RBG-47951, 2018 Annual Radioactive Effluent Release Report
| ML19121A492 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/01/2019 |
| From: | Schenk T Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47951 | |
| Download: ML19121A492 (76) | |
Text
- -=-" Entergy.
RBG-47951 May 1, 2019 Attn: Document Control Desk U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738
Subject:
2018 Annual Radioactive Effluent Release Report River Bend Station - Unit 1 License No. NPF-47 Docket No. 50-458 Entergy Operations, Inc.
River Bend Station 5485 US 61N St 70775 Tel 225-38 l -4 177 Tim Schenk Manager-Regulatory Assurance Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period of January 1, 2018 through December 31, 2018. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.
Should you have any questions regarding the enclosed, please contact Tim Schenk, at (225) 381-4177.
Tim Schenk TAS/tf
Enclosure:
cc:
2018 Annual Radioactive Effluent Release Report NRC Region IV Regional Administrator, w/o Enclosure NRC Senior Resident Inspector - River Bend Station, Unit 1 Ji Young Wiley, Department of Environmental Quality, Office of Environmental Compliance, Radiological Emergency Planning and Response Section Public Utility Commission of Texas, Attn: PUC Filing Clerk NRC Project Manager
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--.-,.,.:. n ~*OJ Plant: River Bend Nuclear Station Page 1 of 75 YEAR: 2018 Document Number: RBG-47951 Annual Radioactive Effluent Release Report
Plant: River Bend Nuclear Station Year: 2018 Page 2 of 75 Annual Radioactive Effluent Release Report TABLE OF CONTENTS
1.0 INTRODUCTION
......................................................................................................................... 3 2.0 SUPPLEMENTAL INFORMATION.............................................................................................. 3 3.0 GASEOUS EFFLUENTS........................................................................................................... 16 4.0 LIQUID EFFLUENTS................................................................................................................ 20 5.0 SOLID WASTE
SUMMARY
...................................................................................................... 25 6.0 RADIOLOGICAL IMPACT TO MAN.......................................................................................... 27 7.0 METEORLOGICAL DATA......................................................................................................... 30 ATTACHMENTS - Groundwater Monitoring Well Sampling Results...........................................................4 7
Plant: River Bend Nuclear Station Year:2018 Page 3 of 75 Annual Radioactive Effluent Release Report
1.0 INTRODUCTION
This is the Annual Radioactive Effluent Release Report for the period of January 1, 2018, through December 31, 2018. This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.1.1 1 OCFR50, Appendix I Limits
- 1.
Fission and activation gases:
- a.
In accordance with Technical Requirement (TR) 3.11.2.2, the air dose due to noble gases released in gaseous effluent to areas at and beyond the SITE BOUNDARY shall be limited to:
- 1)
Quarterly Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta
- 2)
Yearly Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta
- 2.
Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.
- a.
In accordance with Technical Requirement 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from radioiodines (1-131 and 1-133), tritium (H-3) and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluent releases to areas at and beyond the SITE BOUNDARY shall be limited to:
- 1)
Quarterly Less than or equal to 7.5 mrem to any organ
- 2)
Yearly Less than or equal to 15 mrem to any organ
Plant: River Bend Nuclear Station Year:2018 Page 4 of 75 Annual Radioactive Effluent Release Report
- 3.
Liquid Effluents Dose
- a.
In accordance with Technical Requirement 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to UNRESTRICTED AREAS shall be limited to:
- 1)
Quarterly Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ
- 2)
Yearly Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ
- 4.
Total Dose (40CFR190)
- a.
In accordance with Technical Requirement 3.11.4, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to:
Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.
Less than or equal to 75 mrem, Thyroid 2.1.2 Miscellaneous Limits
- 1.
Technical Requirement 3.11.2.1 - Fission and Activation Gases
- a.
In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be:
Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin
- 2.
Technical Requirement 3.11.2.1 - Radioiodine (1-131 & 1-133) and Particulate
- a.
In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioiodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to:
Less than or equal to 1500 mrem/yr to any organ
Plant: River Bend Nuclear Station Year:2018 Page 5 of 75 Annual Radioactive Effluent Release Report
- 3.
Technical Requirement 3.11.1.1 - Liquid Effluent
- a.
In accordance with Technical Requirement 3.11.1.1, the concentration of radioactive material released in liquid effluent to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 1 OCFR20, Appendix 8, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/milliliter total concentration.
- 4.
Technical Requirement 3.11.2.5 - Ventilation Exhaust Treatment
- a.
In accordance with Technical Requirement 3.11.2.5, the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period.
- 5.
Technical Requirement 3.11.1.3 - Liquid Radwaste Treatment System
- a.
In accordance with Technical Requirement 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.
2.2 Effluent Concentration Limits
- 1.
Gaseous Releases
- a.
The concentrations of radioactive gaseous releases are based on the dose rate restrictions in RBS Technical Requirements, rather than the Effluent Concentration Limits (ECL) listed in 1 OCFR20 Appendix B, Table 2, Column 1.
- 2.
Liquid Releases
- a.
The Effluent Concentration Limits of radioactive materials in liquid effluents are limited to ten times 1 OCFR20, Appendix 8, Table 2, Column
- 2.
2.3 Measurements & Approximations of Total Radioactivity
- 1.
Gaseous Efflluent
- a.
Fission & activation gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed using high purity germanium detectors coupled to computerized pulse height analyzers. The sampling and analysis frequencies are described in Table 4.
Plant: River Bend Nuclear Station Year:2018 Page 6 of 75 Annual Radioactive Effluent Release Report Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundance that can then be applied to the noble gas gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. If no activity was detected between the stack grab sample and a significant increase in hourly averages was recorded, the nuclide relative abundance of the last sample (or the last similar event), which indicated the presence of activity, was used to obtain nuclide specific activities. Correction factors for the monitors are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.
- b.
Particulate and Radioiodine (1-131 & 1-133)
Particulates, lodine-131 and lodine-133 are continuously sampled from the three release points using a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 4. Analysis is performed to identify and quantify radionuclides using high purity germanium detectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and duration of the sample, the nuclide specific activity released to the environment can be obtained. Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Strontium-89 and Strontium-90 (Sr-89 and Sr-90) are quantitatively analyzed by counting by gas flow proportional counting.
Gross alpha analysis is performed using a zinc sulfide scintillation counter.
- c.
Tritium Tritium grab samples are obtained from the three gaseous release points at the specified frequencies listed in Table 4 using an ice bath condensation collection method. The collected sample is then analyzed using a liquid scintillation counter. Given the tritium concentration, process flow rate, and time period for which the sample is obtained, the tritium activity released to the environment can be determined. Due to the frequency of sampling, it is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtained.
Plant: River Bend Nuclear Station Year:2018 Page 7 of 75 Annual Radioactive Effluent Release Report
- d.
Carbon-14 The bounding annual dose from C-14 was calculated using guidance from Regulatory Guide 1.21, Revision 2, NUREG-0016, and the methodology in Regulatory Guide 1.109. The results of this calculation are listed in Table 13. The C-14 source term of 11 curies was taken from the site calculation PR(C)-359-3A, Gaseous Releases per NUREG-0016 Revision
- 1. Carbon-14 does not have dose factors associated with standing on contaminated ground; therefore, no ground plane dose was calculated.
There is no milk pathway within five miles of River Bend Station so this pathway is not evaluated. RBS does not take credit for decay in the X/Q.
This calculation assumes the inhalation, meat and vegetation pathways are at the site boundary in the sector with the highest X/Q. The dose from liquid effluents is not calculated as the dose contribution from C-14 is considered to be insignificant as indicated in Regulatory Guide 1.21, Revision 2. According to EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, 95% of the carbon released is in the form of carbon dioxide and this contributes the highest dOSf3 to man.
The ingestion pathway, specifically vegetation, is the most likely route of intake for man. An assumption has been made for gaseous releases that plants obtain all of their C-14 from carbon dioxide.
- e.
Nickel-63 No Nickel-63 was quantified in 2018.
- f.
Gaseous Effluent Summary Information Gaseous effluent summary information is located in Table 1, Table 2, and Table 3. It should be noted that an entry of "O.OOE+OO" Curie (Ci) or microcurie/second (uCi/sec) in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 4. Also, any nuclide not appearing in the tables was < LLD for all four quarters.
- 2.
Liquid Effluents
- a.
Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 8. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high purity germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined using a liquid scintillation counter. Strontium-89 and Strontium-90 are quantitatively analyzed by scintillation techniques (Cherenkov counting). lron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross alpha analysis is performed using a zinc sulfide scintillation counter. The activity of each nuclide released to the environment is determined from the nuclide specific concentration and total tank volume released.
Plant: River Bend Nuclear Station I
Year: 2018 I Page 8 of 75 Annual Radioactive Effluent Release Report
- b.
Liquid effluent summation information is located in Table 5 and Table 6.
It should be noted that an entry of "O.OOE+OO" Ci or uCi/ml in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 8. Also, any nuclide not appearing in the tables was < LLD for all four quarters.
- 3.
Estimate of Total Error
- a.
Liquid The maximum error associated with sample collection, laboratory analysis, and discharge volume is collectively estimated to be:
Fission and Activation
+ 14.2%
Products Tritium
+ 14.2%
Dissolved and Entrained
+ 14.2%
Noble Gases Gross Alpha Radioactivity
+ 14.2%
- b.
Gaseous The maximum error (not including sample line loss) associated with sample flow, process flow, sample collection, monitor accuracy and laboratory analysis are collectively estimated to be:
Noble Gases
+/- 37.0%
+ 18.6%
Particulate
+ 18.6%
+ 18.2%
- c.
Determination of Total Error The total error (i.e., collective error due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.) is calculated using the following equation:
Where:
Er = total error E1... En = individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.
Plant: River Bend Nuclear Station Year:2018 Annual Radioactive Effluent Release Report 2.4 Batch Releases:
2.4.1 Liquid Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2018, through December 31, 2018 are shown in Table 7.
Page 9 of 75 The Mississippi River stream flow is obtained by averaging data from the U. S. Army Corp of Engineers website using flow gauge data at Tarbert Landing.
2.4.2 Gaseous There were no routine batch releases of gaseous effluents from River Bend Station during the reporting period of January 1, 2018, through December 31, 2018.
I 2.5 Abnormal Releases There were no abnormal releases in 2018.
2.6 Maior Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems Engineering performed a review of the Asset Suite database to evaluate non-administrative design changes completed or partially completed during 2018 involving the subject systems (i.e. changes classified as evaluations or nuclear changes).
These design changes were then reviewed to determine if there have been any major changes to the subject systems. The review was based on a major change being defined as a modification which affected the method of processing or the effluent from the system. Also, to be a "major change" the change must have affected the Updated Safety Analysis Report (USAR).
The Engineering Changes (EC's) to liquid, solid or gaseous radwaste systems implemented during this time period were:
EC-78823 Radwaste Building Scaffold over LWS-TK1 D This EC evaluates installation of temporary shadow shielding installed on scaffolding over LWS-TK1 D, Waste Collector Tank 1 D. This change has no direct interface with radwaste components and does not impact any method of radwaste processing or system effluent.
EC-77758 Radwaste Building Scaffold over LWS-TK2A, 28 and 2C This EC evaluates installation of temporary shadow shielding installed on scaffolding over LWS-TK2A, B and C, Floor Drain Collector Tank 2A, B, and C. This change has no direct interface with radwaste components and does not impact any method of radwaste processing or system effluent.
Plant: River Bend Nuclear Station Year: 2018 Page 10 of 75 Annual Radioactive Effluent Release Report EC-76726 Provide a Method for Standby Cooling Tower Basin Periodic Slowdown to the Radwaste Discharge Line when Co60 is Detected This Temporary Modification EC was installed 4/28/2018 and provides a temporary blow-down path for the Standby Cooling Tower (SBCT) to the CWS blow-down line as recommended by the I.E.Bulletin 90-10 Evaluation in CR-RBS-2017-1030 CA-4. The purpose of this temporary blow-down path is to enable an alternate method for discharging water inventory of the Standby Cooling Tower. It is needed to maintain SBCT level within its operating parameters until bulk Co-60 nuclide levels in the SBCT basin are reduced sufficiently. The SBCT level fluctuates due to inputs from rainwater, Standby Service Water (SSW) pump operation, and other factors. The normal method of discharging SBCT wastewater to the Flume is no longer viable until Co-60 effluent in the upper SBCT basin is within acceptable levels as determined by site management and the action plan developed by CR-RBS-2017-1030 is complete. When this discharge pathway is in use, other LWS discharges are suspended.
It should be noted that the Co-60 amounts and chemical concentrations are determined and verified to be less than allowable limits by initial sampling and analysis prior to discharge from the SBCT and from periodic sampling in accordance with Chemistry procedure COP-0813 to meet UFSAR and 1 OCFR20 requirements.
As a result of CR-RBS-2017-1030 an IEB 80-10 Evaluation was performed as required by EN-CY-108 Section 5.S(c). The evaluation concluded that none of the radiological dose limits detailed in 10 CFR 20.1301, 10 CFR 20.1302, 10 CFR 50, Appendix I or 40 CFR 190 would be exceeded. Any release would require an abnormal release permit to ensure that the conclusions developed by the evaluation remain valid and the results must be provided as part of the Annual Radiological Effluent Release Report.
The introduction of Co-60 to the normal and standby service water systems is considered a one-time event with plant and public radiological impacts of the magnitude of the original evaluated system contamination.
There is no adverse impact created by the introduction of Co-60 into the SBCT. While this IEB 80-10 Evaluation concluded that none of the above radioactive dose limits would be exceeded, the Evaluation also recommended not sending radiologically contaminated water to the Waste Water Treatment Plant (WWTP) or to the CWS flume. This TMOD EC provides an acceptable alternate pathway which temporarily discharges the SBCT effluent to the CWS blowdown pit (instead of sending it to the CWS flume) where it is further diluted and therefore meets the requirements and methods of performing and or controlling the design function of radioactive effluent discharge as described in the UFSAR.
This change is not considered as a major change as there is no impact on the Liquid Radwaste system that affects the method of processing or system effluent.
Plant: River Bend Nuclear Station Year: 2018 Page 11 of 75 Annual Radioactive Effluent Release Report EC-70436 - Emergency TMOD: Install a Temporary Gag Device onto N64-AOVF032A in Order to Assure the Valve Remains Open during Offgas System Operation The purpose of this Emergency TMOD EC is to temporarily gag OPEN N64-AOVF032A, OFG SYS CLR CONDENSER A INLET ISOL VLV. The associated ASCO solenoid valve, N64-SOVF032A, is leaking air (CR-RBS-2017-02567). The solenoid valve energizes and ports air normally when signaled to CLOSE the AOV. The defective solenoid is apparently intermittently porting air to the AOV, causing erratic operation of the AOV and leading to Operations concern that the valve would close inadvertently and stall OFFGAS flow, requiring a plant shutdown.
N64-AOVF032A valve is the Offgas Cooler Condenser Inlet Isolation valve. During normal Offgas operation the AOV is throttled open to port process air from the holdup line to the associated cooler condenser, N64-CNDB01 OA, to further chill the process air to drive out moisture to improve charcoal adsorber efficiency downstream.
This Emergency TMOD EC was installed at-risk without paperwork on 11/15/2017 per WO 00469930 with preparation of the Emergency TMOD EC to follow. This EC was not documented on the 2017 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems, LO-RL0-2018-00003 CA-3, as the EC installation sign-off was not completed until 1 /16/2018. This Emergency TMOD was removed 2/6/2018.
This change is not considered to be a major change as there is no impact on the system that affects the method of processing or system effluent.
EC 58815 - Replace Obsolete Offgas Dryer Heater Temperature Controller N64-TICR0328 This EC replaces the original obsolete LFE Corporation model 227 temperature controller with an equivalent SOLO Temperature Controller Model SL4896-CRE. The replacement controller critical characteristics are acceptable and provide the same level of process control as the original temperature controller.
This change is not considered as a major change as there is no impact on the system that affects the method of processing or system effluent.
EC 58771 - Add Removable Spool Piece to Pipe OFG-002-234-4 for Cleaning of Offgas Dryer N64-DRY030C This Engineering Change (EC) has been generated to add a removable spool piece to pipe OFG-002-234-4 for cleaning of Off-gas Desiccant Dryer Skid "C" (N64-DRYD030C).
Dryer Vessels (N64-DRYD030A, B, C, and D), two on each dryer train, are ASME VIII pressure vessels, 36 W' OD filled with 900 lb of desiccant, each of which reduces the dew point of the gas stream to -90°F. At the bottom of the vessel, a perforated plate and screen prevents the desiccant from settling at the inlet port and obstructing gas flow.
Plant: River Bend Nuclear Station Year:2018 I Page 12 of 75 Annual Radioactive Effluent Release Report This change is not considered a major change as providing a spool piece to enable access for cleaning does not change the design or operating parameters of the Dryers or the Offgas system and there is no change to system effluent.
EC-53367 - Liquid Radwaste Piping Replacement River Bend Station (RBS) Condition Report CR-RBS-2000-2033 identified leakage on 2" diameter Liquid Waste System (LWS) discharge line LWS-002-615-4, leading to elevated levels of radioactive material in the soil adjacent to the buried portion of piping. This line functions in parallel with a 3" diameter Service Water Piping (SWP) line, SWP-003-1043-4. Line SWP-003-1043-4 was dedicated to the LWS by M86-0156 in order to increase the discharge capacity to the Circulating Water System (CWS).
This EC removes a portion of discharge line LWS-002-615-4, and all of lines LWS-003-1000-4 and LWS-002-640-4 from 2" valve LWS-AOV257 to the CWS blowdown pit. The segment of line SWP-003-1043-4 routed inside the plant is also removed by this modification. Line LWS-002-640-4 and the buried segment of SWP-003-1043-4 are retired-in-place by filling the lines with a flowable grout and installing blind flanges on the ends. The existing lines are replaced by approximately 100 feet of 2" diameter piping and approximately 1000 feet of 4" diameter piping. The new LWS piping utilizes the existing LWS/SWP pipe routing and existing pipe supports, where possible, for the portion of piping inside the piping tunnels.
A new engineered trench configuration is installed for the exterior portion of piping in the site yard, from the Turbine Building (TB) to the CWS blowdown pit. Stainless steel pipe is used for the in-plant piping and heat fusion joined High Density Polyethylene (HOPE) pipe is used for the exterior piping that is routed inside the concrete trench. Flanges are installed at the stainless steel/HOPE piping interface. Inside the CWS blowdown pit, the new 4" diameter LWS line connects to line CWS-020-35-4 via new 4" diameter CWS valve and line. The new 4" diameter CWS valve and line is installed by performing a 'hot tap' on line CWS-020-35-4.
Two (2) new, 6" diameter wall penetrations are installed to route the 4" diameter HOPE piping. The first new penetration is installed at El. 93' on the south wall of the Turbine Building, near existing penetrations for lines LWS-002-615-4 and SWP-003-1043-4. The second penetration is installed at El. 90.67' on the west wall of the CWS Slowdown Pit, approximately 27'-9" from the south edge.
There is no impact to the method of liquid waste processing or system effluent as a result of this change.
Plant: River Bend Nuclear Station Year: 2018 I Page 13 of 75 Annual Radioactive Effluent Release Report EC-41004 Provide Temporary Equipment and Process Details to Pump, Store, and Discharge Ground Water from Well #MW-125 to the Temporary Slowdown Line Previously Installed in TMOD EC 35300 The purpose of this Temporary Modification (TMOD) was to provide a temporary above-ground path for groundwater discharges from well MW-125 in the Unit 2 hole to the temporary blowdown piping via valve TMOD EC 35300-V6, which discharges to the blowdown pit via 4 inch HOPE (High Density Polyethylene) pipe installed by TMOD EC 35300. TMOD EC-41004 was installed on 8/2/2013 and determined not to constitute a major change as reported in the 2013 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems, LO-RL0-2014-00005 CA-2. This TMOD was removed 3/29/2018.
EC-35300 Add Temporary Above-Ground LWS Slowdown Line including Changes to Support EC-41004 and EC-47012 A temporary modification (TMOD) has been installed per EC-35300 to allow the LWS to discharge processed liquid radwaste to the CWS blowdown pit. EC-35300 disconnected lines LWS-002-615-4 and SWP-003-1043-4 from the LWS and placed the lines out-of-service. Installation of EC-53367 requires the disconnection of temporary modification EC-35300 from the LWS. This TMOD was installed 5/20/2012 and determined not to constitute a major change as reported in the 2012 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems, LO-RL0-2013-00006 CA-2. This TMOD was removed 3/19/2018.
No EC was identified as being completed during this time period that modified any radioactive waste system major component such that the processing method or effluent was changed. Also no changes were identified affecting the method of processing solid, liquid or gaseous waste or the isotopic composition or the quantity of liquid, solid, or gaseous waste as described in the USAR.
In conclusion, no design changes were completed during the specified time period that constituted a major change to either the liquid, solid or gaseous radwaste treatment systems.
- 2. 7 Land Use Census Changes The Land Use Census for 2018 was conducted as required by the Technical Requirements Manual (TRM) (TR 3.12.2). The results of the Land Use Census will be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.
A garden census is not conducted pursuant to the note in the TRM 3.12.2 that allows the sampling of broadleaf vegetation in the highest calculated average ground-level D/Q sector near site boundary in lieu of the garden census.
The milk animal census identified no milk animals within 8 km (5 miles) of River Bend site. This information was verified by the County Agents from West Feliciana, East Feliciana and Pointe Coupee parishes.
Plant: River Bend Nuclear Station Year:2018 Page 14 of 75 Annual Radioactive Effluent Release Report One resident census change was noted in Sector A that changed the nearest resident in Sector A from 1.9 km to 1.7 km.
No locations were identified this period that would yield a calculated dose or dose commitment greater than those currently calculated in Requirement TSR 3.11.2.3.1.
The County Agents confirmed that there was no commercial harvesting of crawfish within the five-mile radius downstream of RBS. RBS conservatively uses the invertebrate pathway although not required by NUREG-0133 liquid dose factor methodology for fresh water nuclear power plants.
2.8 Effluent Monitor Instrument lnoperability 2.8.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.2-1 of Technical Requirement 3.3.11.2 were, if inoperable at any time in the period January 1, 2018, through December 31, 2018, restored to operable status within the required time.
2.8.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability The minimum number of channels required to be OPERABLE as described in Table 3.3.11.3-1 of Technical Requirement 3.3.11.3 were, if inoperable at any time in the period January 1, 2018, through December 31, 2018, restored to operable status within the required time.
2.9 Offsite Dose Calculation Manual Changes There were no changes to the Offsite Dose Calculation Manual in 2018.
2.10 Radiological Environmental Monitoring Program Changes There were no changes to the Radiological Environmental Monitoring Program during the reporting period January 1, 2018, through December 31, 2018.
2.11 Process Control Program (PCP) Changes There were no changes to the Process Control Program (PCP) in 2018.
2.12 NON-REMP Groundwater Monitoring Results (NEI 07-07)
Ground water samples were taken in support of the Groundwater Protection Initiative (GPI). These samples are not part of the Radiological Environmental Monitoring Program. The sample results for 2018 are located in Table 17, Table 18, and Table 19.
River Bend Station made no NEI 07-07 voluntary notifications in 2018.
Plant: River Bend Nuclear Station Year:2018 Page 15 of 75 Annual Radioactive Effluent Release Report 2.13 Outside Tanks The maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of January 1, 2018, through December 31, 2018 was less than or equal to the 1 O curie limit as required by Technical Specification 5.5.8.b.
Plant: River Bend Nuclear Station Year:2018 Page 16 of 75 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gas Effluent and Waste Disposal Report Table 1, Gaseous Effluents-Summation of All Releases A.
Fission & Activation Gases Unit Quarter Quarter Quarter Quarter 3
Annual 1
2 4
- 1.
Total Release Ci 2.26E+02 8.71E+01 1.66E+02 4.82E+02 9.61E+02
- 2.
Average release rate for the period
µCi/sec 2.91E+01 1.11E+01 2.09E+01 6.06E+01 3.05E+01 B.
- 1.
Total Iodine - 131 Ci 1.11 E-02 2.40E-02 2.36E-02 5.04E-02 1.09E-01
- 2.
Average release rate for the period
µCi/sec 1.43E-03 3.0SE-03 2.97E-03 6.34E-03 3.46E-03
- c.
Particulates
- 1.
Particulates with half-lives> 8 days Ci 4.12E-04 4.62E-04 6.28E-04 6.98E-04 2.20E-03
- 2.
Average release rate for the period
µCi/sec 5.30E-05 5.87E-05 7.90E-05 8.78E-05 6.97E-05 D.
- 1.
Total Release Ci 2.93E+OO 3.85E+OO 8.34E+OO 3.04E+OO 1.82E+01
- 2.
Average release rate for the period
µCi/sec 3.77E-01 4.90E-01 1.0SE+OO 3.83E-01 5.76E-01 E.
Gross Alpha
- 1.
Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2.
Average release rate for the period
µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO F.
- 1.
Total Release Ci 2.71E+OO 2.74E+OO 2.77E+OO 2.77E+OO 1.1 E+01
- 2.
Average release rate for the period
µCi/sec 3.49E-01 3.48E-01 3.48E-01 3.48E-01 3.49E-01
% of limit is located in the Radiological Impact to Man Table
Plant: River Bend Nuclear Station Year: 2018 Page 17 of 75 Annual Radioactive Effluent Release Report Table 2, Gaseous Effluents - Ground Level Release - Continuous Mode Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission Gases Xe-131 m Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.45E+OO 1.45E+OO Xe-133 Ci 1.32E+01 2.77E+OO 3.19E+OO 1.67E+01 3.59E+01 Xe-135 Ci 4.89E+OO 6.42E+OO 1.28E+01 4.17E+01 6.58E+01 Xe-135m Ci 8.55E+OO 7.75E+OO 1.26E+01 1.21 E+01 4.10E+01 Xe-138 Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.60E-01 8.60E-01 Total for Period Ci 2.67E+01 1.69E+01 2.85E+01 7.29E+01 1.45E+02 Iodines 1-131 Ci 1.26E-04 1.88E-04 2.67E-04 2.32E-04 8.14E-04 1-133 Ci 5.46E-05 8.57E-05 8.1 BE-05 7.41 E-05 2.96E-04 Total for Period Ci 1.81 E-04 2.73E-04 3.49E-04 3.06E-04 1.11E-03 Particulates Cr-51 Ci O.OOE+OO O.OOE+OO 4.14E-06 O.OOE+OO 4.14E-06 Co-60 Ci 4.19E-06 2.19E-06 1.1 BE-06 1.67E-06 9.23E-06 Ce-141 Ci 3.92E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.92E-07 Total for Period Ci 4.58E-06 2.19E-06 5.32E-06 1.67E-06 1.38E-05 Tritium H-3 Ci 5.77E-01 1.79E+OO 7.17E+OO 1.42E+OO 1.10E+01
Plant: River Bend Nuclear Station Year: 2018 I Page 18 of 75 Annual Radioactive Effluent Release Report Table 3, Gaseous Effluents - Mixed Mode Release - Continuous Mode Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission Gases Ar-41 Ci 1.45E+OO 3.27E-02 1.72E-02 O.OOE+OO 1.50E+OO Kr-83m Ci O.OOE+OO 1.12E+OO O.OOE+OO O.OOE+OO 1.12E+OO Kr-85m Ci 3.27E+01 1.10E+01 9.75E+OO 1.41E+OO 5.49E+01 Kr-87 Ci 3.02E+OO O.OOE+OO 1.98E+OO 6.34E-01 5.63E+OO Kr-88 Ci 2.91E+01 O.OOE+OO 1.22E+01 2.06E+OO 4.33E+01 Xe-131 m Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-04 1.65E-04 Xe-133 Ci 6.14E+01 5.67E+OO 1.03E+01 2.48E+02 3.25E+02 Xe-133m Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.92E+OO 3.92E+OO Xe-135 Ci 2.70E+01 2.87E+01 5.30E+01 9.98E+01 2.09E+02 Xe-135m Ci 1.64E+01 1.41E+01 3.65E+01 3.12E+01 9.82E+01 Xe-137 Ci 5.70E+OO O.OOE+OO O.OOE+OO 4.90E+OO 1.06E+01 Xe-138 Ci 2.28E+01 9.56E+OO 1.37E+01 1.71 E+01 6.32E+01 Total for Period Ci 2.00E+02 7.02E+01 1.38E+02 4.09E+02 8.16E+02 Iodines 1-131 Ci 1.73E-03 3.66E-03 4.11E-03 7.42E-03 1.69E-02 1-133 Ci 9.17E-03 2.00E-02 1.91 E-02 4.27E-02 9.1 OE-02 Total for Period Ci 1.09E-02 2.37E-02 2.32E-02 5.01 E-02 1.08E-01 Particulates Mn-54 Ci 4.64E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.64E-06 Co-58 Ci 1.57E-06 O.OOE+OO O.OOE+OO 1.96E-06 3.53E-06 Co-60 Ci 2.71E-05 1.53E-05 2.18E-06 8.82E-06 5.34E-05 Zn-65 Ci 1.48E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-06 Sr-89 Ci 1.97E-04 2.82E-04 3.49E-04 4.01 E-04 1.23E-03 Sr-90 Ci 2.74E-06 O.OOE+OO 2.05E-06 O.OOE+OO 4.79E-06 Nb-95 Ci O.OOE+OO O.OOE+OO 1.14E-06 O.OOE+OO 1.14E-06 Ru-103 Ci 5.83E-07 O.OOE+OO O.OOE+OO O.OOE+OO 5.83E-07 Ag-110m Ci 3.34E-06 O.OOE+OO 2.46E-06 1.94E-05 2.52E-05 Cs-134 Ci 1.54E-06 O.OOE+OO 3.13E-06 O.OOE+OO 4.67E-06 Cs-136 Ci 8.73E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.73E-07 Cs-137 Ci 2.86E-06 O.OOE+OO 1.56E-06 O.OOE+OO 4.42E-06 Ba-140 Ci 1.64E-04 1.62E-04 2.61E-04 2.65E-04 8.51 E-04 Total for Period Ci 4.08E-04 4.59E-04 6.23E-04 6.96E-04 2.19E-03 Tritium H-3 Ci 2.35E+OO 2.07E+OO 1.17E+OO 1.62E+OO 7.21 E+OO
Plant: River Bend Nuclear Station Year: 2018 Page 19 of 75 Annual Radioactive Effluent Release Report Table 4, Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Type of Activity Lower Lim it of Analysis Detection (LLD)
Type Frequency Frequency Analysis uC/ml M
Principle Gamma 1.00E-04 Main Plant Exhaust M
Emitters Duct Grab Sample H-3 1.00E-06 Fuel Building M
Principle Gamma 1.00E-04 Ventilation Exhaust M
Emitters Duct Grab Sample H-3 1.00E-06 Radwaste Building M
Principle Gamma 1.00E-04 Ventilation Exhaust M
Emitters Duct Grab Sample H-3 1.00E-06 All Release Types w
1-131 1.00E-12 Continuous as listed above Charcoal Sample 1-133 1.00E-10 w
Principle Gamma Continuous Emitters (1-131, 1.00E-11 Particulate Sample Others)
M Continuous Composite Gross Alpha 1.00E-11 Particulate Sample Q
Continuous Composite Sr-89, Sr-90 1.00E-11 Particulate Sample Noble Gases Continuous Noble Gas Monitor Gross Beta or 1.00E-6 Gamma W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days
Plant: River Bend Nuclear Station Year: 2018 Page 20 of 75 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent and Waste Disposal Report Table 5, Liquid Effluents-Summation of All Releases A.
Fission & Activation Products Unit Quarter Quarter Quarter Quarter Annual 1
2 3
4
- 1.
Total Release (not including tritium, Ci 2.48E-03 3.59E-03 2.30E-03 7.77E-04 9.14E-03 gases or alpha) 2 Average diluted concentration during
µCi/ml 2.72E-09 2.67E-09 1.62E-09 5.54E-09 1.80E-09 period B.
- 1.
Total Release Ci 1.04E+01 1.41E+01 2.46E+01 1.19E+01 6.10E+01
- 2.
Average diluted concentration during
µCi/ml 1.14E-05 1.0SE-05 1.72E-05 8.SOE-05 1.20E-05 period.
- c.
Dissolved & Entrained Gases
- 1.
Total Release Ci 5.66E-02 7.69E-02 3.40E-01 1.26E-01 5.99E-01
- 2.
Average diluted concentration during
µCi/ml 6.21E-08 5.73E-08 2.39E-07 8.97E-08 1.18E-07 period D.
Gross Alpha Activity
- 1.
Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E.
Volume Of Waste Released (prior Liters 1.65E+06 2.87E+06 4.97E+06 2.05E+06 1.15E+07 to dilution)
F.
Volume Of Dilution Water Used During Liters Period 9.12E+08 1.34E+09 1.42E+09 1.40E+09 5.08E+09
% of limit is located in the Radiological Impact to Man Table
Plant: River Bend Nuclear Station Year: 2018 Page 21 of 75 Annual Radioactive Effluent Release Report Table 6, Liquid Effluents - Batch Release Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission and Activation Products Cr-51 Ci 1.30E-05 O.OOE+OO O.OOE+OO 1.65E-05 2.95E-05 Mn-54 Ci 2.13E-04 1.11 E-04 3.61 E-05 O.OOE+OO 3.60E-04 Co-57 Ci O.OOE+OO 1.03E-06 O.OOE+OO O.OOE+OO 1.03E-06 Co-58 Ci 1.40E-06 O.OOE+OO 4.16E-06 O.OOE+OO 5.56E-06 Co-60 Ci 2.03E-03 2.86E-03 1.87E-03 7.12E-04 7.48E-03 Ni-65 Ci O.OOE+OO 1.55E-05 O.OOE+OO O.OOE+OO 1.55E-05 Zn-65 Ci 3.89E-05 1.93E-05 4.30E-06 O.OOE+OO 6.25E-05 Br-82 Ci O.OOE+OO 9.12E-07 O.OOE+OO O.OOE+OO 9.12E-07 Rb-88 Ci 4.19E-05 1.90E-04 1.56E-04 O.OOE+OO 3.88E-04 Sr-91 Ci O.OOE+OO 9.63E-06 O.OOE+OO O.OOE+OO 9.63E-06 Zr-95 Ci 2.64E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.64E-06 Nb-97 Ci O.OOE+OO 2.39E-06 O.OOE+OO O.OOE+OO 2.39E-06 Ru-103 Ci O.OOE+OO O.OOE+OO 1.1 BE-06 O.OOE+OO 1.18E-06 Ag-110m Ci O.OOE+OO 4.46E-06 3.66E-06 O.OOE+OO 8.12E-06 Rh-105 Ci O.OOE+OO O.OOE+OO 5.83E-06 8.69E-06 1.45E-05 Sb-122 Ci O.OOE+OO 4.74E-06 O.OOE+OO O.OOE+OO 4.74E-06 1-131 Ci 9.05E-06 9.72E-06 1.27E-04 3.79E-05 1.84E-04 1-133 Ci O.OOE+OO O.OOE+OO 2.27E-05 1.63E-06 2.43E-05 Cs-134 Ci 2.68E-05 7.53E-06 1.31 E-06 O.OOE+OO 3.57E-05 Cs-137 Ci 3.26E-05 8.36E-06 O.OOE+OO O.OOE+OO 4.10E-05 Cs-138 Ci O.OOE+OO 2.34E-05 O.OOE+OO O.OOE+OO 2.34E-05 Ba-139 Ci O.OOE+OO O.OOE+OO 5.22E-06 O.OOE+OO 5.22E-06 Ba-140 Ci O.OOE+OO 4.36E-06 O.OOE+OO O.OOE+OO 4.36E-06 Ba-142 Ci O.OOE+OO 2.54E-04 5.45E-05 O.OOE+OO 3.0BE-04 La-140 Ci 5.47E-05 2.63E-05 8.54E-06 O.OOE+OO 8.95E-05 Ce-141 Ci 1.53E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-05 Ce-144 Ci O.OOE+OO 2.64E-05 O.OOE+OO O.OOE+OO 2.64E-05 W-187 Ci O.OOE+OO 4.94E-06 O.OOE+OO O.OOE+OO 4.94E-06 Total for Period Ci 2.48E-03 3.59E-03 2.30E-03 7.77E-04 9.14E-03 Tritium H-3 Ci 1.04E+01 1.41E+01 2.46E+01 1.19E+01 6.10E+01 Total for Period Ci 1.04E+01 1.41E+01 2.46E+01 1.19E+01 6.10E+01
Plant: River Bend Nuclear Station Year:2018 Page 22 of 75 Annual Radioactive Effluent Release Report Table 6, Liquid Effluents - Batch Release Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Dissolved and Entrained Gases Kr-85m Ci O.OOE+OO 9.28E-06 O.OOE+OO O.OOE+OO 9.28E-06 Kr-85 Ci O.OOE+OO 2.48E-04 O.OOE+OO O.OOE+OO 2.48E-04 Kr-87 Ci O.OOE+OO 2.07E-05 O.OOE+OO O.OOE+OO 2.07E-05 Kr-88 Ci 1.78E-05 1.15E-04 1.06E-04 O.OOE+OO 2.39E-04 Xe-131 m Ci O.OOE+OO O.OOE+OO 4.BOE-04 9.35E-04 1.42E-03 Xe-133m Ci 1.33E-03 1.55E-03 9.32E-03 2.66E-03 1.49E-02 Xe-133 Ci 2.90E-02 4.06E-02 2.03E-01 6.58E-02 3.38E-01 Xe-135 Ci 2.63E-02 3.44E-02 1.27E-01 5.64E-02 2.44E-01 Total for Period Ci 5.66E-02 7.69E-02 3.40E-01 1.26E-01 5.99E-01
Plant: River Bend Nuclear Station Year:2018 Page 23 of 75 Annual Radioactive Effluent Release Report Table 7, Supplemental Information for Liquid Effluents - Batch Mode Report for 2018 Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Number of releases 29 45 80 34 188 Total Release Time minutes 8.76E+03 1.50E+04 2.63E+04 1.12E+04 6.12E+04 Maximum Release Time minutes 3.64E+02 1.09E+03 1.32E+03 9.13E+02 1.32E+03 Average Release Time minutes 3.02E+02 3.32E+02 3.29E+02 3.29E+02 3.25E+02 Minimum Release Time minutes 1.30E+02 2.65E+02 2.36E+02 2.57E+02 1.30E+02 Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Average Mississippi River stream ft3/sec flow during periods of release into 723, 166 768, 136 421,963 752,061 a flowing stream
Plant: River Bend Nuclear Station Year: 2018 I Page 24 of 75 Annual Radioactive Effluent Release Report Table 8, Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Minimum Type of Activity Lower Limit of Analysis Detection (LLD)
Type Frequency Frequency Analysis uC/ml Batch Waste Principle Gamma 5.00E-07 Release (Liquid p
p Emitters; except 5.00E-06 Ce-144 Radwaste Recovery Each Batch Each Batch Sample Tanks) 1-131 1.00E-06 p
Dissolved and M
Entrained Gases 1.00E-05 Each Batch I M (Gamma Emitters) p M
H-3 1.00E-05 Each Batch Composite Gross Alpha 1.00E-07 p
Q Sr-89, Sr-90 5.00E-8 Each Batch Composite Fe-55 1.00E-06 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days
Plant: River Bend Nuclear Station I
Year:2018 Page 25 of 75 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE
SUMMARY
5.1 Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel}
5.1.1 Types of Waste Table 9, Types of Solid Waste Summary Types of Waste Total Quantity Total Activity Est. Total (m3)
(Ci)
Error(%)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
9.33E+01 9.24E+01 25
- b. Dry compressible waste, contaminated equip, etc.
7.15E+02 1.67E+01 25
- c. Irradiated components, control rods, etc.
O.OOE+OO O.OOE+OO 25
- d. Other (Water, EHC, Waste Oil, etc.)
2.79E+01 3.55E-01 25 5.1.2 Estimate of major nuclide composition (by waste type) only >1 % [Note 11 are reported.
Table 10, Major Nuclides Major Nuclide Composition Isotope Curies C-14 7.3 6.74E+OO Mn-54 2.64 2.44E+OO Fe-55 26.31 2.43E+01 Co-60 51.76 4.78E+01
- a. Resins, filters, evaporator bottoms, etc.
Ni-63 2.17 2.00E+OO Zn-65 3.85 3.56E+OO Cs-134 1.44 1.33E+OO Cs-137 2.83 2.61E+OO Mn-54 3.2 5.37E-01 Fe-55 53.74 9.0E+OO
- b. Dry compressible waste, contaminated Co-60 36.91 6.18E+OO equip, etc.
Ni-63 1.87 3.13E-01 Zn-65 1.58 2.65E-01
- c. Irradiated components, control rods, etc.
N/A N/A N/A
Plant: River Bend Nuclear Station Year: 2018 Page 26 of 75 Annual Radioactive Effluent Release Report Table 10, Major Nuclides Major Nuclide Composition Isotope Curies Cr-51 1.23 4.36E-03 Mn-54 4.4 1.56E-02
- d. Other (Water, EHC, Waste Oil, Etc.)
Fe-55 48.21 1.71E-01 Co-60 42.15 1.50E-01 Zn-65 1.03 3.67E-03
[Note 1] - "Major" radionuclide is equivalent to a "principle" radionuclide, i.e. greater than 1 percent of total activity.
5.1.3 Solid Waste Disposition Table 11, Solid Waste Disposition (Specify Site or Unit)
Number of Mode of Transportation Destination Shipments 4
Truck Energy Solutions, LLC (Gallaher) - Oak Ridge, TN 35 Truck Energy Solutions (Bear Creek) - Oak Ridge, TN Table 12, Irradiated Fuel Shipments Disposition No Irradiated Fuel Shipments for 2018 Number of Mode of Transportation Destination Shipments NIA N/A N/A
Plant: River Bend Nuclear Station Year:2018 Page 27 of 75 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 1 OCFR Part50, Appendix I Evaluation Table 13, Dose Assessment Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Total Body Total Body Dose 5.60E-05 2.96E-05 2.67E-05 4.03E-06 1.26E-04
% of Limit 3.73E-03 1.97E-03 1.78E-03 2.69E-04 4.19E-03 Liquid Effluent Dose Limit, 5 mrem 5 mrem 5mrem 5mrem 10 mrem Any Organ Maximum Organ Dose 2.19E-04 1.62E-04 1.17E-04 9.83E-04 5.41 E-04
% of Limit 4.38E-03 3.24E-03 2.35E-03 1.97E-04 5.41E-03 Gaseous Effluent Dose 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Limit, Gamma Air Gamma Air Dose 1.48E-01 7.42E-02 1.50E-01 2.42E-01 6.13E-01
% of Limit 2.95E+OO 1.48E+OO 3.00E+OO 4.83E+OO 6.13E+OO Gaseous Effluent Dose 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Lim it, Beta Air Beta Air Dose 9.65E-02 4.89E-02 9.12E-02 2.53E-01 4.89E-01
% of Limit 9.60E-01 4.90E-01 9.10E-01 2.53E+OO 2.45E+OO Gaseous Effluent Organ Dose Limit (Iodine, 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Tritium, Particulates with >
8 day half-life)
Gaseous Effluent Organ Dose (Iodine, Tritium, 8.13E-02 1.65E-01 2.13E-01 3.0BE-01 7.67E-01 Particulates with> 8 day half-life)
% of Limit 1.0SE+OO 2.20E+OO 2.84E+OO 4.10E+OO 5.11E+OO
Plant: River Bend Nuclear Station Year:2018 Page 28 of 75 Annual Radioactive Effluent Release Report Table 13, Dose Assessment (continued)
Quarter 1 Quarter 2 Quarter 3 Quarter4 Annual Gaseous Effluent Organ Dose Limit (Carbon 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Bounding Calculation)
Gaseous Effluent Organ Dose (Carbon 1.16E+OO 1.17E+OO 1.18E+OO 1.18E+OO 4.70E+OO Bounding Calculation)
% of Limit 1.55E+01 1.56E+01 1.58E+01 1.58E+01 3.13E+01 6.2 Dose to Members of the Public Inside the Site Boundary The maximally exposed member of the pubic was calculated to be member of the West Feliciana Parish Sheriff's Office (WFPSO) that opened a substation in a facility within the site boundary beginning in 2018. The office is estimated to be occupied during normal work hours for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year. It should be noted that the liquid effluent pathway dose was not considered since the individual would not engage in activities that would allow exposure to this pathway.
Annual Critical Annual Total Annual Skin Annual Location Organ Dose Body Dose Dose (mrem)
Duration Factor (mrem)
(mrem)
Alligator Bayou 4.90E-05 8.13E-06 5.67E-07 4.57E-03 Deer Hunters 2.23E-03 6.12E-04 4.84e-05 2.92E-02 Onsite RV Park 5.20E-03 1.43E-03 1.13E-04 6.82E-02 WFPSO Building 1.74E-02 4.78E-03 3.78E-04 2.28E-01 6.3 40CFR Part 190 Evaluation for an Individual in the Unrestricted Area An assessment (see Table 14) was made of radiation doses to the likely most-exposed member of the public from River Bend and other nearby uranium fuel cycle sources (none within five miles). The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
Plant: River Bend Nuclear Station Year: 2018 Page 29 of 75 Annual Radioactive Effluent Release Report Table 14, EPA 40 CFR PART 190 Evaluation Total Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 2.15E+OO 2.28E+OO 6.36E+OO
% of Limit 8.60E+OO 3.04E+OO 2.54E+01 Liquid dose, gaseous dose including a bounding calculation of C-14 dose, direct shine, ISFSI and any other nuclear power related facility within 5 miles of the station are considered when calculating dose compliance with 40 CFR 190.
Plant: River Bend Nuclear Station Year: 2018 Page 30 of 75 Annual Radioactive Effluent Release Report 7.0 METEORLOGICAL DATA Cumulative joint frequency distributions and annual average data for continuous releases are listed below. The meteorological recovery for 2018 was 96.4%.
7.1 Joint Frequency Distributions All Stability Classes Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
102 46 63 101 117 201 76 0
0 0
NNE 66 46 73 118 140 116 6
0 0
0 NE 73 44 61 142 136 76 3
0 0
0 ENE 93 62 56 106 48 37 0
0 0
0 E
48 68 62 84 48 24 0
0 0
0 ESE 46 58 70 125 79 53 2
0 0
0 SE 50 63 110 220 202 188 39 2
0 0
SSE 14 47 63 168 157 274 143 5
0 0
s 14 25 56 119 122 166 80 0
0 0
SSW 10 19 43 87 56 73 25 0
0 0
SW 9
38 48 50 46 60 10 0
0 0
WSW 17 43 25 46 61 76 6
0 0
0 w
30 57 26 63 86 113 10 0
0 0
WNW 76 56 42 56 85 93 24 0
0 0
NW 99 71 36 58 72 115 76 1
0 0
NNW 107 58 34 73 82 129 68 0
0 0
Total 854 801 868 1616 1537 1794 568 8
0 0
Number of Calms: 398 Number of Invalid Hours: 316 Number of Valid Hours: 8444 Total Hours for the Period: 8760 Total 706 565 535 402 334 433 874 871 582 313 261 274 385 432 528 551 8046
Plant: River Bend Nuclear Station Year: 2018 Page 31 of 75 Annual Radioactive Effluent Release Report Stability Class A Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
0 5
7 59 27 0
0 0
98 NNE 0
0 0
3 31 44 4
0 0
0 82 NE 0
0 1
4 31 26 2
0 0
0 64 ENE 0
0 1
7 13 10 0
0 0
0 31 E
0 0
0 9
14 16 0
0 0
0 39 ESE 0
0 0
10 21 15 1
0 0
0 47 SE 0
0 1
4 42 55 8
0 0
0 110 SSE 0
1 0
3 14 56 48 0
0 0
122 s
0 0
0 5
5 45 36 0
0 0
91 SSW 0
0 0
2 6
13 12 0
0 0
33 SW 0
0 1
2 3
18 3
0 0
0 27 WSW 0
0 0
4 17 41 4
0 0
0 66 w
0 1
2 2
28 82 9
0 0
0 124 WNW 0
0 0
2 19 52 16 0
0 0
89 NW 0
0 0
4 13 25 27 0
0 0
69 NNW 0
0 0
4 8
23 29 0
0 0
64 Total 0
2 6
70 272 580 226 0
0 0
1156 Number of Calms: 0 Number of Valid Hours: 1156 Total Hours for the Period: 1156
Plant: River Bend Nuclear Station Year: 2018 Page 32 of 75 Annual Radioactive Effluent Release Report Stability Class B Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
0 1
8 10 5
0 0
0 24 NNE 0
0 0
2 6
3 0
0 0
0 11 NE 0
0 1
7 13 4
0 0
0 0
25 ENE 0
0 0
4 2
1 0
0 0
0 7
E 0
0 0
5 4
0 0
0 0
0 9
ESE 0
0 0
4 3
0 0
0 0
0 7
SE 0
0 0
2 16 8
2 0
0 0
28 SSE 0
0 0
3 8
34 12 1
0 0
58 s
0 0
1 3
7 24 15 0
0 0
50 SSW 0
0 1
2 6
14 6
0 0
0 29 SW 0
0 0
1 9
7 2
0 0
0 19 WSW 1
0 0
1 15 13 0
0 0
0 30 w
0 0
0 4
12 12 0
0 0
0 28 WNW 0
0 0
4 22 14 2
0 0
0 42 NW 0
0 0
1 10 6
9 0
0 0
26 NNW 0
0 0
4 5
5 11 0
0 0
25 Total 1
0 3
48 146 155 64 1
0 0
418 Number of Calms: 0 Number of Valid Hours: 418 Total Hours for the Period: 418
Plant: River Bend Nuclear Station Year: 2018 Page 33 of 75 Annual Radioactive Effluent Release Report Stability Class C Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 1
0 12 16 20 3
0 0
0 52 NNE 0
0 1
7 17 14 1
0 0
0 40 NE 0
0 0
8 10 3
1 0
0 0
22 ENE 0
0 1
8 7
0 0
0 0
0 16 E
0 0
3 11 4
0 0
0 0
0 18 ESE 0
1 1
7 4
4 0
0 0
0 17 SE 0
0 1
20 14 18 2
0 0
0 55 SSE 0
0 0
11 18 33 26 2
0 0
90 s
0 0
0 6
24 24 9
0 0
0 63 SSW 0
0 1
3 10 15 4
0 0
0 33 SW 0
0 1
7 18 14 4
0 0
0 44 WSW 0
0 1
10 15 13 0
0 0
0 39 w
0 0
0 11 22 15 0
0 0
0 48 WNW 0
0 0
13 18 9
2 0
0 0
42 NW 0
0 1
6 6
16 9
0 0
0 38 NNW 0
0 0
8 15 20 5
0 0
0 48 Total 0
2 11 148 218 218 66 2
0 0
665 Number of Calms: 2 Number of Valid Hours: 667 Total Hours for the Period: 667
Plant: River Bend Nuclear Station Year:2018 Page 34 of 75 Annual Radioactive Effluent Release Report Stability Class D Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 5
10 38 51 92 33 0
0 0
229 NNE 1
4 17 44 66 34 1
0 0
0 167 NE 3
5 13 44 55 24 0
0 0
0 144 ENE 2
7 8
27 5
12 0
0 0
0 61 E
1 3
14 26 13 6
0 0
0 0
63 ESE 1
4 14 33 22 15 0
0 0
0 89 SE 1
9 19 58 58 42 19 2
0 0
208 SSE 0
6 7
30 42 71 50 2
0 0
208 s
0 4
3 26 25 42 16 0
0 0
116 SSW 0
4 5
27 22 22 2
0 0
0 82 SW 0
2 11 17 10 16 1
0 0
0 57 WSW 0
4 3
13 8
8 2
0 0
0 38 w
0 5
8 31 20 3
1 0
0 0
68 WNW 1
0 18 24 20 7
2 0
0 0
72 NW 0
0 7
25 30 46 22 0
0 0
130 NNW 2
2 7
22 34 76 22 0
0 0
165 Total 12 64 164 485 481 516 171 4
0 0
1897 Number of Calms: 2 Number of Valid Hours: 1899 Total Hours for the Period: 1899
Plant: River Bend Nuclear Station Year: 2018 Page 35 of 75 Annual Radioactive Effluent Release Report Stability Class E Period of Record: 01/01/2018-12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
7 12 23 34 34 20 8
0 0
0 138 NNE 5
19 32 61 18 21 0
0 0
0 156 NE 7
18 35 68 27 19 0
0 0
0 174 ENE 12 19 29 49 19 14 0
0 0
0 142 E
9 21 24 29 13 2
0 0
0 0
98 ESE 20 31 42 59 29 19 1
0 0
0 201 SE 32 32 66 115 67 65 8
0 0
0 385 SSE 6
21 39 99 69 77 7
0 0
0 318 s
2 11 39 65 58 30 4
0 0
0 209 SSW 3
12 28 49 11 9
1 0
0 0
113 SW 6
23 26 20 5
5 0
0 0
0 85 WSW 3
21 19 16 6
1 0
0 0
0 66 w
7 19 10 13 4
1 0
0 0
0 54 WNW 10 12 11 13 5
10 2
0 0
0 63 NW 6
14 13 18 7
22 9
1 0
0 90 NNW 8
12 12 31 19 5
1 0
0 0
88 Total 143 297 448 739 391 320 41 1
0 0
2380 Number of Calms: 32 Number of Valid Hours: 2412 Total Hours for the Period: 2412
Plant: River Bend Nuclear Station Year:2018 Page 36 of 75 Annual Radioactive Effluent Release Report Stability Class F Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
18 11 23 8
0 0
0 0
0 0
60 NNE 19 16 22 1
2 0
0 0
0 0
60 NE 19 14 10 10 0
0 0
0 0
0 53 ENE 16 8
10 10 2
0 0
0 0
0 46 E
12 14 13 3
0 0
0 0
0 0
42 ESE 10 15 9
12 0
0 0
0 0
0 46 SE 13 16 22 20 5
0 0
0 0
0 76 SSE 6
14 15 22 5
3 0
0 0
0 65 s
10 10 9
13 2
1 0
0 0
0 45 SSW 5
2 7
4 1
0 0
0 0
0 19 SW 2
11 9
3 1
0 0
0 0
0 26 WSW 9
9 1
2 0
0 0
0 0
0 21 w
8 21 5
2 0
0 0
0 0
0 36 WNW 25 15 8
0 1
1 0
0 0
0 50 NW 32 25 13 3
5 0
0 0
0 0
78 NNW 18 15 7
4 0
0 0
0 0
0 44 Total 222 216 183 117 24 5
0 0
0 0
767 Number of Calms: 126 Number of Valid Hours: 893 Total Hours for the Period: 893
Plant: River Bend Nuclear Station Year: 2018 Page 37 of 75 Annual Radioactive Effluent Release Report Stability Class G Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 30 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
77 17 7
3 1
0 0
0 0
0 105 NNE 41 7
1 0
0 0
0 0
0 0
49 NE 44 7
1 1
0 0
0 0
0 0
53 ENE 63 28 7
1 0
0 0
0 0
0 99 E
26 30 8
1 0
0 0
0 0
0 65 ESE 15 7
4 0
0 0
0 0
0 0
26 SE 4
6 1
1 0
0 0
0 0
0 12 SSE 2
5 2
0 1
0 0
0 0
0 10 s
2 0
4 1
1 0
0 0
0 0
8 SSW 2
1 1
0 0
0 0
0 0
0 4
SW 1
2 0
0 0
0 0
0 0
0 3
WSW 4
9 1
0 0
0 0
0 0
0 14 w
15 11 1
0 0
0 0
0 0
0 27 WNW 40 29 5
0 0
0 0
0 0
0 74 NW 61 32 2
1 1
0 0
0 0
0 97 NNW 79 29 8
0 1
0 0
0 0
0 117 Total 476 220 53 9
5 0
0 0
0 0
763 Number of Calms: 236 Number of Valid Hours: 999 Total Hours for the Period: 999
Plant: River Bend Nuclear Station Year: 2018 Page 38 of 75 Annual Radioactive Effluent Release Report All Stability Classes Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 2
11 28 44 158 273 19 0
0 535 NNE 1
4 9
27 56 260 236 14 0
0 607 NE 0
5 8
31 89 203 241 9
1 0
587 ENE 1
3 11 40 90 151 156 26 0
0 478 E
4 4
11 49 65 110 148 13 1
0 405 ESE 2
6 8
32 64 241 536 119 12 0
1020 SE 1
2 9
34 73 233 302 43 10 0
707 SSE 1
5 5
38 68 197 248 62 2
0 626 s
1 4
10 34 90 214 201 37 2
0 593 SSW 2
2 10 38 64 190 173 22 0
0 501 SW 0
5 8
44 52 164 89 13 0
0 375 WSW 0
1 8
31 75 167 100 12 1
0 395 w
1 2
6 41 64 229 120 5
0 0
468 WNW 0
0 9
22 53 148 106 23 2
0 363 NW 1
8 7
22 60 100 160 26 2
0 386 NNW 0
1 3
27 30 141 178 22 0
0 402 Total 15 54 133 538 1037 2906 3267 465 33 0
8448 Number of Calms: 1 Number of Invalid Hours: 311 Number of Valid Hours: 8449 Total Hours for the Period: 8760
Plant: River Bend Nuclear Station I
Year:2018 Page 39 of 75 Annual Radioactive Effluent Release Report Stability Class A Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
0 0
2 16 54 3
0 0
75 NNE 0
0 0
0 5
38 36 5
0 0
84 NE 0
0 0
1 4
35 32 3
0 0
75 ENE 0
0 0
2 4
21 26 1
0 0
54 E
0 0
0 2
3 12 30 2
0 0
49 ESE 0
0 0
1 5
29 57 13 0
0 105 SE 0
0 0
0 4
25 40 4
0 0
73 SSE 0
0 1
1 3
17 48 21 0
0 91 s
0 0
1 1
4 14 35 13 0
0 68 SSW 0
0 0
1 3
9 14 9
0 0
36 SW 0
0 0
1 2
10 21 3
0 0
37 WSW 0
0 0
0 9
34 27 3
0 0
73 w
0 0
0 1
7 73 75 3
0 0
159 WNW 0
0 0
1 2
27 26 9
2 0
67 NW 0
0 0
1 4
10 38 8
0 0
61 NNW 0
0 0
1 4
11 32 1
0 0
49 Total 0
0 2
14 65 381 591 101 2
0 1156 Number of Calms: 0 Number of Valid Hours: 1156 Total Hours for the Period: 1156
Plant: River Bend Nuclear Station Year:2018 Page 40 of 75 Annual Radioactive Effluent Release Report Stability Class B Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
0 0
3 3
8 0
0 0
14 NNE 0
0 0
0 2
12 3
1 0
0 18 NE 0
0 0
2 3
19 4
0 0
0 28 ENE 0
0 0
1 2
6 2
0 0
0 11 E
0 0
0 0
4 2
1 0
0 0
7 ESE 0
0 0
0 2
8 12 2
0 0
24 SE 0
0 0
0 2
11 13 4
0 0
30 SSE 0
0 0
0 5
16 15 4
1 0
41 s
0 0
0 0
5 13 10 6
0 0
34 SSW 0
0 0
0 2
11 14 5
0 0
32 SW 0
0 0
1 4
11 10 1
0 0
27 WSW 0
0 0
1 5
22 5
1 0
0 34 w
0 0
0 2
4 36 9
0 0
0 51 WNW 0
0 0
0 1
15 7
1 0
0 24 NW 0
0 0
1 5
4 10 0
0 0
20 NNW 0
0 0
1 1
7 10 4
0 0
23 Total 0
0 0
9 50 196 133 29 1
0 418 Number of Calms: 0 Number of Valid Hours: 418 Total Hours for the Period: 418
Plant: River Bend Nuclear Station Year: 2018 I Page 41 of 75 Annual Radioactive Effluent Release Report Stability Class C Period of Record: 01/01/2018 -12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
1 6
3 13 21 1
0 0
45 NNE 0
0 0
2 4
19 18 1
0 0
44 NE 0
0 0
2 7
8 6
1 0
0 24 ENE 0
0 1
3 11 6
4 2
0 0
27 E
0 0
0 3
4 5
4 0
0 0
16 ESE 0
0 1
2 2
18 14 8
0 0
45 SE 0
0 1
3 8
21 22 6
0 0
61 SSE 0
0 0
2 2
15 23 10 1
0 53 s
0 0
0 1
7 20 15 3
1 0
47 SSW 0
0 1
5 10 11 19 3
0 0
49 SW 0
0 0
5 5
15 13 3
0 0
41 WSW 0
0 0
4 10 14 15 2
0 0
45 w
0 0
0 2
17 22 13 0
0 0
54 WNW 0
0 0
4 10 16 9
1 0
0 40 NW 0
0 0
3 4
6 23 2
0 0
38 NNW 0
0 1
3 4
17 14 0
0 0
39 Total 0
0 6
50 108 226 233 43 2
0 668 Number of Calms: 0 Number of Valid Hours: 668 Total Hours for the Period: 668
Plant: River Bend Nuclear Station Year:2018 Page 42 of 75 Annual Radioactive Effluent Release Report Stability Class D Period of Record: 01/01/2018-12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
4 6
16 48 117 9
0 0
200 NNE 0
1 1
9 20 63 92 4
0 0
190 NE 0
1 5
12 31 51 64 3
1 0
168 ENE 1
1 2
6 19 37 36 4
0 0
106 E
0 4
2 12 12 10 40 5
0 0
85 ESE 0
1 1
3 11 40 92 35 3
0 186 SE 0
0 2
8 9
35 50 16 9
0 129 SSE 0
1 0
7 7
19 50 22 0
0 106 s
0 1
5 6
15 30 41 11 1
0 110 SSW 1
0 2
6 7
30 41 3
0 0
90 SW 0
2 1
11 9
14 20 6
0 0
63 WSW 0
0 1
7 16 15 23 6
1 0
69 w
0 0
0 13 13 30 11 2
0 0
69 WNW 0
0 1
6 14 22 30 7
0 0
80 NW 0
1 2
6 16 19 49 9
1 0
103 NNW 0
0 1
5 5
42 76 16 0
0 145 Total 2
13 30 123 220 505 832 158 16 0
1899 Number of Calms: 0 Number of Valid Hours: 1899 Total Hours for the Period: 1899
Plant: River Bend Nuclear Station Year: 2018 Page 43 of 75 Annual Radioactive Effluent Release Report Stability Class E Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 1
4 4
8 33 51 6
0 0
107 NNE 0
2 0
8 12 69 72 3
0 0
166 NE 0
2 1
5 22 51 96 2
0 0
179 ENE 0
0 1
10 33 57 52 18 0
0 171 E
2 0
2 10 22 35 57 6
1 0
135 ESE 0
1 3
10 26 89 238 54 9
0 430 SE 0
2 1
8 28 79 118 12 1
0 249 SSE 0
2 0
6 15 66 93 5
0 0
187 s
0 1
1 6
21 71 84 4
0 0
188 SSW 1
1 3
12 18 81 74 2
0 0
192 SW 0
0 1
4 11 61 18 0
0 0
95 WSW 0
1 1
6 7
45 24 0
0 0
84 w
0 2
2 5
11 24 8
0 0
0 52 WNW 0
0 4
2 7
19 20 5
0 0
57 NW 0
3 1
5 7
9 21 7
1 0
54 NNW 0
1 1
10 6
24 23 1
0 0
66 Total 3
19 26 111 254 813 1049 125 12 0
2412 Number of Calms: 0 Number of Valid Hours: 2412 Total Hours for the Period: 2412
Plant: River Bend Nuclear Station Year: 2018 Page 44 of 75 Annual Radioactive Effluent Release Report Stability Class F Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 1
1 6
4 16 6
0 0
0 34 NNE 0
0 2
3 8
29 11 0
0 0
53 NE 0
1 1
3 9
23 25 0
0 0
62 ENE 0
1 2
8 12 12 18 1
0 0
54 E
1 0
4 11 15 17 12 0
0 0
60 ESE 0
1 1
6 12 30 81 7
0 0
138 SE 0
0 3
7 14 34 32 1
0 0
91 SSE 1
0 1
14 20 25 12 0
0 0
73 s
0 2
1 10 12 30 13 0
0 0
68 SSW 0
1 0
4 8
22 5
0 0
0 40 SW 0
2 5
13 11 15 6
0 0
0 52 WSW 0
0 1
4 16 14 4
0 0
0 39 w
1 0
1 3
5 16 3
0 0
0 29 WNW 0
0 2
4 3
12 6
0 0
0 27 NW 0
0 3
2 8
19 8
0 0
0 40 NNW 0
0 0
6 3
15 10 0
0 0
34 Total 3
9 28 104 160 329 252 9
0 0
894 Number of Calms: 0 Number of Valid Hours: 894 Total Hours for the Period: 894
Plant: River Bend Nuclear Station Year:2018 Page 45 of 75 Annual Radioactive Effluent Release Report
~ Stability Class G Period of Record: 01/01/2018 - 12/31/2018 Elevation: Primary Sensors - 150 Foot Wind Speed (meters/second)
Wind 0.22-0.51-0.76-1.1-1.6-2.1-3.1-5.1-7.1-
>10.0 Total Direction 0.50 0.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 N
0 0
1 6
8 29 16 0
0 0
60 NNE 1
1 6
5 5
30 4
0 0
0 52 NE 0
1 1
6 13 16 14 0
0 0
51 ENE 0
1 5
10 9
12 18 0
0 0
55 E
1 0
3 11 5
29 4
0 0
0 53 ESE 2
3 2
10 6
27 42 0
0 0
92 SE 1
0 2
8 8
28 27 0
0 0
74 SSE 0
2 3
8 16 39 7
0 0
0 75 s
1 0
2 10 26 36 3
0 0
0 78 SSW 0
0 4
10 16 26 6
0 0
0 62 SW 0
1 1
9 10 38 1
0 0
0 60 WSW 0
0 5
9 12 23 2
0 0
0 51 w
0 0
3 15 7
28 1
0 0
0 54 WNW 0
0 2
5 16 37 8
0 0
0 68 NW 1
4 1
4 16 33 11 0
0 0
70 NNW 0
0 0
1 7
25 13 0
0 0
46 Total 7
13 41 127 180 456 177 0
0 0
1001 Number of Calms: 1 Number of Valid Hours: 1002 Total Hours for the Period: 1002
Plant: River Bend Nuclear Station Year:2018 Annual Radioactive Effluent Release Report 7.2 Stability Class Table 15, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours (Percentage)
Extremely Unstable A
13.69 Moderately Stable 8
4.95 Slightly Unstable c
7.90 Neutral D
22.49 Slightly Stable E
28.56 Moderately Stable F
10.58 Extremely Stable G
11.83 Table 16, Atmospheric Dispersion and Deposition Rates for the Maximum Individual Dose Calculations Analysis Gamma air dose (3) and Beta Air Dose Maximum Receptor (4)
Resident Garden Meat animal Immersion Milk animal (5)
Other on-site Receptors Notes:
(1) All CHI/Q = 10-7 sec/m3 (2) All D/Q = 10-9 m-2 Location (meters) 994 m WNW (Containment) 994 mWNW 7,000 mWNW 115 m ENE 275 m N 2500 SW Ground Level Releases CHI/Q -
421.0 CHI/Q -
421.0 D/Q 50.3 CHI/Q -
3.58 D/Q 0.38 CHI/Q -
5977.0 D/Q 529.7 CHI/Q - 1644.0 D/Q
- 345.6 CHI/Q -
34.45 D/Q 3.35 (3) Maximum offsite location (property boundary) with highest CHI/Q (unoccupied).
(4) Maximum hypothetical occupied offsite location with highest CHI/Q and D/Q.
(5) No milk animal within 5 miles radius, hypothetical location in worst sector.
(6) Other onsite receptors Page46 of75 Mixed Mode Releases CHI/Q - 33.1 CHI/Q - 33.1 D/Q
- 18.0 CHI/Q -.870 D/Q
-.223 CHI/Q - 407.5 D/Q 46.9 CHI/Q - 169.1 D/Q
- 68.4 CHI/Q -
4.65 D/Q 1.40 (7) Revisions to X/Q and D/Q can be performed using NUREG/CR-2919, XOQDOQ, Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations
RBG-47951 Rev.2018 Page 47 of 75 Annual Radioactive Effluent Release Report Page 1 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-205 02/01/18 pCi/L
< 1.3E+OO
< 1.SE+OO
< 3.2E+OO
< 1.4E+OO
< 2.7E+OO
< 1.6E+OO
< 2.7E+OO
< 8.8E+OO
< 1.4E+OO
< 1.4E+OO
< 1.4E+01
< 4.6E+OO MW-104 02/06/18 pCi/L
< 2.2E+OO
< 2.6E+OO
< 6.0E+OO
< 2.1E+OO
< 4.7E+OO
< 2.SE+OO
< 4.SE+OO
< 1.3E+01
< 2.6E+OO
< 2.4E+OO
< 2.2E+01
< 7.4E+OO MW-104 02/06/18 pCi/L
< 2.0E+OO
< 2.3E+OO
< 5.0E+OO
< 2.3E+OO
< 3.8E+OO
< 2.6E+OO
< 3.9E+OO
< 1.1 E+01
< 2.3E+OO
< 2.0E+OO
< 2.1 E+01
< 5.8E+OO MW-106 02/06/18 pCi/L
< 2.3E+OO
< 2.7E+OO
< 6.7E+OO
< 2.6E+OO
< 5.6E+OO
< 2.8E+OO
< 5.3E+OO
< 1.5E+01
< 3.0E+OO
< 3.0E+OO
< 2.7E+01
< 8.SE+OO MW-110 02/06/18 pCi/L
< 2.7E+OO
< 2.9E+OO
< 7.7E+OO
< 3.0E+OO
< 6.4E+OO
< 3.0E+OO
< 4.4E+OO
< 1.1 E+01
< 2.8E+OO
< 3.0E+OO
< 2.2E+01
< 9.2E+OO MW-112 02/06/18 pCi/L
< 3.0E+OO
< 3.3E+OO
< 7.9E+OO
< 2.9E+OO
< 6.2E+OO
< 3.1 E+OO
< 6.0E+OO
< 1.2E+01
< 3.2E+OO
< 3.0E+OO
< 2.4E+01
< 8.8E+OO MW-114 02/06/18 pCi/L
< 3.1 E+OO
< 3.2E+OO
< 7.1E+OO
< 2.9E+OO
< 6.1E+OO
< 3.6E+OO
< 6.3E+OO
< 1.4E+01
< 3.2E+OO
< 3.2E+OO
< 2.7E+01
< 7.SE+OO MW-116 02/06/18 pCi/L
< 2.SE+OO
< 3.8E+OO
< 7.2E+OO
< 3.1E+OO
< 6.2E+OO
< 3.7E+OO
< 6.0E+OO
< 1.3E+01
< 3.1E+OO
< 3.6E+OO
< 2.5E+01
< 9.2E+OO MW-116 02/06/18 pCi/L
< 3.7E+OO
< 4.2E+OO
< 8.8E+OO
< 4.4E+OO
< 7.3E+OO
< 4.SE+OO
< 7.6E+OO
< 1.5E+01
< 3.9E+OO
< 3.8E+OO
< 3.0E+01
< 1.1 E+01 MW-118 02/06/18 pCi/L
< 3.4E+OO
< 3.7E+OO
< 7.8E+OO
< 2.9E+OO
< 5.8E+OO
< 3.7E+OO
< 6.0E+OO
< 1.3E+01
< 3.2E+OO
< 3.4E+OO
< 2.6E+01
< 7.0E+OO MW-124 02/06/18 pCi/L
< 2.8E+OO
< 3.3E+OO
< 6.4E+OO
< 3.3E+OO
< 5.9E+OO
< 3.3E+OO
< 4.7E+OO
< 1.1 E+01
< 3.3E+OO
< 3.1E+OO
< 2.5E+01
< 7.4E+OO MW-137 02/06/18 pCi/L
< 2.8E+OO
< 3.3E+OO
< 6.6E+OO
< 2.6E+OO
< 5.1E+OO
< 3.2E+OO
< 5.6E+OO
< 1.2E+01
< 2.7E+OO
< 2.6E+OO
< 2.5E+01
< 7.5E+OO MW-137 02/06/18 pCi/L
< 3.6E+OO
< 3.4E+OO
< 8.3E+OO
< 3.5E+OO
< 6.2E+OO
< 4.1E+OO
< 6.2E+OO
< 1.4E+01
< 3.7E+OO
< 3.4E+OO
< 2.8E+01
< 8.5E+OO MW-139 02/06/18 pCi/L
< 3.4E+OO
< 3.7E+OO
< 9.3E+OO
< 4.3E+OO
< 6.5E+OO
< 3.7E+OO
< 6.1E+OO
< 1.4E+01
< 4.1 E+OO
< 3.7E+OO
< 2.8E+01
< 1.3E+01 MW-141 02/06/18 pCi/L
< 2.8E+OO
< 3.0E+OO
< 5.8E+OO
< 2.2E+OO
< 5.0E+OO
< 3.2E+OO
< 4.5E+OO
< 1.2E+01
< 3.0E+OO
< 2.7E+OO
< 2.4E+01
< 7.1E+OO MW-153 02/06/18 pCi/L
< 3.4E+OO
< 4.5E+OO
< 9.3E+OO
< 3.6E+OO
< 5.7E+OO
< 4.4E+OO
< 7.6E+OO
< 1.5E+01
< 4.3E+OO
< 4.0E+OO
< 3.0E+01
< 8.1E+OO MW-161 02/06/18 pCi/L
< 2.5E+OO
< 2.9E+OO
< 6.5E+OO
< 3.1E+OO
< 4.8E+OO
< 3.3E+OO
< 5.9E+OO
< 1.2E+01
< 3.0E+OO
< 2.9E+OO
< 2.4E+01
< 7.2E+OO
RBG-47951 Rev.2018 Page 48 of 75 Annual Radioactive Effluent Release Report Page 2 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-178 02/06/18 pCi/L
< 3.6E+OO
< 3.7E+OO
< 9.4E+OO
< 3.4E+OO
< 7.6E+OO
< 3.4E+OO
< 7.1E+OO
< 1.5E+01
< 3.7E+OO
< 3.9E+OO
< 3.0E+01
< 9.6E+OO MW-179 02/06/18 pCi/L
< 2.6E+OO
< 3.0E+OO
< 6.7E+OO
< 2.7E+OO
< 6.0E+OO
< 3.1E+OO
< 5.3E+OO
< 1.1 E+01
< 2.9E+OO
< 2.7E+OO
< 2.3E+01
< 6.4E+OO MW-186 02/06/18 pCi/L
< 2.1E+OO
< 2.3E+OO
< 5.2E+OO
< 2.4E+OO
< 4.2E+OO
< 2.4E+OO
< 4.0E+OO
< 1.2E+01
< 2.2E+OO
< 2.1E+OO
< 2.1E+01
< 7.2E+OO MW-187 02/06/18 pCi/L
< 2.3E+OO
< 2.8E+OO
< 6.0E+OO
< 2.4E+OO
< 5.1E+OO
< 3.1E+OO
< 4.8E+OO
< 1.4E+01
< 2.7E+OO
< 2.5E+OO
< 2.6E+01
< 7.5E+OO MW-05 02/07/18 pCi/L
< 2.6E+OO
< 3.0E+OO
< 7.4E+OO
< 3.1 E+OO
< 5.8E+OO
< 3.0E+OO
< 5.2E+OO
< 1.4E+01
< 2.8E+OO
< 2.6E+OO
< 2.7E+01
< 9.4E+OO MW-06 02/07/18 pCi/L
< 3.1 E+OO
< 3.2E+OO
< 7.2E+OO
< 2.6E+OO
< 6.4E+OO
< 3.6E+OO
< 5.5E+OO
< 1.5E+01
< 2.8E+OO
< 3.1E+OO
< 2.8E+01
< 9.7E+OO MW-06 02/07/18 pCi/L
< 3.1E+OO
< 3.3E+OO
< 7.2E+OO
< 3.5E+OO
< 6.3E+OO
< 3.4E+OO
< 5.8E+OO
< 1.5E+01
< 3.3E+OO
< 3.2E+OO
< 2.8E+01
< 8.2E+OO MW-08 02/07/18 pCi/L
< 2.3E+OO
< 2.5E+OO
< 5.7E+OO
< 2.1E+OO
< 4.2E+OO
< 2.6E+OO
< 4.4E+OO
< 1.3E+01
< 2.5E+OO
< 2.2E+OO
< 2.1 E+01
< 6.8E+OO MW-103 02/07/18 pCi/L
< 3.9E+OO
< 4.6E+OO
< 8.9E+OO
< 3.7E+OO
< 7.0E+OO
< 4.0E+OO
< 8.3E+OO
< 1.4E+01
< 4.3E+OO
< 4.2E+OO
< 3.2E+01
< 8.3E+OO MW-107 02/07/18 pCi/L
< 2.4E+OO
< 2.6E+OO
< 5.5E+OO
< 2.1 E+OO
< 4.2E+OO
< 2.5E+OO
< 4.2E+OO
< 1.2E+01
< 2.4E+OO
< 2.4E+OO
< 2.2E+01
< 7.3E+OO MW-108 02/07/18 pCi/L
< 2.1E+OO
< 2.2E+OO
< 6.0E+OO
< 2.1 E+OO
< 4.3E+OO
< 2.8E+OO
< 4.3E+OO
< 1.4E+01
< 2.4E+OO
< 2.1E+OO
< 2.3E+01
< 7.4E+OO MW-111 02/07/18 pCi/L
< 2.4E+OO
< 2.6E+OO
< 6.1 E+OO
< 2.7E+OO
< 4.7E+OO
< 2.6E+OO
< 4.8E+OO
< 1.2E+01
< 2.4E+OO
< 2.3E+OO
< 2.1E+01
< 6.7E+OO MW-120 02/07/18 pCi/L
< 2.2E+OO
< 2.3E+OO
< 6.3E+OO
< 2.6E+OO
< 4.7E+OO
< 2.6E+OO
< 4.2E+OO
< 1.3E+01
< 2.6E+OO
< 2.4E+OO
< 2.3E+01
< 8.9E+OO MW-120 02/07/18 pCi/L
< 2.5E+OO
< 2.8E+OO
< 6.4E+OO
< 2.3E+OO
< 5.3E+OO
< 3.2E+OO
< 5.6E+OO
< 1.5E+01
< 2.8E+OO
< 2.9E+OO
< 2.7E+01
< 8.2E+OO MW-122R 02/07/18 pCi/L
< 2.2E+OO
< 2.4E+OO
< 5.0E+OO
< 2.7E+OO
< 4.6E+OO
< 2.5E+OO
< 4.6E+OO
< 1.2E+01
< 2.4E+OO
< 2.3E+OO
< 2.2E+01
< 7.2E+OO MW-125 02/07/18 pCi/L
< 4.1E+OO
< 4.6E+OO
< 9.6E+OO
< 4.2E+OO
< 7.1E+OO
< 4.6E+OO
< 8.2E+OO
< 1.5E+01
< 5.4E+OO
< 4.5E+OO
< 3.5E+01
< 8.9E+OO MW-14 02/07/18 pCi/L
< 1.9E+OO
< 2.1 E+OO
< 5.2E+OO
< 2.3E+OO
< 4.1E+OO
< 2.4E+OO
< 4.1E+OO
< 1.2E+01
< 2.2E+OO
< 2.1E+OO
< 1.9E+01
< 7.8E+OO
RBG-47951 Rev.2018 Page 49 of 75 Annual Radioactive Effluent Release Report Page 3 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-151 02/07/18 pCi/L
< 2.3E+OO
< 2.5E+OO
< 5.2E+OO
< 2.2E+OO
< 4.6E+OO
< 2.7E+OO
< 4.1E+OO
< 1.4E+01
< 2.4E+OO
< 2.0E+OO
< 2.5E+01
< 7.8E+OO MW-155 02/07/18 pCi/L
< 4.2E+OO
< 4.0E+OO
< 9.5E+OO
< 4.8E+OO
< 7.1E+OO
< 4.7E+OO
< 8.4E+OO
< 1.4E+01
< 4.3E+OO
< 4.6E+OO
< 3.2E+01
< 8.2E+OO MW-155 02/07/18 pCi/L
< 3.3E+OO
< 4.0E+OO
< 8.4E+OO
< 3.9E+OO
< 6.9E+OO
< 3.6E+OO
< 6.5E+OO
< 1.3E+01
< 3.5E+OO
< 3.8E+OO
< 2.5E+01
< 8.0E+OO MW-156 02/07/18 pCi/L
< 4.3E+OO
< 3.9E+OO
< 1.0E+01
< 3.8E+OO
< 8.5E+OO
< 4.6E+OO
< 7.2E+OO
< 1.5E+01
< 4.4E+OO
< 4.5E+OO
< 2.5E+01
< 9.1E+OO MW-157 02/07/18 pCi/L
< 3.8E+OO
< 4.1 E+OO
< 8.6E+OO
< 4.2E+OO
< 7.3E+OO
< 4.5E+OO
< 8.2E+OO
< 1.5E+01
< 4.3E+OO
< 4.0E+OO
< 3.1 E+01
< 9.7E+OO MW-165 02/07/18 pCi/L
< 2.6E+OO
< 2.8E+OO
< 7.4E+OO
< 3.1E+OO
< 6.9E+OO
< 3.2E+OO
< 6.0E+OO
< 1.3E+01
< 2.7E+OO
< 2.8E+OO
< 2.5E+01
< 8.9E+OO MW-170 02/07/18 pCi/L
< 2.9E+OO
< 3.2E+OO
< 7.1E+OO
< 3.0E+OO
< 5.1E+OO
< 3.4E+OO
< 5.4E+OO
< 1.5E+01
< 3.0E+OO
< 2.8E+OO
< 2.6E+01
< 1.0E+01 MW-180 02/07/18 pCi/L
< 2.3E+OO
< 2.6E+OO
< 6.0E+OO
< 2.1 E+OO
< 4.8E+OO
< 2.7E+OO
< 4.5E+OO
< 1.5E+01
< 2.5E+OO
< 2.4E+OO
< 2.4E+01
< 6.7E+OO MW-207 02/07/18 pCi/L
< 3.5E+OO
< 3.9E+OO
< 9.7E+OO
< 4.4E+OO
< 7.4E+OO
< 4.4E+OO
< 7.5E+OO
< 1.4E+01
< 4.5E+OO
< 3.2E+OO
< 2.4E+01
< 1.0E+01 MW-209 02/07/18 pCi/L
< 2.8E+OO
< 2.9E+OO
< 6.4E+OO
< 2.7E+OO
< 6.0E+OO
< 3.0E+OO
< 5.3E+OO
< 1.2E+01
< 3.0E+OO
< 3.0E+OO
< 2.4E+01
< 6.3E+OO MW-211 02/07/18 pCi/L
< 3.6E+OO
< 4.2E+OO
< 9.1E+OO
< 3.5E+OO
< 7.1E+OO
< 4.2E+OO
< 7.1E+OO
< 1.3E+01
< 4.4E+OO
< 4.1E+OO
< 2.7E+01
< 9.1E+OO MW-213 02/07/18 pCi/L
< 4.1 E+OO
< 3.3E+OO
< 8.2E+OO
< 4.8E+OO
< 6.8E+OO
< 4.3E+OO
< 8.0E+OO
< 1.5E+01
< 4.4E+OO
< 4.1E+OO
< 3.2E+01
< 9.6E+OO MW-217 02/07/18 pCi/L
< 3.4E+OO
< 3.8E+OO
< 8.9E+OO
< 3.7E+OO
< 7.3E+OO
< 4.3E+OO
< 7.1E+OO
< 1.4E+01
< 4.0E+OO
< 4.0E+OO
< 2.9E+01
< 7.8E+OO PZ-01 02/07/18 pCi/L
< 3.2E+OO
< 4.2E+OO
< 9.3E+OO
< 3.9E+OO
< 7.5E+OO
< 4.0E+OO
< 7.6E+OO
< 1.4E+01
< 3.8E+OO
< 3.5E+OO
< 2.6E+01
< 7.6E+OO SW-101 02/07/18 pCi/L
< 2.4E+OO
< 2.5E+OO
< 6.1E+OO
< 2.4E+OO
< 4.3E+OO
< 2.7E+OO
< 4.6E+OO
< 1.4E+01
< 2.4E+OO
< 2.2E+OO
< 2.4E+01
< 7.7E+OO MW-100 02/08/18 pCi/L
< 2.8E+OO
< 3.3E+OO
< 7.4E+OO
< 2.8E+OO
< 6.5E+OO
< 3.6E+OO
< 6.0E+OO
< 1.3E+01
< 3.3E+OO
< 3.1E+OO
< 2.7E+01
< 8.8E+OO MW-126 02/08/18 pCi/L
< 2.2E+OO
< 2.6E+OO
< 6.0E+OO
< 2.3E+OO
< 5.0E+OO
< 2.7E+OO
< 4.9E+OO
< 1.3E+01
< 2.6E+OO
< 2.4E+OO
< 2.2E+01
< 7.5E+OO
RBG-47951 l
Rev.2018 Page 50 of 75 Annual Radioactive Effluent Release Report Page 4 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-128 02/08/18 pCi/L
< 2.SE+OO
< 2.8E+OO
< 6.6E+OO
< 2.6E+OO
< 5.4E+OO
< 3.1E+OO
< 5.2E+OO
< 1.3E+01
< 2.7E+OO
< 2.SE+OO
< 2.4E+01
< 8.7E+OO MW-128 02/08/18 pCi/L
< 2.2E+OO
< 2.SE+OO
< 5.9E+OO
< 2.SE+OO
< 4.9E+OO
< 2.7E+OO
< 4.7E+OO
< 1.3E+01
< 2.7E+OO
< 2.SE+OO
< 2.4E+01
< 7.1E+OO MW-130 02/08/18 pCi/L
< 2.SE+OO
< 2.8E+OO
< 6.4E+OO
< 3.1 E+OO
< 5.4E+OO
< 3.2E+OO
< 5.3E+OO
< 1.5E+01
< 2.7E+OO
< 3.0E+OO
< 2.5E+01
< 8.0E+OO MW-130 02/08/18 pCi/L
< 2.3E+OO
< 2.9E+OO
< 6.4E+OO
< 2.6E+OO
< 4.SE+OO
< 2.9E+OO
< 4.9E+OO
< 1.5E+01
< 2.SE+OO
< 2.4E+OO
< 2.6E+01
< 8.0E+OO MW-131 02/08/18 pCi/L
< 2.4E+OO
< 2.8E+OO
< 6.2E+OO
< 2.4E+OO
< 5.3E+OO
< 3.0E+OO
< 4.6E+OO
< 1.3E+01
< 2.7E+OO
< 2.SE+OO
< 2.4E+01
< 7.7E+OO MW-132 02/08/18 pCi/L
< 2.0E+OO
< 2.1E+OO
< 4.7E+OO
< 1.8E+OO
< 3.7E+OO
< 2.3E+OO
< 3.9E+OO
< 1.1 E+01
< 2.1E+OO
< 2.1E+OO
< 1.9E+01
< 6.0E+OO MW-134 02/08/18 pCi/L
< 3.0E+OO
< 3.4E+OO
< 7.2E+OO
< 3.4E+OO
< 6.2E+OO
< 3.SE+OO
< 6.0E+OO
< 1.4E+01
< 3.SE+OO
< 3.4E+OO
< 2.5E+01
< 9.3E+OO MW-142 02/08/18 pCi/L
< 3.0E+OO
< 3.1E+OO
< 7.0E+OO
< 2.SE+OO
< 6.0E+OO
< 3.0E+OO
< 6.0E+OO
< 1.2E+01
< 3.1E+OO
< 3.1E+OO
< 2.5E+01
< 7.7E+OO MW-144 02/08/18 pCi/L
< 3.1E+OO
< 3.SE+OO
< 7.9E+OO
< 3.SE+OO
< 6.6E+OO
< 3.3E+OO
< 6.1E+OO
< 9.6E+OO
< 3.SE+OO
< 3.0E+OO
< 2.3E+01
< 7.8E+OO MW-146 02/08/18 pCi/L
< 2.9E+OO
< 2.8E+OO
< 6.0E+OO
< 2.9E+OO
< 6.4E+OO
< 3.4E+OO
< 5.7E+OO
< 9.9E+OO
< 3.1E+OO
< 3.1E+OO
< 2.1 E+01
< 7.3E+OO MW-147 02/08/18 pCi/L
< 4.4E+OO
< 5.1E+OO
< 1.0E+01
< 5.SE+OO
< 8.SE+OO
< 5.2E+OO
< 7.6E+OO
< 1.5E+01
< 4.7E+OO
< 4.2E+OO
< 3.1 E+01
< 1.0E+01 MW-148 02/08/18 pCi/L
< 2.9E+OO
< 2.9E+OO
< 7.4E+OO
< 3.2E+OO
< 5.8E+OO
< 3.3E+OO
< 5.2E+OO
< 1.4E+01
< 2.8E+OO
< 3.2E+OO
< 2.5E+01
< 8.6E+OO MW-158 02/08/18 pCi/L
< 2.9E+OO
< 2.9E+OO
< 6.3E+OO
< 2.SE+OO
< 6.0E+OO
< 3.4E+OO
< 5.4E+OO
< 1.0E+01
< 3.2E+OO
< 3.3E+OO
< 2.1 E+01
< 5.8E+OO MW-159 02/08/18 pCi/L
< 4.0E+OO
< 5.1E+OO
< 1.0E+01
< 5.2E+OO
< 8.0E+OO
< 5.1E+OO
< 9.3E+OO
< 1.5E+01
< 5.0E+OO
< 4.7E+OO
< 3.4E+01
< 1.2E+01 MW-162 02/08/18 pCi/L
< 2.7E+OO
< 3.6E+OO
< 7.3E+OO
< 3.0E+OO
< 6.2E+OO
< 3.3E+OO
< 6.4E+OO
< 1.5E+01
< 3.3E+OO
< 3.0E+OO
< 2.9E+01
< 1.0E+01 MW-164 02/08/18 pCi/L
< 2.4E+OO
< 2.SE+OO
< 6.6E+OO
< 3.1E+OO
< 5.4E+OO
< 2.7E+OO
< 4.SE+OO
< 1.1 E+01
< 2.9E+OO
< 2.SE+OO
< 2.2E+01
< 7.6E+OO MW-167 02/08/18 pCi/L
< 2.6E+OO
< 2.8E+OO
< 6.4E+OO
< 2.6E+OO
< 5.3E+OO
< 2.9E+OO
< 5.1E+OO
< 1.2E+01
< 2.9E+OO
< 2.6E+OO
< 2.4E+01
< 8.2E+OO
RBG-47951 I
Rev.2018 Page 51 of 75 Annual Radioactive Effluent Release Report Page 5 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-169 02/08/18 pCi/L
< 3.6E+OO
< 5.2E+OO
< 1.2E+01
< 5.3E+OO
< 8.6E+OO
< 5.0E+OO
< 6.9E+OO
< 1.5E+01
< 5.2E+OO
< 4.9E+OO
< 3.0E+01
< 1.1 E+01 MW-172 02/08/18 pCi/L
< 2.SE+OO
< 2.9E+OO
< 6.3E+OO
< 2.7E+OO
< 4.7E+OO
< 2.9E+OO
< 5.0E+OO
< 1.2E+01
< 2.9E+OO
< 2.7E+OO
< 2.3E+01
< 6.8E+OO MW-174 02/08/18 pCi/L
< 3.0E+OO
< 3.0E+OO
< 6.9E+OO
< 2.6E+OO
< 5.9E+OO
< 3.4E+OO
< 5.2E+OO
< 1.4E+01
< 3.0E+OO
< 3.0E+OO
< 2.4E+01
< 8.2E+OO MW-182 02/08/18 pCi/L
< 2.7E+OO
< 3.0E+OO
< 7.6E+OO
< 3.0E+OO
< 5.6E+OO
< 3.0E+OO
< 5.7E+OO
< 1.5E+01
< 2.8E+OO
< 2.9E+OO
< 2.6E+01
< 9.2E+OO MW-185 02/08/18 pCi/L
< 3.4E+OO
< 3.4E+OO
< 8.3E+OO
< 4.1 E+OO
< 6.6E+OO
< 4.1 E+OO
< 6.0E+OO
< 1.4E+01
< 3.0E+OO
< 3.4E+OO
< 2.8E+01
< 9.4E+OO MW-188 02/08/18 pCi/L
< 2.9E+OO
< 3.2E+OO
< 5.9E+OO
< 2.9E+OO
< 6.1E+OO
< 3.4E+OO
< 5.7E+OO
< 1.4E+01
< 3.3E+OO
< 3.2E+OO
< 2.6E+01
< 7.7E+OO MW-205 02/08/18 pCi/L
< 3.3E+OO
< 3.6E+OO
< 7.3E+OO
< 3.SE+OO
< 6.9E+OO
< 3.9E+OO
< 6.1E+OO
< 1.1 E+01
< 4.2E+OO
< 4.0E+OO
< 2.5E+01
< 7.7E+OO MW-215 02/08/18 pCi/L
< 3.9E+OO
< 4.0E+OO
< 8.1E+OO
< 3.6E+OO
< 8.0E+OO
< 4.2E+OO
< 7.3E+OO
< 1.4E+01
< 3.8E+OO
< 4.0E+OO
< 2.8E+01
< 7.3E+OO MW-219 02/08/18 pCi/L
< 3.1E+OO
< 3.6E+OO
< 7.5E+OO
< 3.3E+OO
< 6.8E+OO
< 3.6E+OO
< 6.SE+OO
< 1.2E+01
< 3.4E+OO
< 3.4E+OO
< 2.6E+01
< 7.8E+OO PZ-03 02/08/18 pCi/L
< 2.8E+OO
< 3.4E+OO
< 7.1E+OO
< 3.2E+OO
< 6.2E+OO
< 3.SE+OO
< 6.4E+OO
< 1.5E+01
< 3.2E+OO
< 3.0E+OO
< 2.9E+01
< 8.0E+OO SW-102 02/08/18 pCi/L
< 2.4E+OO
< 2.8E+OO
< 5.9E+OO
< 2.4E+OO
< 5.4E+OO
< 3.0E+OO
< 5.1E+OO
< 1.4E+01
< 2.7E+OO
< 2.7E+OO
< 2.5E+01
< 6.9E+OO SW-103 02/08/18 pCi/L
< 2.2E+OO
< 2.6E+OO
< 6.9E+OO
< 2.6E+OO
< 5.0E+OO
< 2.9E+OO
< 4.8E+OO
< 1.4E+01
< 2.6E+OO
< 2.6E+OO
< 2.4E+01
< 9.0E+OO SW-104 02/08/18 pCi/L
< 2.4E+OO
< 2.3E+OO
< 5.8E+OO
< 2.3E+OO
< 4.4E+OO
< 2.7E+OO
< 4.6E+OO
< 1.3E+01
< 2.7E+OO
< 2.4E+OO
< 2.2E+01
< 7.3E+OO MW-201 02/20/18 pCi/L
< 6.3E+OO
< 6.7E+OO
< 1.5E+01
< 7.1E+OO
< 1.3E+01
< 7.6E+OO
< 1.2E+01
< 1.2E+01
< 7.7E+OO
< 7.6E+OO
< 2.9E+01
< 7.7E+OO MW-203 02/20/18 pCi/L
< 6.4E+OO
< 6.7E+OO
< 1.4E+01
< 5.9E+OO
< 1.7E+01
< 7.3E+OO
< 1.1E+01
< 1.2E+01
< 8.1E+OO
< 7.2E+OO
< 3.4E+01
< 9.6E+OO MW-221 02/21/18 pCi/L
< 6.9E+OO
< 7.0E+OO
< 8.2E+OO
< 7.9E+OO
< 1.3E+01
< 7.8E+OO
< 1.1 E+01
< 1.0E+01
< 7.1E+OO
< 6.9E+OO
< 3.3E+01
< 9.SE+OO MW-223 02/22/18 pCi/L
< 3.8E+OO
< 3.2E+OO
< 8.1E+OO
< 4.9E+OO
< 7.7E+OO
< 4.9E+OO
< 6.1E+OO
< 1.1 E+01
< 3.7E+OO
< 3.3E+OO
< 2.2E+01
< 7.9E+OO
RBG-47951 Rev.2018 Page 52 of 75 Annual Radioactive Effluent Release Report Page 6 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-225 04/11/18 pCi/L
< 4.5E+OO
< 4.7E+OO
< 8.4E+OO
< 2.5E+OO
< 9.1 E+OO
< 4.7E+OO
< 8.9E+OO
< 1.3E+01
< 4.7E+OO
< 4.7E+OO
< 2.6E+01
< 9.4E+OO MW-227 04/11/18 pCi/L
< 4.5E+OO
< 5.6E+OO
< 1.1 E+01
< 5.9E+OO
< 1.1 E+01
< 5.5E+OO
< 9.4E+OO
< 1.4E+01
< 5.3E+OO
< 4.9E+OO
< 3.1 E+01
< 1.1 E+01 MW-229 04/11/18 pCi/L
< 4.8E+OO
< 5.0E+OO
< 1.1 E+01
< 5.1E+OO
< 9.0E+OO
< 5.5E+OO
< 7.4E+OO
< 1.1E+01
< 4.3E+OO
< 3.8E+OO
< 3.0E+01
< 1.1 E+01 MW-233 04/11/18 pCi/L
< 5.1E+OO
< 4.0E+OO
< 1.1 E+01
< 5.7E+OO
< 8.4E+OO
< 5.6E+OO
< 8.4E+OO
< 1.4E+01
< 4.4E+OO
< 5.6E+OO
< 2.9E+01
< 1.0E+01 MW-235 04/11/18 pCi/L
< 5.2E+OO
< 5.6E+OO
< 1.1 E+01
< 4.7E+OO
< 1.1 E+01
< 6.3E+OO
< 8.8E+OO
< 1.4E+01
< 6.0E+OO
< 5.2E+OO
< 3.4E+01
< 1.3E+01 MW-231 05/01/18 pCi/L
< 6.2E+OO
< 6.1E+OO
< 1.2E+01
< 7.1E+OO
< 1.3E+01
< 5.9E+OO
< 1.2E+01
< 1.1E+01
< 6.6E+OO
< 6.6E+OO
< 3.4E+01
< 1.1 E+01 MW-155 05/10/18 pCi/L
< 1.2E+OO
< 1.3E+OO
< 3.0E+OO
< 1.1 E+OO
< 2.2E+OO
< 1.4E+OO
< 2.4E+OO
< 8.2E+OO
< 1.3E+OO
< 1.2E+OO
< 1.3E+01
< 4.2E+OO MW-155 05/10/18 pCi/L
< 1.3E+OO
< 1.5E+OO
< 3.6E+OO
< 1.5E+OO
< 2.9E+OO
< 1.6E+OO
< 2.8E+OO
< 8.1E+OO
< 1.5E+OO
< 1.3E+OO
< 1.4E+01
< 5.4E+OO MW-169 05/10/18 pCi/L
< 1.5E+OO
< 1.7E+OO
< 3.9E+OO
< 1.3E+OO
< 3.0E+OO
< 1.8E+OO
< 3.1E+OO
< 9.8E+OO
< 1.6E+OO
< 1.5E+OO
< 1.8E+01
< 5.5E+OO MW-211 05/10/18 pCi/L
< 1.4E+OO
< 1.5E+OO
< 3.6E+OO
< 1.4E+OO
< 2.9E+OO
< 1.6E+OO
< 2.7E+OO
< 8.8E+OO
< 1.5E+OO
< 1.4E+OO
< 1.5E+01
< 4.6E+OO MW-215 05/10/18 pCi/L
< 1.6E+OO
< 1.8E+OO
< 4.3E+OO
< 1.7E+OO
< 3.2E+OO
< 2.0E+OO
< 3.3E+OO
< 1.1 E+01
< 1.8E+OO
< 1.7E+OO
< 1.7E+01
< 6.1E+OO MW-229 05/10/18 pCi/L
< 1.3E+OO
< 1.5E+OO
< 3.8E+OO
< 1.6E+OO
< 2.8E+OO
< 1.7E+OO
< 2.7E+OO
< 9.2E+OO
< 1.5E+OO
< 1.4E+OO
< 1.5E+01
< 5.2E+OO MW-142 05/15/18 pCi/L
< 3.2E+OO
< 3.5E+OO
< 8.0E+OO
< 3.2E+OO
< 6.4E+OO
< 3.7E+OO
< 6.3E+OO
< 1.3E+01
< 3.4E+OO
< 3.5E+OO
< 2.6E+01
< 7.8E+OO MW-144 05/15/18 pCi/L
< 1.8E+OO
< 2.0E+OO
< 4.8E+OO
< 2.0E+OO
< 3.8E+OO
< 2.1 E+OO
< 3.7E+OO
< 1.1 E+01
< 1.9E+OO
< 1.8E+OO
< 2.0E+01
< 7.5E+OO MW-146 05/15/18 pCi/L
< 1.8E+OO
< 2.1E+OO
< 5.1E+OO
< 2.1 E+OO
< 3.9E+OO
< 2.2E+OO
< 3.9E+OO
< 1.2E+01
< 2.0E+OO
< 1.9E+OO
< 2.0E+01
< 7.3E+OO MW-147 05/15/18 pCi/L
< 1.6E+OO
< 1.9E+OO
< 4.2E+OO
< 1.6E+OO
< 3.4E+OO
< 1.9E+OO
< 3.2E+OO
< 1.0E+01
< 1.9E+OO
< 1.7E+OO
< 1.8E+01
< 6.1E+OO MW-148 05/15/18 pCi/L
< 3.5E+OO
< 3.3E+OO
< 8.4E+OO
< 3.6E+OO
< 6.9E+OO
< 3.5E+OO
< 6.6E+OO
< 1.5E+01
< 3.7E+OO
< 3.7E+OO
< 2.9E+01
< 9.0E+OO
RBG-47951 Rev.2018 Page 53 of 75 Annual Radioactive Effluent Release Report Page 7 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-151 05/15/18 pCi/L
< 3.0E+OO
< 3.4E+OO
< 8.0E+OO
< 3.4E+OO
< 5.9E+OO
< 3.3E+OO
< 5.9E+OO
< 1.3E+01
< 3.0E+OO
< 3.0E+OO
< 2.4E+01
< 8.9E+OO MW-158 05/15/18 pCi/L
< 2.0E+OO
< 2.2E+OO
< 5.1E+OO
< 2.0E+OO
< 4.2E+OO
< 2.5E+OO
< 4.0E+OO
< 1.4E+01
< 2.2E+OO
< 2.1E+OO
< 2.4E+01
< 7.7E+OO MW-159 05/15/18 pCi/L
< 2.0E+OO
< 2.3E+OO
< 5.2E+OO
< 2.2E+OO
< 4.4E+OO
< 2.3E+OO
< 4.3E+OO
< 1.3E+01
< 2.2E+OO
< 2.1E+OO
< 2.2E+01
< 7.6E+OO MW-159 05/15/18 pCi/L
< 1.7E+OO
< 1.8E+OO
< 4.5E+OO
< 1.6E+OO
< 3.6E+OO
< 1.9E+OO
< 3.2E+OO
< 1.2E+01
< 1.9E+OO
< 1.7E+OO
< 2.1 E+01
< 6.1E+OO MW-162 05/15/18 pCi/L
< 4.2E+OO
< 4.7E+OO
< 9.7E+OO
< 4.5E+OO
< 9.2E+OO
< 4.4E+OO
< 8.6E+OO
< 1.4E+01
< 4.7E+OO
< 4.0E+OO
< 3.0E+01
< 1.2E+01 MW-164 05/15/18 pCi/L
< 3.8E+OO
< 4.5E+OO
< 1.1 E+01
< 4.7E+OO
< 7.2E+OO
< 4.4E+OO
< 7.3E+OO
< 1.4E+01
< 4.3E+OO
< 4.0E+OO
< 3.0E+01
< 1.1 E+01 MW-165 05/15/18 pCi/L
< 3.4E+OO
< 3.5E+OO
< 8.8E+OO
< 4.1E+OO
< 7.7E+OO
< 3.8E+OO
< 7.7E+OO
< 1.3E+01
< 4.1E+OO
< 4.2E+OO
< 2.9E+01
< 9.6E+OO MW-178 05/15/18 pCi/L
< 2.1 E+OO
< 2.8E+OO
< 6.6E+OO
< 2.7E+OO
< 4.9E+OO
< 2.7E+OO
< 4.9E+OO
< 1.3E+01
< 2.6E+OO
< 2.6E+OO
< 2.5E+01
< 8.7E+OO MW-179 05/15/18 pCi/L
< 1.5E+OO
< 1.7E+OO
< 3.9E+OO
< 1.6E+OO
< 3.2E+OO
< 1.9E+OO
< 3.3E+OO
< 7.8E+OO
< 1.7E+OO
< 1.7E+OO
< 1.5E+01
< 5.0E+OO MW-186 05/15/18 pCi/L
< 3.8E+OO
< 4.1E+OO
< 1.0E+01
< 3.9E+OO
< 9.2E+OO
< 3.8E+OO
< 8.6E+OO
< 1.4E+01
< 4.4E+OO
< 4.0E+OO
< 2.8E+01
< 1.2E+01 MW-187 05/15/18 pCi/L
< 3.6E+OO
< 4.5E+OO
< 8.9E+OO
< 4.1E+OO
< 8.3E+OO
< 5.0E+OO
< 6.7E+OO
< 1.4E+01
< 4.6E+OO
< 4.5E+OO
< 3.4E+01
< 9.0E+OO MW-201 05/15/18 pCi/L
< 2.3E+OO
< 2.8E+OO
< 6.4E+OO
< 2.6E+OO
< 4.9E+OO
< 3.0E+OO
< 4.8E+OO
< 1.4E+01
< 2.3E+OO
< 2.3E+OO
< 2.4E+01
< 8.9E+OO MW-203 05/15/18 pCi/L
< 1.4E+OO
< 1.5E+OO
< 3.7E+OO
< 1.5E+OO
< 2.7E+OO
< 1.5E+OO
< 2.7E+OO
< 5.9E+OO
< 1.5E+OO
< 1.4E+OO
< 1.3E+01
< 4.3E+OO MW-110 05/16/18 pCi/L
< 2.7E+OO
< 3.2E+OO
< 7.2E+OO
< 2.8E+OO
< 5.9E+OO
< 2.8E+OO
< 5.1E+OO
< 1.4E+01
< 2.9E+OO
< 2.9E+OO
< 2.6E+01
< 8.8E+OO MW-112 05/16/18 pCi/L
< 2.5E+OO
< 2.7E+OO
< 5.4E+OO
< 2.4E+OO
< 5.3E+OO
< 2.9E+OO
< 4.8E+OO
< 1.5E+01
< 2.6E+OO
< 2.4E+OO
< 2.4E+01
< 7.4E+OO MW-112 05/16/18 pCi/L
< 2.2E+OO
< 2.4E+OO
< 6.2E+OO
< 2.4E+OO
< 4.6E+OO
< 2.6E+OO
< 4.8E+OO
< 1.5E+01
< 2.6E+OO
< 2.1E+OO
< 2.6E+01
< 8.4E+OO MW-114 05/16/18 pCi/L
< 1.9E+OO
< 2.1E+OO
< 5.0E+OO
< 2.0E+OO
< 3.6E+OO
< 2.2E+OO
< 3.9E+OO
< 1.3E+01
< 2.0E+OO
< 2.0E+OO
< 2.3E+01
< 7.7E+OO
RBG-47951 Rev.2018 Page 54 of 75 Annual Radioactive Effluent Release Report Page 8 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-116 05/16/18 pCi/L
< 1.7E+OO
< 1.8E+OO
< 4.1E+OO
< 1.8E+OO
< 3.3E+OO
< 1.9E+OO
< 3.3E+OO
< 8.2E+OO
< 1.8E+OO
< 1.7E+OO
< 1.6E+01
< 4.9E+OO MW-124 05/16/18 pCi/L
< 2.3E+OO
< 2.7E+OO
< 5.9E+OO
< 2.7E+OO
< 4.7E+OO
< 2.6E+OO
< 4.3E+OO
< 1.3E+01
< 2.4E+OO
< 2.4E+OO
< 2.4E+01
< 7.8E+OO MW-125 05/16/18 pCi/L
< 1.7E+OO
< 2.1E+OO
< 4.5E+OO
< 1.8E+OO
< 3.6E+OO
< 2.4E+OO
< 3.7E+OO
< 1.4E+01
< 1.9E+OO
< 2.0E+OO
< 2.3E+01
< 7.3E+OO MW-137 05/16/18 pCi/L
< 1.7E+OO
< 2.0E+OO
< 4.2E+OO
< 1.9E+OO
< 3.4E+OO
< 2.2E+OO
< 3.7E+OO
< 1.4E+01
< 2.0E+OO
< 1.9E+OO
< 2.1 E+01
< 6.3E+OO MW-139 05/16/18 pCi/L
< 2.2E+OO
< 2.5E+OO
< 5.7E+OO
< 2.4E+OO
< 4.2E+OO
< 2.8E+OO
< 4.5E+OO
< 1.5E+01
< 2.5E+OO
< 2.0E+OO
< 2.5E+01
< 9.2E+OO MW-141 05/16/18 pCi/L
< 2.0E+OO
< 2.3E+OO
< 5.9E+OO
< 2.2E+OO
< 4.3E+OO
< 2.3E+OO
< 4.1E+OO
< 1.2E+01
< 2.0E+OO
< 2.1E+OO
< 2.3E+01
< 7.9E+OO MW-156 05/16/18 pCi/L
< 2.3E+OO
< 2.5E+OO
< 6.1E+OO
< 2.5E+OO
< 4.9E+OO
< 2.7E+OO
< 4.2E+OO
< 1.1 E+01
< 2.4E+OO
< 2.2E+OO
< 2.1 E+01
< 8.1E+OO MW-157 05/16/18 pCi/L
< 2.2E+OO
< 2.7E+OO
< 5.5E+OO
< 2.4E+OO
< 4.5E+OO
< 2.7E+OO
< 4.5E+OO
< 1.3E+01
< 2.5E+OO
< 2.4E+OO
< 2.3E+01
< 6.7E+OO MW-161 05/16/18 pCi/L
< 2.2E+OO
< 2.5E+OO
< 6.0E+OO
< 2.1E+OO
< 4.4E+OO
< 2.7E+OO
< 4.6E+OO
< 1.5E+01
< 2.5E+OO
< 2.1E+OO
< 2.5E+01
< 8.4E+OO MW-205 05/16/18 pCi/L
< 2.3E+OO
< 2.7E+OO
< 6.9E+OO
< 2.4E+OO
< 5.7E+OO
< 2.9E+OO
< 5.2E+OO
< 1.4E+01
< 2.7E+OO
< 2.6E+OO
< 2.7E+01
< 1.0E+01 MW-207 05/16/18 pCi/L
< 1.9E+OO
< 2.1E+OO
< 4.8E+OO
< 1.9E+OO
< 3.5E+OO
< 2.3E+OO
< 3.8E+OO
< 1.2E+01
< 2.0E+OO
< 1.7E+OO
< 2.0E+01
< 7.0E+OO MW-213 05/16/18 pCi/L
< 2.1E+OO
< 2.4E+OO
< 6.1 E+OO
< 2.0E+OO
< 4.1E+OO
< 2.4E+OO
< 4.4E+OO
< 1.3E+01
< 2.1E+OO
< 2.1E+OO
< 2.3E+01
< 9.3E+OO MW-217 05/16/18 pCi/L
< 2.1E+OO
< 2.4E+OO
< 5.4E+OO
< 2.1E+OO
< 4.3E+OO
< 2.5E+OO
< 4.2E+OO
< 1.3E+01
< 2.3E+OO
< 2.0E+OO
< 2.1E+01
< 7.6E+OO MW-219 05/16/18 pCi/L
< 2.1E+OO
< 2.4E+OO
< 5.9E+OO
< 2.2E+OO
< 4.2E+OO
< 2.7E+OO
< 4.5E+OO
< 1.5E+01
< 2.4E+OO
< 2.0E+OO
< 2.5E+01
< 8.1E+OO MW-223 05/16/18 pCi/L
< 1.8E+OO
< 2.1E+OO
< 5.1 E+OO
< 2.0E+OO
< 3.7E+OO
< 2.2E+OO
< 3.8E+OO
< 1.4E+01
< 1.9E+OO
< 1.9E+OO
< 2.2E+01
< 6.5E+OO MW-225 05/16/18 pCi/L
< 2.0E+OO
< 2.7E+OO
< 5.3E+OO
< 2.2E+OO
< 4.5E+OO
< 2.4E+OO
< 4.1E+OO
< 1.2E+01
< 2.3E+OO
< 2.4E+OO
< 2.0E+01
< 6.7E+OO MW-225 05/16/18 pCi/L
< 1.8E+OO
< 2.0E+OO
< 4.5E+OO
< 1.7E+OO
< 3.6E+OO
< 2.2E+OO
< 3.6E+OO
< 1.5E+01
< 1.9E+OO
< 1.8E+OO
< 2.2E+01
< 6.8E+OO
RBG-47951 Rev.2018 Page 55 of 75 Annual Radioactive Effluent Release Report Page 9 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-227 05/16/18 pCi/L
< 2.1 E+OO
< 2.5E+OO
< 5.4E+OO
< 2.1E+OO
< 4.5E+OO
< 2.5E+OO
< 4.4E+OO
< 1.5E+01
< 2.3E+OO
< 2.1E+OO
< 2.6E+01
< 6.8E+OO MW-231 05/16/18 pCi/L
< 1.3E+OO
< 1.4E+OO
< 2.8E+OO
< 1.3E+OO
< 2.3E+OO
< 1.4E+OO
< 2.5E+OO
< 5.3E+OO
< 1.4E+OO
< 1.4E+OO
< 1.1 E+01
< 3.0E+OO MW-233 05/16/18 pCi/L
< 1.6E+OO
< 1.9E+OO
< 4.1E+OO
< 1.7E+OO
< 3.3E+OO
< 2.0E+OO
< 3.4E+OO
< 1.1 E+01
< 1.8E+OO
< 1.7E+OO
< 1.8E+01
< 4.9E+OO MW-235 05/16/18 pCi/L
< 1.8E+OO
< 2.0E+OO
< 4.9E+OO
< 1.9E+OO
< 3.9E+OO
< 2.2E+OO
< 3.9E+OO
< 1.4E+01
< 2.1E+OO
< 1.9E+OO
< 2.3E+01
< 7.5E+OO PZ-01 05/16/18 pCi/L
< 1.8E+OO
< 2.0E+OO
< 4.4E+OO
< 1.8E+OO
< 3.6E+OO
< 2.1E+OO
< 3.4E+OO
< 1.0E+01
< 1.9E+OO
< 1.8E+OO
< 1.9E+01
< 6.4E+OO MW-100 05/17/18 pCi/L
< 3.7E+OO
< 4.1E+OO
< 6.6E+OO
< 5.0E+OO
< 7.5E+OO
< 4.1E+OO
< 6.7E+OO
< 1.4E+01
< 3.8E+OO
< 4.0E+OO
< 3.3E+01
< 5.1E+OO MW-106 05/17/18 pCi/L
< 3.5E+OO
< 4.3E+OO
< 9.4E+OO
< 4.1E+OO
< 7.5E+OO
< 5.1E+OO
< 8.2E+OO
< 1.4E+01
< 5.1E+OO
< 4.8E+OO
< 2.9E+01
< 7.9E+OO MW-106 05/17/18 pCi/L
< 3.9E+OO
< 4.1E+OO
< 9.9E+OO
< 3.3E+OO
< 8.7E+OO
< 3.7E+OO
< 7.1E+OO
< 1.3E+01
< 5.0E+OO
< 3.7E+OO
< 2.4E+01
< 9.5E+OO MW-118 05/17/18 pCi/L
< 2.5E+OO
< 2.6E+OO
< 6.5E+OO
< 2.6E+OO
< 4.9E+OO
< 2.7E+OO
< 4.8E+OO
< 1.5E+01
< 2.7E+OO
< 2.4E+OO
< 2.7E+01
< 9.2E+OO MW-120 05/17/18 pCi/L
< 4.0E+OO
< 5.0E+OO
< 1.0E+01
< 5.4E+OO
< 8.2E+OO
< 5.8E+OO
< 7.6E+OO
< 1.4E+01
< 5.5E+OO
< 5.5E+OO
< 2.7E+01
< 1.0E+01 MW-122R 05/17/18 pCi/L
< 3.8E+OO
< 4.6E+OO
< 8.9E+OO
< 5.8E+OO
< 1.1 E+01
< 4.5E+OO
< 9.0E+OO
< 1.3E+01
< 4.1E+OO
< 3.9E+OO
< 3.3E+01
< 1.2E+01 MW-126 05/17/18 pCi/L
< 4.3E+OO
< 4.7E+OO
< 1.1 E+01
< 4.7E+OO
< 1.0E+01
< 4.6E+OO
< 8.6E+OO
< 1.3E+01
< 5.0E+OO
< 4.6E+OO
< 3.1E+01
< 1.1 E+01 MW-126 05/17/18 pCi/L
< 4.6E+OO
< 5.0E+OO
< 1.0E+01
< 5.9E+OO
< 7.4E+OO
< 4.9E+OO
< 1.1 E+01
< 1.3E+01
< 5.1E+OO
< 5.0E+OO
< 3.0E+01
< 1.1 E+01 MW-128 05/17/18 pCi/L
< 4.2E+OO
< 4.5E+OO
< 1.0E+01
< 4.2E+OO
< 1.0E+01
< 4.7E+OO
< 8.0E+OO
< 1.3E+01
< 4.8E+OO
< 4.7E+OO
< 3.2E+01
< 1.0E+01 MW-130 05/17/18 pCi/L
< 4.8E+OO
< 4.8E+OO
< 9.9E+OO
< 5.3E+OO
< 9.9E+OO
< 5.5E+OO
< 9.2E+OO
< 1.4E+01
< 6.3E+OO
< 4.4E+OO
< 3.1E+01
< 1.0E+01 MW-131 05/17/18 pCi/L
< 4.1E+OO
< 4.8E+OO
< 1.0E+01
< 3.7E+OO
< 7.1E+OO
< 3.9E+OO
< 8.5E+OO
< 1.4E+01
< 4.2E+OO
< 4.0E+OO
< 2.9E+01
< 1.1 E+01 MW-132 05/17/18 pCi/L
< 4.7E+OO
< 4.7E+OO
< 1.1 E+01
< 4.8E+OO
< 9.4E+OO
< 4.8E+OO
< 8.8E+OO
< 1.4E+01
< 5.0E+OO
< 5.2E+OO
< 3.2E+01
< 9.8E+OO
RBG-47951 I
Rev.2018 Page 56 of 75 Annual Radioactive Effluent Release Report Page 10 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-134 05/17/18 pCi/L
< 4.9E+OO
< 5.3E+OO
< 9.9E+OO
< 5.1E+OO
< 9.6E+OO
< 5.2E+OO
< 8.9E+OO
< 1.4E+01
< 4.8E+OO
< 4.7E+OO
< 3.2E+01
< 9.8E+OO MW-153 05/17/18 pCi/L
< 2.2E+OO
< 2.2E+OO
< 5.6E+OO
< 2.5E+OO
< 4.9E+OO
< 2.6E+OO
< 4.4E+OO
< 1.5E+01
< 2.4E+OO
< 2.2E+OO
< 2.4E+01
< 8.8E+OO MW-167 05/17/18 pCi/L
< 5.3E+OO
< 4.2E+OO
< 1.2E+01
< 5.5E+OO
< 1.2E+01
< 5.9E+OO
< 1.0E+01
< 1.4E+01
< 5.2E+OO
< 6.0E+OO
< 3.6E+01
< 1.0E+01 MW-170 05/17/18 pCi/L
< 3.9E+OO
< 4.6E+OO
< 1.1 E+01
< 4.5E+OO
< 8.1 E+OO
< 4.3E+OO
< 8.9E+OO
< 1.5E+01
< 5.1E+OO
< 4.9E+OO
< 2.9E+01
< 1.0E+01 MW172 05/17/18 pCi/L
< 4.8E+OO
< 5.6E+OO
< 1.1E+01
< 5.1 E+OO
< 1.1 E+01
< 5.2E+OO
< 8.8E+OO
< 1.3E+01
< 4.7E+OO
< 4.6E+OO
< 3.4E+01
< 8.7E+OO MW-174 05/17/18 pCi/L
< 4.4E+OO
< 5.0E+OO
< 9.6E+OO
< 5.5E+OO
< 8.8E+OO
< 4.7E+OO
< 9.1E+OO
< 1.5E+01
< 5.3E+OO
< 4.9E+OO
< 3.3E+01
< 1.1 E+01 MW-180 05/17/18 pCi/L
< 3.1E+OO
< 4.8E+OO
< 7.5E+OO
< 5.1 E+OO
< 8.3E+OO
< 4.7E+OO
< 7.6E+OO
< 1.5E+01
< 4.7E+OO
< 5.0E+OO
< 2.9E+01
< 1.0E+01 MW-182 05/17/18 pCi/L
< 4.8E+OO
< 4.4E+OO
< 1.0E+01
< 5.0E+OO
< 9.0E+OO
< 4.9E+OO
< 8.2E+OO
< 1.3E+01
< 4.8E+OO
< 4.3E+OO
< 3.3E+01
< 7.0E+OO MW-185 05/17/18 pCi/L
< 3.5E+OO
< 4.0E+OO
< 7.9E+OO
< 4.1E+OO
< 7.5E+OO
< 3.6E+OO
< 6.5E+OO
< 9.7E+OO
< 4.1E+OO
< 3.9E+OO
< 2.5E+01
< 7.8E+OO MW-188 05/17/18 pCi/L
< 4.4E+OO
< 4.4E+OO
< 9.7E+OO
< 2.6E+OO
< 9.1E+OO
< 4.7E+OO
< 8.5E+OO
< 1.3E+01
< 3.5E+OO
< 4.4E+OO
< 2.9E+01
< 8.2E+OO MW-209 05/17/18 pCi/L
< 2.0E+OO
< 2.5E+OO
< 5.5E+OO
< 2.0E+OO
< 4.2E+OO
< 2.5E+OO
< 4.2E+OO
< 1.4E+01
< 2.1E+OO
< 2.1E+OO
< 2.3E+01
< 8.6E+OO MW-221 05/17/18 pCi/L
< 2.1 E+OO
< 2.5E+OO
< 5.9E+OO
< 2.3E+OO
< 4.4E+OO
< 2.5E+OO
< 4.5E+OO
< 1.2E+01
< 2.3E+OO
< 2.0E+OO
< 2.3E+01
< 8.8E+OO PZ-03 05/17/18 pCi/L
< 5.2E+OO
< 6.0E+OO
< 1.1 E+01
< 6.6E+OO
< 1.1 E+01
< 4.8E+OO
< 8.6E+OO
< 1.4E+01
< 5.4E+OO
< 5.1E+OO
< 2.9E+01
< 1.2E+01 SW-101 05/17/18 pCi/L
< 4.6E+OO
< 5.5E+OO
< 1.1 E+01
< 5.1E+OO
< 1.1 E+01
< 6.5E+OO
< 9.1E+OO
< 1.4E+01
< 5.9E+OO
< 5.1E+OO
< 3.4E+01
< 1.4E+01 SW-102 05/17/18 pCi/L
< 4.4E+OO
< 4.9E+OO
< 1.1 E+01
< 6.6E+OO
< 9.6E+OO
< 6.1E+OO
< 9.0E+OO
< 1.4E+01
< 5.6E+OO
< 5.4E+OO
< 3.4E+01
< 1.4E+01 SW-103 05/17/18 pCi/L
< 5.3E+OO
< 5.6E+OO
< 9.9E+OO
< 5.2E+OO
< 8.6E+OO
< 5.7E+OO
< 9.0E+OO
< 1.5E+01
< 5.7E+OO
< 4.3E+OO
< 3.3E+01
< 1.2E+01 SW-104 05/17/18 pCi/L
< 4.3E+OO
< 5.0E+OO
< 9.3E+OO
< 4.6E+OO
< 9.5E+OO
< 4.5E+OO
< 8.0E+OO
< 1.4E+01
< 4.7E+OO
< 4.3E+OO
< 3.0E+01
< 9.4E+OO
RBG-47951 l
Rev.2018 Page 57 of 75 Annual Radioactive Effluent Release Report Page 11 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-124 08/21/18 pCi/L
< 3.SE+OO
< 3.3E+OO
< 9.9E+OO
< 4.2E+OO
< 9.4E+OO
< 4.9E+OO
< 8.3E+OO
< 1.5E+01
< 3.7E+OO
< 4.3E+OO
< 2.6E+01
< 1.0E+01 MW-125 08/21/18 pCi/L
< 1.6E+OO
< 1.9E+OO
< 4.2E+OO
< 1.8E+OO
< 3.7E+OO
< 2.0E+OO
< 3.4E+OO
< 7.2E+OO
< 2.0E+OO
< 1.8E+OO
< 1.5E+01
< 4.6E+OO MW-142 08/21/18 pCi/L
< 6.6E+OO
< 6.2E+OO
< 1.7E+01
< 7.2E+OO
< 1.4E+01
< 6.0E+OO
< 1.2E+01
< 1.4E+01
< 8.2E+OO
< 7.9E+OO
< 3.6E+01
< 6.3E+OO MW-144 08/21/18 pCi/L
< 4.8E+OO
< 5.3E+OO
< 1.2E+01
< 4.4E+OO
< 1.1 E+01
< 5.9E+OO
< 9.8E+OO
< 1.5E+01
< 5.1E+OO
< 5.3E+OO
< 3.2E+01
< 1.3E+01 MW-146 08/21/18 pCi/L
< 1.9E+OO
< 2.1E+OO
< 4.6E+OO
< 2.0E+OO
< 3.7E+OO
< 2.2E+OO
< 3.6E+OO
< 8.1E+OO
< 2.1 E+OO
< 1.9E+OO
< 1.6E+01
< 5.8E+OO MW-147 08/21/18 pCi/L
< 3.4E+OO
< 4.0E+OO
< 8.9E+OO
< 4.7E+OO
< 8.6E+OO
< 4.2E+OO
< 7.SE+OO
< 1.2E+01
< 4.2E+OO
< 4.1E+OO
< 2.7E+01
< 6.9E+OO MW-148 08/21/18 pCi/L
< 6.SE+OO
< 6.2E+OO
< 1.3E+01
< 7.3E+OO
< 1.3E+01
< 6.3E+OO
< 1.0E+01
< 1.2E+01
< 7.8E+OO
< 5.7E+OO
< 3.7E+01
< 9.0E+OO MW-151 08/21/18 pCi/L
< 6.6E+OO
< 6.2E+OO
< 1.3E+01
< 5.6E+OO
< 9.SE+OO
< 6.8E+OO
< 1.2E+01
< 1.4E+01
< 6.9E+OO
< 5.6E+OO
< 3.1 E+01
< 1.2E+01 MW-155 08/21/18 pCi/L
< 3.9E+OO
< 4.0E+OO
< 8.4E+OO
< 3.8E+OO
< 7.7E+OO
< 4.8E+OO
< 8.SE+OO
< 1.4E+01
< 5.1 E+OO
< 4.9E+OO
< 3.0E+01
< 8.6E+OO MW-156 08/21/18 pCi/L
< 1.7E+OO
< 1.8E+OO
< 4.4E+OO
< 1.8E+OO
< 3.SE+OO
< 2.1E+OO
< 3.6E+OO
< 7.4E+OO
< 1.9E+OO
< 1.9E+OO
< 1.6E+01
< 5.SE+OO MW-157 08/21/18 pCi/L
< 1.8E+OO
< 1.9E+OO
< 4.3E+OO
< 1.8E+OO
< 3.4E+OO
< 2.1E+OO
< 3.6E+OO
< 7.7E+OO
< 1.9E+OO
< 1.8E+OO
< 1.5E+01
< 4.8E+OO MW-158 08/21 /18 pCi/L
< 4.SE+OO
< 5.SE+OO
< 1.0E+01
< 5.4E+OO
< 1.0E+01
< 4.6E+OO
< 7.9E+OO
< 1.5E+01
< 4.8E+OO
< 5.1E+OO
< 3.2E+01
< 1.2E+01 MW-159 08/21/18 pCi/L
< 4.3E+OO
< 4.3E+OO
< 1.0E+01
< 4.4E+OO
< 8.3E+OO
< 4.6E+OO
< 7.6E+OO
< 1.5E+01
< 4.8E+OO
< 4.4E+OO
< 2.7E+01
< 1.1 E+01 MW-159 08/21/18 pCi/L
< 4.7E+OO
< 4.8E+OO
< 9.9E+OO
< 4.3E+OO
< 9.8E+OO
< 5.6E+OO
< 9.1E+OO
< 1.5E+01
< 4.8E+OO
< 5.3E+OO
< 3.2E+01
< 1.1 E+01 MW-162 08/21/18 pCi/L
< 5.2E+OO
< 6.0E+OO
< 1.0E+01
< 6.2E+OO
< 1.0E+01
< 6.3E+OO
< 1.2E+01
< 1.0E+01
< 5.8E+OO
< 4.7E+OO
< 2.8E+01
< 1.0E+01 MW-164 08/21/18 pCi/L
< 6.6E+OO
< 7.3E+OO
< 1.7E+01
< 7.4E+OO
< 1.3E+01
< 8.0E+OO
< 1.1E+01
< 1.3E+01
< 7.4E+OO
< 7.3E+OO
< 4.3E+01
< 9.3E+OO MW-165 08/21/18 pCi/L
< 5.6E+OO
< 5.9E+OO
< 1.0E+01
< 5.9E+OO
< 1.1 E+01
< 6.1E+OO
< 8.8E+OO
< 1.1 E+01
< 6.2E+OO
< 5.7E+OO
< 3.2E+01
< 9.9E+OO
RBG-47951 Rev.2018 Page 58 of 75 Annual Radioactive Effluent Release Report Page 12 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-169 08/21/18 pCi/L
< 6.4E+OO
< 6.8E+OO
< 1.3E+01
< 6.5E+OO
< 1.3E+01
< 6.8E+OO
< 7.9E+OO
< 1.3E+01
< 6.8E+OO
< 7.0E+OO
< 3.2E+01
< 1.4E+01 MW-178 08/21/18 pCi/L
< 4.0E+OO
< 6.2E+OO
< 1.0E+01
< 4.8E+OO
< 7.5E+OO
< 6.2E+OO
< 1.1 E+01
< 1.5E+01
< 5.7E+OO
< 5.5E+OO
< 3.1 E+01
< 1.3E+01 MW-179 08/21/18 pCi/L
< 4.3E+OO
< 4.8E+OO
< 8.5E+OO
< 4.4E+OO
< 8.7E+OO
< 5.3E+OO
< 8.1E+OO
< 1.4E+01
< 4.8E+OO
< 5.3E+OO
< 3.3E+01
< 8.1E+OO MW-186 08/21/18 pCi/L
< 5.0E+OO
< 6.0E+OO
< 1.3E+01
< 4.8E+OO
< 1.0E+01
< 5.8E+OO
< 1.0E+01
< 1.2E+01
< 6.3E+OO
< 4.8E+OO
< 2.8E+01
< 1.1 E+01 MW-187 08/21/18 pCi/L
< 5.3E+OO
< 5.6E+OO
< 1.3E+01
< 5.9E+OO
< 1.3E+01
< 6.8E+OO
< 1.2E+01
< 1.2E+01
< 7.1 E+OO
< 6.2E+OO
< 2.9E+01
< 9.9E+OO MW-201 08/21/18 pCi/L
< 7.0E+OO
< 6.0E+OO
< 1.4E+01
< 5.4E+OO
< 1.5E+01
< 7.0E+OO
< 1.2E+01
< 1.4E+01
< 8.2E+OO
< 5.9E+OO
< 3.5E+01
< 8.9E+OO MW-203 08/21/18 pCi/L
< 6.2E+OO
< 7.4E+OO
< 1.3E+01
< 5.2E+OO
< 1.2E+01
< 6.3E+OO
< 1.1 E+01
< 1.4E+01
< 6.8£+00
< 6.1E+OO
< 3.7E+01
< 9.3E+OO MW-215 08/21/18 pCi/L
< 5.6E+OO
< 5.8E+OO
< 1.3E+01
< 7.9E+OO
< 1.0E+01
< 6.9E+OO
< 1.3E+01
< 1.3E+01
< 7.8E+OO
< 7.5E+OO
< 4.1 E+01
< 1.5E+01 MW-217 08/21/18 pCi/L
< 5.1E+OO
< 4.6E+OO
< 1.1 E+01
< 5.7E+OO
< 1.1 E+01
< 5.6E+OO
< 7.6E+OO
< 1.1 E+01
< 6.4E+OO
< 5.7E+OO
< 2.8E+01
< 6.2E+OO MW-100 08/22/18 pCi/L
< 6.5E+OO
< 6.3E+OO
< 1.6E+01
< 5.3E+OO
< 1.6E+01
< 7.6E+OO
< 1.1E+01
< 1.4E+01
< 7.7E+OO
< 6.9E+OO
< 3.7E+01
< 1.2E+01 MW-110 08/22/18 pCi/L
< 1.8E+OO
< 2.1E+OO
< 4.8E+OO
< 1.9E+OO
< 3.8E+OO
< 2.2E+OO
< 3.6E+OO
< 9.3E+OO
< 2.1E+OO
< 2.0E+OO
< 1.8E+01
< 5.6E+OO MW-112 08/22/18 pCi/L
< 5.1 E+OO
< 5.4E+OO
< 1.3E+01
< 5.3E+OO
< 1.2E+01
< 6.1E+OO
< 9.8E+OO
< 1.5E+01
< 6.2E+OO
< 5.4E+OO
< 3.3E+01
< 1.2E+01 MW-114 08/22/18 pCi/L
< 1.8E+OO
< 2.0E+OO
< 4.8E+OO
< 2.0E+OO
< 3.7E+OO
< 2.0E+OO
< 3.6E+OO
< 9.8E+OO
< 2.1 E+OO
< 1.9E+OO
< 1.8E+01
< 6.1E+OO MW-116 08/22/18 pCi/L
< 2.0E+OO
< 2.1E+OO
< 4.8E+OO
< 2.3E+OO
< 4.2E+OO
< 2.4E+OO
< 3.9E+OO
< 8.9E+OO
< 2.3E+OO
< 2.3E+OO
< 1.7E+01
< 6.0E+OO MW-118 08/22/18 pCi/L
< 4.6E+OO
< 4.8E+OO
< 1.0E+01
< 4.9E+OO
< 9.8E+OO
< 4.7E+OO
< 8.6E+OO
< 1.3E+01
< 5.1E+OO
< 4.5E+OO
< 3.3E+01
< 1.1 E+01 MW-137 08/22/18 pCi/L
< 4.4E+OO
< 4.5E+OO
< 1.0E+01
< 4.9E+OO
< 8.6E+OO
< 4.9E+OO
< 8.1E+OO
< 1.3E+01
< 4.5E+OO
< 4.7E+OO
< 3.1E+01
< 8.1E+OO MW-139 08/22/18 pCi/L
< 4.7E+OO
< 4.3E+OO
< 9.9E+OO
< 4.4E+OO
< 1.0E+01
< 4.5E+OO
< 8.9E+OO
< 1.2E+01
< 4.8E+OO
< 4.6E+OO
< 2.9E+01
< 1.0E+01
RBG-47951 Rev.2018 Page 59 of 75 Annual Radioactive Effluent Release Report Page 13 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-141 08/22/18 pCi/L
< 4.8E+OO
< 5.3E+OO
< 9.1E+OO
< 4.0E+OO
< 9.1E+OO
< 5.2E+OO
< 8.9E+OO
< 1.4E+01
< 4.8E+OO
< 5.2E+OO
< 3.3E+01
< 8.7E+OO MW-153 08/22/18 pCi/L
< 5.1E+OO
< 5.5E+OO
< 9.2E+OO
< 3.9E+OO
< 9.1E+OO
< 5.2E+OO
< 9.2E+OO
< 1.5E+01
< 5.5E+OO
< 4.9E+OO
< 3.3E+01
< 9.7E+OO MW-153 08/22/18 pCi/L
< 1.8E+OO
< 2.1E+OO
< 4.9E+OO
< 1.9E+OO
< 3.8E+OO
< 2.2E+OO
< 3.5E+OO
< 9.2E+OO
< 2.0E+OO
< 1.9E+OO
< 1.8E+01
< 5.7E+OO MW-161 08/22/18 pCi/L
< 1.8E+OO
< 1.8E+OO
< 4.5E+OO
< 1.8E+OO
< 3.7E+OO
< 2.1E+OO
< 3.5E+OO
< 8.9E+OO
< 1.9E+OO
< 1.9E+OO
< 1.6E+01
< 4.9E+OO MW-170 08/22/18 pCi/L
< 7.2E+OO
< 6.5E+OO
< 8.6E+OO
< 4.8E+OO
< 1.5E+01
< 7.1E+OO
< 1.3E+01
< 1.3E+01
< 7.2E+OO
< 6.1E+OO
< 4.1E+01
< 1.1E+01 MW-182 08/22/18 pCi/L
< 6.2E+OO
< 4.9E+OO
< 1.2E+01
< 4.0E+OO
< 1.2E+01
< 7.0E+OO
< 1.1E+01
< 1.1 E+01
< 6.2E+OO
< 7.1E+OO
< 2.9E+01
< 1.0E+01 MW-188 08/22/18 pCi/L
< 6.2E+OO
< 5.4E+OO
< 1.3E+01
< 6.0E+OO
< 1.3E+01
< 6.2E+OO
< 1.0E+01
< 8.9E+OO
< 7.0E+OO
< 4.8E+OO
< 3.3E+01
< 9.3E+OO MW-205 08/22/18 pCi/L
< 7.0E+OO
< 6.8E+OO
< 1.5E+01
< 5.7E+OO
< 1.4E+01
< 8.7E+OO
< 1.2E+01
< 1.4E+01
< 7.7E+OO
< 7.1E+OO
< 3.5E+01
< 1.3E+01 MW-207 08/22/18 pCi/L
< 6.2E+OO
< 6.4E+OO
< 1.1 E+01
< 8.0E+OO
< 1.2E+01
< 7.3E+OO
< 1.1 E+01
< 1.4E+01
< 6.9E+OO
< 7.7E+OO
< 3.3E+01
< 1.1 E+01 MW-209 08/22/18 pCi/L
< 6.8E+OO
< 7.5E+OO
< 1.5E+01
< 7.8E+OO
< 1.6E+01
< 8.5E+OO
< 1.4E+01
< 1.4E+01
< 8.5E+OO
< 8.9E+OO
< 3.9E+01
< 1.2E+01 MW-211 08/22/18 pCi/L
< 7.0E+OO
< 9.1 E+OO
< 1.8E+01
< 6.6E+OO
< 1.6E+01
< 8.3E+OO
< 1.2E+01
< 1.3E+01
< 7.5E+OO
< 7.3E+OO
< 3.8E+01
< 7.7E+OO MW-211 08/22/18 pCi/L
< 6.3E+OO
< 6.9E+OO
< 1.4E+01
< 5.9E+OO
< 1.4E+01
< 6.5E+OO
< 1.2E+01
< 1.2E+01
< 8.6E+OO
< 5.6E+OO
< 3.2E+01
< 1.3E+01 MW-213 08/22/18 pCi/L
< 5.5E+OO
< 6.8E+OO
< 1.6E+01
< 7.6E+OO
< 1.4E+01
< 6.9E+OO
< 1.0E+01
< 1.0E+01
< 6.3E+OO
< 6.4E+OO
< 3.0E+01
< 1.2E+01 MW-213 08/22/18 pCi/L
< 5.9E+OO
< 6.8E+OO
< 1.6E+01
< 7.8E+OO
< 1.3E+01
< 6.1 E+OO
< 1.0E+01
< 1.2E+01
< 6.8E+OO
< 7.0E+OO
< 3.1 E+01
< 9.2E+OO MW-221 08/22/18 pCi/L
< 6.4E+OO
< 7.2E+OO
< 1.5E+01
< 1.0E+01
< 1.7E+01
< 7.8E+OO
< 1.2E+01
< 1.4E+01
< 5.6E+OO
< 8.7E+OO
< 2.9E+01
< 1.4E+01 MW-227 08/22/18 pCi/L
< 6.5E+OO
< 6.8E+OO
< 1.5E+01
< 7.7E+OO
< 1.2E+01
< 6.7E+OO
< 9.6E+OO
< 1.1 E+01
< 6.6E+OO
< 7.3E+OO
< 3.2E+01
< 1.5E+01 MW-229 08/22/18 pCi/L
< 6.9E+OO
< 7.0E+OO
< 1.5E+01
< 5.9E+OO
< 1.6E+01
< 6.0E+OO
< 1.1 E+01
< 1.3E+01
< 7.2E+OO
< 6.7E+OO
< 3.8E+01
< 9.6E+OO
RBG-47951 Rev.2018 Page 60 of 75 Annual Radioactive Effluent Release Report Page 14 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-229 08/22/18 pCi/L
< 6.4E+OO
< 8.3E+OO
< 2.0E+01
< 8.6E+OO
< 1.7E+01
< 8.4E+OO
< 1.3E+01
< 1.4E+01
< 8.1E+OO
< 7.6E+OO
< 4.5E+01
< 1.4E+01 MW-231 08/22/18 pCi/L
< 6.7E+OO
< 6.7E+OO
< 1.3E+01
< 8.8E+OO
< 1.6E+01
< 6.7E+OO
< 1.2E+01
< 1.4E+01
< 7.6E+OO
< 6.2E+OO
< 3.8E+01
< 1.3E+01 PZ-01 08/22/18 pCi/L
< 2.1E+OO
< 2.4E+OO
< 5.3E+OO
< 1.9E+OO
< 4.4E+OO
< 2.3E+OO
< 4.1E+OO
< 1.0E+01
< 2.2E+OO
< 2.0E+OO
< 1.9E+01
< 7.3E+OO MW-219 08/23/18 pCi/L
< 8.2E+OO
< 6.9E+OO
< 1.6E+01
< 8.5E+OO
< 1.4E+01
< 7.9E+OO
< 1.5E+01
< 1.4E+01
< 8.1E+OO
< 7.5E+OO
< 2.9E+01
< 1.5E+01 MW-223 08/23/18 pCi/L
< 8.5E+OO
< 8.2E+OO
< 1.5E+01
< 9.3E+OO
< 2.0E+01
< 8.0E+OO
< 1.1 E+01
< 1.3E+01
< 8.2E+OO
< 7.9E+OO
< 3.6E+01
< 1.1 E+01 MW-225 08/23/18 pCi/L
< 7.2E+OO
< 6.5E+OO
< 1.5E+01
< 8.6E+OO
< 1.6E+01
< 8.6E+OO
< 1.2E+01
< 1.4E+01
< 7.7E+OO
< 6.6E+OO
< 4.2E+01
< 1.2E+01 MW-233 08/23/18 pCi/L
< 7.1 E+OO
< 8.6E+OO
< 1.8E+01
< 7.0E+OO
< 1.4E+01
< 7.7E+OO
< 1.2E+01
< 1.4E+01
< 5.8E+OO
< 8.5E+OO
< 3.3E+01
< 9.2E+OO MW-235 08/23/18 pCi/L
< 7.9E+OO
< 5.8E+OO
< 1.4E+01
< 7.5E+OO
< 1.8E+01
< 7.3E+OO
< 1.1 E+01
< 1.5E+01
< 8.6E+OO
< 8.8E+OO
< 3.8E+01
< 1.2E+01 SW-103 08/23/18 pCi/L
< 6.3E+OO
< 7.3E+OO
< 1.6E+01
< 7.5E+OO
< 1.5E+01
< 5.8E+OO
< 1.4E+01
< 1.5E+01
< 8.0E+OO
< 7.3E+OO
< 3.3E+01
< 8.5E+OO MW-148 09/10/18 pCi/L
< 6.3E+OO
< 5.2E+OO
< 1.3E+01
< 6.7E+OO
< 1.3E+01
< 6.3E+OO
< 1.2E+01
< 1.4E+01
< 6.6E+OO
< 6.1E+OO
< 2.8E+01
< 9.2E+OO MW-112 11/06/18 pCi/L
< 2.4E+OO
< 2.7E+OO
< 5.8E+OO
< 3.1E+OO
< 5.3E+OO
< 2.6E+OO
< 4.3E+OO
< 5.8E+OO
< 2.8E+OO
< 2.7E+OO
< 1.4E+01
< 4.7E+OO MW-114 11/06/18 pCi/L
< 6.2E+OO
< 6.9E+OO
< 1.2E+01
< 6.0E+OO
< 1.2E+01
< 6.5E+OO
< 1.2E+01
< 1.4E+01
< 6.3E+OO
< 7.2E+OO
< 3.0E+01
< 1.5E+01 MW-116 11/06/18 pCi/L
< 5.6E+OO
< 5.5E+OO
< 1.2E+01
< 7.3E+OO
< 1.1 E+01
< 5.8E+OO
< 1.3E+01
< 1.4E+01
< 5.8E+OO
< 6.6E+OO
< 3.6E+01
< 1.2E+01 MW-118 11/06/18 pCi/L
< 4.9E+OO
< 4.8E+OO
< 1.5E+01
< 6.2E+OO
< 1.3E+01
< 5.7E+OO
< 1.1 E+01
< 1.3E+01
< 6.0E+OO
< 5.4E+OO
< 3.4E+01
< 1.0E+01 MW-139 11/06/18 pCi/L
< 5.3E+OO
< 5.9E+OO
< 1.2E+01
< 4.5E+OO
< 1.2E+01
< 5.4E+OO
< 1.0E+01
< 1.3E+01
< 6.2E+OO
< 5.2E+OO
< 3.2E+01
< 1.0E+01 MW-141 11/06/18 pCi/L
< 2.3E+OO
< 2.4E+OO
< 4.8E+OO
< 2.6E+OO
< 4.9E+OO
< 2.5E+OO
< 4.5E+OO
< 5.7E+OO
< 2.5E+OO
< 2.5E+OO
< 1.5E+01
< 4.6E+OO MW-142 11/06/18 pCi/L
< 1.9E+OO
< 1.8E+OO
< 4.0E+OO
< 2.2E+OO
< 3.7E+OO
< 2.0E+OO
< 3.8E+OO
< 4.6E+OO
< 2.1 E+OO
< 2.0E+OO
< 1.2E+01
< 4.2E+OO
RBG-47951 Rev.2018 Page 61 of 75 Annual Radioactive Effluent Release Report Page 15 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-144 11/06/18 pCi/L
< 5.6E+OO
< 6.2E+OO
< 1.1 E+01
< 5.9E+OO
< 1.0E+01
< 5.4E+OO
< 9.9E+OO
< 1.2E+01
< 6.SE+OO
< 5.8E+OO
< 3.0E+01
< 8.9E+OO MW-146 11/06/18 pCi/L
< 3.2E+OO
< 3.SE+OO
< 7.0E+OO
< 4.6E+OO
< 7.8E+OO
< 3.7E+OO
< 6.2E+OO
< 9.1E+OO
< 4.1E+OO
< 3.4E+OO
< 2.2E+01
< 8.1E+OO MW-147 11/06/18 pCi/L
< 3.2E+OO
< 3.3E+OO
< 7.1E+OO
< 2.6E+OO
< 6.8E+OO
< 4.0E+OO
< 5.6E+OO
< 8.9E+OO
< 3.4E+OO
< 3.2E+OO
< 1.9E+01
< 6.SE+OO MW-148 11/06/18 pCi/L
< 2.7E+OO
< 2.8E+OO
< 6.3E+OO
< 2.9E+OO
< 5.8E+OO
< 2.9E+OO
< 4.8E+OO
< 7.1E+OO
< 3.1E+OO
< 2.6E+OO
< 1.7E+01
< 5.8E+OO MW-158 11/06/18 pCi/L
< 3.1E+OO
< 3.SE+OO
< 6.8E+OO
< 3.3E+OO
< 7.9E+OO
< 3.8E+OO
< 5.8E+OO
< 9.1E+OO
< 3.7E+OO
< 3.2E+OO
< 2.0E+01
< 5.8E+OO MW-159 11/06/18 pCi/L
< 2.7E+OO
< 2.9E+OO
< 5.7E+OO
< 2.8E+OO
< 5.4E+OO
< 3.6E+OO
< 5.1E+OO
< 7.1 E+OO
< 3.0E+OO
< 2.8E+OO
< 1.8E+01
< 6.3E+OO MW-159 11/06/18 pCi/L
< 2.9E+OO
< 3.3E+OO
< 8.2E+OO
< 4.8E+OO
< 6.4E+OO
< 3.4E+OO
< 5.3E+OO
< 7.4E+OO
< 3.4E+OO
< 3.1E+OO
< 2.1E+01
< 6.6E+OO MW-161 11/06/18 pCi/L
< 3.9E+OO
< 3.6E+OO
< 7.4E+OO
< 4.4E+OO
< 8.9E+OO
< 5.SE+OO
< 7.SE+OO
< 1.1 E+01
< 4.9E+OO
< 4.7E+OO
< 2.6E+01
< 7.1E+OO MW-162 11/06/18 pCi/L
< 3.7E+OO
< 3.1 E+OO
< 7.9E+OO
< 4.SE+OO
< 7.4E+OO
< 3.3E+OO
< 6.0E+OO
< 7.9E+OO
< 3.6E+OO
< 3.0E+OO
< 2.0E+01
< 6.1E+OO MW-178 11/06/18 pCi/L
< 3.1 E+OO
< 3.4E+OO
< 6.7E+OO
< 4.1E+OO
< 7.1E+OO
< 3.7E+OO
< 6.2E+OO
< 7.4E+OO
< 3.8E+OO
< 3.9E+OO
< 1.9E+01
< 7.1E+OO MW-179 11/06/18 pCi/L
< 2.8E+OO
< 2.8E+OO
< 6.4E+OO
< 2.7E+OO
< 6.SE+OO
< 3.4E+OO
< 6.4E+OO
< 7.6E+OO
< 3.SE+OO
< 3.3E+OO
< 1.7E+01
< 6.SE+OO MW-179 11/06/18 pCi/L
< 2.2E+OO
< 2.4E+OO
< 4.6E+OO
< 2.2E+OO
< 4.3E+OO
< 2.3E+OO
< 4.1E+OO
< 5.6E+OO
< 2.6E+OO
< 2.2E+OO
< 1.4E+01
< 4.2E+OO MW-201 11/06/18 pCi/L
< 2.9E+OO
< 3.3E+OO
< 6.2E+OO
< 3.2E+OO
< 6.1E+OO
< 3.1E+OO
< 5.4E+OO
< 7.6E+OO
< 3.3E+OO
< 3.1E+OO
< 1.6E+01
< 6.1E+OO MW-203 11/06/18 pCi/L
< 3.SE+OO
< 4.0E+OO
< 8.8E+OO
< 3.6E+OO
< 7.9E+OO
< 4.3E+OO
< 7.0E+OO
< 1.1 E+01
< 4.4E+OO
< 4.0E+OO
< 2.3E+01
< 9.2E+OO MW-05 11/07/18 pCi/L
< 4.SE+OO
< 4.7E+OO
< 9.8E+OO
< 5.2E+OO
< 9.2E+OO
< 4.9E+OO
< 9.3E+OO
< 1.2E+01
< 5.SE+OO
< 4.8E+OO
< 2.7E+01
< 9.6E+OO MW-100 11/07/18 pCi/L
< 1.9E+OO
< 2.2E+OO
< 4.9E+OO
< 2.3E+OO
< 4.6E+OO
< 2.2E+OO
< 3.6E+OO
< 8.3E+OO
< 2.2E+OO
< 2.2E+OO
< 1.7E+01
< 5.3E+OO MW-110 11/07/18 pCi/L
< 6.3E+OO
< 6.SE+OO
< 1.2E+01
< 6.3E+OO
< 1.3E+01
< 6.7E+OO
< 1.0E+01
< 1.1 E+01
< 6.1E+OO
< 6.3E+OO
< 3.2E+01
< 1.1 E+01
RBG-47951 Rev.2018 Page 62 of 75 Annual Radioactive Effluent Release Report Page 16 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-124 11/07/18 pCi/L
< 5.1E+OO
< 5.3E+OO
< 1.1 E+01
< 5.7E+OO
< 1.1 E+01
< 5.3E+OO
< 1.0E+01
< 1.1 E+01
< 6.4E+OO
< 5.3E+OO
< 2.9E+01
< 9.SE+OO MW-124 11/07/18 pCi/L
< 4.7E+OO
< 4.SE+OO
< 9.4E+OO
< 4.8E+OO
< 9.8E+OO
< 7.7E+OO
< 8.7E+OO
< 1.1 E+01
< 5.8E+OO
< 5.1E+OO
< 2.4E+01
< 9.4E+OO MW-125 11/07/18 pCi/L
< 4.6E+OO
< 6.7E+OO
< 1.5E+01
< 9.0E+OO
< 1.3E+01
< 7.6E+OO
< 1.2E+01
< 1.3E+01
< 9.1E+OO
< 6.9E+OO
< 3.4E+01
< 1.2E+01 MW-126 11/07/18 pCi/L
< 5.7E+OO
< 4.7E+OO
< 1.0E+01
< 6.0E+OO
< 9.4E+OO
< 5.4E+OO
< 9.6E+OO
< 1.2E+01
< 5.3E+OO
< 5.3E+OO
< 3.2E+01
< 9.1E+OO MW-126 11/07/18 pCi/L
< 6.2E+OO
< 6.6E+OO
< 1.3E+01
< 7.4E+OO
< 1.8E+01
< 1.1 E+01
< 1.1 E+01
< 1.4E+01
< 7.8E+OO
< 6.8E+OO
< 4.0E+01
< 1.4E+01 MW-137 11/07/18 pCi/L
< 5.7E+OO
< 6.3E+OO
< 1.2E+01
< 6.3E+OO
< 1.1 E+01
< 5.9E+OO
< 9.4E+OO
< 1.4E+01
< 7.3E+OO
< 5.7E+OO
< 3.6E+01
< 1.4E+01 MW-151 11/07/18 pCi/L
< 2.0E+OO
< 2.2E+OO
< 4.6E+OO
< 2.0E+OO
< 4.4E+OO
< 2.4E+OO
< 4.1E+OO
< 8.4E+OO
< 2.1E+OO
< 2.1E+OO
< 1.7E+01
< 5.0E+OO MW-153 11/07/18 pCi/L
< 5.4E+OO
< 5.SE+OO
< 1.1 E+01
< 6.6E+OO
< 9.SE+OO
< 5.6E+OO
< 9.0E+OO
< 1.1 E+01
< 6.4E+OO
< 5.2E+OO
< 3.0E+01
< 6.0E+OO MW-155 11/07/18 pCi/L
< 4.SE+OO
< 4.8E+OO
< 1.2E+01
< 5.7E+OO
< 9.3E+OO
< 5.7E+OO
< 9.3E+OO
< 1.0E+01
< 4.4E+OO
< 5.4E+OO
< 2.7E+01
< 9.3E+OO MW-156 11/07/18 pCi/L
< 6.3E+OO
< 6.6E+OO
< 1.1 E+01
< 5.9E+OO
< 1.1 E+01
< 7.2E+OO
< 9.9E+OO
< 1.2E+01
< 6.6E+OO
< 6.1E+OO
< 3.4E+01
< 1.0E+01 MW-157 11/07/18 pCi/L
< 6.0E+OO
< 6.4E+OO
< 1.4E+01
< 6.4E+OO
< 1.4E+01
< 5.6E+OO
< 8.3E+OO
< 1.3E+01
< 6.3E+OO
< 5.0E+OO
< 3.6E+01
< 1.2E+01 MW-164 11/07/18 pCi/L
< 3.7E+OO
< 3.6E+OO
< 8.4E+OO
< 3.8E+OO
< 7.SE+OO
< 3.8E+OO
< 6.7E+OO
< 1.1 E+01
< 3.7E+OO
< 3.7E+OO
< 2.4E+01
< 7.2E+OO MW-165 11/07/18 pCi/L
< 2.7E+OO
< 3.0E+OO
< 6.1E+OO
< 3.1E+OO
< 6.2E+OO
< 3.4E+OO
< 5.4E+OO
< 9.8E+OO
< 3.1E+OO
< 3.0E+OO
< 2.1 E+01
< 6.8E+OO MW-172 11/07/18 pCi/L
< 2.0E+OO
< 2.2E+OO
< 5.0E+OO
< 2.0E+OO
< 4.2E+OO
< 2.4E+OO
< 4.1E+OO
< 8.1E+OO
< 2.3E+OO
< 2.2E+OO
< 1.6E+01
< 5.9E+OO MW-180 11/07/18 pCi/L
< 3.1E+OO
< 3.1 E+OO
< 7.6E+OO
< 3.4E+OO
< 6.0E+OO
< 3.2E+OO
< 5.2E+OO
< 1.1 E+01
< 3.4E+OO
< 3.1E+OO
< 2.1 E+01
< 7.9E+OO MW-182 11/07/18 pCi/L
< 4.1 E+OO
< 4.3E+OO
< 9.8E+OO
< 4.4E+OO
< 9.1E+OO
< 4.8E+OO
< 6.9E+OO
< 1.4E+01
< 4.3E+OO
< 4.2E+OO
< 2.9E+01
< 1.2E+01 MW-186 11/07/18 pCi/L
< 4.8E+OO
< 5.8E+OO
< 1.3E+01
< 5.9E+OO
< 1.0E+01
< 5.9E+OO
< 8.1E+OO
< 1.5E+01
< 5.0E+OO
< 5.2E+OO
< 3.5E+01
< 1.1E+01
RBG-47951 Rev.2018 Page 63 of 75 Annual Radioactive Effluent Release Report Page 17 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-187 11/07/18 pCi/L
< 4.5E+OO
< 4.9E+OO
< 8.1E+OO
< 3.6E+OO
< 1.1 E+01
< 5.1 E+OO
< 7.9E+OO
< 1.3E+01
< 4.9E+OO
< 4.5E+OO
< 2.5E+01
< 1.4E+01 MW-211 11/07/18 pCi/L
< 1.9E+OO
< 2.1E+OO
< 4.6E+OO
< 1.9E+OO
< 3.8E+OO
< 2.5E+OO
< 3.8E+OO
< 7.1E+OO
< 2.1E+OO
< 1.8E+OO
< 1.5E+01
< 5.3E+OO MW-225 11/07/18 pCi/L
< 3.7E+OO
< 3.7E+OO
< 9.3E+OO
< 3.9E+OO
< 8.4E+OO
< 4.9E+OO
< 7.2E+OO
< 9.1E+OO
< 4.7E+OO
< 4.4E+OO
< 2.5E+01
< 7.5E+OO MW-233 11/07/18 pCi/L
< 4.2E+OO
< 4.7E+OO
< 1.2E+01
< 5.1E+OO
< 1.1 E+01
< 4.9E+OO
< 8.9E+OO
< 1.1 E+01
< 4.9E+OO
< 5.0E+OO
< 2.5E+01
< 9.5E+OO PZ-01 11/07/18 pCi/L
< 2.7E+OO
< 2.7E+OO
< 6.3E+OO
< 3.2E+OO
< 5.6E+OO
< 3.2E+OO
< 4.7E+OO
< 6.6E+OO
< 3.2E+OO
< 3.0E+OO
< 1.6E+01
< 5.6E+OO PZ-03 11/07/18 pCi/L
< 5.1 E+OO
< 4.9E+OO
< 1.3E+01
< 5.7E+OO
< 1.3E+01
< 5.8E+OO
< 7.1E+OO
< 1.1 E+01
< 5.0E+OO
< 4.7E+OO
< 3.0E+01
< 9.9E+OO MW-04 11/08/18 pCi/L
< 5.5E+OO
< 5.1 E+OO
< 1.1 E+01
< 7.6E+OO
< 9.7E+OO
< 7.0E+OO
< 1.0E+01
< 1.2E+01
< 6.6E+OO
< 6.9E+OO
< 3.2E+01
< 1.1 E+01 MW-08 11/08/18 pCi/L
< 3.8E+OO
< 3.6E+OO
< 7.5E+OO
< 4.4E+OO
< 6.5E+OO
< 3.9E+OO
< 5.8E+OO
< 7.4E+OO
< 3.9E+OO
< 3.6E+OO
< 1.9E+01
< 6.3E+OO MW-103 11/08/18 pCi/L
< 2.9E+OO
< 3.1E+OO
< 7.0E+OO
< 2.7E+OO
< 6.3E+OO
< 3.5E+OO
< 5.5E+OO
< 9.4E+OO
< 3.3E+OO
< 3.1E+OO
< 2.0E+01
< 6.6E+OO MW-104 11/08/18 pCi/L
< 2.9E+OO
< 3.2E+OO
< 7.4E+OO
< 2.9E+OO
< 6.5E+OO
< 3.3E+OO
< 5.3E+OO
< 1.2E+01
< 3.3E+OO
< 3.1E+OO
< 2.5E+01
< 8.2E+OO MW-106 11/08/18 pCi/L
< 3.3E+OO
< 3.3E+OO
< 7.7E+OO
< 4.1 E+OO
< 7.5E+OO
< 4.2E+OO
< 6.3E+OO
< 9.5E+OO
< 3.4E+OO
< 3.5E+OO
< 2.3E+01
< 6.3E+OO MW-107 11/08/18 pCi/L
< 3.1E+OO
< 3.3E+OO
< 8.8E+OO
< 4.1E+OO
< 7.5E+OO
< 4.3E+OO
< 5.6E+OO
< 1.2E+01
< 4.1E+OO
< 3.7E+OO
< 2.6E+01
< 9.2E+OO MW-108 11/08/18 pCi/L
< 3.0E+OO
< 3.5E+OO
< 7.5E+OO
< 3.0E+OO
< 6.9E+OO
< 3.5E+OO
< 6.0E+OO
< 1.2E+01
< 3.5E+OO
< 3.4E+OO
< 2.6E+01
< 7.7E+OO MW-111 11/08/18 pCi/L
< 3.8E+OO
< 4.0E+OO
< 8.2E+OO
< 4.1 E+OO
< 5.7E+OO
< 3.8E+OO
< 6.5E+OO
< 1.2E+01
< 3.7E+OO
< 3.5E+OO
< 2.5E+01
< 7.6E+OO MW-120 11/08/18 pCi/L
< 6.8E+OO
< 7.5E+OO
< 1.3E+01
< 6.1 E+OO
< 1.6E+01
< 7.1E+OO
< 1.2E+01
< 1.5E+01
< 7.4E+OO
< 6.5E+OO
< 3.6E+01
< 1.3E+01 MW-122R 11/08/18 pCi/L
< 6.6E+OO
< 5.4E+OO
< 1.2E+01
< 7.1E+OO
< 1.5E+01
< 6.9E+OO
< 1.2E+01
< 1.5E+01
< 6.5E+OO
< 7.5E+OO
< 3.5E+01
< 9.8E+OO MW-128 11/08/18 pCi/L
< 4.3E+OO
< 4.7E+OO
< 1.1 E+01
< 4.7E+OO
< 1.3E+01
< 5.5E+OO
< 8.6E+OO
< 1.4E+01
< 4.9E+OO
< 4.4E+OO
< 3.0E+01
< 8.9E+OO
RBG-47951 Rev.2018 I Page 64 of 75 Annual Radioactive Effluent Release Report Page 18 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-130 11/08/18 pCi/L
< 4.9E+OO
< 4.8E+OO
< 1.2E+01
< 6.2E+OO
< 1.2E+01
< 6.1E+OO
< 8.6E+OO
< 1.0E+01
< 5.9E+OO
< 5.3E+OO
< 2.6E+01
< 9.9E+OO MW-131 11/08/18 pCi/L
< 2.6E+OO
< 3.0E+OO
< 6.8E+OO
< 3.0E+OO
< 5.7E+OO
< 3.2E+OO
< 5.1E+OO
< 7.0E+OO
< 3.2E+OO
< 3.0E+OO
< 1.8E+01
< 5.6E+OO MW-132 11/08/18 pCi/L
< 3.6E+OO
< 3.8E+OO
< 8.1E+OO
< 4.3E+OO
< 8.4E+OO
< 4.4E+OO
< 7.9E+OO
< 1.1 E+01
< 3.8E+OO
< 3.8E+OO
< 2.6E+01
< 8.6E+OO MW-134 11/08/18 pCi/L
< 4.1 E+OO
< 4.2E+OO
< 1.1 E+01
< 3.7E+OO
< 7.7E+OO
< 4.3E+OO
< 7.2E+OO
< 1.1 E+01
< 4.4E+OO
< 4.0E+OO
< 3.0E+01
< 9.1E+OO MW-14 11/08/18 pCi/L
< 2.7E+OO
< 2.5E+OO
< 6.2E+OO
< 2.8E+OO
< 5.7E+OO
< 3.1E+OO
< 5.6E+OO
< 7.9E+OO
< 2.9E+OO
< 2.9E+OO
< 1.9E+01
< 6.3E+OO MW-167 11/08/18 pCi/L
< 4.4E+OO
< 4.3E+OO
< 8.6E+OO
< 3.8E+OO
< 8.7E+OO
< 5.6E+OO
< 7.9E+OO
< 1.1 E+01
< 4.4E+OO
< 4.6E+OO
< 2.3E+01
< 9.2E+OO MW-169 11/08/18 pCi/L
< 2.4E+OO
< 2.6E+OO
< 5.7E+OO
< 2.4E+OO
< 5.3E+OO
< 2.9E+OO
< 4.8E+OO
< 9.0E+OO
< 2.7E+OO
< 2.5E+OO
< 1.9E+01
< 6.0E+OO MW-170 11/08/18 pCi/L
< 3.1E+OO
< 3.6E+OO
< 7.3E+OO
< 3.3E+OO
< 7.0E+OO
< 3.7E+OO
< 6.3E+OO
< 1.2E+01
< 3.4E+OO
< 3.2E+OO
< 2.5E+01
< 9.1E+OO MW-170 11/08/18 pCi/L
< 2.7E+OO
< 2.7E+OO
< 6.1 E+OO
< 2.8E+OO
< 4.6E+OO
< 2.9E+OO
< 4.7E+OO
< 9.3E+OO
< 2.6E+OO
< 2.6E+OO
< 1.8E+01
< 6.9E+OO MW-174 11/08/18 pCi/L
< 4.6E+OO
< 4.3E+OO
< 1.1 E+01
< 4.9E+OO
< 1.1 E+01
< 7.0E+OO
< 9.4E+OO
< 1.4E+01
< 5.7E+OO
< 4.9E+OO
< 3.3E+01
< 1.2E+01 MW-174 11/08/18 pCi/L
< 2.5E+OO
< 2.5E+OO
< 5.2E+OO
< 2.9E+OO
< 5.4E+OO
< 2.8E+OO
< 4.4E+OO
< 7.8E+OO
< 2.7E+OO
< 2.4E+OO
< 1.8E+01
< 4.7E+OO MW-18 11/08/18 pCi/L
< 2.4E+OO
< 2.6E+OO
< 5.5E+OO
< 2.7E+OO
< 5.6E+OO
< 2.7E+OO
< 4.4E+OO
< 5.9E+OO
< 2.7E+OO
< 2.7E+OO
< 1.5E+01
< 4.2E+OO MW-18 11/08/18 pCi/L
< 6.4E+OO
< 5.4E+OO
< 7.5E+OO
< 4.3E+OO
< 1.1 E+01
< 6.1E+OO
< 9.3E+OO
< 1.1 E+01
< 5.3E+OO
< 6.0E+OO
< 2.8E+01
< 8.3E+OO MW-185 11/08/18 pCi/L
< 6.0E+OO
< 4.9E+OO
< 1.3E+01
< 5.7E+OO
< 1.1 E+01
< 7.1 E+OO
< 1.1E+01
< 1.3E+01
< 6.3E+OO
< 5.9E+OO
< 3.3E+01
< 1.2E+01 MW-185 11/08/18 pCi/L
< 4.6E+OO
< 5.9E+OO
< 1.5E+01
< 6.4E+OO
< 1.1 E+01
< 6.4E+OO
< 8.3E+OO
< 9.3E+OO
< 7.7E+OO
< 5.5E+OO
< 3.1 E+01
< 1.2E+01 MW-188 11/08/18 pCi/L
< 2.8E+OO
< 3.2E+OO
< 6.5E+OO
< 2.7E+OO
< 5.9E+OO
< 3.1E+OO
< 4.7E+OO
< 8.5E+OO
< 3.3E+OO
< 3.0E+OO
< 1.9E+01
< 5.5E+OO MW-205 11/08/18 pCi/L
< 4.3E+OO
< 4.5E+OO
< 9.2E+OO
< 4.7E+OO
< 6.7E+OO
< 4.5E+OO
< 7.9E+OO
< 1.4E+01
< 4.6E+OO
< 4.4E+OO
< 2.5E+01
< 1.1 E+01
RBG-47951 Rev.2018 Page 65 of 75 Annual Radioactive Effluent Release Report Page 19 of 29 Groundwater Monitoring Well Sampling Results Table 17, Gamma Isotopic Results Station ID Sample Date Units MN-54 C0-58 FE-59 C0-60 ZN-65 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 MW-207 11/08/18 pCi/L
< 5.2E+OO
< 6.0E+OO
< 1.5E+01
< 6.0E+OO
< 1.2E+01
< 5.8E+OO
< 8.SE+OO
< 1.1 E+01
< 5.SE+OO
< 5.SE+OO
< 2.7E+01
< 7.7E+OO MW-209 11/08/18 pCi/L
< 2.4E+OO
< 2.4E+OO
< 5.1E+OO
< 2.4E+OO
< 5.1E+OO
< 2.SE+OO
< 4.4E+OO
< 5.7E+OO
< 2.7E+OO
< 2.4E+OO
< 1.3E+01
< 4.7E+OO MW-213 11/08/18 pCi/L
< 4.8E+OO
< 5.1E+OO
< 1.1 E+01
< 5.6E+OO
< 1.1 E+01
< 6.2E+OO
< 1.0E+01
< 1.5E+01
< 5.9E+OO
< 5.1E+OO
< 3.4E+01
< 1.0E+01 MW-215 11/08/18 pCi/L
< 5.3E+OO
< 4.9E+OO
< 1.2E+01
< 7.6E+OO
< 1.4E+01
< 7.7E+OO
< 1.2E+01
< 1.3E+01
< 5.8E+OO
< 6.1E+OO
< 3.6E+01
< 1.2E+01 MW-217 11/08/18 pCi/L
< 6.7E+OO
< 6.SE+OO
< 1.4E+01
< 7.4E+OO
< 1.6E+01
< 7.4E+OO
< 1.1 E+01
< 1.2E+01
< 7.1E+OO
< 7.SE+OO
< 3.2E+01
< 1.2E+01 MW-219 11/08/18 pCi/L
< 3.SE+OO
< 4.1E+OO
< 9.2E+OO
< 4.4E+OO
< 6.9E+OO
< 4.1E+OO
< 5.0E+OO
< 1.1 E+01
< 4.2E+OO
< 4.0E+OO
< 2.3E+01
< 9.9E+OO MW-221 11/08/18 pCi/L
< 2.1E+OO
< 2.1E+OO
< 4.3E+OO
< 2.2E+OO
< 4.1E+OO
< 2.3E+OO
< 3.9E+OO
< 4.9E+OO
< 2.3E+OO
< 2.1E+OO
< 1.2E+01
< 4.3E+OO MW-223 11/08/18 pCi/L
< 5.8E+OO
< 5.3E+OO
< 1.2E+01
< 5.8E+OO
< 1.2E+01
< 5.9E+OO
< 1.1E+01
< 1.1 E+01
< 6.2E+OO
< 5.SE+OO
< 3.3E+01
< 1.2E+01 MW-227 11/08/18 pCi/L
< 5.3E+OO
< 6.0E+OO
< 1.3E+01
< 5.SE+OO
< 1.2E+01
< 6.9E+OO
< 1.2E+01
< 1.4E+01
< 6.6E+OO
< 5.9E+OO
< 3.5E+01
< 1.2E+01 MW-229 11/08/18 pCi/L
< 5.2E+OO
< 4.SE+OO
< 1.2E+01
< 7.7E+OO
< 1.6E+01
< 6.8E+OO
< 9.8E+OO
< 1.1 E+01
< 5.6E+OO
< 5.8E+OO
< 2.9E+01
< 6.7E+OO MW-231 11/08/18 pCi/L
< 2.7E+OO
< 2.9E+OO
< 6.4E+OO
< 3.0E+OO
< 6.0E+OO
< 3.3E+OO
< 5.9E+OO
< 8.9E+OO
< 3.1E+OO
< 3.3E+OO
< 2.1 E+01
< 5.9E+OO MW-235 11/08/18 pCi/L
< 2.SE+OO
< 2.8E+OO
< 6.7E+OO
< 2.7E+OO
< 5.0E+OO
< 3.0E+OO
< 5.0E+OO
< 9.3E+OO
< 3.0E+OO
< 2.SE+OO
< 1.9E+01
< 6.4E+OO SW-104 11/08/18 pCi/L
< 2.6E+OO
< 2.7E+OO
< 6.1E+OO
< 3.2E+OO
< 5.2E+OO
< 2.6E+OO
< 4.7E+OO
< 5.SE+OO
< 2.8E+OO
< 2.4E+OO
< 1.4E+01
< 5.0E+OO T-14 11/08/18 pCi/L
< 2.SE+OO
< 2.4E+OO
< 5.7E+OO
< 2.6E+OO
< 5.4E+OO
< 2.7E+OO
< 4.3E+OO
< 5.3E+OO
< 2.8E+OO
< 2.7E+OO
< 1.4E+01
< 4.3E+OO Table 18, Hard to Detect Nuclides Station ID Sample Date Units FE-55 Nl-63 SR-89 SR-90 CM-242 CM-243/244 PU-238 MW-158 02/08/18 pCi/L
< 1.1 E+02
< 2.0E+01
< 9.3E+OO
< 2.6E+OO
< 2.9E-02
< 8.1 E-02
< 1.3E-01
RBG-47951 Rev.2018 Page 66 of 75 Annual Radioactive Effluent Release Report Page 20 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-104 02/06/18 pCi/L
< 6.9E+02 MW-185 05/17/18 pCi/L
< 6.8E+02 MW-104 02/06/18 pCi/L
< 6.9E+02 MW-188 05/17/18 pCi/L
< 6.6E+02 MW-106 02/06/18 pCi/L
< 6.9E+02 MW-209 05/17/18 pCi/L
< 5.9E+02 MW-110 02/06/18 pCi/L 6.10E+04 MW-221 05/17/18 pCi/L
< 6.1 E+02 MW-112 02/06/18 pCi/L 5.80E+03 PZ-03 05/17/18 pCi/L
< 6.6E+02 MW-114 02/06/18 pCi/L 2.70E+03 SW-101 05/17/18 pCi/L
< 6.5E+02 MW-116 02/06/18 pCi/L 1.40E+04 SW-102 05/17/18 pCi/L
< 6.4E+02 MW-116 02/06/18 pCi/L 1.30E+04 SW-103 05/17/18 pCi/L
< 6.3E+02 MW-118 02/06/18 pCi/L 2.80E+03 SW-104 05/17/18 pCi/L
< 6.4E+02 MW-124 02/06/18 pCi/L 1.80E+04 MW-124 08/21/18 pCi/L 9.60E+04 MW-137 02/06/18 pCi/L 2.50E+04 MW-125 08/21/18 pCi/L 3.60E+05 MW-137 02/06/18 pCi/L 2.70E+04 MW-142 08/21/18 pCi/L
< 6.6E+02 MW-139 02/06/18 pCi/L 1.00E+03 MW-144 08/21/18 pCi/L 1.40E+03 MW-141 02/06/18 pCi/L 2.70E+03 MW-146 08/21/18 pCi/L 1.40E+05 MW-153 02/06/18 pCi/L 1.30E+03 MW-147 08/21/18 pCi/L 1.40E+04 MW-161 02/06/18 pCi/L 3.60E+03 MW-148 08/21/18 pCi/L 4.30E+03 MW-178 02/06/18 pCi/L 8.00E+03 MW-151 08/21/18 pCi/L
< 6.6E+02
RBG-47951 Rev.2018 Page 67 of 75 Annual Radioactive Effluent Release Report Page 21 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-179 02/06/18 pCi/L 3.30E+05 MW-155 08/21/18 pCi/L 7.60E+04 MW-186 02/06/18 pCi/L
< 6.9E+02 MW-156 08/21/18 pCi/L 2.60E+03 MW-187 02/06/18 pCi/L
< 6.8E+02 MW-157 08/21/18 pCi/L 1.50E+05 MW-05 02/07/18 pCi/L
< 6.7E+02 MW-158 08/21/18 pCi/L 3.90E+05 MW-06 02/07/18 pCi/L
< 6.9E+02 MW-159 08/21/18 pCi/L 1.60E+03 MW-06 02/07/18 pCi/L
< 6.9E+02 MW-159 08/21/18 pCi/L 1.40E+03 MW-08 02/07/18 pCi/L
< 6.9E+02 MW-162 08/21/18 pCi/L
< 6.7E+02 MW-103 02/07/18 pCi/L
< 5.2E+02 MW-164 08/21/18 pCi/L
< 6.5E+02 MW-107 02/07/18 pCi/L
< 6.9E+02 MW-165 08/21/18 pCi/L
< 6.6E+02 MW-108 02/07/18 pCi/L
< 6.8E+02 MW-169 08/21/18 pCi/L
< 6.7E+02 MW-111 02/07/18 pCi/L
< 6.9E+02 MW-178 08/21/18 pCi/L 1.40E+04 MW-120 02/07/18 pCi/L
< 6.6E+02 MW-179 08/21/18 pCi/L 4.20E+05 MW-120 02/07/18 pCi/L
< 6.8E+02 MW-186 08/21/18 pCi/L
< 6.5E+02 MW-122R 02/07/18 pCi/L
< 6.9E+02 MW-187 08/21/18 pCi/L
< 6.7E+02 MW-125 02/07/18 pCi/L 3.10E+05 MW-201 08/21/18 pCi/L
< 6.8E+02 MW-14 02/07/18 pCi/L
< 6.4E+02 MW-203 08/21/18 pCi/L
< 6.8E+02 MW-151 02/07/18 pCi/L
< 6.6E+02 MW-215 08/21/18 pCi/L
< 6.9E+02
RBG-47951 Rev.2018 Page 68 of 75 Annual Radioactive Effluent Release Report Page 22 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-155 02/07/18 pCi/L 1.90E+05 MW-217 08/21/18 pCi/L
< 6.7E+02 MW-155 02/07/18 pCi/L 2.00E+05 MW-100 08/22/18 pCi/L
< 6.7E+02 MW-156 02/07/18 pCi/L 2.30E+03 MW-110 08/22/18 pCi/L 5.00E+04 MW-157 02/07/18 pCi/L 1.30E+05 MW-112 08/22/18 pCi/L 7.30E+03 MW-165 02/07/18 pCi/L
< 7.0E+02 MW-114 08/22/18 pCi/L 2.40E+03 MW-170 02/07/18 pCi/L
< 6.9E+02 MW-116 08/22/18 pCi/L 7.60E+03 MW-180 02/07/18 pCi/L
< 6.5E+02 MW-118 08/22/18 pCi/L 3.00E+03 MW-207 02/07/18 pCi/L
< 5.3E+02 MW-137 08/22/18 pCi/L 2.70E+04 MW-209 02/07/18 pCi/L
< 6.3E+02 MW-139 08/22/18 pCi/L 1.20E+03 MW-211 02/07/18 pCi/L
< 5.3E+02 MW-141 08/22/18 pCi/L 2.90E+03 MW-213 02/07/18 pCi/L
< 5.2E+02 MW-153 08/22/18 pCi/L 1.20E+03 MW-217 02/07/18 pCi/L
< 5.3E+02 MW-153 08/22/18 pCi/L 1.90E+03 PZ-01 02/07/18 pCi/L 5.30E+04 MW-161 08/22/18 pCi/L 1.20E+03 SW-101 02/07/18 pCi/L
< 6.6E+02 MW-170 08/22/18 pCi/L
< 6.6E+02 MW-100 02/08/18 pCi/L
< 6.8E+02 MW-182 08/22/18 pCi/L
< 6.5E+02 MW-126 02/08/18 pCi/L
< 6.5E+02 MW-188 08/22/18 pCi/L
< 6.5E+02 MW-128 02/08/18 pCi/L
< 6.5E+02 MW-205 08/22/18 pCi/L
< 6.8E+02
RBG-47951 Rev.2018 Page 69 of 75 Annual Radioactive Effluent Release Report Page 23 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-128 02/08/18 pCi/L
< 6.5E+02 MW-207 08/22/18 pCi/L
< 6.6E+02 MW-130 02/08/18 pCi/L
< 6.6E+02 MW-209 08/22/18 pCi/L
< 6.6E+02 MW-130 02/08/18 pCi/L
< 6.5E+02 MW-211 08/22/18 pCi/L
< 6.7E+02 MW-131 02/08/18 pCi/L
< 6.8E+02 MW-211 08/22/18 pCi/L
< 6.7E+02 MW-132 02/08/18 pCi/L
< 6.6E+02 MW-213 08/22/18 pCi/L
< 6.8E+02 MW-134 02/08/18 pCi/L
< 6.9E+02 MW-213 08/22/18 pCi/L
< 6.8E+02 MW-142 02/08/18 pCi/L
< 6.9E+02 MW-221 08/22/18 pCi/L
< 6.6E+02 MW-144 02/08/18 pCi/L 8.30E+02 MW-227 08/22/18 pCi/L
< 6.7E+02 MW-146 02/08/18 pCi/L 2.00E+05 MW-229 08/22/18 pCi/L
< 6.7E+02 MW-147 02/08/18 pCi/L 1.90E+05 MW-229 08/22/18 pCi/L
< 6.6E+02 MW-148 02/08/18 pCi/L
< 6.8E+02 MW-231 08/22/18 pCi/L
< 6.7E+02 MW-158 02/08/18 pCi/L 7.00E+05 PZ-01 08/22/18 pCi/L 5.40E+04 MW-159 02/08/18 pCi/L 2.80E+03 MW-219 08/23/18 pCi/L
< 6.6E+02 MW-162 02/08/18 pCi/L
< 6.9E+02 MW-223 08/23/18 pCi/L
< 6.9E+02 MW-164 02/08/18 pCi/L
< 4.8E+02 MW-225 08/23/18 pCi/L
< 6.7E+02 MW-167 02/08/18 pCi/L
< 6.8E+02 MW-233 08/23/18 pCi/L
< 6.7E+02 MW-169 02/08/18 pCi/L
< 5.3E+02 MW-235 08/23/18 pCi/L
< 6.8E+02
RBG-47951 Rev.2018 Page 70 of 75 Annual Radioactive Effluent Release Report Page 24 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-172 02/08/18 pCi/L
< 6.5E+02 SW-103 08/23/18 pCi/L
< 6.8E+02 MW-174 02/08/18 pCi/L
< 6.9E+02 MW-148 09/10/18 pCi/L 5.50E+03 MW-182 02/08/18 pCi/L
< 6.9E+02 MW-112 11/06/18 pCi/L 5.70E+03 MW-185 02/08/18 pCi/L
< 6.8E+02 MW-114 11/06/18 pCi/L 1.80E+03 MW-188 02/08/18 pCi/L
< 6.8E+02 MW-116 11/06/18 pCi/L 9.40E+03 MW-205 02/08/18 pCi/L
< 5.3E+02 MW-118 11/06/18 pCi/L 2.70E+03 MW-215 02/08/18 pCi/L
< 5.2E+02 MW-139 11/06/18 pCi/L 1.20E+03 MW-219 02/08/18 pCi/L
< 5.2E+02 MW-141 11/06/18 pCi/L 2.50E+03 PZ-03 02/08/18 pCi/L
< 6.8E+02 MW-142 11/06/18 pCi/L
< 6.6E+02 SW-102 02/08/18 pCi/L
< 6.8E+02 MW-144 11/06/18 pCi/L
< 6.3E+02 SW-103 02/08/18 pCi/L
< 6.6E+02 MW-146 11/06/18 pCi/L 1.80E+05 SW-104 02/08/18 pCi/L
< 6.6E+02 MW-147 11/06/18 pCi/L 9.60E+04 MW-201 02/20/18 pCi/L
< 6.5E+02 MW-148 11/06/18 pCi/L 7.80E+03 MW-203 02/20/18 pCi/L
< 6.6E+02 MW-158 11/06/18 pCi/L 5.50E+05 MW-221 02/21/18 pCi/L
< 6.4E+02 MW-159 11/06/18 pCi/L 2.00E+03 MW-223 02/22/18 pCi/L
< 6.7E+02 MW-159 11/06/18 pCi/L 2.10E+03 MW-225 04/11/18 pCi/L
< 6.0E+02 MW-161 11/06/18 pCi/L 7.90E+02
RBG-47951 Rev.2018 Page 71 of 75 Annual Radioactive Effluent Release Report Page 25 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-227 04/11/18 pCi/L
< 6.1E+02 MW-162 11/06/18 pCi/L
< 6.6E+02 MW-229 04/11/18 pCi/L
< 6.0E+02 MW-178 11/06/18 pCi/L 8.40E+03 MW-233 04/11/18 pCi/L
< 5.9E+02 MW-179 11/06/18 pCi/L 4.10E+05 MW-235 04/11/18 pCi/L
< 6.0E+02 MW-179 11/06/18 pCi/L 4.10E+05 MW-231 05/01/18 pCi/L
< 6.2E+02 MW-201 11/06/18 pCi/L
< 6.5E+02 MW-155 05/10/18 pCi/L 8.40E+04 MW-203 11/06/18 pCi/L
< 6.6E+02 MW-155 05/10/18 pCi/L 8.50E+04 MW-05 11/07/18 pCi/L
< 6.6E+02 MW-169 05/10/18 pCi/L
< 6.0E+02 MW-100 11/07/18 pCi/L
< 6.2E+02 MW-211 05/10/18 pCi/L
< 6.0E+02 MW-110 11/07/18 pCi/L 4.00E+04 MW-215 05/10/18 pCi/L
< 6.0E+02 MW-124 11/07/18 pCi/L 7.60E+04 MW-229 05/10/18 pCi/L
< 6.1E+02 MW-124 11/07/18 pCi/L 7.80E+04 MW-142 05/15/18 pCi/L
< 6.6E+02 MW-125 11/07/18 pCi/L 4.20E+05 MW-144 05/15/18 pCi/L 1.80E+03 MW-126 11/07/18 pCi/L
< 5.8E+02 MW-146 05/15/18 pCi/L 1.20E+05 MW-126 11/07/18 pCi/L
< 6.6E+02 MW-147 05/15/18 pCi/L 1.40E+04 MW-137 11/07/18 pCi/L 1.60E+04 MW-148 05/15/18 pCi/L
< 6.7E+02 MW-151 11/07/18 pCi/L
< 6.3E+02 MW151 05/15/18 pCi/L
< 6.3E+02 MW-153 11/07/18 pCi/L 1.40E+03
RBG-47951 Rev.2018 Page 72 of 75 Annual Radioactive Effluent Release Report Page 26 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-158 05/15/18 pCi/L 4.10E+05 MW-155 11/07/18 pCi/L 1.40E+05 MW-159 05/15/18 pCi/L 1.50E+03 MW-156 11/07/18 pCi/L 2.60E+03 MW-159 05/15/18 pCi/L 1.40E+03 MW-157 11/07/18 pCi/L 1.70E+05 MW-162 05/15/18 pCi/L
< 6.4E+02 MW-164 11/07/18 pCi/L
< 6.3E+02 MW-164 05/15/18 pCi/L
< 6.8E+02 MW-165 11/07/18 pCi/L
< 6.5E+02 MW-165 05/15/18 pCi/L
< 6.6E+02 MW-172 11/07/18 pCi/L
< 6.3E+02 MW-178 05/15/18 pCi/L 1.40E+04 MW-180 11/07/18 pCi/L
< 6.3E+02 MW-179 05/15/18 pCi/L 3.80E+05 MW-182 11/07/18 pCi/L
< 6.3E+02 MW-186 05/15/18 pCi/L
< 6.5E+02 MW-186 11/07/18 pCi/L
< 6.5E+02 MW-187 05/15/18 pCi/L
< 6.4E+02 MW-187 11/07/18 pCi/L
< 6.5E+02 MW-201 05/15/18 pCi/L
< 6.1 E+02 MW-211 11/07/18 pCi/L
< 6.3E+02 MW-203 05/15/18 pCi/L
< 6.1E+02 MW-225 11/07/18 pCi/L
< 6.5E+02 MW-110 05/16/18 pCi/L 4.20E+04 MW-233 11/07/18 pCi/L
< 6.5E+02 MW-112 05/16/18 pCi/L 6.70E+03 PZ-01 11/07/18 pCi/L 5.90E+04 MW-112 05/16/18 pCi/L 6.20E+03 PZ-03 11/07/18 pCi/L
< 6.5E+02 MW-114 05/16/18 pCi/L 1.40E+03 MW-04 11/08/18 pCi/L
< 6.5E+02 MW-116 05/16/18 pCi/L 4.40E+03 MW-08 11/08/18 pCi/L
< 6.6E+02
RBG-47951 Rev.2018 Page 73 of 75 Annual Radioactive Effluent Release Report Page 27 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-124 05/16/18 pCi/L 1.00E+05 MW-103 11/08/18 pCi/L
< 6.4E+02 MW-125 05/16/18 pCi/L 3.10E+05 MW-104 11/08/18 pCi/L
< 6.3E+02 MW-137 05/16/18 pCi/L 1.90E+04 MW-106 11/08/18 pCi/L
< 6.3E+02 MW-139 05/16/18 pCi/L 7.80E+02 MW-107 11/08/18 pCi/L
< 6.6E+02 MW-141 05/16/18 pCi/L 2.50E+03 MW-108 11/08/18 pCi/L
< 6.3E+02 MW-156 05/16/18 pCi/L 2.40E+03 MW-111 11/08/18 pCi/L
< 6.5E+02 MW-157 05/16/18 pCi/L 1.50E+05 MW-120 11/08/18 pCi/L
< 6.5E+02 MW-161 05/16/18 pCi/L 1.50E+03 MW-122R 11/08/18 pCi/L
< 6.5E+02 MW-205 05/16/18 pCi/L
< 6.2E+02 MW-128 11/08/18 pCi/L
< 6.3E+02 MW-207 05/16/18 pCi/L
< 6.2E+02 MW-130 11/08/18 pCi/L
< 6.6E+02 MW-213 05/16/18 pCi/L
< 6.1E+02 MW-131 11/08/18 pCi/L
< 6.6E+02 MW-217 05/16/18 pCi/L
< 6.2E+02 MW-132 11/08/18 pCi/L
< 6.3E+02 MW-219 05/16/18 pCi/L
< 6.1E+02 MW-134 11/08/18 pCi/L
< 6.4E+02 MW-223 05/16/18 pCi/L
< 6.2E+02 MW-14 11/08/18 pCi/L
< 6.3E+02 MW-225 05/16/18 pCi/L
< 6.1E+02 MW-167 11/08/18 pCi/L
< 6.6E+02 MW-225 05/16/18 pCi/L
< 6.2E+02 MW-169 11/08/18 pCi/L
< 6.2E+02 MW-227 05/16/18 pCi/L
< 6.1E+02 MW-170 11/08/18 pCi/L
< 6.3E+02
RBG-47951 Rev.2018 Page 74 of 75 Annual Radioactive Effluent Release Report Page 28 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-231 05/16/18 pCi/L
< 6.3E+02 MW-170 11/08/18 pCi/L
< 5.8E+02 MW-233 05/16/18 pCi/L
< 6.2E+02 MW-174 11/08/18 pCi/L
< 6.4E+02 MW-235 05/16/18 pCi/L
< 6.1E+02 MW-174 11/08/18 pCi/L
< 6.3E+02 PZ-01 05/16/18 pCi/L 5.60E+04 MW-18 11/08/18 pCi/L
< 6.6E+02 MW-100 05/17/18 pCi/L
< 6.6E+02 MW-18 11/08/18 pCi/L
< 6.6E+02 MW-106 05/17/18 pCi/L
< 6.3E+02 MW-185 11/08/18 pCi/L
< 6.5E+02 MW-106 05/17/18 pCi/L
< 6.4E+02 MW-185 11/08/18 pCi/L
< 6.5E+02 MW-118 05/17/18 pCi/L 2.40E+03 MW-188 11/08/18 pCi/L
< 6.3E+02 MW-120 05/17/18 pCi/L
< 6.7E+02 MW-205 11/08/18 pCi/L
< 6.3E+02 MW-122R 05/17/18 pCi/L
< 6.7E+02 MW-207 11/08/18 pCi/L
< 6.5E+02 MW-126 05/17/18 pCi/L
< 6.7E+02 MW-209 11/08/18 pCi/L
< 6.5E+02 MW-126 05/17/18 pCi/L
< 6.7E+02 MW-213 11/08/18 pCi/L
< 6.3E+02 MW-128 05/17/18 pCi/L
< 6.7E+02 MW-215 11/08/18 pCi/L
< 6.6E+02 MW-130 05/17/18 pCi/L
< 6.3E+02 MW-217 11/08/18 pCi/L
< 6.5E+02 MW-131 05/17/18 pCi/L
< 6.4E+02 MW-219 11/08/18 pCi/L
< 6.4E+02 MW-132 05/17/18 pCi/L
< 6.6E+02 MW-221 11/08/18 pCi/L
< 6.6E+02 MW-134 05/17/18 pCi/L
< 6.7E+02 MW-223 11/08/18 pCi/L
< 6.5E+02
RBG-47951 Rev.2018 Page 75 of 75 Annual Radioactive Effluent Release Report Page 29 of 29 Groundwater Monitoring Well Sampling Results Table 19, Tritium Analysis Results Station ID Start Date Units H-3 Station ID Start Date Units H-3 MW-153 05/17/18 pCi/L 1.00E+03 MW-227 11/08/18 pCi/L
< 6.3E+02 MW-167 05/17/18 pCi/L
< 6.5E+02 MW-229 11/08/18 pCi/L
< 6.5E+02 MW-170 05/17/18 pCi/L
< 6.6E+02 MW-231 11/08/18 pCi/L
< 6.4E+02 MW172 05/17/18 pCi/L
< 6.7E+02 MW-235 11/08/18 pCi/L
< 6.4E+02 MW-174 05/17/18 pCi/L
< 6.7E+02 SW-104 11/08/18 pCi/L
< 6.5E+02 MW-180 05/17/18 pCi/L
< 6.6E+02 T-14 11/08/18 pCi/L
< 6.5E+02 MW-182 05/17/18 pCi/L
< 6.7E+02