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
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Revision as of 04:45, 20 June 2019

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" 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

  • Northbroak,ll60061-1310 phone (847) 564-0700
  • fax (847) 564-4517 Approved:

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.

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)

...................................................................................

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

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. 1 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. 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.

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,

?, 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.

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).

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.

4 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.

5 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.

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

' 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 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.

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.

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 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 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.

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.

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.

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. 10 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 borate TLDs, one depleted of 6 Li and 10 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. 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.

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.

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)

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°/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 < 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°/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 1 96th 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. 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)

ISFSI-16 (neutron) a "C" denotes control location.

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°/SW 1.53 mi@ 103°/ESE 2.3 mi@ 131 °/SE 3.0 mi@ 118°/ESE 2.6 mi@ 134°/SE 11.5 mi@ 323°/NW 11.2 mi @4r/NE 11.6 mi@ 130°/SE 10.3 mi@ 226°/ 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.

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 -lnnerRing

--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.

0.035 0.033 0.031 0.029 0.027 0.025 :§ 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*

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)

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°/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°/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°/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)

Airborne Pathway 0.002 0.030 (204/204)

M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 (0.007-0.088) 2.6 rni@ 134°/SE (0.009-0.088)

(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°/SE (0.049-0.087)

(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*

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

______ _ 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° /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

___ ,_. __ _ 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)

(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

-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

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

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)

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)

(2.56-3.65)

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

  • 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 Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

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 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).

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 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

.. 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 Lab Code Date CF-62,63 1/7/2015 CF-62,63 1/7/2015 CF-62,63 1n/2015 CF-62,63 1/7/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83, 84 1/12/2015 SG-83,84 1/12/2015 AP-011215NB 1/12/2015 WW-315,316 1/27/2015 DW-6001 0,60011 1/28/2015 DW-60010,60011 1/28/2015 SG-336,337 1/30/2015 SG-336,337 1/30/2015 SG-336,337 1/30/2015 AP-020415NB 2/4/2015 AP-021115NB 2/11/2015 DW-60023,60024 2/26/2015 DW-60023,60024 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 SG-834,835 2/2/2015 SG-834,835 2/2/2015 DW-60031 , 60032 3/4/2015 DW-60036,60037 3/4/2015 DW-60036,60037 3/4/2015 DW-60048,60049 3/4/2015 DW-60048,60049 3/4/2015 AP-1169, 1170 3/19/2015 DW-60069,60070 4/8/2015 AP-040915 4/9/2015 WW-2394,2395 4/13/2015 SG-1847, 1848 4/20/2015 SG-1847, 1848 4/20/2015 SG-1847, 1848 4/20/2015 XWW-2267,2268 4/23/2015 XWW-2078,2079 4/27/2015 Analysis Gr. Beta Be-7 K-40 Sr-90 K-40 Tl-208 Pb-212 Pb-214 Bi-214 Ra-226 Ac-228 Gr. Beta H-3 Ra-226 Ra-228 Bi-214 Pb-214 Ac-228 Gr. Beta Gr. Beta Ra-226 Ra-228 K-40 Tl-208 Pb-212 Bi-212 Ac-228 Gr. Alpha Gr. Beta Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Alpha Gr. Beta H-3 K-40 Pb-214 Ac-228 H-3 H-3 First Result 5.72+/-0.12 0.915 +/- 0.135 3.97 +/- 0.28 0.017 +/- 0.006 10.11 +/- 1.42 0.57 +/- 0.07 1.73+/-0.10 13.33 +/- 0.33 13.48 +/- 0.39 25.68 +/- 2.19 13.33 +/- 0.59 0.025 +/- 0.004 1,961 +/- 178 1.25+/-0.14 2.00 +/- 0.66 6.63 +/- 0.20 6.45 +/- 0.19 4.43 +/- 0.24 0.021 +/- 0.004 0.034 +/- 0.004 1.52+/-0.15 0.97 +/- 0.48 11.96 +/- 0.98 0.36 +/- 0.04 0.92 +/- 0.06 1.26 +/- 0.45 1.35 +/- 0.22 113.3+/-6.3 82.27 +/- 2.79 185.4 +/- 7.4 6.89 +/- 0.34 4.43 +/- 0.73 0.84 +/- 0.10 0.68 +/- 0.41 0.20 +/- 0.02 3.58 +/- 0.88 0.027 +/- 0.005 1,628 +/- 139 3.24 +/- 1.18 5.80 +/- 0.22 5.26 +/- 0.51 6,584 +/- 244 359.0 +/- 89.6 A5-1 Concentration (pCi/L)8 Second Result 5.78 +/- 0.12 0.919 +/- 0.102 3.88 +/- 0.23 0.011 +/- 0.006 9.69 +/- 1.20 0.56 +/- 0.06 1.58 +/- 0.09 13.88 +/- 0.28 13.45 +/- 0.29 26.22 +/- 1.53 12.86 +/- 0.43 0.023 +/- 0.004 1,868 +/- 174 1.40 +/- 0.15 1.39 +/- 0.60 6.45 +/- 0.45 6.45 +/- 0.37 4.20 +/- 0.58 0.019 +/- 0.035 0.040 +/- 0.047 1.51 +/- 0.15 1.66 +/- 0.58 11.49 +/- 0.82 0.31 +/- 0.04 0.91 +/- 0.06 1.50 +/- 0.40 1.23+/-0.17 117.2 +/- 2.8 84.33 +/- 2.74 177.0 +/- 7.2 6.88 +/- 0.32 4.41 +/-0.72 0.94 +/- 0.11 1.42 +/- 0.58 0.24 +/- 0.10 3.92 +/- 0.88 0.023 +/- 0.005 1,695 +/- 141 1.99+/-0.76 6.23 +/- 0.76 5.00 +/- 0.42 6,164 +/- 237 418.7 +/- 92.3 Averaged Result Acceptance 5.75 +/- 0.42 Pass 0.917+/-0.15 Pass 3.92 +/- 0.33 Pass 0.014 +/- 0.004 Pass 9.90 +/- 1.16 Pass 0.57 +/- 0.05 Pass 1.65 +/- 0.13 Pass 13.61 +/- 0.22 Pass 13.47 +/- 0.24 Pass 25.95 +/- 1.34 Pass 13.09 +/- 0.36 Pass 0.024 +/- 0.003 Pass 1,915 +/- 124 Pass 1.33 +/- 0.10 Pass 1. 70 +/- 0.45 Pass 6.54 +/- 0.21 Pass 6.45 +/- 0.21 Pass 4.32 +/- 0.31 Pass 0.035 +/- 0.020 Pass 0.037 +/- 0.003 Pass 1.52 +/- 0.11 Pass 1.32 +/- 0.38 Pass 11.72 +/- 0.64 Pass 0.34 +/- 0.03 Pass 0.91 +/- 0.05 Pass 1.38 +/- 0.30 Pass 1.29 +/- 0.14 Pass 115.2 +/- 3.4 Pass 83.30 +/- 1.96 Pass 181.2 +/- 5.2 Pass 6.89 +/- 0.23 Pass 4.42 +/- 0.51 Pass 0.89 +/- 0.07 Pass 1.05 +/- 0.36 Pass 0.22 +/- 0.07 Pass 3.75 +/- 0.62 Pass 0.025 +/- 0.003 Pass 1,662 +/- 99 Pass 2.62 +/- 0.70 Pass 6.02 +/- 0.40 Pass 5.13 +/- 0.33 Pass 6,374 +/- 170 Pass 388.9 +/- 64.3 Pass 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 Lab Code Date AP-3822, 3823 7/1/2015 AP-3969, 3970 7/1/2015 WW-3632, 3633 7/6/2015 W-4368, 4369 7/6/2015 W-4368, 4369 7/6/2015 DW-60138, 60139 717/2015 DW-60138, 60139 717/2015 WW-4158, 4159 7/9/2015 Ml-2902, 2903 7/10/2015 SG-3533, 3534 7/10/2015 DW-60150, 60151 7/10/2015 DW-60150, 60151 7/10/2015 VE-3716, 3717 7/14/2015 Ml-3759, 3760 7/15/2015 Ml-3759, 3760 7/15/2015 AP-072115 7/21/2015 VE-4053, 4054 7/21/2015 VE-4053, 4054 7/21/2015 AP-4200, 4201 7/29/2015 AP-4200, 4201 7/29/2015 W-4137, 4138 7/31/2015 XWW-4431, 4432 8/5/2015 SG-4305, 4306 8/6/2015 AP-081015 8/10/2015 AP-081115 8/11/2015 VE-4452, 4453 8/11/2015 AP-081715 8/17/2015 DW-60195, 60196 8/17/2015 DW-60195, 60196 8/17/2015 DW-60198, 60199 8/17/2015 VE-4578, 4579 8/18/2015 SW-4662, 4663 8/25/2015 DW-60212, 60213 8/25/2015 LW-4788, 4789 8/27/2015 AP-083115 8/31/2015 AP-4875, 4876 9/3/2015 VE-5083, 5084 9/14/2015 VE-5083, 5084 9/14/2015 VE-5167, 5168 9/16/2015 VE-5167, 5168 9/16/2015 BS-5188, 5189 9/16/2015 F-5419, 5420 9/17/2015 DW-60238, 60239 9/18/2015 DW-60238, 60239 9/18/2015 AP-092215NB 9/22/2015 WW-5398, 5399 9/22/2015 AP-6007, 6008 9/28/2015 Analysis Be-7 Be-7 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 K-40 Gr. Alpha Ra-226 Ra-228 K-40 K-40 Sr-90 Gr. Beta Be-7 K-40 Be-7 K-40 Ra-226 H-3 Ra-228 Gr. Beta Gr. Beta K-40 Gr. Beta Ra-226 Ra-228 Gr. Alpha K-40 H-3 Ra-226 Gr. Beta Gr. Beta Be-7 Be-7 K-40 Be-7 K-40 K-40 K-40 Ra-226 Ra-228 Gr. Beta H-3 Be-7 First Result 0.075 +/- 0.011 0.063 +/- 0.008 5,169 +/- 225 26.70 +/- 4.00 34.62 +/- 2.10 0.07 +/- 0.04 1.04+/-0.41 138.8 +/- 82.4 1271 +/- 118 238.0 +/- 8.2 1.53+/-0.16 2.68 +/- 0.68 3.85 +/- 0.33 1819 +/- 127 1.00 +/- 0.36 0.022 +/- 0.004 0.52 +/- 0.15 8.00 +/- 0.42 1.06+/-0.12 5.03 +/- 0.24 0.58 +/- 0.13 4,773 +/-213 10.34 +/- 0.58 0.038 +/- 0.005 0.024 +/- 0.004 3.77 +/- 0.29 0.030 +/- 0.005 0.39+/-0.10 1.43 +/- 0.51 2.93 +/- 0.94 4.14 +/- 0.25 351.3 +/- 89.8 0.09 +/- 0.07 0.97 +/- 0.51 0.032 +/- 0.005 0.294 +/- 0.125 0.47 +/- 0.23 6.20 +/- 0.51 0.40 +/- 0.11 3.56 +/- 0.27 9.69 +/- 0.51 3.48 +/- 0.47 1.93 +/- 0.23 4.44 +/- 0.78 0.021 +/- 0.004 1,857 +/- 145 0.08 +/- 0.01 A 5-3 Concentration (pCi/L)' Second Result 0.068 +/- 0.012 0.064 +/- 0.010 5,058 +/- 223 24.10 +/- 3.90 33.30 +/- 2.02 0.11 +/- 0.05 1.15+/-0.47 174.0 +/- 84.1 1308 +/- 115 249.5 +/- 8.5 1.49 +/- 0.12 1.89 +/- 0.62 3.71 +/- 0.31 1764 +/- 140 0.61 +/- 0.32 0.027 +/- 0.004 0.49 +/- 0.11 7.61 +/- 0.31 0.96 +/- 0.11 4.96 +/- 0.23 0.45 +/- 0.14 4,915 +/- 216 11.46 +/- 0.62 0.039 +/- 0.005 0.020 +/- 0.004 3.78 +/- 0.26 0.030 +/- 0.005 0.37 +/- 0.10 1.97 +/- 0.61 2.11 +/- 0.96 4.32 +/- 0.24 415.6 +/- 92.8 0.10+/-0.08 1.68 +/- 0.59 0.031 +/- 0.005 0.202 +/- 0.109 0.56 +/- 0.19 6.36 +/- 0.50 0.41 +/-0.10 3.91 +/- 0.24 10.51 +/- 0.52 3.49 +/- 0.56 2.31 +/- 0.26. 5.61 +/- 0.84 0.025 +/- 0.004 1,846 +/- 144 0.08 +/- 0.01 Averaged Result 0.072 +/- 0.008 0.063 +/- 0.006 5,114 +/- 159 25.40 +/- 2.79 33.96 +/- 1.46 0.09 +/- 0.03 1.10+/-0.31 156.4 +/- 58.9 1289 +/- 82 243.8 +/- 5.9 1.51 +/- 0.10 2.29 +/- 0.46 3.78 +/- 0.23 1791 +/- 94 0.80 +/- 0.24 0.024 +/- 0.003 0.50 +/- 0.09 7.81 +/- 0.26 1.01 +/- 0.08 4.99 +/- 0.16 0.52+/-0.10 4,844 +/- 152 10.90 +/- 0.42 0.039 0.004 0.022 0.003 3.77 +/- 0.20 0.030 +/- 0.003 0.38 +/- 0.07 1.70 +/- 0.40 2.52 +/- 0.67 4.23 +/- 0.17 383.4 +/- 64.6 0.10 +/- 0.05 1.32 +/- 0.39 0.031 +/- 0.003 0.248 +/- 0.083 0.52 +/- 0.15 6.28 +/- 0.36 0.41 +/- 0.07 3.74+/-0.18 10.10 +/- 0.36 3.49 +/- 0.36 2.12 +/- 0.17 5.03 +/- 0.57 0.023 +/- 0.00 1,852 +/- 102 0.08 +/- 0.01 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 Pass Pass 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 LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 AP-7351 , 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 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. Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass ' 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). Lab Code b Date Analysis Laboratory result MAS0-975 2/1/2015 Ni-63 341 +/- 18 MAS0-975 2/1/2015 Sr-90 523 +/- 12 MAS0-97 5 2/1 /2015 Tc-99 614 +/- 12 MAS0-975 2/1/2015 Cs-134 533 +/- 6 MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 MAS0-975 2/1/2015 Co-57 0.5+/-1.0 MAS0-975 2/1/2015 Co-60 741 +/- 8 MAS0-975 2/1/2015 Mn-54 1 , 153 +/- 9 MAS0-975 2/1/2015 Zn-65 892 +/- 18 MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 MAW-969 ct 2/1/2015 Co-57 10.2 +/- 0.4 MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 MAW-969 2/1/2015 H-3 569 +/- 13 MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 MAW-969 2/1/2015 U-238 0.84 +/- 0.09 MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 MAW-947 2/1/2015 1-129 1.26 +/- 0.12 MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 MAAP-978 f 2/1/2015 Co-57 0.04 +/- 0.04 MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 -MAAP-978 2/1/2015 Mn-54 1.11 +/-0.08 MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 A6-1 Concentration a Known Activity 448 653 867 678 0.0 0.0 817 1,198 1064 0.654 23.5 19.1 29.9 0.00 563 6.88 0.00 0.00 18.3 3.18 0.01 0.83 0.148 0.97 9.48 1.07 2.79 1.49 0.068 1.15 0.00 1.51 0.00 1.02 0.83 0.000 0.085 0.016 0.099 Control Limits c 314-582 457 -849 607-1 '127 475 -881 NA c NA c 572 -1,062 839 -1,557 745 -1,383 0.458 -0.850 16.5 -30.6 13.4 -24.8 20.9 -38.9 NA c 394 -732 4.82-8.94 NA c NA c 12.8 -23.8 2.23-4.13 NAe 0.58 -1.08 0.104-0.192 0.68 -1.26 6.64 -12.32 0.32 -1.81 1.40 -4.19 1.04-1.94 0.048 -0.089 0.81 -1.50 NA c 1.06-1.96 NA c 0.71 -1.33 0.58 -1.08 NA c 0.059-0.110 0.011 -0.020 0.069 -0.129 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass 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 MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298-553 Fail MAS0-4903 9 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 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 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.

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.

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.

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 . 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.

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.

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

<J) c:: 0.. <J) E <J) "E ro 0.. ro (f) E (,9 I-ro <J) 0 (f) I-<J) --. .$ 0 0.. ro 1i5 E <J) {g ro ..c: (f) 0> ::J J: (f)

< z j 0 * / r J I ' I (

  • 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

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 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, 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-------,----

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)

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.

  • 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.

E-7

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' ..... '"" FIGURE2 SlTEMAP Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes.

Collection Concentration (pCi/L) Lab Code Date 3H s*Mn ssFe ssco so co sszn 95 ZrNb 13<cs 137cs 14oBala 1<<ce 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 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 1 0 Monitoring Well #7 (M-39) MWW-4760 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 1 0 < 10 < 15 < 18 Monitoring Well #8 (M-40). MWW-4761 08/24/15 < 173 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 26 E-9 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Lab Code MWW-250 MWW-709 MWW-1199 MWW-1896 MWW-2567 MWW-3147 MWW-4087 MWW-4772 MWW-5398 MWW-6096 MWW-6614 MWW-7260 MWW-710 MWW-2568 MWW-4773 MWW-6615 MWW-252 MWW-711 MWW-1138 MWW-1897 MWW-2569 MWW-3148 MWW-4273 MWW-4762 MWW-5244 MWW-5938 MWW-6616 MWW-7061 MWW-712 MWW-2570 MWW-4763 MWW-6617 MWW-713 MWW-2571 MWW-4764 MWW-6618 Collection Date 01121115 02120115 03117115 04122115 05120115 06118/15 07121115 08121115 09122115 10120115 11117115 12115115 02120115 05120115 08121115 11117115 01121115 02124115 03117115 04122115 05121115 06118115 07123115 08124115 09123115 10120115 11118115 12115115 02124115 05121115 08124115 11118115 02120115 05120115 08125115 11117115 2556 +/- 199 667 +/- 103 282 +/- 85 < 147 < 151 361 +/- 89 5443 +/- 226 6493 +/- 237 1857 +/- 145 353 +/- 95 182 +/- 87 1652 +/- 135 < 146 < 151 < 173 < 149 251+/-110 381 +/- 90 453 +/- 98 283 +/- 88 352 +/- 106 250 +/- 84 180 +/- 88 236 +/- 100 293 +/- 86 270 +/- 90 258 +/- 91 155 +/- 79 < 146 < 151 260 +/- 101 < 149 < 146 < 151 < 146 < 149 Concentration (pCiiL) Monitoring Well #9A (M-44) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 23 < 10 < 30 < 10 < 30 < 10 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 <15 <10 <10 < 15 < 15 < 22 < 26 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 Monitoring Well #98 (M-51) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 Monitoring Well #1 0 (M-45) <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 < 15 < 15 < 23 < 18 < 20 < 18 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 20 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 34 Monitoring Well #11 (M-46) < 10 < 30 < 10 < 30 < 10 < 30 < 10 < 30 < 10 < 10 <10 <10 <10 <10 <10 <10 < 30 < 30 < 30 < 30 Monitoring Well #12A (M-47) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 <15 <15 < 15 < 15 < 15 < 15 < 47 < 26 < 33 < 26 < 27 < 16 < 22 < 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).

Lab Code MWW-714 MWW-2572 MWW-4765 MWW-6619 MWW-254 MWW-715 MWW-1139 MWW-1898 MWW-2573 MWW-3149 MWW-4274 MWW-4766 MWW-5245 MWW-5939 MWW-6620 MWW-7062 MWW-255 MWW-717 MWW-1140 MWW-1899 MWW-2574 MWW-3893 MWW-4767 MWW-5246 MWW-5940 MWW-6621 MWW-7064 MWW-256 MWW-718 MWW-1900 MWW-2575 MWW-3150 MWW-4275 MWW-4769 MWW-5247 MWW-5941 MWW-6622 MWW-7065 Collection Date 02/20/15 05/20/15 08/25/15 11/17/15 01/21/15 02/24/15 03/17/15 04/22/15 05/20/15 06/18/15 07/27/15 08/25/15 09/23/15 10/20/15 11/18/15 12/15/15 01/21/15 02/24/15 03/17/15 04/22/15 05/20/15 06/18/15 08/25/15 09/23/15 10/20/15 11/18/15 12/15/15 01/21/15 02/16/15 04/21/15 05/19/15 06/16/15 07/20/15 08/17/15 09/23/15 10/20/15 11/16/15 12/14/15 < 146 < 151 < 173 < 149 < 182 < 146 < 153 < 147 < 151 < 143 153 +/- 87 < 173 255 +/- 84 161 +/- 85 182 +/- 87 < 146 < 182 203 +/- 81 220 +/- 87 240 +/- 85 < 151 215 +/- 88 172 +/- 83 184 +/- 81 169 +/- 86 < 149 < 146 < 182 < 146 < 147 < 151 < 143 < 151 < 173 < 142 < 147 < 149 < 146 Concentration (pCi/L) Monitoring Well #128 (M-48) < 10 < 30 < 10 < 10 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 Monitoring Well #13A (M-49) <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 < 15 < 15 < 25 < 26 < 32 <28 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 < 10 < 30 < 1 0 < 10 < 30 < 15 < 10 < 10 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 22 Monitoring Well #138 (M-50) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 33 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 1 0 < 15 < 20 Monitoring Well #14 (M-52) < 10 < 30 < 10 < 10 < 30 < 15 < 1 0 < 10 < 15 < 45 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 18 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 21 E-11 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L) Lab Code Date 3H 54 Mn sgFe sa co so co sszn 95 ZrNb 134cs 137Cs 14oBala 144ce 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.

Lab Code MWW-1896 Collection Date 04/22/15 Location Gross Alpha MW-9a < 1.6 E-13 Concentration (pCi/L} < 4.1 < 3.3 < 674 < 101 I Environmental, Inc. Midwest laboratory 700 Landwehr Ro'd , Northbrook, ll60062*1310 phone (847) 564.0700.

fax (847) 564-4517 Reviewed and Approved 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 MNGP TABLE OF CONTENTS Section Page 10 20 30 List of Tables...................................................................................................................

iii INTRODUCTION

............................................................................................................ . LISTING OF MISSED SAMPLES .................................................................................. . DATA TABLES ............................................................................................................... . ii iv v vi 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 Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's), (continued).

Location M-01C M-02C M-03C M-04C Mean+/- s.d. M-01S M-02S M-03S M-04S M-OSS M-06S Mean+/- s.d. M-1-01 M-1-02 M-1-03 M-1-04 M-1-05 M-1-06 M-1-07 M-l-08 M-1-09 M-1-10 M-1-11 M-1-12 M-1-13 Mean+/- s.d. 1st Qtr. 11.8 +/- 1.5 15.9 +/- 0.8 13.2 +/- 0.4 14.7+/-1.7 13.9 +/- 1.8 mRem/91 days 2nd Qtr. 3rd Qtr. 13.2 +/- 0.8 16.6 +/- 1.4 14.8 +/- 0.6 14.0 +/- 0.5 14.6+/-1.5 12.5 +/- 1.5 17.4 +/- 0.9 15.2+/-0.9 15.1 +/-1.6 15.1 +/- 2.0 Indicators (Special Interest Areas) 10.4 +/- 1.0 12.5 +/- 0.5 9.4 +/- 1.4 13.5 +/- 1.0 13.2 +/- 0.6 14.5 +/- 1.5 12.2 +/- 0.7 14.7 +/- 0.7 13.2 +/- 1.1 16.6+/-1.1 14.4 +/- 0.8 17.6 +/- 1.2 14.5 +/- 0.6 14.9 +/- 0.8 15.3+/-1.1 15.2 +/- 0.7 15.5 +/- 0.5 15.2+/-1.1 13.7+/-2.2 14.2 +/- 1.1 14.2 +/- 2.8 ISFSI TLDs 39.4 +/- 1.2 26.7 +/- 2.0 42.8 +/- 2.0 36.4 +/- 1.2 24.3 +/- 0.6 38.1 +/- 1.2 29.6 +/- 1.0 23.2 +/- 1.1 32.4 +/- 1.3 36.7 +/- 2.6 34.4 +/- 2.4 29.2 +/- 2.6 80.3 +/- 5.0 67.3 +/- 3.1 68.3 +/- 4.6 30.3 +/- 2.4 21.6 +/- 0.8 30.0 +/- 2.2 30.3+/-1.4 27.5 +/- 1.7 31.1 +/-2.7 28.9 +/- 2.9 24.1+/-0.5 29.6 +/- 3.0 234.8 +/- 12.1 220.1 +/- 3.7 70.5 +/-4.1 43.3 +/- 1.7 28.6 +/- 1.3 41.6+/-1.2 12.4+/-1.7 15.1 +/- 0.5 13.1 +/- 1.7 14.1+/-0.7 14.3 +/- 0.6 15.2 +/- 0.9 17.1 +/- 1.3 12.8 +/- 0.8 15.6 +/- 2.0 48.7 +/- 58.4 41.5 +/- 55.4 35.2 +/- 17.9 1-2 4th Qtr. 16.0 +/- 1.3 20.3+/-1.1 17.6+/-1.1 16.6+/-1.0 17.6 +/- 1.9 13.9 +/- 0.9 15.9+/-1.1 17.0+/-1.2 17.0+/-1.1 17.9+/-1.3 18.8 +/- 1.1 16.7 +/- 1.7 41.7+/-2.4 36.9 +/- 1.1 31.9 +/- 1.3 37.7 +/- 2.7 79.5+/-2.1 25.4 +/- 1.3 32.8 +/- 1.6 28.7 +/- 2.7 61.3+/-2.7 35.3 +/- 1.6 16.7+/-1.2 ' 15.4 +/- 1.3 16.6 +/- 1.6 35.4 +/- 18.1 MNGP Previous Cumulative Annual Average Average 13.4 14.4 17.5 14.1 15.2 14.3 15.1 14.2 15.3 14.3 11.6 10.3 14.3 11.7 14.3 13.0 16.4 14.6 15.6 14.1 16.2 15.6 14.7 13.2 37.7 36.1 33.9 29.8 29.3 25.6 34.5 35.6 73.9 65.9 26.8 25.0 30.4 27.7 27.9 26.6 146.6 170.5 37.2 33.2 14.3 13.9 14.7 13.9 15.5 13.5 40.2 39.8 Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 3* Location:

M-1 (C) Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m;;) Gross Beta Required LLD 0.010 01-07-15 319 0.041 +/- 0.004 01-14-15 321 0.042 +/- 0.004 01-21-15 323 0.036 +/- 0.004 01-28-15 315 0.021 +/- 0.003 02-04-15 357 0.029 +/- 0.003 02-11-15 389 0.033 +/- 0.003 02-18-15 354 0.044 +/- 0.004 02-25-15 354 0.062 +/- 0.004 03-04-15 352 0.036 +/- 0.004 03-11-15 353 0.025 +/- 0.004 03-18-15 392 0.019 +/- 0.003 03-25-15 352 0.024 +/- 0.003 04-01-15 354 0.018 +/- 0.003 1st Quarter Mean+/- s.d. 0.033 +/- 0.012 04-08-15 357 0.023 +/- 0.003 04-15-15 351 0.021 +/- 0.003 04-22-15 355 0.014 +/- 0.003 04-29-15 355 0.021 +/- 0.003 05-06-15 443 0.021 +/- 0.003 05-13-15 440 0.008 +/- 0.002 05-20-15 447 0.010 +/- 0.002 05-27-15 435 0.018 +/- 0.003 06-03-15 442 0.018 +/- 0.002 06-10-15 441 0.016 +/- 0.002 06-17-15 441 0.013 +/- 0.002 06-24-15 351 0.021 +/- 0.003 07-01-15 441 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.017 +/- 0.005 Date Volume Collected (mJ) Required LLD 07-08-15 443 07-15-15 443 07-22-15 441 07-29-15 439 08-05-15 440 08-12-15 305 08-19-15 353 08-26-15 337 09-02-15 353 09-09-15 352 09-16-15 302 09-23-15 352 09-30-15 326 3rd Quarter Mean +/- s.d. 10-07-15 325 10-14-15 324 10-21-15 301 10-28-15 336 11-04-15 397 11-11-15 351 11-18-15 353 11-25-15 387 12-02-15 382 12-09-15 350 12-16-15 353 12-23-15 354 12-30-15 384 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are< 0.03 pCi/m 3 unless otherwise noted. 2-1 MNGP Gross Beta 0.010 0.022 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.002 0.026 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.004 0.031 +/- 0.004 0.022 +/- 0.003 0.038 +/- 0.004 0.028 +/- 0.003 0.033 +/- 0.004 0.025 +/- 0.003 0.039 +/- 0.004 0.027 +/- 0.007 0.023 +/- 0.003 0.031 +/- 0.004 0.035 +/- 0.004 0.022 +/- 0.003 0.025 +/- 0.003 0.039 +/- 0.004 0.033 +/- 0.004 0.022 +/- 0.003 0.044 +/- 0.004 0.061 +/- 0.005 0.016 +/- 0.003 0.044 +/- 0.004 0.040 +/- 0.004 0.034 +/- 0.012 0.028 0.032 Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-2 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Reguired LLD 0.010 01-07-15 352 0.038 +/- 0.004 01-14-15 326 0.038 +/- 0.004 01-21-15 329 0.031 +/- 0.003 01-28-15 321 0.021 +/- 0.003 02-04-15 NDb 02-11-15 322 0.040 +/- 0.004 02-18-15 325 0.048 +/- 0.004 02-25-15 326 0.073 +/- 0.005 03-04-15 324 0.035 +/- 0.004 03-11-15 351 0.027 +/- 0.004 03-18-15 328 0.025 +/- 0.004 03-25-15 323 0.027 +/- 0.004 04-01-15 352 0.019 +/- 0.003 1st Quarter Mean+/- s.d. 0.035 +/- 0.015 04-08-15 330 0.023 +/- 0.003 04-15-15 349 0.027 +/- 0.003 04-22-15 325 0.017 +/- 0.003 04-29-15 329 0.021 +/- 0.003 05-06-15 NDb 05-13-15 351 0.010 +/- 0.002 05-20-15 358 0.011 +/- 0.002 05-27-15 347 0.019 +/- 0.003 06-03-15 351 0.019 +/- 0.003 06-10-15 353 0.019 +/- 0.003 06-17-15 352 0.014 +/- 0.003 06-24-15 354 0.018 +/- 0.003 07-01-15 340 0.020 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 341 07-15-15 341 07-22-15 325 07-29-15 350 08-05-15 353 08-12-15 330 08-19-15 342 08-26-15 326 09-02-15 342 09-09-15 348 09-16-15 318 09-23-15 337 09-30-15 318 3rd Quarter Mean+/- s.d. 10-07-15 314 10-14-15 315 10-21-15 314 10-28-15 263 11-04-15 353 11-11-15 352 11-18-15 326 11-25-15 327 12-02-15 327 12-09-15 328 12-16-15 326 12-23-15 304 12-30-15 324 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. b "NO" = No data, see Table 2.0, Listing of Missed Samples. 3-1 MNGP Gross Beta 0.010 0.025 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 0.024 +/- 0.003 0.017 +/- 0.003 0.025 +/- 0.003 0.031 +/- 0.004 0.025 +/- 0.003 0.038 +/- 0.004 0.027 +/- 0.003 0.033 +/- 0.004 0.024 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.006 0.023 +/- 0.003 0.027 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.004 0.027 +/- 0.003 0.045 +/- 0.004 0.037 +/- 0.004 0.025 +/- 0.004 0.051 +/- 0.005 0.066 +/- 0.005 0.021 +/- 0.003 0.051 +/- 0.005 0.050 +/- 0.005 0.037 +/- 0.014 0.029 0.028 Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-3 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Required LLD 0.010 01-07-15 326 0.041 +/- 0.004 01-14-15 353 0.042 +/- 0.004 01-21-15 357 0.034 +/- 0.003 01-28-15 348 0.020 +/- 0.003 02-04-15 357 0.029 +/- 0.003 02-11-15 351 0.057 +/- 0.004 02-18-15 353 0.048 +/- 0.004 02-25-15 353 0.066 +/- 0.004 03-04-15 378 0.035 +/- 0.004 03-11-15 379 0.024 +/- 0.003 03-18-15 383 0.022 +/- 0.003 03-25-15 350 0.028 +/- 0.004 04-01-15 352 0.020 +/- 0.003 1st Quarter Mean+/- s.d. 0.036 +/- 0.015 04-08-15 358 0.023 +/- 0.003 04-15-15 349 0.024 +/- 0.003 04-22-15 352 0.015 +/- 0.003 04-29-15 357 0.020 +/- 0.003 05-06-15 350 0.025 +/- 0.003 05-13-15 380 0.007 +/- 0.002 05-20-15 385 0.012 +/- 0.002 05-27-15 400 0.018 +/- 0.003 06-03-15 378 0.017 +/- 0.003 06-10-15 380 0.019 +/- 0.003 06-17-15 352 0.013 +/- 0.003 06-24-15 382 0.018 +/- 0.003 07-01-15 340 0.021 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 409 07-15-15 409 07-22-15 380 07-29-15 324 08-05-15 407 08-12-15 369 08-19-15 342 08-26-15 339 09-02-15 342 09-09-15 342 09-16-15 344 09-23-15 337 09-30-15 346 3rd Quarter Mean +/- s.d. 10-07-15 340 10-14-15 315 10-21-15 314 10-28-15 316 11-04-15 329 11-11-15 329 11-18-15 304 11-25-15 328 12-02-15 328 12-09-15 306 12-16-15 331 12-23-15 387 12-30-15 301 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. 4-1 MNGP Gross Beta 0.010 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.030 +/- 0.004 0.021 +/- 0.003 0.027 +/- 0.003 0.033 +/- 0.004 0.022 +/- 0.003 0.044 +/- 0.004 0.028 +/- 0.003 0.031 +/- 0.004 0.025 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.007 0.025 +/- 0.003 0.035 +/- 0.004 0.031 +/- 0.004 0.028 +/- 0.004 D.030 +/- 0.004 0.047 +/- 0.004 0.041 +/- 0.004 0.025 +/- 0.004 0.053 +/- 0.005 0.082 +/- 0.006 0.019 +/- 0.003 0.041 +/-0.004 0.057 +/- 0.005 0.040 +/- 0.017 0.030 0.027 Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-4 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m3) Gross Beta Required LLD 0.010 01-07-15 352 0.035 +/- 0.003 01-14-15 353 0.040 +/- 0.004 01-21-15 356 0.033 +/- 0.003 01-28-15 347 0.021 +/- 0.003 02-04-15 355 0.034 +/- 0.003 02-11-15 350 0.042 +/- 0.004 02-18-15 326 0.047 +/- 0.004 02-25-15 327 0.070 +/- 0.005 03-04-15 350 0.039 +/- 0.004 03-11-15 350 0.023 +/- 0.003 03-18-15 330 0.028 +/- 0.004 03-25-15 324 0.029 +/- 0.004 04-01-15 326 0.021 +/- 0.003 1st Quarter Mean+/- s.d. 0.036 +/- 0.013 04-08-15 331 0.024 +/- 0.003 04-15-15 323 0.025 +/- 0.003 04-22-15 327 0.014 +/- 0.003 04-29-15 329 0.023 +/- 0.003 05-06-15 407 0.023 +/- 0.003 05-13-15 405 0.009 +/- 0.002 05-20-15 413 0.011 +/- 0.002 05-27-15 401 0.019 +/- 0.003 06-03-15 407 0.018 +/- 0.003 06-10-15 391 0.017 +/- 0.003 06-17-15 404 0.014 +/- 0.002 06-24-15 NOb 07-01-15 397 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m3) 07-08-15 409 07-15-15 406 07-22-15 383 07-29-15 405 08-05-15 407 08-12-15 329 08-19-15 328 08-26-15 326 09-02-15 352 09-09-15 351 09-16-15 331 09-23-15 350 09-30-15 329 3rd Quarter Mean +/- s.d. 10-07-15 327 10-14-15 327 10-21-15 327 10-28-15 329 11-04-15 356 11-11-15 350 11-18-15 352 11-25-15 352 12-02-15 352 12-09-15 352 12-16-15 351 12-23-15 328 12-30-15 350 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. b "NO" No data; see Table 2.0, Listing of Missed Samples. 5-1 MNGP Gross Beta 0.010 0.021 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.003 0.039 +/- 0.004 0.024 +/- 0.003 0.044 +/- 0.004 0.030 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.003 0.044 +/- 0.004 0.029 +/- 0.009 0.026 +/- 0.003 0.040 +/- 0.004 0.033 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.004 0.038 +/- 0.004 0.039 +/- 0.004 0.024 +/- 0.003 0.050 +/- 0.004 0.068 +/- 0.005 0.022 +/- 0.003 0.051 +/- 0.005 0.054 +/- 0.004 0.039 +/- 0.013 0.031 0.028 Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-5 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Required LLD 0.010 01-07-15 323 0.046 +/- 0.004 01-14-15 324 0.042 +/- 0.004 01-21-15 323 0.038 +/- 0.004 01-28-15 NOb 02-04-15 356 0.031 +/- 0.003 02-11-15 352 0.038 +/- 0.004 02-18-15 294 0.054 +/- 0.005 02-25-15 324 0.071 +/- 0.005 03-04-15 351 0.034 +/- 0.004 03-11-15 352 0.023 +/- 0.003 03-18-15 326 0.024 +/- 0.004 03-25-15 292 0.030 +/- 0.004 04-01-15 352 0.018 +/- 0.003 1st Quarter Mean+/- s.d. 0.038 +/- 0.015 04-08-15 298 0.024 +/- 0.004 04-15-15 291 0.027 +/- 0.004 04-22-15 324 0.016 +/- 0.003 04-29-15 326 0.022 +/- 0.003 05-06-15 384 0.022 +/- 0.003 05-13-15 381 0.009 +/- 0.002 05-20-15 387 0.011 +/- 0.002 05-27-15 378 0.016 +/- 0.003 06-03-15 382 0.019 +/- 0.003 06-10-15 382 0.017 +/- 0.003 06-17-15 380 0.012 +/- 0.002 06-24-15 353 0.020 +/- 0.003 07-01-15 368 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 370 07-15-15 370 07-22-15 352 07-29-15 351 08-05-15 382 08-12-15 341 08-19-15 352 08-26-15 324 09-02-15 326 09-09-15 271 09-16-15 301 09-23-15 325 09-30-15 298 3rd Quarter Mean +/- s.d. 10-07-15 298 10-14-15 298 10-21-15 297 10-28-15 326 11-04-15 359 11-11-15 367 11-18-15 252 11-25-15 354 12-02-15 323 12-09-15 323 12-16-15 353 12-23-15 295 12-30-15 352 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are< 0.03 pCi/m 3 unless otherwise noted. b "NO"= No data, see Table 2.0, Listing of Missed Samples. 6-1 MNGP Gross Beta 0.010 0.023 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.003 0.021 +/- 0.003 0.024 +/- 0.003 0.032 +/- 0.004 0.022 +/- 0.003 0.047 +/- 0.004 0.037 +/- 0.004 0.035 +/- 0.004 0.028 +/- 0.004 0.045 +/- 0.005 0.029 +/- 0.009 0.025 +/- 0.004 0.039 +/- 0.004 0.036 +/- 0.004 0.025 +/- 0.004 0.029 +/- 0.003 0.043 +/- 0.004 0.032 +/- 0.005 0.025 +/- 0.003 0.050 +/- 0.005 0.088 +/- 0.006 0.015 +/- 0.003 0.048 +/- 0.005 0.050 +/- 0.004 0.039 +/- 0.018 0.031 0.031 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.

Activity (pCi/m 3) 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 Volume(m 3) 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 Volume(m 3) 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.

Activity (pCilm 3) Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-3 Lab Code MAP-1844 MAP-3821 MAP-6032 MAP-7412 Volume(m 3) 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 Volume(m 3) 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.

Activity (pCi/m 3) Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-5 Lab Code MAP-1846 MAP-3824 MAP-6034 MAP-7414 Volume(m 3) 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 Period Collected November December b 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 Table 12. River water and drinking water, analysis of quarterly composites for tritium. Collection:

Quarterly composites of weekly collections.

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

Water frozen remainder of quarter. b Water frozen 12-30-15.

12-1 < 152 < 154 < 152 < 146 < 151 < 165 < 152 < 154 < 152 < 146 < 151 < 157 < 152 < 154 < 152 < 146 < 151 < 157 MNGP MNGP Table 13. Well water, analysis for tritium and gamma-emitting isotopes.

Sample Description and Concentration (pCi/L) Date Collected 1/21/2015 4/15/2015 7/22/2015 10/21/2015 Lab Code MWW-240 MWW-1703 MWW-4031 MWW-5964 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/22/2015 MWW-241 MWW-1704 MWW-4032 MWW-6097 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/21/2015 MWW-242 MWW-1705 MWW-4034 MWW-5965 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/21/2015 MWW-243 MWW-1706 MWW-4035 MWW-5967 Cumulative Averages H-3 (< 500 pCi/L) < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 a> lO <h l1.. Q) lO ' 0 0 Monticello (M-11) 0 <D ' 0 0 lO (l) ' c N lO a> ' .0 z ('-. C0 .,.... ' U) 0 < 10 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 45 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 29 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 34 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 26 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 45 Plant Well No. 1 (M-12) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 21 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 35 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 2 8 < 10 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 35 Hasbrouck (M-55) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 38 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 21 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 38 < 1 0 < 30 < 1 0 < 10 < 30 < 15 < 1 0 < 1 0 < 15 < 28 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 38 lmholte (M-43C) < 1 0 < 30 < 1 0 < 1 0 < 1 0 *< 30 < 1 0 < 1 0 < 1 0 < 30 < 1 0 < 1 0 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 30 < 15 < 30 < 15 < 30 < 15 < 1 0 < 1 0 < 15 < 36 < 1 0 < 1 0 < 15 < 39 < 1 0 < 1 0 < 15 < 49 <10 <10 <15 <17 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 49 13-1 Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCi!g wet) Upstream 1 000' M-8 (C) Date Collected 05-26-15 05-26-15 09-22-15 Lab Code MF-2724 MF-2725 MF-5239 Sample Type Shorthead Smallmouth Shorthead Red horse Bass Red horse K-40 2.56 +/- 0.35 3.46 +/- 0.44 3.58 +/- 0.42 Mn-54 < 0.013 < 0.017 < 0.017 Fe-59 < 0.043 < 0.041 < 0.031 Co-58 < 0.016 < 0.018 < 0.017 Co-60 < 0.012 < 0.018 < 0.011 Zn-65 < 0.029 < 0.026 < 0.018 Nb-95 < 0.022 < 0.031 < 0.027 Zr-95 < 0.024 < 0.025 < 0.043 Cs-134 < 0.015 < 0.016 < 0.014 Cs-137 < 0.015 < 0.018 < 0.011 Ba-La-140

< 0.045 < 0.035 < 0.045 Ce-144 < 0.130 < 0.127 < 0.105 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 09-22-15 MF-5240 Smallmouth Bass 3.65 +/- 0.46 < 0.016 < 0.056 < 0.019 < 0.010 < 0.033 < 0.030 < 0.043 < 0.020 < 0.017 < 0.073 < 0.119 MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCi!g wet) Date Collected Lab Code Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Date Collected Lab Code Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 Ce-144 05-26-15 MF-2726 Shorthead Red horse 3.08 +/- 0.45 < 0.016 < 0.043 < 0.020 < 0.014 < 0.029 < 0.021 < 0.031 < 0.018 < 0.014 < 0.031 < 0.102 Cumulative Average 3.39 < 0.025 < 0.046 < 0.025 < 0.025 < 0.070 < 0.030 < 0.058 < 0.025 < 0.020 < 0.122 < 0.141 Downstream 1 000' M-9 05-26-15 09-22-15 MF-2727 MF-5241 Smallmouth Shorthead Bass Red horse 3.20 +/- 0.64 3.56 +/- 0.42 < 0.025 < 0.015 < 0.019 < 0.046 < 0.025 < 0.013 < 0.025 < 0.013 < 0.070 < 0.031 < 0.030 < 0.018 < 0.058 < 0.039 < 0.025 < 0.014 < 0.020 < 0.010 < 0.122 < 0.057 < 0.141 < 0.108 Previous Average 3.03 < 0.018 < 0.059 < 0.028 < 0.021 < 0.035 < 0.043 < 0.046 < 0.020 < 0.017 < 0.217 < 0.126 14-2 MNGP 09-22-15 MF-5242 Smallmouth Bass 3.71 +/- 0.43 < 0.015 < 0.033 < 0.021 < 0.008 < 0.050 < 0.029 < 0.032 < 0.017 < 0.017 < 0.056 < 0.068 MNGP Table 15. Aquatic invertebrates, analysis for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCilg wet) Cumulative Previous Average Average Upstream 1 000' 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 1 000' 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 1 000' 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 1 000' 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 Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/g dry) Cumulative 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 K-40 9.49 +/- 0.51 10.54 +/- 0.54 10.01 Mn-54 < 0.021 < 0.018 < 0.021 Fe-59 < 0.068 < 0.050 < 0.068 Co-58 < 0.022 < 0.019 < 0.022 Co-60 < 0.014 < 0.011 < 0.014 Zn-65 < 0.041 < 0.038 <0.041 Nb-95 < 0.031 < 0.028 < 0.031 Zr-95 < 0.046 < 0.026 < 0.046 Ru-103 < 0.041 < 0.016 <0.041 Ru-106 < 0.13 < 0.13 < 0.13 Cs-134 < 0.014 < 0.016 < 0.016 Cs-137 < 0.017 < 0.021 < 0.021 Ba-La-140

< 0.20 < 0.11 < 0.20 Ce-144 < 0.11 < 0.11 < 0.11 16-2 MNGP Previous Average < 0.22 10.89 < 0.017 < 0.040 < 0.017 < 0.013 < 0.045 < 0.025 < 0.039 < 0.026 < 0.102 < 0.014 0.059 < 0.092 < 0.088 (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

  • Northbroak,ll60061-1310 phone (847) 564-0700
  • fax (847) 564-4517 Approved:

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.

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)

...................................................................................

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

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. 1 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. 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.

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,

?, 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.

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).

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.

4 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.

5 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.

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

' 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 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.

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.

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 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 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.

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.

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.

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. 10 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 borate TLDs, one depleted of 6 Li and 10 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. 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.

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.

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)

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°/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 < 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°/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 1 96th 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. 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)

ISFSI-16 (neutron) a "C" denotes control location.

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°/SW 1.53 mi@ 103°/ESE 2.3 mi@ 131 °/SE 3.0 mi@ 118°/ESE 2.6 mi@ 134°/SE 11.5 mi@ 323°/NW 11.2 mi @4r/NE 11.6 mi@ 130°/SE 10.3 mi@ 226°/ 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.

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 -lnnerRing

--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.

0.035 0.033 0.031 0.029 0.027 0.025 :§ 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*

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)

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°/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°/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°/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)

Airborne Pathway 0.002 0.030 (204/204)

M-5, Air Station 0.031 (51/51) 0.028 (52/52) 0 (0.007-0.088) 2.6 rni@ 134°/SE (0.009-0.088)

(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°/SE (0.049-0.087)

(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*

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

______ _ 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° /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

___ ,_. __ _ 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)

(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

-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

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

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)

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)

(2.56-3.65)

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

  • 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 Number Non-Routine Results* 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

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 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).

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 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

.. 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 Lab Code Date CF-62,63 1/7/2015 CF-62,63 1/7/2015 CF-62,63 1n/2015 CF-62,63 1/7/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83,84 1/12/2015 SG-83, 84 1/12/2015 SG-83,84 1/12/2015 AP-011215NB 1/12/2015 WW-315,316 1/27/2015 DW-6001 0,60011 1/28/2015 DW-60010,60011 1/28/2015 SG-336,337 1/30/2015 SG-336,337 1/30/2015 SG-336,337 1/30/2015 AP-020415NB 2/4/2015 AP-021115NB 2/11/2015 DW-60023,60024 2/26/2015 DW-60023,60024 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 S-799,800 2/26/2015 SG-834,835 2/2/2015 SG-834,835 2/2/2015 DW-60031 , 60032 3/4/2015 DW-60036,60037 3/4/2015 DW-60036,60037 3/4/2015 DW-60048,60049 3/4/2015 DW-60048,60049 3/4/2015 AP-1169, 1170 3/19/2015 DW-60069,60070 4/8/2015 AP-040915 4/9/2015 WW-2394,2395 4/13/2015 SG-1847, 1848 4/20/2015 SG-1847, 1848 4/20/2015 SG-1847, 1848 4/20/2015 XWW-2267,2268 4/23/2015 XWW-2078,2079 4/27/2015 Analysis Gr. Beta Be-7 K-40 Sr-90 K-40 Tl-208 Pb-212 Pb-214 Bi-214 Ra-226 Ac-228 Gr. Beta H-3 Ra-226 Ra-228 Bi-214 Pb-214 Ac-228 Gr. Beta Gr. Beta Ra-226 Ra-228 K-40 Tl-208 Pb-212 Bi-212 Ac-228 Gr. Alpha Gr. Beta Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Alpha Gr. Beta H-3 K-40 Pb-214 Ac-228 H-3 H-3 First Result 5.72+/-0.12 0.915 +/- 0.135 3.97 +/- 0.28 0.017 +/- 0.006 10.11 +/- 1.42 0.57 +/- 0.07 1.73+/-0.10 13.33 +/- 0.33 13.48 +/- 0.39 25.68 +/- 2.19 13.33 +/- 0.59 0.025 +/- 0.004 1,961 +/- 178 1.25+/-0.14 2.00 +/- 0.66 6.63 +/- 0.20 6.45 +/- 0.19 4.43 +/- 0.24 0.021 +/- 0.004 0.034 +/- 0.004 1.52+/-0.15 0.97 +/- 0.48 11.96 +/- 0.98 0.36 +/- 0.04 0.92 +/- 0.06 1.26 +/- 0.45 1.35 +/- 0.22 113.3+/-6.3 82.27 +/- 2.79 185.4 +/- 7.4 6.89 +/- 0.34 4.43 +/- 0.73 0.84 +/- 0.10 0.68 +/- 0.41 0.20 +/- 0.02 3.58 +/- 0.88 0.027 +/- 0.005 1,628 +/- 139 3.24 +/- 1.18 5.80 +/- 0.22 5.26 +/- 0.51 6,584 +/- 244 359.0 +/- 89.6 A5-1 Concentration (pCi/L)8 Second Result 5.78 +/- 0.12 0.919 +/- 0.102 3.88 +/- 0.23 0.011 +/- 0.006 9.69 +/- 1.20 0.56 +/- 0.06 1.58 +/- 0.09 13.88 +/- 0.28 13.45 +/- 0.29 26.22 +/- 1.53 12.86 +/- 0.43 0.023 +/- 0.004 1,868 +/- 174 1.40 +/- 0.15 1.39 +/- 0.60 6.45 +/- 0.45 6.45 +/- 0.37 4.20 +/- 0.58 0.019 +/- 0.035 0.040 +/- 0.047 1.51 +/- 0.15 1.66 +/- 0.58 11.49 +/- 0.82 0.31 +/- 0.04 0.91 +/- 0.06 1.50 +/- 0.40 1.23+/-0.17 117.2 +/- 2.8 84.33 +/- 2.74 177.0 +/- 7.2 6.88 +/- 0.32 4.41 +/-0.72 0.94 +/- 0.11 1.42 +/- 0.58 0.24 +/- 0.10 3.92 +/- 0.88 0.023 +/- 0.005 1,695 +/- 141 1.99+/-0.76 6.23 +/- 0.76 5.00 +/- 0.42 6,164 +/- 237 418.7 +/- 92.3 Averaged Result Acceptance 5.75 +/- 0.42 Pass 0.917+/-0.15 Pass 3.92 +/- 0.33 Pass 0.014 +/- 0.004 Pass 9.90 +/- 1.16 Pass 0.57 +/- 0.05 Pass 1.65 +/- 0.13 Pass 13.61 +/- 0.22 Pass 13.47 +/- 0.24 Pass 25.95 +/- 1.34 Pass 13.09 +/- 0.36 Pass 0.024 +/- 0.003 Pass 1,915 +/- 124 Pass 1.33 +/- 0.10 Pass 1. 70 +/- 0.45 Pass 6.54 +/- 0.21 Pass 6.45 +/- 0.21 Pass 4.32 +/- 0.31 Pass 0.035 +/- 0.020 Pass 0.037 +/- 0.003 Pass 1.52 +/- 0.11 Pass 1.32 +/- 0.38 Pass 11.72 +/- 0.64 Pass 0.34 +/- 0.03 Pass 0.91 +/- 0.05 Pass 1.38 +/- 0.30 Pass 1.29 +/- 0.14 Pass 115.2 +/- 3.4 Pass 83.30 +/- 1.96 Pass 181.2 +/- 5.2 Pass 6.89 +/- 0.23 Pass 4.42 +/- 0.51 Pass 0.89 +/- 0.07 Pass 1.05 +/- 0.36 Pass 0.22 +/- 0.07 Pass 3.75 +/- 0.62 Pass 0.025 +/- 0.003 Pass 1,662 +/- 99 Pass 2.62 +/- 0.70 Pass 6.02 +/- 0.40 Pass 5.13 +/- 0.33 Pass 6,374 +/- 170 Pass 388.9 +/- 64.3 Pass 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 Lab Code Date AP-3822, 3823 7/1/2015 AP-3969, 3970 7/1/2015 WW-3632, 3633 7/6/2015 W-4368, 4369 7/6/2015 W-4368, 4369 7/6/2015 DW-60138, 60139 717/2015 DW-60138, 60139 717/2015 WW-4158, 4159 7/9/2015 Ml-2902, 2903 7/10/2015 SG-3533, 3534 7/10/2015 DW-60150, 60151 7/10/2015 DW-60150, 60151 7/10/2015 VE-3716, 3717 7/14/2015 Ml-3759, 3760 7/15/2015 Ml-3759, 3760 7/15/2015 AP-072115 7/21/2015 VE-4053, 4054 7/21/2015 VE-4053, 4054 7/21/2015 AP-4200, 4201 7/29/2015 AP-4200, 4201 7/29/2015 W-4137, 4138 7/31/2015 XWW-4431, 4432 8/5/2015 SG-4305, 4306 8/6/2015 AP-081015 8/10/2015 AP-081115 8/11/2015 VE-4452, 4453 8/11/2015 AP-081715 8/17/2015 DW-60195, 60196 8/17/2015 DW-60195, 60196 8/17/2015 DW-60198, 60199 8/17/2015 VE-4578, 4579 8/18/2015 SW-4662, 4663 8/25/2015 DW-60212, 60213 8/25/2015 LW-4788, 4789 8/27/2015 AP-083115 8/31/2015 AP-4875, 4876 9/3/2015 VE-5083, 5084 9/14/2015 VE-5083, 5084 9/14/2015 VE-5167, 5168 9/16/2015 VE-5167, 5168 9/16/2015 BS-5188, 5189 9/16/2015 F-5419, 5420 9/17/2015 DW-60238, 60239 9/18/2015 DW-60238, 60239 9/18/2015 AP-092215NB 9/22/2015 WW-5398, 5399 9/22/2015 AP-6007, 6008 9/28/2015 Analysis Be-7 Be-7 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 H-3 K-40 Gr. Alpha Ra-226 Ra-228 K-40 K-40 Sr-90 Gr. Beta Be-7 K-40 Be-7 K-40 Ra-226 H-3 Ra-228 Gr. Beta Gr. Beta K-40 Gr. Beta Ra-226 Ra-228 Gr. Alpha K-40 H-3 Ra-226 Gr. Beta Gr. Beta Be-7 Be-7 K-40 Be-7 K-40 K-40 K-40 Ra-226 Ra-228 Gr. Beta H-3 Be-7 First Result 0.075 +/- 0.011 0.063 +/- 0.008 5,169 +/- 225 26.70 +/- 4.00 34.62 +/- 2.10 0.07 +/- 0.04 1.04+/-0.41 138.8 +/- 82.4 1271 +/- 118 238.0 +/- 8.2 1.53+/-0.16 2.68 +/- 0.68 3.85 +/- 0.33 1819 +/- 127 1.00 +/- 0.36 0.022 +/- 0.004 0.52 +/- 0.15 8.00 +/- 0.42 1.06+/-0.12 5.03 +/- 0.24 0.58 +/- 0.13 4,773 +/-213 10.34 +/- 0.58 0.038 +/- 0.005 0.024 +/- 0.004 3.77 +/- 0.29 0.030 +/- 0.005 0.39+/-0.10 1.43 +/- 0.51 2.93 +/- 0.94 4.14 +/- 0.25 351.3 +/- 89.8 0.09 +/- 0.07 0.97 +/- 0.51 0.032 +/- 0.005 0.294 +/- 0.125 0.47 +/- 0.23 6.20 +/- 0.51 0.40 +/- 0.11 3.56 +/- 0.27 9.69 +/- 0.51 3.48 +/- 0.47 1.93 +/- 0.23 4.44 +/- 0.78 0.021 +/- 0.004 1,857 +/- 145 0.08 +/- 0.01 A 5-3 Concentration (pCi/L)' Second Result 0.068 +/- 0.012 0.064 +/- 0.010 5,058 +/- 223 24.10 +/- 3.90 33.30 +/- 2.02 0.11 +/- 0.05 1.15+/-0.47 174.0 +/- 84.1 1308 +/- 115 249.5 +/- 8.5 1.49 +/- 0.12 1.89 +/- 0.62 3.71 +/- 0.31 1764 +/- 140 0.61 +/- 0.32 0.027 +/- 0.004 0.49 +/- 0.11 7.61 +/- 0.31 0.96 +/- 0.11 4.96 +/- 0.23 0.45 +/- 0.14 4,915 +/- 216 11.46 +/- 0.62 0.039 +/- 0.005 0.020 +/- 0.004 3.78 +/- 0.26 0.030 +/- 0.005 0.37 +/- 0.10 1.97 +/- 0.61 2.11 +/- 0.96 4.32 +/- 0.24 415.6 +/- 92.8 0.10+/-0.08 1.68 +/- 0.59 0.031 +/- 0.005 0.202 +/- 0.109 0.56 +/- 0.19 6.36 +/- 0.50 0.41 +/-0.10 3.91 +/- 0.24 10.51 +/- 0.52 3.49 +/- 0.56 2.31 +/- 0.26. 5.61 +/- 0.84 0.025 +/- 0.004 1,846 +/- 144 0.08 +/- 0.01 Averaged Result 0.072 +/- 0.008 0.063 +/- 0.006 5,114 +/- 159 25.40 +/- 2.79 33.96 +/- 1.46 0.09 +/- 0.03 1.10+/-0.31 156.4 +/- 58.9 1289 +/- 82 243.8 +/- 5.9 1.51 +/- 0.10 2.29 +/- 0.46 3.78 +/- 0.23 1791 +/- 94 0.80 +/- 0.24 0.024 +/- 0.003 0.50 +/- 0.09 7.81 +/- 0.26 1.01 +/- 0.08 4.99 +/- 0.16 0.52+/-0.10 4,844 +/- 152 10.90 +/- 0.42 0.039 0.004 0.022 0.003 3.77 +/- 0.20 0.030 +/- 0.003 0.38 +/- 0.07 1.70 +/- 0.40 2.52 +/- 0.67 4.23 +/- 0.17 383.4 +/- 64.6 0.10 +/- 0.05 1.32 +/- 0.39 0.031 +/- 0.003 0.248 +/- 0.083 0.52 +/- 0.15 6.28 +/- 0.36 0.41 +/- 0.07 3.74+/-0.18 10.10 +/- 0.36 3.49 +/- 0.36 2.12 +/- 0.17 5.03 +/- 0.57 0.023 +/- 0.00 1,852 +/- 102 0.08 +/- 0.01 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 Pass Pass 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 LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 S0-6841, 6842 11/24/2015 Cs-137 0.18 +/- 0.03 0.16 +/- 0.03 0.17 +/- 0.02 S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 AP-7351 , 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 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. Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass ' 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). Lab Code b Date Analysis Laboratory result MAS0-975 2/1/2015 Ni-63 341 +/- 18 MAS0-975 2/1/2015 Sr-90 523 +/- 12 MAS0-97 5 2/1 /2015 Tc-99 614 +/- 12 MAS0-975 2/1/2015 Cs-134 533 +/- 6 MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 MAS0-975 2/1/2015 Co-57 0.5+/-1.0 MAS0-975 2/1/2015 Co-60 741 +/- 8 MAS0-975 2/1/2015 Mn-54 1 , 153 +/- 9 MAS0-975 2/1/2015 Zn-65 892 +/- 18 MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 MAW-969 ct 2/1/2015 Co-57 10.2 +/- 0.4 MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 MAW-969 2/1/2015 H-3 569 +/- 13 MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 MAW-969 2/1/2015 U-238 0.84 +/- 0.09 MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 MAW-947 2/1/2015 1-129 1.26 +/- 0.12 MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 MAAP-978 f 2/1/2015 Co-57 0.04 +/- 0.04 MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 -MAAP-978 2/1/2015 Mn-54 1.11 +/-0.08 MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 A6-1 Concentration a Known Activity 448 653 867 678 0.0 0.0 817 1,198 1064 0.654 23.5 19.1 29.9 0.00 563 6.88 0.00 0.00 18.3 3.18 0.01 0.83 0.148 0.97 9.48 1.07 2.79 1.49 0.068 1.15 0.00 1.51 0.00 1.02 0.83 0.000 0.085 0.016 0.099 Control Limits c 314-582 457 -849 607-1 '127 475 -881 NA c NA c 572 -1,062 839 -1,557 745 -1,383 0.458 -0.850 16.5 -30.6 13.4 -24.8 20.9 -38.9 NA c 394 -732 4.82-8.94 NA c NA c 12.8 -23.8 2.23-4.13 NAe 0.58 -1.08 0.104-0.192 0.68 -1.26 6.64 -12.32 0.32 -1.81 1.40 -4.19 1.04-1.94 0.048 -0.089 0.81 -1.50 NA c 1.06-1.96 NA c 0.71 -1.33 0.58 -1.08 NA c 0.059-0.110 0.011 -0.020 0.069 -0.129 Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass 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 MAS0-4903 9 8/1/2015 Sr-90 231 +/- 7 425 298-553 Fail MAS0-4903 9 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 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 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.

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.

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.

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 . 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.

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.

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

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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 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, 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-------,----

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)

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.

  • 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.

E-7

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Collection Concentration (pCi/L) Lab Code Date 3H s*Mn ssFe ssco so co sszn 95 ZrNb 13<cs 137cs 14oBala 1<<ce 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 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 1 0 Monitoring Well #7 (M-39) MWW-4760 08/24/15 < 173 < 10 < 30 < 10 < 10 < 30 < 15 < 1 0 < 10 < 15 < 18 Monitoring Well #8 (M-40). MWW-4761 08/24/15 < 173 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 26 E-9 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Lab Code MWW-250 MWW-709 MWW-1199 MWW-1896 MWW-2567 MWW-3147 MWW-4087 MWW-4772 MWW-5398 MWW-6096 MWW-6614 MWW-7260 MWW-710 MWW-2568 MWW-4773 MWW-6615 MWW-252 MWW-711 MWW-1138 MWW-1897 MWW-2569 MWW-3148 MWW-4273 MWW-4762 MWW-5244 MWW-5938 MWW-6616 MWW-7061 MWW-712 MWW-2570 MWW-4763 MWW-6617 MWW-713 MWW-2571 MWW-4764 MWW-6618 Collection Date 01121115 02120115 03117115 04122115 05120115 06118/15 07121115 08121115 09122115 10120115 11117115 12115115 02120115 05120115 08121115 11117115 01121115 02124115 03117115 04122115 05121115 06118115 07123115 08124115 09123115 10120115 11118115 12115115 02124115 05121115 08124115 11118115 02120115 05120115 08125115 11117115 2556 +/- 199 667 +/- 103 282 +/- 85 < 147 < 151 361 +/- 89 5443 +/- 226 6493 +/- 237 1857 +/- 145 353 +/- 95 182 +/- 87 1652 +/- 135 < 146 < 151 < 173 < 149 251+/-110 381 +/- 90 453 +/- 98 283 +/- 88 352 +/- 106 250 +/- 84 180 +/- 88 236 +/- 100 293 +/- 86 270 +/- 90 258 +/- 91 155 +/- 79 < 146 < 151 260 +/- 101 < 149 < 146 < 151 < 146 < 149 Concentration (pCiiL) Monitoring Well #9A (M-44) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 23 < 10 < 30 < 10 < 30 < 10 < 10 < 30 < 10 < 10 < 30 <15 <10 <10 <15 <10 <10 < 15 < 15 < 22 < 26 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 Monitoring Well #98 (M-51) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 Monitoring Well #1 0 (M-45) <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 < 15 < 15 < 23 < 18 < 20 < 18 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 20 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 34 Monitoring Well #11 (M-46) < 10 < 30 < 10 < 30 < 10 < 30 < 10 < 30 < 10 < 10 <10 <10 <10 <10 <10 <10 < 30 < 30 < 30 < 30 Monitoring Well #12A (M-47) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 <15 <15 < 15 < 15 < 15 < 15 < 47 < 26 < 33 < 26 < 27 < 16 < 22 < 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).

Lab Code MWW-714 MWW-2572 MWW-4765 MWW-6619 MWW-254 MWW-715 MWW-1139 MWW-1898 MWW-2573 MWW-3149 MWW-4274 MWW-4766 MWW-5245 MWW-5939 MWW-6620 MWW-7062 MWW-255 MWW-717 MWW-1140 MWW-1899 MWW-2574 MWW-3893 MWW-4767 MWW-5246 MWW-5940 MWW-6621 MWW-7064 MWW-256 MWW-718 MWW-1900 MWW-2575 MWW-3150 MWW-4275 MWW-4769 MWW-5247 MWW-5941 MWW-6622 MWW-7065 Collection Date 02/20/15 05/20/15 08/25/15 11/17/15 01/21/15 02/24/15 03/17/15 04/22/15 05/20/15 06/18/15 07/27/15 08/25/15 09/23/15 10/20/15 11/18/15 12/15/15 01/21/15 02/24/15 03/17/15 04/22/15 05/20/15 06/18/15 08/25/15 09/23/15 10/20/15 11/18/15 12/15/15 01/21/15 02/16/15 04/21/15 05/19/15 06/16/15 07/20/15 08/17/15 09/23/15 10/20/15 11/16/15 12/14/15 < 146 < 151 < 173 < 149 < 182 < 146 < 153 < 147 < 151 < 143 153 +/- 87 < 173 255 +/- 84 161 +/- 85 182 +/- 87 < 146 < 182 203 +/- 81 220 +/- 87 240 +/- 85 < 151 215 +/- 88 172 +/- 83 184 +/- 81 169 +/- 86 < 149 < 146 < 182 < 146 < 147 < 151 < 143 < 151 < 173 < 142 < 147 < 149 < 146 Concentration (pCi/L) Monitoring Well #128 (M-48) < 10 < 30 < 10 < 10 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 0 < 30 < 1 0 < 1 0 < 30 Monitoring Well #13A (M-49) <15 <10 <10 <15 <10 <10 <15 <10 <10 <15 <10 <10 < 15 < 15 < 15 < 15 < 25 < 26 < 32 <28 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 < 10 < 30 < 1 0 < 10 < 30 < 15 < 10 < 10 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 22 Monitoring Well #138 (M-50) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 33 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 18 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 10 < 15 < 28 < 10 < 30 < 10 < 10 < 30 < 15 < 10 < 1 0 < 15 < 20 Monitoring Well #14 (M-52) < 10 < 30 < 10 < 10 < 30 < 15 < 1 0 < 10 < 15 < 45 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 18 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 27 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 21 E-11 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L) Lab Code Date 3H 54 Mn sgFe sa co so co sszn 95 ZrNb 134cs 137Cs 14oBala 144ce 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.

Lab Code MWW-1896 Collection Date 04/22/15 Location Gross Alpha MW-9a < 1.6 E-13 Concentration (pCi/L} < 4.1 < 3.3 < 674 < 101 I Environmental, Inc. Midwest laboratory 700 Landwehr Ro'd , Northbrook, ll60062*1310 phone (847) 564.0700.

fax (847) 564-4517 Reviewed and Approved 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 MNGP TABLE OF CONTENTS Section Page 10 20 30 List of Tables...................................................................................................................

iii INTRODUCTION

............................................................................................................ . LISTING OF MISSED SAMPLES .................................................................................. . DATA TABLES ............................................................................................................... . ii iv v vi 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 Table 1. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD's), (continued).

Location M-01C M-02C M-03C M-04C Mean+/- s.d. M-01S M-02S M-03S M-04S M-OSS M-06S Mean+/- s.d. M-1-01 M-1-02 M-1-03 M-1-04 M-1-05 M-1-06 M-1-07 M-l-08 M-1-09 M-1-10 M-1-11 M-1-12 M-1-13 Mean+/- s.d. 1st Qtr. 11.8 +/- 1.5 15.9 +/- 0.8 13.2 +/- 0.4 14.7+/-1.7 13.9 +/- 1.8 mRem/91 days 2nd Qtr. 3rd Qtr. 13.2 +/- 0.8 16.6 +/- 1.4 14.8 +/- 0.6 14.0 +/- 0.5 14.6+/-1.5 12.5 +/- 1.5 17.4 +/- 0.9 15.2+/-0.9 15.1 +/-1.6 15.1 +/- 2.0 Indicators (Special Interest Areas) 10.4 +/- 1.0 12.5 +/- 0.5 9.4 +/- 1.4 13.5 +/- 1.0 13.2 +/- 0.6 14.5 +/- 1.5 12.2 +/- 0.7 14.7 +/- 0.7 13.2 +/- 1.1 16.6+/-1.1 14.4 +/- 0.8 17.6 +/- 1.2 14.5 +/- 0.6 14.9 +/- 0.8 15.3+/-1.1 15.2 +/- 0.7 15.5 +/- 0.5 15.2+/-1.1 13.7+/-2.2 14.2 +/- 1.1 14.2 +/- 2.8 ISFSI TLDs 39.4 +/- 1.2 26.7 +/- 2.0 42.8 +/- 2.0 36.4 +/- 1.2 24.3 +/- 0.6 38.1 +/- 1.2 29.6 +/- 1.0 23.2 +/- 1.1 32.4 +/- 1.3 36.7 +/- 2.6 34.4 +/- 2.4 29.2 +/- 2.6 80.3 +/- 5.0 67.3 +/- 3.1 68.3 +/- 4.6 30.3 +/- 2.4 21.6 +/- 0.8 30.0 +/- 2.2 30.3+/-1.4 27.5 +/- 1.7 31.1 +/-2.7 28.9 +/- 2.9 24.1+/-0.5 29.6 +/- 3.0 234.8 +/- 12.1 220.1 +/- 3.7 70.5 +/-4.1 43.3 +/- 1.7 28.6 +/- 1.3 41.6+/-1.2 12.4+/-1.7 15.1 +/- 0.5 13.1 +/- 1.7 14.1+/-0.7 14.3 +/- 0.6 15.2 +/- 0.9 17.1 +/- 1.3 12.8 +/- 0.8 15.6 +/- 2.0 48.7 +/- 58.4 41.5 +/- 55.4 35.2 +/- 17.9 1-2 4th Qtr. 16.0 +/- 1.3 20.3+/-1.1 17.6+/-1.1 16.6+/-1.0 17.6 +/- 1.9 13.9 +/- 0.9 15.9+/-1.1 17.0+/-1.2 17.0+/-1.1 17.9+/-1.3 18.8 +/- 1.1 16.7 +/- 1.7 41.7+/-2.4 36.9 +/- 1.1 31.9 +/- 1.3 37.7 +/- 2.7 79.5+/-2.1 25.4 +/- 1.3 32.8 +/- 1.6 28.7 +/- 2.7 61.3+/-2.7 35.3 +/- 1.6 16.7+/-1.2 ' 15.4 +/- 1.3 16.6 +/- 1.6 35.4 +/- 18.1 MNGP Previous Cumulative Annual Average Average 13.4 14.4 17.5 14.1 15.2 14.3 15.1 14.2 15.3 14.3 11.6 10.3 14.3 11.7 14.3 13.0 16.4 14.6 15.6 14.1 16.2 15.6 14.7 13.2 37.7 36.1 33.9 29.8 29.3 25.6 34.5 35.6 73.9 65.9 26.8 25.0 30.4 27.7 27.9 26.6 146.6 170.5 37.2 33.2 14.3 13.9 14.7 13.9 15.5 13.5 40.2 39.8 Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131 3* Location:

M-1 (C) Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m;;) Gross Beta Required LLD 0.010 01-07-15 319 0.041 +/- 0.004 01-14-15 321 0.042 +/- 0.004 01-21-15 323 0.036 +/- 0.004 01-28-15 315 0.021 +/- 0.003 02-04-15 357 0.029 +/- 0.003 02-11-15 389 0.033 +/- 0.003 02-18-15 354 0.044 +/- 0.004 02-25-15 354 0.062 +/- 0.004 03-04-15 352 0.036 +/- 0.004 03-11-15 353 0.025 +/- 0.004 03-18-15 392 0.019 +/- 0.003 03-25-15 352 0.024 +/- 0.003 04-01-15 354 0.018 +/- 0.003 1st Quarter Mean+/- s.d. 0.033 +/- 0.012 04-08-15 357 0.023 +/- 0.003 04-15-15 351 0.021 +/- 0.003 04-22-15 355 0.014 +/- 0.003 04-29-15 355 0.021 +/- 0.003 05-06-15 443 0.021 +/- 0.003 05-13-15 440 0.008 +/- 0.002 05-20-15 447 0.010 +/- 0.002 05-27-15 435 0.018 +/- 0.003 06-03-15 442 0.018 +/- 0.002 06-10-15 441 0.016 +/- 0.002 06-17-15 441 0.013 +/- 0.002 06-24-15 351 0.021 +/- 0.003 07-01-15 441 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.017 +/- 0.005 Date Volume Collected (mJ) Required LLD 07-08-15 443 07-15-15 443 07-22-15 441 07-29-15 439 08-05-15 440 08-12-15 305 08-19-15 353 08-26-15 337 09-02-15 353 09-09-15 352 09-16-15 302 09-23-15 352 09-30-15 326 3rd Quarter Mean +/- s.d. 10-07-15 325 10-14-15 324 10-21-15 301 10-28-15 336 11-04-15 397 11-11-15 351 11-18-15 353 11-25-15 387 12-02-15 382 12-09-15 350 12-16-15 353 12-23-15 354 12-30-15 384 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are< 0.03 pCi/m 3 unless otherwise noted. 2-1 MNGP Gross Beta 0.010 0.022 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.002 0.026 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.004 0.031 +/- 0.004 0.022 +/- 0.003 0.038 +/- 0.004 0.028 +/- 0.003 0.033 +/- 0.004 0.025 +/- 0.003 0.039 +/- 0.004 0.027 +/- 0.007 0.023 +/- 0.003 0.031 +/- 0.004 0.035 +/- 0.004 0.022 +/- 0.003 0.025 +/- 0.003 0.039 +/- 0.004 0.033 +/- 0.004 0.022 +/- 0.003 0.044 +/- 0.004 0.061 +/- 0.005 0.016 +/- 0.003 0.044 +/- 0.004 0.040 +/- 0.004 0.034 +/- 0.012 0.028 0.032 Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-2 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Reguired LLD 0.010 01-07-15 352 0.038 +/- 0.004 01-14-15 326 0.038 +/- 0.004 01-21-15 329 0.031 +/- 0.003 01-28-15 321 0.021 +/- 0.003 02-04-15 NDb 02-11-15 322 0.040 +/- 0.004 02-18-15 325 0.048 +/- 0.004 02-25-15 326 0.073 +/- 0.005 03-04-15 324 0.035 +/- 0.004 03-11-15 351 0.027 +/- 0.004 03-18-15 328 0.025 +/- 0.004 03-25-15 323 0.027 +/- 0.004 04-01-15 352 0.019 +/- 0.003 1st Quarter Mean+/- s.d. 0.035 +/- 0.015 04-08-15 330 0.023 +/- 0.003 04-15-15 349 0.027 +/- 0.003 04-22-15 325 0.017 +/- 0.003 04-29-15 329 0.021 +/- 0.003 05-06-15 NDb 05-13-15 351 0.010 +/- 0.002 05-20-15 358 0.011 +/- 0.002 05-27-15 347 0.019 +/- 0.003 06-03-15 351 0.019 +/- 0.003 06-10-15 353 0.019 +/- 0.003 06-17-15 352 0.014 +/- 0.003 06-24-15 354 0.018 +/- 0.003 07-01-15 340 0.020 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 341 07-15-15 341 07-22-15 325 07-29-15 350 08-05-15 353 08-12-15 330 08-19-15 342 08-26-15 326 09-02-15 342 09-09-15 348 09-16-15 318 09-23-15 337 09-30-15 318 3rd Quarter Mean+/- s.d. 10-07-15 314 10-14-15 315 10-21-15 314 10-28-15 263 11-04-15 353 11-11-15 352 11-18-15 326 11-25-15 327 12-02-15 327 12-09-15 328 12-16-15 326 12-23-15 304 12-30-15 324 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. b "NO" = No data, see Table 2.0, Listing of Missed Samples. 3-1 MNGP Gross Beta 0.010 0.025 +/- 0.003 0.023 +/- 0.003 0.019 +/- 0.003 0.024 +/- 0.003 0.017 +/- 0.003 0.025 +/- 0.003 0.031 +/- 0.004 0.025 +/- 0.003 0.038 +/- 0.004 0.027 +/- 0.003 0.033 +/- 0.004 0.024 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.006 0.023 +/- 0.003 0.027 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.004 0.027 +/- 0.003 0.045 +/- 0.004 0.037 +/- 0.004 0.025 +/- 0.004 0.051 +/- 0.005 0.066 +/- 0.005 0.021 +/- 0.003 0.051 +/- 0.005 0.050 +/- 0.005 0.037 +/- 0.014 0.029 0.028 Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-3 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Required LLD 0.010 01-07-15 326 0.041 +/- 0.004 01-14-15 353 0.042 +/- 0.004 01-21-15 357 0.034 +/- 0.003 01-28-15 348 0.020 +/- 0.003 02-04-15 357 0.029 +/- 0.003 02-11-15 351 0.057 +/- 0.004 02-18-15 353 0.048 +/- 0.004 02-25-15 353 0.066 +/- 0.004 03-04-15 378 0.035 +/- 0.004 03-11-15 379 0.024 +/- 0.003 03-18-15 383 0.022 +/- 0.003 03-25-15 350 0.028 +/- 0.004 04-01-15 352 0.020 +/- 0.003 1st Quarter Mean+/- s.d. 0.036 +/- 0.015 04-08-15 358 0.023 +/- 0.003 04-15-15 349 0.024 +/- 0.003 04-22-15 352 0.015 +/- 0.003 04-29-15 357 0.020 +/- 0.003 05-06-15 350 0.025 +/- 0.003 05-13-15 380 0.007 +/- 0.002 05-20-15 385 0.012 +/- 0.002 05-27-15 400 0.018 +/- 0.003 06-03-15 378 0.017 +/- 0.003 06-10-15 380 0.019 +/- 0.003 06-17-15 352 0.013 +/- 0.003 06-24-15 382 0.018 +/- 0.003 07-01-15 340 0.021 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 409 07-15-15 409 07-22-15 380 07-29-15 324 08-05-15 407 08-12-15 369 08-19-15 342 08-26-15 339 09-02-15 342 09-09-15 342 09-16-15 344 09-23-15 337 09-30-15 346 3rd Quarter Mean +/- s.d. 10-07-15 340 10-14-15 315 10-21-15 314 10-28-15 316 11-04-15 329 11-11-15 329 11-18-15 304 11-25-15 328 12-02-15 328 12-09-15 306 12-16-15 331 12-23-15 387 12-30-15 301 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. 4-1 MNGP Gross Beta 0.010 0.019 +/- 0.003 0.019 +/- 0.003 0.021 +/- 0.003 0.030 +/- 0.004 0.021 +/- 0.003 0.027 +/- 0.003 0.033 +/- 0.004 0.022 +/- 0.003 0.044 +/- 0.004 0.028 +/- 0.003 0.031 +/- 0.004 0.025 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.007 0.025 +/- 0.003 0.035 +/- 0.004 0.031 +/- 0.004 0.028 +/- 0.004 D.030 +/- 0.004 0.047 +/- 0.004 0.041 +/- 0.004 0.025 +/- 0.004 0.053 +/- 0.005 0.082 +/- 0.006 0.019 +/- 0.003 0.041 +/-0.004 0.057 +/- 0.005 0.040 +/- 0.017 0.030 0.027 Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-4 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m3) Gross Beta Required LLD 0.010 01-07-15 352 0.035 +/- 0.003 01-14-15 353 0.040 +/- 0.004 01-21-15 356 0.033 +/- 0.003 01-28-15 347 0.021 +/- 0.003 02-04-15 355 0.034 +/- 0.003 02-11-15 350 0.042 +/- 0.004 02-18-15 326 0.047 +/- 0.004 02-25-15 327 0.070 +/- 0.005 03-04-15 350 0.039 +/- 0.004 03-11-15 350 0.023 +/- 0.003 03-18-15 330 0.028 +/- 0.004 03-25-15 324 0.029 +/- 0.004 04-01-15 326 0.021 +/- 0.003 1st Quarter Mean+/- s.d. 0.036 +/- 0.013 04-08-15 331 0.024 +/- 0.003 04-15-15 323 0.025 +/- 0.003 04-22-15 327 0.014 +/- 0.003 04-29-15 329 0.023 +/- 0.003 05-06-15 407 0.023 +/- 0.003 05-13-15 405 0.009 +/- 0.002 05-20-15 413 0.011 +/- 0.002 05-27-15 401 0.019 +/- 0.003 06-03-15 407 0.018 +/- 0.003 06-10-15 391 0.017 +/- 0.003 06-17-15 404 0.014 +/- 0.002 06-24-15 NOb 07-01-15 397 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m3) 07-08-15 409 07-15-15 406 07-22-15 383 07-29-15 405 08-05-15 407 08-12-15 329 08-19-15 328 08-26-15 326 09-02-15 352 09-09-15 351 09-16-15 331 09-23-15 350 09-30-15 329 3rd Quarter Mean +/- s.d. 10-07-15 327 10-14-15 327 10-21-15 327 10-28-15 329 11-04-15 356 11-11-15 350 11-18-15 352 11-25-15 352 12-02-15 352 12-09-15 352 12-16-15 351 12-23-15 328 12-30-15 350 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are < 0.03 pCi/m 3 unless otherwise noted. b "NO" No data; see Table 2.0, Listing of Missed Samples. 5-1 MNGP Gross Beta 0.010 0.021 +/- 0.003 0.024 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.003 0.018 +/- 0.003 0.027 +/- 0.003 0.039 +/- 0.004 0.024 +/- 0.003 0.044 +/- 0.004 0.030 +/- 0.003 0.037 +/- 0.004 0.027 +/- 0.003 0.044 +/- 0.004 0.029 +/- 0.009 0.026 +/- 0.003 0.040 +/- 0.004 0.033 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.004 0.038 +/- 0.004 0.039 +/- 0.004 0.024 +/- 0.003 0.050 +/- 0.004 0.068 +/- 0.005 0.022 +/- 0.003 0.051 +/- 0.005 0.054 +/- 0.004 0.039 +/- 0.013 0.031 0.028 Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131

a. Location:

M-5 Units: pCi/m 3 Collection:

Continuous, weekly exchange.

Date Volume Collected (m") Gross Beta Required LLD 0.010 01-07-15 323 0.046 +/- 0.004 01-14-15 324 0.042 +/- 0.004 01-21-15 323 0.038 +/- 0.004 01-28-15 NOb 02-04-15 356 0.031 +/- 0.003 02-11-15 352 0.038 +/- 0.004 02-18-15 294 0.054 +/- 0.005 02-25-15 324 0.071 +/- 0.005 03-04-15 351 0.034 +/- 0.004 03-11-15 352 0.023 +/- 0.003 03-18-15 326 0.024 +/- 0.004 03-25-15 292 0.030 +/- 0.004 04-01-15 352 0.018 +/- 0.003 1st Quarter Mean+/- s.d. 0.038 +/- 0.015 04-08-15 298 0.024 +/- 0.004 04-15-15 291 0.027 +/- 0.004 04-22-15 324 0.016 +/- 0.003 04-29-15 326 0.022 +/- 0.003 05-06-15 384 0.022 +/- 0.003 05-13-15 381 0.009 +/- 0.002 05-20-15 387 0.011 +/- 0.002 05-27-15 378 0.016 +/- 0.003 06-03-15 382 0.019 +/- 0.003 06-10-15 382 0.017 +/- 0.003 06-17-15 380 0.012 +/- 0.002 06-24-15 353 0.020 +/- 0.003 07-01-15 368 0.019 +/- 0.003 2nd Quarter Mean +/- s.d. 0.018 +/- 0.005 Date Volume Collected (m") 07-08-15 370 07-15-15 370 07-22-15 352 07-29-15 351 08-05-15 382 08-12-15 341 08-19-15 352 08-26-15 324 09-02-15 326 09-09-15 271 09-16-15 301 09-23-15 325 09-30-15 298 3rd Quarter Mean +/- s.d. 10-07-15 298 10-14-15 298 10-21-15 297 10-28-15 326 11-04-15 359 11-11-15 367 11-18-15 252 11-25-15 354 12-02-15 323 12-09-15 323 12-16-15 353 12-23-15 295 12-30-15 352 4th Quarter Mean +/- s.d. Cumulative Average Previous Annual Average a lodine-131 concentrations are< 0.03 pCi/m 3 unless otherwise noted. b "NO"= No data, see Table 2.0, Listing of Missed Samples. 6-1 MNGP Gross Beta 0.010 0.023 +/- 0.003 0.021 +/- 0.003 0.019 +/- 0.003 0.027 +/- 0.003 0.021 +/- 0.003 0.024 +/- 0.003 0.032 +/- 0.004 0.022 +/- 0.003 0.047 +/- 0.004 0.037 +/- 0.004 0.035 +/- 0.004 0.028 +/- 0.004 0.045 +/- 0.005 0.029 +/- 0.009 0.025 +/- 0.004 0.039 +/- 0.004 0.036 +/- 0.004 0.025 +/- 0.004 0.029 +/- 0.003 0.043 +/- 0.004 0.032 +/- 0.005 0.025 +/- 0.003 0.050 +/- 0.005 0.088 +/- 0.006 0.015 +/- 0.003 0.048 +/- 0.005 0.050 +/- 0.004 0.039 +/- 0.018 0.031 0.031 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.

Activity (pCi/m 3) 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 Volume(m 3) 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 Volume(m 3) 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.

Activity (pCilm 3) Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-3 Lab Code MAP-1844 MAP-3821 MAP-6032 MAP-7412 Volume(m 3) 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 Volume(m 3) 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.

Activity (pCi/m 3) Cumulative Previous 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Average Average M-5 Lab Code MAP-1846 MAP-3824 MAP-6034 MAP-7414 Volume(m 3) 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 Period Collected November December b 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 Table 12. River water and drinking water, analysis of quarterly composites for tritium. Collection:

Quarterly composites of weekly collections.

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

Water frozen remainder of quarter. b Water frozen 12-30-15.

12-1 < 152 < 154 < 152 < 146 < 151 < 165 < 152 < 154 < 152 < 146 < 151 < 157 < 152 < 154 < 152 < 146 < 151 < 157 MNGP MNGP Table 13. Well water, analysis for tritium and gamma-emitting isotopes.

Sample Description and Concentration (pCi/L) Date Collected 1/21/2015 4/15/2015 7/22/2015 10/21/2015 Lab Code MWW-240 MWW-1703 MWW-4031 MWW-5964 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/22/2015 MWW-241 MWW-1704 MWW-4032 MWW-6097 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/21/2015 MWW-242 MWW-1705 MWW-4034 MWW-5965 Cumulative Averages 1/21/2015 4/15/2015 7/22/2015 10/21/2015 MWW-243 MWW-1706 MWW-4035 MWW-5967 Cumulative Averages H-3 (< 500 pCi/L) < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 < 182 < 152 < 147 < 149 < 500 a> lO <h l1.. Q) lO ' 0 0 Monticello (M-11) 0 <D ' 0 0 lO (l) ' c N lO a> ' .0 z ('-. C0 .,.... ' U) 0 < 10 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 45 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 29 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 34 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 26 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 45 Plant Well No. 1 (M-12) < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 31 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 21 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 35 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 2 8 < 10 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 35 Hasbrouck (M-55) < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 38 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 21 < 1 0 < 30 < 1 0 < 1 0 < 30 < 1 5 < 1 0 < 1 0 < 15 < 38 < 1 0 < 30 < 1 0 < 10 < 30 < 15 < 1 0 < 1 0 < 15 < 28 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 38 lmholte (M-43C) < 1 0 < 30 < 1 0 < 1 0 < 1 0 *< 30 < 1 0 < 1 0 < 1 0 < 30 < 1 0 < 1 0 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 30 < 15 < 30 < 15 < 30 < 15 < 1 0 < 1 0 < 15 < 36 < 1 0 < 1 0 < 15 < 39 < 1 0 < 1 0 < 15 < 49 <10 <10 <15 <17 < 1 0 < 30 < 1 0 < 1 0 < 30 < 15 < 1 0 < 1 0 < 15 < 49 13-1 Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCi!g wet) Upstream 1 000' M-8 (C) Date Collected 05-26-15 05-26-15 09-22-15 Lab Code MF-2724 MF-2725 MF-5239 Sample Type Shorthead Smallmouth Shorthead Red horse Bass Red horse K-40 2.56 +/- 0.35 3.46 +/- 0.44 3.58 +/- 0.42 Mn-54 < 0.013 < 0.017 < 0.017 Fe-59 < 0.043 < 0.041 < 0.031 Co-58 < 0.016 < 0.018 < 0.017 Co-60 < 0.012 < 0.018 < 0.011 Zn-65 < 0.029 < 0.026 < 0.018 Nb-95 < 0.022 < 0.031 < 0.027 Zr-95 < 0.024 < 0.025 < 0.043 Cs-134 < 0.015 < 0.016 < 0.014 Cs-137 < 0.015 < 0.018 < 0.011 Ba-La-140

< 0.045 < 0.035 < 0.045 Ce-144 < 0.130 < 0.127 < 0.105 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 09-22-15 MF-5240 Smallmouth Bass 3.65 +/- 0.46 < 0.016 < 0.056 < 0.019 < 0.010 < 0.033 < 0.030 < 0.043 < 0.020 < 0.017 < 0.073 < 0.119 MNGP Table 14. Fish, analysis of edible portions for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCi!g wet) Date Collected Lab Code Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 Ce-144 Date Collected Lab Code Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-La-140 Ce-144 05-26-15 MF-2726 Shorthead Red horse 3.08 +/- 0.45 < 0.016 < 0.043 < 0.020 < 0.014 < 0.029 < 0.021 < 0.031 < 0.018 < 0.014 < 0.031 < 0.102 Cumulative Average 3.39 < 0.025 < 0.046 < 0.025 < 0.025 < 0.070 < 0.030 < 0.058 < 0.025 < 0.020 < 0.122 < 0.141 Downstream 1 000' M-9 05-26-15 09-22-15 MF-2727 MF-5241 Smallmouth Shorthead Bass Red horse 3.20 +/- 0.64 3.56 +/- 0.42 < 0.025 < 0.015 < 0.019 < 0.046 < 0.025 < 0.013 < 0.025 < 0.013 < 0.070 < 0.031 < 0.030 < 0.018 < 0.058 < 0.039 < 0.025 < 0.014 < 0.020 < 0.010 < 0.122 < 0.057 < 0.141 < 0.108 Previous Average 3.03 < 0.018 < 0.059 < 0.028 < 0.021 < 0.035 < 0.043 < 0.046 < 0.020 < 0.017 < 0.217 < 0.126 14-2 MNGP 09-22-15 MF-5242 Smallmouth Bass 3.71 +/- 0.43 < 0.015 < 0.033 < 0.021 < 0.008 < 0.050 < 0.029 < 0.032 < 0.017 < 0.017 < 0.056 < 0.068 MNGP Table 15. Aquatic invertebrates, analysis for gamma-emitting isotopes.

Collection:

Semiannually Sample Description and Concentration (pCilg wet) Cumulative Previous Average Average Upstream 1 000' 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 1 000' 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 1 000' 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 1 000' 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 Table 16. Shoreline (SS) sediments, analysis for gamma-emitting isotopes (continued).

Sample Description and Concentration (pCi/g dry) Cumulative 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 K-40 9.49 +/- 0.51 10.54 +/- 0.54 10.01 Mn-54 < 0.021 < 0.018 < 0.021 Fe-59 < 0.068 < 0.050 < 0.068 Co-58 < 0.022 < 0.019 < 0.022 Co-60 < 0.014 < 0.011 < 0.014 Zn-65 < 0.041 < 0.038 <0.041 Nb-95 < 0.031 < 0.028 < 0.031 Zr-95 < 0.046 < 0.026 < 0.046 Ru-103 < 0.041 < 0.016 <0.041 Ru-106 < 0.13 < 0.13 < 0.13 Cs-134 < 0.014 < 0.016 < 0.016 Cs-137 < 0.017 < 0.021 < 0.021 Ba-La-140

< 0.20 < 0.11 < 0.20 Ce-144 < 0.11 < 0.11 < 0.11 16-2 MNGP Previous Average < 0.22 10.89 < 0.017 < 0.040 < 0.017 < 0.013 < 0.045 < 0.025 < 0.039 < 0.026 < 0.102 < 0.014 0.059 < 0.092 < 0.088