BYRON 2020-0031, Annual Radiological Environmental Operating Report - Part 4 of 4

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Annual Radiological Environmental Operating Report - Part 4 of 4
ML20121A032
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Site: Byron  Constellation icon.png
Issue date: 04/30/2020
From:
Teledyne Brown Engineering Environmental Services
To:
Office of Nuclear Reactor Regulation
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ML20121A027 List:
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BYRON 2020-0031
Download: ML20121A032 (26)
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Errata Data The 2018 AREOR Table D-2 Listing of Missed Samples contained the following typographical error for the surface water sample taken on 01 /16/18:

TABLE D-2 LISTING OF MISSED SAMPLES Sample Location Collection Type Code Date Reason BY-12 SW 01/02/18 Sample unobtainable due to ice on river BY-29 BY-12 SW 01/09/18 Sample unobtainable due to ice on river BY-29 BY-12 SW 01/16/18 Sample unobtainable due to ice on river BY-12 BY-12 SW 02/06/18 Sample unobtainable due to ice on river BY-29 BY-12 SW 02/13/18 Sample unobtainable due to ice on river BY-29 BY-12 SW 02/20/18 Sample unobtainable due to ice on river BY-29 OSLD BY-109-2 03/28/18 Dosimeter received damaged - readings not obtained OSLD BY-04 07/02/18 Dosimeter missing during quarterly exchange SW BY-29 11/27/18 Sample unobtainable due to icy conditions The correct location should have been BY-29.

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Intentionally left blank APPENDIX H ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

Intentionally left blank NRC.Docket No: 50-454 50-455 BYRON NUCLEAR GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2019 Prepared By Teledyne Brown Engineering Environmental Services

-=r Allii ...~ Exelon Generation, Byron Nuclear Generating Station Byron, IL 61010 April 2020

Intentionally left blank Table Of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A. Objectives of the RGPP ...... .. .............................................................................. 3 B. Implementation of the Objectives ........................................................................ 3 C. Program Description ........................................................................................... 4 D. Characteristics of Tritium (H-3) ........................................................................... 4 Ill. Program Description ...................................................................................................... 6 A. Sample Analysis .................................................................................................. 6 B. Data Interpretation ............................................................................................... 6 C. Background Analysis ................................. ................. ......... ................................ 7

1. Background Concentrations of Tritium ....................... .. ............................ 7 IV. Results and discussion .................................................................................................. 9 A. Groundwater Results ................................................................. .. ........................ 9 B. Drinking Water Well Survey .............................................................................. 10 C. Summary of Results - Inter-laboratory Comparison Program .......................... 10 D. Leaks, Spills, and Releases .............................................................................. 10 E. Trends ............................................................................................................... 10 F. Investigations ..................................... .. .............................................................. 10 G. Actions Taken ................................................................................................... 10

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Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Byron Nuclear Generating Station, 2019 Figures Figure A-1 Monitoring Well Locations, Byron Nuclear Generating Station, 2019 (Extra wells noted on map are for reference only.)

Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium, Strontium, and Gross Alpha in Groundwater Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019 Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Byron Nuclear Generating Station, 2019

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I. Summary and Conclusions In 2006, Exelon instituted a comprehensive monitoring program to evaluate the impact of station operations on groundwater in the vicinity of Byron Nuclear Generating Station. The monitoring was conducted in two phases. Phase 1 of the monitoring was part of a comprehensive study initiated by Exelon to determine whether groundwater or surface water at and in the vicinity of Byron Nuclear Generating Station had been adversely impacted by any releases of radionuclides. Phase 1 was conducted by Conestoga Rovers and Associates (CRA) and the conclusions were made available to state and federal regulators as well as the public.

Phase 2 of the RGPP was conducted by Exelon corporate and station personnel to initiate follow up of Phase 1 and begin long-term monitoring at groundwater locations selected during Phase 1. This is the fifteenth in a series of annual reports on the status of the Radiological Groundwater Protection Program (RGPP) conducted at Byron Nuclear Generating Station . This report covers groundwater and surface water samples collected from the environment both on and off station property in 2019. During that time period , 129 analyses were performed on 62 samples from 18 locations.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples tested. In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

In 2019, seventeen (17) Radiological Groundwater Protection Program (RGPP) monitoring wells were sampled in total. Groundwater samples were obtained in March, May, August, and November and analyzed for tritium. In addition, a study of gamma, beta, and alpha radioisotopes was performed in accordance with Nuclear Energy Institute (NEI) 07-07, Groundwater Protection Initiative, for the samples obtained in May. None of these May samples showed concentrations of radionuclides above what is considered background levels.

Three wells contained levels of tritium above the lower limit of detection (LLD) of 200 pCi/L. They were: AR-4 (201 pCi/L in March, 298 pCi/L in May, 272 pCi/L in August, <200 pCi/L in November) and AR-11 (520 pCi/L in March, 611 pCi/L in May, 549 pCi/L in August, 566 pCi/L in November) and AR-7 (246 pCi/L in March, 231 pCi/L in May, 280 pCi/L in August, <200 pCi/L in October). Wells AR-4 and AR-11 are near the Circulating Water Slowdown piping, where historical leakage through vacuum breakers was known to have occurred.

Tritium in Well AR-7, located on-site just west of plant structures, has been measured in this well slightly above detection limits on an intermittent basis since the well was first drilled in 2006. The tritium present in this well is likely due to legacy tritium prior to 2006 or precipitation recapture and is not believed to be the result of new leaks. The tritium measured in this well has been at or below tritium levels that have been historically measured in rainwater as a result of precipitation recapture from permitted gaseous releases. In August 2014, a break in the well piping was discovered about six feet below the surface that could have served as the entry point for tritium in the recapture water. Tritium present in well AR-7 has shown a gradual decrease since 2014 and was less than detectable in the most recent November 2019 sample. Should the water in these aquifers migrate to off-site wells used for drinking, the off-site dose consequence from tritium present in any of these three wells would be negligible.

There are no existing or new leaks evident at the site and all groundwater well sample results are well below the drinking water tritium standard of 20,000 pCi/L.

In December 2018, two new wells, AR-12 and AR-13, were installed near well AR-7. These wells were added to provide additional monitoring capabilities in the area directly west of plant structures. No tritium was detected in these wells during 2019.

Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected in any samples above their respective LLDs of 10 and 1 pCi/L.

Gross Alpha analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2019.

Gross Alpha (dissolved) was not detected in any groundwater locations. Gross Alpha (suspended) was not detected in any groundwater locations.

Concentrations of Gross Alpha which are slightly above detectable levels are considered to be background and are not the result of plant effluents.

In 2019, a 5-year hydrogeologic investigation for the Byron Nuclear Generating Station was performed in accordance with NEI 07-07 guidance. There were no Areas for Evaluation (AFE) as a result of the investigation and the investigation concluded there is no current risk from exposure to radionuclides associated with licensed plant operations through any of the identified potential exposure pathways.

In assessing all the data gathered for this report, it was concluded that the operation of Byron Nuclear Generating Station had no adverse radiological impact on the environment, and there are no known active releases into the groundwater at Byron Nuclear Generating Station.

II. Introduction The Byron Station, a two-unit PWR station, is located about two miles east of the Rock River and approximately three miles southwest of Byron in Ogle County, Illinois. The reactors are designed to have capacities of 1,268 and 1,241 MW gross, respectively. Unit One loaded fuel in November 1984 and went on line February 2, 1985. Unit Two went on line January 9, 1987.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2019.

A. Objectives of the RGPP The long-term objectives of the RGPP are as follows:

1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources
2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface
3. Perform routine water sampling and radiological analysis of water from selected locations
4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner
5. Regularly assess analytical results to identify adverse trends
6. Take necessary corrective actions to protect groundwater resources B. Implementation of the Objectives The objectives identified have been implemented at Byron Nuclear Generating Station as discussed below:
1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Conestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public.
2. The Byron Nuclear Generating Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface and shallow subsurface are updated based on ongoing measurements.
3. Byron Nuclear Generating Station will continue to perform routine sampling and radiological analysis of water from selected locations.
4. Byron Nuclear Generating Station has implemented new procedures to identify and report new leaks, spills, or other detections with potential radiological significance in a timely manner.
5. Byron Nuclear Generating Station staff and consulting hydrogeologist assess analytical results on an ongoing basis to identify adverse trends.

C. Program Description Sample Collection Sample locations can be found in Table A-1 and Figure A-1, Appendix A.

Groundwater/Surface Water Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following EPA methods.

Groundwater is collected from drilled wells. Surface water is collected from the Construction Runoff Pond (CROP), which collects stormwater runoff from the site protected area prior to discharge offsite. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables as data are received .

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3)

Tritium (chemical symbol H-3) is a radioactive isotope of hydrogen. The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen.

Tritiated water behaves the same as ordinary water in both the

. environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 14 days. Within one month or so after ingestion, essentially all tritium is cleared. Organically bound tritium (tritium that is incorporated in organic compounds) can remain in the body for a longer period.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors, where the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to Helium-3 (3He). This radioactive decay releases a beta particle (low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Byron Nuclear Generating Station RGPP in 2019.

In order to achieve the stated objectives, the current program includes the following analyses (as required by procedure):

1. Concentrations of gamma emitters in groundwater/surface water
2. Concentrations of strontium in groundwater
3. Concentrations of tritium in groundwater/surface water
4. Concentrations of gross alpha in groundwater/surface water B. Data Interpretation The radiological data collected prior to Byron Nuclear Generating Station becoming operational were used as a baseline with which these operational data were compared . For the purpose of this report, Byron Nuclear Generating Station was considered operational at initial criticality.

Several factors were important in the interpretation of the data:

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated. Exelon reports the TPU by following the result with plus or minus +/- the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the AREOR.

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric radiation, fall-out, domestic water, surface water, marine life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Environmental Radiological Monitoring for Byron Nuclear Generating Nuclear Power Station, Commonwealth Edison Company, Annual Report 1984, April, 1985.

The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater. All groundwater samples listed in the pre-Operational REMP report were <200 pCi/L.

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others.

Additional detail may be found by consulting references (CRA 2006).

a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle.

Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and Sr-90 comes from the former atmospheric testing of thermonuclear weapons.

Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere.

The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected worldwide from 1960 to 2006. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.
c. Surface Water Data Tritium concentrations are routinely measured in large surface water bodies, including Lake Michigan and the Mississippi River.

Illinois surface water data were typically less than 100 pCi/L.

The USEPA RadNet surface water data typically has a reported

'Combined Standard Uncertainty' of 35 to 50 pCi/L. According to USEPA, this corresponds to a+/- 70 to 100 pCi/L 95% confidence bound on each given measurement. Therefore, the typical background data provided may be subject to measurement uncertainty of approximately +/- 70 to 100 pCi/L.

The radio-analytical laboratory is counting tritium results to an Exelon-specified LLD of 200 pCi/L. Typically, the lowest positive measurement will be reported within a range of 40 - 240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from background at this concentration.

IV. Results and Discussion A. Groundwater Results Groundwater Samples were collected from on- and off-site wells throughout the year in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below:

Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1, Appendix 8). Tritium values ranged from less than the detection limit to 611 pCi/L. Outside of the station boundary, tritium concentrations were all less than detection limit (<200 pCi/L). The tritium detected in groundwater samples has been isolated to the Galena- Platteville aquifer, which is isolated from the deeper regional groundwater aquifer by the semi-confining Glenwood Formation . Groundwater quality data from production wells and monitoring wells at the station located below this aquifer do not indicate concentrations of tritium greater than the LLD of 200 pCi/L. As such, the tritium impact is limited to the Galena- Platteville aquifer.

Strontium Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected in any samples above their respective LLDs of 10 and 1 pCi/L.

Gross Alpha (dissolved and suspended)

Gross Alpha analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2019.

Gross Alpha (dissolved) was not detected in any groundwater locations.

Gross Alpha (suspended) was not detected in any groundwater locations.

Concentrations of Gross Alpha which are slightly above detectable levels are considered to be background and are not the result of plant effluents.

Gamma Emitters Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective LLDs in any of the samples during 2019.

B. Drinking Water Well Survey No drinking water well surveys were conducted in 2019.

C. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE are presented in the AREOR.

D. Leaks, Spills, and Releases There are no new previously unidentified leaks or plumes at Byron Station. There were no new leaks, spills or releases at Byron Station in 2019.

E. Trends Wells AR-4 and AR-11 have shown an overall decrease in tritium concentration since first sampled in 2006. Tritium has been measured in Well AR-7 since 2012, however, tritium has been previously measured in this well and it is believed to be the result of legacy tritium prior to 2006 or precipitation recapture, not the result of a new spill or leak.

F. Investigations There were no investigations that took place in 2019 as a result of groundwater sample results.

G. Actions Taken

1. Compensatory Actions No compensatory actions were initiated in 2019.
2. Installation of Monitoring Wells No new monitoring wells were installed in 2019.
3. Actions to Recover/Reverse Plumes No actions were undertaken to recover/reverse plumes in 2019.

APPENDIX A LOCATION DESIGNATION

Intentionally left Blank TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Distance and Direction, Byron Nuclear Generating Station, 2019 Site Site Type Temporary/Permanent Distance and Direction AR-1 Monitoring Well Permanent 0.36 miles/NNW AR-2 Monitoring Well Permanent 0.6 miles/NW AR-3 Monitoring Well Permanent 0.8 miles/NW AR-4 Monitoring Well Permanent 1.36 miles/WNW AR-5 Monitoring Well Permanent 1.92 miles/WNW AR-6 Monitoring Well Permanent 2.04 miles/WNW AR-7 Monitoring Well Permanent 0.04 miles/W AR-8 Monitoring Well Permanent 0.12 miles/S AR-9 Monitoring Well Permanent 0.24 miles/E AR-10 Monitoring Well Permanent 0.28 miles/NE AR-11 Monitoring Well Permanent 1.36 miles/WNW AR-12 Monitoring Well Permanent 366 feet/W AR-13 Monitoring Well Permanent 461 feet/WSW CAR-1 Monitoring Well Permanent 2.25 miles/WNW CAR-3 Monitoring Well Permanent 0.16 miles/SE DF-24 (EPA well) Monitoring Well Permanent 1.36 miles/WNW GW-9 Monitoring Well Permanent 0.9 miles/WNW MW-1 (EPA well) Monitoring Well Permanent 0.6 miles/NW MW-3 (EPA well) Monitoring Well Permanent 0.8 miles/NW TW-13 Monitoring Well Permanent 2.3 miles/WNW TW-14 Monitoring Well Permanent 2.25 miles/WNW TW-15 Monitoring Well Permanent 2.2 miles/WNW Well? Monitoring Well Permanent 0.4 miles/SE CROP Surface Water Permanent 0.2 miles NE A-1

I *+

  • II OF-24

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N Q

AR-11 **

0 2,000 Feet Explanation:

A Surface Water

  • Monitaing Well Figure A-1 Monitoring Well Locations, Byron Nuclear Generating Station, 2019

APPENDIX B DATA TABLES

Intentionally left blank TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM AND GROSS ALPHA IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATING STATION, 2019 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus)

AR-1 03/14/19 < 194 AR-1 05/29/19 < 187 < 9.4 < 0.7 < 0.9 < 1.1 AR-1 08/20/19 < 185 AR-1 11/06/19 < 189 AR-2 05/29/19 < 186 < 0.6 < 0.7 AR-2 11/04/19 < 185 AR-3 03/14/19 < 190 AR-3 05/29/19 < 185 < 6.7 < 0.9 < 0.6 < 0.7 AR-3 08/21/19 < 187 AR-3 11/04/19 < 187 AR-4 03/14/19 201 :t 127 AR-4 05/30/19 298 :t 127 < 6.3 < 0.9 < 0.7 < 2.8 AR-4 08/21/19 272 :t 129 AR-4 11/04/19 < 188 AR-7 03/13/19 246 :t 132 AR-7 05/28/19 231 :t 131 < 5.1 < 1.0 < 3.1 < 2 .1 AR-7 08/19/19 280 :t 127 AR-7 11/05/19 < 191 AR-8 03/13/19 < 194 AR-8 05/28/19 < 194 < 8.1 < 0.9 < 0.8 < 1.1 AR-8 08/19/19 < 184 AR-8 11/05/19 < 189 AR-9 03/14/19 < 193 AR-9 05/29/19 < 195 < 9.8 < 1.0 < 1.0 < 1.1 AR-9 08/20/19 < 182 AR-9 11/06/19 < 195 AR-10 03/14/19 < 192 AR-10 05/29/19 < 194 < 4.6 < 0.9 < 1.7 < 1.1 AR-10 08/20/19 < 184 AR-10 11/06/19 < 189 AR-11 03/14/19 520 :t 144 AR-11 05/30/19 611 :t 141 < 6.9 < 0.9 < 1.1 < 1.2 AR-11 08/21/19 549 :t 140 AR-11 11/04/19 566 :t 139 AR-12 03/13/19 < 191 AR-12 05/28/19 < 196 < 3.9 < 0.8 < 4.5 < 1.7 AR-12 08/19/19 < 181 AR-12 11/05/19 < 192 AR-13 03/13/19 < 194 AR-13 05/28/19 < 193 < 8.8 < 1.0 < 2.7 < 0.6 AR-13 08/19/19 < 183 AR-13 11/05/19 < 188 CAR-1 05/29/19 < 185 < 0.9 < 1.1 CAR-1 11/04/19 < 186 CAR-3 03/13/19 < 195 CAR-3 05/28/19 < 193 < 7.7 < 0.9 < 1.0 < 0.5 CAR-3 08/19/19 < 180 CAR-3 11/05/19 < 196 DF-24 03/14/19 < 192 DF-24 05/29/19 < 185 DF-24 08/21/19 < 191 DF-24 11/04/19 < 188 MW-1 05/29/19 < 186 MW-1 11/04/19 < 188 MW-3 05/29/19 < 188 MW-3 11/04/19 < 183 TW-13 05/29/19 < 183 < 0.6 < 1.2 TW-13 11/04/19 < 186

  • CROP 03/14/19 < 194
  • CROP 05/29/19 < 193 < 0.5 < 0.5
  • CROP 08/20/19 < 181
  • CROP 11/06/19 < 194
  • Surface Water Sample Bold values indicate LLD was not met due to high solids content B-1

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF BYRON NUCLEAR GENERATION STATION, 2019 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 AR-1 05/29/19 < 45 < 72 <4 <4 < 9 < 5 <8 < 5 < 8 < 14 < 5 <4 < 30 < 9 AR-2 05/29/19 < 41 < 92 <4 < 5 < 9 <4 < 10 < 5 < 8 < 15 < 5 < 5 < 30 < 8 AR-3 05/29/19 < 48 < 38 < 5 <6 < 11 <6 < 9 < 5 < 9 < 14 <6 < 5 < 35 < 6 AR-4 05/30/19 < 52 < 80 <6 <6 < 14 < 6 < 12 < 7 < 11 < 14 <6 <6 < 37 < 11 AR-7 05/28/19 < 27 < 29 < 3 < 3 < 6 < 3 <5 < 3 < 5 < 9 < 3 < 3 < 19 < 7 AR-8 05/28/19 < 40 < 45 <5 <4 < 11 <5 <8 <6 < 8 < 13 < 5 <4 < 28 < 9 AR-9 05/29/19 < 43 < 48 <4 <4 < 9 < 5 < 9 <6 < 9 < 14 < 5 < 5 < 31 < 8 AR-10 05/29/19 < 55 < 49 <6 <6 < 13 < 5 < 12 <6 < 11 < 14 <6 <7 < 36 < 12 AR-11 05/30/19 < 57 < 57 < 7 <6 < 13 <6 < 9 < 7 < 10 < 15 <7 <6 < 39 < 14 AR-12 05/28/19 < 49 < 74 < 5 <4 < 12 <6 <9 <6 < 10 < 15 < 5 < 5 < 32 < 12 AR-13 05/28/19 < 40 < 87 <4 <4 < 10 <4 <8 <4 < 8 < 14 < 5 < 5 < 30 < 10 CAR-1 05/29/19 < 51 < 109 <6 <6 < 12 < 5 < 13 <6 < 10 < 15 < 5 <6 < 35 < 8 a, CAR-3 05/28/19 < 50 < 77 < 5 <5 < 12 < 5 < 12 < 5 < 9 < 15 < 5 < 5 < 34 < 11 I

N TW-13 05/29/19 < 53 < 99 < 7 < 5 < 12 < 5 < 10 <6 < 10 < 13 <6 <4 < 33 < 12

  • CROP 05/29/19 < 43 < 34 <5 < 5 < 12 < 6 < 10 <4 < 10 < 13 < 5 <4 < 32 < 9
  • Surface Water Sample
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