ML17118A245
| 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: |
| References | |
| NG-17-0092 | |
| Download: ML17118A245 (63) | |
Text
{{#Wiki_filter:Enclosure 1 to NG-17-0092 Duane Arnold Energy Center 2016 Annual Radioactive Material Release Report 62 pages follow -NEXT era M 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 Intentionally blank 2016 Annual Radioactive Material Release Report Duane Arnold Energy Center DOCKET NUMBER. 50-331 Appr o ved By: J oate:
I I Intentionall y bl a nk DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Table of Contents REGULATORY LIMITS MAXIMUM PERMISSIBLE CONCENTRATIONS AVERAGE ENERGY MEASUREMENTS OF TOTAL RADIOACTIVITY GASEOUS EFFLUENTS Table 1A -Gaseous Effluents -Summation of All Releases Table 1 B -Gaseous Effluents by Quarter Table 1C -Gaseous Effluents by Release Point Estimated Release of Gaseous of Carbon-14 Gaseous Effluents: Historical Trend LIQUID EFFLUENTS Table 2A -Liquid Effluents -Summation of All Releases Table 28 -Liquid Effluents RADIOACTIVE SOLID WASTE Shipments In 2016 Waste Classification per 10 CFR 61 Summary Tables of Radioactive Solid Waste RADIOLOGICAL IMPACT ON MAN
SUMMARY
OF METEOROLOGICAL DATA Stability Class Data 33' Wind Rose Data 33' Stability Class Data 156' Wind Rose Data 156' 6 7 7 7 9 13 15 20 22
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. Page6 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 VERA GE 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) Page 7 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 1 T022, 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) Page 8 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 Units Fission and Activation Gases 1. Total Release Ci 2. Average Release Rate for Period uCi/sec 3. Percent of Applicable Limit % Iodines 1. Total 1-131 Ci 2. Average Release Rate for Period uCi/sec 3. Percent of Applicable Limit % Particulates
- 1. Total Particulates w/ balflife >8 days Ci 2. Average Release Rate for Period uCi/sec 3. Percent of Applicable Limit % Tritium 1. Total Release Ci 2. Average Release Rate for Period uCi/sec 3. Percent of Applicable Limit % Carbon 14 1. Total Carbon-14 Ci 2. Average Release Rate for Period uCi/sec 3. Percent of Applicable Limit % l.65E+Ol 2.09E+OO
- 2.59E-06 3.29£-07
- 2.08E-05 2.64E-06
- 4.60E+OO 5.85E-01
- 2.41E+OO 3.07E-01
- 4.76E+ol 6.05E+OO
- 3.89E-06 4.95E-07
- 4.43£-05 5.63E-06
- 5.24E+OO 6.66E-01
- 2.24E+OO 2.82E-Ol
- 3rd Quarter 5.26E+Ol 6.62£+00
- 7.72E-06 9.71E-07
- 5.84£-05 7.53E-06
- l.06E+Ol l.34E+OO
- 2.35E+OO 2.96E-Ol
- 2.06£+01 2.59E+OO
- l.20E-06 l.50E-06
- l.02E-3 l.28E-04
- l.21E+Ol l.52EOO
- l.63E+OO 2.05E-Ol
- Est. Total En-or,% l.60E+Ol I 1.80£+01 I l.80E+Ol I l.60E+Ol I
- 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. Page9 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 5. Carbon-14 Ci 2.41E+OO 2.24E+OO 2.35E+OO 1.63E+OO 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 1 C -Gaseous Effluents by Release Point ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ( 2016) GASEOUS EFFLUENTS BY RELEASE POINT (Curies) RELEASE POINT: OFFGAS STACK REACTOR TURBINE 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. Page 11 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 1.E+O -'---+--+---+--+--+--->-- --+--+---+--+--
--+--+---+----- --+--+--__, DAEC Gaseous Effluents 1 1.E-1 +---+---;>----<---+--+--+-----+--+- -+---+---+--+---+--+---t---+--+---; 1 curies 1.E-2 --1--+---1--r---+---+--t----+-+---+--+---+---1--+---+--+----+--+---;
- E xcluding Carbon-14 Page 12 -o-Tritlum
--¢-*Noble Gas -o -Particulates -*--Iodines 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 1st 2nd 3rd 4th Units Quarter Quarter Quarter Quarter Fission and Activation Gases 1. Total Release (not including Ci O.OOE+OO O.OOE+OO O.OOE+oO O.OOE+OO 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. 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 liters O.OOE+OO 5.00E+04 2.04£+06 2.85E+06 (prior to dilution)
Volume of dilution water used during period liters 0.00E+OO 3.76£+06 1.18£+08 4.70E+o07 Est. Total Error,% 2.00E+OI 2.00E+Ol I *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: Waste activity: Waste volume: Waste density: External volume: Waste type: 27,800 lbs 3.43E-02 Ci 1,000 ft3 27 .8 lbs/ft 3 1,360 ft 3 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 SHIPMENTS (ft3) (m 3) 6 1020 2 . 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 SHIPMENTS (ft3) (m3) Dry Active Waste 15 18820 532.92 DESTINATION Energy Solutions Bear Creek Facility, Oakridge TN ACTIVITY (curies) 42.57 ACTIVITY (curies) 1.054 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 Hit . l C I e s orica omparison 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.OO E+OO 0.000% Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO 0.000% Nb-95 O.OOE+OO O.OO E+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+O O 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 Nuclide (mCi) (mCi) (mCi) (mCi) (mCi) H-3 5.08E-01 8.63E-01 6.03E-01 2.81E+OO 4.79E+OO C-14 8.54E-03 1.0lE-02 8.26E-03 3.31E-02 6.00E-02 K-40 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cr-51 7.67E-01 O.OOE+OO O.OOE+OO 9.19E-01 1.69E+OO Mn-54 8.95E+OO 1.75E+Ol 1.02E+01 5.79E+01 9.45E+01 Fe-55 7.36E+Ol 1.44E+02 9.14E+01 4.72E+02 7.81E+02 Co-57 O.OOE+OO O.OOE+OO O.OOE+OO 4.40E-03 4.40E-03 Co-58 O.OOE+OO O.OOE+OO O.OOE+OO 5.53E-01 5.53E-01 Ni-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO 3.66E-01 3.66E-01 Co-60 3.12E+Ol 5.07E+Ol 3.48E+01 1.65E+02 2.82E+02 Ni-63 1.54E+OO 3.41E+OO 2.24E+OO 1.11E+01 1.83E+01 Zn-65 1.22E+OO 2.49E+OO 1.39E+OO 8.21E+OO 1.33E+01 Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-91 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Zr-95 O.OOE+OO O.OOE+OO O.OOE+OO 2.24E-02 2.24E-02 Nb-95 O.OOE+OO O.OOE+OO O.OOE+OO 7.57E-02 7.57E-02 Tc-99 3.70E-02 1.53E-02 2.22E-02 4.97E-02 1.24E-01 Ag-110m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sn-113 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-124 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sb-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-125 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-129 6.39E-03 1.08E-02 7.76E-03 5.26E-02 7.75E-02 Cs-137 2.19E-01 O.OOE+OO 1.74E-01 6.11E-01 1.00E+OO Ce-144 O.OOE+OO O.OOE+OO O.OOE+OO 1.00E-01 1.00E-01 Pu-239 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Am-241 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 1.18E+02 2.19E+02 1.41E+02 7.21E+02 1.20E+03 Page 18 Percent Abundance 0.399% 0.005% 0.000% 0.141% 7.889% 65.199% 0.000% 0.046% 0.000% 0.031% 23.537% 1.525% 1.110% 0.000% 0.000% 0.000% 0.002% 0.006% 0.010% 0.000% 0.000% 0.000% 0.000% 0.000% 0.006% 0.084% 0.008% 0.000% 0.000% 100.00% 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-805 w 0.00617 mrem 15 mrem Lungs 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' Period of Rec.ord = Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period 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 N 0 2 6 0 0 0 1'11\'""E 0 5 4 2 0 0 NE 1 12 11 1 0 0 E1'""E 2 15 2 0 0 0 E 0 5 1 0 0 0 ESE 2 6 2 0 0 0 SE 2 24 18 0 0 0 SSE 2 64 35 0 0 s 4 76 37 0 0 SSW 2 44 30 4 0 0 SW 1 20 17 8 2 0 WSW 0 17 10 2 3 0 w 0 3 18 4 0 1 WNW 0 5 23 18 4 2 1',.W 1 2 39 22 13 3 1'11°'1-w 0 1 16 6 2 1 Total 17 301 269 69 24 7 Cahn Hours not Included ab on for: Total P erlod Variable Direction Hours for: Total P erlod Iuva lid H oun for: Total Period Valid Hours for this Stability Class for: Total P erlod Total Hou I'S for Period Wind Rose Data 33' Total 8 11 25 19 6 10 44 102 118 80 48 32 26 52 80 26 687 15 0 80 687 8786 l (lD/l0 171 1 ll;'.: t.4J.i (WINDS FHOM) N (NOT INC l UO f.O IN Pl on 11 Unta: ?.3:00 f*nd [lain: 1/1/7{111 CIO:flO Sensors Snlcr.ted \l;SH v.nr. Lcg 1 11d a Wltln$£E D lf SS T HA ll \SM.:H ,*, CJ 't\1 tl l)5 F tE r'\UiSS: Tl tAl l t:S l.i;l t ,. Wind Rose (Direction From) Page 23 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MA TE RIAL RELEASE REPOR T Stability Class Data 156' Period of Record= Ilevation: Speed: WS1 5 6 Stability Class A Joint Frequency Distribution Hours at Each Wind Speed and Direc t ion Total Period 1 2/31/2015 2 3: 00 -111/2 01 7 00: 00 Direc t ion: WD1 5 6 Lapse: DELT Delta Temperature E x tremel y U nstable Wind Speed (mph) Wind Dir*ection .!.-4 1--8 8-13 13-19 19-25 :::. 25 Total N 0 2 2 NN E 0 2 16 l'i-:E 0 8 13 ENE 2 11 1 E 0 2 3 ESE 0 2 3 SE 0 8 19 SSE 0 11 5 4 s 0 21 60 SSW 0 2 22 SW 0 6 2 4 WSW 0 2 7 w 1 l 7 WNW 0 2 20 NW 0 2 1 7 Nl'i\Y 0 6 Total 3 83 274 Calm Hours not Included ab on for: V ariable Direction Hours for: In v alid Hours for: V alid Hours for this Stabilit y Class for: Total Hours for Period Wind Rose Data 156' 3 0 0 7 2 0 0 2 0 2 0 0 2 3 2 0 0 16 0 0 0 5 2 0 0 7 10 l 0 38 45 4 0 11 4 44 5 1 131 39 7 0 7 0 13 8 6 57 4 2 1 16 2 5 I 5 4 0 24 13 3 6 2 22 16 8 65 9 1 0 1 7 24 6 58 2 4 688 Total Period 0 I otal Period 0 Total Period 79 Total Period 688 8 7 86 WIND ROSE FRO M) . N t (NO I INl:l lJ l1b ll IN Pl.I ll) U"" '=')... Stu11 Oulu: 1 2/31fl015 23:00 f od n a rn: 1/l/?1117 00:00 Se r\sof'i S el e 0 t4.!d 1 .. 0\/.1"; t n9 o ml
- Tl-W I J i f.&H 1" !A"J l l)S Pf!r: 1'lt S'.i I HArl l!lMt-"H n -.. Wind Rose (Direction From) Page 24 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 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 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-7 6), 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 Off site 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 Analysis Location Collection 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. 1 OE-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 < 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 Attachment lA 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 CS-134 < 9.45E-09 uCi/ml K-40 < 1.10E-07 uCi/ml 03/06/16 3_2016.03.07_001 BA-140 < 2.59E-08 uCi/ml CS-134 < 1.01E-08 uCi/ml K-40 < 1.33E-07 uCi/ml 03/20/16 3_2016.03-21_004 BA-140 < 2.60E-08 uCi/ml CS-134 < 1.19E-08 uCi/ml K-40 < 1.1 OE-07 uCi/ml 04117/16 3_2016.04-18_001 BA-140 < 2.65E-08 uCi/ml CS-134 < 1.01E-08 uCi/ml K-40 # 1.79E-07 uCi/ml 05/01/16 3_2016.05.02_001 BA-140 < 2.59E-08 uCl/ml CS-134 < 1.19E-08 uCi/ml K-40# 1.94E-07 uCi/ml 08/21/16 3_2016-08-22_002 BA-140 < 2.47E-08 uCl/ml CS-134 < 1.25E-08 uCl/ml K-40 < 1.10E-07 uci/ml 10/30/16 3_2016-10-31_001 BA-140 < 3.00E-08 uCi/ml CS-134 < 1.19E-08 uCl/ml K-40 < 1.10E-07 uCl/ml 11/13/16 3_2016-11-14_003 BA-140 < 2.90E-08 uCi/ml CS-134 < 1.71E-08 uCl/ml K-40 < 1.10E-07 uCl/ml 11/27/16 3_2016-11-28_003 BA-140 < 2.59E-08 uCl/ml CS-134 < 1.09E-08 uCl/ml K-40 < 1.1 OE-07 uCl/ml 12126/16 3_2016-12-27 _002 BA-140 < CS-134 < K-40 < 2.60E-08 uCi/ml 8.34E-09 uCi/ml 1.10E-07 uCl/ml 05/29/16 3_2016.05-29_006 BA-140 < CS-134 < K-40 < 2.49E-08 uCi/ml 8.34E-09 uCl/ml 1.10E-07 uCi/ml 12111/16 3_2016-12-12_004 BA-140 < CS-134 < K-40 < 2.59E-08 uCi/ml 1.41 E-08 uCi/ml 1.48E-07 uCi/ml 01/10/16 3_2016.01-11_002 BA-140 < 2.60E-08 uCi/ml CS-134 < 1.29E-08 uCi/ml K-40 # 1.94E-07 uCi/ml 02121/16 3_2016.02-22_005 BA-140 < 2.59E-08 uCi/ml CS-134 < 8.34E-09 uCi/ml K-40 < 1.10E-07 uCi/ml CE-144 < 7.12E-08 uCl/ml CS-137 < 8.11E-09 uCi/ml LA-140 < 1.95E-08 uCl/ml CE-144 < 4.11E-08 uCl/ml CS-137 < 8.11E-09 uCi/ml LA-140 < 1.88E-08 uCi/ml CE-144 < 9.40E-08 uCi/ml CS-137 < 1.20E-08 uCi/ml LA-140 < 1.98E-08 uCi/ml CE-144 < 4.01E-08 uCi/ml CS-137 < 8.11E-09 uCl/ml LA-140 < 1.81E-08 uCi/ml CE-144 < 7.34E-08 uCl/ml CS-137 < 9.46E-09 uCl/ml LA-140 < 1.92E-08 uCl/ml CE-144 < 7.62E-08 uCl/mi CS-137 < 9.86E-09 uCl/ml LA-140 < 1.34E-08 uCl/ml CE-144 < 1.02E-07 uCl/ml CS-137 < 9.96E-09 uCl/ml LA-140 < 1.78E-08 uCl/ml CE-144 < 9.96E-08 UCl/ml CS-137 < 1.26E-08 uCl/ml LA-140 < 1.95E-08 uCl/ml CE*144 < 6.15E-08 uCl/ml CS-137 < 8.11E-09 uCl/ml LA-140 < 1.92E-08 uCl/ml CE-144 < 7.59E-08 uCi/ml CS-137 < 1.32E-08 uCl/ml LA-140 < 1.97E-08 uCi/ml CE-144 < 4.76E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml LA-140 < 1.42E-08 uCi/ml CE-144 < 7.80E-08 uCl/ml CS-137 < 8.11E-09 uCi/ml LA-140 < 1.90E-08 uCi/ml CE-144 < 9.20E-08 uCi/ml CS-137 < 8.11E-09 uCi/ml LA-140 < 1.96E-08 uCi/ml CE-144 < 7.12E-08 uCi/ml CS-137 < 9.59E-09 uCi/ml LA-140 < 1.92E-08 uCi/ml 4 C0-58 < 8.04E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml C0-58 < 8.03E-09 uCi/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 8.09E-09 uCl/ml C0-58 < 8.04E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 8.09E-09 uCl/ml C0-58 < 8.02E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 8.09E-09 uCi/ml C0-58 < 8.03E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 9.84E-09 uCi/ml C0-58 < 8.45E-09 uCl/ml FE-59 < 1.72E-08 uCl/ml MN-54 < 8.08E-09 uCl/ml C0-58 < 8.02E-09 uCl/ml FE-59 < 1. 73E-08 uCl/ml MN-54 < 8.09E-09 uCl/ml C0-58 < 1.12E-08 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 9.03E-09 uCl/ml C0-58 < 8.03E.Q9 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 1.01E-08 uCl/ml C0-58 < 8.04E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml MN-54 < 8.53E-09 uCi/ml C0-58 < 7.98E-09 uCi/ml FE-59 < 1. 72E-08 uCi/mi MN-54 < 9.82E-09 uCi/ml C0-58 < 9.77E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml MN-54 < 9.84E-09 uCi/ml C0-58 < 8.04E-09 uCi/ml FE-59 < 1.74E-08 uCi/ml MN-54 < 8.09E-09 uCi/ml C0-58 < 8.03E-09 uCl/ml FE-59 < 1.74E-08 uCl/ml MN-54 < 8.09E-09 uCl/ml C0-60 < 1.1 OE-08 uCi/ml 1-131 < 8.46E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E-08 uCi/ml 1-131 < 6.61E-09 uCi/ml ZN-65 < 2.29E-08 uCi/ml C0-60 < 1.10E-08 uCl/ml 1-131 < 8.48E-09 uCl/mi ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E-08 uCi/ml 1-131 < 6.72E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E-08 uCi/ml 1-131 < 7.15E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.1 OE-08 uCi/ml 1-131 < 7.94E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E.Q8 uCl/ml 1-131 < 6.15E-09 uCl/ml ZN-65 < 2.41E-08 uCl/ml C0-60 < 1.1 OE-08 uCl/ml 1-131 < 6.66E-09 uCl/ml ZN-65 < 2.90E-08 uCl/ml C0-60 < 1.1 OE-08 uCi/ml 1-131 < 9.69E-09 uCi/ml ZN-65 < 1.93E-08 uCl/ml C0-60 < 1.17E-08 uCl/ml 1-131 < 7.18E-09 uCl/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E-08 uCl/ml 1-131 < 7.14E-09 uCl/ml ZN-65 < 2.28E-08 uCl/ml C0-60 < 1.1 OE-08 uCl/ml 1-131 < 9.79E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml C0-60 < 1.10E-08 uCi/ml 1-131 < 6.28E-09 uCi/ml ZN-65 < 2.75E-08 uCi/ml C0-60 < 1.1 OE-08 uCi/ml 1-131 < 8.92E-09 uCi/ml ZN-65 < 1.93E-08 uCi/ml 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. 1 OE-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 Attachment 1A 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 Attachment 1B 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. Location Lab Code Collection: Annually Units: pCi/g dry Date Collected Sr-90 H-3 {pCi/L) K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 D-15a DSO-2701 05-26-16 < 0.048 < 148 14.33 +/- 0.81 < 0.027 < 0.085 < 0.026 < 0.020 < 0.053 < 0.052 < 0.038 < 0.048 < 0.21 < 0.022 0.13 +/- 0.035 " < 0.079 < 0.19 a Cs-137 identified is related to nuclear weapons testing. Attachment lB 2 D-16 DSO-2702 05-23-16 < 0.032 < 148 9.53 +/- 0.71 < 0.019 < 0.048 < 0.016 < 0.023 < 0.053 < 0.027 < Q,Q4? < < 0.17 < 0.019 0.11 +/- 8 < 0.049 < 0.10 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. Lal; Code Date H-3 0-016 -*-op;*l2Z . -01101r16"-** .. *;c*l45 Df=l'-004 02/24.116 DP-1173 (}3114.116 l)p, 15115 Q.:\}(}8.11 fi OP-:ff?!:! 05102116 OP-2773 06Jotf16 DP-3527 07110!16 .OP-41!46 0&'01f16 Df:.1-4611 owo:ma DP-5342 10l05f16 OP-6002 11l03f16 DP* 6890 12/01(16 0-112 OP* 124 01{01116 D?-006 0.2124/16 DP* 1175 03114116 DP* 1507 04I08!'1n l'Jp, :B'l'4 Mlll:ll1ii DP-2775 00/01116 DP-3523 07/1Dl16 OP-4148 08/01116 Df.'-4679 DP" 5344 10.105116 OP-6084 11/03118 OP-6002 12/01116 0-127 NOb DP* 008 02124116 OP* 117fl 03114116 o?-1500 Q4jood6 DP-2177 MJ02J1B DP* 2:778 001'01/16 DP-3525 07f10l16 DP-4150 OOJ0111fi OP* 4651 091'01116 DP-SJ46 10JOS/16 DP-0066 11.IO:l/16 m>-95.g,i 12101116 -. ---. "ND" o No data; sample f!01 availab'e Attachment lB .q55 < 146 ..:: 148 < 149 < 183 < 147 171 +/- 81 161 3: 91 < 142 < 181J < 152 <; 145 c 155 < 191 +/-B-4 *-. ;.: 149 <; 183 495 +/- 101 < 150 283 :t9S-1007 ii: 116 < 100 < 152 1504 t 141 17:9!>
- 145 1004.t126
+/- 187 762 +/- ,122 3!l56 ;t 197 2173+/-153 5387 t229 50201234 837 :L 119 frtO :t 98 3 Lab Code D-111 *up;:*12a****** OP* 805 OP-1174 OP-1506 21"73 OP-2714 01'3-3!)21 Of', 4147 OP* 4676 DP-5343 DP-6083 DP-009*1 D-114 DP* 125 OP* 801 DP-1176 DP-1500 DP-2US DP* 2777 OP-3524 DP-4149 OP-4680 DP-5345. DP* 6065 DP-0093 0-128 OP-809 op. 1H9 DP-151i DP-2rn; OP-2779 DP-3526 DP* 4151 GP* 4682 OP-5347 DP-6007 rn>-6895 --... --..,110 __ ""'" .. Date .. li1107/16 .. 02/24/16 03/141113 04/08116 U5/02116 06/0trte 07110it6 013J011t6 09:)02116 10/05116 11100116 1:2101l16 01/0'f/16 02124/16 03.114116 04/08!16 OOI01ft6 07110/16 08/01116 09102116 10/05116 11f03.116 t2i'01116 02124.116 03.!'14116 04/66i16 05!02/16 06/01116 07/10it6 08l01/H3 09KJ1/16 10,105116 111031'16 12/01{16 Ut11is: H-3 . ....... . < 155 <:: 150 ...: 148 172 +/- 83" < 183 431 ::: 98 316 +/- B8 5H ! 10& 554 !98 < 180 < 152 659 :t 102 < 100 < 197 203+/-122 ;m; 287 :1:g2 278 +/- 87 234 +/-93 759 +/- 101 < 180 < 152 415::: 00 310 +/- 94 s3o :too < 149 365 :t 109 1743;!;144 734 :I: 100 1000t125 2794 ;I: 170 ":HID .: 152 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. rnonlhl)' ar;;illyscs fot gamma @mittlng isotopes. tooaiion: D-16 Coric.en.tr!llio:n (pCrlt) LabC<l(le Date !>!Mn Q!Co oc'Co *6zn 9$Nb 1157.:r 1311 "Jl;Ce 1?;1 C1> 14116\'l 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 OP-804 021'2411$ ..:::8.3 < 13.2 ... 5.5 "'5.9 < < 7.3 ..:::g,8 < 8.:5 ..-.*7.7 <6.0 < 3fl.3 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 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 OP-2172 05102ft6 <5.0 < 11.6 < 5.2 <ll8 <5.3 <6.3 < 11.8 <S.9 < 5.6 < 5.0 <262 OP* 2713 OOI01f18 < !"6 *: t2.7 <41 ..: 5,4 ..: 6.5 -::66 00 9 7 <9.7 <5.8 <6.6 -::43.1 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 DP-4146 00f01f16 < 4.11 <7.5 < 4.7 <3.9 <9.0 ..::7.9 < 7.1 < 11.0 <:!i7 < *t5 < 30.4 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 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 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 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 Attachment lB 4 1""\::i -.: 3.7 ..-.5.B .;: 7.6 <; 2.0 < 5.2 "'<l.3 < 3.4 < 7.2 <47 <32 < 6.1 ..: 1. *1 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 '. CoŽ ' * * ' "'Dale Loo Code Oat,; H*S(f.CilL'; ---*** -" !01AJ bWN-676" 01111115 ;;* 14-0 rw,*w-4656 0623/'16 270 i 89 nww. 1!123 0:l;*3a.'H! "'147 bVN/. .. 6223 1111:17115
- 180 nww. 1157 o.lil21l6 "173 mw .... 1s2s 05/00116 320 +/- 91 D-tllB (016) nwi,v. r,19 ()2/\l/16 "146 OWN*
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<; 151 oC 1.9 -d.o DV'IW-2016 4/2212016 MW*21A 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 D*128a "'09 ..: 534 < 125 <2.2 ., 1 ::;i DWW*2498 4127/2016 D*134a ..: 0.9 <531 < 114 .; 23 < 1.3 DWW-2494 41'29F),016 D-12Sa < 1.0 <&30 -:; 113 < 1.a <: 1 1 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 0*134a -:HJ *=532 e: 140 < 1.8 -:: i r) OWW* 2400 515a01£i. MW*1!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 <$1g -:: 133 < 2.2 < 1.0 r:AM!'J-253*1 5l612(}'f6 0-12aa *: u ..: 541 < 12t < 2.2 .... t 1 fWJW* 2535 5f6.12016 D-134a .::; 1.0 < 534 '.: 143 <HJ <0.9 OWW-2542 516.12016 E:W-01 <0.9 '\!: 515 <120 <! 3.8 *= 2 £} OWW* .2632 5/9t2{116 D*f28s < 1:1' <547 <132 .::H < 1.0 oww-:2536 5/M016 CM34t1 -.* 1.0 <! 56t .;: 141 < i.8 d.O DWW-2533 5116-12016 D*128a *: 1 1 "'. 517 <:111 -: 17 >;,Q.9 DWlll* 2537 511612016 D-134a ...:u <534 < 156 ., 1.7 <: 0.9 DWW-303& 5119l20t6 MW-18a 1.1 +/-08 <327 < i48 <2.Q *= 1.$ fMN'I-3039 5/Ul/2016 MW-21A 31 :ii(I <330 <! 143 <14 fYMN-3040 MW*22A 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* 5126l20i6 D*134a t3'i:0.9 <340 < 109 *: :?C "* 1.0 bWtJ'I* 3120 .513C\'2016 D-128a u +/-0.8 -:355 -.:2.0 "* 12 CTl!N'I* 3122 5*'30J2M6 D*132a 1.6 :!:OS <325 <:9B < 2.1 ..: 11 DWW* 3196 5f31JJ2016 D-134.;:i 1 <1 < 334 < 131 -c 18 < 1.0 t:N'.'W* 3194 61212016 < t.O <; 329 -=134 <'.' l.8 < 0.9 fJtNW-3195 6f2*'2016 0*132a 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 D*1.34a 1.2 +/- 0.7 "320 <( 100 <:2.9 1.5 O'lilW* 3199 6/2J201fi D*1:34a < 1.1 <35tl "112 < 1.8 < f.Q DWtN-3200 6niW16 D*i34a .. 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 .Sr*li>!.l.
Sr*9(), f<!*55 No-133 Will be p.:.1tcmit'i! ii lrili1im
- i. 1 K pC1IL Attachment 1B 19 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1B: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB Grotm<1wat<1r Prot&e:lii:m Prour.am Summary. Monitoring wells. c.ondi!iooal analys(!s for gross alpha, iron*S5, nickel*63, sm:mtlutri-$9 and " Coltec1ioo Lab Code location Grosr;. Alpha : 5 Fe w.*sr "'0 Si OWW* 3727 6/212016 M\1\l-21a 2 .. 5 :!: i.0 <734 *: 113 < 36 "' 1.1 DWW-3728 6'2l2016 rlfli\l-22a 2.5 t 1.0
-: 148 <:4.0 < L1 OWN-3729 a1.212rne MW*2Sa 3.0 +/- t.O <: 738 .; 120 .; 3.2 ,, 0.9 OWW-3721 fi,IQ/6016 0-132i'i 1.:2 +/- (l 7 .;:'73() 105 3.7 <U OWN-37.23 6.1612016 D-134a -n.o "'755 130 <3.2 ..;, r:JWW-3119 6f9!20*1e 0-126.a < r.() .; 735 < 122 <4.5 "".. 1 . .:1 D'v'ffl-3722 1$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 "'107 < 3.0 < G.9 OWW-3732 6}1312Cittl D-12'3a <10 "'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 <:. 1.0 < < 115 <2.8 <:. 0.9 aww-3738 6116/2016 MVV-1aa < 11 < 745 "111 < 2Jj c; 6.9 fYW\"I* 3739 tll1612016 MW*21EI < 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$70 0-132a .;: 1.0 <TT7 12'1 <3.9 .;: {6 DWW-3871 61:2011011$ 0-13% .;: < 191 -: 140 .:3.3 C, 'i:2 DWW-3875 6/20.12:016 "'* l. 1 < 638 < 105 <::J.8 < 1.0 DWVV* 3878 6."20t.2016 MW*2341 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 MW*2211 1.7 x 1.2 <779 <1:(!4 "41 < 1.3 O\M"I-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 $12112016 D*1:l4a <;;1.(1 *: 786 q;lO "4.5 < 1. i DW'N* 4479 6>'2-912016 MW*16lll 3.6+/-1.!.'i "744 *: t14 c 4.4 "'-08 DWlN-4480 s..-n..-.z.nrn M 1 N*21'3 6.2 +/-4 .. 0 <: 765 *: i23 .:34 <0.8 DW'IJll-4481 6129.12016 M'.'\1\21!! 5 0 +/-2.3 < 748 *: 123 .!1 .. 7 < 12 DWW* 4483 6l29l2016 MW*22a 3.J +/-2.9 ..::838 <. 117 "'3.5 0:9 DWW* 4485 e.*29,12()16 1.8 +/- 3. <S33 <: 1:11 <HI -e: 1.0 CN.n/'J-4600 ?!51201$ U+/-0.8 <. 819 <: 120 .;; 3.5 *; '1.0 OW\N-4602 D*13.2lll 4.5 +/-'LO "'824 *= 116 .::4.9 '<: O\Wtl* 4604 11512016 D*134a 1.:2 +/-0.9 "'886 o.: 110 ..;; 3.4 <; 1.0 OWW-Jtl7l 7/Bl.20t6 MW*1Sa 6.0 +/-35 1J: ¢ 782 "110 *: 2:8 .; 1 0 DWV-1-3874 718!2016 MW*2h 3.1 +/-17 ¢ 823 .-.; 117 < ""o.e DWW-J876 7/8.12016 MV!/*2'2a 2.5:!:.H! <; 791 .;: < 3.1 .; 1"1 D\WI-3879 7.o'8!2(116 <::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 D*132a 13 :!:0.8 < 811 -:*1119 <46 " i .4 fYiNW* 4605 7112i201S D-134a, . ,,; 10 <846 .r; 102 -=3.3 < '!.O !bf i}1lt!Wf11t. grnll!lo 111tili1.;i, Sr--09. Sr-90, Fe*S!i. and Nl*63 wllf be p!)d0<111ad if ti'Jillll'I <1r.:tl'li!;y > 1 K pCilt . alpha reanalyzed wllh a 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 Attachment 1B 20 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D*28. Gro1mdwater Protse6on Prosram Summ;;iry, Monitoring wells, conditional amilyses for gross alpha, 1ror1-55, niekef-63, strontium-{19 aria Wontium*90 ". Collt.iction L<'l-bCOde Ds1i;. location Gross Alpha 11Ni wsr "nsr O\WJ-4600 li.'111.t-1fhl t.7+/-11 .;$50 < 128 ., < 1.0 DWW-4607 7/Mll016 M'IN'*21a 1.$ ;t(l.9 .::834 *: 124 <2.8 ..::O.ll .. DVVW*.OGOa 7f14f2016 MW*2la L::l +/-0:9 *= a34 <112 .t.2.:1 <0.9 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 0*132a u :t01 <915 <95 *: 4.0 *: 1 1 DWW-4692 1/1812016 D-134a 0.9:Hl.7 <8$1 <90 ..:3,3 -:o.9 OWvV* 4035 7l21!':2Cl16 M\N*21s 2-4:t13 <il05 "'121 -=2.2 <; 0.9 DWV'l-4693 fr.,? 1/2016 MW*18a .: 1 0 < 868 "'103 .::.33 *: tH! .. D'W\fll, 4595 71'2112016 MW*22a 1.3 f: 1.0 <864 < aa oC :;.7 "'-' 1.0 O\l'IW* 46ff/ n:m:w1a MW-23a l.4 +/-: 1.2 <874 < 91 < 3.4 < 0.9 D\W!f-4969 7.12512015 o-12aa <0.8 *=655 <98 <3.5 <0.9 DWW-4972 7.1251W16 D-1341!1 < 1.2 c: 85() "'*103 < 3.4 <0.9 Pl/ifW* 6000 7!25/Z{l16 D-132a l.9 +/-Ul ..: 577 <; 91 <.: 8.2 ..-..:os l:N1NV.-4694 7t.29;2()16 MW-18.a H:t09 <908 "' f;t;? "'3.l 1.::! r:ANW-4696 7/2912016 MW-22i;. < 1.B. <914 <93 .: 34 < 1.0 OWW* 469-B 7129120Hl
- 14 <880 .:{II) <21.i ,;;Q.8 owi.v-4699 712912016
< 0.4 <874 ...:113 <3.2 <Ul O\/llW* 4970 81/2016 D*128a <0.9 <678 <: 1 *=l.7 < t.O DWV'I-4973 81112016 D-134a -:t.3 <930 ..: 102 <2.6 *= D 9 D'WW-4591 SJU2016 0-132a <. 1.4 <834 < 14$ "'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_> DWW-4974 3li0.12016 0-1340. .q1 *; 883 < 106 <2.9 < LO ov.rw. 4975 8.1101'2016 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 D*128a .: 0.9 -<:556 <97 < 7.9 *"'12 DWW* !i38a 8.11512016 < 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
- = oa DWW-5392 6.i26.16 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 MW*22<< <: <$73 < HlB .; 7.4 < f.3 m*1w.
8/2612GH'l tl"IW*iJ<J* 1.5 +/- 0 g <552 <99 <!U .,. 09 oww. 5357 8!'29120i6 o-uaa < ?,() "'541 < 116 *! 6.4 c.Hi DWiN* 5390 Si29l2016 D*134a 1$ i 10 "561 < 1(.'{) ..: 4 7 <! 0.8 DWW* $393 9.111'2016 MW* tea 2.0:i:11 ..; 543 <il9 .: -4 4 < 0.9 DvVW* MOO 9!1/'2016 MW*22a 2.5+/-11 ..: 543 < t01 *: 5.7 <09 OWN* 6403 9/1{2016 "' "11 "'550 *: ns ..:5_7 .c.Q.8 fJWW. rme 91612CH<l o-12aa "'1.0 <004 c..13fJ r.:4.5 <0.9 OWl/.J-5278 9.'tl.'20f6 D*13'4* < 1,i "'582 ..::.92 *= 5.2 < *12 D'M/'J. S260 91'61'2016 P.NlPl*18a 2.7 :t.2.4 *! 578 ..::.00 <4.1 <O fl DWW-5282 91'6./2016 t!f1N-22a 2.1 :!; 1.0 <5(12 ..:5() < 1.0 r:JIM"J-528<1 9.iij./2016 MW-23-a < 1.2 < 578 <; 93 ..:4.3 <0.8 . ' tv>.alyse:s for QM1ma, gic*osi; r.ilpl"l;;l. Sr-Mr, Sr-oo, f.a-55 ar.:t !lE! pari.rh"ftled iflri11um ilCli*'.'iy > 1K pC11L. Attachment 1B 21 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 1B: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB D*2B. Gtoundwator Pro.roctton Prnuram Summa!}!. Monitoring welts. oond1tional tot gross alpha, lrO:li-55, nir.Kel-63. stroni:iu:m-89 .and stronfo.im;9o -;r *---DWil'I* 5277 9n3120 °' 128a < 1.0 "'5 79 .:: oo < 4.7 *: .o D1MtiJ-5279 9il3J'20H3 !J-.134a 1.9 ::t 1.0 < 579 < 92 <<1.2 ..:: DWW-5281 !ll13./2i016 MW-18.l\ ..;;545 ._*95 <40 -::()!l> DVVW-5283 9t13/2Q1B MW-;;!2a 3.4 .; 2.:3 .; 561 <: 94 < 3.B -:: 0.9 D'IN'N-5285 9113/2016 l'Wlv-23a <1.2 <582 <:91 <4.1 <il!l DWW-5219 !li'20i20H> 0* 11lla l.6 +/- (Hl <: 56'5 < 87 < 4.3 ..:: -iO D\"M'-5222 D-134a 2'.1 +/- 1.0 .;; 552 ..: 90 < 3.4 "'0.8 OWN-5224 9/20J2016 M'W-1$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 3.1 ;; U ., 008 < 111 < J . ..Q *: o 9 DllNIJ-522i 9127/2016 .25;1;1.0 .c;543 <99 <3.fl <lO [Nl\N-5223 9J27l201S
- n tu < 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 MW*11la 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 0*13411 <1.2 ..:516 <B<I <6.4 .o:it r.IWW-5528 11l/1112016 MW-1Ba 2.2 it 1 ..: 52'8 < 102 < 3.2 < 0:8 O'il.JW-5529 'l0/11!2016 Mli'lf*22a
"' U -< 52.f!; "' 98 < 3. l "' 0.8 IYW'N-5530 10111.'2016 MW*23a *: 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'l*f/JTJ. 10l25l2016 D-134a <:1.4 .;&Ul -<96 *::rn -.;1.4 D\l\*\*'I* '5373 10.'25/ZO 16 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'.'\"1*6376 11i1.':2.016 D-120a <H) <!>63 ..:.$9 <3,:$ f;/377 11fH2016 D-134a <; u .; 549 *: 100 "'9.6 ""2.e fi#W-* 6SUJ. 111112018 M\N-18s 1.8:t1.0 ..:. < 00 < < 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 < 94 < 3 .3 < 0:9 &36*1 1if712C!H5 D-101 .:: 0.{f -: 541 ..;; 1M < 3 0 <HJ m*it*N-6280-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 " < 1.0 QiAt'lN* fi34<1 11/6.12016 0*134at. < 1.1 < 571 *: 1l2 .: t.4 -: 0.9 Attachment 18 22 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB 0*28. Groundwater Prontifrn Summa!)'; Monitonng \\MHS. condrtlonai ailatyses for gros!!I arpha, iron-55. nickel-63. strontimn-89 and strrnilium-90" Cnllech<'><i . ,,,,, dNi hsr """"""'"tr toi::ation Gros."S Alp<'i<1 *"Fe 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 .: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 <S*M *=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 < <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 94 < 2.5 -: 'i.O oViNJ-ooe 111291'2016 d-134a "' 1.1 .:: 64S < 101 <3.5 1.1 DWW-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 Attachment 18 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-*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 -* 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 MH-213 MH-219 DWJIJ, 1H1 03111116 *= t50 DWIN-E"iJ!De 07/12/16 5404 ;t 232 Attachment lB 24 Attachment lB DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB Supplemental Analyses for Drinking Water 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 0*54 0-S:l: Lab Code DW1>\I-56.r"..4 5645 DWW* 5646 DWW-61313 Oat@ CoJIOC'l.ed io-w-1s 10-19-16 10.19-16 11.01. rn H*3 .::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 4 9 '" 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 " 1.9 < 2.4 .e: :2.'6 '"'_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 H*3 < 147 < 147 ... 147 H31 < 0 1 < 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:: 1 9 .:: 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 0 134 -:!. 2:.3 < 3.4 <: 3.2 Cs-137 ..: 1.4 < 2 0 ,, a.a Ba-140 < 66 < 13.2 <; 11.6 la-140 < 1.8 -= 1.5 .: 3 4 Attachment 18 26}}