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Annual Radioactive Material Release Report
	ML17118A245
Person / Time
Site:	Duane Arnold
Issue date:	04/24/2017
From:	; NextEra Energy Duane Arnold
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML17118A243	List: ML17118A245; ML17118A246; NG-17-0092, Duane Arnold, 2016 Annual Radioactive Material Release Report;
References
	NG-17-0092
	Download: ML17118A245 (63)
	v • d • e

{{#Wiki_filter:Enclosure 1 to NG-17-0092 Duane Arnold Energy Center 2016 Annual Radioactive Material Release Report 62 pages follow

   - NEXTeraM ENERGY~                      ~

DUANE ARNOLD

2016 -

Annual Radioactive Material Release Report Duane Arnold Energy Center Cedar Rapids, Iowa Docket No. 50-331 January 1, 2016 through December 31, 2016

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Intentionally blank DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table of Contents REGULATORY LIMITS 6 MAXIMUM PERMISSIBLE CONCENTRATIONS 7 AVERAGE ENERGY 7 MEASUREMENTS OF TOTAL RADIOACTIVITY 7 GASEOUS EFFLUENTS 9 Table 1A - Gaseous Effluents - Summation of All Releases Table 1B - Gaseous Effluents by Quarter Table 1C - Gaseous Effluents by Release Point Estimated Release of Gaseous of Carbon-14 Gaseous Effluents: Historical Trend LIQUID EFFLUENTS 13 Table 2A - Liquid Effluents - Summation of All Releases Table 28 - Liquid Effluents RADIOACTIVE SOLID WASTE 15 Shipments In 2016 Waste Classification per 10 CFR 61 Summary Tables of Radioactive Solid Waste RADIOLOGICAL IMPACT ON MAN 20

SUMMARY

OF METEOROLOGICAL DATA 22 Stability Class Data 33' Wind Rose Data 33' Stability Class Data 156' Wind Rose Data 156'

SUMMARY

OF GROUND WATER PROTECTION INITIATIVE ISSUES 25 DESCRIPTION OF CHANGES TO THE OFFSITE DOSE ASSESSMENT MANUAL 26 Revision 35 --+ Revision 37 ATTACHMENT 1- GROUND WATER PROTECTION PROGRAM RESULTS ATTACHMENT 2 - OFFSITE DOSE ASSESSMENT MANUAL Page 5 of28

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT REGULATORY LIMITS Fission and Activation Gases Dose Rate

Less than 500 mrem/year to the whole body.
Less than 3000 mrem/year to the skin.

Gamma Air Dose

1) Less than or equal to 5 mrad/quarter.
2) Less than or equal to 10 mrad/year.

Beta Air Dose

1) Less than or equal to 10 mrad/quarter.
2) Less than or equal to 20 mrad/year.

Airborne Particulates, Iodines and Tritium Dose Rate

Less than 1500 mrem/year.

Dose

Less than or equal to 7.5 tmem/quarter to any organ.
Less than or equal to 15 mrem/year to any organ.

Liquid Effluents Dose

Less than or equal to 1.5 imem to the whole body during any calendar quarter.
Less than or equal to 5 mrem to any organ during any calendar quarter.
Less than or equal to 3 mrem to the whole body during any calendar year.
Less than or equal to 10 mrem to any organ during any calendar year.

Concentration

Liquid effluents released from the site to unrestricted areas shall not exceed ten times (lOx) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.

40CFR190 and 10CFR72 Dose

1) Less than or equal to 25 mrem annual whole body dose.
2) Less than or equal to 75 mrem annual thyroid dose.
3) Less than or equal to 25 mrem annual dose to any other critical organ.

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT MAXIMUM PERMISSIBLE CONCENTRATIONS Dose rates, rather than effluent concentrations, are used to calculate permissible release rates for gaseous effluents. The maximum pem1issible dose rates for gaseous releases are defined in Duane Arnold Offsite Dose Assessment Manual (ODAM). ODAM Limiting Condition for Operation (OLCO) 6.2.2. Liquid effluent concentrations are limited per ODAM OLCO 6.1.2 to ten times (lOx) the concentration specified in 10CFR20 Appendix B, Table 2, Column 2. A VERAGE ENERGY The ODAM limits dose rates at or beyond the site boundary due to the release of noble gases to less than or equal to 500 mrem per year to the total body and less than or equal to 3,000 mrem per year to the skin, and average energy is not used to determine dose to the public. Compliance with these limits is demonstrated based on dose calculations using measured isotopic concentrations of effluent streams and not based on gross count rate measuring systems.

Therefore, the average beta and gamma energies (E-BAR) for gaseous effluents as described in Regulatory Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.

MEASUREMENTS OF TOTAL RADIOACTIVITY Gaseous Effluents

Gaseous Effluents from the Offgas Stack, Reactor Building Vents, Turbine Building Vent and the Low Level Radwaste Storage and Processing Facility (LLRPSF) are continuously sampled for iodines and particulates. Sample media is changed weekly and analyzed by gamma spectroscopy. The gross alpha analyses are performed onsite. The particulate filters are composited on a quarterly basis and sent to a vendor for Sr-89, Sr-90, Fe-55 and Ni-63. Total error is calculated based on stack flow error, sample flow error, and analytical error.
Noble gas grab samples of the same four release points are obtained monthly and analyzed by gan11Tia spectroscopy. Total error is based on stack flow error, analytical error, and calculated sampling error.
Tritium samples from all four release points are obtained quarterly and analyzed by liquid scintillation. Total error is based on stack flow error, analytical error, and calculated sampling error.
A beta sensitive radiation detector provides for continuous monitoring at each of the above described release points. For the year 2016, there were no instances where ODAM required gaseous radiation monitoring or sampling systems were inoperable on an active release point for a period of 30 (contiguous) days or more. (ODAM OLCO 6.2.1.1 A.2)

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Liquid Effluents

Service water systems are sampled once per week for gamma emitters. Portions of the weekly service water samples are composited for a monthly analysis for tritium and gross alpha. If there is a positive identification ofreactor by-product radioactivity in these samples, analysis for Sr-89, Sr-90 and Fe-55 are performed. Total error is based on the volume discharge error and analytical error.
ODAM defined "Clean" Systems are sampled prior to free release. Samples are collected prior to release and analyzed for gamma emitters and tritium. If reactor byproduct gamma emitters are identified, analyses for Si-89, Sr-90 and Fe-55 are performed. "Clean Systems" include: CST Containment Pit, Transformer Pit, Neutralizing Tank 1T022, and FRAC tanks. Total error is based on the volume discharge error, dilution flow error and analytical error.
No radioactive batch releases ofliquids from plant radwaste systems were perfom1ed in 2016. There were 97 radioactive batch releases of tritiated groundwater and rainfall recapture from catch basins.

All releases were less than 6,000 pCi/L. The DAEC Groundwater Protection Plan Administrative Control Procedure, ACP 1411.35, tritium limit is 20,000 pCi/L, which is identical to the EPA drinking water limit for tritium.

Continuous monitoring with gamma sensitive radiation detectors is provided for plant service water systems. For the year 2016, there were no instances where these liquid radiation monitoring systems were inoperable on an active release point for a period of 30 (contiguous) days or more. (ODAM OLCO 6.1.1.1 A.2)

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT GASEOUS EFFLUENTS There were no radioactive gaseous batch releases from the Duane Arnold Energy Center during this report period. All gaseous effluent releases were continuous and resulted in a small fraction of the 10 CFR 50, Appendix I dose objectives. For all release points, quarterly average gross alpha concentration of radioactivity measured less than 4.IOE-09 µCi/cc. There were no Abnormal releases of gaseous effluents during the period. Table lA - Gaseous Effluents - Summation of All Releases 3rd Est. Total Units Quarter En-or,% Fission and Activation Gases

1. Total Release Ci l.65E+Ol 4.76E+ol 5.26E+Ol 2.06£+01 l.60E+Ol I

2. Average Release Rate for Period uCi/sec 2.09E+OO 6.05E+OO 6.62£+00 2.59E+OO

3. Percent of Applicable Limit % * * *

Iodines

1. Total 1-131 Ci 2.59E-06 3.89E-06 7.72E-06 l.20E-06 1.80£+01 I

2. Average Release Rate for Period uCi/sec 3.29£-07 4.95E-07 9.71E-07 l.50E-06

3. Percent of Applicable Limit % * * *

Particulates

1. Total Particulates w/ balflife >8 days Ci 2.08E-05 4.43£-05 5.84£-05 l.02E-3 l.80E+Ol I

2. Average Release Rate for Period uCi/sec 2.64E-06 5.63E-06 7.53E-06 l.28E-04

3. Percent of Applicable Limit % * * *

Tritium

1. Total Release Ci 4.60E+OO 5.24E+OO l.06E+Ol l.21E+Ol l.60E+Ol I

2. Average Release Rate for Period uCi/sec 5.85E-01 6.66E-01 l.34E+OO l.52EOO

3. Percent of Applicable Limit % * * *

Carbon 14

1. Total Carbon-14 Ci 2.41E+OO 2.24E+OO 2.35E+OO l.63E+OO

2. Average Release Rate for Period uCi/sec 3.07E-01 2.82E-Ol 2.96E-Ol 2.05E-Ol

3. Percent of Applicable Limit % * * * *

Applicable limits have been removed from the Technical Specifications. The comparison to ODAM limits is contained in the Radiological hnpact on Man section of this report.

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table lB - Gaseous Effluents by Quarter ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ( 2016) GASEOUS EFFLUENTS BY CALENDAR QUARTER (Curies) Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Fission gases krypton-85 Ci ND ND 6.28E-02 1.42E-01 krypton-85M Ci 6.13E-02 ND 7.11E-03 1.54E-02 krypton-87 Ci 1.56E+OO 5.49E+OO 7.82E-04 1.69E-03 krypton-88 Ci ND ND 6.61E-03 1.43E-02 xenon-131M Ci ND ND 1.09E-02 2.75E-02 xenon-133 Ci 8.36E+OO 2.57E+01 4.94E+01 2.00E+01 xenon-133M Ci 9.08E-09 ND 2.54E-02 5.24E-02 xenon-135 Ci 6.46E+OO 1.64E+01 3.02E+OO 3.44E-01 xenon-135M Ci ND ND 3.20E-02 6.91E-02 argon-41 Ci ND ND ND ND Total for period Ci 2.10E+01 5.28E+01 6.32E+01 3.27E+01

2. Iodines iodine-131 Ci 2.59E-06 3.89E-06 7.72E-06 1.20E-05 iodine-133 Ci 7.28E-06 9.41E-06 1.74E-05 6.89E-06 iodine-135 Ci ND ND ND ND Total for period Ci 9.87E-06 1.33E-05 2.51E-05 1.88E-05

3. Particulates strontium-89 Ci 7.34E-07 1.16E-06 1.08E-06 1.39E-06 strontium-90 Ci 5.00E-09 ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND barium-lanthanum-140 Ci 2.06E-07 3.39E-07 1.48E-07 ND chromium-51 Ci 3.12E-06 ND 4.14E-06 3.99E-04 cobalt-58 Ci ND 2.55E-07 9.75E-07 2.95E-05 cobalt-60 Ci 2.67E-06 6.35E-07 8.33E-06 1.01E-04 manganese-54 Ci 1.58E-06 2.95E-05 2.69E-05 3.54E-04 lron-55 Ci 1.25E-05 1.24E-05 1.55E-05 2.12E-05 iron-59 Ci ND ND 1.42E-06 7.57E-05 nickel-63 Ci 1.0?E-05 ND 3.0BE-07 2.98E-06 zinc-65 Ci ND ND ND ND Total for period Ci 3.15E-05 4.43E-05 5.87E-05 1.02E-03

4. Tritium Ci 4.60E+OO 5.24E+OO 1.06E+01 1.21 E+01 Tritium Total Ci 4.60E+OO 5.24E+OO 1.06E+01 1.21E+01 Ci 2.41E+OO 2.24E+OO 2.35E+OO 1.63E+OO

5. Carbon-14 Carbon-14 Total Ci 2.41E+OO 2.24E+OO 2.35E+OO 1.63E+OO ND means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the DAEC Offsite Dose Assessment Manual.

Page 10

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table 1C - Gaseous Effluents by Release Point ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ( 2016) GASEOUS EFFLUENTS BY RELEASE POINT (Curies) REACTOR TURBINE RELEASE POINT: OFFGAS STACK LLRPSF BUILDING BUILDING RELEASE HEIGHT: 328 FEET 156 FEET 90 FEET 65 FEET RE:LEASE MODE: ELEVATED WAKE SPLIT WAKE SPLIT WAKE SPLIT argon-41 ND ND ND ND barium-140 6.93E-07 ND ND ND cesium-137 ND ND ND ND chromium-51 3.35E-06 4.03E-04 ND ND cerium-141 ND ND ND ND cobalt-58 ND 3.07E-05 ND ND cobalt-60 1.29E-06 1.09E-04 2.20E-06 ND iodine-131 1.38E-05 1.02E-05 2.12E-06 ND iodine-133 2.90E-05 1.19E-05 ND ND iron-55 3.54E-06 4.90E-05 9.03E-06 ND krypton-85m 8.38E-02 ND ND ND krypton-87 7.05E+OO ND ND ND manganese-54 4.80E-06 4.06E-04 2.38E-06 ND nickel-63 3.61E-08 1.40E-05 ND ND strontium-89 1.16E-06 2.21E-06 1.00E-06 ND strontium-90 5.00E-09 ND ND ND tritium 1.14E+01 1.57E+01 5.32E+OO 1.17E-01 Xenon-133 8.70E+01 1.93E+OO 1.45E+01 ND xenon-135 2.62E+01 6.35E-03 ND ND xenon-135m 1.01E-01 ND ND ND xenon-138 ND ND ND ND zinc-65 ND 3.69E-05 ND ND xenon-133m 6.36E-02 1.41 E-02 ND ND xenon-131m 3.84E-02 ND ND ND krypton-88 2.09E-02 ND ND ND krypton-85 2.05E-01 ND ND ND iron-59 ND 7.71E-05 ND ND carbon-14 ** 8.64 - - - ND means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the DAEC Offsite Dose Assessment Manual.

- Carbon-14 release was estimated using methods of the EPRI document, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", Report 1021106, issued December 2010.

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Estimated Release of Gaseous ofCarbon-14 The estimate of gaseous carbon-14 (C-14) released from the Duane Arnold Energy Center was derived using the EPRI document, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", Report

1021106, issued December 2010. The site specific source term for the DAEC was estimated using the proxy generation rate values from Table 3-1 and the actual 2016 power history for the site.

The total amount of C-14 released from the site in 2016 was estimated to be 8.64 Curies. Using the dose calculation methodology from Regulatory Guide 1.109, the resultant maximally exposed receptor organ from C-14 is the bone of a child, located 2,470 meters towards the East-Northeast. The dose is 1.13E-01 mRem (0.113 mrem). This is a fraction of the l 1mem annual whole body dose received to the average US citizen from natural occurring carbon-14, primarily generated through cosmogenesis in the terrestrial biosphere. (

Reference:

National Council of Radiation Protection Report 94,"Exposure of the Population in the United States and Canada from Natural Background Radiation.") Gaseous Effluents Trend Curies per year, Historical Trend

                                                                                                                                          -o-Tritlum 1.E+O  -'- - - + - - + - - - + - - + - - + - - - > - --1-- - + - - + - - - + - - + - -- - + - -+ - - - + - - - - - --+--+--__,

DAEC Gaseous Effluents - -¢-*Noble Gas 11.E-1 + - - - + - - - ; > - - - - < - - - + - - + - - + - - - - - + - - + -- +---+---+- - + - - - + - - + - - - t - - - + - - + - - - ; 1curies 1.E-2 --1--+---1--r---+---+--t----+-+---+--+---+---1--+---+--+----+--+---;

                                                                                                                                          -o - Particulates
                                                                                                                                          - *- -Iodines
       *Excluding Carbon-14 Page 12

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT LIQUID EFFLUENTS Liquid effluent release in the form of service water from the facility was continuous during the period. No reactor by-product radionuclides were identified in samples from service water. There were no liquid releases from the plant radioactive waste handling systems in 2016. There were 97 radioactive batch releases from the groundwater protection mitigation system in 2016. There were no abnonnal releases of radioactive liquids during the period. Table 2A - Liquid Effluents - Summation of All Releases Est. 1st 2nd 3rd 4th Total Units Quarter Quarter Quarter Quarter Error,% Fission and Activation Gases

1. Total Release (not including O.OOE+OO O.OOE+OO O.OOE+OO Ci O.OOE+oO 2.00E+OI Tritium, gases, alpha)

2. Average Release Rate for Period uCi/sec O.OOE+OO O.OOE+OO O.OOE+oO O.OOE+OO

3. Percent of Applicable Limit % * * *

Tl'itium

1. Total Release Ci O.OOE+OO 4.79E-04 8.35E-03 8.48E-03 2.00E+Ol I

2. Average Release Rate for Period uCi/sec O.OOE+OO l.27E-07 7.36E*08 l.81E-07

3. Percent of Applicable Limit % * * *

Volume of Water Release O.OOE+OO 5.00E+04 liters 2.04£+06 2.85E+06 (prior to dilution)

Volume of dilution water liters 0.00E+OO 3.76£+06 1.18£+08 4.70E+o07 used during period

      *Applicable limits have been removed from the Technical Specifications. The comparison to ODAM limits is contained in the Radiological Impact on Man section of this report.

Page 13

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table 2B - Liquid Effluents ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ( 2016) LIQUID EFFLUENTS {Curies) Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter strontium-89 Ci ND ND ND ND strontium-90 Ci ND ND ND ND cesium-134 Ci ND ND ND ND cesium-137 Ci ND ND ND ND iodine-131 Ci ND ND ND ND cobalt-58 Ci ND ND ND ND cobalt-60 Ci ND ND ND ND iron-55 Ci ND ND ND ND iron-59 Ci ND ND ND ND zinc-65 Ci ND ND ND ND manganese-54 Ci ND ND ND ND chromium-51 Ci ND ND ND ND zirconiu m-niobium-95 Ci ND ND ND ND molybdenum-99 Ci ND ND ND ND technetium-99m Ci ND ND ND ND barium-lanthanum-140 Ci ND ND ND ND cerium-141 Ci ND ND ND ND other Ci ND ND ND ND tritium Ci ND 4.79E-04 8.35E-03 8.48E-03 Total for period (above) Ci ND ND ND ND xenon-133 Ci ND ND ND ND xenon-135 Ci ND ND ND ND ND means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the DAEC Offsite Dose Assessment Manual. Page 14

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT RADIOACTIVE SOLID WASTE A total of twenty-one solid radioactive waste shipments were made during 2016. Six shipments of spent resin were made in 2016. These shipments of spent resin in poly liners were shipped for direct burial at Energy Solutions, located in Clive, Utah at their Containerized Waste Facility (CWF). All of these shipments contained resin from the condensate system and all were transported by highway. Fifteen shipments of Dry Active Waste (DAW) were shipped for processing and then to burial during the year 2016. All 15 shipments were sent to Energy Solutions Bear Creek processing facility for sorting and subsequently shipped for burial at Energy Solutions Clive, Utah facility. The transportation for this waste was by highway. There were no shipments of liquid waste in 2016. During an internal audit of radioactive solid waste records, a single diy active waste shipment was not included in the 2011 Annual Radiological Material Release Report (Condition Report 02182217). Specifically: Waste weight: 27,800 lbs Waste activity: 3.43E-02 Ci Waste volume: 1,000 ft3 Waste density: 27 .8 lbs/ft3 External volume: 1,360 ft3 Waste type: DAW Page 15

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Shipments in 2016 Listed below are tables summarizing the Duane Arnold Energy Center's generation of Radioactive Solid Waste for the period of January 1, 2016 through December 31, 2016. Shipments Made To Burial Facilities in 2016: NO. VOLUME VOLUME ACTIVITY SHIPMENTS (ft3) (m3) (curies) 6 1020 2 . 42.57 ON Energy Solutions, Containerized Waste Facility and Bulk Waste Facility Clive, Utah See Table 3A below for Major Nuclides Shipments Made To Processing Facilities in 2016: WASTE TYPE NO. VOLUME VOLUME ACTIVITY SHIPMENTS (ft3) (m3) (curies) Dry Active Waste 15 18820 532.92 1.054 DESTINATION Energy Solutions Bear Creek Facility, Oakridge TN The solid waste was subsequently delivered to Containerized Waste Facility and Bulk Waste Facility Clive, Utah See Table 3B below for Major Nuclides Total Solid Waste Disposition for 2016: WASTE VOLUME VOLUME ACTIVITY (ft3) (m3) (curies) Shipped 19840 561.81 43.62 Buried 19840 561.81 43.62 SOLIDIFICATION AGENT: None MODE OF TRANSPORTATION: Exclusive-Use Vehicle (Trncks). IRRADIATED COMPONENTS: There were no shipments ofi1rndiated components or nuclear fuel in 2016 See Table 3C below for Annual Summary of Major Nuclides I Waste Classification per 10 CFR 61 NUMBER OF SHIPMENTS IN 2016 21 A-Stable 0 B 0 c 0 S't I e Hit . l C omparison s orica Year Volume Buried(ft3) Activity (Ci) 2007 l.40E+04 110 2008 5.42E+03 134 2009 l.16E+04 58 2010 l.14E+04 23 2011 7.26E+03 324 2012 2.48E+04 58 2013 7.19E+03 52 2014 2.70E+04 33 2015 6.68E+03 48 Page 16

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Summary of Radioactive Solid Waste- Spent Resin (January 1, 2016 - December 31, 2016) MAJOR NUCLIDE COMPOSITION Table 3A Spent Resin Principle 1st QTR 2nd QTR 3rd QTR 4th QTR Total Percent Nuclide (mCi) (mCi) (mCi) (mCi) (mCi) Abundance H-3 1.12E+01 1.80E+OO 1.30E+01 0.048% C-14 2.91E+01 9.73E+OO 3.89E+01 0.143% K-40 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Mn-54 3.28E+03 9.13E+02 4.19E+03 15.469% Fe-55 1.16E+04 4.12E+03 1.57E+04 57.981% Co-57 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Co-58 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Ni-59 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Co-60 3.24E+03 1.12E+03 4.36E+03 16.074% Nl-63 3.86E+02 1.29E+02 5.15E+02 1.899% Zn-65 1.85E+03 2.86E+02 2.14E+03 7.882% Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sr-90 2.48E+OO 3.12E-01 2.79E+OO 0.010% Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Nb-95 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Tc-99 4.68E+OO 7.39E-01 5.42E+OO 0.020% Ag-110m O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% 1-125 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% 1-129 1.26E+OO 2.00E-01 1.46E+OO 0.005% Cs-137 1.09E+02 1.74E+01 1.27E+02 0.468% Ce-144 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Pu-239 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Am-241 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Totals O.OOE+OO 2.05E+04 6.60E+03 O.OOE+OO 2.71E+04 100.00% Page 17

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Summary Tables of Radioactive Solid Waste Dry Active Waste (January 1, 2016 - December 31, 2016) MAJOR NUCLIDE COMPOSITION Table 3B Dry Active Waste Principle 1st QTR 2ndQTR 3rd QTR 4th QTR Total Percent Nuclide (mCi) (mCi) (mCi) (mCi) (mCi) Abundance H-3 5.08E-01 8.63E-01 6.03E-01 2.81E+OO 4.79E+OO 0.399% C-14 8.54E-03 1.0lE-02 8.26E-03 3.31E-02 6.00E-02 0.005% K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Cr-51 7.67E-01 O.OOE+OO O.OOE+OO 9.19E-01 1.69E+OO 0.141% Mn-54 8.95E+OO 1.75E+Ol 1.02E+01 5.79E+01 9.45E+01 7.889% Fe-55 7.36E+Ol 1.44E+02 9.14E+01 4.72E+02 7.81E+02 65.199% Co-57 O.OOE+OO O.OOE+OO O.OOE+OO 4.40E-03 4.40E-03 0.000% Co-58 O.OOE+OO O.OOE+OO O.OOE+OO 5.53E-01 5.53E-01 0.046% Ni-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-01 3.66E-01 0.031% Co-60 3.12E+Ol 5.07E+Ol 3.48E+01 1.65E+02 2.82E+02 23.537% Ni-63 1.54E+OO 3.41E+OO 2.24E+OO 1.11E+01 1.83E+01 1.525% Zn-65 1.22E+OO 2.49E+OO 1.39E+OO 8.21E+OO 1.33E+01 1.110% Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO 2.24E-02 2.24E-02 0.002% Nb-95 O.OOE+OO O.OOE+OO O.OOE+OO 7.57E-02 7.57E-02 0.006% Tc-99 3.70E-02 1.53E-02 2.22E-02 4.97E-02 1.24E-01 0.010% Ag-110m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% 1-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% 1-129 6.39E-03 1.08E-02 7.76E-03 5.26E-02 7.75E-02 0.006% Cs-137 2.19E-01 O.OOE+OO 1.74E-01 6.11E-01 1.00E+OO 0.084% Ce-144 O.OOE+OO O.OOE+OO O.OOE+OO 1.00E-01 1.00E-01 0.008% Pu-239 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Am-241 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Totals 1.18E+02 2.19E+02 1.41E+02 7.21E+02 1.20E+03 100.00% Page 18

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Summary of Radioactive Solid Waste-Annual Summary (January 1, 2016 - December 31, 2016) MAJOR NUCLIDE COMPOSITION Table 3C Radwaste Annual Summary Nuclide Curies H-3 1.74E-02 C-14 4.45E-02 K-40 O.OOE+OO Cr-51 1.40E-01 Mn-54 4.94E+OO Fe-55 1.87E+01 Co-57 O.OOE+OO Co-58 5.65E-02 Ni-59 O.OOE+OO Fe-59 4.70E-02 Co-60 5.21E+OO Ni-63 6.02E-01 Zn-65 2.31E+OO Sr-89 O.OOE+OO Sr-90 2.95E-03 Sr-91 O.OOE+OO Zr-95 O.OOE+OO Nb-95 O.OOE+OO Tc-99 5.85E-03 Ag-110m O.OOE+OO Sn-113 O.OOE+OO Sb-124 O.OOE+OO Sb-125 O.OOE+OO 1-125 O.OOE+OO 1-129 1.58E-03 Cs-137 1.36E-01 Ce-144 O.OOE+OO Pu-239 O.OOE+OO Am-241 O.OOE+OO Total 3.22E+01 Page 19

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT RADIOLOGICAL IMPACT ON MAN The annual offsite radiation dose to a member of the public was determined by assessment of environmental dosimetry results, by calculations based on monitored effluent releases and by estimating the release of gaseous carbon-14. 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). Pre-operational and 2016 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, 1 mile and control TLD populations. Estimated Offsite Dose from Effluent Releases 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". Dose to members of the public from carbon-14 in gaseous effluent is calculated separately and is described below. Results of the MIDAS dose calculations are displayed here: 1.) There were 97 batch releases of radioactive material to liquid effluents (groundwater mitigation) in 2016. 2.) The maximum dose to air at the site boundary from noble gases released was 0.00162 mrad from gamma radiation at 936 meters towards the Northwest. 3.) The maximum dose to air at the site boundary from noble gases released was 0.00213 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 0.0032 mrem, at 2120 meters towards the Northwest. 5.) The skin dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.0038 mrem, at 2120 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 of0.00617 mrem. 7.) The hypothetical maximally exposed organ due to airborne carbon-14 was the bone of a child located 2470 meters to the North of the site. The dose was 0.113 mrem. Page 20

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Conclusion No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2016. The calculated doses are below the regulatory limits stated in Appendix I to 10CFR50 and in 40CFR190. Estimated Maximum Offsite Individual Doses for 2016 Type Age Distance Direction Dose or Dose Equivalent Annual 10 CFR 50, Group (meters) (mrem) Aooendix I "Limit" Direct Radiation None * (as measured bv TLDs) Liquid Releases Whole Bodv Dose Child D* SE 0.00253 mrem 3mrem Organ Dose Child - D* SE 0.00253 mrem 10 mrem Liver Noble Gas Gamma Air Dose 936 NW 0.00162 mrad 10 mrad Beta Air Dose 1176 N 0.00213 mrad 20 mrad Whole Body All 2120 NW 0.00320 mrem 5mrem Skin Adult 2120 NW 0.00380 mrem 15 mrem Particulates & Iodines Organ Dose Child-Lungs 805 w 0.00617 mrem 15 mrem Carbon 14 Organ Dose Child-Bone 2470 N 0.113 mrem 15 mrem

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.

D* Receptor location is aquatic pathway at Cedar River, See Offsite Dose Assessment Manual, ODAM, figure 3-2. Page 21

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT

SUMMARY

OF METEOROLOGICAL DATA The following pages are a summation of meteorological data accumulated during the 2016 calendar year by the MIDAS software (Meteorological Information and Dose Assessment System) at the Duane Arnold Energy Center. Better than 90% data recovery was obtained for combined wind speed, delta temperature and wind direction. A table smnmarizing data collection is printed here: Met. Data Recovery Elevation and Sensors % Joint Recovery "good" data 10 meter Wind Direction Wind Speed 99.1% Delta Temp 50 meter Wind Direction Wind Speed 99.1% Delta Temp Listed on the following pages are wind rose plots and stability class summary tables for the specified sensor heights (33 feet or 156 feet). Joint Frequency tables for each of the individual stability classes are maintained on site and are available upon request. Page 22

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Stability Class Data 33' Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Rec.ord = 12/31 /2015 23:00 - 1/1/2017 00:00 Elevation: Speed: WS33 Direction: WD33 Lapse: DELT Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph) Wind Direction !.-4 .!-8 8-13 13-19 19-25 ~~ Total N 0 2 6 0 0 0 8 1'11\'""E 0 5 4 2 0 0 11 NE 1 12 11 1 0 0 25 E1'""E 2 15 2 0 0 0 19 E 0 5 1 0 0 0 6 ESE 2 6 2 0 0 0 10 SE 2 24 18 0 0 0 44 SSE 2 64 35 0 0 102 s 4 76 37 0 0 118 SSW 2 44 30 4 0 0 80 SW 1 20 17 8 2 0 48 WSW 0 17 10 2 3 0 32 w 0 3 18 4 0 1 26 WNW 0 5 23 18 4 2 52 1',.W 1 2 39 22 13 3 80 1'11°'1-w 0 1 16 6 2 1 26 Total 17 301 269 69 24 7 687 Cahn Hours not Included ab on for: Total P erlod 15 Variable Direction Hours for: Total P erlod 0 Iuva lid H oun for: Total Period 80 Valid Hours for this Stability Class for: Total P erlod 687 Total Hou I'S for Period 8786 Wind Rose Data 33' l(lD/l0171 1ll;'.:t.4J.i (WINDS FHOM) N

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Page 23

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Stability Class Data 156' Joint Frequency Distribution Hours at Each Wind Speed and Direct ion Total Period Period of Record= 12/31 /2015 23:00 - 111/201 7 00 :00 Ilevation: Speed: WS1 56 Direc tion : WD1 56 Lapse: DELT Stability Class A Delta Temperature Extremel y Unstable Wind Speed (mph) Wind Dir*ection .!.- 4 1-- 8 8-13 13-19 19-25 :::. 25 Total N 0 2 2 3 0 0 7 NNE 0 2 16 2 0 0 20 l'i-:E 0 8 13 2 0 0 23 ENE 2 11 1 2 0 0 16 E 0 2 3 0 0 0 5 ESE 0 2 3 2 0 0 7 SE 0 8 19 10 l 0 38 SSE 0 11 54 45 4 0 114 s 0 21 60 44 5 1 131 SSW 0 2 22 39 7 0 70 SW 0 6 24 13 8 6 57 WSW 0 2 7 4 2 1 16 w 1 l 7 25 I 5 40 WNW 0 2 20 24 13 3 62 NW 0 2 17 22 16 8 65 Nl'i\ Y 0 6 9 1 0 17 Total 3 83 274 246 58 24 688 Calm Hours not Included ab on for: Total Period 0 Variable Direction Hours for : I otal Period 0 Invalid Hours for: Total Period 79 Valid Hours for this Stability Class for : Total Period 688 Total Hours for Period 8786 Wind Rose Data 156' WIND ROSE (Wll~DS FROM) . N t riwi*1 ~hCO*iT CJ.l 1.t.S. (NO I INl:l lJl1b ll IN Pl.Ill) U"" '=' ).. Stu11 Oulu: 12/31fl015 23:00 f od n arn: 1/l/?1117 00:00 Ser\sof'i S ele 0t4.!d

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DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT

SUMMARY

OF GROUNDWATER PROTECTION INITIATIVE ISSUES The Duane Arnold Energy Center has committed to the Nuclear Energy Institute's Industry Groundwater Protection Initiative - NEI 07-07. Per NEI 07-07, the following information is presented:

Ground Water Protection Program (GWPP) samples were collected and analyzed in accordance with the requirements and guidance of the site procedure ACP 1411.35.

Program results are presented in Attachment 1.

No reactor-by-product gamma emitting isotopes were identified.
In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than (<) 20,000 pCi/L.
Tritium concentrations range from non-detectable at less than 180 pCi/L to 296,589 pCi/L from monitoring well MW-22A (D-66). No site or neighboring drinking water wells are installed in this shallow aquifer and no tritium has been identified in neighboring drinking water wells or onsite drinking water (deep aquifers). The EPA Drinking Water Standard for tritium is 20,000 pCi/L and equates to an annual dose of 4 mrem/yr. Using extraction well EW-OlA (D-68) discharge water with an average concentration of 3,070 pCi/L and assuming EW-OlA is the only drinking water source for an entire year, the maximum dose consequence would be approximately 0.614 mrem/yr.

The highest concentration from EW-OlA was 5,860 pCi/L and equates to approximately 1.172 mrem/yr.

In 2016, there was one instance where state and local officials were notified of a spill of radioactive liquid.

COURTESY OFFSITE NOTIFICATION MADE TO STATE AND COUNTY OFFICIALS "On April 12, at 1235 CDT, Duane Amold Energy Center contacted officials with the State oflowa (Bureau of Radiological Health and Department of Natural Resources) and Linn County Public Health Department in accordance with the nuclear industry voluntary reporting criteria contained in NEI 07-07

      'Industry Ground Water Protection Initiative'. The site contacted the agencies as courtesy to notify them about the identification of low levels of tritium found within the site's protected area from a potential new source. Samples were taken, and no regulatory limits were exceeded. The site team is working with industry experts on pinpointing the cause and installing an extraction well to remediate the situation.
      "This report is being made in accordance with 10 CFR 50.72(b)(2)(xi), as a result of notification to offsite agencies.
      "The Licensee has notified the NRC Resident Inspectors.
      "There is no risk to plant employees, the public or drinking water."

See Attachment IA and lB for analyses results from samples collected for the GWPP.

Page 25

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT DESCRIPTION OF CHANGES TO THE OFFSITE DOSE ASSESSMENT MANUAL Before implementation of the following described changes, a review was perfom1ed to validate that the levels ofradioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I were not affected. The review also verified that the changes did not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. Revision 35 ~Revision 36 Revision 36 to the ODAM was made effective on 9/2/2016. Changes implemented included: Table of Contents:

Revised organization due to additional pages and data.

Basis of Mixing Ratios:

Cedar River annual average flow was updated using U.S. Geological Survey-Iowa Data Book for water year records 1902-2015.

Figure 3-2:

Revised color map to include GPS compass overlay for sector delineation.

Figure 5-1:

Revised maps to include new REMP-GWPP sampling points for new monitoring wells and electrical vaults.

Table 5-1:

Revised REMP-GWPP sampling locations to include D-16a soil-precipitation sampling, twenty-two additional electrical vault sampling locations (D-73 to D-75, D-87 to D-90, D-92 to D-95, D-97, D-98, D-100 to D-106 and D-119 to D-121), eight new monitoring wells (D-62 to D-67), and two new extraction wells (D68 and D-69).

Table 7.1-2, Section C:

Revised "Clean" Systems Batch Release sample points to include FRAC tanks.

6.1.2/7.1.2 Liquid Effluent Concentration:

Revised "Clean" Systems Batch Release sample points to include FRAC tanks.

Appendix A:

Revised Dose Transfer Factors for Radionuclides in Effluent Air to include Fe-55.

Revision 36 ~Revision 37 Revision 37 to the ODAM was made effective on 2/9/2017. Changes implemented included: Offsite Dose Assessment Manual Title Page: Page 26

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT

Licensing Manager, Emergency Planning (EP), and Chemistry Manager are required signatories. In addition, the position title "Plant Manager" was changed to "Site Director".

Section 1.0:

Inclusion of the Groundwater Protection Program (GWPP). The GWPP compliments the Radiological Environmental Monitoring Program (REMP).

Section 2.3:

Revised Basis of Mixing Ratios to include the City of Palo, Iowa for alluvial well withdraw and the distance to the City of Cedar Rapids alluvial well field.

Section 2.8:

Revised narrative to include:

  "In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than(<) 20,000 pCi/L.

Groundwater samples are analyzed on-site and validated by off-site secondary laboratory. Off-site laboratory results are published in Annual Radiological Material Release Report and Annual Radiological Environmental Report." Figure 3-2:

Revised color map.

Figure 5-1:

Revised maps to include new REMP-GWPP sampling points for new monitoring wells.

Figure 5-2:

Revised maps to include new Palo, Iowa, air sampler and TLD location.

Table 5-1:

Revised REMP-GWPP sampling locations to include new Palo, Iowa air sampler (D-5a),

relocate Cedar River bed sediment sampling (D-49), on-site drinking water sample location (D-52), inclusion of a formal control sampling location (D-56) for REMP-GWPP quality assurance samples, inclusion of new goat milk sampling location (D-76), and fifteen new monitoring wells. Radioactive Liquid Effluent Concentration 0 7.1.2:

Inclusion within OSR 7.1.2.6 for GWPP mitigation system.

Page 27

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table 7.1-2, Section D:

Inclusion of new subsection "D" for GWPP Mitigation System for continuous liquid effluent release.

Radiological Environmental Monitoring Program 0 6.3.2:

Inclusion of REMP and GWPP under Offsite Dose Assessment Controls Table 6.3-1:
Inclusion ofREMP drinking water monthly samples (change from GWPP quarterly) and change from semi-monthly to monthly milk sampling.

Table 6.3-2:

Inclusion of GWPP exposure pathway and/or sample type, minimum number of samples, sampling schedule, and type and frequency of analysis.

Table 6.3-3:

Sequence change in table order number.

Table 6.3-4:

Sequence change in table order number.

Bases Section, Liquid Effluent Concentration 6.1.2/7.1.2:

Remove acronyms and state, "principal gamma emitters and iodine."
Add paragraph:

"The GWPP mitigation system sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents in the shallow groundwater. Further, the GWPP mitigation plan support a reduction in contaminate concentration such that releases are expected below Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/L."

Misspelling correction for "Cedar River."

Changes to the ODAM:

Update section "b" to remove title "Plant Manger" and replace title with "Site Director".

ODAM Revision Date Histo Revision: 29 30 31 32 33 34 35 36 37 Date: 9/15/11 3/11/13 8/12/14 3/19/15 11/4/15 12/18/15 3/1/16 9/2/16 2/9/17 Page 28

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1: GROUND WATER PROTECTION PROGRAM RESULTS Presented in Attachment IA are analysis results from the site Ground Water Protection Program (GWPP) as determined by the site laboratory.

Gamma Spectroscopy results for site surface water samples.
Tritium results for site surface water samples
Gamma Spectroscopy results for sewage effluent samples.

The Duane Arnold chemistry laboratory participates in Cross Check Program with the firm: Eckert & Ziegler Analytics from Atlanta GA. The Radiochemistry Cross Check program results are available upon request. Presented in Attachment lB are analysis results from site's Ground Water Protection Program (GWPP) as detennined by a contracted vendor laboratory

Tritium results for site monitoring well samples.
Conditional analyses results for hard-to-detect isotopes and gamma emitters for select monitoring well and surface water samples.
Tritium results for site precipitation samples.
Strontium-90, Tritium and Gamma Spectroscopy results for site soil samples.
Supplemental Analyses for electrical vault and drinking water sample locations The vendor laboratory providing these GWPP sample analysis results is Environmental fuc. Midwest Laboratory of Northbrook, IL. The Environmental Inc. laboratory pru1icipates in several cross check programs. These cross check program results are presented in the 2016 Duane Arnold Energy Center Annual Radiological Environmental Operating Report or by request.

Groundwater Protection Program details can be found in Attachment 2, the Duane Arnold Offsite Dose Assessment Manual (ODAM), Table 6.3-2, and sampling locations can be found in ODAM, Table 5-1. Specifically, GWPP sample locations are identified by station number, GWPP, and station location and sample type. A simplified map of enviromnental sample locations can be found in the ODAM, Figure 5-1 and Figure 5-2. GWPP Sampling Deviations Sample Collection Analysis Location Comments Tvoe Period Precip Tritium D-127, D-128 January No viable sample collected Attachment 1 Cover Sheets Page 1 of 1

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB Groundwater Protection Program Summary The following data can also be found in the Duane Arnold Energy Center Annual Radiological Environmental Operating Report Attachment lA 1

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB D-69 06109116 3_2016-06-09_005 BA-140 < 2.50E-08 uCilml CE-144 < 9.02E-08 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.14E-08 UCi/ml CS-137 < 8.11 E-09 uCiiml FE-59 < 1. 72E-08 uCi/ml 1-131 < 7.56E-09 UCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.44E-08 uCi/ml MN-54 < 8.08E-09 uCi/ml ZN-65 < 2.41 E-08 UCi/ml D-68 06/03/16 3_2016-06-03_002 BA-140 < 2.47E-08 uCi/ml CE-144 < 7.19E-08 uCi/ml C0-58 < 7.96E-09 uCi/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 1.43E-08 uCi/ml CS-137 < 1.10E-08 uCi/ml FE-59 < 1.71E-08 uCi/ml 1-131 < 1.01 E-08 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.31 E-08 uCi/ml MN-54 < 8.07E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 07/29/16 3_2016-07-29_010 BA-140 < 2.52E-08 uCi/ml CE-144 < 7.66E-08 uCi/ml C0-58 < 7.99E-09 uCi/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 1.19E-08 uCi/ml CS-137 < 1.09E-08 uCi/ml FE-59 < 1.72E-08 UCi/ml 1-131 < 1.04E-08 uCl/ml K-40 < 1.1 OE-07 uCi/ml LA-140 < 1.52E-08 uCl/ml MN-54 < 1.30E-08 uCi/ml ZN-65 < 2.58E-08 uCl/ml 06/27/16 3_2016-06-27_005 BA-140 < 2.92E-08 uCl/ml CE-144 < 1.01 E-07 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCilml CS-134 < 1.12E-08 UCi/ml CS-137 < 1.16E-08 uCl/ml FE-59 < 1. 72E-08 UCi/ml 1-131 < 9.14E-09 uCl/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.44E-08 uCl/ml MN-54 < 1.39E-08 uCl/ml ZN-65 < 1.93E-08 uCl/ml 0*73 11/07/16 3_2016-11-07_003 BA*140 < 3.02E-08 UCi/ml CE-144 < 1.04E-07 uCi/ml C0-58 < 7.97E-09 uCl/ml C0-60 < 1.10E-08 UCl/ml CS-134 < 8.99E-09 uCl/ml CS-137 < 9.24E-09 uCi/ml FE-59 < 1.77E-08 uCl/ml 1-131 < 5.83E-09 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.37E-08 uCi/ml MN-54 < 8.08E-09 uCl/ml ZN-65 < 2.85E-08 uCi/ml 11/07/16 2_2016*11-07_004 BA-140 < 1.88E-08 uCi/ml CE-144 < 9.15E-08 uCi/ml C0-58 < 6.42E-09 uCl/ml C0-60 < 9.51 E-09 uCl/ml CS-134 < 1.01E-08 uCl/ml CS-137 < 1.08E-08 uCl/ml FE-59 < 1.57E-08 uCl/ml 1-131 < 1.13E-08 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.26E-08 uCi/ml MN-54 < 1.11 E-08 uCl/ml ZN-65 < 2.52E-08 uCl/ml D-88 07/12/16 3_2016-07-12_008 BA-140 < 2.49E-08 uCi/ml CE-144 < 5.57E-08 uCl/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1. 1OE-08 uCUml CS-134 < 8.34E-09 uCi/ml CS-137 < 8.11 E-09 uCiiml FE-59 < 1.72E-08 uCi/ml 1-131 < 7.13E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.41E-08 uCi/ml MN-54 < 9.47E-09 uCl/ml ZN-65 < 1. 93E-08 uCl/ml D-89 07/11/16 3_2016-07*11_004 BA-140 < 2.47E-08 uCl/ml CE-144 < 6.59E-08 UCl/ml C0-58 < 7.97E-09 uCi/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 1.30E-08 uCi/ml CS-137 < 8.11E-09 UCi/ml FE-59 < 1. 72E-08 uCl/ml 1-131 < 6.4BE-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.34E-08 uCi/ml MN-54 < 8.08E-09 uCi/ml ZN-65 < 1.93E-OB ucl/ml D-90 03/08/16 3_2016-03-08_007 BA-140 < 2.48E-08 UCi/ml CE-144 < 4.98E-08 uCi/ml C0-58 < 7.97E-09 uCl/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 1.35E-08 UCi/ml CS-137 < 8.11 E-09 uCl/ml FE-59 < 1.72E-OB uCl/ml 1-131 < 5.84E-09 UCl/ml K-40 < 1.82E-07 uCi/ml LA-140 < 1.39E-08 uCi/ml MN-54 < 8.0BE-09 uCi/ml ZN-65 < 1.93E-08 uCl/ml D-92 03/08116 3_2016-03-08_006 BA-140 < 2.48E-08 UCi/ml CE-144 < 5.69E-08 uCi/ml C0-58 < 7.97E-09 uCl/ml C0-60 < 1.10E-OB uCl/ml CS-134 < 8.33E-09 UCi/ml CS-137 < 8.66E-09 uCi/ml FE-59 < 1.72E-08 uCi/ml 1-131 < 5.84E-09 uCl/ml K-40 < 1.10E-07 UCi/ml LA-140 < 1.38E-08 uCi/ml MN-54 < 8.59E-09 uCi/ml ZN-65 < 1.93E-08 uCl/ml D-93 03111/16 3_2016-03-11_003 BA-140 < 2.48E-08 uCi/ml CE-144 < 7.82E-08 uCi/ml C0-58 < 7.97E-09 uCi/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 8.33E-09 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1. 72E-08 uCl/ml 1-131 < 7.10E-09 uCilml K-40 < 1.10E-07 uCi/ml LA-140 < 1.38E-08 uCi/ml MN-54 < 8. 76E-09 uCi/ml ZN-65 < 1.93E-08 uCl/ml Attachment lA 2

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB D-97 03/08/16 3_2016-03-08_005 BA-140 < 2.49E-08 uCi/ml CE-144 < 4.98E-08 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.08E-08 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1. 72E-08 uCilml 1-131 < 6.23E-09 uCi/ml K-40< 1.10E-07 uCi/ml LA-140 < 1.42E-08 uCilml MN-54 < 1.02E-08 uCi/ml ZN-65 < 1.93E-08 uCi/ml D-100 11/07/16 3_2016-11-07_004 BA-140 < 2.49E-08 uCi/ml CE-144 < 9.02E-08 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.1 OE-08 uCi/ml CS-134 < 1.09E-08 uCi/ml CS-137 < 1.02E-08 uCi/ml FE-59 < 1.72E-08 uCi/ml 1-131 < 6.55E-09 uCi/ml K-40 < 1.10E-07 uCilml LA-140 < 1.42E-08 uCilml MN-54 < 8.08E-09 uCilml ZN-65 < 1. 93E-08 uCi/ml D-101 11/07/16 3_2016-11-07_008 BA-140 < 2.49E-08 uCi/ml CE-144 < 6.84E-08 uCilml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCilml CS-134 < 1.36E-08 uCi/ml CS-137 < 8.11E-09 uCilml FE-59 < 1.72E-08 uCilml 1-131 < 7.91E-09 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.42E-08 uCi/ml MN-54 < 8.08E-09 uCilml ZN-65 < 1.93E-08 uCi/ml D-103 03/07/16 3_2016-03-07_005 BA-140 < 2.47E-08 uCilml CE-144 < 5.63E-08 uCilml C0-58 < 7.96E-09 uCilml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.28E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.71E-08 uCilml 1-131 < 6.13E-09 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.32E-08 uCilml MN-54 < 1.15E-08 uCilml ZN-65 < 1.93E-08 uCilml D-104 03/07/16 3_2016-03-07_006 BA-140< 2.47E-08 uCilml CE-144 < 7.41 E-08 uCi/ml C0-58 < 7.97E-09 uCilml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.01E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1. 72E-08 uCilml 1-131 < 5.80E-09 uCi/ml K-40 < 1.10E-07 uCilml LA-140 < 1.34E-08 uCi/ml MN-54 < 8.08E-09 uCilml ZN-65 < 1.93E-08 uCi/ml D-105 03111/16 3_2016-03-11_002 BA-140 < 2.48E-08 uCi/ml CE-144 < 8.98E-08 uCi/ml C0-58 < 8.21E-09 uCi/ml C0-60< 1.10E-08 uCi/ml CS-134 < 1.02E-08 uCi/ml CS-137 < 8.11E-09 uCilml FE-59 < 1.72E-08 uCilml 1-131 < 6.49E-09 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.36E-08 uCilml MN-54 < 8.08E-09 uCilml ZN-65 < 1.93E-08 uCi/ml D-107 08/07/16 3_2016-08-08_002 BA-140< CS- 2. 62E-08 uCi/ml CE-144 < 4.85E-08 uCi/ml C0-58 < 8. 05E-09 uCilml C0-60 < 1.39E-08 uCi/ml 134< 8.34E-09 uCilml CS-137 < 8.11E-09 uCilml FE-59 < 1.74E-08 uCilml ~131 < 6.34E-09 uCi/ml K-40 < 1.10E-07 uCilml LA-140 < 2.04E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 10/02116 3_2016-10-03_005 BA-140 < 2.58E-08 uCi/ml CE-144 < 9.10E-08 uCilml C0-58 < 8.03E-09 uCilml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.84E-09 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 6.21 E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.86E-08 uCi/ml MN-54 < 9.84E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 09/18/16 3_2016-09-19_004 BA-140< 2.58E-08 uCi/ml CE-144 < 1.09E-07 uCi/ml C0-58 < 8.02E-09 uCilml C0-60< 1.1 OE-08 uCilml CS-134 < 1.44E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E-08 uCilml 1-131 < 6.56E-09 uCilml K-40 < 1.10E-07 uCi/ml LA-140 < 1.82E-08 uCi/ml MN-54 < 9.23E-09 uCilml ZN-65 < 2.36E-08 uCi/ml 06/26/16 3_2016-06-27_002 BA-140 < 2.61 E-08 uCi/ml CE-144 < 9.84E-08 uCilml C0-58 < 8.05E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.24E-08 uCi/ml CS-137 < 1.02E-08 uCi/ml FE-59 < 1.74E-08 uCilml 1-131 < 7. 70E-09 uCilml K-40 < 1.1 OE-07 uCi/ml LA-140 < 2.04E-08 uCi/ml MN-54 < 1.22E-08 uCi/ml ZN-65 < 1.93E-08 uCi/ml Attachment lA 3

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB 02107/16 3_2016.02.08_007 BA-140 < 2.60E-08 uCi/ml CE-144 < 7.12E-08 uCl/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.1 OE-08 uCi/ml CS-134 < 9.45E-09 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 8.46E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.95E-08 uCl/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 03/06/16 3_2016.03.07_001 BA-140 < 2.59E-08 uCi/ml CE-144 < 4.11E-08 uCl/ml C0-58 < 8.03E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.01E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 6.61E-09 uCi/ml K-40 < 1.33E-07 uCi/ml LA-140 < 1.88E-08 uCi/ml MN-54 < 8.09E-09 uCl/ml ZN-65 < 2.29E-08 uCi/ml 03/20/16 3_2016.03-21_004 BA-140 < 2.60E-08 uCi/ml CE-144 < 9.40E-08 uCi/ml C0-58 < 8.04E-09 uCl/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 1.19E-08 uCi/ml CS-137 < 1.20E-08 uCi/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 8.48E-09 uCl/mi K-40 < 1.1 OE-07 uCi/ml LA-140 < 1.98E-08 uCi/ml MN-54 < 8.09E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml 04117/16 3_2016.04-18_001 BA-140 < 2.65E-08 uCi/ml CE-144 < 4.01E-08 uCi/ml C0-58 < 8.02E-09 uCl/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.01E-08 uCi/ml CS-137 < 8.11E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 6.72E-09 uCi/ml K-40 # 1.79E-07 uCi/ml LA-140 < 1.81E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 05/01/16 3_2016.05.02_001 BA-140 < 2.59E-08 uCl/ml CE-144 < 7.34E-08 uCl/ml C0-58 < 8.03E-09 uCl/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.19E-08 uCi/ml CS-137 < 9.46E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 7.15E-09 uCi/ml K-40# 1.94E-07 uCi/ml LA-140 < 1.92E-08 uCl/ml MN-54 < 9.84E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 08/21/16 3_2016-08-22_002 BA-140 < 2.47E-08 uCl/ml CE-144 < 7.62E-08 uCl/mi C0-58 < 8.45E-09 uCl/ml C0-60 < 1.1 OE-08 uCi/ml CS-134 < 1.25E-08 uCl/ml CS-137 < 9.86E-09 uCl/ml FE-59 < 1.72E-08 uCl/ml 1-131 < 7.94E-09 uCl/ml K-40 < 1.10E-07 uci/ml LA-140 < 1.34E-08 uCl/ml MN-54 < 8.08E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml 10/30/16 3_2016-10-31_001 BA-140 < 3.00E-08 uCi/ml CE-144 < 1.02E-07 uCl/ml C0-58 < 8.02E-09 uCl/ml C0-60 < 1.10E.Q8 uCl/ml CS-134 < 1.19E-08 uCl/ml CS-137 < 9.96E-09 uCl/ml FE-59 < 1.73E-08 uCl/ml 1-131 < 6.15E-09 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.78E-08 uCl/ml MN-54 < 8.09E-09 uCl/ml ZN-65 < 2.41E-08 uCl/ml 11/13/16 3_2016-11-14_003 BA-140 < 2.90E-08 uCi/ml CE-144 < 9.96E-08 UCl/ml C0-58 < 1.12E-08 uCl/ml C0-60 < 1.1 OE-08 uCl/ml CS-134 < 1.71E-08 uCl/ml CS-137 < 1.26E-08 uCl/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 6.66E-09 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.95E-08 uCl/ml MN-54 < 9.03E-09 uCl/ml ZN-65 < 2.90E-08 uCl/ml 11/27/16 3_2016-11-28_003 BA-140 < 2.59E-08 uCl/ml CE*144 < 6.15E-08 uCl/ml C0-58 < 8.03E.Q9 uCl/ml C0-60 < 1.1 OE-08 uCi/ml CS-134 < 1.09E-08 uCl/ml CS-137 < 8.11E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 9.69E-09 uCi/ml K-40 < 1.1 OE-07 uCl/ml LA-140 < 1.92E-08 uCl/ml MN-54 < 1.01E-08 uCl/ml ZN-65 < 1.93E-08 uCl/ml 12126/16 3_2016-12-27_002 BA-140 < 2.60E-08 uCi/ml CE-144 < 7.59E-08 uCi/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.17E-08 uCl/ml CS-134 < 8.34E-09 uCi/ml CS-137 < 1.32E-08 uCl/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 7.18E-09 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.97E-08 uCi/ml MN-54 < 8.53E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 05/29/16 3_2016.05-29_006 BA-140 < 2.49E-08 uCi/ml CE-144 < 4.76E-08 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCl/ml CS-134 < 8.34E-09 uCl/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.72E-08 uCi/mi 1-131 < 7.14E-09 uCl/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.42E-08 uCi/ml MN-54 < 9.82E-09 uCi/ml ZN-65 < 2.28E-08 uCl/ml 12111/16 3_2016-12-12_004 BA-140 < 2.59E-08 uCi/ml CE-144 < 7.80E-08 uCl/ml C0-58 < 9.77E-09 uCi/ml C0-60 < 1.1 OE-08 uCl/ml CS-134 < 1.41 E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 9.79E-09 uCi/ml K-40 < 1.48E-07 uCi/ml LA-140 < 1.90E-08 uCi/ml MN-54 < 9.84E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 01/10/16 3_2016.01-11_002 BA-140 < 2.60E-08 uCi/ml CE-144 < 9.20E-08 uCi/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.29E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 6.28E-09 uCi/ml K-40 # 1.94E-07 uCi/ml LA-140 < 1.96E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 2.75E-08 uCi/ml 02121/16 3_2016.02-22_005 BA-140 < 2.59E-08 uCi/ml CE-144 < 7.12E-08 uCi/ml C0-58 < 8.03E-09 uCl/ml C0-60 < 1.1 OE-08 uCi/ml CS-134 < 8.34E-09 uCi/ml CS-137 < 9.59E-09 uCi/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 8.92E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.92E-08 uCi/ml MN-54 < 8.09E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml Attachment lA 4

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATIACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB 04/03/16 3_2016-04-04_002 BA-140 < 2.96E-08 uCi/ml CE-144 < 8.03E-08 uCilml C0-58 < 8.03E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.05E-08 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 6.26E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.92E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 05/15/16 3_2016-05-16_005 BA-140 < 2.60E-08 uCi/ml CE-144 < 9.31 E-08 uCi/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 9.20E-09 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 6.65E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.95E-08 uCi/ml MN-54 < 1.01 E-08 uCi/ml ZN-65 < 1.93E-08 uCi/ml 06/12/16 3_2016-06-13_005 BA-140 < 2.49E-08 uCi/ml CE-144 < 9.02E-08 uCi/ml C0-58 < 7.98E-09 uCilml C0-60 < 1.10E-08 uCilml CS-134 < 8.84E-09 uCilml CS-137 < 8.11 E-09 uCilml FE-59 < 1.74E-08 uCilml 1-131 < 6.21E-09 uCilml K-40 < 1.10E-07 uCi/ml LA-140 < 1.97E-08 uCilml MN-54 < 8.58E-09 uCilml ZN-65 < 1.93E-08 uCilml 07/10/16 3_2016-07-11_001 BA-140 < 2.57E-08 uCilml CE-144 < 1.00E-07 uCilml C0-58 < 8.02E-09 uCi/ml C0-60 < 1.10E-08 uCilml CS-134 < 1.22E-08 uCilml CS-137 < 9.27E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 1.14E-08 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.80E-08 uCi/ml MN-54 < 8.09E-09 uCilml ZN-65 < 2.60E-08 uCilml 07/24/16 3_2016-07-25_005 BA-140 < 2.61 E-08 uCl/ml CE-144 < 9.77E-08 uCilml C0-58 < 8.04E-09 uCilml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.34E-09 uCi/ml CS-137 < 9.10E-09 uCilml FE-59 < 1.74E-08 uCilml 1-131 < 9.57E-09 uCilml K-40 < 1.10E-07 uCi/ml LA-140 < 2.00E-08 uCilml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCilml D-119 09/30/16 3_2016-09-30_020 BA-140 < 2.51 E-08 uCi/ml CE-144 < 6.35E-08 uCi/ml C0-58 < 7.99E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.34E-09 uCilml CS-137 < 8.11E-09 uCilml FE-59 < 1. 72E-08 uCilml 1-131 < 5.94E-09 uCilml K-40 < 1.10E-07 uCi/ml LA-140 < 1.50E-08 uCilml MN-54 < 9.43E-09 uCilml ZN-65 < 1.93E-08 uCilml 07/14/16 3_2016-07-14_008 BA-140 <CS- 2.48E-08 uCi/ml CE-144 < 8.95E-08 uCilml C0-58 < 8.45E-09 uCilml C0-60 < 1.10E-08 uCilml 134< 1.32E-08 uCilml CS-137 < 8.66E-09 uCilml FE-59 < 1. 72E-08 uCi/ml 1-131 < 5.82E-09 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.35E-08 uCilml MN-54 < 8.08E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 11/07/16 3_2016-11-07_009 BA-140 < 2.49E-08 uCi/ml CE-144 < 8.32E-08 uCi/ml C0-58 < 7.98E-09 uCilml C0-60 < 1.10E-08 uCilml CS-134 < 1.26E-08 uCilml CS-137 < 8.11E-09 uCilml FE-59 < 1. 72E-08 uCi/ml 1-131 < 6.55E-09 uCilml K-40# 2.83E-07 uCilml LA-140 < 1.42E-08 uCilml MN-54 < 8.08E-09 uCilml ZN-65 < 1.93E-08 uCilml 05118/16 3_2016-05-19_002 BA-140 < 2.60E-08 uCilml CE-144 < 5.13E-08 uCilml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.34E-09 uCi/ml CS-137 < 8.11 E-09 uCilml FE-59 < 1.74E-08 uCilml 1-131 < 6.26E-09 uCilml K-40# 3.43E-07 uCi/ml LA-140 < 1.93E-08 uCilml MN-54 < 1.11 E-08 uCilml ZN-65 < 1.93E-08 uCilml 07/13/16 3_2016-07-13_010 BA-140 < 2.50E-08 uCilml CE-144 < 5.92E-08 uCilml C0-58 < 7.98E-09 uCilml C0-60 < 1.10E-08 uCilml CS-134< 9.02E-09 uCi/ml CS-137 < 8.11E-09 uCilml FE-59 < 1. 72E-08 uCi/ml 1-131 < 5.91E-0_9 uCilml K-40 < 1.10E-07 uCilml LA-140 < 1.46E-08 uCilml MN-54 < 8.08E-09 uCi/ml ZN-65 < 1.93E-08 uCilml Attachment lA 5

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lA: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB 0-120 11/07/16 3_2016-11-07_010 BA-140 < 2.49E-08 uCi/ml CE-144 < 6.65E-08 uCi/ml C0-58 < 7.98E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.04E-08 UCi/ml CS-137 < 8.61E-09 uCi/ml FE-59 < 1.72E-08 uCi/ml 1-131 < 5.88E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.42E-08 uCi/ml MN-54 < 8.0SE..09 uCl/ml ZN-65 < 1.93E-08 uCi/ml 09/30/16 3_2016-09-30_021 BA-140 < 2.51E-08 uCi/ml CE-144 < 5.63E..Q8 uCi/ml C0-58 < 7.99E..Q9 uCl/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.34E-09 uCl/ml CS-137 < 9.10E..Q9 uCi/ml FE-59 < 1. 72E..Q8 uCi/ml 1-131 < 6.95E-09 uCi/ml K-40 < 1. 1OE-07 uCi/ml LA-140 < 1.51 E-08 uCi/ml MN-54 < 1.32E-08 uCi/ml ZN-65 < 1.93E-08 UCi/ml D-121 05/18/16 3_2016-05-19_003 BA-140 < 2.60E-08 uCi/ml CE-144 < 6.71E-08 uCl/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 9.10E-09 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1.74E..Q8 uCi/ml 1-131 < 7.63E..09 uCl/ml K-40 # 2.68E-07 uCi/ml LA-140 < 1.95E..Q8 uCi/ml MN-54 < 9.27E-09 uCi/ml ZN-65 < 1.93E-08 uCl/ml 07/13/16 3_2016-07-13_013 BA-140 < 2.81 E-08 uCl/ml CE-144 < 9.06E..Q8 uCi/ml C0-58 < 7.99E..Q9 uCi/ml C0-60 < 1.10E..08 uCl/ml CS-134 < 1.00E-08 uCl/ml CS-137 < 8.11E..09 uCi/ml FE-59 < 1.72E-08 uCi/ml 1-131 < 8.38E..09 uCi/ml K-40# 2.53E-07 uCl/ml LA-140 < 1.52E..Q8 uCl/ml MN-54 < 8.33E..Q9 uCi/ml ZN-65 < 1.93E..Q8 uCi/ml 11/07/16 3_2016-11-08_002 BA-140 < 2.55E-08 uCi/ml CE-144 < 6.89E..Q8 uCi/ml C0-58 < 8.01E-09 uCl/ml C0-60 < 1.10E..08 UCi/ml CS-134 < 8.34E-09 uCi/ml CS-137 < 8.11 E..09 uCl/ml FE-59 < 1.73E-08 uCl/ml 1-131 < 6.45E..09 uCl/ml K-40 < 1.31E-07 uCl/ml LA-140 < 1.68E-08 uCi/ml MN-54 < 8.09E..Q9 uCl/ml ZN-65 < 1.93E..Q8 uCi/ml D-122 11/08/16 2_2016-11-11_002 BA-140 < 2.54E-08 uCl/ml CE-144 < 8.80E..Q8 uCl/ml C0-58 < 6.59E-09 uCl/ml C0-60 < 9.51 E..09 uCi/ml CS-134 < 8.12E..Q9 uCl/ml CS-137 < 6.34E..Q9 uCi/ml FE-59 < 1.60E..08 uCi/ml 1-131 < 9.32E..Q9 uCi/ml K-40 < 9.61 E-08 uCl/ml LA-140 < 3.80E..Q8 uCl/ml MN-54 < 1.13E-08 uCi/ml ZN-65 < 1.70E..08 uCi/ml 05/18/16 3_2016-05-19_004 BA-140 < 2.61 E-08 uCl/ml CE-144 < 6.71E..Q8 uCl/ml C0-58 < 8.04E..09 uCl/ml C0-60 < 1.10E..Q8 uCi/ml CS-134 < 1.26E-08 uCl/ml CS-137 < 8.11E..09 ucl/ml FE-59 < 1.74E-08 uCl/ml 1-131 < 6.31E..Q9 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 2.00E..08 uCl/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E..Q8 uCl/ml 07/06/16 3_2016-07-06_006 BA-140 < 2.49E-08 uCl/ml CE-144 < 8.85E-08 uCl/ml C0-58 < 7.98E-09 uCl/ml C0-60< 1.10E-08 ucl/ml CS-134 < 8.89E-09 uCi/ml CS-137 < 8.11E..09 uCl/ml FE-59 < 1.72E-08 uCl/ml 1-131 < 7.13E..09 ucl/ml K-40 < 1.1 OE-07 uCl/ml LA-140 < 1.41E-08 uCl/ml MN-54 < 8.08E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml 09/12116 3_2016-09-12_007 BA-140 <CS- 2.49E-08 uCl/ml CE-144 < 7.33E-08 uCi/ml C0-58 < 7.97E..Q9 uCi/ml C0-60 < 1.10E..Q8 uCi/ml 134 < 8.33E-09 uCl/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1. 72E..Q8 UCl/ml 1-131 < 6.20E..Q9 uCl/ml K-40 < 1.10E-07 uCl/ml LA-140 < 1.39E..Q8 uCl/ml MN-54 < 8.08E-09 uCi/ml ZN-65 < 1.93E..Q8 uCl/ml 10/17/16 3_2016-10-17_003 BA-140 < 2.49E-08 UCl/ml CE-144 < 4.91E..Q8 uCi/ml C0-58 < 7.97E-09 uCl/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.39E-08 uCl/ml CS-137 < 8.11 E..09 uCi/ml FE-59 < 1.72E..Q8 UCl/ml 1-131 < 6.53E..Q9 UCi/ml K-40 < 1.10E-07 ucl/ml LA-140 < 1.40E..Q8 uCilml MN-54 < 8.0SE-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml D-123 07/13/16 3_2016-07-13_015 BA-140 < 2.52E-08 uci/ml CE-144 < 7.37E..Q8 uCi/ml C0-58 < 7.99E-09 uCi/ml C0-60 < 1.10E..08 uCi/ml CS-134 < 9.45E-09 uCi/ml CS-137 < 8.11 E..09 uCi/ml FE-59 < 1.72E-08 uCl/ml 1-131 < 5.96E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.53E..Q8 uCi/ml MN-54 < 1.18E..Q8 uCi/ml ZN-65 < 1.93E..Q8 uCi/ml Attachment lA 6

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1A: GROUND WATER PROTECTION PROGRAM RESULTS-DAEC LAB D-124 07/13/16 3_2016-07-13_016 BA-140 < 2.52E-08 uCi/ml CE-144 < 7.37E-08 uCi/ml C0-58 < 7.99E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.27E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml FE-59 < 1. 72E-08 uCi/ml 1-131 < 5.96E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 1.53E-08 uCi/ml MN-54 < 9.88E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 11/08/16 3_2016-11-11_004 BA-140 < 2.98E-08 uCi/ml CE-144 < 7.16E-08 uCi/ml C0-58 < 1.04E-08 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.43E-08 uCi/ml CS-137 < 9.74E-09 uCi/ml FE-59 < 1.79E-08 uCi/ml 1-131 < 9.37E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 4.36E-08 uCi/ml MN-54 < 8.13E-09 uCi/ml ZN-65 < 2.44E-08 uCi/ml 05/18/16 3_2016-05-19_005 BA-140 < 2.61E-08 uCi/ml CE-144 < 5.87E-08 uCi/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.05E-08 uCi/ml CS-137 < 1.06E-08 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 7.37E-09 uCi/ml K-40 < 1.1 OE-07 uCi/ml LA-140 < 2.00E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml D-125 07/13/16 3_2016-07-13_017 BA-140 < 2.52E-08 uCi/ml CE-144 < 6.98E-08 uCi/ml C0-58 < 7.99E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 9.96E-09 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1.72E-08 uCi/ml 1-131 < 6.33E-09 uCi/ml K-40 < 1.1 OE-07 uCi/ml LA-140 < 1.54E-08 uCi/ml MN-54 < 1.41E-08 uCl/ml ZN-65 < 1.93E-08 uCi/ml 11/08/16 3_2016-11-11_005 BA-140 < 2.91E-08 uCi/ml CE-144 < 6.13E-08 uCi/ml C0-58 < 8.20E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 8.36E-09 uCi/ml CS-137 < 8.11 E-09 uCl/ml FE-59 < 1.80E-08 uCi/ml 1-131 < 9.11E-09 uCi/ml K-40< 1.1 OE-07 uCi/ml LA-140 < 4.56E-08 uCi/ml MN-54 < 8.13E-09 uCi/ml ZN-65 < 2.25E-08 uCi/ml 05/18/16 3_2016-05-19_006 BA-140 < 2.61E-08 uCi/ml CE-144 < 5.87E-08 uCi/ml C0-58 < 8.04E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.03E-08 uCi/ml CS-137 < 8.11 E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml 1-131 < 7.69E-09 uCi/ml K-40 < 1.10E-07 uCi/ml LA-140 < 2.03E-08 uCl/ml MN-54 < 8.09E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 03/10/16 3_2016-03-10_003 BA-140 < 2.47E-08 uCi/ml CE-144 < 8.39E-08 uCi/ml C0-58 < 7.96E-09 uCi/ml C0-60 < 1.10E-08 uCi/ml CS-134 < 1.17E-08 uCi/ml CS-137 < 1.02E-08 uCl/ml FE-59 < 1.71E-08 uCi/ml 1-131 < 5. 78E-09 uCi/ml K-40 < 1.48E-07 uCi/ml LA-140 < 1.31E-08 uCi/ml MN-54 < 9.31E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml A 7

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB Groundwater Protection Program Summary The following data can also be found in the Duane Arnold Energy Center Annual Radiological Environmental Operating Report B 1

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB QUANE ARNOLD Table 21. Soil, analysis for strontium-90 and gamma-emitting isotopes. Collection: Annually Units: pCi/g dry Location D-15a D-16 Lab Code DSO- 2701 DSO- 2702 Date Collected 05-26-16 05-23-16 Sr-90 < 0.048 < 0.032 H-3 {pCi/L) < 148 < 148 K-40 14.33 +/- 0.81 9.53 +/- 0.71 Mn-54 < 0.027 < 0.019 Fe-59 < 0.085 < 0.048 Co-58 < 0.026 < 0.016 Co-60 < 0.020 < 0.023 Zn-65 < 0.053 < 0.053 Nb-95 < 0.052 < 0.027 Zr-95 < 0.038 < Q,Q4? Ru-103 < 0.048 < 0.0?~ Ru-106 < 0.21 < 0.17 Cs-134 < 0.022 < 0.019 Cs-137 0.13 +/- 0.035 " 0.11 +/- 0.0~~ 8 Ce-141 < 0.079 < 0.049 Ce-144 < 0.19 < 0.10 a Cs-137 identified is related to nuclear weapons testing. Attachment lB 2

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATIACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB 0...1. Groundwater Protecti:on Program S1;.1mmary. Precipitation sampl!M!i for tritium analysls. Ut11is: pC~L Lal; Code Date H-3 Lab Code Date H-3 0-016 D-111

    -*-op;*l2Z           ~** .-01101r16"-**   *~*-*~**~*~** .. *;c*l45      *up;:*12a****** .. li1107/16 .. ........  --~-;:*T4s-*   .

Df=l'- 004 02/24.116 .q55 OP* 805 02/24/16 < 155 DP- 1173 (}3114.116 < 146 OP- 1174 03/141113 <:: 150 l)p, 15115 Q.:\}(}8.11 fi ..:: 148 OP- 1506 04/08116 ...: 148 OP- :ff?!:! 05102116 < 149 OP~ 21"73 U5/02116 172 +/- 83" OP- 2773 06Jotf16 < 183 OP- 2714 06/0trte < 183 DP- 3527 07110!16 < 147 01'3- 3!)21 07110it6 431 ::: 98

           .OP- 41!46          0&'01f16                   171 +/- 81             Of', 4147        013J011t6           316 +/- B8 Df:.1- 4611         owo:ma                     161 3: 91            OP* 4676         09:)02116           5H ! 10&

DP- 5342 10l05f16 < 142 DP- 5343 10/05116 554 !98 OP- 6002 11l03f16 < 181J DP- 6083 11100116 < 180 DP* 6890 12/01(16 < 152 DP- 009*1 1:2101l16 < 152 0-112 D-114 OP* 124 01{01116 <; 145 DP* 125 01/0'f/16 659 :t 102 D?-006 0.2124/16 c 155 OP* 801 02124/16 < 100 DP* 1175 03114116 < ~50 DP- 1176 03.114116 < 197 DP* 1507 04I08!'1n 191 +/-B-4 DP- 1500 04/08!16 203+/-122 l'Jp, :B'l'4 Mlll:ll1ii *-. ;.: 149 DP- 2US <15/0!U~G ;m; :;:~- DP-2775 00/01116 <; 183 DP* 2777 OOI01ft6 DP- 3523 07/1Dl16 495 +/- 101 OP- 3524 07110/16 287 :1:g2 OP- 4148 08/01116 < 150 DP- 4149 08/01116 278 +/- 87 Df.'- 4679 0~2116 283 :t9S- OP- 4680 09102116 234 +/-93 DP" 5344 10.105116 1007 ii: 116 DP- 5345. 10/05116 759 +/- 101 OP-6084 11/03118 < 100 DP* 6065 11f03.116 < 180 OP- 6002 12/01116 < 152 DP- 0093 t2i'01116 < 152 0-127 0-128 NOb ND~ DP* 008 02124116 1504 t 141 OP- 809 02124.116 415::: 00 OP* 117fl 03114116 17:9!> *145 op. 1H9 03.!'14116 310 +/- 94 o?-1500 Q4jood6 1004.t126 DP- 151i 04/66i16 s3o :too DP- 2177 MJ02J1B 28~M +/- 187 DP- 2rn; 05!02/16 < 149 DP* 2:778 001'01/16 762 +/- ,122 OP- 2779 06/01116 365 :t 109 DP- 3525 07f10l16 3!l56 ;t 197 DP- 3526 07/10it6 1743;!;144 DP- 4150 OOJ0111fi 2173+/-153 DP* 4151 08l01/H3 734 :I: 100 OP* 4651 091'01116 5387 t229 GP* 4682 09KJ1/16 1000t125 DP- SJ46 10JOS/16 50201234 OP- 5347 10,105116 2794 ;I: 170 DP- 0066 11.IO:l/16 837 :L 119 DP- 6007 111031'16 ":HID m>-

           - . 95.g,i
                   --- .       12101116                  frtO :t 98          rn>-
                                                                              - - 6895  ... - -
                                                                                             ~

12/01{16 .: 152

                                                                             ..,110 _ _ ""'" ..
    ~ "ND" o      No data; sample f!01 availab'e Attachment lB 3

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D-1A. GN'.ltJndwater Protection Program Summary. F>r~clpltation. rnonlhl)' coftec~K:Jns. ar;;illyscs fot gamma @mittlng isotopes. tooaiion: D-16 Coric.en.tr!llio:n (pCrlt) LabC<l(le Date !>!Mn 5

                                                     ~Fe    Q!Co     oc'Co     6zn      9$Nb        1157.:r  1311   "Jl;Ce    1?;1 C1>  14116\'l 1""\::i DP- 122          Oi/07/16          < 2.5 <4.7           < 2.6    < 2.1     <4.3      < 2.4      "'2.a    <; 5.2  "':ts     < 2.IS ..; 15.1     -.: 3.7 OP- 804          021'2411$         ..:::8.3 < 13.2      ... 5.5  "'5.9 11.~
                                                                              <           < 7.3      ..:::g,8 < 8.:5  ..-.*7.7  <6.0 < 3fl.3       ..-.5.B DP- 1173         03f14/t6          <: 6.3      .:6.6    <: 6.3   < 6.2 "'10.2        .;; 8.2 .: 13.1 *: 15.9 < 5.7         ..: 6,, -= 39.S    .;: 7.6 DP- 1505         04100116          <2.8 <2.3           < 2.2.    < 1.9 .; 3.6        < 2..6 <:: 3.5 <3.9         <2.0      *~  2.5 < 12.0     <; 2.0 OP- 2172         05102ft6          <5.0 < 11.6         < 5.2     <ll8     <5.3       <6.3 < 11.8 <S.9            < 5.6     < 5.0 <262         <    5.2 OP* 2713         OOI01f18          < !"6 *: t2.7       <41       ..: 5,4  ..: 6.5    -::66 00 9 7 <9.7           <5.8      <6.6 -::43.1       "'<l.3 DP- 3527          01110/H:l         <2.3 <3.4           < 3.3     <"IA     <4.2      .:::3.2 < 2.9 ..:6.2         <2.8      <Ul -<: 10.6       < 3.4 DP- 4146         00f01f16          < 4.11 <7.5         < 4.7     <3.9     <9.0       ..::7.9 < 7.1 < 11.0        <:!i7     < *t5 < 30.4       < 7.2 OP- 4877          OO'W16            <4.3 .-: 7.9        ..;;5,0   "'1.6    ..;;4,5    -:33       ..:6,7 < 12 t    .-:5.0    < 4.0 .;;22.3      <47 DP- 5342          10!05/16          <3.7 <2.7           <3.4     <3.0      <3.3       e3.0       ..:3_4 ..:6.7    <3.9      <4.0 < 21.9        <32 op. ooa2          11f0311A          <54 < 11.3          <5.3      .:; 3.1  <.4.5     <6.-4       <6.7 < 13.1      <6.1      <5.4 < 24.t!l      < 6.1 OP- 6890         12101/H:i         <6:5        <'38    <4:8      <4.6     < 3:8      <   1,tt   < 8:3 <9.3       <6.3      <5.5 < *m:1       ..: 1. *1 Attachment lB 4

DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB t:J.2, Groumlwa1ar Prcteetlon Prngll!lffi Summary. Ground wator, Mmtitcruig Willis. ar.aly:ros fot tri!itmi '.

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DWW- 4600 071.29116 19768 +/-419 DWW- 6347 ll.Nll.116 43141 +Bf!i OYVW* 497!l OIY04116 14322 ! 359 OWW- 6B3~ Wl5HS 32136 i.!3.i OWW* 5@1 Ol!J1Cl16 10047 t 317 rNWV- 0034 11.122/Hl 40078 +/-58!1 D'NW- 5402 ~!1116 -0097 t 303 OV'/W* 7023 l2121/f6 70035 :+/- 779 DWIN* MOO 00/01116 12494 +/- 338 MW-24A oww. 7024 1:?.'30/ti'I < 1114 -.... ~ M'N*25A ..... ~- f11NW- 7025 1Zi'Z~l1G $677;t191 mw..** 7026 12/:ll!i/HJ 4557 i 211 U\/V.::?BA OWW- 702?' 1;;:..2ms ~n t1w DSW~ 7028 l2/3Qlt6 2922+/-175 Attachment lB 10 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB --~-* 176'1:: 14D 319 :!: 102 474 ! 97 "iij2 B 11 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB ~!.!l.!!njwater Protection Prograrn Sumrn!!:!J. Monitoring wells. analy-s.es for gainmrM:mittmg Isotopes. 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fJ!l'.'W- 7026 t2t.30ll016 -£Ji <3.9 <1.7 <.2."t .;:33 "41 <3.J <.2.9 <3.2 o( 25,9 ..: 71 MIJV-2SA DWW* 7"J27 12121/2016 .,, 2. 3 < 8.2 .:'..M -:: :;u < 5.1 < 6.:2 ..;: 6.:2 : 3.'.'i .-.: J ;> < 48.G < 11.r.J 'tNIJW. 702.S 12'3¢.120113 ..::3.2 -=:;o.9: -=1.9 ..,-3.0 -=6.7 .::'1 ..e. .;;f.3 <32 <3.f:i -<42.7 -to.3 Attachment lB 17 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB .~fldW~ltr ProfetUon Program Summary, Monitoong wells, -eonrJllional .arialyses for gross alpha, 4rorHH'i, nii;;kel-63. strontium-Bf! and s!mnlium-90 Colleetirm Lab Code Date location Gro$$ A~phil< ~'F't.i >>:1Ni o;i:;lr "'s1 oww- sse 2.116,:WUl D-12Ba .: to <602 < t.16 .; 19 < 1s mwv- 793 2/'16!2016 D-134a < 1.1 <674 : 130 < 118 : 0.5 r:IW\flJ- 657 ;(/1'9J°2{l15 D-128a .:: 1.0 =63a < 144 ..: t9 < 1.G fitNW-658 2f19tl01G D-128b "'1.6 <600 "146 < 1.6 < 1.4 tf,NW- 821 2.2s12010 0-128a < 0.9 <631 <; 126 < 1.5 = t.4 DW"V-822 212612015 D-i34a 2.0 t 0.9 .:;531 < 127 = 1 3 c 1.3 OWW-890 31212016 D-t2aa 0.9 ;!: 0.7 -: 644 nW "'1 5 <: 1.0 DWiN- 891 31212016 D134a -: HI .: 671 < t35 <Ui .:; 1 1 DWW 961 3/B/.2016 D-128a .: ~ .0 <655 <tZ1 <: 1, 1 ~: 0.!3 l:NIJiN- 91!8 3.181'2'016 0-134a 15+/-0.8 <:649 < 113 < 1.() '°" () R fYINW- 1027 3o'1C:\"l016 0-128a .: 1,0 <652 .;; 100 ..;; 1.3 ,.,_i:j DWW-1028 3.'10l201t3 0-134~ 13+/-0.8 =$99 < 152 <' l."1 -= 1 1 fJWW- 'l.15i 3116'20113 D-126a <:.11) <639 < 118 ..;; 16 < 1. 1 01/tfiN 1152 31Hll20!1l P-13tt<l H +/-0.8 <670 <: 111 <:UI -r.1.2 DW'W-12CJq wa1w1e D126a ..:u <609 "110 c; 1.3 .-.: ~ 1 DWW- 12(15 Jl'l312U 16 D-134a 11 :t 0.6 <"624 .;: 123 . ;; 15 <ii Dlf.lW 1312 3l3(rt6 4).12:$1i 1.7 +/- 0.8 : 625 .: 149 < 1..il ..;; 1 '7 fYiNVtJ- 13!l 3lJOl2016 D-134a Hi :t 0.8 <625 -: 129 <: 1.1 < 1.0 0\N'-'il* 1740 4l212016 [M2~ < 1.0 < 7!)0 <142 < 2.CI < 1JI OWN- t74S 412/2016 0134a < 1.2 "'690 < t49 "'17 ~;o.9 OVYW 1470 41412016 D-t20a < 1,0 <759 : 1:(3 .:u <0.6 DWW 1471 41412()1$ 013411 <U .: 149 <; 12'3 .::2.0 <: 1 () DV\W- 141'2 4/tilW16 MW-'Z2A 11):!:06 '-' 721 "118 <= 'i.S < 1.IJ rJINW 1473 41612016 MW-21A 2.0 :!: 1.0 <600 <C 13~ < 1.6 < 0.8 r:N'l'o"I* 1742 418/2016 0-12&!! ..:; 1.0 <C 619 < 145 < 1.9 .: 1 n O'M"I- t/'4i 4/812016 0-134a < 10 <720 < 162 "1 t < 1:6 tJ\'VW 174:3 41111201£1 0-1288 <(J.9 <:: 746 = 117 < 1.5 .;: 0.9 D'MN- 1747 4/111;!0~6 tM34a < 1.0 = 741 ; 121 <HI ..; 1. i OWiN-1559 4nJ,'20t6 D-12Sa .: 1.2 <. 7911 <-139 <' 1J5 < 1.0 OW'ofll, 1560 4/13.1:2016 D-13'1-a 1.3 :t0.9 .;: 1'4'9 ; 148 .;: 1.7 "'1 n DW\N- 1779 .j,, ~);fl) 16 lM32a 1 . 4 tO.a ..; B33 < 137 :07 ..: 0.4 riWW- 1712 4.'15/2016 D-128b <: 1.0 < 744 .;: 110 o:0.7 < 0.4 r;J1NW* ~009 4115/2016 tM,2~ ""L1 .:SH~ .: 129 < 2.0 >;1{1 DWW- 2:012 41151'.?016 D-124a t .:2 ;t 0.8 <546 < 130 <24 "- 1.1 D'MN- 17'~4 41if!l2015 D1:2Ba .:: 1.() ...:792 < 12B <14 "'0.9 D'JINJ- 1748 4l1SIW16 D-134a ""1,0 <737 < 1HS .:~A "'1.0 DWW- 2492 4/2()1.20 t6 D-12.Sa .: 1.1 <524 < 127 <:2,2 < L2 Di.WJ- 2497 4l'20f.2016 l>-134a ""12 <<543 .:; 103 -=2.:Z < 1.2 D'WW 2017 4i2U:2016 MW:JOA 1.2 +/-0.9 .; 54~ .; 124 < 1.8 <0,9 D'li\!W-WU) 4.'22t.?o16 0-128.a "'11 <575 <: i18 ;Lil <* i.O _, Analyws, for g.arnma. gross ali:fra, sr-f.9, SrOO, Fl(l5f1 "'id N~ii::i \!1'141 Ile penc.!!Y'.OO 1r 1rili\ll11 iSClr.~l:r > 1K pCi;'L
B 18
DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1B: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D-.20, Groundwatar Pro!.x:tfon Pn>tttam Summa!>!. Monitorillg wells. conc:iit~,onal analy'SI'.!$ for gr(>ss afPha, iron-55. nicl<el-63. suon!lum-89 af'H.i strontium-90 ". Collediain '!c~g~------.~~ ~Code ... 031e Lora lion GmssAlph,-; si;Fe ~'M OW'i/Y- 20 13 4.'.2212016 D134a < 1.3 ..:54() .; 130 < 2.4 -~ 1.2 r::Jt,,WJ . ;?{l15 4i22l2016 MW-19.A ..: 1 ~ ~~543 <; 151 oC 1.9 -d.o DV'IW-2016 4/2212016 MW21A 4.2 +/- 2.0 =557 < 122 < 1.0 <0.9 O'vVW* 2011 4l25/2016 D-i28a <:; 1.0 <549 < 134 < 1.9 "' t (l OWW- 20t4 4i251201S [l.1'343 < 1.2 <u19 -::123 <2.1 .:. 1.1 OMV- 2493 4/2/l.2016 D128a "'09 ..: 534 < 125 <2.2 ., 1 ::;i DWW2498 4127/2016 D134a ..: 0.9 <531 < 114 .; 23 < 1.3 DWW-2494 41'29F),016 D-12Sa < 1.0 <&30 -:; 113 < 1.a <: 11 r/tNiN 2499 412912016 D-13.l'la u :1:0.6 <5&0 < 135 -= 1 7 '" 1 n tJWW- 2495 5!22016 0-128a <'U <622 -:: 99' ..: 1.9 < 1.2 D\Wtl- 2500 5.1211016 0134a -:HJ =532 e: 140 < 1.8 -:: i r) OWW* 2400 515a01£i. MW1!la < f .1 <515 <: 103 <: 1J5 < 1.1 OWW- 2539 e.,.'6/.201ti MV'.'-20A "12 <r.45 .;; 133 <'.2.3 -:: 1.1 fJWW, 2'540 51512016 M'W-.21A .; 11 <MB < 117 <2A < ~ 4 r:JWlNO< 2541 5/'5.'2016 tlN'M.2.A < UJ <$1g -:: 133 < 2.2 < 1.0 r:AM!'J- 2531 5l612(}'f6 0-12aa : u ..: 541 < 12t < 2.2 .... t 1 fWJW* 2535 5f6.12016 D-134a .::; 1.0 < 534 '.: 143 <HJ <0.9 OWW-2542 516.12016 E:W-01 <0.9 '\!: 515 <120 <! 3.8 = 2 £} OWW .2632 5/9t2{116 Df28s < 1:1' <547 <132 .::H < 1.0 oww- :2536 5/M016 CM34t1 -. 1.0 <! 56t .;: 141 < i.8 d.O DWW- 2533 5116-12016 D128a : 1 1 "'. 517 <:111 -: 17 >;,Q.9 DWlll* 2537 511612016 D-134a ...:u <534 < 156 ., 1.7 <: 0.9 DWW- 303& 5119l20t6 MW-18a 1.1 +/-08 <327 < i48 <2.Q = 1.$ fMN'I- 3039 5/Ul/2016 MW-21A 31 :ii(I <330 <! 143 -=2~ <14 fYMN- 3040 5!~912(116 MW22A 4.3 +/-1.1 ., 334 <124 <3.1 .;: Lf.I [W!/l.'IJ. :,:n;.>,.+ 5119!2Cl16 MW-23a 39 :t tll .:334 < 107 <2.7 .; i.2 O'NW- 3116 5126.12016 o.12aa < 1.0 <324 < 102 <2.8 < 1.8 DWW* 3121 512&;;:016 (}132tt <HI -c356 .; 100 <; 2:.2 0:: 1.6 DW'lfl* 3.1~3 5126l20i6 D134a t3'i:0.9 <340 < 109 : :?C "* 1.0 bWtJ'I* 3120 .513C\'2016 D-128a u +/-0.8 -:355 "~17 -.:2.0 "* 12 CTl!N'I* 3122 5'30J2M6 D132a 1.6 :!:OS <325 <:9B < 2.1 ..: 11 DWW* 3196 5f31JJ2016 D-134.;:i 1 <1 ~~oa < 334 < 131 -c 18 < 1.0 t:N'.'W* 3194 61212016 D-12~ < t.O <; 329 -=134 <'.' l.8 < 0.9 fJtNW- 3195 6f2'2016 0132a 1.!) f; 0.9 < 324 < 121 "'* 1.7 <:0.8 tWVW* 3197 612/201S D-134a "1.2 <335 .;: 103 ...: 1.9 <HJ O'M't/- 219B 6.t?J2()1fi D1.34a 1.2 +/- 0.7 "320 <( 100 <:2.9 ~ 1.5 O'lilW 3199 6/2J201fi D1:34a < 1.1 <35tl "112 < 1.8 < f.Q DWtN- 3200 6niW16 Di34a .. 1.2 "3:22 < 122 : 19 "1 0 om.1- :;..zo1 &2.'2016 M'N-18a 1.4+/-06 <32<l "152 < 1.7 < 10
A!f<ilyi;i;s for gamm.a, 9rns!I a,~h:a, .Srli>!.l. Sr9(), f<!55 an~ No-133 Will be p.:.1tcmit'i! ii lrili1im ~cl.Wily i. 1K pC1IL B 19
DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1B: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D2B~ Grotm<1wat<1r Prot&e:lii:m Prour.am Summary. Monitoring wells. c.ondi!iooal analys(!s for gross alpha, ironS5, nickel63, sm:mtlutri-$9 and $1tonfa~m-90 " Coltec1ioo Lab Code Di!!~ location Grosr;. Alpha : 5 Fe t;:~;Ni w.sr 0 "' Si OWW 3727 6/212016 M\1\l-21a 2.. 5 :!: i.0 <734 : 113 < 36 "' 1.1 DWW- 3728 6'2l2016 rlfli\l-22a 2.5 t 1.0 "14~~ -: 148 <:4.0 < L1 OWN- 3729 a1.212rne MW2Sa 3.0 +/- t.O <: 738 .; 120 .; 3.2 ,, 0.9 OWW- 3721 fi,IQ/6016 0-132i'i 1.:2 +/- (l 7 .;:'73() ~ 105 41'~ 3.7 <U OWN- 37.23 6.1612016 D-134a -n.o "'755 ~ 130 <3.2 ..;, C!.~J r:JWW-3119 6f9!201e 0-126.a < r.() .; 735 < 122 <4.5 "".. 1 ..:1 D'v'ffl- 3722 1$l9i:2016 O-i32a < 0 g. = 7!.'..3 < 111 ...;.2.s <:0.9 DWW- 372'4 6i9tl016 0-134" c10 <194 .or 122 <20 .; LO DWW-3737 6i9f.W1S f.IM'-1Ba <: 0 g <:72~ "'107 < 3.0 < G.9 OWW- 3732 6}1312Cittl D-12'3a <10 -=7~4 "'126 < 2.6 .:ti.a DWW- 3734 M3120H:I D-132a 1.4 +/- 0.8 .: 761 < 116 <3.2 ~: ib DWu'i!- 3735 61'r3'2016 0-i:Ma 1.2 +/- C!'i' .:: (42 < 117 <3.4 <: 1.0 DWN- 3733 611612'016 0-1281'1 < 1.0 -:74$ < 136 <2.5 ""1.b D'!,WJ- 3736 611611016 D-'134~ <:. 1.0 < 74~ < 115 <2.8 <:. 0.9 aww- 3738 6116/2016 MVV-1aa < 11 < 745 "111 < 2Jj c; 6.9 fYW\"I 3739 tll1612016 MW21EI < 1.2 ..: 750 -: 115 < 3.B "" 1 3 OW'N* 3140 6li6f20Hi MW-22EI Hi:i::1.0 <: 760 <135 <4.1 ""1 8 oww- 3677 611612016 MW-2.3a 2.0 +/- 10 .. a;-,5 <;" 111 <4.0 '.: 1.0 DWW* 3369 6ll012016 1>12&! "'to "822 "122 .;::3.6 <:: 10 DWW- 3$70 61201~016 0-132a .;: 1.0 <TT7 -~ 12'1 <3.9 .;: {6 DWW- 3871 61:2011011$ 0-13% .;: ~.o < 191 -: 140 .:3.3 C, 'i:2 DWW- 3875 6/20.12:016 MW22~ "' l. 1 < 638 < 105 <::J.8 < 1.0 DWVV* 3878 6."20t.2016 MW2341 6.7+/-1.S b <. 78:2 -=i2t'.I "-':l.O .,,. Q a f!M!W. 41178 6.'23J2016 MW-18i!! 1 3 :t 0.8 <: 765 "'118 e :ia ""an O\M'i/- 4482 6123i2016 MW2211 1.7 x 1.2 <779 <1:(!4 "41 < 1.3 O\M"I- 4~75 612712016 D-12811 < 1.1 d'IOS ..: 12'3 ..,; J.13 ..;.0,8 D'M'J- 4476 e121.201e D-1::J.2m 1.3 +/-0.8 dl.06 : 120 ..: 4.i ""..1.0 DWW- 4477 $12112016 D1:l4a <;;1.(1 : 786 q;lO "4.5 < 1. i DW'N* 4479 6>'2-912016 MW16lll 3.6+/-1.!.'i "744 : t14 c 4.4 "'-08 DWlN- 4480 s..-n..-.z.nrn M1N21'3 6.2 +/-4..0 <: 765 : i23 .:34 <0.8 DW'IJll- 4481 6129.12016 M'.'\1\21!! 5 0 +/-2.3 < 748 : 123 ~ .!1 . 7 < 12 DWW* 4483 6l29l2016 MW22a 3.J +/-2.9 ..::838 <. 117 "'3.5 ~: 0:9 DWW 4485 e.29,12()16 MW2~ 1.8 +/- 3. ~ <S33 <: 1:11 <HI -e: 1.0 CN.n/'J- 4600 ?!51201$ 0125~ U+/-0.8 <. 819 <: 120 .;; 3.5 ; '1.0 ~ OW\N-4602 7i~'l'2011;i D13.2lll 4.5 +/-'LO "'824 = 116 .::4.9 '<: ~.4 O\Wtl* 4604 11512016 D134a 1.:2 +/-0.9 "'886 o.: 110 ..;; 3.4 <; 1.0 1J: OWW- Jtl7l 7/Bl.20t6 MW1Sa 6.0 +/-35 ¢ 782 "110 : 2:8 .; 1 0 DWV 3874 718!2016 MW2h 3.1 +/-17 ¢ 823 .-.; 117 < ~t3 ""o.e DWW- J876 7/8.12016 MV!/2'2a 2.5:!:.H! <; 791 .;: ~11 < 3.1 .; 1"1 D\WI- 3879 7.o'8!2(116 MW2~ <::2.0 <:'. 786 .-.; t;!? "'3.0 < 1.2 tJWVV- 4001 7112.1201li 0-126;;; ..:[)JJ <939 " 116 "'3 5 0:: 1.0 OVVW* 4003 7112i2.01B D132a 13 :!:0.8 < 811 -:1119 <46 " i .4 fYiNW* 4605 7112i201S D-134a, . ,,; 10 <846 .r; 102 -=3.3 < '!.O ~ .A.Ml~ !bf i}1lt!Wf11t. grnll!lo 111tili1.;i, Sr--09. Sr-90, FeS!i. and Nl63 wllf be p!)d0<111ad if ti'Jillll'I <1r.:tl'li!;y > 1K pCilt . ~Grose alpha reanalyzed wllh a f~sutt of 5.01:1 A pCilL c Gross .alpha reanalyzed wi1h a resun of 4.2t0.8 pCllL "' (koss alpha reanalyzed with a resuli of 51 fl.6 f~'l.. B 20 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D28. Gro1mdwater Protse6on Prosram Summ;;iry, Monitoring wells, conditional amilyses for gross alpha, 1ror1-55, niekef-63, strontium-{19 aria Wontium90 ". Collt.iction ~sFe 11 L<'l-bCOde Ds1i;. location Gross Alpha Ni wsr "nsr O\WJ-4600 7.1~41211'6 li.'111.t-1fhl t.7+/-11 .;$50 < 128 ., ~,4 < 1.0 DWW-4607 7/Mll016 M'IN'21a 1.$ ;t(l.9 .::834 : 124 <2.8 ..::O.ll DVVW.OGOa 7f14f2016 MW2la L::l +/-0:9 = a34 <112 .t.2.:1 <0.9 o~'tl\'IJ* 46o9 ?.'14/2016 MW-2:!.a 14 :td).8 <907 ! 1-11 .: 2.S .:; 1.0 DWN-4690 "fl16l2016 D-12Sa <119 "'91::'> <95 <: 3 i' "'0.9 01/'lW* 4691 7HB1'2016 0132a u :t01 <915 <95 : 4.0 : 1 1 DWW-4692 1/1812016 D-134a 0.9:Hl.7 <8$1 <90 ..:3,3 -:o.9 OWvV 4035 7l21!':2Cl16 M\N21s 2-4:t13 <il05 "'121 -=2.2 <; 0.9 DWV'l-4693 fr.,? 1/2016 MW18a .: 1 0 < 868 "'103 .::.33 : tH! D'W\fll, 4595 71'2112016 MW22a 1.3 f: 1.0 <864 < aa oC :;.7 "'-' 1.0 O\l'IW* 46ff/ n:m:w1a MW-23a l.4 +/-: 1.2 <874 < 91 < 3.4 < 0.9 D\W!f- 4969 7.12512015 o-12aa <0.8 =655 <98 <3.5 <0.9 DWW-4972 7.1251W16 D-1341!1 < 1.2 c: 85() "'103 < 3.4 <0.9 Pl/ifW* 6000 7!25/Z{l16 D-132a l.9 +/-Ul ..: 577 <; 91 <.: 8.2 ..-..:os l:N1NV.- 4694 7t.29;2()16 MW-18.a H:t09 <908 "' f;t;? "'3.l ~ 1.::! r:ANW-4696 7/2912016 MW-22i;. < 1.B. <914 <93 .: 34 < 1.0 OWW 469-B 7129120Hl MW2~ : 14 <880 .:{II) <21.i ,;;Q.8 owi.v- 4699 712912016 EW-~ < 0.4 <874 ...:113 <3.2 <Ul O\/llW* 4970 81/2016 D128a <0.9 <678 <: 1 ~{I =l.7 < t.O DWV'I- 4973 81112016 D-134a -:t.3 <930 ..: 102 <2.6 *= D 9 D'WW- 4591 SJU2016 0-132a <. 1.4 <834 < 14$ "'1.9 <G.8 DWW-4976 8/4."2015 MW**18a "'09 <898 : g; < 2.9 <=0.9 DW\l'JJ'- 49'78 61412016 MW-22a < 1.3 .:922 < 102 <=2.S -<0.9 r>WVI/ 4979 S,14/WHi MV'lf-233 < 1.2 <953 <101 <2.$ ..;:QJJ OWIN- 4971 8/101'.Z016 D-12Ba <0.9 <87('1 .:90 <2.t_> <=i}~ DWW- 4974 3li0.12016 0-1340. .q1 ; 883 < 106 <2.9 < LO ov.rw. 4975 8.1101'2016 .~W18e 22 :i 1.{) < 900 <: 9! <3.5 oC 1 1 oww. 5397 at1Dr.l016 M'JIJ-22@ 1.0 +/-0.7 "648 < rna -=6.4 <0.9 f:NVW 5401 6i10.'2(,}16 MW,2J.a ~ 11? <555 <:96 : 136 .;:1.() rNVW* 5300 6{15120115 D128a .: 0.9 -<:556 <97 < 7.9 "'12 DWW* !i38a 8.11512016 D-13~a < 1.0 <: 543 < 102 <:$,3 < 1.0 D'lllW* 5$98 81181.2016 tJM-22a 25+/-1.1 < 545 < 101 <6.2 <<-Hi DWIN* 5399 8.ll5i2016 D-134a "'1.0 < 55.9 oC 107 ~:5.0 = oa DWW- 5392 6.i26.16 MW-H~a 1.1 :!:0.9 <: 55.Z < 11t <: 1. 1 : 1.2 rYWW* 53913 B/2612018 MW-2bi < 1.1 -=M8 "': 123 "6,4 ...:o.9 OO'JW* 5399 812512016 MW22<< <: 1.~ <$73 < HlB .; 7.4 < f.3 m1w. ~Ao2 8/2612GH'l tl"IWiJ<J 1.5 +/- 0 g <552 <99 <!U .,. 09 oww. 5357 8!'29120i6 o-uaa < ?,() "'541 < 116 ! 6.4 c.Hi DWiN 5390 Si29l2016 D134a 1$ i 10 "561 < 1(.'{) ..: 4 7 <! 0.8 DWW $393 9.111'2016 MW* tea 2.0:i:11 ..; 543 <il9 .: -4 4 < 0.9 DvVW* MOO 9!1/'2016 MW22a 2.5+/-11 ..: 543 < t01 : 5.7 <09 OWN* 6403 9/1{2016 l'vWu'2~ "' "11 "'550 : ns ..:5_7 .c.Q.8 fJWW. rme 91612CH<l o-12aa "'1.0 <004 c..13fJ r.:4.5 <0.9 OWl/.J- 5278 9.'tl.'20f6 D13'4 < 1,i "'582 ..::.92 = 5.2 < 12 D'M/'J. S260 91'61'2016 P.NlPl18a 2.7 :t.2.4 ! 578 ..::.00 <4.1 <O fl DWW- 5282 91'6./2016 t!f1N-22a 2.1 :!; 1.0 <5(12 ~94 ..:5() < 1.0 r:JIM"J- 528<1 9.iij./2016 MW-23-a < 1.2 < 578 <; 93 ..:4.3 <0.8 . ~ ' tv>.alyse:s for QM1ma, gicosi; r.ilpl"l;;l. Sr-Mr, Sr-oo, f.a-55 ar.:t Ni~J ~ !lE! pari.rh"ftled iflri11um ilCli'.'iy > 1K pC11L. B 21 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1B: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D2B. Gtoundwator Pro.roctton Prnuram Summa!}!. Monitoring welts. oond1tional anal~se:s tot gross alpha, lrO:li-55, nir.Kel-63. stroni:iu:m-89 .and stronfo.im;9o -;r --- DWil'I* 5277 9n3120 ~6 °'128a < 1.0 "'5 79 .:: oo < 4.7 : ~ .o D1MtiJ- 5279 9il3J'20H3 !J-.134a 1.9 ::t 1.0 < 579 < 92 <<1.2 . :: O.~ DWW-5281 !ll13./2i016 MW-18.l\ 32~24 ..;;545 ._95 <40 -::()!l> DVVW- 5283 9t13/2Q1B MW-;;!2a 3.4 .; 2.:3 .; 561 <: 94 < 3.B -:: 0.9 D'IN'N-5285 9113/2016 l'Wlv-23a <1.2 <582 <:91 <4.1 <il!l DWW- 5219 !li'20i20H> 0 11lla l.6 +/- (Hl <: 56'5 < 87 < 4.3 ..:: -iO D\"M'- 5222 ~!2012015 D-134a 2'.1 +/- 1.0 .;; 552 ..: 90 < 3.4 "'0.8 OWN- 5224 9/20J2016 M'W-1$a 4 $ :t 1 7 < 539 .. 100 < 3.S ., b.9 OMV- 5226 9/20120Hl Uio/'i-'nf.1 S. 6 :t 1 5 < 542 <: 113 < 3.3 ..:: 6.9 D\'l/W* 5229 9120.'2CU6 MW'23.f< < 1.3 < 572 < 114 < 3.7 -: i :o DWW 5227 9</22.'2Dt6 MW-22~ 3.1 ;; U ., 008 < 111 < J ...Q : o9 DllNIJ-522i 9127/2016 Q.,121;1~ .25;1;1.0 .c;543 <99 <3.fl <lO [Nl\N- 5223 9J27l201S !'.H3~a ::n t u < 570 < 95 <: 3A) < 0.0 DWW-5225 912712016 MW-1Ba <:20 <543 <99 <3.'3 .:to rnl'JV.J- 5228 9..'27i201 B MW-2;.?a ;u +/- 1 A < 592 < Ull < 3.1 <'! 0. 9 DvWtf- 5209 9l.27l2016 MW-23a <: 1.2 < 570 <9'9 <3.'1 ..:; H.1 DWl/J-5716 10/41201El D-12Sa ..:1.2 <518 <94 <4.2 <0.9 'fJWW- 53111 10l.tt2016 0..1:'.l4a " 1.4 < 547 < 109 < 3.6 <U OVVW-5719 101412D16 MW11la 26:1:1.1 <524 <91 <4.5 ..::0.9 D\WJ- 5721 1014120t9 . MW-na 23:t1.3 .:537 <94 "4.2 <:(l'1 OW!/'J- 57:2a tOW.2016 MW-233 "'1 4 <.'. 531 < 913 <; 5.3 < tu Dli'tJ\N- 5525 1011V2il16 0-128.a <HJ -<54B <96 < 3.4 .::(Iii D\iV'l/'J-5526 10/H/2015 013411 <1.2 ..:516 <B<I <6.4 .o:it r.IWW- 5528 11l/1112016 MW-1Ba 2.2 i t 1 ..: 52'8 < 102 < 3.2 < 0:8 O'il.JW- 5529 'l0/11!2016 Mli'lf22a "' U -< 52.f!; "' 98 < 3. l "' 0.8 IYW'N- 5530 10111.'2016 MW23a : 1.:? .::545 < 87 < :J..4 "'rn OWW- 5717 t0.118.'2016 D-128a ..:: 1.0 "'513 < 94 ..:4.0 <:0.9 OWW- 5718 10./18.'2016 D-134a 1 ~ :i 11 < 526 < 103 .. 4.6 .::. 1 Q D\NW- 5720 10/18120113 M'u'll 18a 21 HUI -= 549 < 93 < 3.7 <:CHI OWW* 5722 1Mll120Hl MW-22a 13::t1 0 < 532 < 91 <4.3 < 10 OWW* 5725 10/Hll2016 MW-23a ..:. 12 ..:. 516 < 95 <: 3.B < Il.9 DVW'I* 6371 10125!'2016 0-128a -= 10 . :. 610 ..:. HJ5 < 3B -c; 10 OWV'lf/JTJ. 10l25l2016 D-134a <:1.4 .;&Ul -<96 ::rn -.;1.4 D\l\\'I* '5373 10.'25/ZO16 M.V-18a < 1.2 : !15e -= 142 <n -~ 1.::. DW\"1- 6374 10.'25/2016 MW-22a 3.7 +/- 1 2 .; 523 : 100 ~ 3.9 < 1.0 r:N'J\"I 6:;175 11J125/2016 MW-23a 2.3:I:1 1 "'e.<12 .-:. 91 ..z 3.6 ..:: 0.9 O>\i'.'\"16376 11i1.':2.016 D-120a <H) <!>63 ..:.$9 <3,:$ <~.O CJi~N.f f;/377 11fH2016 D-134a <; u .; 549 : 100 "'9.6 ""2.e fi#W- 6SUJ. 111112018 M\N-18s 1.8:t1.0 ..:. SS~ < 00 < ~.S < 1.1 0'/'/Vl-637S 111112016 rlM''l2.a 23i1.1 ..:.$$9 <95 <!J:J <1.0 O\WI- 63130 nl112G16 t.IM'-23a . -: 1 2 .q;~ < 94 < 3 .3 < 0:9 O~W~ &361 1if712C!H5 D-101 .:: 0.{f -: 541 ..;; 1M < 30 <HJ mitN-6280- ~11s1.Wt6 D-127a c.OJJ .:582 <98 -=2.1 <'i.1 mwJ. s::Mo HJ8J20H5 r.M2Sa e: 1.0 "'595 .: a!.! -= 2.s .., u mwJ. 6341 H/8/2016 o-nea u +/- o.e < 564 -.: 93 " ~!.5 < 1.0 QiAt'lN fi34<1 11/6.12016 0134at. < 1.1 < 571 : 1l2 .: t.4 -: 0.9 ..,....D'W\....,..~_-.-fi.~4~.P--~----~.w1_s~.-...M~W~~1B~a;.__~~~~~"'-1~.<-5<1_,,_2-1~0-1-z~.3~~~~~o~.9;;_.,~ 8 22 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB 028. Groundwater Pr{l~fil)n Prontifrn Summa!)'; Monitonng \\MHS. condrtlonai ailatyses for gros!!I arpha, iron-55. nickel-63. strontimn-89 and strrnilium-90" Cnllech<'><i . ,,,,, """"""'"tr L~bCode 0;J1t~ toi::ation Gros."S Alp<'i<1 "Fe dNi hsr !.t'J~ .~r O\Ni,V- 6346 1 il8t.!015 MW-22a : 1 2 < 589 = 92 <2.6 ..;: 1.1 DWW-6347 11rM!016 M1/o/-23a ""12 <5fl~ .:92 < :2.9 : t f DWI/II- 6829 1111612tn6 MV'J-22a < 111 <522 :SE! <:3.i ..; 1 (') [JIN#- 6831 1 t/1512016 MW-23a < 1.1 < 54'4 .::97 <3.6 : t 1 DW\'V- 8832 1111512016 MW-18a "'U <550 < 95 <; 2.8 <0.9 D\f'IW- 6!1.13 11/15/2016 D-t28a <U <SM =89 <2.7 -:0.9 DWW-6037 11.'1512016 D-134e e 1.1 < 534 = 101 <; 2.7 ., ti<;) DWW- 6534 '112212016 M'W-23a <:12 < 5~2 <89 <2.6 -= 1 [; rJWVIJ-* 6835 111221'2016 W/-22a .:; 1.3 <532 = 87 c']7 =U.l r:JWW- 68J6 1'lll212fl16 D-134a < L2 ,c 538 = 88 <3-.1 < 1 1 D\NViJ- 6838 11i2lf.20 16 MW-1fla "" f.1 : 555 .: 86 < 2.4 <Q.9 01/W.J- 68'39 111'2212016 D-120a "'1.1 ~54a ~ 94 < 2.5 -: 'i.O oViNJ- ooe 111291'2016 d-134a "' 1.1 .:: 64S < 101 <3.5 ~ 1.1 DWW- 701~ t2i211201G d-128a ~; 1.0 <590 : 6'4 < 1.9 ..: 1 0 DWW- 7020 t2J2112016 d-134a --: 1.1 <:626 < 91 <2.1 ~ i. 1 f:N\IW- 7021 12r111201 s mw-1Ba <<U <:397 ..: 114 " 1.7 -=0.9 r:NVW- 7022 12121/2016 mw-22a ""1 0 .::$26 "106 < 1_9 = 1.0 DWW- 7023 12121/2016 mw-23a ""1.3 .::642 .; H:IO <<U3 =0,9 DWW-7025 12121.'2016 mw-25a "'1.1 <: 634 <H!.! < 1.£1 = 1,0 DWW-7027 1212112016 mw-2Sa 1.6 +/-0.8 ";623 "'100 .:: 1.8 .; 10 r:Nil\N* 7026 f.213il!21J16 mw-25a 16 :t0.8 ~ 623 .-: 10i <1-6 : 1. 1 r:JIJVW 7028 12002016 mw-26a ;a :t0.9 <43 .-: 122 < 1.5 .:0,9 8 23 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATIACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB Supplemental Analyses for Electrical Vaults IJnits: pCii'L Date H-3 Lab Codi!! H-3 0~119 Vaul~ 0-121 Vavlt ......;;.....;,..;;.._~~~~~~~~~~~_;;;.;...;-~--~~~~~- DSW- 7{18 02124.'76 211 +/- QJ DSW* 799 02/24t16 MH-102 23.4 +/- 95 DliWt/- 1001 03/0f:J.'16 240 +/- 8§ MH-104 DSW- 6256 t 11'07116 11/07.116 .;: 1fl() MH-100 MH-19? DWW- 5234 11107116 < 1eo 1 li'J.J7l16 MH-115 MH~!. -OVVW- 1051 03t08.'16 ...:: 1'1fl DVV\N- 1063 031-08/16 .; 146 MH-22:2 MH-114 D'IMN- 1064 -03/00;116 = 146 !JiNW- H70 03HH16 <1~ MH-213 MH-219 DWJIJ, 1H1 03111116 = t50 DWIN- E"iJ!De 07/12/16 5404 ;t 232 Attachment lB 24 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB Supplemental Analyses for Drinking Water Attachment lB 25 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB ,~ ~-- Location D-52 D-5-3 054 0-S:l: Lab Code DW1>\I- 56.r"..4 rn;~w. 5645 DWW* 5646 DWW- 61313 Oat@ CoJIOC'l.ed io-w-1s 10-19-16 10.19-16 11.01. rn H3 .::179 <:179 ..:17!3 < 111 1-131 ..: 0.3 < 03 < 0.4 .; 0.3 Mn-54 : 3.6 < 5.B ..: j..2 = :u Fe-59 < .:).ll ..;: 1.1 ... 57 { 4.0 Co--5!:1 < 2.2 "'2.9 ..:: 28. < 2.4 Co-60 ..;: 3.7 <.: 4.5 < 3,!fi ..;: 26 Zn-65 .: 27 < 5.4 .'. 3.6 ..: :1 :'i, Nb-95 ';. 26 < 3.3 ...: 4.5 .:. 2.o:!I Zr-95 < 3.7 ..: 64 < 71 < 5.6 1-131 < 59 -=: 5.2 -~ 49 '" 4.5 Cs.134 < 3.9 ~= 5.2 : 4 f < 3.9 Cs-137 ..: 4.0 .:; 4.6 < 3.6 Jr.:; 3.0 Ba-140 ..:: 14 7 < 13.0 =tl3 ..:: 13.9 La-1'10 < 3.3 < 2.4 .e: :2.'6 " 1.9 ' " ' _ A_ _ tocatron D-52 D-53 0-54 Lai>Cooe D\VW- 0083 DWW* 6884 D\N'N- 6885 Da'!e CollE"cted 12-19-16 12-1S-16 12-19-16 H3 < 147 < 147 ... 147 H31 < 01 < 0.3 ""QJ Mn-54 < 1.6 ...: 1.6 < 2.9 f&-59 ..: 3.8 '"a1 < 4.9 Co-58 < t .e ..: 1.7 *: 2.2 Co-80 0:: 19 .:: 19 < 1.4 Zn-65 < JB < 5.2 < 5.2 Nb-9ll < 2.3 .;; 3.0 < 2.7 Zr-95 < 2:9 < 2.8 < 5.4 f-131 ..: J.7 .: 3.8 < 3Jl Cs 134 0 -:!. 2:.3 < 3.4 <: 3.2 Cs-137 ..: 1.4 < 20 ,, a.a Ba-140 < 66 < 13.2 <; 11.6 la-140 < 1.8 -= 1.5 .: 3 4 8 26}}

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