Text

Duane Arnold - Annual Radiological Environmental Operating Report January 1 to December 31, 2015
	ML16138A173
Person / Time
Site:	Duane Arnold
Issue date:	05/12/2016
From:	; ATI Environmental
To:	; NextEra Energy Duane Arnold, Office of Nuclear Reactor Regulation
References
	NG-16-0110, Project 8001
	Download: ML16138A173 (59)
	v • d • e

All Environmental, Inc * .,."" l'"\I Midwest Laboratory 700 Landwehr Road

Northbrook, IL 60062-2310 phone (847) 56Hl700. lax (847)

DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 REPORT to the UNITED STATES NUCLEAR REGULA TORY COMMISSION Annual Radiological Environmental Operating Report January 1 to December 31, 2015 Prepared by ATI ENVIRONMENTAL, Inc. Midwest Laboratory Project No. 8001 PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report, with the exception of Appendices D and E which were completed by DAEC personnel.

All environmental samples, with the exception of aquatic, were collected by personnel of DAEC. Aquatic samples were collected by the University of Iowa Hygienic Laboratory.

The report was prepared by Environmental, Inc., Midwest Laboratory, with the exception of Appendices D and E, which were prepared by DAEC personnel.

ii TABLE OF CONTENTS PARTI No. PREFACE .....................................................................................................................

ii List of Tables .................................................................................................................

v List of Figures ...............................................................................................................

vi

1.0 INTRODUCTION

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

1 2.0

SUMMARY

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

2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ...............................

3 3.1 Program Design and Data Interpretation

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

3 3.2 Program Description

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

.4 3.2.1 Environmental Monitoring

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

.4 3.2.2 Ground Water Protection Program ......................................................................

5 3.3 Program Execution

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

5 3.4 Laboratory Procedures

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

6 3.5 Program Modifications

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

6 4.0 RE SUL TS AND DISCUSSION

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

7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents

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

7 4.2 Program Findings ...................................................................................................

7 5.0 TABLES AND FIGURES .............................................................................................

10

6.0 REFERENCES

CITED ................................................................................................

25 APPENDICES A lnterlaboratory Comparison Program Results ..........................................................

A-1 B Data Reporting Conventions

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

B-1 C Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas .....................................................................

C-1 D Summary of the Land Use Census ..........................................................................

D-1 E Annual Radiation Dose Assessment

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

E-1 iii TABLE OF CONTENTS (continued)

PARTll Data Tabulations and Analyses ......................................................................................

i iv LIST OF TABLES 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic Analyses .........................................................................................................

11 5.2 Sample Collection and Analysis Program ...................................................................

12 5.3 Sampling Locations, DAEC .........................................................................................

14 5.4 Type and Frequency of Collections

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

16 5.5 Sample Codes for Tables 5.4 and 5.6 .........................................................................

17 5.6 Program Deviations

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

18 5. 7 Radiological Environmental Monitoring Program Summary ......................................

19 In addition, the following tables are included in the Appendices:

Appendix A A-0 Attachment A. ...........................................................................................................

A0-2 A-1 Environmental Resource Associates (RAD) ............................................................

A 1-1 A-2 lnterlaboratory Comparison Program Results, Thermoluminescent Dosimeters (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 Resource Associates (MRAD) .........................................................

A7-1 Appendix C C-1 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas ..............................................................

C-2 v LIST OF FIGURES 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center .........................................................................

23 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles .........................................................................................................

24 vi

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, 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.

The REMP fulfills the requirements of Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant. The REMP also fulfills the requirements of 10 CFR 72.44( d)(2) for operation of the ISFSI. Tabulations of individual analyses made during the year are included in Part II of this report. The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in Linn County, Iowa, on the Cedar River, and owned and operated by NextEra Energy Resources.

Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975. 1 2.0

SUMMARY

The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described.

Results for the year 2015 are summarized and discussed.

Program findings show only background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center. No effect on the environment is indicated in the areas surrounding the site of the Duane Arnold Energy Center. 2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) is to assess the impact of the plant on its environment.

For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters

{TLDs). Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; and (4) Industrial and medical radioactive waste. In interpreting the data, effects due to the DAEC operation 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 DAEC 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 station effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location.

The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources. An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified:

zirconium-95, cesium-137, and cerium-144.

These 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 ten (10) days after reactor shutdown.

On the other hand, ten (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). The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.

These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products.

They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations.

Nuclides of the final group, beryllium-7, which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and provide a comparison between levels of naturally occurring radionuclides and radionuclides that could be attributed to the operation of the plant. Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational.

Results of the DAEC'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 3.2 Program Description 3.2.1 Environmental Monitoring The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5. To monitor the air environment, a continuous air sampler is employed.

Airborne particulates and activated charcoal canisters are mounted on the intake of the air sampler to collect airborne particulates and airborne iodine respectively.

2015 began with nine sampling locations.

Eight of the nine locations are indicators and one is a control (D-13). Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity.

If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed.

Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes.

Charcoal canister samples are analyzed weekly for iodine-131.

Ambient gamma radiation is monitored at a total of 50 locations.

A TLD is placed at each location and exchanged and analyzed quarterly.

The TLD locations are distributed as follows:

Two on-site locations

Eighteen in a circle within a 0.5 mi. radius from the DAEC stack.

Six in 22.5° sectors within 1 mi. from the DAEC stack.

Ten in 22.5° sectors between 1 and 3 miles from the DAEC stack.

Ten control locations greater than 3 miles from the DAEC stack.

Four along sections of the Independent Spent Fuel Storage Installation (ISFSI) fenceline.

Surface water is collected monthly from four river locations, D-49 (Lewis Access, Control, 4 mi. upstream), D-50 (Inlet), D-51 (Discharge) and D-61 (downstream of Discharge) and also from Pleasant Creek Lake (D-99). The monthly samples are analyzed for tritium and gamma-emitting isotopes.

Additional analyses are performed on samples collected from the control and indicator loc,ations, D-49 and D-61. Analyses for low-level iodine-131 are performed on monthly collections and quarterly composites are prepared and analyzed for strontium-89 and strontium-90.

The aquatic environment .is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish. River bottom sediment is collected semiannually at the plant's intake and discharge (D-50 and D-51) and the site's north drainage ditch (D-107a).

The samples are analyzed for gamma-emitting isotopes.

Potable ground water is collected quarterly from a treated municipal water system (D-53), the inlet to the municipal water treatment system (D-54), three indicator locations (D-55, D-57, D-58) and one control location (D-72). The samples are analyzed for tritium and gamma emitting isotopes.

Any positive identification of a reactor by-product material initiates analyses for hard to detect isotopes of Ni-63, Sr-89, Sr-90, Fe-55 and gross alpha. Beginning in the fourth quarter of 2014 all samples were analyzed to a lower MDA of 2 pCi/L for 1-131. Milk is collected monthly from one indicator and one control location during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September

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

For additional monitoring of the terrestrial environment, grain, hay, grass and broadleaf vegetation samples are collected annually, as available, from nine locations:

one control (D-138) and eight indicators (D-16, D-57, D-96, D-109, D-110 and D-118). Grain, hay and broadleaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least two broad leaf vegetation samples are analyzed for iodine-131.

If any of the cattle grazing on-site are slaughtered for home use, a meat sample is collected.

The sample is analyzed for gamma-emitting isotopes.

4 3.2.2 Ground Water Protection Program Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program. For results from these analyses, refer to the Duane Arnold Energy Center, 2015 Annual Radioactive Material Release Report. 3.3 Program Execution The program was executed as described in the preceding section with the following exceptions:

(1) Airborne Particulates I Airborne Iodine: No air particulate I air iodine sample available at location D-5, after 04/1/2015 due to D-5 air sampler power permanently removed by local utility. D-5 sampler suspended from ODAM as active air sampler location.

No air particulate I air iodine sample at location D-13, for the week ending 05/01/15 due to power outage at the sampler. No air particulate I air iodine sample at location D-13, for the week ending 06/25/15 due to power outage at the sample. (2) Thermoluminescent Dosimetry The second quarter, 2015 TLD at location D-39 was missing in the field. The TLD was replaced.

Whereabouts of missing D-39 and cause for loss are unknown; potentially due to theft or vandalism.

(3) Vegetation Annual vegetation samples were not readily available from locations D-96 and D-109 for 2015 due to harvesting of crops prior to scheduled sample collection.

(4) Surface Water Surface water was not available at locations D-49, D-50 and D-99 for the 1/19/15 collections due to frozen water conditions.

Surface water was not available at locations D-50 and D-99 for the 2/18/15 collections due to frozen water conditions.

Surface water was not sent for the expected collection date of 10/31/15.

CE02088659 documents deviation to work order and auditing performance gaps. (5) Well Water Well water for locations D-53, D-54, D-55, D-57, D-58 and D-72(C) was analyzed late for 1-131 resulting in a failure to reach the required LLD. Due to short half-life of 1-131 and sampling/shipping constraints, samples arrived too late for effective 1-131 analysis.

5 3.4 Laboratory Procedures The lodine-131 analyses in milk and water were made using a sensitive radiochemical procedure involving separation of iodine using an ion-exchange method, solvent extraction and subsequent beta counting.

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

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

The gamma isotopic analysis provides a spectrum with an energy range from 80 to 2048 KeV. Specific isotopes included in the gamma library are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as Be-7, K-40 and Ra daughters, are frequently detected but may not be listed. Tritium was measured by liquid scintillation spectrometry.

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, 2014). The QA Program includes participation in lnterlaboratory Comparison (crosscheck)

Programs.

Results obtained in crosscheck programs are presented in Appendix A. 3.5 Program Modifications There were several changes to the REMP program in 2015. Analyses for low level 1-131 on quarterly REMP well water samples were added. Vegetation sampling was removed from locations 58 and 72. Additionally, the requirement to analyze precipitation samples for gamma emitters was removed in 2015. 6 4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for those listed in Table 5.6. Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission.

For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range. Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion.

A complete tabulation of results for 2015 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center. 4.1 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. 4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected outside of the Owner Controlled Area in 2015. The trace levels of strontium-90 and cesium-137, still measurable in soil and sediments are attributed to deposition of fallout from previous decades. Airborne Particulates The average annual gross beta concentrations in airborne particulates were similar at indicator and control locations (0.027 and 0.024 pCi/m 3 , respectively) and similar to levels observed from 1995 through 2014. The results are tabulated below. Year Indicators Controls Year Indicators Controls Concentration (pCi/m 3) Concentration (pCi/m 3) 1999 0.026 0.027 2008 0.029 0.029 2000 0.026 0.027 2009 0.031 0.030 2001 0.026 0.026 2010 0.028 0.028 2002 0.027 0.027 2011 0.030 0.029 2003 0.029 0.029 2012 0.030 0.029 2004 0.028 0.028 2013 0.028 0.025 2005 0.031 0.031 2014 0.026 0.025 2006 0.029 0.027 2015 0.027 0.024 2007 0.031 0.031 Average annual gross beta concentrations in airborne particulates.

7 4.2 Program Findings.

Airborne Particulates (continued)

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.

Beryllium-7, produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples, with an average activity of 0.040 pCi/m3 for indicator locations and 0.059 pCi/m3 for the control location.

No reactor by-product radionuclides were identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. Airborne Iodine 3 Levels of airborne iodine-131 measured below the required limit of 0.030 pCi/m with the exception of two samples collected at location D-13 for the weeks ending 4/23/15 and 06/17/15 and one sample at location D-15 for the week ending 5/21/15. The failure to reach the LLD was due to reduced sample volume as a result of power failures to the air sampling pumps. Ambient Radiation (TLDs) At ten control locations, thermoluminescent dosimeter (TLD) readings averaged 15.9 mR/quarter.

At locations within a half mile, one mile and three mile radius of the stack, the measurements averaged 18.4, 18.5 and 15.5 mR/quarter, respectively.

The two on-site locations D-15 and D-16 averaged 16.7 and 14.2 mR/quarter respectively.

These average measurements are similar to the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975). The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and averages 11.5 mrad/quarter for Middle America.

Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter.

No plant effect is indicated.

ISFSI Facility Operations Monitoring Four TLDs, placed directionally along the ISFSI fenceline, averaged 32.8 mR/quarter.

The TLD site D-30, located between the nearest residence and the ISFSI site averaged 19.3 mR/quarter.

Calculated dose rates indicate the site is in compliance with 10 CFR 72.104 and 40 CFR 190. lodine-131 concentrations in milk samples were less than the LLD level of 0.5 pCi/L. No gamma-emitting isotopes, excepting naturally occurring potassium-40, were detected in any milk samples. This is consistent with findings that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968). No reactor by-product radionuclides were identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. Ground Water (potable)

Tritium concentrations in ground water samples were less than the LLD of 147 pCi/L in all samples analyzed.

Gamma-emitting isotopes were below detection limits. No reactor by-product radionuclides could be identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. 8 4.2 Program Findings (continued)

Vegetation lodine-131 concentrations in vegetation samples were less than the LLD level of 0.03 pCi/g wet weight in all samples analyzed.

With the exception of potassium-40, which was observed in all vegetation samples, all other gamma-emitting isotopes were below detection limits. No reactor by-product radionuclides were identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. Surface Water Surface water was tested for tritium and gamma emitting isotopes in fifty samples from five locations.

No measurable tritium activity was detected above an LLD of 173 pCi/L. Analyses for 1-131 were performed on samples from locations D-49 (control) and D-61 (0.5 mi. downstream, indicator).

No measurable 1-131 was detected above an LLD of 0.5 pCi/L. Quarterly composites were also prepared from the samples collected at locations D-49 and D-61 and tested for and strontium-90.

All samples tested below detection limits. No plant effect on surface water is indicated.

Fish were collected in May and September, 2015, and analyzed for gamma-emitting isotopes.

With the exception of naturally-occurring potassium-40, no gamma-emitting isotopes were identified in edible portions of fish. The potassium-40 level was similar at both the indicator and control locations (3.30 and 3.43 pCi/g wet, respectively).

No reactor by-product radionuclides were identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. River Sediments Seven river sediments were collected in 2015 during the months of June, August and November, and analyzed for gamma-emitting isotopes.

Potassium-40 activity ranged from 3.32 to 7.80 pCi/g dry weight and averaged 6.29 pCi/ g dry weight at the indicator locations and 7.58 pCi/g dry weight at the control location.

No reactor by-product radionuclides were identified.

All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual. Ground Water Protection Program Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program. For results from these analyses, refer to the Duane Arnold Energy Center, 2015 Annual Radioactive Material Release Report. 9 5.0 TABLES AND FIGURES 10 Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.

Designation Comment Isotope Half-life a Naturally Occurring A. Cosmogenic Produced by interaction of cosmic rays Be-7 53.2 d with atmosphere B. Terrestrial Primordial K-40 1.26x10 9 y II. Fission Products b Nuclear accidents and detonations constitute the major environmental source. A. Short-lived 1-131 8.04 d Ba-140 12.8 d B. Other than Short-lived Nb-95 35.15 d Zr-95 65 d Ru-103 39.35 d Ru-106 368.2 d Cs-134 2.061 y Cs-137 30.174y Ce-141 32.5 d Ce-144 284.31 d Ill. Activation Products Typically found in nuclear power plant Mn-54 312.5 d effluents Fe-59 45.0 d Co-58 70.78 d Co-60 5.26 y Zn-65 245 d Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, EML-334 (U. S. Department of Energy, 1978). Includes fission-product daughters.

11 Table 5.2 Sample collection and analysis program. Exposure Sample Pathway and/or Point Sample Type Airborne Particulates Airborne Iodine 3 5 6 7 11 13 15 16 40 3 5 6 7 11 13 15 16 40 Description Hiawatha Paloc Center Point Shellsburg Todd ville Alburnett (C) On-site North On-site South Wickiup Hill Hiawatha Paloc Center Point Shellsburg Toddville Alburnett (C) On-site North On-site South Wickiup Hill Sampling Location a Sampling and Collection Frequency Continuous operation of sampler with sample collection at least once per week or as required by dust loading Continuous operation of sampler with sample collection at least once per week. Type and Frequency of Analysis b Analyze for gross beta activity more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after filter change. Perform gamma isotopic analysis on each sample having gross beta activity greater than ten times the yearly mean of the control samples. Composite weekly samples to form a quarterly composite (by location).

Analyze quarterly composite for gamma isotopic.

Analyze each cartridge for iodine-131.

Ambient Radiation 1-3, 5-8 (Controls)

One dosimeter continuously Read gamma radiation dose Surface Water 10, 11, 13 (Indicators) 15-23, 28-32, Within 0.5 mile of Stack 33-42 Within 3.0 miles of Stack 43-48 Within 1.0 mile of 82-86, 91 Stack 161-164 ISFSI Fence line at each location.

quarterly.

Dosimeters are changed at least quarterly.

49 Lewis Access (C) Once per month. 50 Plant Intake Gamma isotopic and tritium analysis for each sample (by location).

51 Plant Discharge 61 -% mi. downstream from Plant Discharge 99 Pleasant Creek Lake 12 Locations 49 and 61, analyses for low-level 1-131. Quarterly composites for Sr-89, Sr-90.

Table 5.2 Sample collection and analysis program, (continued).

Sampling Location a Exposure Sample Description Sampling and Collection Type and Frequency Pathway and/or Point Frequency of Analysis b Sample Type Ground 53 Treated Municipal Grab sample at least Analysis gamma emitting Water 54 Water once per quarter isotopes, iodine-131 and tritium on Inlet to Municipal Wate quarterly samples. 55 Treatment System 57,58 On-site well If reactor by-product gamma 72 (C) Wells off-site and emitters are identified, or if tritium within 4 km of DAEC concentrations measure > MDA, then analyze for Ni-63, Sr-89, Sr-90 and alpha emitters.

River 50 Plant Intake (C) At least once every six Gamma isotopic analysis of each Sediment 51 Plant Discharge months. sample 107a North Drainage Ditch (on-site)

Vegetation 16,57 Farms raising food Annually at harvest Gamma isotopic analysis, 96,109 crops time. Two samples of including iodine-131, on each 110,118 each: grain, green leafy, sample. and forage. 138 (C) Fish 49 Cedar River upstream One sample per 6 Gamma isotopic analysis on of DAEC not months (once during edible portions.

influenced by effluent January through June (C) and once during July 61 through December).

Downstream of DAEC in influence of effluent d 138 (C) Farm near Newhall, IA At least once per two During the grazing season: Milk weeks during the Gamma isotopic and iodine-131 110 Dairy Farm within 7.8 grazing season. analyses of each sample. miles from Site At least once per month During the non-grazing season: during the non-grazing Gamma isotopic and iodine-131 season. analyses of each sample. a (C) denotes control location.

All other locations are indicators.

b Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis.

0 Sample not available after April 1, 2015. d The grazing season is considered to be May 1 through September

30. 13 Table 5.3 Sampling locations, Duane Arnold Energy Center. Sampling Location Code Location Description Distance and Direction from Site Stack D-1 Cedar Rapids 20,800 meters SE D-2 Marion 16,900 meters ESE D-3 Hiawatha 10,800 meters SE D-5 Palo 4,500 meters SSW D-6 Center Point 9,660 meters N D-7 Shellsburg 7,950 meters W D-8 Urbana 15,000 meters NNW D-10 Atkins 13,600 meters SSW D-11 Toddville 4,980 meters E D-13 Alburnett 14,500 meters ENE D-15 On-site, North-Northwest 1,050 meters NNW D-16 On-site, South-Southeast 520 meters SSE D-17 On-site, N 1,050 meters N D-18 On-site, NNE 630 meters NNE D-19 On-site, NE 590 meters NE D-20 On-site, ENE 550 meters ENE D-21 On-site, ENE 515 meters ENE D-22 On-site, ESE 535 meters ESE D-23 On-site, SE 490 meters SE D-28 On-site, WSW 730 meters WSW D-29 On-site, W 630 meters W D-30 On-site, WNW 640 meters WNW D-31 On-site, NW 1,020 meters NW D-32 On-site, NNW 1,110 meters NNW D-33 3 mile ring 4,340 meters N D-34 3 mile ring 3,930 meters NNE D-35 3 mile ring 2,800 meters NE D-36 3 mile ring 3,500 meters ENE D-37 3 mile ring 2,960 meters E D-38 3 mile ring 3, 180 meters ESE D-39 3 mile ring 2,510 meters SE D-40 3 mile ring 2,430 meters SSE D-41 3 mile ring 5,680 meters S D-42 3 mile ring 4,380 meters SSE D-43 1 mile ring 1,590 meters SSW D-44 1 mile ring 1,580 meters WSW D-45 1 mile ring 1,420 meters W D-46 1 mile ring 1,580 meters WNW D-47 1 mile ring 1, 760 meters NW D-48 1 mile ring 1,680 meters NNW 14 Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).

Sampling Location Code Location Description Distance and Direction from Site Stack D-49 Lewis Access, upstream of DAEC 6,750 meters NNW D-50 Plant Intake 560 meters SE D-51 Plant Dischan:ie 600 meters SE D-53 Treated Municipal Water 13,900 meters SE D-54 Inlet, Municipal Water Treatment System 13,900 meters SE D-55 Production Well D-57 Farm (Off-site Well) 805 meters W D-58 Farm (Off-site Well) 97 4 meters WSW-SW D-61 Downstream of plant discharae 670 meters SSE D-72 Farm 3,200 meters SSW D-82 On-site, SSE 660 meters SSE D-83 On-site, SSE 620 meters SSE D-84 On-site, S 610 meters S D-85 On-site, SSW 660 meters SSW D-86 On-site, SW 850 meters SW D-91 On-site, NNW 1,090 meters NNW D-96 Farm 11,400 meters SSW D-99 Pleasant Creek Lake 3,880 meters WNW D-107a North DrainaQe Ditch D-109 Farm 5,890 meters SW D-110 Farm 12,700 meters SW D-118 Farm 2,230 meters NW D-138 Farm 21,600 meters WSW D-161 ISFSI Fence East On-site D-162 ISFSI Fence South On-site D-163 ISFSI Fence West On-site D-164 ISFSI Fence North On-site 15 Table 5.4 Type and Frequency of collection.

Location Weekly Monthly Quarterly Semiannually Annually 0-1 TLO 0-2 TLO 0-3 AP,AI TLD 0-5 AP,AI TLD 0-6 AP,AI TLD 0-7 AP,AI TLO 0-8 TLO 0-10 TLO 0-11 AP,AI TLO 0-13 AP,AI TLO 0-15 AP,AI TLD 0-16 AP,AI TLO G 0-17 to 0-23 TLO 0-28 to 0-39 TLO 0-40 AP,AI TLO 0-41 to 0-48 TLO 0-49 SW F 0-50 SW BS 0-51 SW BS 0-53 WW 0-54 WW 0-55 WW 0-57 WW G 0-58 WW 0-61 SW F 0-72 WW 0-82 to 0-86 TLO 0-91 TLO 0-96 G 0-99 SW 0-107A BS 0-109 G 0-110 Ml* 0-118 G 0-138 Ml* G 0-161 to 0-164 TLO On-site

Biweekly during the grazing season. 16 Table 5.5. Sample codes used in Table 5.4 and Table 5.6. Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter Ml Milk WW Well Water G Vegetation ME Meat SW Surface Water F Fish BS River Sediment 17 Table 5.6. Program Deviations, Duane Arnold Energy Center. Sample Collection Date Type Analysis Location(s) or Period Comments SW H-3/ 1-131/ Gamma D-49 01-19-15 Water frozen. SW H-3/Gamma D-50 01-19-15 Water frozen. SW H-3 /Gamma D-99 01-19-15 Water frozen. SW H-3/Gamma D-50 02-18-15 Water frozen. SW H-3/ Gamma D-99 2-18-15 Water frozen. No power to D-5 air sampler due to AP/Al Gross Beta/ 1-131 D-5 04-10-15 permanent loss of power when local utility disconnected power to source utility pole. No power to D-5 air sampler due to AP/Al Gross Beta/ 1-131 D-5 04-17-15 permanent loss of power when local utility disconnected power to source utility pole. AP/Al Gross Beta/ 1-131 D-13 05-01-15 No power to sampler. AP/Al Gross Beta/ 1-131 D-13 06-25-15 No power to sampler. AP/Al Gross Beta/ 1-131 D-15 07-11-14 Low volume due to power outage. TLD Ambient Gamma D-39 07-14-15 Missing in field potentially due to theft or vandalism.

SW H-3/ 1-131/Gamma D-49 10-31-15 CE02088659 documents missed sample. Sample required per ODAM 6.3.2 SW H-3/Gamma D-50 10-31-15 CE02088659 documents missed sample. Sample required per ODAM 6.3.2 SW H-3/Gamma D-51 10-31-15 CE02088659 documents missed sample. Sample required per ODAM 6.3.2 SW H-3/1-131/Gamma D-61 10-31-15 CE02088659 documents missed sample. Sample required per ODAM 6.3.2 SW Gamma D-99 10-31-15 CE02088659 documents missed sample. Sample required per ODAM 6.3.2 18 Table 5.7 Radiological Environmental Monitoring Program Summary. Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses a Airborne GB 427 Particulates (pCi/m 3) GS 33 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Airborne Iodine 1-131 427 (pCi/m 3) TLDs (mR/quarter)

Control Locations Gamma 40 Within 0.5 mi. Gamma 80 of Stack Within 1.0 mi. Gamma 24 of Stack Within 3.0 mi. Gamma 39 of Stack ISFSI border Gamma 16 Duane Arnold Energy Center Docket No. 50-331 Linn, Iowa Reporting Period January-December, 2015 (County, State) Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLD b Mean (F) 0 Mean (F) 0 Mean (F) 0 Routine Range 0 Location d Range 0 Range 0 Results 0 Airborne Pathway 0.003 0.027 (377/377)

D-50 0.031 (13/13) 0.024 (50/50) 0 (0.001-0.142)

Plant Intake (0.018-0.054)

(0.008-0.058) 0.020 0.040 (29/29) D-50 0.067 (1/1) 0.059 (4/4) 0 (0.044-0.090)

Plant Intake (0. 067-0. 067) (0.051-0.068) 0.0690 <LLD <LLD 0 0.0023 <LLD <LLD 0 0.0043 <LLD <LLD 0 0.0012 <LLD <LLD 0 0.0015 <LLD <LLD 0 0.0034 <LLD <LLD 0 0.0022 <LLD <LLD 0 0.0022 <LLD <LLD 0 0.0093 <LLD <LLD 0 0.0106 <LLD <LLD 0 0.0013 <LLD <LLD 0 0.0024 <LLD <LLD 0 0.0054 <LLD <LLD 0 0.030 <LLD <LLD 0 Direct Radiation 1.0 None D-8,Urbana 17.5 (4/4) 15.9 (40/40) 0 10 mi. NW (15.6-20.5)

(11.1-21.1) 1.0 18.4 (80/80) D-29,0n-site 23.4 (4/4) None 0 (10.5-26.

7) 0.5mi. W (20-26.7) 1.0 18.5 (24/24) D-47 20.7 (4/4) None 0 (12.1-24.6) 1760 m NW (17-23.5) 1.0 15.5 (39/39) D-41, 18.2 (3/4) None 0 (9.7-25.2) 3.5 mi. S (16-25.2) 1.0 32.8 (16/16) D-161 50.5 (4/4) None 0 (12.7-56.8)

ISFSI Fence (43.1-56.8) 19 Table 5.7 Radiological Environmental Monitoring Program Summary. Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses*

Duane Arnold Energy Center Linn, Iowa (County, State) Indicator Locations LLD b Mean (F) 0 Range 0 Docket No. 50-331 Reporting Period January-December, 2015 Location with Highest Control Number Annual Mean Locations Non-Mean (F) 0 Mean (F) 0 Routine Location d Range 0 Range 0 Results e Waterborne Pathway Surface Water H-3 50 173 <LLD --<LLD 0 (pCi/L) 1-131 21 0.5 <LLD --<LLD 0 -Sr-89 8 0.8 <LLD --<LLD 0 Sr-90 8 0.6 <LLD --<LLD 0 GS 50 Mn-54 4.3 <LLD --<LLD 0 Fe-59 7.7 <LLD --<LLD 0 Co-58 4.8 <LLD --<LLD 0 Co-60 3.7 <LLD --<LLD 0 Zn-65 8.9 <LLD --<LLD 0 Nb-95 4.4 <LLD --<LLD 0 Zr-95 8.1 <LLD --<LLD 0 1-131 9.8 <LLD --<LLD 0 Cs-134 5.1 <LLD --<LLD 0 Cs-137 5.1 <LLD --<LLD 0 Ba-140 25.9 <LLD --<LLD 0 La-140 5.2 <LLD --<LLD 0 Sediments GS 7 (pCi/g dry) K-40 1.0 6.29 (5/5) D-51, 7.75 (2/2) 7.58 (2/2) 0 (3.32-7.80)

Plant Discharge (7.70-7.80)

(7.52-7.65)

Mn-54 0.014 <LLD --<LLD 0 Fe-59 0.070 <LLD --<LLD 0 Co-58 0.022 <LLD --<LLD 0 Co-60 0.014 <LLD --<LLD 0 Zn-65 0.044 <LLD --<LLD 0 Nb-95 0.029 <LLD --<LLD 0 Zr-95 0.043 <LLD --<LLD 0 Ru-103 0.032 <LLD --<LLD 0 Ru-106 0.12 <LLD --<LLD 0 Cs-134 0.013 <LLD --<LLD 0 Cs-137 0.015 <LLD --<LLD 0 Ce-141 0.064 <LLD --<LLD 0 Ce-144 0.13 <LLD --<LLD 0 20 Table 5.7 Radiological Environmental Monitoring Program Summary. Name of Facility Location of Facility Sample Type and Type Number of (Units) Analyses a Ground Water, 1-131 1 potable (pCi/L) H-3 GS Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Milk 1-131 (pCi/L) GS K-40 Cs-134 Cs-137 Ba-140 La-140 Broadleaf GS Vegetation K-40 (pCi/g wet) Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ce-141 Ce-144 18 24 24 36 36 4 Duane Arnold Energy Center Docket No. 50-331 Linn, Iowa Reporting Period January-December, 2015 (County, State) Indicator Location with Highest Control Number Locations Annual Mean Locations Non-LLD b Mean (F) 0 Mean (F) 0 Mean (F) 0 Routine Range 0 Location d Range 0 Range 0 Results' Waterborne Pathway 0.5 <LLD --<LLD 0 --147 <LLD --<LLD 0 4.5 <LLD --<LLD 0 7.1 <LLD --<LLD 0 3.7 <LLD --<LLD 0 3.0 <LLD --<LLD 0 8.6 <LLD --<LLD 0 4.7 <LLD --<LLD 0 6.2 <LLD --<LLD 0 22.3 <LLD --<LLD 0 4.9 <LLD --<LLD 0 4.4 <LLD --<LLD 0 29.2 <LLD --<LLD 0 6.5 <LLD --<LLD 0 Ingestion Pathway 0.5 <LLD --<LLD 0 100 1412 (18/18) D-110, Farm 1412 (18/18) 1396 (18/18) 0 (1273-1631}

7.9 mi. SW (1273-1631) ( 1273-1552}

5 <LLD --<LLD 0 5 <LLD --<LLD 0 60 <LLD --<LLD 0 5 <LLD --<LLD 0 0.5 3.98 (4/4) D-57, Farm 3.69 (212) none 0 (2.10-5.27) 0.5miW (2.10-5.27)

<LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 <LLD --none 0 21 Table 5.7 Radiological Environmental Monitoring Program Summary. Duane Arnold Energy Center Docket No. 50-331 Name of Facility Location of Facility Linn, Iowa Reporting Period January-December, 2015 (County, State) Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Type Number of LLD b Mean (F) 0 Mean (F) 0 Mean (F) 0 (Units) Analyses a Range 0 Location d Range 0 Range 0 Ingestion Pathway (cont.) Vegetation GS 6 (Grain and Forage) K-40 0.5 8.93 (3/3) D-138, Farm 12.92 (3/3) 12.92 (3/3) (pCi/g wet) (2.62-13.98) 13.4 mi WSW (2.38-21.05)

(2.38-21.05)

Mn-54 <LLD --<LLD Fe-59 <LLD --<LLD Co-58 <LLD --<LLD Co-60 <LLD --<LLD Zn-65 <LLD --<LLD Nb-95 <LLD --<LLD Zr-95 <LLD --<LLD Ru-103 <LLD --<LLD Ru-106 <LLD --<LLD 1-131 <LLD --<LLD Cs-134 <LLD --<LLD Cs-137 <LLD --<LLD Ce-141 <LLD --<LLD Ce-144 <LLD --<LLD Fish GS 8 (pCi/g wet) K-40 1.0 3.30 (4/4) D-49, Upstream, 3.43 (4/4) 3.43 (4/4) (3.12-3.53) 4.0mi. NNW (3.25-3. 73) (3.25-3. 73) Mn-54 0.028 <LLD --<LLD Fe-59 0.055 <LLD --<LLD Co-58 0.024 <LLD --<LLD Co-60 0.017 <LLD --<LLD Zn-65 0.035 <LLD --<LLD Nb-95 0.048 <LLD --<LLD Zr-95 0.046 <LLD --<LLD Ru-103 0.046 <LLD --<LLD Ru-106 0.26 <LLD --<LLD Cs-134 0.026 <LLD --<LLD Cs-137 0.027 <LLD --<LLD Ce-141 0.058 <LLD --<LLD Ce-144 0.137 <LLD --<LLD

GB = Gross beta; GS = Gamma spectroscopy b LLD = Nominal lower limit of detection based on 4.66 sigma counting error for the background sample. 0 Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.

Non-routine results are those which exceed ten times the control station value for the location.

If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.

'Laboratory received 24 well water samples in 2015 but 6 samples were analyzed for 1-131 after 3 half-lives causing the results to fail to reach the required LLD and so are not included on this table. (see table 5.6 Program deviations) 22 Number Non-Routine Results e 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 0 Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center. + N I 51 58 .-------1

.CEDAR RNER I 0 I r----0 91 ---17 -1 I 32 I I I I I 31 I I I I 30 I I I I I 29 I I I is I [I] u -i 1 (t) -.. "" co 0 !!! ( 162 0 Q'. 0 w 55 L-----86 GATE 2000feet 19 See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

23 Figure 5.2. Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles. 110 ATKINS *10 99 10 MILE RADIUS CENTER PblNT eo0 DAEC SITE 109 72 PALO* 05 96 36 37 TODDVILLE 38 *11 CEDAR RAPIDS ALBURNETT

13. See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.

24

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-Salih.

1955. Beryllium-?

Produced by Cosmic Rays. Science 121: 451-453. Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275-276. Environmental, Inc., Midwest Laboratory.

2015 Study Plan, SP-DAEC-8001, revision 24 February 12, 2015, The Operational Radiological Environmental Monitoring Program for the Duane Arnold Energy Center, Cedar Rapids, Iowa 2001 through 2015. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report -Part II, Data Tabulations and Analyses, January -December, 2001 -2015. 1984 to 2000. (formerly Teledyne Brown Engineering, Environmental Services, Midwest Laboratory)

Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report -Part II, Data Tabulations and Analyses, January -December, 1983 -1999. ___ 1982 to 1984. (formerly Hazleton Environmental Sciences Corporation)

Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report -Part II, Data Tabulations and Analyses, January-December 1981 -1983. ___ 2012. Quality Assurance Program Manual, Rev. 3, 14 November2012.

___ 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, Chicago, Illinois, 369-382. National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746. U. S. Department of Energy. 1978. Environmental Quarterly, Appendix E. Half-Life Tables, 1 January 1978, EML-334. U. S. Nuclear Regulatory Commission.

1977. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 OCFR Part 50, Appendix I. Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125. 25

All Environmental, Inc. ,'f{ :l""'\I Midwest Laboratory 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 -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 C!nalyte 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 ApperitlixA lnterlaboratorv 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" SAMPLES LABORATORY PRECISION:

ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES" Analysis Gamma Emitters Strontium-89b Strontium-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 pCi/liter or kg 5 to 50 pCi/liter 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 pCi/liter

> 100 pCi/liter

5 4,000 pCi/liter

> 4,000 pCi/liter 0.1 pCi/liter 0.1 pCi/liter, gram, or sample :5 55 pCi/liter

> 55 pCi/liter

5 35 pCi/liter

> 35 pCi/liter 50 to 100 pCi/liter

> 100 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 pCi/liter 10% 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)°-0933 10% of known value 15% of known value '-10% of known value 6 pCi/liter 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. lnterlaboratory 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 S"r-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 24.1 0 -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, CaS0 4: Dy Cards). a mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental.

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

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 NRG -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 SPMl-697 SPMl-697 SPMl-697 SPMl-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 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/25/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/2/2015 3/11/2015 3/2/2015 3/16/2015 3/16/2015 3/25/2015 4/6/2015 4/8/2015 4/8/2015 4/13/2015 4/20/2015 4/20/2015 4/20/2015 4/20/2015 4/20/2015 4/13/2015 4/13/2015 4/13/2015 4/13/2015 4/24/2015 5/7/2015 5/7/2015 6/12/2015 6/12/2015

6/9/2015 6/9/2015 7/9/2015 7/9/2015 7/21/2015 7/21/2015 Gr. Beta Cs-134 Cs-137 Cs-134 Cs-137 Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 H-3 Ra-226 Ra-228 Cs-134 Cs-137 Fe-55 U-238 Gr. Alpha Gr. Beta C-14 H-3 Sr-89 Sr-90 Cs-134 Cs-137 H-3 Ni-63 Cs-134 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta H-3 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Concentration (pCi/L)8 Laboratory results 2s, n=1 ° 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 1.8.54 -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 TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)" Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 ° Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57 .87 -135.03 Pass SPMl-3863 7/21/2015 Cs-134 38.21 +/- 5.12 47.02 28.21 -65.83 Pass SPMl-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 -102.45 Pass SPMl-3863 7/21/2015 Sr-90 41.05+/-1.62 37.78 22.67 -52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 -65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 -102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 -52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319 -80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 -565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 -754.7 Pass SPMl-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 9/14/2016 Gr. Alpha 19.35 +/- 0.51 20.10 12.06 -28.14 Pass W-091415 9/14/2016 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 10/6/2016 Gr. Alpha 20.62 +/- 0.43 20.10 12.06 -28.14 Pass W-100615 10/6/2016 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 a Liquid sample results are reported in pCi/Liter, air filters( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b Laboratory codes: W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). 0 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 (4.66cr) Acceptance Type LLD Activitl Criteria (4.66 cr) 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 SPMl-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMl-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMl-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMl-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 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 5/7/2015 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 SPMl-3862 Milk 7/21/2015 Cs-134 3.13 1.56+/-1.74 10 SPMl-3862 Milk 7/21/2015 Cs-137 3.20 1.69+/-1.89 10 SPMl-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMl-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 TABLEA-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 (pCi/kg).

b l-131(G);

iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result. A4-2.

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)" Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 117/2015 Gr. Beta 5.72 +/-0.12 5.78 +/- 0.12 5.75 +/- 0.42 Pass CF-62,63 117/2015 Be-7 0.915 +/- 0.135 0.919 +/- 0.102 0.917 +/- 0.15 Pass CF-62,63 117/2015 K-40 3.97 +/- 0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 117/2015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/12/2015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90 +/- 1.16 Pass SG-83,84 1/12/2015 Tl-208 0.57 +/- 0.07 0.56 +/- 0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73 +/- 0.10 1.58 +/- 0.09 1.65 +/-0.13 Pass SG-83,84 1/12/2015 Pb-214 13.33 +/- 0.33 13.88 +/- 0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47 +/- 0.24 Pass SG-83,84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 1/12/2015 Ac-228 13.33 +/- 0.59 *12.86 +/- 0.43 13.09 +/- 0.36 Pass AP-011215NB 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/- 178 1,868 +/- 174 1,915 +/- 124 Pass DW-60010,60011 1/28/2015 Ra-226 1.25 +/- 0.14 1.40 +/- 0.15 1.33 +/- 0.10 Pass DW-60010,60011 1/28/2015 Ra-228 2.00 +/- 0.66 1.39 +/- 0.60 1.70 +/-0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-214 6.45 +/- 0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/- 0.24 4.20 +/- 0.58 4.32 +/- 0.31 Pass AP-020415NB 2/4/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115NB 2/11/2015 Gr. Beta 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass DW-60023,60024 2/26/2015 Ra-226 1.52 +/- 0.15 1.51 +/- 0.15 1.52 +/- 0.11 ' Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/- 0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 2/26/2015 K-40 11.96 +/- 0.98 11.49 +/- 0.82 11.72+/-0.64 Pass S-799,800 2/26/2015 Tl-208 0.36 +/- 0.04 0.31 +/- 0.04 0.34 +/- 0.03 Pass S-799,800 2/26/2015 Pb-212 0.92 +/- 0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 2/26/2015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2/26/2015 Ac-228 1.35 +/- 0.22 1.23 +/-0.17 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3 +/- 6.3 117.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 2/2/2015 Gr. Beta 82.27 +/-2.79 84.33 +/- 2.74 83.30 +/- 1.96 Pass DW-60031,60032 3/4/2015 Gr. Alpha 185.4 +/- 7.4 177.0 +/-7.2 181.2 +/-5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/- 0.34 6.88 +/- 0.32 6.89 +/- 0.23 Pass DW-60036,60037 3/4/2015 Ra-228 4.43 +/- 0.73 4.41 +/- 0.72 4.42 +/- 0.51 Pass DW-60048,60049 3/4/2015 Ra-226 0.84 +/-0.10 0.94 +/- 0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169,1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/9/2015 Gr. Beta 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 4/13/2015 H-3 1,628 +/- 139 1,695 +/- 141 1,662 +/- 99 Pass SG-1847, 1848 4/20/2015 K-40 3.24 +/- 1.18 1.99 +/- 0.76 2.62 +/- 0.70 Pass SG-1847,1848 4/20/2015 . Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847, 1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/23/2015 H-3 6,584 +/- 244 6, 164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/27/2015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/- 64.3 Pass A5-1 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)" Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242+/-198 4,325 +/- 141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/- 3.63 43.61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/- 2.02 51.40 +/- 1.40 Pass SG-1868, 1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 +/- 0.62 13.67 +/- 0.40 Pass SG-1868, 1869 4/28/2015 Ra-228 20.10 +/- 0.92 22.10+/-1.29 21.10+/-0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087,60088 5/14/2015 Ra-226 1.58 +/- 0.17 1.52 +/-0.17 1.55 +/-0.12 Pass DW-60087,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10 +/- 2.43 23.50+/-1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/- 0.61 47.80 +/- 0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/- 7.9 254.6 +/-7.6 261.2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10 +/- 0.92 40.80 +/- 0.83 40.95 +/- 0.62 Pass DW-60095,60096 5/26/2015 Gr. Alpha 1.34 +/- 0.69 0.91 +/- 0.62 1.13 +/-0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/- 0.14 1.08+/-0.12 0.97 +/- 0.09 Pass S-2627,2628 5/29/2015 Cs-137 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/- 0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/-0.48 11.15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/-214 1336 +/- 170 Pass S-2858,2859 6/2/2015 K-40 22,122 +/- 658 20,987 +/- 600 21,555 +/- 445 Pass AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-30107,30108 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 TABLEA-5.

In-House "Duplicate" Samples Concentration (pCi/L)" Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-3822, 3823 7/1/2015 Be-7 0.075 +/- 0.011 0.068 +/- 0.012 0.072 +/- 0.008 Pass AP-3969, 3970 7/1/2015 Be-7 0.063 +/- 0.008 0.064 +/- 0.010 0.063 +/- 0.006 Pass WW-3632, 3633 7/6/2015 H-3 5, 169 +/- 225 5,058 +/- 223 5,114+/-159 Pass \ W-4368, 4369 7/6/2015 Gr. Alpha 26.70 +/-4.00 24.10 +/- 3.90 25.40 +/- 2.79 Pass W-4368, 4369 7/6/2015 Gr. Beta 34.62 +/-2.10 33.30 +/-2.02 33.96 +/- 1.46 Pass DW-60138, 60139 71712015 Ra-226 0.07 +/- 0.04 0.11 +/- 0.05 0.09 +/- 0.03 Pass DW-60138, 60139 71712015 Ra-228 1.04 +/- 0.41 1.15 +/-0.47 1.10+/-0.31 Pass WW-4158, 4159 7/9/2015 H-3 138.8 +/- 82.4 174.0 +/- 84.1 156.4 +/- 58.9 Pass Ml-2902, 2903 7/10/2015 K-40 1271 +/-118 1308+/-115 1289 +/- 82 Pass SG-3533, 3534 7/10/2015 Gr. Alpha 238.0 +/- 8.2 249.5 +/- 8.5 243.8 +/- 5.9 Pass DW-60150, 60151 7/10/2015 Ra-226 1.53 +/- 0.16 1.49+/-0.12 1.51 +/-0.10 Pass DW-60150, 60151 7/10/2015 Ra-228 2.68 +/- 0.68 1.89 +/- 0.62 2.29 +/- 0.46 Pass VE-3716, 3717 7/14/2015 K-40 3.85 +/- 0.33 3.71 +/- 0.31 3.78 +/- 0.23 Pass Ml-3759, 3760 7/15/2015 K-40 1819+/-127 1764 +/- 140 1791 +/- 94 Pass Ml-3759, 3760 7/15/2015 Sr-90 1.00 +/- 0.36 0.61 +/- 0.32 0.80 +/- 0.24 Pass AP-072115 7/21/2015 Gr. Beta 0.022 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 Pass VE-4053, 4054 7/21/2015 Be-7 0.52 +/- 0.15 0.49

+/- 0.11 0.50 +/- 0.09 Pass VE-4053, 4054 7/21/2015 K-40 8.00 +/- 0.42 7.61 +/- 0.31 7.81 +/- 0.26 Pass AP-4200, 4201 7/29/2015 Be-7 1.06 +/- 0.12 0.96 +/- 0.11 1.01 +/- 0.08 Pass AP-4200, 4201 7/29/2015 K-40 5.03 +/- 0.24 4.96 +/- 0.23 4.99 +/- 0.16 Pass W-4137, 4138 7/31/2015 Ra-226 0.58 +/- 0.13 0.45 +/-0.14 0.52 +/- 0.10 Pass XWW-4431, 4432 8/5/2015 H-3 4,773 +/- 213 4,915 +/- 216 4,844 +/- 152 Pass SG-4305, 4306 8/6/2015 Ra-228 10.34 +/- 0.58 11.46 +/- 0.62 10.90 +/- 0.42 Pass AP-081015 8/10/2015 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 0.004 Pass AP-081115 8/11/2015 Gr. Beta 0.024 +/- 0.004 0.020 +/- 0.004 0.022 0.003 Pass VE-4452, 4453 8/11/2015 K-40 3.77 +/- 0.29 3.78 +/- 0.26 3.77 +/- 0.20 Pass AP-081715 8/17/2015 Gr. Beta 0.030 +/- 0.005 0.030 +/- 0.005 0.030 +/- 0.003 Pass DW-60195, 60196 8/17/2015 Ra-226 0.39 +/- 0.10 0.37 +/- 0.10 0.38 +/- 0.07 Pass DW-60195, 60196 8/17/2015 Ra-228 1.43 +/- 0.51 1.97 +/- 0.61 1.70+/-0.40 Pass DW-60198, 60199 8/17/2015 Gr. Alpha 2.93 +/- 0.94 2.11 +/- 0.96 2.52 +/- 0.67 Pass VE-4578, 4579 8/18/2015 K-40 4.14 +/- 0.25 4.32 +/- 0.24 4.23 +/- 0.17 Pass SW-4662, 4663 8/25/2015 H-3 351.3 +/- 89.8 415.6 +/- 92.8 383.4 +/- 64.6 Pass DW-60212, 60213 8/25/2015 Ra-226 0.09 +/- 0.07 0.10 +/- 0.08 0.10 +/- 0.05 Pass LW-4788, 4789 8/27/2015 Gr. Beta 0.97 +/- 0.51 1.68 +/- 0.59 1.32 +/- 0.39 Pass AP-083115 8/31/2015 Gr. Beta 0.032 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-4875, 4876 9/3/2015 Be-7 0.294 +/- 0.125 0.202 +/- 0.109 0.248 +/- 0.083 Pass VE-5083, 5084 9/14/2015 Be-7 0.47 +/- 0.23 0.56 +/- 0.19 0.52

+/- 0.15 Pass VE-5083, 5084 9/14/2015 K-40 6.20 +/- 0.51 6.36 +/- 0.50 6.28 +/- 0.36 Pass VE-5167, 5168 9/16/2015 Be-7 0.40 +/- 0.11 0.41 +/-0.10 0.41 +/- 0.07 Pass VE-5167, 5168 9/16/2015 K-40 3.56 +/- 0.27 3.91 +/- 0.24 3.74+/-0.18 Pass BS-5188, 5189 9/16/2015 K-40 9.69 +/- 0.51 10.51 +/- 0.52 10.10 +/- 0.36 Pass F-5419, 5420 9/17/2015 K-40 3.48 +/- 0.47 3.49 +/- 0.56 3.49 +/- 0.36 Pass DW-60238, 60239 9/18/2015 Ra-226 1.93 +/- 0.23 2.31 +/- 0.26 2.12+/-0.17 Pass DW-60238, 60239 9/18/2015 Ra-228 4.44 +/- 0.78 5.61 +/- 0.84 5.03 +/- 0.57 Pass AP-092215AIB 9/22/2015 Gr. Beta 0.021 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.00 Pass WW-5398, 5399 9/22/2015 H-3 1,857 +/- 145 1,846 +/- 144 1,852+/-102 Pass AP-6007, 6008 9/2812015 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass A5-3 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)" 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 0.078 +/- 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 A5-4 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a 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 activtties that measure below the LLD. Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results are reported in units of pCl/L, except for air filters (pCl/Filter or pCi/m3), food products, vegetation, soil, sediment (pCl/g). A5-5 TABLEA-6.

Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-975 2/1 /2015 Ni-63 341 +/- 18 448 314 -582 Pass MAS0-975 2/1 /2015 Sr-90 523 +/- 12 653 457 -849 Pass MAS0-975 2/1 /2015 Tc-99 614 +/- 12 867 607 -1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/- 6 678 475 -881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5 +/- 1.0 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/- 8 817 572 -1,062 Pass MAS0-975 2/1/2015 Mn-54 1, 153 +/- 9 1,198 839 -1,557 Pass MAS0-975 2/1 /2015 Zn-65 892 +/- 18 1064 745 -1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- 0.078 0.654 0.458 -0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5 -30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 -24.8 Pass MAW-969 d 2/112015 Co-57 10.2 +/- 0.4 29.9 20.9 -38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 -8.94 Pass MAW-969 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8 -23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23 -4.13 Pass MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NA* Pass MAW-969 2/1/2015 Pu-239/240 0.81+/-0.10 0.83 0.58 -1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104 -0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68 -1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64 -12.32 Pass . MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 -1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04-1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 -0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 -1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA c Pass MAAP-978 1 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 -1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/-0.08 1.02 0.71 -1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 -1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 -0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 o.01'6 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069 -0.129 Pass A6-1 TABLEA-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 MAS0-4903 8/1/2015 Cs-134 833+/-10 1,010 707-1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 -1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052+/-10 1,180 826 -1,534 Pass MAS0-4903 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463 -861 Pass A6-2 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Known Lab Code b Date Analysis Laboratory result Activity MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 MAW-5007 8/1/2015 Co-60 17.3 +/- 0.3 17.1 MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 MAW-5007; 8/1/2015 Fe-55 4.2 +/- 14.1 13.1 MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 MAAP-4911 8/1/2015 '"sr-89 3.55 +/- 0.67 3.98 MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 MAVE-4901 8/1/2015 Co-57 7.74 +/- 0.18 6.62 MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 a Results are reported in units of Bq/kg (soil), Bq/L (water) or Sq/total sample (filters, vegetation).

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

Control Limits 0 16.2 -30.0 NA c 14.6 -27.0 12.0 -22.2 151.0 -281.0 9.2-17.0 10.9 -20.3 6.0-11.1 9.7 -18.1 5.03 -9.35 3.36 -6.24 0.13 -0.73 1.76 -5.28 1.04 -1.94 2.79 -5.17 0.74-1.37 0.27 -1.53 0.78 -2.34 4.06 -7.54 NA c 4.63 -8.61 3.19-5.93 5.38 -9.98 3.82 -7.10 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. d Lab result was 27.84. Data entry error resulted in a result.

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 Acceptance Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass TABLE A-7. lnterlaboratory 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 1571.8 +/- 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 2,410 -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. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)". Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result 0 Result d Limits Acceptance ERVE-1100

° 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060 -2, 150 Fail ERVE-1100 1 3/16/2015 Co-60 1,684 +/-48 1,540 1,060 -2, 150 Pass ERVE-1100

° 3/16/2015 Cs-134 1,615 +/- 27 2,650 1,700 -3,440 Fail ERVE-1100 1 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 1 3/16/2015 Cs-137 2,078 +/- 68 1,810 1,310 -2,520 Pass ERVE-1100

° 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 -43,400 Fail ERVE-1100 1 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 -43,400 Pass ERVE-1100 e 3/16/2015 Mn-54 <13.8 <300 0.0 -300.0 Pass ERVE-1100 1 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-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 1 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).

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

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

0 Technician error weighing sample caused submitted gamma results to be understated and outside the control limits.(low) 1 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 determine 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-1103 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 = 2cr 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 + Xz) ands= (1/2) J s; + 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, annual standard deviation would not be the average of quarterly standard deviations.

The average x and standard deviation "s" of a set of n numbers x 1 , x 2 ... xn are defined as follows: s-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 Gross alpha Gross beta b lodine-131 a a background in unrestricted areas . 3 Air (pCi/m) -3 1x10 -1 2.8 x 10 Water (pCi/L) Strontium-89 8,000 Strontium-90 500 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 Potassium-40 c 4,000 Gross alpha 2 Gross beta 10 6 Tritium 1 x 10 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

SUMMARY

OF THE LAND USE CENSUS D-1 Appendix D Summary of the 2015 Land Use Census The Duane Arnold Energy Center Land Use Census was completed during September and October 201,5. All residences, milk animals, cattle, and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within three mile range, additional surveys were performed out to a distance of five miles. The 16 meteorological sectors were identified using Google Earth and digital compass rose overlay for accuracy and precision.

The 2015 Land Use Census identified 183 gardens, which is 29 more gardens than in 2014 and 35 more gardens than in 2013. Gardens were identified using Google Earth, field observation, and interviewing local residents.

Ten meteorological sectors had garden changes. There are ten nearest resident changes attributed to digital compass overlay correction and field observation verification.

Unlike in 2014, the residence at 4318 Power Plant Road was occupied for 2015. In addition, 21 new residences in the SSW sector were included in the survey. There are 14 nearest livestock changes attributed to digital compass overlay correction and field observation verification.

The Iowa Department of Agriculture and Land Stewardship provided a list of permitted commercial dairy farms located within Benton and Linn Counties.

Based on distance from DAEC, some large production dairy farms were included in the survey, but none were located within three or five miles of the )DAEC facility.

DAEC continues to collect milk samples from two permitted dairy farms located beyond five miles from DAEC. The farm at 3217 Otterview Road had a livestock change from goats to dairy cows, which is a change from 2014. The Cedar River was surveyed by boat on November 16th of 2015 for water use downstream of the DAEC to Cedar Rapids. The boat survey verified no additional withdraw sources of river water when compared to historical surveys. Recreational fishing is the only identified food pathway use of Cedar River water between the DAEC and the City of Cedar Rapids, eight miles down-river.

Benton County Public Health Department and Linn County Public Health Department provided groundwater well permit data. In 2015, no new drinking wells or industrial production wells were installed within two miles of the facility.

D-2 As a result of the 2015 Land Use Census, adjustments were made to the Meteorological Information and Dose Assessment System (MIDAS-NU) projection software model for changes in receptor distances.

No significant annual dose corrections were necessary.

The 2015 annual radiation dose assessment can be found in Appendix E. In accordance with the DAEC's Environmental Sampling Procedure ESP 4.4, "Land Use Census", no changes in land use were identified that would adversely affect the safe operation of the DAEC, or that would warrant an update of the DAEC Updated Final Safety Analysis Report (UFSAR). Examples of land use that would warrant an UFSAR update include new hazards near the DAEC such as new gas, pipelines or new installations utilizing toxic gases. NextEra Energy Resources, Duane Arnold has committed to compliance with NEI 07-07, "Nuclear Energy lnstitute's Industry Ground Water Protection Initiative".

Per NEI 07-07, the following information is presented:

No radioactive reactor by-product material was identified in samples collected by the DAEC's Radiological Environmental Monitoring Program (REMP) or the site Ground Water Protection Program (GWPP) above the threshold concentration levels for reporting.

-'

Ground Water Protection Program results are detailed in the site's Annual Radioactive Material Release Report. D-3 APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1 Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a member of the public was determined by assessment of environmental dosimetry results and by calculations based on monitored effluent releases.

Section A. Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM). 1. Pre-operational and 2015 TLD results were evaluated with a paired difference statistical test. The evaluation concluded that there were no significant differences in the TLD populations for the 0.5 mile and 1 mile TLD populations as per Environmental Sampling Procedure, ESP 4.5, Rev 6. 2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for the central United States. Section 8. Estimated Offsite Dose from Effluent Releases 1. The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated using the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with the ODAM. The calculation methods follow those prescribed by Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I". 2. Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed.

The current sampling scheme was determined to be adequate for the identified receptors.

Results of the MIDAS dose calculations are displayed below. 1.) There were no releases of radioactive material to liquid effluents in 2015. 2.) The maximum dose to air at the site boundary from noble gases released was 0.0107 mrad from gamma radiation at 1176 meters towards the North. 3.) The maximum dose to air at the site boundary from noble gases released was 0.0134 mrad beta radiation at 1176 meters towards the North. 4.) The whole body dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.0041 mrem, at 1760 meters towards the North. E-2 5.) The skin dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.0097 mrem, at 1760 meters towards the North. 6.) The hypothetical maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days (excluding carbon-14) was the lungs of a child at 805 meters towards the West, with an estimated dose equivalent of 0.00385 mrem. 7.) The hypothetical maximally exposed organ due to airborne carbon-14 was the bone of a child located 1760 meters to the North of the site. The dose was 0.089 mrem. Conclusion No measurable dose due to the operation of the DAEC or the DAEC ISFSI was detected by environmental TLDs in 2015. The calculated doses are below the regulatory limits stated in Appendix I to 10CFR50, 40CFR190 and 10 CFR 72.104. Estimated Maximum Offsite Individual Doses for 2015 Type Age Distance Direction Dose or Dose Equivalent Annual 1 O CFR 50, Group (meters) (mrem) Appendix I "Limit" Direct Radiation None * (as measured by TLDs) Liquid Releases Whole Body Dose Child s 0.000000 mrem 3 mrem Organ Dose Child -s 0.000000 mrem 10 mrem Liver Noble Gas Gamma Air Dose 588 SE 0.0107 mrad 10 mrad Beta Air Dose 2416 SE 0.0134 mrad 20 mrad Whole Body All 1620 NNW 0.0041 mrem 5 mrem Skin Adult 1620 NNW 0.0097 mrem 15 mrem Particulates

& Iodines Organ Dose Child-2450 ESE 0.00385 mrem 15 mrem Lungs Carbon 14 Organ Dose Child-2500 ENE 0.089 mrem 15 mrem Bone

There is no Appendix I limit for direct radiation.

It is listed here to demonstrate compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid. E-3

All Environmental, Inc * .,."" l'"\I Midwest Laboratory 700 Landwehr Road

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