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{{#Wiki_filter:Enclosure 1 to NG-17-0092 Duane Arnold Energy Center 2016 Annual Radioactive Material Release Report 62 pages follow | {{#Wiki_filter:Enclosure 1 to NG-17-0092 Duane Arnold Energy Center 2016 Annual Radioactive Material Release Report 62 pages follow | ||
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* 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 | - NEXTeraM ENERGY~ ~ | ||
I I | DUANE ARNOLD | ||
-Summation of All Releases Table | * 2016 - | ||
Historical Trend LIQUID EFFLUENTS Table 2A -Liquid Effluents | Annual Radioactive Material Release Report Duane Arnold Energy Center Cedar Rapids, Iowa Docket No. 50-331 January 1, 2016 through December 31, 2016 | ||
-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 | |||
Intentionally blank 2016 Annual Radioactive Material Release Report Duane Arnold Energy Center DOCKET NUMBER. 50-331 Approved By: J | |||
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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== | ==SUMMARY== | ||
OF METEOROLOGICAL DATA Stability Class Data 33' Wind Rose Data 33' Stability Class Data 156' Wind Rose Data 156' | OF METEOROLOGICAL DATA 22 Stability Class Data 33' Wind Rose Data 33' Stability Class Data 156' Wind Rose Data 156' | ||
==SUMMARY== | ==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 | 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 500 mrem/year to the whole body. | ||
* Less than 3000 mrem/year to the skin. Gamma Air Dose | * Less than 3000 mrem/year to the skin. | ||
Gamma Air Dose | |||
* 1) Less than or equal to 5 mrad/quarter. | * 1) Less than or equal to 5 mrad/quarter. | ||
* 2) Less than or equal to 10 mrad/year. | * 2) Less than or equal to 10 mrad/year. | ||
Line 41: | Line 49: | ||
Dose | Dose | ||
* Less than or equal to 7.5 tmem/quarter to any organ. | * 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 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 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 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 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 | * 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. | * 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 | 40CFR190 and 10CFR72 Dose | ||
* 1) Less than or equal to 25 mrem annual whole body dose. | * 1) Less than or equal to 25 mrem annual whole body dose. | ||
* 2) Less than or equal to 75 mrem annual thyroid 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. | * 3) Less than or equal to 25 mrem annual dose to any other critical organ. | ||
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 | 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 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. | * 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 | 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. | * 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. | ||
Sample media is changed weekly and analyzed by gamma spectroscopy. | * 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. | ||
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. | * 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. | ||
* Noble gas grab samples of the same four release points are obtained monthly and analyzed by gan11Tia spectroscopy. | * 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) | ||
Total error is based on stack flow error, analytical error, and calculated sampling error. | Page 7 | ||
* 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. | DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT Liquid Effluents | ||
* 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. | ||
* Service water systems are sampled once per week for gamma emitters. | * 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. | ||
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. | * 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. | ||
Total error is based on the volume discharge error and analytical error. | 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. | ||
* 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 | * 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) | ||
* 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. | Page 8 | ||
* 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 | 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. | ||
-Summation of All Releases Units Fission and Activation Gases 1. Total Release Ci | For all release points, quarterly average gross alpha concentration of radioactivity measured less than 4.IOE-09 µCi/cc. | ||
: 1. Total Particulates w/ balflife >8 days Ci 2. | 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. | |||
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 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. | |||
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 | |||
-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: | Specifically: | ||
Waste weight: | 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 | ||
Exclusive-Use Vehicle (Trncks). | 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. | ||
IRRADIATED COMPONENTS: | Shipments Made To Burial Facilities in 2016: | ||
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 | 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: | ||
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. | 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== | ==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. | 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. | ||
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' | Better than 90% data recovery was obtained for combined wind speed, delta temperature and wind direction. A table smnmarizing data collection is printed here: | ||
Speed: WS33 Direction: | Met. Data Recovery Elevation and Sensors % Joint Recovery "good" data 10 meter Wind Direction Wind Speed 99.1% | ||
WD33 Lapse: DELT Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph) Wind Direction | Delta Temp 50 meter Wind Direction Wind Speed 99.1% | ||
!.-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' | 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. | ||
?.3:00 f*nd [lain: 1/1/7{111 CIO:flO Sensors Snlcr.ted | Page 22 | ||
\l;SH v.nr. | |||
CJ 't\ | 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 Rose (Direction From) Page 23 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE | 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 | |||
.!.-4 1--8 8-13 13-19 19-25 :::. 25 Total N 0 2 2 | !JOO!'.~L~Tn~ | ||
* Tl-W I J i f.&H 1" !A" | (NOT INCl UOf.O IN Pl on 11 | ||
~ ~tnn Unta: 1?(J1(1.01~ ?.3:00 f* nd [lain: 1/1/7{111 CIO:flO Sensors Snlcr.ted | |||
\l;SH v.nr. | |||
Lcg111d a Wltln$ £EDlf SS THAll \ SM.: H | |||
,*, Vl\/ f()Sftf.0 Lf~J/'Wj1 S t,f..'t! | |||
CJ 't\1tll)5FtE r'\ UiSS: Tl tAl l t:S l.i;l t | |||
,. VAf.11.J~EC00o:\£.A I ER:,H.\t i 1 2; 1,11!H Wind Rose (Direction From) | |||
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 | |||
\','£ 1 ~ fii 1..0\/.1"; | |||
t n9oml * | |||
~ '*'r ~ JO~!-'.-Fl:. IHf. ~ Tl-W I J i f.&H 1" !A"Jll)SPf!r:1' lt S'.i I HArl l!lMt-"H n WJM!)~i:.t:t-lll£Sa rHNn ~S MAi | |||
-.. 1;*.~ 1C-SPf:CLJ GOJ:MER 1HAtl t l 'JU~ | |||
Wind Rose (Direction From) | |||
Page 24 | |||
DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT | |||
==SUMMARY== | ==SUMMARY== | ||
OF GROUNDWATER PROTECTION INITIATIVE ISSUES The Duane Arnold Energy Center has committed to the Nuclear Energy Institute's Industry Groundwater Protection Initiative | 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: | ||
-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. | ||
* 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 | Program results are presented in Attachment 1. | ||
* No reactor-by-product gamma emitting isotopes were identified. | * 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. | * 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). | * 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 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. | 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'. | * In 2016, there was one instance where state and local officials were notified of a spill of radioactive liquid. | ||
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. | 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 | ||
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." | '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. | ||
* 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. | "This report is being made in accordance with 10 CFR 50.72(b)(2)(xi), as a result of notification to offsite agencies. | ||
The review also verified that the changes did not adversely impact the accuracy or reliability of effluent dose or setpoint calculations. | "The Licensee has notified the NRC Resident Inspectors. | ||
Revision 35 36 Revision 36 to the ODAM was made effective on 9/2/2016. | "There is no risk to plant employees, the public or drinking water." | ||
Changes implemented included: | * 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: | Table of Contents: | ||
* Revised organization due to additional pages and data. Basis of Mixing Ratios: | * 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. | * Cedar River annual average flow was updated using U.S. Geological Survey-Iowa Data Book for water year records 1902-2015. | ||
Figure 3-2: | Figure 3-2: | ||
* Revised color map to include GPS compass overlay for sector delineation. | * Revised color map to include GPS compass overlay for sector delineation. | ||
Figure 5-1: | Figure 5-1: | ||
* Revised maps to include new REMP-GWPP sampling points for new monitoring wells and electrical vaults. Table 5-1: | * Revised maps to include new REMP-GWPP sampling points for new monitoring wells and electrical vaults. | ||
* 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: | Table 5-1: | ||
* Revised "Clean" Systems Batch Release sample points to include FRAC tanks. 6.1.2/7.1.2 Liquid Effluent Concentration: | * 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). | ||
* Revised "Clean" Systems Batch Release sample points to include FRAC tanks. Appendix A: | Table 7.1-2, Section C: | ||
* 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. | * Revised "Clean" Systems Batch Release sample points to include FRAC tanks. | ||
Changes implemented included: | 6.1.2/7.1.2 Liquid Effluent Concentration: | ||
Offsite Dose Assessment Manual Title Page: Page 26 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT | * Revised "Clean" Systems Batch Release sample points to include FRAC tanks. | ||
* Licensing Manager, Emergency Planning (EP), and Chemistry Manager are required signatories. | Appendix A: | ||
In addition, the position title "Plant Manager" was changed to "Site Director". | * 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: | Section 1.0: | ||
* Inclusion of the Groundwater Protection Program (GWPP). The GWPP compliments the Radiological Environmental Monitoring Program (REMP). Section 2.3: | * Inclusion of the Groundwater Protection Program (GWPP). The GWPP compliments the Radiological Environmental Monitoring Program (REMP). | ||
* 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: | Section 2.3: | ||
* 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. | * 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. | ||
Off-site laboratory results are published in Annual Radiological Material Release Report and Annual Radiological Environmental Report." Figure 3-2: | Section 2.8: | ||
* Revised color map. Figure 5-1: | * Revised narrative to include: | ||
* Revised maps to include new REMP-GWPP sampling points for new monitoring wells. Figure 5-2: | "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. | * Revised maps to include new Palo, Iowa, air sampler and TLD location. | ||
Table 5-1: | 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- | * Revised REMP-GWPP sampling locations to include new Palo, Iowa air sampler (D-5a), | ||
* 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: | 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. | ||
* Inclusion of new subsection "D" for GWPP Mitigation System for continuous liquid effluent release. Radiological Environmental Monitoring Program 0 6.3.2: | Radioactive Liquid Effluent Concentration 0 7.1.2: | ||
* Inclusion of REMP and GWPP under | * 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. | * Inclusion ofREMP drinking water monthly samples (change from GWPP quarterly) and change from semi-monthly to monthly milk sampling. | ||
Table 6.3-2: | 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. | * 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: | Table 6.3-3: | ||
* Sequence change in table order number. Table 6.3-4: | * Sequence change in table order number. | ||
* Sequence change in table order number. Bases Section, Liquid Effluent Concentration 6.1.2/7.1.2: | 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." | * 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. | * Add paragraph: | ||
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." | "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: | * Misspelling correction for "Cedar River." | ||
Changes to the ODAM: | |||
* Update section "b" to remove title "Plant Manger" and replace title with "Site Director". | * Update section "b" to remove title "Plant Manger" and replace title with "Site Director". | ||
ODAM Revision Date Histo Revision: | 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 | ||
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. | |||
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. | * Gamma Spectroscopy results for site surface water samples. | ||
* Tritium 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 | * 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. | * 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. | * 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. | * Tritium results for site precipitation samples. | ||
* Strontium-90, Tritium and Gamma Spectroscopy results for site soil 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 | |||
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!1/(}1/1$ | DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATIACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB 0-2. GrOl!lndwater Proteciior1 P.l'ogram Sommtiiy Gro~md wa1e;, Mon4onng wells, an~s ror ll'11iun1 *. | ||
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< 14-0 DWW-S2!J5 111{JUl16 D'trt1* | U\/V.::?BA OWW- 702?' 1;;:..2ms ~n t1w DSW~ 7028 l2/3Qlt6 2922+/-175 Attachment lB 10 | ||
07!0!l>'16 | |||
* | DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT 18: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB | ||
--~-* | |||
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CG.'-0511& | DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATTACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB | ||
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.... ,.....,.,,,,.,,..,,,,_,,,,.,..,.,,,,, ___ 9 DUANE ARNOLD ENERGY CENTER 2016 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ATIACHMENT lB: GROUND WATER PROTECTION PROGRAM RESULTS-OFFSITE LAB 0-2. GrOl!lndwater Proteciior1 P.l'ogram Sommtiiy wa1e;, Mon4onng wells, ror ll'11iun1 | |||
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Revision as of 05:12, 30 October 2019
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
- 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
Intentionally blank 2016 Annual Radioactive Material Release Report Duane Arnold Energy Center DOCKET NUMBER. 50-331 Approved By: J
~ ~~ oate: vd~!lz I I
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.
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 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.
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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.
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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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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 ~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 '.
~all Co' ' * * ' "'Dale Loo Code Oat,; H*S(f.CilL'; ---*~*---~*-***~***--,-----*v**- ---*** - " !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* ~'529 OO.*U'.J.116 "*J52 OWW- 1tJ24 00/30/16 "'147 DWN* 4556 00;'2:.vrn . ;: 152 DWIN* rn;s CM/t:!i1& ..;:173 DWW* 6:!24 11!07116 "1f,J oww.600 (}2111116 "14B OVoJ\'J. '1000 om411e -: 150 l)V<JW. H~9 OM12'!l6 "173 oww. 41357 OS.12(>116 <, ~5t DWW* 2(l3() 06/01lliS "'152 CM"N- 6221.i 111{)7/16 < H9 *-*-*****- - -- - '
tfliW ~mi} OWN*i.iill 02/11115 ..;: 146 DWW- 4058 Ol\12~/lS -t: 152 OWW* UGO 04!12116 <H3 DWW* 0226 11!()7Jl6 < 1$0 DWN* 2631 IJSIO\l/16 < 1!52 0-H3A 'OJA! oww. 182 02/11/16 <: 'i'/'1 OWN.. 4M9 OB.124116 "'15Z DWW- 176~ ~112116 <'73 DV'IW. 6227 11107116 < 180 fJl.M'Y* 2632 00/lOJlli < t!i2 0-113$ 10:~~- oww.. 7B3 02/11116 ..;: 111 OWW* 4600 00124111.l "152 OVW'I- 1762 04112116 <.113 0'1-JW. 6228 IHOilH! "100 O'NW* 2633 05/t0/16 < 152 oww:. 002 02/15/Hl < 14-0 O!NW- 2389 05/07116 !iJ.2 !82 OW#- 1925 03i30il6 .,_ 147 oww. 4565 Ot!/22116 263 HI$ OWW* 1764 04112'1!6 *:173 (j\f{'/','- 6229 1l/0811li < 180 oww. 004 l);!J11iJ!6 >: 1115 f>V'/IN- 2300 MJG7Jl5 <: 14!i DW-1/, 1926 O:lt30IH'i <! 147 DWW- 451!6 oal221Hl < 152 DWW- 1765 041121\ll <: 173 OW#- 6ni'J H/00116 -. H.lO 0-H!IA ~OSA~
DWW-685 02.'l2i'1(i "'t46 DW\'1,t* .j(;(U 000.4116 2:!>1 +/-07 fNMI. 1166 {).q/j 1116 -