RA-19-022, Annual Radiological Groundwater Protection Program Report 2018

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Annual Radiological Groundwater Protection Program Report 2018
ML19126A089
Person / Time
Site: Oyster Creek
Issue date: 04/30/2019
From:
Exelon Generation Co, Teledyne Brown Engineering Environmental Services
To:
Office of Nuclear Reactor Regulation
References
RA-19-022
Download: ML19126A089 (43)
v • d • e


Text

Docket No: 50-219 OYSTER CREEK GENERATING STATION UNIT 1 Annual Radiological Groundwater Protection Program Report 1 January through 31 December 2018 Prepared By Teledyne Brown Engineering Environmental Services

) 6-" Exelon Generation Oyster Creek Generating Station Forked River, NJ 08731 April 2019

Table of Contents I. Summary and Conclusions .............................................................................................. 1 II. Introduction ..................................................................................................................... 3 A. Objectives of the RGPP ...................................................................................... 4

8. Implementation of the Objectives ........................................................................ 6 C. Program Description ........................................................................................... 6 D. Characteristics of Tritium (H-3) ........................................................................... 7 111. Program Description ...................................................................................................... 7 A. Sample Analysis .................................................................................................. 7
8. Data Interpretation ............................................................................................... 8 C. Background Analysis ........................................................................................... 9 IV. Results and Discussion ............................................................................................... 11 A. Program Exceptions .......................................................................................... 11
8. Groundwater Results ......................................................................................... 11 C. Surface Water Results ...................................................................................... 12 D. Precipitation Water Results ............................................................................... 12 E. Summary of Results - Inter-laboratory Comparison Program .......................... 13 F. Leaks, Spills, and Releases .............................................................................. 13 G. Trends ............................................................................................................... 13 H. Investigations ............................................................................ :....................... 13 I. Actions Taken ..................................................................................................... 13 V. References ................................................................................................................... 14

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Figures Figure A-1 Sampling locations - Selected Cohansey and Cape May Formation Wells, Oyster Creek Generating Station, 2018 Security-Related Information: Detailed maps of the Oyster Creek Generating Station have been withheld from public disclosure under 10 CFR 2.390 and N.J.S.A. 47:1A-1.1 Appendix B Data Tables Tables Table B.-1.1 Concentrations of Tritium, Strontium, Gross Alpha and Gross Beta in Groundwater Samples C0llected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-1.2 Concentrations of Gamma Emitters in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-1.3 Concentrations of Hard-To-Detects in Groundwater Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-11.1 Concentrations of Tritium in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-11.3 Concentrations of Hard-To-Detects in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 Table B-111.1 Concentrations of Tritium in Precipitation Water Samples Collected as Part of the Radiological Groundwater Protection Program, Oyster Creek Generating Station, 2018 ii

I. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP) conducted for the Oyster Creek Generating Station (OCGS) by Exelon Generation Company LLC (Exelon) covers the period 01 January 2018 through 31 December 2018.

This report covers groundwater and surface water samples collected from the environment, both on and off station property in 2018. In 2018, 761 analyses were performed on 271 samples from 63 locations.

There were three inadvertent releases of contaminated water into the groundwater during 2009 resulting in a plume located west of the turbine building, which is monitored via a series of monitoring wells.

Gamma-emitting radionuclide Potassium-40 (K-40) was detected in 2 of the 63 groundwater well samples. The concentrations ranged from 65 to 73 pCi/L.

K-40 was detected in 3 of 4 surface water samples. The concentrations ranged from 186 to 237 pCi/L. Tritium concentrations have decreased substantially since 2009.

In the case of tritium, Exelon specified that its laboratories achieve a lower limit of detection 100 times lower than the drinking water limit specified by the United States Environmental Protection Agency (USEPA) (200 pCi/1 versus 20,000 pCi/1).

As expected, tritium was detected in groundwater samples. The 2018 Tritium concentrations varied from <174 to 3,030 pCi/1. The well with the highest concentration was MW-571.

No detectable tritium (greater than the MDC) was found in surface water samples collected from onsite and offsite monitoring locations during 2018.

Tritium was detected in one of the 20 precipitation water samples at a concentration of 304 pCi/L.

Strontium-89 (Sr-89) and Strontium-90 (Sr-90) were not detected in any groundwater samples during 2018.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second quarter sampling in 2018. There were 56 samples taken from 50 groundwater well locations. Gross Alpha (dissolved) was detected in 7 samples. The concentrations ranged from 0.4 to 3.9 pCi/L. Gross Alpha (suspended) was detected in 8 samples and ranged from 2.0 to 8.4 pCi/L. Gross Beta (dissolved) was detected in 47 samples and ranged from 0.9 to 31.5 pCi/L. Gross Beta (suspended) was detected in 12 samples and ranged from 1.8 to 13.5 pCi/L.

-- __J

"Hard-To-Detect" analyses were performed on a select group of groundwater locations. The analyses for groundwater included Americium-241 (Am-241 ),

Cerium-242 (Cm-242), Cerium-243/244 (Cm-243/244), Plutonium-238 (Pu-238),

Plutonium-239/240 (Pu-239/240), Uranium-234 (U-234), Uranium-235 (U-235),

Uranium-238 (U-238), lron-55 (Fe-55), and Nickel-63 (Ni-63). All Hard-To-Detect

  • analyses were less than the MDC. Occasionally the isotopes of U-234 and U-238 are detected and are considered background.

II. Introduction The Oyster Creek Nuclear Generating Station consists of a single boiling water reactor (BWR) and turbine generator was capable of producing 650 megawatts of electricity. The Station operates under Nuclear Regulatory Commission (NRC) renewed facility operating license number DPR-16. Brackish water from Barnegat Bay is supplied to the circulating water system. The circulating water system is designed to supply a continuous flow of water from Barnegat Bay through the plant to remove the waste heat released by the power cycle in the Main Condenser. The circulating water system is comprised of the intake canal from Barnegat Bay to the plant, the Main Condenser Circulating Water System, the dilution plant, and the discharge canal to Barnegat Bay. The dilution plant portion of the system minimizes the adverse effects of hot discharge water on aquatic life in the discharge canal and Barnegat Bay to meet the conditions of the Oyster Creek New Jersey Pollutant Discharge Elimination system (NJPDES)

Permit No. NJ0005550. Approximately 1 million gallons per minute of water were withdrawn, and reduced to 125,000 gpm by the end of 2018, from the intake canal for dilution and station use and returned to the discharge canal.

The Station is located in the Atlantic Coastal Plain physiographic province.

Topography in the region of the Station is a slightly undulating coastal plain having low relief. The land surface gradually rises from sea level at Barnegat Bay, which is located east of the Station, to approximately 50 feet above mean sea level (AMSL) 2 miles inland. This region of the coastal plain has numerous tidal marshes and is incised by easterly flowing streams and creeks. Elevations at the Station property west of Route 9 range from approximately Oto 15 feet AMSL immediately adjacent to the intake and discharge canals to slightly more than 30 feet AMSL in the northwest portion of the Station property. The 132-acre developed portion of the Site located within the "horseshoe" formed by the intake and discharge canals west of Route 9 has an approximate average elevation of 20 feet AMSL. In the immediate vicinity of the intake and discharge canals, the Station property slopes steeply down to the canal. The average elevation of the surface water level in the intake and discharge canals is approximately 1-foot AMSL. The remaining 637-acre portion of the property located east of Route 9 is primarily vegetated and undeveloped. The ground surface is relatively level except for the steep slopes at areas adjacent to the intake and discharge canals.

The three shallowest stratigraphic units in the vicinity of the Oyster Creek area in descending order are the Cape May Formation, the Cohansey Formation, and the Kirkwood Formation. Some of the Station structures are constructed to depths of approximately 50 feet below ground surface (bgs). Excavations were completed from grade, through the fill, Cape May Formation, Upper Clay, and into the Cohansey Formation during construction. Consequently, the bottoms of some Station structures are completed within the Cohansey Formation and some structures breach the Upper Clay.

The Cape May Formation regionally has an average thickness of 40 feet and at OCGS, the Cape May is described as a light gray to tan, medium- to fine-grained sand, with trace to some silt and occasional coarse sand. It is generally poorly compacted. The Cape May Formation varies from Oto 21 feet in thickness based on historical boring logs. The variation principally is due to the varying amount of material excavated and replaced by fill during Station construction.

When present, the thickness of the Cape May generally ranges from 15 to 20 feet thick. The base of the Cape May generally is defined by the presence of a dark clay unit referred to as the Upper Clay unit. The Upper Clay is a stiff to hard, gray, plastic organic clay containing inclusions (also described as lenses or partings) of dense fine sand with trace to some organic silt. The deposits of fine sand within the Upper Clay layer have high relative d.ensities and occur as lenses or inclusions.

The Cohansey Formation is primarily composed of a light-colored, fine- to very coarse-grained quartzose sand with lenses of silt and clay. Although most borings at the Station do not penetrate the entire Cohansey Formation, this formation appears to be approximately 60 to 80 feet thick at OCGS. A clay sequence, referred to at the Station as the "Lower Clay", marks the base of the Cohansey, which generally is present to approximately 90 to 100 feet bgs. The lower clay is a dense gray medium- to fine-grained sand containing trace to some organic silt and layers or inclusions of very stiff to hard gray organic clay.

The thickness of the lower clay is estimated to be approximately 10 to 20 feet in the vicinity of OCGS.

The Cohansey Formation is underlain by the Kirkwood Formation which consists of several stratigraphic units. The Kirkwood Formation is described as a medium- to fine-grained sand with trace silt. The thickness of this formation beneath the Station is unknown. The south domestic supply well terminates in the Kirkwood at a depth of 310 feet bgs. The Kirkwood thickness in Ocean County ranges from approximately 300 to 400 feet.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) and Environmental Inc. (Midwest Labs) on samples collected in 2018.

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

  • Ensure that the site characterization of geology and hydrology provides an understanding of predominant ground water gradients based upon current site conditions
  • Identify site risk based on plant design and work practices
  • Evaluate all SSCs that contain or could contain licensed material and for which there is a credible mechanism for the licensed material to reach groundwater
  • Evaluate work practices that involve licensed material and for which there is a credible mechanism for the licensed material to reach groundwater
  • Perform on-site monitoring to ensure timely detection of inadvertent radiological releases to ground water
  • Understand background concentrations of radioactive analytes outside of the REMP, as required
  • Evaluate return/re-use of previously discharged radioactive effluents in gaseous or liquid effluents that are returned from the environment to the operating nuclear power facility
  • Ensure controls are established for the selection, installation and retirement of monitoring wells
  • Perform remediation protocols to prevent migration of licensed material off-site and to minimize decommissioning impacts
  • Ensure that records of leaks, spills, remediation efforts are retained and retrievable to meet the requirements of 10 CFR 50.75(g)
  • Ensure periodic communications are held on the RGPP with the designated State/Local officials
  • Ensure timely verbal and written reporting occurs if there is an inadvertent release of licensed materials to the soil, groundwater or surface water
  • Document and report all applicable RGPP data
  • Identify and resolve deficiencies via the Corrective Action Process as delineated in Pl- DC-125, "Decommissioning Corrective Action Program"
  • Perform program oversight to ensure effective implementation of the voluntary RGPP B. Implementation of the Objectives The objectives identified have been implemented at the Oyster Creek Generating Station through compliance with approved procedures EN-AA-408-4000, Radiological Groundwater Protection Program Implementation, and site specific procedure EN-OC-408-4160, RGPP Reference Material; for Oyster Creek Generating Station.

C. Program Description Samples for the OCGS site were collected for Exelon by on-site personnel and Normandeau Associates, Inc. This section describes the general collection methods used to obtain environmental samples for the OCGS RGPP in 2018. Sample locations can be found in Table A-1, Appendix A.

1. Sample Collection Samples of water are collected, managed, transported and analyzed in accordance with approved procedures. Both groundwater and surface water are collected. Sample locations, sample collection frequencies and analytical frequencies are controlled in accordance with approved station procedures.

Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events.

2. Sample Analysis Samples are analyzed in accordance with approved procedures that are based on industry standards.
3. Quality Control Analytical laboratories are subject to internal quality assurance programs, industry cross-check programs, nuclear industry audits, as well as being certified by the State of New Jersey.
4. Data Interpretation Station personnel review and evaluate all analytical data deliverables as data is received. Analytical data results are reviewed by both station personnel and independent consultants, including a hydrogeologist, for adverse trends or changes to hydrogeologic conditions.

D. Characteristics of Tritium (H-3)

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

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through the skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout the body. Tritium is excreted primarily through urine with a clearance rate characterized by an effective biological half-life of about 10 days.

Tritium is produced naturally in the upper atmosphere when cosmic rays strike air molecules. Tritium is also produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production reactors. Also, tritium was released into the atmosphere from Chernobyl in 1986. Like normal water, tritiated water is colorless and odorless. Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, and therefore tritiated water will travel at the same velocity as the average groundwater velocity.

Tritium has a half-life of approximately 12.3 years. It decays spontaneously to Helium-3 (He-3). This radioactive decay releases a beta particle (18.6 keV low-energy electron). The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous radionuclides because it emits very weak radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.

Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Oyster Creek Generating Station RGPP in 2018. The sampling frequencies are increased if activity is detected.

In order to achieve the stated objectives, the current program includes the following analyses for groundwater, surface water, and precipitation water:

1. Gamma emitters
2. Strontium-89 and Strontium-90
3. Tritium
4. Gross Alpha (Dissolved and Suspended) and Gross Beta (Dissolved and Suspended)
5. Selected transuranics
6. Fe-55
7. Ni-63
8. Data Interpretation The radiological data collected prior to Oyster Creek Generating Station becoming operational, as well as background data from publicly available databases, were used as a baseline with which these operational data were compared. For the purpose of this report, Oyster Creek Generating Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:
1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required OCGS detection capabilities for environmental sample analysis.

The minimum detectable concentration (MDC) is defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal as an after the fact estimate

  • of the presence of activity.
2. Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.

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

Analytical uncertainties are reported at the 95% confidence level.

C. Background Analysis

1. Background Concentrations of Tritium The purpose of the following discussion is to summarize background measurements of tritium in various media performed by others. Additional detail may be found by consulting references.
a. Tritium Production Tritium is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper atmosphere, "cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and Sr-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and peaked in 1963 with the signing of the limited test ban treaty. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment. Also, tritium was released into the atmosphere from Chernobyl in 1986.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. One publicly available database that provides tritium concentrations in precipitation is the USEPA's RadNet database. RadNet provides tritium precipitation concentration data for samples collected at stations throughout the U.S. from 1978 up to and including 1996.

Tritium concentrations in precipitation in New Jersey from 1978 through 1996 have ranged from 600 pCi/1 in 1979 to 0 pCi/1 in 1996, with an average of 185 pCi/1. Water from previous years and decades is naturally captured in groundwater, so some well water sources today are affected by the surface water from the 1960s that was elevated in tritium.

c. Surface Water Data Tritium concentrations are routinely measured in surface

. water bodies, including Oyster Creek and the Delaware River. New Jersey surface water data between 1978 and 1998 averaged 185 pCi/1.

The USEPA Rad Net surface water data typically has a reported 'Combined Standard Uncertainty' of 2 standard deviations. This corresponds to a +/- 36 to +/-100 pCi/1 confidence bound on each given reported measurement so that the typical surface water background data provided by RadNet may be subject to measurement uncertainty of up to 100 pCi/1.

The radio-analytical laboratory counts tritium results to an Exelon-specified LLD of 200 pCi/1 with a typical uncertainty of +/-100 pCi/1. Therefore, sample results reported by TBE near this LLD cannot be distinguished from natural background concentrations in surface water.

IV. Results and Discussion A. Program Exceptions There were no program exceptions in 2018.

B. Groundwater Results Samples were collected from on-site locations in accordance with the station radiological groundwater protection program. As reported in GHD's 2018 Hydrogeologic Investigation Report, groundwater flow in the vicinity of the Torus Water Storage Tank and the Condensate Storage Tank is towards the intake and discharge canals.

Tritium Samples from 52 locations were analyzed for tritium activity (Table B-1.1, Appendix B). Tritium was detected in 14 of 181 samples. The values ranged from <179 to 3,030 pCi/1. The well with the highest concentration was MW-571. (Table B-1.1, Appendix B)

Strontium Strontium-89 and Strontium-90 were not detected in any location sampled in 2018. (Table B-1.1, Appendix B)

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater samples during the second sampling in 2018. There were 56 samples taken from 50 groundwater well locations. Gross Alpha (dissolved) was detected in 7 samples. The concentrations ranged from 0.4 to 3.9 pCi/L. Gross Alpha (suspended) was detected in 8 samples and ranged from 2.0 to 8.4 pCi/L. Gross Beta (dissolved) was detected in 47 samples and ranged from 0.9 to 31.5 pCi/L. Gross Beta (suspended) was detected in 12 samples and ranged from 1.8 to 13.5 pCi/L. (Table B-1.1, Appendix B)

Gamma Emitters Gamma-emitting nuclide K-40 was detected in 2 of 63 samples analyzed during 2018. The concentrations ranged from 65 to 73 pCi/L. (Table B-1.2, Appendix B).

"Hard-To-Detect" "Hard-To-Detect" analyses were performed on a select group of groundwater locations. The analyses for groundwater included Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-234, U-235, U-238, Fe-55, and Ni-63. All Hard-To-Detect analyses were less than the MDC.

Occasionally the isotopes of U-234 and U-238 are detected and are considered background. (Table B-1.3, Appendix B).

C. Surface Water Results Samples were collected from on-site locations in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below:

Tritium Samples from 6 locations were analyzed for tritium activity (Table B-11.1, Appendix B). No detectable tritium (greater than the LLD) was found in any surface water samples collected from onsite and offsite monitoring locations.

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions are not required on a routine basis and were not analyzed in 2018.

Gamma Emitters Naturally-occurring K-40, a gamma-emitting nuclide, was detected in 3 of 4 samples analyzed. The concentrations ranged from 186 to 237 pCi/L.

(Table B-11.2, Appendix B)

"Hard-To-Detect" "Hard-To-Detect" analyses are not required on a routine basis and were not analyzed in 2018.

D. Precipitation Water Results Precipitation samples were collected from onsite and offsite locations in accordance with the station radiological groundwater protection program.

Analytical results and anomalies are discussed below:

Tritium Samples from five locations were collected from onsite and offsite monitoring locations and analyzed for tritium activity (Table B-111.1, Appendix B). Tritium was detected in one of the precipitation water samples at a concentration of 304 pCi/L. (Table B-111.1, Appendix B)

E. Summary of Results - Inter-Laboratory Comparison Program Inter-Laboratory Comparison Program results for TBE and Environmental Inc. (Midwest Labs) are presented in the 2018 Oyster Creek AREOR.

This report is part of the AREOR.

F. Leaks, Spills, and Releases There were no abnormal liquid releases during 2018.

G. Trends Active remediation of tritium in groundwater due to the spills that occurred in 2009 was initiated in October 2010. Trending of the data due to active remediation is on-going. Overall, the station has seen a decreasing trend in tritium values.

H. Investigations GHD Services Inc. performed an independent assessment of the tritium plume. The results of their assessment can be found in References 1, 2 and 3.

I. Actions Taken

1. Compensatory Actions Active remediation of tritium in groundwater due to the spills that occurred in 2009 was initiated in October, 2010.
2. Installation of Monitoring Wells The following wells were installed in 2010 to better characterize and monitor the tritium plume and site hydrology:

Well Number Formation Well Installation Date W-581 Cohansey July W-591 Cohansey March W-60 I c'ohansey July W-611 Cohansey July W-62 Cape May March W-631 Cohansey July W-64 Cape May March W-65 Cape May March W-661 Cohansey July W-67 Cape May March W-681 Cohansey July W-691 Cohansey July W-70 I Cohansev July W-71 Cape May August W-72 Cape May August W-73 Cohansey October Pumpinq well

3. Actions to Recover/Reverse Plumes Oyster Creek Generating Station is currently addressing the tritium in groundwater through pumping of groundwater out of W-73 into the intake structure.

V. References

1. Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleetwide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (6), April 2011
2. Conestoga Rovers and Associates, Site Investigation Report, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (4), August 2009
3. Conestoga Rovers and Associates, Remedial Investigation Workplan, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No. 055875 (5),

October 2009 Intentionally left blank APPENDIX A LOCATION DESIGNATION

Intentionally left blank TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List

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North 358373.33 2,000 OWN Domestic 300.0 B Kirkwood 574672.98 pCi/L Well South 356955.90 2,000 DWS Domestic 145.0 B Kirkwood 574616.69 pCi/L Well E oflSFSI 357632.49 21.0 2,000 LW-1 Cape May (microwave 575569.96 pCi/L zone}

E of ISFSI 357645.30 21.0 2,000 LW-2 Cape May (microwave 575581.92 pCi/L zone}

E of ISFSI 357630.20 21.0 2,000 LW-3 D Cape May (microwave 575575.52 pCi/L zone)

East of ISFSI- 357652.78 49.0 2,000 LW-4 D Cohansey (microwave 575573.75 pCi/L zone}

SWof 357380.76 2,000 MW-1A-2A MFOT 24.0 D Cape May 575043.44 pCi/L Moat East of 358551.94 2,000 MW-1G-1A fueling 20.0 Cape May 575308.91 pCi/L station East of 358550.57 45.0 2,000 MW-1G-18 fueling Cohansey 575316.19 pCi/L station Roadway-357598.17 2,000 MW-11-1A NWof 19.0 D Cape May 574412.70 pCi/L TWST Roadway-357574.80 2,000 MW-11-2A SE of 17.5 D Cape May 574493.50 pCi/L TWST Roadway- 357297.90 2,000 MW-15K-1A 19.0 D Cape May Intake 574469.50 pCi/L Yard-W 357573.30 2,000 MW-16D of MAC 25.0 D Cape May 574746.50 pCi/L Building A-1

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List

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Finninger 2,000 MW-24-2A Farm- 356838.52 18.0 Cape May pCi/L near DSB 579470.94 Finninger 356828.49 2,000 MW-24-3A Farm- 17.0 Cape May 578969.05 pCi/L near DSB Main 2,000 Surface MCD Condenser N/A N/A SW pCi/L Water Discharge Intake 2,000 Surface SW-1 N/A N/A SW Canal pCi/L Water RT9 2,000 Surface SW-2 South NIA N/A SW pCi/L Water Bridge 2,000 Surface SW-3 Fire Pond N/A N/A SW pCi/L Water Dilution Pump 357029.86 2,000 W-1 50.0 Cohansey Area- 574140.61 pCi/L West Bank North Yard 358311.70 2,000 W-1A 50.0 B Cohansey Area 574679.00 pCi/L North Yard 358312.80 2,000 W-18 20.0 Cape May Area 574685.40 pCi/L West end 357149.22 60.0 2,000 W-1C Cohansey of backsite 572741.00 pCi/L West end 357151.55 150.0 2,000 W-1K of Kirkwood 572728.77 pCi/L backsite S ofEDG 356965.65 57.0 2,000 W-2 Cohansey Bldg 574555.73 pCi/L Field-W 358105.00 2,000 W-2A of North 50.0 Cohansey 574348.60 pCi/L Yard Bldg A-2

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List Field-W of North 358110.30 2,000 W-2B 20.0 B Cape May Yard 574348.50 pCi/L Buildin Forked 357923.67 60.0 2,000 W-2C River CT Cohansey 573809.92 pCi/L Site Forked 358030.88 150.0 2,000 W-2K River CT Kirkwood 573762.54 pCi/L Site Intake -

357173.00 24.0 2,000 W-3 Access D Cape May 574499.10 pCi/L Road Plant 358067.92 50.0 2,000 W-3A Access Cohansey 575664.22 pCi/L Road Plant 358070.58 2,000 W-3B Access 20.0 Cape May 575656.25 pCi/L Road Finninger Farm-N 356595.30 60.0 2,000 W-3C Cohansey of 576663.33 pCi/L Dischar e Finninger Farm-N 356602.17 2,000 W-3K 100.0 Kirkwood of 576675.04 pCi/L Dischar e Intake -

357176.40 2,000 W-4 Access 55.0 D Cohansey 574497.70 pCi/L Road SE of 356913.30 2,000 W-4A OCAB 575387.10 50.0 B Cohansey pCi/L Building SE of 356916.40 2,000 W-4B OCAB 20.0 B Cape May 575388.90 pCi/L Building Finninger 359305.61 60.0 2,000 W-4C Farm -S of Cohansey 575867.58 pCi/L Intake Finning er 359321.83 2,000 W-4K Farm -S of 100.00 Kirkwood 575874.07 pCi/L Intake A-3

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List

,);-;~--:;-:~' ****"*t;::S"c',.~

- "'~

iifi}li~

1 NW Yard area, near 357510.95 2,000 W-5 20.5 D Cape May Fire Water 574374.05 pCi/L Tank Finninger Farm-E 356758.59 2,000 W-5C 60.0 B Cohansey of dredge 580642.26 pCi/L s oils Finninger Farm-E 356743.81 2,000 W-5K 150.0 B Kirkwood of dredge 580646.48 pCi/L s oils NWYard-near Fire 357514.02 2,000 W-6 52.0 D Cohansey Water 574373.77 pCi/L Tank NE- 357074.46 2,000 W-7 20.0 D Cape May Building 4 574713.08 pCi/L Roadway-357289.29 2,000 W-9 NE of SAS 20.0 D Cape May 574892.74 pCi/L Building NW of SAS 357286.29 2,000 W-10 60.0 D Cohansey Building 574890.61 pCi/L Yard-NW 357669.10 2,000 W-12 ofDWPC 20.0 D Cape May 574755.60 pCi/L Building Yard-NW 357666.00 2,000 W-13 ofDWPC 50.0 D Cohansey 574755.90 pCi/L Building Yard-SW 357702.41 2,000 W-14 of 53.0 D Cohansey 575018.75 pCi/L Warehouse Yard-SW 357705.83 2,000 W-15 of 20.0 D Cape May 575017.70 pCi/L Warehouse Yard- E of 357967.26 2,000 W-16 20.0 D Cape May LLRW 574933.03 pCi/L Road/ Exit 358078.05 2,000 W-17 150.0 Kirkwood NearW-3A 575667.14 pCi/L A-4

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List Near 357005.78 2,000 W-18 EDG 20.0 Cape May 574621.6 pCi/L Building Near 357077.91 2,000 W-19 EDG 20.0 Cape May 574633.23 pCi/L Building SWof 356927.46 2,000 W-20 EDG 20.0 Cape May 574542.59 pCi/L Building Near 357009.15 2,000 W-21 EDG 20.0 Cape May 574518.22 pCi/L Building Near 357024.50 2,000 W-22 EOG 39.0 Cape May 574590.19 pCi/L Building Near 357054.89 2,000 W-23 EDG 20.0 Cape May 574564.88 pCi/L Building South of TB 357128.94 2,000 W-24 Wofold 574650.77 19.0 D pCi/L Cape May Machine Sho Near 356962.59 2,000 W-25 EDG 20.0 Cape May 574677.59 pCi/L Building Near 357006.60 2,000 W-26 EOG 20.0 Cape May 574644.03 pCi/L Building Near 357042.43 2,000 W-27 EOG 574636.35 20.0 Cape May pCi/L Building Near 356991.29 2,000 W-28 EDG 19.5 Cape May 574573.64 pCi/L Building Near 357012.62 2,000 W-29 EOG 574568.69 19.5 Cape May pCi/L Building Near 357058.00 2,000 W-30 EOG 19.5 Cape May 574516.71 pCi/L Building A-5

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List Near 357051.78 2,000 W-31 EOG 574495.62 19.5 pCi/L Cape May Building Near 356978.58 2,000 W-32 EOG 574528.44 19.5 pCi/L Cape May Building Near 357026.93 2,000 W-33 EOG 574499.17 19.5 pCi/L Cape May Building South of TB 357196.14 2,000 W-34 Wofold 40.0 0 Cohansey 574649.43 pCi/L Machine Sho Between CST and 357368.21 2,000 MW-50 20.0 E Cape May Intake 574436.80 pCi/L Structure Near 357378.30 2,000 MW-51 20.0 E Cape May CST 574480.80 pCi/L Near 357400.90 2,000 MW-52 Intake 20.0 0 Cape May 574353.00 pCi/L Structure Near end ofCW 357272.80 2,000 MW-53 20.0 0 Cape May discharge 574447.60 pCi/L i in Near 357276.20 2,000 MW-54 Intake 20.0 E Cape May 574311.70 pCi/L Structure Between CST and 357354.88 2,000 MW-55 30.0 E Cape May Intake 574440.07 pCi/L Structure By 357305.30 2,000 MW-561 NaOCI 52.0 E Cohansey 574465.50 pCi/L tanks Near 357343.71 2,000 MW-571 Intake 50.0 E Cohansey 574373.89 pCi/L Structure Near 357346.70 2,000 MW-581 Intake 72.0 0 Cohansey 574377.28 pCi/L Structure A-6

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List

'!fff.-'."~ . : ' -', ,_ --;_,- ... *..

liill~ MW-591 Intake Roadway 357422.14 44.0 D 2,000 Cohansey

-NWof 574406.38 pCi/L CST Near 357346.55 2,000 MW-601 Intake 92.0 D Cohansey 574373.88 pCi/L Structure Between CST and 357328.64 2,000 MW-611 72.0 E Cohansey Intake 574444.45 pCi/L Structure NW Corner of 357467.93 2,000 MW-62 25.0 D Cape May Turbine 574524.10 pCi/L Bid Between CST and 357329.40 2,000 MW-631 92.0 D Cohansey Intake 574447.67 pCi/L Structure Near 357343.96 2,000 MW-64 Intake 25.0 E Cape May 574377.88 pCi/L Structure Intake Roadway 357421.00 2,000 MW-65 25.0 D Cape May

-NWof 574402.55 pCi/L CST SE of 357320.44 2,000 MW-661 Reactor 80.0 D Cohansey 574889.18 pCi/L Bldg West side of 357401.99 2,000 MW-67 25.0 E Cape May Turbine 574540.38 pCi/L Bldg SE of 357323.83 2,000 MW-681 Reactor 100.0 D Cohansey 574897.64 pCi/L Bldg Yard-NWof 357664.03 2,000 MW-691 78.0 D Cohansey DWPC 574760.93 pCi/L Buildin Yard-NWof 357670.57 2,000 MW-701 98.0 D Cohansey DWPC 574759.18 pCi/L Buildin S of 357365.52 2,000 MW-71 Reactor 25.0 D Cape May 574841.89 pCi/L Bldg A-7

TABLEA-1: Radiological Groundwater Protection Program - Sampling Locations, Oyster Creek Generating Station, 2018 Oyster Creek Generating Station RGPP Sample Point List N of Reactor 357549.87 2,000 MW-72 25.0 D Cape May Bldg 574788.52 pCi/L Remediation MW-73 System N/A N/A N/A N/A N/A

  • Tritium sampling frequency based upon agreement made with the NJDEP on 04/26/13.

D = Daily W=Weekly M = Monthly S = Semi-annual B = Biennial A-8

Figure A-1 Sampling Locations - Selected Cohansey and Cape May Formation Wells ,

Oyster Creek Generating Station , 2018 A-9

Figure A-1 Sampling Locations - Selected Cohansey and Cape May Formation Wells, Oyster Creek Generating Station , 2018 A-10

APPENDIX B DATA TABLES

Intentionally left blank TABLE 8-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus)

DWN 04/18/18 < 182 DWN 08/03/18 < 194 DWS 04/18/18 < 177 DWS 08/03/18 < 191 LW-3 01/19/18 < 190 LW-3 04/24/18 < 180 < 4.1 < 0.9 < 0.3 < 1.1 < 0.8 < 1.6 LW-3 08/01/18 < 193 LW-4 01/19/18 < 195 LW-4 04/24/18 < 179 < 5.1 < 0.7 < 0.3 < 1.0 1.9 +/- 0.6 < 1.6 LW-4 08/01/18 < 185 MW-1A-2A 01/18/18 < 190 MW-1A-2A 04/23/18 < 176 < 4.6 < 0.7 < 1.0 < 0.9 3.1 +/- 1.0 < 1.6 MW-1A-2A 08/01/18 < 186 MW-11-1A 01/17/18 < 192 MW-11-1A 04/18/18 < 178 < 4.8 < 0.6 < 0.6 < 0.9 3.0 +/- 0.8 < 1.6 MW-11-1A 07/31/18 < 190 MW-11-1A 10/30/18 < 187 MW-11-2A 01/17/18 < 194 MW-11-2A 04/19/18 < 184 < 5.5 < 0.7 < 0.3 < 3.1 1.4 +/- 0.6 < 2.7 MW-11-2A 08/01/18 < 187 MW-11-2A 10/30/18 < 186 MW-15K-1A 01/18/18 TBE < 188 MW-15K-1A 01/18/18 TBE < 192 MW-15K-1A 01/18/18 EIML < 153 MW-15K-1A 04/18/18 TBE < 180 < 5.8 < 0.8 < 1.5 < 1.1 7.6 +/- 1.1 < 1.6 MW-15K-1A 04118/18 TBE < 179 < 5.3 < 0.7 < 1.5 < 1.1 8.7 +/- 1.2 < 1.6 MW-15K-1A 04/18/18 EIML < 156 < 0.8 < 0.5 \1) < 0.8 \lJ < 0.7 MW-15K-1A 07/31/18 TBE < 189 MW-15K-1A 07/31/18 TBE < 200 MW-15K-1A 07/31/18 EIML < 152 MW-15K-1A 10/30/18 < 187 MW-16D 01/18/18 < 189 MW-16D 04/19/18 < 178 < 5.1 < 0.6 < 2.2 < 1.2 3.4 +/- 1.3 3.3 +/- 1.3 MW-16D 08/01/18 < 198 MW-16D 10/31/18 < 189 MW-50 01/17/18 < 192 MW-50 04/17/18 < 179 < 4.7 < 0.7 0.9 +/- 0.5 < 1.4 2.5 +/- 0.7 < 1.9 MW-50 07/31/18 329 +/- 132 MW-52 01/17/18 TBE < 190 MW-52 01/17/18 TBE < 190 MW-52 01/17/18 EIML < 156 MW-52 04/18/18 < 180 < 4.1 < 0.7 < 0.7 4.4 +/- 1.8 4.5 +/- 0.9 3.2 +/- 1.7 MW-52 07/31/18 TBE < 188 MW-52 07/31/18 TBE < 187 MW-52 07/31/18 EIML < 152 MW-53 01/19/18 < 192 MW-53 04/24/18 < 178 < 4.8 < 0.7 < 0.9 < 0.9 8.3 +/- 1.2 < 1.7 MW-53 08/01/18 < 186 MW-54 01/17/18 < 187 MW-54 04/18/18 < 177 < 6.3 < 0.8 < 2.2 2.6 +/- 1.5 16.9 +/- 2.0 3.0 +/- 1.4 MW-54 07/31/18 393 +/- 137 MW-55 01/17/18 < 190 1

< l Reported values are TOTAL (not Suspended)

Bolded values indicate LLD was not met due to high solid content in the sample B-1

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-8 (Dis) Gr-8 (Sus)

MW-55 04/17/18 < 178 < 6.7 < 0.7 < 1.3 < 1.1 18.8 +/- 2.0 < 1.8 MW-55 07/31/18 < 190 MW-55 10/30/18 < 189 MW-561 01/17/18 1180 +/- 190 MW-561 04/18/18 1520 +/- 215 < 8.5 < 0.7 < 0.6 < 1.4 5.6 +/- 0.9 < 2.2 MW-561 07/31/18 1670 +/- 233 MW-561 10/30/18 902 +/- 166 MW-571 01/17/18 851 +/- 159 MW-571 04/17/18 3030 +/- 358 < 8.2 < 0.8 < 1.9 < 1.3 31.5 +/- 2.2 < 1.9 MW-571 07/31/18 1400 +/- 213 MW-571 10/30/18 1020 +/- 174 MW-581 01/17/18 < 189 MW-581 04/17/18 < 180 < 6.2 < 0.8 0.7 +/- 0.3 < 1.0 1.1 +/- 0.5 < 1.7 MW-581 07/31/18 < 189 MW-591 01/17/18 < 188 MW-591 04/18/18 < 177 < 4.4 < 0.7 3.9 +/- 1.2 < 1.7 10.1 +/- 1.5 < 2.9 MW-591 07/31/18 < 189 MW-591 10/30/18 < 191 MW-601 01/17/18 < 189 MW-601 04/17/18 < 177 < 5.2 < 0.8 < 0.3 < 1.0 1.0 +/- 0.5 < 1.6 MW-601 07/31/18 < 189 MW-611 01/17/18 < 189 MW-611 04/17/18 < 184 < 6.6 < 0.8 < 0.4 < 1.1 1.7 +/- 0.6 < 1.6 MW-611 07/31/18 < 190 MW-611 10/30/18 < 188 MW-62 01/17/18 < 190 MW-62 04/18/18 < 175 < 3.8 < 0.6 1.6 +/- 1.0 8.4 +/- 1.8 4.4 +/- 1.6 13.5 +/- 1.9 MW-62 08/01/18 < 192 MW-62 10/30/18 < 193 MW-631 01/17/18 < 191 MW-631 04/18/18 < 182 < 6.1 < 0.8 < 0.3 < 1.0 0.9 +/- 0.5 < 1.6 MW-631 07/31/18 < 193 MW-64 01/17/18 < 187 MW-64 04/17/18 < 181 < 5.2 < 0.8 < 0.8 2.0 +/- 1.3 12.7 +/- 1.3 3.1 +/- 1.3 MW-64 07/31/18 < 190 MW-64 10/30/18 TBE < 191 MW-64 10/30/18 TBE < 193 MW-64 10/30/18 EIML < 152 MW-65 01/17/18 < 189 MW-65 04/18/18 TBE < 179 < 4.6 < 0.6 < 13.5 < 0.9 20.7 +/- 4.0 < 1.7 MW-65 04/18/18 TBE < 179 < 4.5 < 0.6 < 10.8 < 0.9 19.2 +/- 3.7 < 1.7 MW-65 04/18/18 EIML < 156 < 0.8 < 0.5 \I) < 4.5 \II < 3.2 MW-65 07/31/18 < 189 MW-65 10/30/18 < 192 MW-661 01/18/18 < 190 MW-661 04/20/18 < 174 < 5.3 < 0.8 < 0.3 < 1.0 2.1 +/- 0.6 < 1.7 MW-661 08101/18 < 186 MW-67 01/17/18 841 +/- 159 MW-67 04/18/18 400 +/- 130 < 6.0 < 0.6 < 0.4 2.8 +/- 1.7 5.2 +/- 0.9 4.4 :!: 1.8 MW-67 08/01/18 320 +/- 132 MW-67 10/30/18 278 +/- 126 MW-681 01/18/18 < 190 1

< > Reported values are TOTAL (not Suspended)

Balded values Indicate LLD was not met due to high solid content in the sample B-2

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

MW-681 04/19/18 < 175 < 6.0 < 0.6 < 0.3 < 0.9 1.5 +/- 0.5 < 1.6 MW-681 08/01/18 < 188 MW-691 01/18/18 < 190 MW-691 04/19/18 < 179 < 6.2 < 0.9 < 0.3 < 1.1 1.1 +/- 0.5 3.2 +/- 1.2 MW-691 08/01/18 < 192 MW-701 01/18/18 < 187 MW-701 04/19/18 < 180 < 4.7 < 0.7 < 0.4 < 0.9 3.5 +/- 0.6 < 1.7 MW-701 08/01/18 < 193 MW-71 01/18/18 < 192 MW-71 04/20/18 < 179 < 2.7 < 0.6 < 1.6 < 0.9 15.1 +/- 1.7 < 1.6 MW-71 08/01/18 < 193 MW-71 10/31/18 TBE < 187 MW-71 10/31/18 TBE < 190 MW-71 10/30/18 EIML < 152 MW-72 01/18/18 < 198 MW-72 04/19/18 < 175 < 5.0 < 0.7 < 0.4 < 1.0 2.6 +/- 0.6 < 1.7 MW-72 08/01/18 < 195 MW-72 10/31/18 < 190 SEWER PIT 08/02/18 . < 186 W-1A 04/20/18 < 179 W-28 04/20/18 < 179 W-3 01/18/18 < 194 W-3 04/18/18 < 179 < 5.1 < 0.6 < 4.9 < 1.1 < 4.4 < 1.8 W-3 07/31/18 < 191 W-3 10/30/18 < 193 W-4 01/18/18 TBE < 196 W-4 01/18/18 TBE < 191 W-4 01/18/18 EIML < 156 W-4 04/18/18 TBE < 177 < 4.2 < 0.6 < 1.0 < 0.9 5.8 +/- 1.1 < 1.6 W-4 04/18/18 TBE < 178 < 4.8 < 0.6 < 1.4 < 1.0 6.9 +/- 1.1 < 1.7 W-4 04/18/18 E/ML < 156 < 0.9 < 0.6 \1} < 0.8 \l} < 0.8 W-4 07/31/18 < 189 W-4 07/31/18 < 191 W-4 07/31/18 EIML < 152 W-4A 04/20/18 < 180 W-48 04/20/18 < 176 W-5 01/17/18 TBE < 195 W-5 01/17/18 TBE < 190 W-5 01/17/18 EIML < 156 W-5 04/18/18 TBE < 182 < 5.4 < 0.6 < 0.5 < 0.9 3.6 +/- 0.7 < 1.6 W-5 04/18/18 TBE < 179 < 5.7 < 0.8 < 0.5 < 1.0 2.8 +/- 0.7 < 1.7 W-5 04/18/18 EIML < 156 < 0.7 < 0.7 PJ < 0.9 \I}< 0.6 W-5 07/31/18 TBE < 189 W-5 07/31/18 TBE < 188 W-5 07/31/18 EIML < 152 W-5 10/30/18 TBE < 191 W-5 10/30/18 TBE < 196 W-5 10/30/18 EIML < 152 W-5C 04/23/18 < 179 W-5K 04/23/18 < 180 W-6 01/17/18 < 196 W-6 04/18/18 < 174 < 4.3 < 0.7 2.8 +/- 0.9 < 2.7 6.1 +/- 1.2 < 3.4 1

< > Reported values are TOTAL (not Suspended)

Bolded values indicate LLD was not met due to high solid content in the sample 8-3

TABLE 8-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM, GROSS ALPHA, AND GROSS BETA IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 Sr-89 Sr-90 Gr-A (Dis) Gr-A (Sus) Gr-B (Dis) Gr-B (Sus)

W-6 07/31/18 < 188 W-7 01/18/18 TBE < 191 W-7 01/18/18 TBE < 195 W-7 01/18/19 EIML < 156 W-7 04/20/18 TBE < 180 < 5.7 < 0.8 < 3.1 4.8 +/- 1.5 11.8 +/- 2.9 7.7 +/- 1.6 W-7 04/20/18 TBE < 175 < 4.8 < 0.8 < 3.7 2.9 +/- 1.2 10.4 +/- 2.9 3.2 +/- 1.3 W-7 04/18/18 EIML < 156 < 0.7 < 0.4 \l/ < 4.5 \l) < 3.6 W-7 08/02118 TBE < 191 W-7 08/02/18 TBE < 189 W-7 08/02/18 EIML < 152 W-9 01/18/18 < 197 W-9 04/19/18 < 181 < 5.0 < 0.8 < 0.7 < 1.0 4.9 +/- 0.9 < 1.7 W-9 08/01/18 < 194 W-9 10/31/18 < 194 W-10 01/18/18 < 200 W-10 04/19/18 < 178 < 5.3 < 0.9 0.4 +/- 0.3 < 0.9 1.6 +/- 0.5 < 1.6 W-10 08/01/18 < 184 W-12 01/18/18 < 197 W-12 04/19/18 < 176 < 4.7 < 0.8 < 0.7 < 0.9 2.5 +/- 0.8 1.8 +/- 1.0 W-12 08/01/18 < 190 W-12 10/31/18 < 190 W-13 01/18/18 < 200 W-13 04/19/18 < 184 < 6.0 < 0.6 < 0.4 < 1.1 1.5 +/- 0.7 2.8 +/- 1.2 W-13 08/01/18 < 185 W-14 01/18/18 < 197 W-14 04/19/18 < 178 . 4.4 < 0.9 0.6 +/- 0.3 < 1.0 3.2 +/- 0.6 < 1.7 W-14 08/02/18 < 195 W-15 01118/18 < 191 W-15 04/19/18 < 179 < 4.7 < 0.7 < 0.7 4.4 +/- 1.6 5.9 +/- 1.0 5.9 +/- 1.5 W-15 08/02/18 < 190 W-16 01/18/18 TBE < 192 W-16 01/18/18 TBE < 189 W-16 01/18/19 EIML < 156 W-16 04/19/18 TBE < 184 < 6.4 < 0.8 < 0.3 < 1.0 1.1 +/- 0.6 < 1.6 W-16 04/19/18 TBE < 183 < 6.3 < 0.8 < 0.3 < 1.0 1.0 +/- 0.6 < 1.6 W-16 04/18/18 EIML < 156 < 0.8 < 0.5 \I/ < 0.5 \I/ < 0.8 W-16 08/01/18 TBE < 187 W-16 08/01/18 TBE < 197 W-16 08/01/18 EIML < 152 W-24 01/18/18 < 192 W-24 04/20/18 < 177 < 4.2 < 0.7 < 0.4 < 1.0 2.3 +/- 0.6 < 1.7 W-24 08/02/18 < 194 W-34 01/19/18 < 191 W-34 04/24/18 < 177 < 7.1 < 0.8 < 0.9 < 1.0 6.3 +/- 1.0 < 1.7 W-34 08/01/18 < 191 W-34 10/31/18 < 187 1

< >Reported values are TOTAL (not Suspended)

Balded values indicate LLD was not met due to high solid content in the sample B-4

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PC I/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 OWN 04/18/18 < 31 < 50 <3 <3 < 8 <3 <6 <4 <5 < 10 < 3 <3 < 24 < 10 DWS 04/18/18 < 30 < 54 <4 <4 <9 < 3 < 5 <4 < 6 < 13 <3 <4 < 26 <8 LW-3 04/24/18 < 52 < 111 <6 <6 < 11 < 7 < 12 <7 < 12 < 14 <6 <6 < 39 < 12 LW-4 04/24/18 < 13 < 32 < 1 <2 <4 < 2 <3 <2 < 3 <5 <2 <2 < 11 < 5 MW-1A-2A 04/23/18 < 38 < 39 < 3 <4 < 8 < 5 < 7 < 4 < 8 < 8 <4 <4 < 18 <6 MW-11-1A 04/18/18 < 37 < 58 < 4 <4 < 8 <4 < 9 < 4 < 7 < 13 <4 <4 < 31 <9 MW-11-2A 04/19/18 < 17 < 30 <2 <2 <4 < 2 < 3 < 2 <4 < 10 <2 <2 < 17 <6 MW-15K-1A 04/18/18 TBE < 26 < 62 <3 <2 <4 < 2 <6 < 2 <4 < 9 <2 < 1 < 15 <5 MW-15K-1A 04/18/18 TBE < 23 < 22 <2 < 3 < 6 <2 < 4 < 3 < 4 < 13 < 2 <2 < 23 <8 MW-15K-1A 04/18/18 EIML < 26 < 62 <3 <2 <4 < 2 < 6 < 3 <4 < 12 <2 <3 < 3 <4 MW-15K-1A 10/30/18 < 61 < 61 <5 <6 < 15 < 7 < 13 < 7 < 11 < 12 <5 <8 < 30 <8 MW-160 04/19/18 < 18 73 +/- 25 <2 <2 <4 < 2 <3 < 2 <3 < 10 <2 <2 < 17 <5 MW-50 04/17/18 < 19 < 30 <2 <2 <5 <2 <4 <2 <3 < 10 <2 <2 < 18 <6 CJ MW-52 04/18/18 < 29 < 49 <3 <3 < 8 <3 <6 <3 <6 < 10 <3 <3 < 22 <6 I

01 MW-53 04/24/18 < 54 < 58 < 7 <8 < 14 < 6 < 13 < 7 < 14 < 12 <6 <7 < 39 < 10 MW-54 04/18/18 < 21 < 17 <2 <2 < 5 < 2 <4 < 2 <4 < 11 < 2 <2 < 21 <7 MW-55 04/17/18 < 34 < 50 <3 <4 <7 < 4 <6 <3 <6 < 12 <3 <3 < 25 <8 MW-55 10/30/18 < 51 < 123 <6 <6 < 11 < 10 < 14 <6 <9 < 10 <5 <6 < 26 < 14 MW-561 04/18/18 < 22 < 16 < 2 <2 <5 < 2 <4 <2 <4 < 13 <2 <2 < 22 <6 MW-561 10/30/18 < 63 < 50 < 6 <6 < 15 < 4 < 12 < 7 < 14 < 12 <7 < 8 < 30 < 12 MW-571 04/17/18 < 30 < 76 <4 < 3 < 9 < 3 < 7 < 4 <6 < 12 <3 <3 < 28 < 11 MW-571 10/30/18 < 48 < 68 < 7 < 5 < 12 < 6 < 12 < 7 < 10 < 11 <6 <7 < 29 < 11 MW-581 04/17/18 < 22 < 56 <2 < 3 <5 < 3 <5 <3 < 5 < 10 <3 <3 < 18 <6 MW-591 04/18/18 < 31 < 31 <3 < 3 < 8 < 3 < 7 < 3 < 7 < 10 <3 <4 < 22 <8 MW-601 04/17/18 < 32 < 30 <3 <3 < 7 < 3 <6 < 3 <6 < 13 <3 <3 < 27 <7 MW-611 04/17/18 < 26 < 24 <3 <3 <6 <2 <5 < 3 <5 < 10 < 3 < 3 < 20 <7 MW-62 04/18/18 < 28 < 31 <3 <4 <6 < 3 <6 < 3 <6 < 9 <3 < 3 < 21 <6 MW-631 04/18/18 < 32 < 29 < 3 <3 <7 <4 <6 < 3 <6 < 12 < 4 <3 < 24 <6 MW-64 04/17/18 < 26 < 59 <3 <3 < 8 < 3 <6 < 3 <5 < 9 < 3 <3 < 21 <8 MW-65 04/18/18 TBE < 34 < 94 <4 <4 < 9 <4 < 8 < 5 < 9 < 11 <4 <5 < 25 <9 MW-65 04/18/18 TBE < 50 < 86 <5 < 5 < 12 <6 < 11 < 6 < 9 < 15 <6 <6 < 36 < 11 MW-65 04/18/18 EIML < 34 < 54 < 2 <3 < 4 < 2 < 5 < 3 < 5 < 10 <2 <4 < 25 <4 MW-65 10/30/18 < 70 < 125 < 7 <5 < 16 < 10 < 14 < 8 < 12 < 12 <7 < 7 < 28 < 14 MW-661 04/20/18 < 44 < 99 <4 <5 < 10 < 4 < 9 <4 < 8 < 15 <5 <5 < 28 <9 MW-67 04/18/18 < 18 < 31 <2 <2 <4 < 2 <4 < 2 <3 < 10 <2 <2 < 18 <6 MW-67 10/30/18 < 51 < 67 <4 <4 < 10 < 8 < 12 <6 < 11 < 10 <7 <7 < 30 < 11 MW-681 04/19/18 < 29 < 29 <3 < 3 <7 < 3 <6 < 3 <6 < 10 <3 <4 < 21 <6 MW-691 04/19/18 < 17 < 29 <2 <2 < 5 < 2 < 4 < 2 < 3 <9 <2 <2 < 18 <6

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MW-701 04/19/18 < 53 < 59 <6 <7 < 13 < 7 < 15 < 7 < 12 < 14 <6 <6 < 35 < 13 MW-71 04/20/18 < 34 < 62 < 4 <4 <9 <4 <7 <4 < 6 < 9 < 3 <4 < 23 <6 MW-72 04/19/18 < 43 < 75 <4 <4 < 9 <4 <9 <5 <8 < 11 < 5 <5 < 23 <8 W-1A 04/20/18 < 48 < 92 <5 <6 < 12 <6 < 11 <6 <8 < 15 <6 <6 < 33 < 10 W-28 04/20/18 < 45 < 39 < 4 < 5 < 13 < 5 < 9 < 6 < 10 < 13 <6 <6 < 31 < 10 W-3 04/18/18 < 21 < 18 <2 <2 <5 <2 <4 <2 <4 < 12 <2 <2 < 20 <5 W-4 04/18/18 TBE < 40 < 82 <4 <5 < 10 <4 <8 <4 <7 < 12 < 5 <5 < 27 <8 W-4 04/18/18 TBE < 29 < 53 <3 < 3 < 8 <4 < 7 <4 <6 < 10 <4 < 3 < 24 <6 W-4 04/18/18 EIML < 19 < 56 <2 <2 < 3 < 2 < 3 < 2 < 3 < 9 < 3 <3 < 24 <6 W-4A 04/20/18 < 29 < 25 <3 <3 <7 <3 <6 <3 <6 < 13 <3 <3 < 25 < 8 W-48 04/20/18 < 44 < 92 <5 < 5 < 11 <5 < 12 <5 < 9 < 14 <5 <5 < 34 < 10 W-5 04/18/18 TBE < 33 < 78 < 3 <4 < 7 < 4 <6 <4 <6 < 11 <4 < 3 < 26 <8 W-5 04/18/18 TBE < 37 < 36 <4 <5 < 11 <4 < 8 <5 <8 < 13 <5 <5 < 29 < 10 OJ W-5 04/18/18 E/ML < 27 < 78 <2 <3 <5 <3 <4 < 2 <4 < 10 <2 <3 < 22 <5 I

0, W-5C 04/23/18 < 43 < 35 <5 <5 < 11 <5 < 10 < 5 <9 < 10 <6 <5 < 26 <8 W-5K 04/23/18 < 45 < 48 <5 < 5 <8 <6 < 10 <6 < 11 < 12 <6 <6 < 30 <8 W-6 04/18/18 < 34 < 92 <5 < 5 < 11 <4 <9 <6 < 8 < 14 <4 < 5 < 31 < 15 W-7 04/20/18 TBE < 49 < 49 < 5 <6 < 13 <5 < 11 <6 < 10 < 15 <6 <5 < 31 < 13 W-7 04/20/18 TBE < 49 < 45 <4 < 5 < 11 <5 < 10 < 5 < 9 < 15 <6 <5 < 35 < 11 W-7 04/20/18 EIML < 32 < 76 <3 <2 <5 < 2 <4 < 3 < 4 < 10 <3 <2 < 28 <4 W-9 04/19/18 < 47 < 103 <4 <4 <9 < 4 <8 < 4 < 9 < 14 <5 <5 < 33 < 10 W-10 04/19/18 < 25 < 50 <2 <3 <5 <2 <5 < 3 < 5 < 8 <3 <3 < 18 <5 W-12 04/19/18 < 35 < 88 <4 < 5 <9 <4 <9 <5 < 7 < 13 <5 <4 < 31 < 11 W-13 04/19/18 < 20 < 33 <2 <2 <5 < 2 <4 < 2 < 4 < 10 <2 <2 < 19 <6 W-14 04/19/18 < 38 < 69 <4 <5 < 9 < 5 < 10 < 5 <9 < 12 < 4 <4 < 29 < 10 W-15 04/19/18 < 16 < 15 <2 <2 <4 <2 < 3 < 2 <3 < 9 < 2 <2 < 16 <5 W-16 04/19/18 TBE < 19 65 +/- 28 <2 <2 <4 < 2 < 3 < 2 <4 < 10 <2 <2 < 18 < 5 W-16 04/19/18 TBE < 43 < 109 < 5 <5 < 12 <4 < 10 < 5 < 10 < 10 <5 <6 < 34 < 14 W-16 04/19/18 EIML < 23 < 78 < 3 <2 45 < 2 < 3 < 3 < 3 < 10 < 3 < 3 < 24 <5 W-24 04/20/18 < 55 < 47 < 5 <6 < 11 <6 < 12 < 6 < 10 < 15 < 6 <6 < 32 < 10 W-34 04/24/18 < 44 < 97 <4 <6 < 11 <6 < 10 < 6 < 10 < 11 <6 <6 < 28 <8

TABLE B-1.3 CONCENTRATIONS OF HARD-TO-DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 MW-50 04/17/18 < 0.17 < 0.06 < 0.14 < 0.06 < 0.10 < 0.13 < 0.16 < 0.18 < 160 < 5 MW-54 04/18/18 < 0.15 < 0.03 < 0.13 < 0.16 < 0;03 < 0.16 < 0.12 < 0.05 < 188 < 4 MW-55 04/17/18 < 0.07 < 0.02 < 0.08 < 0.07 < 0.06 < 0.06 < 0.10 < 0.06 < 164 < 4 MW-561 04/18/18 < 0.12 < 0.04 < 0.10 < 0.16 < 0.10 < 0.19 < 0.08 < 0.18 < 150 < 4 MW-571 04/17/18 < 0.04 < 0.02 < 0.06 < 0.17 < 0.06 < 0.19 < 0.15 < 0.19 < 176 < 5 MW-611 04/17/18 < 0.06 < 0.06 < 0.11 < 0.15 < 0.11 < 0.07 < 0.12 < 0.13 < 100 < 4 MW-64 04/17/18 < 0.14 < 0.03 < 0.13 < 0.11 < 0.05 < 0.09 < 0.20 < 0.16 < 115 < 4 MW-67 04/18/18 < 0.10 < 0.04 < 0.15 < 0.19 < 0.05 < 0.14 < 0.12 < 0.17 < 168 < 4 OJ I

-...I

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RES ULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE H-3 MCD 01/17/18 < 193 MCD 04/18/18 < 178 MCD 08/01/18 < 190 MCD 10/24/18 < 194 SEWER PIT 01/16/18 < 197 SEWER PIT 04/17/18 < 184 STORM DRAIN EAST 01/16/18 < 198 STORM DRAIN EAST 07/12/18 < 185 SW-1 01/22/18 < 194 SW-1 04/18/18 < 175 SW-1 08/01/18 < 188 SW-1 10/24/18 < 190 SW-2 01/22/18 < 195 SW-2 04/23/18 < 176 SW-2 08/02/18 < 184 SW-2 10/30/18 < 192 SW-3 01/22/18 < 198 SW-3 . 04/23/18 < 176 SW-3 08/02/18 < 186 SW-3 10/30/18 < 191 B-8

TABLE B-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MCD 04/18/18 < 33 223 +/- 53 <4 < 4 < 9 <4 < 7 < 4 < 7 < 13 <4 <4 < 26 <8 SW-1 04/18/18 < 36 186 +/- 55 <3 < 3 < 9 <4 < 7 < 4 < 7 < 15 <4 <3 < 27 <8 SW-2 04/23/18 < 55 237 +/- 83 <6 <7 < 15 <6 < 12 <6 < 12 < 12 <6 <6 < 34 < 11 SW-3 04/23/18 < 70 < 49 < 7 <8 < 12 <6 < 12 <8 < 14 < 13 <8 <8 < 40 <7

TABLE B-11.3 CONCENTRATIONS OF HARD TO DETECTS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING ST ATION, 2018 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE Am-241 Cm-242 Cm-243/244 Pu-238 Pu-239/240 U-234 U-235 U-238 Fe-55 Ni-63 NONE FOR 2018 Cl:J I

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0

TABLE B-111.1 CONCENTRATIONS OF TRITIUM IN PRECIPITATION WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, OYSTER CREEK GENERATING STATION, 2018 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA COLLECTION SITE DATE H-3 2 01/15/18 < 195 2 04/20/18 < 178 2 08/01/18 < 195 2 10/04/18 < 193 3 01/15/18 < 197 3 04/20/18 < 180 3 08/01/18 < 193 3 10/04/18 < 193 4 01/15/18 304 +/- 134 4 04/20/18 < 179 4 08/01/18 < 188 4 10/04/18 < 192 5 01/15/18 < 197 5 04/20/18 < 178 5 08/02/18 < 200 5 10/04/18 < 193 6 01/15/18 < 198 6 04/20/18 < 179 6 08/01/18 < 191 6 10/04/18 < 191 B-11

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