/- 0.004 03-11-15 351 0.027 +/- 0.004 09-09-15 348 0.027 +/- 0.003 03-18-15 328 0.025 +/- 0.004 09-16-15 318 0.033 +/- 0.004 03-25-15 323 0.027 +/- 0.004 09-23-15 337 0.024 +/- 0.003 04-01-15 352 0.019 +/- 0.003 09-30-15 318 0.037 +/- 0.004 1st Quarter Mean+/- s.d. 0.035 +/- 0.015 3rd Quarter Mean+/- s.d. 0.027 +/- 0.006 04-08-15 330 0.023 +/- 0.003 10-07-15 314 0.023 +/- 0.003 04-15-15 349 0.027 +/- 0.003 10-14-15 315 0.027 +/- 0.004 04-22-15 325 0.017 +/- 0.003 10-21-15 314 0.029 +/- 0.004 04-29-15 329 0.021 +/- 0.003 10-28-15 263 0.028 +/- 0.004 05-06-15 NDb 11-04-15 353 0.027 +/- 0.003 05-13-15 351 0.010 +/- 0.002 11-11-15 352 0.045 +/- 0.004 05-20-15 358 0.011 +/- 0.002 11-18-15 326 0.037 +/- 0.004 05-27-15 347 0.019 +/- 0.003 11-25-15 327 0.025 +/- 0.004 06-03-15 351 0.019 +/- 0.003 12-02-15 327 0.051 +/- 0.005 06-10-15 353 0.019 +/- 0.003 12-09-15 328 0.066 +/- 0.005 06-17-15 352 0.014 +/- 0.003 12-16-15 326 0.021 +/- 0.003 06-24-15 354 0.018 +/- 0.003 12-23-15 304 0.051 +/- 0.005 07-01-15 340 0.020 +/- 0.003 12-30-15 324 0.050 +/- 0.005 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.037 +/- 0.014 Cumulative Average 0.029 Previous Annual Average 0.028 3

a lodine-131 concentrations are < 0.03 pCi/m unless otherwise noted.

b "NO" = No data, see Table 2.0, Listing of Missed Samples.

3-1

MNGP Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-3 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Required LLD 0.010 0.010 01-07-15 326 0.041 +/- 0.004 07-08-15 409 0.019 +/- 0.003 01-14-15 353 0.042 +/- 0.004 07-15-15 409 0.019 +/- 0.003 01-21-15 357 0.034 +/- 0.003 07-22-15 380 0.021 +/- 0.003 01-28-15 348 0.020 +/- 0.003 07-29-15 324 0.030 +/- 0.004 02-04-15 357 0.029 +/- 0.003 08-05-15 407 0.021 +/- 0.003 02-11-15 351 0.057 +/- 0.004 08-12-15 369 0.027 +/- 0.003 02-18-15 353 0.048 +/- 0.004 08-19-15 342 0.033 +/- 0.004 02-25-15 353 0.066 +/- 0.004 08-26-15 339 0.022 +/- 0.003 09-02-15 342 0.044 +/- 0.004 03-04-15 378 0.035 +/- 0.004 03-11-15 379 0.024 +/- 0.003 09-09-15 342 0.028 +/- 0.003 03-18-15 383 0.022 +/- 0.003 09-16-15 344 0.031 +/- 0.004 03-25-15 350 0.028 +/- 0.004 09-23-15 337 0.025 +/- 0.003 04-01-15 352 0.020 +/- 0.003 09-30-15 346 0.037 +/- 0.004 1st Quarter Mean+/- s.d. 0.036 +/- 0.015 3rd Quarter Mean +/- s.d. 0.027 +/- 0.007 04-08-15 358 0.023 +/- 0.003 10-07-15 340 0.025 +/- 0.003 04-15-15 349 0.024 +/- 0.003 10-14-15 315 0.035 +/- 0.004 04-22-15 352 0.015 +/- 0.003 10-21-15 314 0.031 +/- 0.004 04-29-15 357 0.020 +/- 0.003 10-28-15 316 0.028 +/- 0.004 05-06-15 350 0.025 +/- 0.003 11-04-15 329 D.030 +/- 0.004 05-13-15 380 0.007 +/- 0.002 11-11-15 329 0.047 +/- 0.004 05-20-15 385 0.012 +/- 0.002 11-18-15 304 0.041 +/- 0.004 05-27-15 400 0.018 +/- 0.003 11-25-15 328 0.025 +/- 0.004 06-03-15 378 0.017 +/- 0.003 12-02-15 328 0.053 +/- 0.005 06-10-15 380 0.019 +/- 0.003 12-09-15 306 0.082 +/- 0.006 06-17-15 352 0.013 +/- 0.003 12-16-15 331 0.019 +/- 0.003 06-24-15 382 0.018 +/- 0.003 12-23-15 387 0.041 +/-0.004 07-01-15 340 0.021 +/- 0.003 12-30-15 301 0.057 +/- 0.005 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.040 +/- 0.017 Cumulative Average 0.030 Previous Annual Average 0.027 a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted.

4-1

MNGP Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-4 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m3) Gross Beta Collected (m3) Gross Beta Required LLD 0.010 0.010 01-07-15 352 0.035 +/- 0.003 07-08-15 409 0.021 +/- 0.003 01-14-15 353 0.040 +/- 0.004 07-15-15 406 0.024 +/- 0.003 01-21-15 356 0.033 +/- 0.003 07-22-15 383 0.018 +/- 0.003 01-28-15 347 0.021 +/- 0.003 07-29-15 405 0.027 +/- 0.003 02-04-15 355 0.034 +/- 0.003 08-05-15 407 0.018 +/- 0.003 02-11-15 350 0.042 +/- 0.004 08-12-15 329 0.027 +/- 0.003 02-18-15 326 0.047 +/- 0.004 08-19-15 328 0.039 +/- 0.004 02-25-15 327 0.070 +/- 0.005 08-26-15 326 0.024 +/- 0.003 09-02-15 352 0.044 +/- 0.004 03-04-15 350 0.039 +/- 0.004 03-11-15 350 0.023 +/- 0.003 09-09-15 351 0.030 +/- 0.003 03-18-15 330 0.028 +/- 0.004 09-16-15 331 0.037 +/- 0.004 03-25-15 324 0.029 +/- 0.004 09-23-15 350 0.027 +/- 0.003 04-01-15 326 0.021 +/- 0.003 09-30-15 329 0.044 +/- 0.004 1st Quarter Mean+/- s.d. 0.036 +/- 0.013 3rd Quarter Mean +/- s.d. 0.029 +/- 0.009 04-08-15 331 0.024 +/- 0.003 10-07-15 327 0.026 +/- 0.003 04-15-15 323 0.025 +/- 0.003 10-14-15 327 0.040 +/- 0.004 04-22-15 327 0.014 +/- 0.003 10-21-15 327 0.033 +/- 0.004 04-29-15 329 0.023 +/- 0.003 10-28-15 329 0.031 +/- 0.004 05-06-15 407 0.023 +/- 0.003 11-04-15 356 0.032 +/- 0.004 05-13-15 405 0.009 +/- 0.002 11-11-15 350 0.038 +/- 0.004 05-20-15 413 0.011 +/- 0.002 11-18-15 352 0.039 +/- 0.004 05-27-15 401 0.019 +/- 0.003 11-25-15 352 0.024 +/- 0.003 06-03-15 407 0.018 +/- 0.003 12-02-15 352 0.050 +/- 0.004 06-10-15 391 0.017 +/- 0.003 12-09-15 352 0.068 +/- 0.005 06-17-15 404 0.014 +/- 0.002 12-16-15 351 0.022 +/- 0.003 06-24-15 NOb 12-23-15 328 0.051 +/- 0.005 07-01-15 397 0.019 +/- 0.003 12-30-15 350 0.054 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.039 +/- 0.013 Cumulative Average 0.031 Previous Annual Average 0.028 3

a lodine-131 concentrations are < 0.03 pCi/m unless otherwise noted.

b "NO" No data; see Table 2.0, Listing of Missed Samples.

5-1

MNGP Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 a.

Location: M-5 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Volume Date Volume Collected (m") Gross Beta Collected (m") Gross Beta Required LLD 0.010 0.010 01-07-15 323 0.046 +/- 0.004 07-08-15 370 0.023 +/- 0.003 01-14-15 324 0.042 +/- 0.004 07-15-15 370 0.021 +/- 0.003 01-21-15 323 0.038 +/- 0.004 07-22-15 352 0.019 +/- 0.003 01-28-15 NOb 07-29-15 351 0.027 +/- 0.003 02-04-15 356 0.031 +/- 0.003 08-05-15 382 0.021 +/- 0.003 02-11-15 352 0.038 +/- 0.004 08-12-15 341 0.024 +/- 0.003 02-18-15 294 0.054 +/- 0.005 08-19-15 352 0.032 +/- 0.004 02-25-15 324 0.071 +/- 0.005 08-26-15 324 0.022 +/- 0.003 09-02-15 326 0.047 +/- 0.004 03-04-15 351 0.034 +/- 0.004 03-11-15 352 0.023 +/- 0.003 09-09-15 271 0.037 +/- 0.004 03-18-15 326 0.024 +/- 0.004 09-16-15 301 0.035 +/- 0.004 03-25-15 292 0.030 +/- 0.004 09-23-15 325 0.028 +/- 0.004 04-01-15 352 0.018 +/- 0.003 09-30-15 298 0.045 +/- 0.005 1st Quarter Mean+/- s.d. 0.038 +/- 0.015 3rd Quarter Mean +/- s.d. 0.029 +/- 0.009 04-08-15 298 0.024 +/- 0.004 10-07-15 298 0.025 +/- 0.004 04-15-15 291 0.027 +/- 0.004 10-14-15 298 0.039 +/- 0.004 04-22-15 324 0.016 +/- 0.003 10-21-15 297 0.036 +/- 0.004 04-29-15 326 0.022 +/- 0.003 10-28-15 326 0.025 +/- 0.004 05-06-15 384 0.022 +/- 0.003 11-04-15 359 0.029 +/- 0.003 05-13-15 381 0.009 +/- 0.002 11-11-15 367 0.043 +/- 0.004 05-20-15 387 0.011 +/- 0.002 11-18-15 252 0.032 +/- 0.005 05-27-15 378 0.016 +/- 0.003 11-25-15 354 0.025 +/- 0.003 06-03-15 382 0.019 +/- 0.003 12-02-15 323 0.050 +/- 0.005 06-10-15 382 0.017 +/- 0.003 12-09-15 323 0.088 +/- 0.006 06-17-15 380 0.012 +/- 0.002 12-16-15 353 0.015 +/- 0.003 06-24-15 353 0.020 +/- 0.003 12-23-15 295 0.048 +/- 0.005 07-01-15 368 0.019 +/- 0.003 12-30-15 352 0.050 +/- 0.004 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 4th Quarter Mean +/- s.d. 0.039 +/- 0.018 Cumulative Average 0.031 Previous Annual Average 0.031 3

a lodine-131 concentrations are< 0.03 pCi/m unless otherwise noted.

b "NO"= No data, see Table 2.0, Listing of Missed Samples.

6-1

MNGP Table 7. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

January April Location Average Minima Maxima Location Average Minima Maxima Control 0.035 0.021 0.042 Control 0.020 0.014 0.023 M-1 0.035 0.021 0.042 M-1 0.020 0.014 0.023 Indicators 0.035 0.020 0.046 Indicators 0.022 0.014 0.027 M-2 0.032 0.021 0.038 M-2 0.022 0.017 0.027 M-3 0.034 0.020 0.042 M-3 0.020 0.015 0.024 M-4 0.032 0.021 0.040 M-4 0.022 0.014 0.025 M-5 0.042 0.038 0.046 M-5 0.022 0.016 0.027 February May Location Average Minima Maxima Location Average Minima Maxima Control 0.042 0.029 0.062 Control 0.015 0.008 0.021 M-1 0.042 0.029 0.062 M-1 0.015 0.008 0.021 Indicators 0.050 0.029 0.073 Indicators 0.015 0.007 0.025 M-2 0.054 0.040 0.073 M-2 0.015 0.010 0.019 M-3 0.050 0.029 0.066 M-3 0.016 0.007 0.025 M-4 0.048 0.034 0.070 M-4 0.016 0.009 0.023 M-5 0.049 0.031 0.071 M-5 0.016 0.009 0.022 March June Location Average Minima Maxima Location Average Minima Maxima Control 0.024 0.018 0.036 Control 0.017 0.013 0.021 M-1 0.024 0.018 0.036 M-1 0.017 0.013 0.021 Indicators 0.027 0.018 0.039 Indicators 0.017 0.012 0.021 M-2 0.027 0.019 0.035 M-2 0.018 0.014 0.020 M-3 0.026 0.020 0.035 M-3 . 0.018 0.013 0.021 M-4 0.028 0.021 0.039 M-4 0.017 0.014 0.019 M-5 0.026 0.018 0.034 M-5 0.017 0.012 0.020 Note: unless otherwise specified, samples collected on the first, second or third day of the month are grouped with data of the previous month.

7-1

MNGP Table 7. Airborne particulate data, gross beta analyses, monthly averages, minima and maxima.

July October Location Average Minima Maxima Location Average Minima Maxima Control 0.023 0.018 0.026 Control 0.028 0.022 0.035 M-1 0.023 0.018 0.026 M-1 0.028 0.022 0.035 Indicators 0.022 0.018 0.030 Indicators 0.030 0.023 0.040 M-2 0.023 0.019 0.025 M-2 0.027 0.023 0.029 M-3 0.022 0.019 0.030 M-3 0.030 0.025 0.035 M-4 0.022 0.018 0.027 M-4 0.032 0.026 0.040 M-5 0.022 0.019 0.026 M-5 0.031 0.025 0.039 August November Location Average Minima Maxima Location Average Minima Maxima Control Control 0.033 0.022 0.044 M-1 0.027 0.019 0.038 M-1 0.033 0.022 0.044 Indicators 0.029 0.017 0.047 Indicators 0.037 0.024 0.053 M-2 0.027 0.017 0.038 M-2 0.037 0.025 0.051 M-3 0.029 0.021 0.044 M-3 0.039 0.025 0.053 M-4 0.031 0.018 0.044 M-4 0.037 0.024 0.050 M-5 0.029 0.021 0.047 M-5 0.036 0.025 0.050 September December Location Average Minima Maxima Location Average Minima Maxima Control Control 0.040 0.016 0.061 M-1 0.031 0.025 0.039 M-1 0.040 0.016 0.061 Indicators 0.033 0.024 0.045 Indicators 0.049 0.015 0.088 M-2 0.030 0.024 0.037 M-2 0.048 0.021 0.066 M-3 0.030 0.025 0.037 M-3 0.050 0.019 0.082 M-4 0.034 0.027 0.044 M-4 0.048 0.022 0.068 M-5 0.036 0.028 0.045 M-5 0.050 0.015 0.088 Note: unless otherwise specified, samples collected on the first, second or third day of the month are grouped with data of the previous month.

7-2

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCi/m )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-1 (C)

Lab Code MAP- 1842 MAP- 3819 MAP- 6030 MAP- 7410 3

Volume(m ) 4534 5299 4884 4597 Be-7 0.065 +/- 0.013 0.077 +/- 0.010 0.077 +/- 0.012 0.043 +/- 0.010 0.066 0.068 Mn-54 < 0.0005 < 0.0004 < 0.0005 < 0.0003 <0.0005 <0.0008 Co-58 < 0.0007 < 0.0004 < 0.0005 < 0.0004 <0.0007 <0.0010 Co-60 < 0.0009 < 0.0004 < 0.0005 < 0.0002 <0.0009 <0.0006 Zn-65 < 0.0011 < 0.0005 < 0.0012 < 0.0010 <0.0012 <0.0011 Zr-Nb-95 < 0.0007 < 0.0006 < 0.0008 < 0.0008 <0.0008 <0.0015 Ru-1 03 < 0.0008 < 0.0008 < 0.0008 < 0.0005 <0.0008 <0.0008 Ru-1 06 < 0.0049 < 0.0027 < 0.0036 < 0.0043 <0.0049 <0.0063 Cs-134 < 0.0006 < 0.0006 < 0.0005 < 0.0006 <0.0006 <0.0011 Cs-137 < 0.0006 < 0.0005 < 0.0006 < 0.0004 <0.0006 <0.0007 Ba-La-140 < 0.0017 < 0.0017 < 0.0015 < 0.0014 <0.0017 <0.0021 Ce-141 < 0.0010 < 0.0008 < 0.0015 < 0.0010 <0.0015 <0.0016 Ce-144 < 0.0033 < 0.0034 < 0.0028 < 0.0022 <0.0034 <0.0046 M-2 Lab Code MAP- 1843 MAP- 3820 MAP- 6031 MAP- 7411 3

Volume(m ) 4338 4138 4370 4173 Be-7 0.070 +/- 0.011 0.079 +/- 0.013 0.072 +/- 0.013 0.051 +/- 0.012 0.068 0.064 Mn-54 < 0.0006 < 0.0008 < 0.0008 < 0.0011 <0.0008 <0.0008 Co-58 < 0.0004 < 0.0005 < 0.0008 < 0.0006 <0.0008 <0.0010 Co-60 < 0.0004 < 0.0005 < 0.0007 < 0.0004 <0.0007 <0.0008 Zn-65 < 0.0017 < 0.0007 < 0.0008 < 0.0014 <0.0017 <0.0015 Zr-Nb-95 < 0.0009 < 0.0011 < 0.0007 < 0.0010 <0.0011 <0.0010 Ru-1 03 < 0.0007 < 0.0006 < 0.0012 < 0.0010 <0.0012 <0.0014 Ru-1 06 < 0.0061 < 0.0085 < 0.0074 < 0.0046 <0.0085 <0.0077 Cs-134 < 0.0007 < 0.0009 < 0.0008 < 0.0008 <0.0009 <0.0010 Cs-137 < 0.0006 < 0.0006 < 0.0010 < 0.0005 <0.0010 <0.0008 Ba-La-140 < 0.0015 < 0.0019 < 0.0024 < 0.0021 <0.0024 <0.0042 Ce-141 < 0.0017 < 0.0010 < 0.0018 < 0.0011 <0.0018 <0.0015 Ce-144 < 0.0033 < 0.0026 < 0.0046 < 0.0048 <0.0046 <0.0040 8-1

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCilm )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-3 Lab Code MAP- 1844 MAP- 3821 MAP- 6032 MAP- 7412 3

Volume(m ) 4636 4761 4689 4227 Be-7 0.064 +/- 0.016 0.077 +/- 0.013 0.075 +/- 0.011 0.052 +/- 0.012 0.067 0.065 Mn-54 < 0.0007 < 0.0005 < 0.0004 < 0.0008 <0.0007 <0.0009 Co-58 < 0.0006 < 0.0004 < 0.0004 < 0.0009 <0.0006 <0.0008 Co-60 < 0.0006 < 0.0003 < 0.0005 < 0.0006 <0.0006 <0.0007 Zn-65 < 0.0006 < 0.0006 < 0.0014 < 0.(}01 0 <0.0014 <0.0009 Zr-Nb-95 < 0.0007 < 0.0008 < 0.0010 < 0.0007 <0.001 0 <0.0008 Ru-103 < 0.0004 < 0.0006 < 0.0009 < 0.0009 <0.0009 <0.0011 Ru-1 06 < 0.0061 < 0.0061 < 0.0041 < 0.0082 <0.0061 <0.0068 Cs-134 < 0.0007 < 0.0006 < 0.0006 < 0.0009 <0.0007 <0.0009 Cs-137 < 0.0006 < 0.0004 < 0.0004 < 0.0007 <0.0006 <0.0006 Ba-La-140 < 0.0018 < 0.0012 < 0.0013 < 0.0043 <0.0018 <0.0016 Ce-141 < 0.0010 < 0.0011 < 0.0013 < 0.0018 <0.0013 <0.0018 Ce-144 < 0.0022 < 0.0035 < 0.0025 < 0.0035 <0.0035 <0.0055 M-4 Lab Code MAP- 1845 MAP- 3822 MAP- 6033 MAP- 7413 3

Volume(m ) 4447 4534 4703 4452 Be-7 0.062 +/- 0.013 0.075 +/- 0.011 0.086 +/- 0.011 0.058 +/- 0.012 0.070 0.058 Mn-54 < 0.0007 < 0.0008 < 0.0005 < 0.0006 <0.0008 <0.0008 Co-58 < 0.0008 < 0.0007 < 0.0005 < 0.0005 <0.0008 <0.0011 Co-60 < 0.0006 < 0.0008 < 0.0004 < 0.0005 <0.0008 <0.0008 Zn-65 < 0.0019 < 0.0019 < 0.0005 < 0.0013 <0.0019 <0.0009 Zr-Nb-95 < 0.0014 < 0.0011 < 0.0008 < 0.0012 <0.0014 <0.0010 Ru-1 03 < 0.0013 < 0.0007 < 0.0008 < 0.0008 <0.0013 <0.0009 Ru-106 < 0.0062 < 0.0073 < 0.0026 < 0.0062 <0.0073 <0.0060 Cs-134 < 0.0010 < 0.0007 < 0.0006 < 0.0007 <0.001 0 <0.0008 Cs-137 < 0.0010 < 0.0005 < 0.0005 < 0.0006 <0.001 0 <0.0010 Ba-La-140 < 0.0017 < 0.0026 < 0.0010 < 0.0015 <0.0026 <0.0030 Ce-141 < 0.0013 < 0.0012 < 0.0009 < 0.0015 <0.0013 <0.0017 Ce-144 < 0.0040 < 0.0034 < 0.0019 < 0.0046 <0.0040 <0.0035 8-2

MNGP Table 8. Airborne particulates, quarterly composites from each location, analysis for gamma-emitting isotopes.

3 Activity (pCi/m )

Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-5 Lab Code MAP- 1846 MAP- 3824 MAP- 6034 MAP- 7414 3

Volume(m ) 3969 4632 4363 4197 Be-7 0.086 +/- 0.014 0.070 +/- 0.011 0.087 +/- 0.012 0.049 +/- 0.013 0.073 0.072 Mn-54 < 0.0005 < 0.0005 < 0.0008 < 0.0006 <0.0008 <0.0009 Co-58 < 0.0007 < 0.0002 < 0.0006 < 0.0004 <0.0007 <0.0006 Co-60 < 0.0004 < 0.0005 < 0.0005 < 0.0006 <0.0005 <0.0006 Zn-65 < 0.0009 < 0.0007 < 0.0007 < 0.0008 <0.0009 <0.0008 Zr-Nb-95 < 0.0014 < 0.0006 < 0.0007 < 0.0013 <0.0014 <0.0011 Ru-1 03 < 0.0012 < 0.0006 < 0.0009 < 0.0008 <0.0012 <0.0011 Ru-106 < 0.0040 < 0.0042 < 0.0072 < 0.0062 <0.0072 <0.0065 Cs-134 < 0.0009 < 0.0006 < 0.0007 < 0.0008 <0.0009 <0.0008 Cs-137 < 0.0006 < 0.0004 < 0.0007 < 0.0007 <0.0007 <0.0007 Ba-La-140 < 0.0016 < 0.0010 < 0.0023 < 0.0015 <0.0023 <0.0019 Ce-141 < 0.0020 < 0.0013 < 0.0015 < 0.0014 <0.0020 <0.0023 Ce-144 < 0.0038 < 0.0031 < 0.0041 < 0.0026 <0.0041 <0.0047 8-3

MNGP Table 9. Pasture grass, vegetation, analysis for gamma-emitting isotopes.

Collection: 3x per year Previous Sample Description and Concentration (pCi/g wet) Annual Annual Average Average Location: M-41 (Training Center)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3772 MVE- 4464 MVE- 4966 Mn-54 < 0.009 < 0.007 < 0.006 < 0.009 < 0.010 Fe-59 < 0.024 < 0.020 < 0.020 < 0.024 < 0.031 Co-58 < 0.008 < 0.010 < 0.014 < 0.014 < 0.009 Co-60 < 0.010 < 0.008 < 0.006 <0.010 < 0.009 Zn-65 < 0.024 < 0.017 < 0.016 < 0.024 < 0.024 Nb-95 < 0.007 < 0.005 < 0.006 < 0.007 < 0.011 1-131 < 0.026 < 0.021 < 0.025 < 0.026 < 0.038 Cs-134 < 0.013 < 0.010 < 0.010 < 0.013 < 0.011 Cs-137 < 0.009 < 0.014 < 0.010 < 0.014 < 0.011 Location: M-42 (Biology Station Road)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3773 MVE- 4465 MVE- 4967 Mn-54 < 0.009 < 0.014 < 0.009 < 0.014 < 0.008 Fe-59 < 0.017 < 0.026 < 0.023 < 0.026 < 0.022 Co-58 < 0.009 < 0.011 < 0.011 < 0.011 < 0.008 Co-60 < 0.006 < 0.007 < 0.007 < 0.007 < 0.008 Zn-65 < 0.022 < 0.018 < 0.020 < 0.022 < 0.024 Nb-95 < 0.009 < 0.012 < 0.009 < 0.012 < 0.012 1-131 < 0.029 < 0.027 < 0.041 <0.041 < 0.030 Cs-134 < 0.011 < 0.012 < 0.011 < 0.012 < 0.011 Cs-137 < 0.012 < 0.013 < 0.013 <0.013 <0.010 Location: M-43 (lmholte Farm, Control)

Date Collected 07-15-15 08-12-15 09-09-15 Lab Code MVE- 3894 MVE- 4466 MVE- 4968 Mn-54 < 0.012 < 0.009 < 0.009 <0.012 < 0.012 Fe-59 < 0.021 < 0.033 < 0.027 < 0.033 < 0.030 Co-58 < 0.008 < 0.012 < 0.006 < 0.012 < 0.013 Co-60 < 0.019 < 0.007 < 0.010 < 0.019 < 0.014 Zn-65 < 0.029 < 0.014 < 0.016 < 0.029 < 0.029 Nb-95 < 0.020 < 0.013 < 0.010 < 0.020 <0.015 1-131 < 0.032 < 0.029 < 0.043 < 0.043 < 0.037 Cs-134 < 0.015 < 0.014 < 0.012 < 0.015 < 0.014 Cs-137 < 0.013 < 0.010 < 0.013 < 0.013 < 0.013 9-1

MNGP Table 10. River water, analysis of monthly composites for gamma-emitting isotopes.

Location: M-8 (C)

Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code NSa NSa MSW-1766 MSW-2440 MSW-2952 Mn-54 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 Co-58 < 10 <10 < 10 Co-60 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 Cs-134 < 10 <10 < 10 Cs-137 < 10 <10 < 10 Ba-La-140 < 15 < 15 < 15 Ce-144 < 10 <10 < 24 Period Collected June July August September October Lab Code MSW-3660 MSW-4496 MSW-5158 MSW-5669 MSW-6328 Mn-54 < 10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 < 10 <10 < 10 <10 < 10 Co-60 < 10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 <10 < 10 Cs-137 < 10 < 10 < 10 <10 < 10 Ba-La-140 < 15 < 15 < 15 <15 < 15 Ce-144 < 22 < 22 < 12 < 39 < 23 Previous b

Period Collected November December Cumulative Annual Lab Code MSW-6947 MSW-7322 Average Average Mn-54 < 10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 < 10 Co-60 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 Ce-144 < 25 < 17 < 39 < 30 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

b Water frozen 12-30-15.

10-1

MNGP Table 10. River water, analysis of monthly composites for gamma-emitting isotopes.

Location: M-9 Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code MSW-326 MSW-1130 MSW-1767 MSW-2441 MSW-2953 Mn-54 <10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 <10 < 10 Co-60 <10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 < 10 <10 < 10 Cs-137 < 10 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 < 15 Ce-144 < 12 < 20 < 11 < 11 < 19 Period Collected June July August September October Lab Code MSW-3661 MSW-4497 MSW-5159 MSW-5670 MSW-6329 Mn-54 <10 < 10 < 10 <10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 < 10 < 10 <10 < 10 Co-60 <10 < 10 < 10 <10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 <15 < 15 Cs-134 < 10 < 10 < 10 < 10 < 10 Cs-137 < 10 < 10 < 10 < 10 < 10 Ba-La-140 < 15 < 15 < 15 < 15 < 15 Ce-144 <23 < 29 < 15 < 30 < 25 Previous Period Collected November December Cumulative Annual Lab Code MSW-6948 MSW-7323 Average Average Mn-54 < 10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 < 10 < 10 < 10 Co-60 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 <10 < 10 < 10 < 10 Cs-137 <10 < 10 < 10 < 10 Ba-La-140 <15 < 15 < 15 < 15 Ce-144 < 24 < 33 < 33 < 33 10-2

MNGP Table 11. Drinking water, City of Minneapolis, M-14, analysis of monthly composites for gross beta, iodine-131, and gamma-emitting isotopes.

Collection: Weekly Sample Description and Concentration (pCi/L)

Period Collected January February March April May Lab Code MDW-523 MDW-871 MDW-1502 MDW-2354 MDW-2777 Gross beta 3.2 +/- 1.1 3.3 +/- 1.0 2.5 +/- 0.9 2.3 +/- 0.8 3.5 +/- 0.7 1-131 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 < 10 < 10 < 10 < 10 <10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 <10 < 10 < 10 <10 Co-60 <10 <10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 <15 < 15 < 15 < 15 < 15 Cs-134 < 10 < 10 <10 <10 <10 Cs-137 < 10 <10 < 10 <10 < 10 Ba-La-140 <15 <15 < 15 < 15 < 15 Ce-144 <16 < 29 <9 < 11 < 24 Period Collected June July August September October Lab Code MDW-3662 MDW-4346 MDW-5010 MDW-5678 MDW-6447 Gross beta 1.5 +/- 0.6 1.2 +/- 0.5 1.4 +/- 0.6 1.3+/-0.6 3.2 +/- 1.0 1-131 < 1.0 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 <10 <10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 < 30 Co-58 <10 <10 < 10 < 10 <10 Co-60 < 10 < 10 < 10 < 10 < 10 Zn-65 < 30 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 <15 < 15 < 15 < 15 Cs-134 <10 <10 < 10 < 10 <10 Cs-137 <10 <10 < 10 < 10 <10 Ba-La-140 < 15 <15 < 15 < 15 < 15 Ce-144 < 29 < 23 < 27 < 35 < 14 Period Collected November December Cumulative Previous Lab Code MDW-6946 MDW-7269 Average Average Gross beta 2.2 +/- 0.6 1.4 +/- 0.9 2.3 2.8 1-131 < 1.0 < 1.0 < 1.0 < 1.0 Mn-54 <10 < 10 < 10 < 10 Fe-59 < 30 < 30 < 30 < 30 Co-58 < 10 <10 < 10 <10 Co-60 < 10 <10 <10 <10 Zn-65 < 30 < 30 < 30 < 30 Zr-Nb-95 < 15 < 15 < 15 < 15 Cs-134 <10 < 10 < 10 < 10 Cs-137 < 10 <10 < 10 <10 Ba-La-140 < 15 <15 < 15 <15 Ce-144 < 26 <16 < 35 < 46 11-1

MNGP Table 12. River water and drinking water, analysis of quarterly composites for tritium.

Collection: Quarterly composites of weekly collections.

Sample Type, Location and Concentration (pCi/L)

Collection Period Lab Code H-3 River Water Upstream, M-8 (C) Required LLD 1st Quartera MSW -1770 < 500 < 152 2nd Quarter MSW- 3663 < 500 < 154 3rd Quarter MSW- 5675 < 500 < 152 4th Quarterb MSW -7326 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 165 River Water Downstream, M-9 1st Quarter MSW -1771 < 500 < 152 2nd Quarter MSW- 3664 < 500 < 154 3rd Quarter MSW- 5676 < 500 < 152 4th Quarter MSW -7327 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 157 Drinking Water Minneapolis, M-14 1st Quarter MOW -1768 < 500 < 152 2nd Quarter MOW- 3665 < 500 < 154 3rd Quarter MOW- 5677 < 500 < 152 4th Quarter MOW -7339 < 500 < 146 Cumulative Average < 500 < 151 Previous Annual Average < 500 < 157 a Composite of two samples for quarter- 03-18 and 03-25-15. Water frozen remainder of quarter.

bWater frozen 12-30-15.

12-1

MNGP Table 13. Well water, analysis for tritium and gamma-emitting isotopes.

Sample Description and Concentration (pCi/L) lO a> ('-.

Date H-3 a> Q) 0 lO '

.0 C0 lO lO

<D (l) z '

<h c'

~

0 0 U)

Collected Lab Code (< 500 pCi/L) l1.. 0 0 N 0 Monticello (M-11) 1/21/2015 MWW-240 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 4/15/2015 MWW-1703 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 29 7/22/2015 MWW-4031 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 34 10/21/2015 MWW-5964 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 26 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 45 Plant Well No. 1 (M-12) 1/21/2015 MWW-241 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 31 4/15/2015 MWW-1704 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 7/22/2015 MWW-4032 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 10/22/2015 MWW-6097 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 35 Hasbrouck (M-55) 1/21/2015 MWW-242 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 4/15/2015 MWW-1705 < 152 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 21 7/22/2015 MWW-4034 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 10/21/2015 MWW-5965 < 149 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 38 lmholte (M-43C) 1/21/2015 MWW-243 < 182 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 36 4/15/2015 MWW-1706 < 152 < 10 *< 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 39 7/22/2015 MWW-4035 < 147 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 49 10/21/2015 MWW-5967 < 149 < 10 < 30 < 10 < 10 < 30 < 15 <10 <10 <15 <17 Cumulative Averages < 500 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 49 13-1

MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCi!g wet)

Upstream 1000' M-8 (C)

Date Collected 05-26-15 05-26-15 09-22-15 09-22-15 Lab Code MF- 2724 MF- 2725 MF- 5239 MF- 5240 Sample Type Shorthead Smallmouth Shorthead Smallmouth Red horse Bass Red horse Bass K-40 2.56 +/- 0.35 3.46 +/- 0.44 3.58 +/- 0.42 3.65 +/- 0.46 Mn-54 < 0.013 < 0.017 < 0.017 < 0.016 Fe-59 < 0.043 < 0.041 < 0.031 < 0.056 Co-58 < 0.016 < 0.018 < 0.017 < 0.019 Co-60 < 0.012 < 0.018 < 0.011 < 0.010 Zn-65 < 0.029 < 0.026 < 0.018 < 0.033 Nb-95 < 0.022 < 0.031 < 0.027 < 0.030 Zr-95 < 0.024 < 0.025 < 0.043 < 0.043 Cs-134 < 0.015 < 0.016 < 0.014 < 0.020 Cs-137 < 0.015 < 0.018 < 0.011 < 0.017 Ba-La-140 < 0.045 < 0.035 < 0.045 < 0.073 Ce-144 < 0.130 < 0.127 < 0.105 < 0.119 Cumulative Previous Average Average K-40 3.31 2.72 Mn-54 < 0.017 < 0.019 Fe-59 < 0.056 < 0.059 Co-58 < 0.019 < 0.023 Co-60 < 0.018 < 0.020 Zn-65 < 0.033 < 0.034 Nb-95 < 0.031 < 0.057 Zr-95 < 0.043 < 0.055 Cs-134 < 0.020 < 0.019 Cs-137 < 0.018 < 0.020 Ba-La-140 < 0.073 < 0.272 Ce-144 < 0.130 < 0.150 14-1

MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCi!g wet)

Downstream 1000' M-9 Date Collected 05-26-15 05-26-15 09-22-15 09-22-15 Lab Code MF- 2726 MF- 2727 MF- 5241 MF- 5242 Sample Type Shorthead Smallmouth Shorthead Smallmouth Red horse Bass Red horse Bass K-40 3.08 +/- 0.45 3.20 +/- 0.64 3.56 +/- 0.42 3.71 +/- 0.43 Mn-54 < 0.016 < 0.025 < 0.015 < 0.015 Fe-59 < 0.043 < 0.019 < 0.046 < 0.033 Co-58 < 0.020 < 0.025 < 0.013 < 0.021 Co-60 < 0.014 < 0.025 < 0.013 < 0.008 Zn-65 < 0.029 < 0.070 < 0.031 < 0.050 Nb-95 < 0.021 < 0.030 < 0.018 < 0.029 Zr-95 < 0.031 < 0.058 < 0.039 < 0.032 Cs-134 < 0.018 < 0.025 < 0.014 < 0.017 Cs-137 < 0.014 < 0.020 < 0.010 < 0.017 Ba-La-140 < 0.031 < 0.122 < 0.057 < 0.056 Ce-144 < 0.102 < 0.141 < 0.108 < 0.068 Date Collected Cumulative Previous Lab Code Average Average Sample Type K-40 3.39 3.03 Mn-54 < 0.025 < 0.018 Fe-59 < 0.046 < 0.059 Co-58 < 0.025 < 0.028 Co-60 < 0.025 < 0.021 Zn-65 < 0.070 < 0.035 Nb-95 < 0.030 < 0.043 Zr-95 < 0.058 < 0.046 Cs-134 < 0.025 < 0.020 Cs-137 < 0.020 < 0.017 Ba-La-140 < 0.122 < 0.217 Ce-144 < 0.141 < 0.126 14-2

MNGP Table 15. Aquatic invertebrates, analysis for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCilg wet) Cumulative Previous Average Average Upstream 1000' M-8 (C)a Date Collected 08-06-15 10-07-15 Lab Code MBO- 4344 MBO- 5607 Be-7 < 1.49 < 0.36 < 1.49 < 0.57 K-40 < 1.91 < 0.66 < 1.91 < 0.84 Mn-54 < 0.088 < 0.042 < 0.088 < 0.024 Fe-59 < 0.24 < 0.090 < 0.24 < 0.13 Co-58 < 0.15 < 0.031 < 0.15 < 0.068 Co-60 < 0.085 < 0.029 < 0.085 < 0.052 Zn-65 < 0.18 < 0.059 < 0.18 < 0.094 Zr-Nb-95 < 0.23 < 0.062 < 0.23 < 0.064 Ru-103 < 0.22 < 0.072 < 0.22 < 0.075 Ru-106 < 0.55 < 0.30 < 0.55 < 0.39 Cs-134 < 0.076 < 0.033 < 0.076 < 0.040 Cs-137 < 0.085 < 0.023 < 0.085 < 0.049 Ba-La-140 < 1.35 < 0.14 < 1.35 < 0.41 Ce-144 < 0.39 < 0.22 < 0.39 < 0.20 Downstream 1000' M-9 Date Collected 08-06-15 10-07-15 Lab Code MBO- 4345 MBO- 5608 Be-7 < 0.67 < 0.60 < 0.67 < 0.55 K-40 < 0.95 < 1.24 < 1.24 < 0.91 Mn-54 < 0.053 < 0.044 < 0.053 < 0.046 Fe-59 < 0.22 < 0.12 < 0.22 < 0.13 Co-58 < 0.078 < 0.064 < 0.078 < 0.046 Co-60 < 0.039 < 0.047 < 0.047 < 0.041 Zn-65 < 0.079 < 0.097 < 0.097 < 0.077 Zr-Nb-95 < 0.13 < 0.11 < 0.13 < 0.067 Ru-103 < 0.13 < 0.087 < 0.13 < 0.070 Ru-106 < 0.48 < 0.33 < 0.48 < 0:38 Cs-134 < 0.050 < 0.043 < 0.050 < 0.041 Cs-137 < 0.039 < 0.038 < 0.039 < 0.040 Ba-La-140 < 1.15 < 0.32 < 1.15 < 0.22 Ce-144 < 0.25 < 0.23 < 0.25 < 0.24 15-1

MNGP Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes.

Collection: Semiannually Sample Description and Concentration (pCilg dry) Cumulative Previous Average Average Upstream 1000' M-8 (C)

Date Collected 08-06-15 10-07-15 Lab Code MSS- 4416 MSS- 5604 Be-7 < 0.29 < 0.27 < 0.29 < 0.16 K-40 11.58+/-0.54 11.53 +/- 0.51 11.55 9.12 Mn-54 < 0.017 < 0.014 <0.017 < 0.016 Fe-59 < 0.073 < 0.068 < 0.073 < 0.052 Co-58 < 0.022 < 0.011 < 0.022 < 0.016 Co-60 < 0.016 < 0.013 <0.016 <0.014 Zn-65 < 0.044 < 0.032 < 0.044 < 0.034 Nb-95 < 0.024 < 0.035 < 0.035 < 0.015 Zr-95 < 0.048 < O.Q46 < 0.048 < 0.028 Ru-103 < 0.039 < 0.018 < 0.039 < 0.018 Ru-106 < 0.083 < 0.13 < 0.13 < 0.075 Cs-134 < 0.013 < 0.014 < 0.014 < 0.012 Cs-137 < 0.017 < 0.015 <0.017 <0.012 Ba-La-140 < 0.21 < 0.085 <0.21 < 0.081 Ce-144 < 0.12 < 0.092 <0.12 < 0.081 Downstream 1000' M-9 Date Collected 08-06-15 10-07-15 Lab Code MSS- 4417 MSS- 5605 Be-7 < 0.26 < 0.30 < 0.30 < 0.27 K-40 10.51 +/- 0.54 10.41 +/- 0.54 10.46 10.58 Mn-54 < 0.018 < 0.016 <0.018 < 0.018 Fe-59 < 0.041 < 0.076 < 0.076 < 0.068 Co-58 < 0.021 < 0.026 < 0.026 < 0.027 Co-60 < 0.017 < 0.013 < 0.017 < 0.016 Zn-65 < 0.039 < 0.039 < 0.039 < 0.040 Nb-95 < 0.030 < 0.051 < 0.051 < 0.044 Zr-95 < 0.052 < 0.027 < 0.052 < 0.042 Ru-103 < 0.036 < 0.032 < 0.036 < 0.030 Ru-106 < 0.12 < 0.11 < 0.12 < 0.16 Cs-134 < 0.012 < 0.017 <0.017 < 0.015 Cs-137 0.034 +/- 0.016 0.024 +/- 0.014 0.029 0.035 Ba-La-140 < 0.10 < 0.14 < 0.14 < 0.11 Ce-144 < 0.11 < 0.13 < 0.13 < 0.12 16-1

MNGP Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/g dry) Cumulative Previous Average Average Montissippi Park M-15 Date Collected 08-06-15 10-07-15 Lab Code MSS- 4418 MSS- 5606 Be-7 < 0.33 < 0.22 < 0.33 < 0.22 K-40 9.49 +/- 0.51 10.54 +/- 0.54 10.01 10.89 Mn-54 < 0.021 < 0.018 < 0.021 < 0.017 Fe-59 < 0.068 < 0.050 < 0.068 < 0.040 Co-58 < 0.022 < 0.019 < 0.022 < 0.017 Co-60 < 0.014 < 0.011 < 0.014 < 0.013 Zn-65 < 0.041 < 0.038 <0.041 < 0.045 Nb-95 < 0.031 < 0.028 < 0.031 < 0.025 Zr-95 < 0.046 < 0.026 < 0.046 < 0.039 Ru-103 < 0.041 < 0.016 <0.041 < 0.026 Ru-106 < 0.13 < 0.13 < 0.13 < 0.102 Cs-134 < 0.014 < 0.016 < 0.016 < 0.014 Cs-137 < 0.017 < 0.021 < 0.021 0.059 Ba-La-140 < 0.20 < 0.11 < 0.20 < 0.092 Ce-144 < 0.11 < 0.11 < 0.11 < 0.088 16-2