ML20143A099

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Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report
ML20143A099
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 05/15/2020
From: Laura Smith
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML20143A099 (107)


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!SP' Exelon Generation May 15, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant; Unit Nos. 1 & 2; Larry 0. Smith Manager-Regulatory Assurance Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410-495-5219 Office www.exeloncorp.com Larry.smith2@exeloncorp.com Renewed Facility Operating License Nos. DPR-53 and DPR-69 Docket Nos. 50-317 & 50-318

Subject:

References:

Independent Spent Fuel Storage Installation; Material License No. SNM-2505 NRC Docket No. 72-8 Annual Radiological Environmental Operating Report

1.

Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.2

2.

Calvert Cliffs Independent Spent Fuel Storage Installation Technical Specification 6.2 In accordance with References 1 and 2, Calvert Cliffs Nuclear Power Plant is submitting the Annual Radiological Environmental Operating Report (Attachment 1). There are no regulatory commitments contained in this correspondence. Should you have questions regarding this matter, please contact me at (410) 495-5219 or Mr. Ron Thomas at (410) 495-6970. Respectfully, ~kj~ Larry D. Smith i,!iZ 5 /vt-1 :5 >

1- /p J0,(_IL JU'-{SS Manager - Regulatory Assurance LDS/imd

Document Control Desk May 15, 2020 Page 2

Attachment:

(1) Annual Radiological Environmental Operating Report for the Calvert Cliffs Nuclear Power Plant Units 1 and 2 and the Independent Spent Fuel Storage Installation cc: NRC Regional Administrator, Region 1 NRC Project Manager, Calvert Cliffs NRC Resident Inspector, Calvert Cliffs S. Gray, MD-DNR

ATTACHMENT (1) ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 AND THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION Calvert Cliffs Nuclear Power Plant May 15, 2020

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR THE CAL VERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND2 AND THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION January 1 - December 31, 2019 A. M. Barnett M.Prosceo EXELON GENERATION, LLC MAY2020

TABLE OF CONTENTS January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 LIST OF FIGURES...................................................................................................................... ii LIST OF TABLES....................................................................................................................... iii I.

SUMMARY

................................................................................................................................. 5 II. CAL VERT CLIFFS NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...................................................... 7 II.A. INTRODUCTION............................. ;........................................................................................................... 7 11.B. PROGRAM....................................................................................... :............................................................ 7 II.B.1 Objectives............................................................................................................................................... 7 11.B.2 Sample Collection................................................................................................................................... 8 11.B.3 Data Interpretation................................................................................................................................ 8 11.B.4 Program Exceptions............................................................................................................................... 8 11.C. RESULTS AND DISCUSSIONS................................................................................................................... 9 11.C.1 Aquatic Environment............................................................................................................................. 9 11.C.1.a Bay Water............................................................................................................................................. 9 11.C.1.b Aquatic Organisms............................................................................................................................ 10 11.C.1.c Shoreline Sediment............................................................................................................................ 10 11.C.2 Atmospheric Environment.................................................................................................................. 13 11.C.2.a Air Particulate Filters............................................. :......................................................................... 13 11.C.2.b Air Iodine.......................................................................................................................................... 13 11.C.3 Terrestrial Environment.................................................................................................................... 15 11.C.3.a Vegetation............................................. :............................................................................................ 15 11.C.4 Direct Radiation................................................................................................................................... 15 11.D. CONCLUSION....................................................................................................... *...................................... 20 III. INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM....................................................26 III.A. INTRODUCTION....................................................................................................................................... 26 111.B. PROGRAM.................................................................................................................................................. 26 111.B.1 Obiectives............................................................................................................................................ 26 111.B.2 Sample Collection............................................................................................................................... 27 111.B.3 Data Interpretation............................................................................................................................ 27 111.B.4 Program Exceptions........................................................................................................................... 27 111.C. RESULTS AND DISCUSSIONS............................................................................................................... 28 111.C.1 Atmospheric Environment................................................................................................................ 28 111.C.1.a Air Particulate Filters..................................................................................................................... 28 111.C.2 Terrestrial Environment................................................................................................................... 29 111.C.2.a Vegetation........................................................................................................................................ 29 111.C.2.b Soils.................................................................................................................................................. 29 111.C.3 Direct Radiation...................................... ~......................................................................................... 29 111.D. CONCLUSION............................................................................................................................................ 31 IV. REFERENCES...................................................................................................................... 35 APPENDIX A Sample Locations for the REMP and the ISFSL...........................................37 APPENDIX B Analysis Results for the REMP and the ISFSI............................................... 46 APPENDIX C Quality Assurance Program............................................................................. 68 APPENDIX D Land Use Survey................................................................................................ 86 APPENDIX E Additional Samples and Analysis Results....................................................... 87

LIST OF FIGURES Figure Title Page January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 1 Tritium in Chesapeake Bay Water..................................................................................... 11 2 Silver-I IOm and Potassium-40 in Chesapeake Bay Oysters............................................12 3 Nuclear Fallout in the Calvert Cliffs Area.........................................................................14 4a Mean TLD Gamma Dose, Calvert Cliffs Nuclear Power Plant......................................... 17 4b 2019 Quarterly TLD Gamma Dose, per Location, Calvert Cliffs Nuclear Power Plant...18 5 Atmospheric Dispersion Around CCNPP Average Relative Air Concentrations (X/Q)... 22 6 Atmospheric Dispersion Around CCNPP Average Relative Ground Deposition (D/Q).. 23 7 Mean TLD Gamma Dose, ISFSI.........................................................................-.............. 32 A-1 Map of Southern Maryland and Chesapeake Bay Showing Location of Calvert Cliffs Nuclear Power Plant.......................................................................................................... 40 A-2 Calvert Cliffs Nuclear Power Plant Sampling Locations, 0-2 Miles.................................41 A-3 Calvert Cliffs Nuclear Power Plant Sampling Locations, 0-10 Miles...............................42 A-4 Independent Spent Fuel Storage Installation Sampling Locations....................................44 A-5 Enlarged Map of the Independent Spent Fuel Storage Installation Sampling Locations..45 E-1 Site Map Groundwater Monitoring Wells.......................................................................102 E-2 Site Map Rainwater Locations......................................................................................... 102 ii

LIST OF TABLES Table Title Page January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 1 Synopsis of 2019 Calvert Cliffs Nuclear Power Plant Radiological Environmental Monitoring Program........................................................................................................... 24 2 Annual Summary of Radioactivity in the Environs of the Calvert Cliffs Nuclear Power Plant Units 1 and 2............................................................................................................. 25 3 Synopsis of2019 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Radiological Environmental Monitoring Program......................................... 33 4 Annual Summary of Radioactivity in the Environs of the Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation............................................................ 34 A-1 Locations of Environmental Sampling Stations for the Calvert Cliffs Nuclear Power Plant

                                                                                                                                                                                                                                                                                        • 39 A-2 Locations of Environmental Sampling Stations for the Independent Spent Fuel Storage Installation at Calvert Cliffs..............................................................................................43 B-1 Concentration of Tritium and Gamma Emitters in Bay Water..........................................48 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish.........................................49 B-3 Concentration of Gamma Emitters in Oyster Samples...................................................... 50 B-4 Concentration of Gamma Emitters in Shoreline Sediment................................................ 51 B-5 Concentration of Iodine-131 in Filtered Air...................................................................... 52 B-6 Concentration of Beta Emitters in Air Particulates............................................................ 54 B-7 Concentration of Gamma Emitters in Air Particulates...................................................... 58 B-8a Concentration of Gamma Emitters in Vegetation Samples............................................... 59 B-8b Concentration of Gamma Emitters in Vegetation From Locations Around the ISFSI...... 61 B-9 Concentration of Gamma Emitters in Soil Samples From Locations Around the ISFSI.. 62 B-10 Typical MDA Ranges for Gamma Spectrometry.............................................................. 63 B-11 Typical LLDs for Gamma Spectrometry........................................................................... 64 B-12 Direct Radiation................................................................................................................. 65 C-1 Results of Participation in Cross Check Programs............................................................ 70 C-2 Results of Quality Assurance Program.............................................................................. 75 C-3 Calvert Cliffs Nuclear Power Plant ODCM Required LLDs............................................. 85 D-1 Land Use Survey................................................................................................................ 86 E-1 Locations of Non-Tech Spec and Radiological Groundwater Environmental Sampling Stations for Calvert Cliffs Nuclear Power Plant................................................................ 89 E-2 Synopsis of 2019 Calvert Cliffs Nuclear Power Plant Non-Tech Spec Radiological Environmental Monitoring Program.................................................................................. 90 E-3 Annual Summary for Calvert Cliffs Nuclear Power Plant Units 1 & 2 Non-Tech Spec Radiological Environmental Monitoring Program............................................................ 91 E-4 Concentration of Gamma Emitters in Bottom Sediment................................................... 92 E-5 Concentration oflodine-131 in Filtered Air...................................................................... 93 E-6 Alpha Isotopic and Pu-241 in Groundwater...................................................................... 95 E-7 Gross Alpha and Gross Beta Activity in Groundwater...................................................... 96 lll

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 E-8 Concentration of Radiostrontium in Groundwater............................................................ 97 E-9 Concentration of Tritium in Groundwater......................................................................... 98 E-10 Concentration of Tritium in Surface Water, Precipitation, and Subsurface Drainage....... 99 E-11 Gross Concentration of Gamma Emitters in Groundwater.............................................. 100 E-12 Gross Concentration of Gamma Emitters in Surface Water, Precipitation and MH....... 101 iv

I.

SUMMARY

January 1 - December 31, 2019 .Docket Nos.50-317/50-318/72-8 During 2019, Calvert Cliffs Nuclear Power Plant (CCNPP) Units 1 and 2, a total of2447 radiological analyses were performed, and the analytical results reviewed. Most of these analyses were performed to satisfy the requirements of the Offsite Dose Calculation Manual (ODCM) (Ref. 6), the Environmental Technical Specifications (Ref. 5) and the Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications (Ref. 10). Some of these samples, although not required by either the ODCM or the Technical Specifications, were collected to maintain our commitments to the surrounding community and to maintain historical continuity of the CCNPP Radiological Environmental Monitoring Program (REMP) that started in 1970. The entire monitoring program in place around CCNPP is divided into three parts: the original REMP, the ISFSI monitoring program, and the Non-ODCM Radiological Environmental Monitoring. The following paragraphs describe each of these parts in more detail. A total of 944 radiochemical analyses were performed on 906 environmental samples; and 546 thermo luminescent dosimeters (TLDs) were analyzed for ambient radiation exposure rates as part of the original REMP. These analyses were performed to satisfy the requirements of the ODCM (Ref. 6) and the Environmental Technical Specifications (Ref. 5). For the ISFSI monitoring program, 320 radiochemical analyses were performed on 300 environmental samples, 224 of which were in common with the original REMP. In addition, 480 TLDs, 24 in common with the original REMP, were analyzed for ambient radiation exposure rates. These analyses were performed to satisfy the requirements of the ODCM (Ref. 6) and the ISFSI Technical Specifications (Ref. 10). Lastly, 229 radiochemical analyses were performed on 183 quality assurance samples and 120 quality assurance TLDs were analyzed as part of an internal and external quality assurance program associated with Teledyne Brown Engineering. Laboratory inter-comparison samples obtained from Environmental Resource Associates (ERA) and Analytics' Inc. were also analyzed. Samples collected from the aquatic environment included bay water, fish, oysters, and shoreline sediment. Bay water was analyzed for tritium and gamma emitters. Fish, oysters, and shoreline sediments were analyzed for gamma emitting radionuclides. Monitoring the atmospheric environment involved sampling the air at various locations surrounding CCNPP and the ISFSL Air particulates and gaseous iodine were collected on glass fiber filters and charcoal cartridges, respectively. The particulate filters were analyzed for beta activity and gamma emitting nuclides. The charcoal cartridges were analyzed for airborne gaseous radioiodine. Samples from the terrestrial environment consisted of vegetation and soil samples collected and analyzed for gamma emitters. Vegetation samples for the original REMP were also analyzed for 1-131. 5

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Measurements of direct radiation, as required by the ODCM, were performed by analyzing TLDs from forty-two locations surrounding CCNPP and the ISFSI. Natural radioactivity was detected in essentially all 2447 radiological analyses performed. Low . levels of man-made fission products were also observed in 9 of these analyses for the CCNPP REMP. One of these observations was for low level Tritium and is attributed to normal plant operations. The other 8 observations were for Cs-137 and attributed to fallout from past atmospheric weapons testing. Detailed discussions about the results of these analyses are contained in the body of this report. To assess the plant's contribution to the radiation levels of the ambient environment, dose* calculations were performed using 2019 data from the plant's effluent releases, 2019 on-site meteorological data, and appropriate pathways. The results of these dose calculations indicate:

a. a maximum thyroid dose of 7.39 x 10-4 mrem via liquid and gaseous pathways, which is about 0.001 % of the acceptable limit of 75 mrem/yr as specified in 40CFR190 "Environmental Radiation Protection Standards for Nuclear Power Operations" and 1 0CFR 72.104, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste";
b. a maximum whole-body dose of 7. 78 x 10-4 mrem via liquid and gaseous pathways, which is about 0.003% of the acceptable limit of 25 mrem/yr as specified in both 40CFR190 and 10CFR72.104; and
c. a maximum calculated dose to all other organs via liquid and gaseous pathways was equal to 1.22 x 10-3 mrem. This dose is about 0.005% of the allowable limit of25 mrem/yr as specified in both 40CFR190 and 10CFR72.104.

Thus, it is concluded based upon the levels of radioactivity observed and the various dose calculations performed, that CCNPP Units 1 and 2 and the ISFSI did not cause any significant radiological impact on the surrounding environment. 6

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 II. CALVERT CLIFFS NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM II.A. INTRODUCTION The REMP has been conducted in the vicinity of CCNPP since the summer of 1970. The Calvert Cliffs site is an operating nuclear generating station consisting of two pressurized water reactors. Unit 1 achieved criticality on October 7, 1974 and commenced commercial operation in May 1975. Unit 2 achieved criticality on November 30, 1976 and went into commercial operation April 1, 1977. The location of the plant in relation to local metropolitan areas is shown on Figure A-1. Results of the monitoring program for the pre-operational period have been reported in a series of documents (Ref. 1-4). The results from previous operational periods are contained in annual reports submitted to the Nuclear Regulatory Commission (NRC) as required. Results of the monitoring program for the current operational period are included in this report. The report presents the content of the REMP (Table 1), the sampling locations (Appendix A), the summary of the analytical results (Table 2), a compilation of the analytical data (Appendix B), the results of the Interlaboratory Comparison Program and the Quality Assurance Program (Appendix C), the results of the Land Use Survey (Appendix D), and a compilation of the analytical data for extra samples collected (Appendix E). Interpretation of the data and conclusions are presented in the body of the report. The environmental surveillance data collected during this reporting period were compared with that generated in previous periods whenever possible to evaluate the environmental radiological impact of CCNPP Units 1 and 2. 11.B. PROGRAM 11.B.1 Objectives The objectives of the REMP for the Calvert Cliffs Nuclear Power Plant are:

a. To verify that radioactivity and ambient radiation levels attributable to plant operation are within the limits specified in the ODCM (Ref. 6) and the Environmental Radiation Protection Standards as stated in 40CFR190,
b. To detect any measurable buildup of long-lived radionuclides in the environment,
c. To monitor and evaluate ambient radiation levels, and
d. To determine whether any statistically significant increase occurs in the concentration of radionuclides in important pathways.

7

11.B.2 Sample Collection January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 The locations of the individual sampling stations are listed in Table A-1 and shown in Figures A-2 and A-3. All samples were collected by contractors to, or personnel of Exelon Generation according to Procedures (Ref. 7, 12 and 15). 11.B.3 Data Interpretation Many results in environmental monitoring occur at or below the minimum detectable activity (MDA). In this report, all results at or below the relevant MDA are reported as being "less than" the MDA value. 11.B.4 Program Exceptions There were two program exceptions during this operating period. A GFCI trip on the air sampler resulted in a lost Sample at A2 for air iodine and air particulate for the week ending May 28th, 2019. This event was entered into the site's corrective action program to prevent future occurrences. DR19 data for Quarter 4 was rejected by the laboratory due to water damaged dosimeters. The plastic bag the dosimeters were in did not hold its seal and was wet at the time of retrieval. The dosimeter was dried, gave erroneous data and was rejected. The event was entered in the corrective action program to document the issue and trend future events should they occur. Calvert Cliffs began adopting the requirements of ANSI/HPS N13.34, Environmental Dosimetry, as suggested in NRC Regulatory Guide 4.3, Rev 2, in June 2018. The mean 90-day ambient radiation was reported for the first quarter of 2018. Beginning in June 2018, ambient radiation was reported as a 91-day average. In early 2020, the calculation for Facility-related dose was finalized and the dosimetry results from 2018 were re-calculated to correct for Extraneous dose: This event was entered in the corrective action program to document the deviation and track re-calculation of the 2018 data. After correction for Extraneous Dose, the 2018 mean 91-day ambient radiation measured at the indicator locations was 8.57 mR and ranged from 4.84 to 14.00 mR. The control locations showed a mean 91-day measurement of 9.99 mR with a range of 6.73 to 14.50 mR. The location with the highest overall mean of 12.08 mR was Taylors Island, Anderson's Property (sample code DR23) which ranged from 11.00 to 14.50 mR. A comparison of the 2018 non-corrected vs corrected results is shown in the table below. Facility-related dose was not detected at any of the monitoring locations in 2018. 8

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 2018 Ambient Radiation Quarterly (91-Day) Summary Mean(mR) Range (mR) Mean (mR) Range (mR) Corrected for Corrected for Extraneous Dose Extraneous Dose Indicator Locations 11.75 9.29-16.56 8.57 4.84-14.00 Control Locations 13.19 11.11-17.25 9.99 6.73-14.50 Highest Overall 15.38 14.40- 17.25 12.08 11.00- 14.50 Location (DR23) 11.C. RESULTS AND DISCUSSIONS All the environmental samples collected during the year were analyzed using Exelon Industrial Services laboratory procedures (Ref. 8), except Tritium which was analyzed by Teledyne Brown Engineering (Ref. 14). The analytical results for this reporting period are presented in Appendix Band are also summarized in Table 2. For discussion, the analytical results are divided into four categories. The categories are Aquatic Environment, Atmospheric Environment, Terrestrial Environment, and Direct Radiation. These categories are further divided into subcategories according to sample type (e.g. Bay Water and Aquatic Organisms for Aquatic Environment). 11.C.l Aquatic Environment The aquatic environment surrounding the plant was monitored by analyzing samples of bay water, aquatic organisms, and shoreline sediment. The samples were obtained from various sampling locations on the Chesapeake Bay near the plant. II.C.1.a Bay Water Monthly bay water samples were taken from two locations during the year. These locations are the Intake Area (sample code WAI) and the Discharge Area (sample code WA2). Composite samples were obtained from each*location for the entire sampling period. These samples were analyzed for tritium and gamma emitters. The tritium analyses, performed on quarterly composites of the monthly bay water samples, revealed one result for tritium at the Discharge Area (sample code W A2) in the first quarterly sample collected from 12/31/2018 to 03/29/2019 at 385 +/- 201 pCi/L. Figure 1 compares tritium observed in the plant discharge and intake with annual effluent releases as reported in the Radioactive Effluent Release Report. Monthly analyses of bay water samples from both locations for gamma emitters exhibited no detectable concentrations of any plant-related radionuclides. 9

11.C.1.b Aquatic Organisms January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Twelve samples of aquatic organisms were obtained from four locations during the year. Samples of fish, when in season, are normally collected from the Discharge Area (sample codes IAl and IA2) and from the Patuxent River (sample codes IA4 and IA5). As shown in Table B-2, two species of fish were sampled at both the plant discharge and the control point in the Patuxent River. Oyster samples were obtained quarterly from Camp Conoy (sample code IA3) and Kenwood Beach (IA6). Figure 2 compares K-40 and Ag-1 lOm observed in oysters from Camp Conoy (IA3) with annual effluent releases of Ag-11 Om as reported in the Radioactive Effluent Release Report. Edible portion of the fish and oyster samples were analyzed for gamma emitters. Gamma spectrometric analyses of the fish exhibited naturally occurring K-40 but no detectable concentrations of any plant-related radionuclides. Oyster samples likewise exhibited naturally occurring K-40 but no detectable concentrations of any plant-related radionuclides. 11.C.1.c Shoreline Sediment Semiannual shoreline sediment samples are taken from one location during the year. This location is Shoreline at Barge Road (sample code WBl). The semiannual shoreline sediment samples obtained from this location were analyzed for gamma emitters.

  • Gamma spectrometric analyses of these samples exhibited naturally occurring radionuclides, but no detectable concentration of any plant-related radionuclides.

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 FIGURE 1 Tritium in Chesapeake Bay Water 1100 'S-909 - g 700 r:: Ill

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.§ 0.05 !lo FIGURE2 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Silver-ll0m and Potassium-40 in Chesapeake Bay Oysters ~ 0 I ~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 ~ ~ ~ oo oo oo oo oo m m m m m o o o o o .-1 rl rl rl rl N Calendar Year 7000~-------~ 0 § 6000 - u i 5000 I'll u- ~ Ji 4000 QJ -! ~ 3000 C *e 2000 0... 1000

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~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 ~ ~ ~ oo oo oo oo oo m m m m m o o o o o rl rl rl rl rl N Calendar Vear ~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 N ~ W 00 0 ~ ~ ~ oo oo oo oo oo m m m m m o o o o o rl rl rl rl rl N Calendar Year 12

11.C.2 Atmospheric Environment January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 The atmospheric environment was monitored by analyzing air particulate filters and charcoal cartridges (for trapping radioiodine species). Samples were collected from eight locations surrounding the plant. The locations are On Site Before Entrance to Camp Conoy (sample code Al), Camp Conoy Road at the Emergency Siren (sample code A2), Bay Breeze Road (sample code A3), Route 765 at Lusby (sample code A4), and at the Emergency Operations Facility (sample code A5), Meteorological Station (sample code SFAl), NNW ofISFSI (sample code SFA3), and SSE ofISFSI (sample code SFA4). Sample locations Al, SFAl, SFA3, and SFA4 are common to the REMP monitoring program and the ISFSI monitoring program. 11.C.2.a Air Particulate Filters Weekly composite air particulate filter samples were collected from the eight locations, referenced, above during the year. These samples were analyzed for beta activity and gamma emitters. Weekly analyses for beta activity on air particulate filters collected from all eight locations showed values characteristic of background levels. The values ranged from 1.0 x 10-2 to 3.4 x 10-2 pCi/m3 for the indicator locations and 1.1 x 10-2 to 3. 7 x 10-2 pCi/m3 at the control location. The location with the highest overall mean of 2.0 x10-2 pCi/m3 was A5, Emergency Operations Facility. Gamma spectrometric analyses of monthly composited air particulate samples exhibited no detectable concentrations of any plant-related radionuclides in any of these samples. Naturally occurring radionuclides, such as Be-7, were detected in nearly all samples. Figure 3 depicts the historical trends of beta activity. 11.C.2.b Air Iodine Weekly composited charcoal cartridges (for trapping radioiodine species) were collected from the eight locations, referenced above, during the year. These samples were analyzed for radioiodine species and exhibited no detectable concentrations ofl-131 during the year. Figure 3 depicts the historical trends of manmade radioiodine activity for location A4, Route 765 at Lusby including the impact I-131 due to significant events such as the fallout resulting from the accident event at Chernobyl in 1986 and the accident event at Fukushima Daiichi in 2011. 13

250 ~200 E g § 150 ~ 'E Q) g 100 0 () ~ 50 0 1200 ,-...1000 C"") § g C 800 0 ~ i::: ~ 600 C: 0 (.) ~ 400 ca Ul Ul e c, 200 0 FIGURE3 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Nuclear Fallout in the Calvert Cliffs Area SURFACE AIR VAPORS, LUSBY, MD (A4) ATMOSPHERIC FALLOUT From Chernobyl U> 00 O N V U> 00 0 00000lCJ'\\O"IO"IO"IO ATMOSPHERIC FALLOUT From Weapons Testing ATMOSPHERIC FALLOUT From Weapons Testing Calendar Year ATMOSPHERIC FALLOUT From Chernobyl ATMOSPHERIC FALLOUT From Fukushima DaHchi Nst-'>000 rl rl .--i .-I N ~ ~ a, .--i m ~ ~ m .--i m ~ ~ a, rl m ~ ~ m rl m ~ ~ m rl ~ ~ ~ 00 00 oo 00 00 a, m m m m o o o o o rl rl rl .--i .--i N Calendar Year 14

11.C.3 Terrestrial Environment January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 The terrestrial environment was monitored by analyzing samples of vegetation collected monthly, when available, from various sampling locations near the plant during the normal growing season. 11.C.3.a Vegetation Vegetation samples were collected from three locations during the year. These locations are On Site Before Entrance to Camp Conoy (sample codes IB4, IB5, and IB6), the Emergency Operations Facility (sample codes IB7, IB8, and IB9), and the Garden Plot at Meteorological Station (sample codes IBl0, IBl 1, and 1B 12). These samples were analyzed for gamma emitters, including analyses for I-131. All samples showed detectable amounts of naturally occurring K-40 and Be-7. No plant related radionuclides were found in any of these samples. 11.C.4 Direct Radiation Direct radiation is measured by a network of TLDs in each overland sector surrounding the plant, both at the plant boundary and at 4 miles from the plant. TLDs were collected quarterly from twenty-three locations surrounding the plant. The twenty indicator locations are On Site Along the Cliffs (sample code DRl), Route 765 Auto Dump (sample code DR2), Giovanni's Tavern (sample code DR3), Route 765 Across from White Sand Dr (sample code DR4), Route 765 at John's Creek (sample code DR5), Lusby (sample code DR6), On Site before the Entrance to Camp Conoy (sample code DR7), On Site at Emergency Siren (sample code DR8), Bay Breeze Road (sample code DR9), Calvert Beach Road & Decatur St (sample code DRl0), Dirt Road off Mackall Rd & and Parran Rd (sample code DRl I), Bowen Rd & Mackall Rd (sample code DRl2), Mackall Rd near Wallville (sample code DR13), Rodney Point (sample code DR14), Mill Bridge Rd & Turner Rd (sample code DRl5), Across from Appeal School (sample code DR16), Cove Point Rd & Little Cove Point Rd (sample code DRI 7), Cove Point (sample code DR18), Long Beach (sample code DR19), and Onsite Near Shore (sample code DR20). The three control locations are the Emergency Operations Facility (sample code DR21), Solomons Island (sample code DR22), and Taylors Island, Anderson's Property (sample code DR23). In June of2018 the site adopted the requirements of the updated ANSI 13.34 standard which measures mean 91-day ambient radiation. The 2019 mean 91-day ambient radiation measured at the indicator locations was I 0.49 mR and ranged from 4.50 to 17.60 mR as reported in Table 2. The control locations showed a 91-day mean of 12.22 mR with ranges from 5.64 to 20.50 mR. The location with the highest overall mean of 15.06 was Taylors Island, Anderson's Property (sample code DR23) which ranged from 8.96 to 20.50 mR. Figure 4-a depicts the long-term trend of mean TLD exposure for the 4-mile, Control Location, and On-Site TLDs. The results for 2018 and 2019 were corrected for Extraneous Dose, which accounts for the slight downward shift in the baseline beginning in 2018. Figure 4-b depicts quarterly exposure at each TLD 15

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 location in 2019, with the locations ranked by increasing exposure. From these graphs, it can be seen that there is a slight bias towards higher exposure at the control locations highlighted in bold. This is predominantly due to the higher background radiation at DR23 (Taylor's Island, 7.8 miles from CCNPP). This slight bias is due to normal variations in background radiation levels and is consistent with pre-operational data. For example, in figure 4a this trend can be observed in the first calendar year of the graph, 1973, which was a year prior to the first criticality of Unit 1 (October 7, 1974). Facility-related dose was not detected at any of the monitoring locations in 2019. 16

V, > Ill C 6 5 4 0 3 l"l'I - a: E 2 1 FIGURE 4a January l - December 31, 2019 Docket Nos. 50-3 17 /50-318/72-8 Mean TLD Gamma Dose, Calvert Cliffs Nuclear Power iPiant(BAP1JJBAP2J --+- 4 Miles (DRl0-18) -II-Control Locations (DR21-23) -+- On-Site (DRl, 7, 8, ) Calendar Year 17 J

70 60 50 a: 40 ..s a,... Ill 0 ~ 30 w 20 10 0 FIGURE 4b January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 2019 Quarterly TLD Gamma Dose, per Location, Calvert Cliffs Nuclear Power Plant 2019 Quarterly (91-Day) Exposure of Environmental TLDs DR19 DR18 DR03 DR06 DR02 DR09 DR07 DR12 DR22 DR16 DR11 DR15 DR14 OROS DR13 DR04 DR21 DR20 DR17 DROl DR08 DR23 TLD Location Ql Q2 Q3 Q4 18

19 January l - December 31, 2019 Docket Nos. 50-3 l 7 /50-318/72-8

11.D. CONCLUSION January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 No man-made fission or activation by-products attributable to plant operations were observed in the environment surrounding the plant during the year. Historical trends for tritium in bay water, Ag-1 lOm and K-40 in oyster samples, nuclear fallout in the Calvert Cliffs area, and TLD data are depicted in Figures 1 through 4. As can be seen from these figures, the plant made no adverse radiological contributions to the surrounding environment. To assess the plant's contribution to the ambient radiation levels of the surrounding environment, dose calculations were performed using the plant's 2019 effluent release data, on site meteorological data (see X/Q and D/Q values presented in Figures 5 and 6), and appropriate pathways. The results of these dose calculations indicate: Gaseous Pathways A maximum thyroid dose of 1.77 x 104 mrem to a child via the plume, ground, vegetable, and inhalation pathways at 2. 7 miles WNW of the containments at Calvert Cliffs. This is about 0.0002% of the acceptable limit of 75 mrem/yr as specified in 40CFRI 90 and 1 OCFR 72.104. A maximum whole-body gamma dose of 4.36 x I 0-5 mrem to a child at 2.7 miles WNW of the containments at Calvert Cliffs. This is about 0.0002% of the acceptable dose limit of 25 mrem/yr as specified in 40CFR190 and 1 OCFR72. l 04. A maximum dose to any other organ, in this case the skin, of 4.75 x 10-5 mrem to a child at 2.7 miles WNW of the containments at Calvert Cliffs. This is about 0.0002% of the acceptable dose limit of25 mrem/yr as specified in 40CFR190 and 10CFR72.104. Liquid Pathways A maximum thyroid dose of 5.62 x I 0-4 mrem to a teenager for all liquid pathways, which is about 0.001 % of the acceptable dose limit of75 mrem/yr as specified in 40CFR190 and IOCFR72.104. A maximum whole-body dose of7.34 x 104 mrem to a teenager via all liquid pathways, which is about 0.003 % of the acceptable dose limit of 25 mrem/yr as stated in 40CFR190 and 10CFR72.104. A maximum dose to any other organ, in this case bone, of 1. 17 x 10-3 mrem to a teenager for all pathways, which is 0.005% of the acceptable dose limit of 25 mrem/yr specified in 40CFR190 and 10CFR72.104. 20

Gaseous and Liquid Pathways Combined January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 A maximum thyroid dose of 7.39 x 10-4 mrem via liquid and gaseous pathways, which is about 0.001 % of the acceptable limit of 75 mrern/yr as specified in 40CFR190 and 1 0CFR 72. 104. A maximum whole-body dose of 7. 78 x 10-4 mrem via liquid and gaseous pathways, which is about 0.003% of the acceptable limit of 25 mrem/yr as specified in 40CFR190 and 10CFR72.104. A maximum calculated dose to all other organs via liquid and gaseous pathways is equal to 1.22 x 10-3 mrem. This dose was about 0.005% of the allowable limit of 25 mrem/yr as specified in 40CFR 190 and 1 0CFR 72.104. In all cases, the calculated doses are a small fraction of the applicable limits specified in 40CFR190 and 10CFR72.104. Therefore, it is concluded that the operation of Calvert Cliffs Units 1 and 2 produced radioactivity and ambient radiation levels significantly below the limits of the ODCM, 40CFR190, and 10CFR72.104. There was no significant buildup of plant-related radionuclides in the environment due to the operation of the CCNPP in 2019. 21

FIGURES January l - December 31, 201 9 Docket Nos. 50-317/50-31 8/72-8 Atmospheric Dispersion Around CCNPP Average Relative Air Concentrations (X/Q) \\ ~ \\ 1 .OV.11;,. [/' ~ -1~ ,,,_I I - / r- ~ SOCltty'H~ ~ -v- _....,.r ) * ',

  • R

.::,;:.~~.:&..;~~:.:.:.::r.;-i::....:.+ ~ Buuvi,e r ver NutT~ l<:S, 15000 efS SlnDn lvert Clffs 2019 22

  • f l FIGURE 6 January 1 - December 31, 2019 Docket Nos. 50-317/50-31 8/72-8 Atmospheric Dispersion Around CCNPP Average Relative Ground Deposition (D/Q)

,verN&a,T~k!, 15000 ftf.S Stm>n -..,;,,a..lvert Cliffs 2019 23

Table 1 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Synopsis of2019 Calvert Cliffs Nuclear Power Plant Radiological Environmental Monitoring Program Sample Type Sampling Number of Number Analysis Analysis Number Frequency 1 Locations Collected Frequency1 Analyzed Aquatic Environment Bay Water, Surface MC 2 24 Gamma MC 24 Water, Drinking Water H-3 QC 8 Fish2 A 4 4 Gamma A 4 Oysters Q 2 8 Gamma Q 8 Shoreline Sediment SA 1 2 Gamma SA 2 Atmospheric Environment Air Iodine3 w 8 416 I-131 w 415 Air Particulates4 w 8 416 Gross Beta w 415 Gamma QC 32 Direct Radiation Ambient Radiation Q 23 552 TLD Q 546 Terrestrial Environment Vegetation5 M 3 36 Gamma M 36 1 W=weekly, M=monthly, Q=quarterly, SA=semiannual, A=annual, C=composite 2 Once in Season, July through September 3 The collection device contains charcoal 4 Beta counting is performed after >72-hour decay, Gamma spectroscopy performed on monthly composites of weekly samples 5 Monthly during growing season when available 24

Medium or Pathway Type and Total Sampled (Unit of Number of Analyses Measurement) Performed Aquatic Environment Bay Water, Surface H-3 (8) Water, Drinking Water (pCi/L) Atmospheric Environment Air Particulates Gross Beta ( 415) (10-2 pCi/m3) Direct Radiation Ambient Radiation TLD (546) (mR/91 days) Table 2 Annual Summary of Radioactivity in the Environs of the Calvert Cliffs Nuclear Power Plant Units 1 and 2 Lower Limit of Indicator Locations Location with Detection (LLD) Mean (F)/Range1 Highest Annual Mean Name/Distance & Direction2 200pCi/L 385 (1/4) Discharge Vicinity WA2 0.3 kmN 0.5 2.0 (363/364) EOFA5 (1.0-3.4) 19.3 km WNW 10.49 (474/480) Taylors Island (4.50-17.60) DR23 12.4 km ENE January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Highest Annual Control Locations Mean (F) / Range 1 Mean (F)/Range 385 (1/4) 2.0 (52/52) 2.0 (52/52) (l.1-3.7) (1.1-3.7) 15.07 (24/24) 12.22 (72/72) (8.96-20.5) (5.64-20.5) 1 Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses. 2 Distance and direction from the central point between the two containment buildings. 25

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 III. INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM III.A. INTRODUCTION In August 1990 BOE initiated a program of additional radiological environmental monitoring around the site for the Independent Spent Fuel Storage Installation (ISFSI). The first dry fuel storage canister was loaded into the ISFSI in November of 1993 with more canisters being loaded in subsequent years. During 2019, five additional canisters of spent fuel were transferred to the ISFSI. Results of the monitoring program for the ISFSI for the current period are included in this report. This report presents the content of the ISFSI REMP (Table 3), the ISFSI sampling locations (Appendix A), the summary of the analytical results of the period (Table 4), and a compilation of the analytical data for the period (Appendix B). Interpretation of the data and conclusions are presented in the body of the report. The ISFSI monitoring program is as described in this section of the report. The results were compared with that generated during the previous ISFSI pre-operational periods (Ref. I I) and the current and previous CCNPP REMP periods. These results are discussed in more detail in Section III. C. 111.B. PROGRAM 111.B.1 Objectives The objectives of the radiological environmental monitoring program for the ISFSI are:

a. To satisfy the community concern regarding the impact of the ISFSI on the environment,
b. To verify that radioactivity and ambient radiation levels attributable to operation of the ISFSI are within the limits specified in the Environmental Radiation Protection Standards as stated in 40CFRPartl 90 and 10CFR72.104,
c. To detect any measurable buildup oflong-lived radionuclides in the environment due to the ISFSI,
d. To monitor and evaluate ambient radiation levels around the ISFSI, and
e. To determine whether any statistically significant increase occurs in the concentration of radionuclides near the ISFSI.

26

111.B.2 Sample Collection January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 The locations of the individual sampling sites are listed in Table A-2 and shown in Figures A-4 and A-5. All samples were collected by contractors to, or personnel of, Exelon Industrial Services personnel according to Exelon Industrial Services Laboratory Procedures (Ref. 7). 111.B.3 Data Interpretation Many results in environmental monitoring occur at or below the minimum detectable activity (MDA). In this report, all results at or below the relevant MDA are reported as being "less than" the MDA value. 111.B.4 Program Exceptions There were no program exceptions to the ISFSI Program in 2019. Calvert Cliffs began adopting the requirements of ANSI/HPS N13.34, Environmental Dosimetry, as suggested in NRC Regulatory Guide 4.3, Rev 2, in June 2018. The mean 90-day ambient radiation was reported for the first quarter of 2018. Beginning in June 2018, ambient radiation was reported as a 91-day average. In early 2020, the calculation for Facility-related dose was finalized and the dosimetry results from 2018 were re-calculated to correct for Extraneous dose. This event was entered in the corrective action program to document the deviation and track re-calculation of the 2018 data. After correction for Extraneous Dose, the 2018 mean 91-day ambient radiation measured at the indicator locations was 27.24 mR and ranged from 6.12 to 70.60 mR. The control location shows a mean 91-day measurement of 9.95 mR with a range of 8.09 to 12.5 mR. The location with the highest overall mean of 59.63 mR was Southeast ofISFSI (sample code SFDR-14) which ranged from 50.00 to 70.60 mR. A comparison of the 2018 corrected vs non-corrected results is shown in the table below. 2018 ISFSI Ambient Radiation Quarterly (91-Day) Summary Exposure (mR) Range (mR) Exposure (mR) Range (mR) Corrected for Corrected for Extraneous Dose Extraneous Dose Indicator Locations 30.45 10.01 - 69.51 27.24 6.12 - 70.60 Control Location 13.23 12.47 - 14.00 9.95 8.09 - 12.5 Highest Overall 62.32 51.1 7-69.51 59.63 50.00- 70.60 Location (SFDR14) Facility-related dose was detected SSE of ISFSI (sample code SFDR9); South of ISFSI (sample code SFDR13); SE ofISFSI (sample code SFDR14); ENE ofISFSI (sample code SFDR15); SW ofISFSI (sample code SFDR16). This is expected as additional spent fuel casks are installed at the ISFSI each year. The ISFSI TLDs are located directly around the perimeter of the ISFSI. Due to the proximity of these TLDs to the spent fuel storage structures, they detect the small increase in radiation exposure each year. However, it is clear from Figure 4a that there is no observable direct radiation exposure of the public from the ISFSI, as the other REMP TLDs 27

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 (on-site, 4 miles, and beyond) show no observable increase in exposure when compared to control TLDs. The 2018 mean 91-day Facility-related dose measured at the indicator locations was 18.04 mR and ranged from 5.33 to 52.50 mR. Facility-related dose was not detected at the indicator location. The location with the highest overall mean of 41.5 8 mR was Southeast of ISFSI (sample code SFDR14 which ranged from 31.90 to 52.50 mR.A summary ofthe 2018 results is shown in the table below. 2018 ISFSI Facility-related Dose Quarterly (91-Day) Summary Exposure (mR) Range (mR) Indicator Locations 18.04 5.33-52.50 Control Location Not Detected NIA Highest Overall Location (SFDR14) 41.58 31.90- 52.50 111.C. RESULTS AND DISCUSSIONS All the environmental samples collected were analyzed using Exelon Industrial Services laboratory procedures (Ref. 8). The analytical results for this reporting period are presented in Appendix B and are also summarized for the period in Table 4. For discussion, the analytical results are divided into three categories. The categories are Atmospheric Environment, Terrestrial Environment, and Direct Radiation. These categories are further divided into subcategories according to sample type (e.g., Vegetation and Soil for Terrestrial Environment). 111.C.1 Atmospheric Environment The atmospheric environment was monitored by analyzing air particulate filters. These samples were collected from five locations surrounding the ISFSI. No source of airborne radioiodine exists for the ISFSI. Airborne radioiodine is, therefore, not considered in assessing the radiological impact of the ISFSI. 111.C.1.a Air Particulate Filters Weekly composite air particulate filter samples were collected from five locations during the period. These locations are On Site Before the Entrance to Camp Conoy (sample code Al), Meteorological Station (sample code SF Al), CCNPP Visitor's Center (sample code SFA2), NNW of the ISFSI (sample code SFA3), and SSE of the ISFSI (sample code SFA4). Sample locations Al, SFAl, SFA3, and SFA4 are in common with CCNPP REMP Program. All samples were analyzed for beta radioactivity and gamma emitting radionuclides. Weekly analyses for beta activity on air particulate filters collected from all five locations showed values characteristic oflevels routinely observed in the REMP. These values ranged 28

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 from 1.0 x 10-2 to 3.1 x 10-2 pCi/m3 for the indicator locations and 1. 1 x 10-2 to 3.2 x 10-2 pCi/m3 for the control location. The location with the highest overall mean of2.0 x 10-2 pCi/m3 was SFA3, NNW of the ISFSI. Gamma spectrometric analyses of quarterly composited air particulate samples exhibited no detectable concentrations of any plant-related radionuclides in any of these samples. Naturally occurring radionuclides, such as Be-7, were detected in nearly all samples. 111.C.2 Terrestrial Environment The terrestrial environment was monitored by analyzing samples of vegetation and soil collected quarterly from the vicinity of the air sampling locations for the ISFSI. 111.C.2.a Vegetation Vegetation samples were collected quarterly from five locations during the year. These locations are Meteorological Station (sample code SFBl), CCNPP Visitor's Center (sample code SFB2), NNW of the ISFSI (sample code SFB3), SSE of the ISFSI (sample code SFB4), and On Site Before the Entrance to Camp Conoy (sample code SFB5). No detectable concentrations of plant-related radionuclides were found in any of these samples. Naturally occurring radionuclides such as K-40 were detected in all samples. 111.C.2.b Soils Soil samples were collected quarterly from five locations surrounding the ISFSI in the vicinity of the air samplers. These locations are: Meteorological Station (sample code SFS 1 ), CCNPP Visitor's Center (sample code SFS2), NNW of the ISFSI (sample code SFS3), SSE of the ISFSI (sample code SFS4), and On Site before the Entrance to Camp Conoy (sample code SFS5). Soil samples were analyzed for gamma emitting radionuclides. Cesium-137 was detected in eight quarterly samples from indicator locations. The Cs-137 concentrations ranged from 58 +/- 28 to 135 +/- 50 pCi/kg. While the presence of Cs-137 in these samples may be plant-related, this range is consistent with that found to be due to the residual fallout from past atmospheric nuclear weapons testing. The activities of this radionuclide are well below the federal limits established . in 40CFR190 and 10CFR72.104. These are comparable to those observed in previous annual reporting periods for the CCNPP REMP and in the earlier pre-operational data for the ISFSI. No detectable concentrations of plant-related radionuclides were found in any of these samples. Naturally occurring radionuclides such as K-40 were also detected in all these samples. 111.C.3 Direct Radiation Direct radiation is measured by a network of TLDs surrounding the ISFSI. These TLDs are collected quarterly from nineteen locations surrounding the ISFSI, plus one control TLD location at the Visitor's Center (sample code SFDR7). The locations include On Site Before the Entrance to Camp Conoy (sample code DR7, common to both the CCNPP Program and the ISFSI Program) and the Meteorological Station (sample code DR30, previously a location maintained 29

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 for historical continuity.) The other sampling locations are SW of ISFSI, (sample code SFDRl); N ofISFSI (sample code SFDR2); North of ISFSI (sample code SFDR3); NE of ISFSI (sample code SFDR4); East ofISFSI (sample code SFDR5); ESE ofISFSI (sample code SFDR6); NNW ofISFSI (sample code SFDR8); SSE ofISFSI (sample code SFDR9); NW ofISFSI (sample code SFDRlO); WNW ofISFSI (sample code SFDRl 1); WSW ofISFSI (sample code SFDR12); South ofISFSI (sample code SFDR13); SE ofISFSI (sample code SFDR14); ENE ofISFSI (sample code SFDR15); SW ofISFSI (sample code SFDR16); NNE ofISFSI (sample code SFDRl 7) and West of ISFSI (sample code SFDRl 8). Sampling locations are shown on Figures A-4 and A-5. The 2019 mean 91-day ambient radiation measured at the ISFSI indicator locations was 28.30 mR and ranged from 5.22 to 63.70 mR as reported in Table 4. The control location showed a 91-day mean of 12.83 mR and ranged from 8.02 to 16.40 mR. The location with the highest overall mean of 54.10 mR with a range of 43.90 to 63.7 mR was SFDR14, SE ofISFSI. These readings are consistent with those expected from the storage of spent fuel in the ISFSI. A comparison of the average monthly radiation levels per calendar year of the ISFSI TLD data from the indicator locations with the ISFSI control location_ at the Visitor's Center, SFDR7, can be seen in Figure 7. Facility-related dose was detected N of ISFSI (sample code SFDR2); NE of ISFSI (sample code SFDR4); East ofISFSI (sample code SFDR5); ESE ofISFSI (sample code SFDR6); SSE of ISFSI (sample code SFDR9); South ofISFSI (sample code SFDR13); SE ofISFSI (sample code SFDR14); ENE ofISFSI (sample code SFDR15); SW ofISFSI (sample code SFDR16). This is expected as additional spent fuel casks are installed at the ISFSI each year. The ISFSI TLDs are located directly around the perimeter of the ISFSI. Due to the proximity of these TLDs to the spent fuel storage structures, they detect the small increase in radiation exposure each year. However, it is clear from Figure 4a that there is no observable direct radiation exposure of the public from the ISFSI, as the other REMP TLDs ( on-site, 4 miles, and beyond) show no observable increase in exposure when compared to control TLDs. The 2019 mean 91-day Facility-related dose measured at the indicator locations was 13.92 mR and ranged from 5.24 to 45.70 mR. Facility-related dose was not detected at the indicator location. The location with the highest overall mean of 36.08 mR was Southeast of ISFSI (sample code SFDR14 which ranged from 25.90 to 45.70 mR. A summary of the 2019 results is shown in the table below. 2019 ISFSI Facility-related Dose Quarterly (91-Day) Summary Exposure (mR) Range (mR) Indicator Locations 13.92 5.24-45.70 Control Location Not Detected NIA Highest Overall Location (SFDR14) 36.08 25.90- 45.70 30

111.D. CONCLUSION January 1-December31,2019 Docket Nos. 50-317 /50-318/72-8 Low levels of Cs-13 7 were observed in the environment surrounding the ISFSI during the period. The Cs-137 observations were attributed to fallout from past atmospheric weapons testing. No plant-related radionuclides were observed in the environs of the ISFSI. In general, the results in the following tables continue the historical trends previously observed at the official sites of the CCNPP REMP. 31

VI > ro "O 12 10 8 ~ 6 - a: E 4 2 0 °' FIGURE 7 Mean TLD Gamma Dose, ~SFSitBAP4JJBAPSJ -+-- Control Location (SFDR7) ISFSI Mean (DR7, SFDRl-6, 8-18) N °' I.D °' 00 °' 0 0 N 0 0 I.D 0 Calendar Year 32 00 0 0 ,-t N ,-t January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 ,-t 00 ,-t 0 N

Sample Type Sampling Frequency 1 Atmospheric Environment Air Particulates2 w Direct Radiation Ambient Radiation Q Terrestrial Environment Vegetation Q Soil Q Table 3 Synopsis of 2019 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Radiological Environmental Monitoring Program Number of Number Analysis Locations Collected 5 260 Gross Beta Gamma 20 480 TLD 5 20 Gamma 5 20 Gamma 1 W=weekly, M=monthly, Q=quarterly, SA=semiannual, A=annual, C=composite January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Analysis Number Frequency1 Analyzed w 260 QC 20 Q 480 Q 20 Q 20 2 Beta counting is performed after >72-hour decay, Gamma spectroscopy performed on monthly composites of weekly samples 33

Medium or Pathway Sampled (Unit of Measurement) Atmospheric Environment Air Particulates (10*2 pCi/m3) Direct Radiation Ambient Radiation (mR/90 days) Terrestrial Environment Soil (pCi/kg) Table 4 Annual Summary of Radioactivity in the Environs of the January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation Type and Total Number of Analyses Performed Gross Beta (260) TLD (480) Gamma(20) Cs-137 Lower Limit of Detection (LLD) 0.5 Indicator Locations Mean (F)/Range1 2.0 (208/208) (1.0-3.1) 28.30 (456/456) (5.22-63.70) 91 (8/16) (58-135) Location with Highest Annual Mean Name/Distance & Direction2 NNW ofISFSI SFA3 0.1 kmNNW SE oflSFSI SFDR14 0.1 km SE NNW oflSFSI SFS3 0.1 kmNNW Highest Annual Mean (F) / Range1 2.0 (52/52) (1.1-3.l) 54.10 (24/24) (43.90-63.70) 102 (4/4) (87-135) Control Locations Mean (F)/Range 1.9 (52/52) (1.I-3.2) 12.83 (24/24) (8.02-16.40) 1 Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses. 2 Distance and direction from the central point between the two containment buildings. 34

IV. REFERENCES January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 (1) Cohen, L. K., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No. 882 Semiannual Report January-June 1971, December 1971; NUS No. 1025 Annual Report 1971, March 1973. (2) Cohen, L. K., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No. 1137 Annual Report 1972, December 1973. (3) Cohen, L. K. and Malmberg, M.S., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No. 1188, Annual Report 1973, October 1974. (4) Malmberg, M. S., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No. 1333, Data Summary Report, September 1970 to September 1974, July 1975 (5) Calvert Cliffs Nuclear Power Plant, Units 1 and 2, License Nos. DPR-53 and DPR-69, Technical Specification 5.6.2; Annual Radiological Environmental Operating Report. (6) CY-CA-170-301 Current Revision, Offsite Dose Calculation Manual for the Calvert Cliffs Nuclear Power Plant. (7) Exelon Industrial Services Sampling Procedures

a. CY-ES-214, Collection of ROPP Water Samples for Radiological Analysis
b. CY-ES-237, Air Iodine and Air Particulate Sample Collection for Radiological Analysis
b. CY-ES-239, EIS Collection Exchange of Field Dosimeters for Radiological Analysis
c. CY-ES-241, Vegetation Sample Collection for Radiological Analysis
d. CY-ES-242, Soil and Sediment Sample Collection for Radiological Analysis
e. CY-ES-247, Precipitation Sampling and Collection for Radiological Analysis (8)

Exelon Industrial Services Analytical Procedures

a. CY-ES-200, Operation of the Panasonic UD-716AGL Automatic Reader
b. CY-ES-204, Sample Preparation for Gamma Analysis
c. CY-ES-205, Operation ofHPGe Detectors with the Genie PC Counting System
d. CY-ES-206, Operation of the Tennelec SSE Proportional Counter
e. CY-ES-246, Sample Preparation for Gross Beta Analysis (9)

Land Use Census Around Calvert Cliffs Nuclear Power Plant, August 2019 (10) Calvert Cliffs Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License SNM-2505 (11) Baltimore Gas and Electric Company, Radiological Environmental Monitoring Program Pre-Operational Report for the Calvert Cliffs Independent Spent Fuel Storage Installation, August 1990 - November 1993, February 1994. 35

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 (12) CY-AA-110-200, Current Revision, Sampling (13) CY-AA-170-1000, Radiological Environmental Monitoring Program (REMP) and Meteorological Program Implementation. (14) Teledyne Browne Engineering, (TBE) 2018 Analysis Procedures Current Revisions

a. TBE-2001 Alpha Isotopic and Pu-241
b. TBE-2006 Iron-55 Activity in Various Matrices
c. TBE-2007 Gamma Emitting Radioisotope Analysis
d. TBE-2008 Gross Alpha and/or Gross Beta Activity in Various Matrices
d. TBE-2011 Tritium Analysis in Drinking Water by Liquid Scintillation
e. TBE-2013 Radionickel Activity in Various Matrices
f. TBE-2019 Radiostrontium Analysis by Ion Exchange (15) Normandeau Associates, Inc. (NAI) Sampling Procedures Current Revisions
a. Procedure No. ER20 Collection of Bottom Sediment for Radiological Analysis (Calvert Cliffs Nuclear Power Plant)
b. Procedure No. ER21 Collection of Fish Samples for Radiological Analysis (Calvert Cliffs Nuclear Power Plant)
c. Procedure No. ER22 Collection of Oyster Samples for Radiological Analysis (Calvert Cliffs Nuclear Power Plant (16) EN-CA-408-4160 Current Revision, RGPP Reference Material for Calvert Cliffs 36

APPENDIX A January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Sample Locations for the REMP and the ISFSI Appendix A contains information concerning the environmental samples which were collected during this operating period. Sample locations and specific information about individual locations for the CCNPP REMP are given in Table A-1. Figure A-1 shows the location of the CCNPP in relation to Southern Maryland and the Chesapeake Bay. Figures A-2 and A-3 show the locations of the power plant sampling sites in relation to the plant site at different degrees of detail. Sample locations and specific information about individual locations for the ISFSI radiological environmental monitoring program are given in Table A-2. Figures A-4 and A-5 show the

  • locations of the ISFSI sampling sites in relation to the plant site at different degrees of detail.

37

Table January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 TABLE OF CONTENTS - SAMPLING LOCATIONS Title Page A-1 Locations of Environmental Sampling Stations for the Calvert Cliffs Nuclear Power Plant

                                                                                                                                                                                                                                                                                        • 39
  • A-2 Locations of Environmental Sampling Stations for the Independent Spent Fuel Storage Installation at Calvert Cliffs............................................................................................... 43 Figure Title Page A-1 Map of Southern Maryland and Chesapeake Bay Showing Location of Calvert Cliffs Nuclear Power Plant.......................................................................................................... 40 A-2 Calvert Cliffs Nuclear Power Plant Sampling Locations, 0-2 Miles.................................41 A-3 Calvert Cliffs Nuclear Power Plant Sampling Locations, 0-10 Miles...............................42 A-4 Independent Spent Fuel Storage Installation Sampling Locations....................................44 A-5 Enlarged Map of the Independent Spent Fuel Storage Installation Sampling Locations.. 45 38

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Station Al 2 A2 A3 A4 AS DR0I DR02 DR03 DR04 DR05 DR06 DR072 DR08 DR09 DRI0 DRll DR12 DR13 DR14 DR15 DR16 DR17 DR18 DR19 DR20 DR21 DR22 DR23 IAI IA2 IA3 IA4 IA5 IA6 IBI0 IBI I IB12 IB4 IB5 IB6 IB7 IB8 IB9 SFAI2 SFA32 SFA42 WAI WA2 WBI TABLEA-1 Locations of Environmental Sampling Stations for the Calvert Cliffs Nuclear Power Plant Distance1 Description (KM) (Miles) On Site Before Entrance to Camp Conoy 0.7 0.5 Camp Conoy Rd, at emergency siren 2.5 1.5 Bay Breeze Rd 2.6 1.6 Route 765, Lusby 2.9 1.8 Emergency Operations Facility 19.3 12.1 On Site, along Cliffs 0.6 0.4 Route 765, Auto Dump 2.7 1.7 Route 765, Giovanni's Tavern (Knotty Pine) 2.3 1.4 Route 765, across from Vera's Beach Club 2.0 1.2 Route 765, John's Creek 2.4 1.5 Route 765, Lusby 2.9 1.8 On Site Before Entrance to Camp Conoy 0.7 0.5 Camp Conoy Rd at Emergency Siren 2.5 1.5 Bay Breeze Rd 2.6 1.6 Calvert Beach Rd and Decatur Street 6.4 4.0 Dirt road off Mackall & Parren Rd 6.6 4.1 Mackall & Bowen Rds 6.7 4.2 Mackall Rd, near Wallville 6.1 3.8 Rodney Point 6.4 4.0 Mill Bridge & Turner Rds 6.2 3.9 Across from Appeal School 6.5 4.1 Cove Point & Little Cove Point Rds 5.9 3.7 Cove Point 7.1 4.5 Long Beach 4.4 2.8 On site, near shore 0.4 0.3 Emergency Operations Facility (EOF) 19.3 12.1 Solomons Island 12.5 7.8 Taylors Island, Anderson's Property 12.4 7.7 Discharge Area 0.3 0.2 Discharge Vicinity 0.3 0.2 Camp Conoy 0.9 0.6 Patuxent River (Area not influenced Patuxent river by plant) Kenwood Beach 10.7 6.7 Meteorological Station 0.7 0.4 Meteorological Station 0.7 0.4 Meteorological Station 0.7 0.4 On site, before entrance to Camp Conoy 0.7 0.5 On site, before entrance to Camp Conoy 0.7 0.5 On site, before entrance to Camp Conoy 0.7 0.5 Emergency offsite facility 19.3 12.1 Emergency offsite facility 19.3 12.1 Emergency offsite facility 19.3 12.1 Meteorological Station 0.7 0.4 NNW ofISFSI 0.6 0.4 SSE ofISFSI 0.8 0.5 Intake area 0.2 0.1 Discharge area 0.3 0.2 Shoreline at Barge Rd. 0.6 0.4 1 Distance and direction from the central point between the two containment buildings 2 Common to both the REMP and ISFSI monitoring program 39 Direction1 (Sector) s SSE SE SSW WNW NW WNW w WSW SW SSW s SSE SE NW WNW w WSW SW SSW s SSE SE NW NNW WNW s ENE N N E Patuxent River NNW-SW SW SW s s s WNW WNW WNW SW SSW SSW NNE N ESE

Figure A-1 January 1 - December 31, 2019 Docket Nos. 50-317/50-31 8/72-8 Map of Southern Maryland and Chesapeake Bay Showing Location of Calvert Cliffs Nuclear Power Plant 40

Figure A-2 January 1 - December 31, 2019 Docket Nos. 50-317 /50-31 8/72-8 Calvert Cliffs Nuclear Power Plant Sampling Locations 0-2 Miles NE 41

Figure A-3 January l - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Calvert Cliffs Nuclear Power Plant Sampling Locations 0-10 Miles 42

Table A-2 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Locations of Environmental Sampling Stations for the Independent Spent Fuel Storage Installation at Calvert Cliffs Distance* Direction* Station Description (KM) (Sector) Air Particulate A1 2 On Site Before Entrance to Camp Conoy 0.3 ESE SFA1 2 Meteorological Station 0.3 NW SFA2 CCNPP Visitor's Center 0.8 N SFA3 2 NNW ofISFSI 0.1 NNW SFA42 SSE of ISFSI 0.1 SSE Direct Radiation DR072 On Site Before Entrance to Camp Conoy 0.3 ESE DR30 Meteorological Station 0.3 NW SFDR0l SW ofISFSI 0.2 SW SFDR02 N ofISFSI 0.2 N SFDR03 North ofISFSI 0.1 N SFDR04 NEofISFSI <0.1 NE SFDR05 East of ISFSI <0.1 E SFDR06 ESE ofISFSI 0.1 ESE SFDR07 CCNPP Visitor's Center 0.8 N SFDR08 NNW of ISFSI 0.l NNW SFDR09 SSE of ISFSI 0.1 SSE SFDRl0 NW of lSFSI 0.1 NW SFDRl 1 WNWISFSI 0.1 WNW SFDR12 WSW ofISFSI <0.1 WSW SFDR13 South of ISFSI <0.1 s SFDR14 SE oflSFSI 0.1 SE SFDR15 ENE oflSFSI <0.1 ENE SFDR16 SW ofISFSI <0.1 SW SFDR17 NNE ofISFSI 0.1 NNE SFDR18 West ofISFSI 0.04 w Vegetation SFBl ISFSI Vegetation Met Station 0.3 NW SFB2 ISFSI Vegetation Visitors Center 0.8 N SFB3 ISFSI Vegetation NNW of ISFSI 0.1 NNW SFB4 ISFSI vegetation SSE of ISFSI 0.1 SSE SFB5 On Site Before Entrance to Camp Conoy 0.3 ESE Soil SFSl ISFSI Soil Meteorological Station 0.3 NW SFS2 ISFSI Soil CCNPP Visitors Center 0.8 N SFS3 ISFSI Soil NNW ofISFSI 0.1 NNW SFS4 ISFSI Soil SSE of ISFSI 0.1 SSE SFS5 ISFSI Soil On Site Before entrance to Camp Conoy 0.3 ESE Distance and d1rect1on from the central pomt of the ISFSI 2 Common to both the REMP and ISFSI monitoring program 43

J .-/ { Figure A-4 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Independent Spent Fuel Storage Installation Sampling Locations f r 44 l* -

Figure A-5 January 1 - December 31, 2019 Docket Nos. 50-317 /50-31 8/72-8 Enlarged Map of the Independent Spent Fuel Storage Installation Sampling Locations 45

APPENDIXB January 1 - December 31, 2019

  • Docket Nos. 50-317 /50-318/72-8 Analysis Results for the REMP and the ISFSI Appendix Bis a presentation of the analytical results for the CCNPP and the ISFSI radiological environmental monitoring programs.

46

Table January 1 - December 31, 2019 Docket Nos. 50-3 l 7 /50-318/72-8 TABLE OF CONTENTS - ANALYTICAL RESULTS Title Page B-1 Concentration of Tritium and Gamma Emitters in Bay Water..........................................48 B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish.........................................49 B-3 Concentration of Gamma Emitters in Oyster Samples...................................................... 50 B-4 Concentration of Gamma Emitters in Shoreline Sediment................................................ 51 B-5 Concentration of Iodine-131 in Filtered Air...................................................................... 52 B-6 Concentration of Beta Emitters in Air Particulates............................................................ 54 B-7 Concentration of Gamma Emitters in Air Particulates...................................................... 5 8 B-8a Concentration of Gamma Emitters in Vegetation Samples............................................... 5 9 B-8b Concentration of Gamma Emitters in Vegetation From Locations Around the ISFSI...... 61 B-9 Concentration of Gamma Emitters in Soil Samples From Locations Around the ISFSI.. 62 B-10 Typical MDA Ranges for Gamma Spectrometry.............................................................. 63 B-11 Typical LLDs for Gamma Spectrometry.......................................................,................... 64 B-12 Direct Radiation................................................................................................................. 65 47

Table B-1 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Concentration of Tritium and Gamma Emitters in Bay Water (Results in units of pCi/L +/- 20') Sample Code Sample Date Gamma Emitters H-3 1 WAI Intake Vicinity 1/29/2019 2/27/2019 3/29/2019 <196 4/26/2019 5/31/2019 7/1/2019 <185 7/31/2019 8/30/2019 9/27/2019 <180 11/1/2019 12/2/2019 12/31/2019 <184 WA2 Discharge Vicinity 1/29/2019 2/27/2019 3/29/2019 385 +/- 201 5/1/2019 5/31/2019 7/1/2019 <184 7/31/2019 8/30/2019 9/27/2019 <182 11/1/2019 12/2/2019 12/31/2019 <187 1 Quarterly composite of monthly samples.

  • All Non-Natural Gamma Emitters <MDA 48

Sample Code IAI Discharge Area IA2 Discharge Area IA41 Patuxent River IA5 1 Patuxent River January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-2 Concentration of Gamma Emitters in the Flesh of Edible Fish (Results in units of pCi/kg (wet) :I: 2 a) Sample Date Sample Type Gamma Emitters 8/12/2019 Spot 8/12/2019 Spanish Mackerel 8/12/2019 Spot 8/12/2019 Spanish Mackerel 1 Control Location

  • All Non-Natural Gamma Emitters <MDA 49

Sample Code IA3 Camp Conoy IA6 1 Kenwood Beach 1 Control Location Table B-3 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Concentration of Gamma Emitters in Oyster Samples (Results in units of pCi/kg (wet) +/- 2 o-) Sample Date Gamma Emitters 3/19/2019 6/25/2019 8/12/2019 10/23/2019 3/19/2019 6/25/2019 8/12/2019 10/23/2019

  • All Non-Natural Gamma Emitters <MDA 50

Table B-4 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Concentration of Gamma Emitters in Shoreline Sediment (Results in units of pCi/kg (dry)+/- 2o-) Sample Code WBI Shoreline at Barge Rd.

  • All Non-Natural Gamma Emitters <MDA 51 Sample Date 4/29/2019 10/1/2019 Gamma Emitters

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-5 Concentration of Iodine-131 in Filtered Air (Results in units of 10-3 pCi/m3 :I: 2a) Start Date Stop Date Al A2 A3 A4 A5 1 SFA1 2 SFA3 SFA4 Entrance Camp Bay Route EOF Met NNW SSE of to Camp Conoy Breeze 765 at Sta of ISFSI Conoy Siren Rd Lusby ISFSI 12/31/2018 1/7/2019 1/7/2019 1/14/2019 1/14/2019 1/22/2019 1/22/2019 1/28/2019 1/28/2019 2/4/2019 2/4/2019 2/11/2019 2/11/2019 2/18/2019 2/18/2019 2/26/2019 2/26/2019 3/4/2019 3/4/2019 3/12/2019 3/12/2019 3/19/2019 3/19/2019 3/26/2019 3/26/2019 4/2/2019 4/2/2019 4/8/2019 4/8/2019 4/15/2019 4/15/2019 4/23/2019 4/23/2019 4/29/2019 4/29/2019 5/7/2019 5/7/2019 5/13/2019 5/13/2019 5/20/2019 5/20/2019 5/28/2019 3 5/28/2019 6/3/2019 6/3/2019 6/10/2019 6/10/2019 6/17/2019 6/17/2019 6/24/2019 6/24/2019 7/1/2019 7/1/2019 7/8/2019 7/8/2019 7/15/2019 7/15/2019 7/22/2019 7/22/2019 7/30/2019 7/30/2019 8/5/2019 8/5/2019 8/12/2019 8/12/2019 8/19/2019 8/19/2019 8/26/2019 8/26/2019 9/3/2019 52

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-5 Concentration oflodine-131 in Filtered Air (Results in units of 10-3 pCi/m3 +/- 2o') Start Date Stop Date Al A2 A3 A4 A5 1 SFA1 2 SFA3 SFA4 Entrance Camp Bay Route EOF Met NNW SSE of to Camp Conoy Breeze 765 at Sta of ISFSI Conoy Siren Rd Lusby ISFSI 9/3/2019 9/9/2019 9/9/2019 9/16/2019 9/16/2019 9/23/2019 9/23/2019 10/1/2019 10/1/2019 10/7/2019 10/7/2019 10/14/2019 10/14/2019 10/21/2019 10/21/2019 10/28/2019 10/28/2019 11/4/2019 11/4/2019 11/11/2019 11/11/2019 11/18/2019 11/18/2019 11/25/2019 11/25/2019 12/2/2019 12/2/2019 12/9/2019 12/9/2019 12/16/2019 12/16/2019 12/23/2019 12/23/2019 12/30/2019 1 Control Location RE1\\.1P Technical Specifications 2 Control Location ISFSI RE1\\.1P Program 3 Lost Sample Due to Power Outage

  • All Non-Natural Gamma Emitters <MDA 53

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-6 Concentration of Beta Emitters in Air Particulates (Results in units of 10-2 pCi/m3 +/- 20') Start Date Stop Date Al A2 A3 A4 A5 1 Entrance to Camp Conoy Bay Breeze Route 765 at EOF Camp Conoy Siren Rd Lusby 12/31/2018 1/7/2019 2.2 +/- 0.1 2.3 +/- 0.1 2.1 +/- 0.1 2.1+/-0.1 2.1 +/- 0.1 1/7/2019 1/14/2019 1.6 +/- 0.1 1.6+/-0.1 1.4 +/- 0.1 1.5 +/- 0.1 1.5 +/- 0.1 1/14/2019 1/22/2019 1.7 +/- 0.1 1.5+/-0.1 1.4 +/- 0.1 1.7+/-0.1 1.7 +/- 0.1 1/22/2019 1/28/2019 2.0 +/- 0.1 2.0 +/- 0.1 2.1 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 1/28/2019 2/4/2019 2.5 +/- 0.1 2.6 +/- 0.1 2.5 +/- 0.1 2.3 +/- 0.1 2.4 +/- 0.1 2/4/2019 2/11/2019 2.3 +/- 0.1 2.4+/-0.1 2.1 +/- 0.1 2.1+/-0.1 2.4 +/- 0.1 2/11/2019 2/18/2019 1.7 +/- 0.1 1.9 +/- 0.1 1.7 +/- 0.1 1.9 +/- 0.1 1.8 +/- 0.1 2/18/2019 2/26/2019 2.3 +/- 0.1 2.5 +/- 0.1 2.1 +/- 0.1 2.3 +/- 0.1 2.1 +/- 0.1 2/26/2019 3/4/2019 1.7 +/- 0.1 1.8 +/- 0.1 1.6 +/- 0.1 1.6 +/- 0.1 1,8 +/- 0.1 3/4/2019 3/12/2019 2.0 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 1.9 +/- 0.1 3/12/2019 3/19/2019 2.6 +/- 0.1 2.7 +/- 0.1 2.7 +/- 0.1 2.6 +/- 0.1 2.5 +/- 0.1 3/19/2019 3/26/2019 1.4+/-0.1 1.5 +/- 0.1 1.5 +/- 0.1 1.5 +/- 0.1 1.4 +/- 0.1 3/26/2019 4/2/2019 1.3 +/- 0.1 1.2 +/- 0.1 1.3 +/- 0.1 1.3 +/- 0.1 1.4+/-0.1 4/2/2019 4/8/2019 2.1 +/- 0.1 1.9+/-0.1 2.0 +/- 0.1 1.8 +/- 0.1 2.0 +/- 0.1 4/8/2019 4/15/2019 1.2 +/- 0.1 1.1 +/- 0.1 1.1 +/-0.1 1.2 +/- 0.1 1.2 +/- 0.1 4/15/2019 4/23/2019 1.1 +/- 0.1 1.0 +/- 0.1 1.1 +/- 0.1 1.1 +/-0.1 1.1 +/-0.1 4/23/2019 4/29/2019 1.4 +/- 0.1 1.4+/-0.1 1.6 +/- 0.1 1.7 +/- 0.1 1.5 +/- 0.1 4/29/2019 5/7/2019 1.2 +/- 0.1 1.2 +/- 0.1 1.3+/-0.1 1.2 +/- 0.1 1.3 +/- 0.1 5/7/2019 5/13/2019 1.1 +/- 0.1 1.2 +/- 0.1 1.2 +/- 0.1 1.2 +/- 0.1 1.2 +/- 0.1 5/13/2019 5/20/2019 2.0 +/- 0.1 2.1+/-0.1 2.1 +/- 0.1 2.3 +/- 0.1 2.2 +/- 0.1 5/20/2019 5/28/2019 1.4 +/- 0.1 2 1.4 +/- 0.1 1.5 +/- 0.1 1.4+/-0.1 5/28/2019 6/3/2019 2.0 +/- 0.1 2.0 +/- 0.1 1.8+/-0.1 2.0 +/- 0.1 1.9 +/- 0.1 6/3/2019 6/10/2019 1.8 +/- 0.1 1.6 +/- 0.4 1.7 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 6/10/2019 6/17/2019 1.4+/-0.1 1.3 +/- 0.1 1.3 +/- 0.1 1.5+/-0.1 1.4 +/- 0.1 6/17/2019 6/24/2019 1.3 +/- 0.1 1.1 +/- 0.1 1.1 +/- 0.1 1.3 +/- 0.1 1.2+/-0.1 6/24/2019 7/1/2019 2.4 +/- 0.1 2.3 +/- 0.1 2.2 +/- 0.1 2.5 +/- 0.1 2.4 +/- 0.1 7/1/2019 7/8/2019 1.9 +/- 0.1 1.8 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 1.7 +/- 0.1 7/8/2019 7/15/2019 1.5 +/- 0.1 1.6+/-0.1 1.8 +/- 0.1 1.7+/-0.1 1.8 +/- 0.1 7/15/2019 7/22/2019 2.2 +/- 0.1 2.3 +/- 0.1 2.1 +/- 0.1 2.4 +/- 0.1 2.3 +/- 0.1 7/22/2019 7/30/2019 1.8 +/- 0.1 1.9 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 7/30/2019 8/5/2019 2.7 +/- 0.2 2.8 +/-0.2 2.6 +/- 0.2 2.5 +/- 0.2 2.4 +/- 0.2 8/5/2019 8/12/2019 2.2 +/- 0.1 2.4+/-0.1 2.5 +/- 0.1 2.5+/-0.1 2.3 +/- 0.1 8/12/2019 8/19/2019 2.7 +/- 0.1 2.6 +/- 0.1 2.7+/- 0.2 2.8 +/- 0.2

  • 3.0+/-0.2 8/19/2019 8/26/2019 1.8 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 8/26/2019 9/3/2019 2.1 +/- 0.1 2.2+/- 0.1 2.2 +/- 0.1 2.2 +/- 0.1 2.3 +/- 0.1 54

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-6 Concentration of Beta Emitters in Air Particulates (Results in units of 10-2 pCi/m3 +/- 2o-) Start Date Stop Date Al A2 A3 A4 A5 1 Entrance to Camp Conoy Bay Breeze Route 765 at EOF Camp Conoy Siren Rd Lusby 9/3/2019 9/9/2019 2.7+/- 0.2 2.5 +/- 0.2 2.6 +/- 0.2 2.5 +/- 0.2 2.6 +/- 0.2 9/9/2019 9/16/2019 2.5 +/- 0.1 2.6 +/- 0.1 2.7 +/- 0.1 2.7 +/- 0.1 2.8+/- 0.2 9/16/2019 9/23/2019 2.3 +/- 0.1 2.3 +/- 0.1 2.5 +/- 0.1 2.3+/-0.1 2.6 +/- 0.1 9/23/2019 10/1/2019 2.6 +/- 0.1 2.5 +/- 0.1 2.7 +/- 0.1 2.7 +/- 0.1 2.6 +/- 0.1 10/1/2019 10/7/2019 2.0 +/- 0.1 1.9 +/- 0.1 2.1+/-0.1 2.1 +/- 0.1 2.1+/-0.1 10/7/2019 10/14/2019 1.9 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 2.0 +/- 0.1 1.9 +/- 0.1 10/14/2019 10/21/2019 2.3 +/- 0.1 2.4+/- 0.2 2.4 +/- 0.1 2.3 +/- 0.1 2.2 +/- 0.1 10/21/2019 10/28/2019 1.9 +/- 0.1 1.6+/-0.1 1.5 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.1 10/28/2019 11/4/2019 1.6 +/- 0.1 1.4+/-0.1 1.4+/-0.1 1.4 +/- 0.1 1.5 +/- 0.1 11/4/2019 11/11/2019 2.7 +/- 0.2 2.3 +/- 0.1 1.9 +/- 0.1 2.5 +/- 0.1 2.6 +/- 0.1 11/11/2019 11/18/2019 2.1+/-0.1 2.1+/-0.1 2.3 +/- 0.1 2.0 +/- 0.1 2.3 +/- 0.1 11/18/2019 11/25/2019 2.5 +/- 0.1 2.3 +/- 0.1 2.3 +/- 0.1 2.4 +/- 0.1 2.6 +/- 0.1 11/25/2019 12/2/2019 1.6 +/- 0.1 1.4+/-0.1 1.5 +/- 0.1 1.5 +/- 0.1 1.6+/-0.1 12/2/2019 12/9/2019 1.6 +/- 0.1 1.3 +/- 0.1 1.5 +/- 0.1 1.5+/-0.1 1.6 +/- 0.1 12/9/2019 12/16/2019 1.6 +/- 0.1 1.5 +/- 0.1 1.6 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 12/16/2019 12/23/2019 2.5 +/- 0.1 2.7 +/- 0.1 2.6 +/- 0.1 2.6 +/- 0.1 2.7 +/- 0.1 12/23/2019 12/30/2019 3.0 +/- 0.2 3.1 +/- 0.2 2.8 +/- 0.2 3.4 +/- 0.2 3.7+/- 0.2 1 Control Location 2 Lost Sample Due to Power Outage 55

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table B Continued Concentration of Beta Emitters in Air Particulates (Results in units of 10-2 pCi/m3 +/- 2a) Start Date Stop Date SFAl SFA2 1 SFA3 SFA4 MET Station Visitors Center NNW ofISFSI SSE ofISFSI 12/31/2018 1/7/2019 1.9 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 2.1+/-0.1 1/7/2019 1/14/2019 1.5 +/- 0.1 1.5+/-0.1 1.5+/-0.1 1.5+/-0.1 1/14/2019 1/22/2019 1.5+/-0.1 1.6 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.1 1/22/2019 1/28/2019 2.1 +/- 0.1 2.1 +/- 0.1 2.1 +/- 0.1 2.2 +/- 0.1 1/28/2019 2/4/2019 2.3 +/- 0.1 2.4 +/- 0.1 2.4 +/- 0.1 2.3 +/- 0.1 2/4/2019 2/11/2019 2.2 +/- 0.1 2.3 +/- 0.1 2.5 +/- 0.1 2.2 +/- 0.1 2/11/2019 2/18/2019 1.8+/-0.1 1.8 +/- 0.1 2.0 +/- 0.1 1.8 +/- 0.1 2/18/2019 2/26/2019 2.4 +/- 0.1 2.3 +/- 0.1 2.4 +/- 0.1 2.5 +/- 0.1 2/26/2019 3/4/2019 1.7 +/- 0.1 1.5 +/- 0.1 1.7 +/- 0.1 1.7 +/- 0.1 3/4/2019 3/12/2019 2.0 +/- 0.1 2.1+/-0.1 2.1+/-0.1 2.0 +/- 0.1 3/12/2019 3/19/2019 2.5 +/- 0.1 2.6 +/- 0.1 2.6 +/- 0.1 2.5 +/- 0.1 3/19/2019 3/26/2019 1.5 +/- 0.1 1.5 +/- 0.1 1.4 +/- 0.1 1.3 +/- 0.1 3/26/2019 4/2/2019 1.3+/-0.1 1.4+/-0.1 1.3 +/- 0.1 1.2 +/- 0.1 4/2/2019 4/8/2019 1.7 +/- 0.1 1.6 +/- 0.1 1.9 +/- 0.1 1.9 +/- 0.1 4/8/2019 4/15/2019 1.1 +/- 0.1 1.2 +/- 0.1 1.1 +/- 0.1 1.1+/-0.1 4/15/2019 4/23/2019 1.1+/-0.1 1.1 +/-0.1 1.1 +/- 0.1 1.1 +/- 0.1 4/23/2019 4/29/2019 1.7+/-0.1 1.5+/-0.1 1.6 +/- 0.1 1.4 +/- 0.1 4/29/2019 5/7/2019 1.2 +/- 0.1 1.1 +/- 0.1 1.2 +/- 0.1 1.0 +/- 0.1 5/7/2019 5/13/2019 1.2 +/- 0.1 1.1 +/- 0.1 1.2 +/- 0.1 1.1+/-0.1 5/13/2019 5/20/2019 2.3 +/- 0.1 2.1 +/- 0.1 2.2 +/- 0.1 2.1 +/- 0.1 5/20/2019 5/28/2019 1.5 +/- 0.1 1.3+/-0.1 1.5 +/- 0.1 1.4+/-0.1 5/28/2019 6/3/2019 2.0+/-0.1 1.9 +/- 0.1 2.0 +/- 0.1 1.9+/-0.1 6/3/2019 6/10/2019 1.8 +/- 0.1 1.6+/-0.1 1.7 +/- 0.1 1.6 +/- 0.1 6/10/2019 6/17/2019 1.5+/-0.1 1.3+/-0.1 1.5 +/- 0.1 1.3 +/- 0.1 6/17/2019 6/24/2019 1.3 +/- 0.1 1.2 +/- 0.1 1.3 +/- 0.1 1.2+/-0.1 6/24/2019 7/1/2019 2.5 +/- 0.1 2.3 +/- 0.1 2.6 +/- 0.1 2.4+/-0.1 7/1/2019 7/8/2019 1.9 +/- 0.1 1.7 +/- 0.1 1.8 +/- 0.1 1.7+/-0.1 7/8/2019 7/15/2019 1.8 +/- 0.1 1.6 +/- 0.1 1.5 +/- 0.1 1.5 +/- 0.1 7/15/2019 7/22/2019 2.3 +/- 0.1 2.3 +/- 0.1 2.5 +/- 0.1 2.3 +/- 0.1 7/22/2019 7/30/2019 2.0 +/- 0.1 1.8 +/- 0.1 1.9 +/- 0.1 1.7 +/- 0.1 7/30/2019 8/5/2019 2.7 +/- 0.2 2.5 +/- 0.2 2.6 +/- 0.2 2.4 +/- 0.2 8/5/2019 8/12/2019 2.6 +/- 0.1 2.4 +/- 0.1 2.5 +/- 0.1 2.2 +/- 0.1 8/12/2019 8/19/2019 2.8 +/- 0.2 2.5 +/- 0.1 2.8 +/- 0.2 2.4 +/- 0.1 8/19/2019 8/26/2019 1.9 +/- 0.1 1.7+/-0.1 1.9 +/- 0.1 1.9 +/- 0.1 8/26/2019 9/3/2019 2.0 +/-0.1 1.9 +/- 0.1 2.2 +/- 0.1 2.0 +/- 0.1 56

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table B Continued Concentration of Beta Emitters in Air Particulates (Results in units of 10-2 pCi/m3 +/- 2a) Start Date Stop Date SFAl SFA21 SFA3 SFA4 MET Station Visitors Center NNW ofISFSI SSE ofISFSI 9/3/2019 9/9/2019 2.7 +/- 0.2 2.5 +/-0.2 2.4+/- 0.2 2.5 +/- 0.2 9/9/2019 9/16/2019 2.6 +/- 0.1 2.4 +/- 0.1 2.5 +/- 0.1 2.6 +/- 0.1 9/16/2019 9/23/2019 2.3 +/- 0.1 2.2 +/- 0.1 2.4 +/- 0.1 2.3 +/- 0.1 9/23/2019 10/1/2019 2.6+/-0.1 2.5 +/-0.l 2.6+/-0.1 2.5 +/-0.l 10/1/2019 10/7/2019 2.2+/-0.2 1.9 +/- 0.1 2.0+/-0.l 2.0 +/- 0.1 10/7/2019 10/14/2019 2.1+/-0.1 1.8 +/- 0.1 1.9 +/- 0.1 1.9 0.1 10/14/2019 10/21/2019 2.3 +/- 0.1 2.2 +/- 0.1 2.4 +/- 0.1 2.1 0.1 10/21/2019 10/28/2019 1.8 +/- 0.1 1.7 +/- 0.1 1.9 +/- 0.1 1.6 0.1 10/28/2019 11/4/2019 1.5+/-0.1 1.5+/-0.1 1.4 +/- 0.1 1.6 0.1 11/4/2019 11/11/2019 2.6 +/- 0.1 2.5 +/- 0.1 2.6+/- 0.1 2.4 0.1 11/11/2019 11/18/2019 2.1 +/- 0.1 2.0 +/- 0.1 2.0 +/- 0.1 2.1 +/- 0.1 11/18/2019 11/25/2019 2.5 +/- 0.1 2.2+/-0.1 2.7+/- 0.2 2.3 0.1 11/25/2019 12/2/2019 1.6 +/- 0.1 1.8 +/- 0.1 1.6+/-0.1 1.5 +/- 0.1 12/2/2019 12/9/2019 1.5 +/- 0.1 1.4+/- 0.1 1.4 +/- 0.1 1.4 +/- 0.1 12/9/2019 12/16/2019 1.7 +/- 0.1 1.7 +/- 0.1 1.7+/- 0.1 1.5 0.1 12/16/2019 12/23/2019 2.5 +/- 0.1 2.6 +/- 0.1 2.6 +/- 0.1 2.4 +/- 0.1 12/23/2019 12/30/2019 2.8 +/- 0.2 3.2 +/- 0.2 3.1 +/- 0.2 3.0 +/- 0.2 1 Control Location 57

Sample Date 4/2/2019 7/1/2019 10/1/2019 12/30/2019 Sample Date 4/2/2019 7/1/2019 10/1/2019 12/30/2019 1 Control Location Table B-7 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Concentration of Gamma Emitters in Air Particulates (Results in units of 10-3 pCi/m3 +/- 2cr) Al A2 A3 A4 A5 1 Entrance to Camp Conoy Bay Breeze Rd Route 765 at EOF Camp Conoy Siren Lusby SFAl SFA2 1 SFA3 SFA4 l\\.1ET Station Visitors Center NNW ofISFSI SSE ofISFSI

  • All Non-Natural Gamma Emitters <MDA 58

Table B-8a January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Concentration of Gamma Emitters in Vegetation Samples (Results in units of pCi/kg (wet)+/- 2o-) Sample Code Sample Date Sample Type Gamma Emitters IB4 Camp Conoy Entrance 6/24/2019 Kale 7/22/2019 Cabbage 8/19/2019 Collards 9/23/2019 Chard IBS Camp Conoy Entrance 6/24/2019 Collards 7/22/2019 Chard 8/19/2019 Chard 9/23/2019 Cabbage IB6 Camp Conoy Entrance 6/24/2019 Cabbage 7/22/2019 Kale 8/19/2019 Kale 9/23/2019 Collards rn1 1 EOF 6/24/2019 Collards 7/22/2019 Eggplant Leaves 8/19/2019 Kale 9/23/2019 Chard IB8 1 EOF 6/24/2019 Chard 7/22/2019 Chard 8/19/2019 Chard 9/23/2019 Eggplant Leaves IB9 1 EOF 6/24/2019 Eggplant Leaves 7/22/2019 Kale 8/19/2019 Eggplant Leaves 9/23/2019 Cabbage 59

Table B-8a January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Concentration of Gamma Emitters in Vegetation Samples (Results in units of pCi/kg (wet)+/- 2<r) Sample Code Sample Date Sample Type Gamma Emitters IBIO Meteorological Station 6/24/2019 Kale 7/22/2019 Collards 8/19/2019 Chard 9/23/2019 Chard IBll Meteorological Station 6/24/2019 Chard 7/22/2019 Chard 8/19/2019 Coliards 9/23/2019 Cabbage IB12 Meteorological Station 6/24/2019 Cabbage 7/22/2019 Cabbage 8/19/2019 Cabbage 9/23/2019 Collards 1 Control Location

  • All Non-Natural Gamma Emitters <MDA 60

Sample Code SFBl MET Station SFB21 Visitor's Center SFB3 NNWofISFSI SFB4 SSE ofISFSI SFBS On Site Before Entrance to Camp Conoy Control Location January 1-December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table B-8b Concentration of Gamma Emitters in Vegetation From Locations Around the ISFSI (Results in units of pCi/kg (wet) +/- 2<f Sample Date 2/26/2019 6/12/2019 9/16/2019 11/18/2019 2/26/2019 6/12/2019 9/16/2019 11/18/2019 2/26/2019 6/12/2019 9/16/2019 11/18/2019 2/26/2019 6/12/2019 9/16/2019 11/18/2019 2/26/2019 6/12/2019 9/16/2019 11/18/2019 Gamma Emitters

  • All Non-Natural Gamma Emitters <MDA 61

Table B-9 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Concentration of Gamma Emitters in Soil Samples From Locations Around the ISFSI (Results in units of pCi/kg (dry) :I: 2a) Sample Code Sample Date Cs-137 Gamma Emitters SFSl MET station 2/26/2019 6/12/2019 9/16/2019 11/18/2019 SFS22 Visitors Center 2/26/2019 6/12/2019 9/16/2019 11/18/2019 SFS3 NNWofISFSI 2/26/2019 99+/-44 6/12/2019 87+/-49 9/16/2019 88+/-39 11/18/2019 135 +/- 50 SFS4 SSE ofISFSI 2/26/2019 6/12/2019 9/16/2019 11/18/2019 SFS5 Entrance to Camp Conoy 2/26/2019 86+/-32 6/12/2019 96+/-25 9/16/2019 81 +/-32 ll/18/2019 58 +/-28 This isotope <MDA 2 Control Location

  • All Non-Natural Gamma Emitters <MDA 62

January l -December31,2019 Docket Nos. 50-317/50-318/72-8 Table B-10 Typical MDA Ranges for Gamma Spectrometry Bay Water, Selected Air Surface Fish Ground water Milk Oysters Shoreline Soil (pCi/kg) Vegetation Particulates

Water, Sediment Nuclides (10-3 pCi/m3)

Drinking (pCi/kg) Wet (pCi/L) (pCi/L) (pCi/kg) (pCi/kg)Dry Dry (pCi/kg) Wet Water (pCi/L) K-40 4.03 - 16.6 16 - 182 2,747 - 4,505 21.5 -66.4 1,286 - 1,529 1,269 - 2,069 781 - 13,761 789 - 10,713 671 - 11,829 Mn-54 0.32 - 1.16 2.7 - 5.6 9.8 - 19.6 2.86 - 5.14 3.6 - 6.6 10.8 - 16.4 41.4-67.1 37.4 - 91.9 10.3 - 53.0 Fe-59 1.01 - 8.52 5.6 - 13.2 31.6 - 93.2 6.04-11.7 9.2 - 15.9 29.3 - 56.7 142 - 251 96.4-389 22.0 - 151 Co-58 0.38 - 2.07 2.7 - 5.6 10.9 - 28.3 2.86 - 5.27 3.7 - 6.3 10.5 - 19.3 53.7 - 82.9 44.6-133 10.9 - 59.8 Co-60 0.28 - 1.09 2.8 - 5.5 10.9 - 24.3 3.01 - 5.38 4.1 - 7.2 11.7-17.0 38.6 - 57.9 32.8 - 85.8 12.9 - 55.0 Zn-65 0.81-3.10 5.5-11.4 23.3 - 57.2 6.41 - 14.4 9.4 - 16.1 22.0 - 43.3 112-198 96.4-275 24.7 - 116 Ag-1 lOm 0.33 -1.06 2.42 - 4.96 8.2-18.1 2.79 - 5.06 3.26-5.64 8.7 - 16.0 36.6 - 175 40.7 - 99.4 10.1 - 61.4 Zr-95 0.72 - 3.88 4.7 - 10.2 20.0 - 47.1 5.62 - 8.75 5.8 - 11.5 19.0 - 34.0 93.5 - 151 84.6 - 26i 19.3-116 Nb-95 0.56 - 4.91 2.9 - 6.0 13.7 - 42.7 3.3 - 5.88 3.9 - 6.5 13.9 - 24.3 82.1 - 157 61.5 - 227 10.9 - 90.5 Ru-106 3.00-12.1 23.8 - 48.1 77.1 - 197 25.6 - 45.3 29.3 - 51.8 88.0 - 141 327.0- 570 314.0-840 92.9 - 541 1-131 1 2.73 - 914 0.4 - 14.9 21.4-2,340 4.87 - 9.04 0.4 - 11.6 22.4 - 107 470 -2,040 139 - 8,060 13.4 - 854 Cs-134 0.31-1.08 2.8 - 5.3 7.8 - 16.0 2.92 - 5.48 3.2 - 5.9 9.7 - 16.5 43.3 - 82.4 33.4 - 109 11.1 - 58.1 Cs-137 0.27 - 1.03 2.0 - 5.4 3.8 - 17.5 2.97 - 5.43 3.4 - 6.0 10.0 - 16.7 38.4 - 65.4 39.1 - 135 11.1 - 62.3 La-140 2.01-116 3.6 - 14.6 15.9-444 4.87 - 10.3 4.5 - 11.4 24.1 - 80.4 368 - 773 136 - 1,820 9.1 - 388 Ba-140 2.01 - 116 3.6 - 14.6 15.9-444 5.86 - 26.0 4.5 - 11.4 24.1 - 80.4 368-773 136 - 1,820 9.1 - 388 Ce-144 1.12 - 3.27 16.8 - 36.7 38.1 - 70.9 17.8 - 32.0 20.5 - 31.0 42.6 - 72.6 208 - 279 191 - 414 46.6 - 289 Cr-51 4.90 - 45.0 23.2 - 50.6 93.0 - 395 26.7 - 42.1 30.4 - 46.8 97.0 - 199 711 - 1,110 489 - 1,810 93.9 - 850 Na-22 0.34 - 1.33 2.7 - 6.0 12.1-28.0 2.78 - 5.94 4.9 - 8.5 13.4 - 19.5 46.4 - 77.4 36.4 - 92.4 8.9 - 54.1 1 This MDA range for I-131 on a charcoal cartridge is typically 2.82 x 10-3 to 5.53 x 10-2 pCi/m3 63

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table B-11 Typical LLDs for Gamma Spectrometry Bay Water, Selected Air Particulates Surface Water, Fish pCi/kg Ground water Oysters pCi/kg MilkpCi/L Soil pCi/kg Vegetation Nuclides 10-3 pCi/m3 Drinking Water (wet) pCi/L (wet) (dry) pCi/kg (wet) pCi/L Na-22 5.0 5.3 12 5.3 12 9.1 78 27 Cr-51 74 37 76 37 76 62 452 174 Mn-54 4.6 4.7 13 4.7 13 7.4 63 19 Co-58 6.7 4.3 12 4.3 12 8.2 78 23 Fe-59 20 11 27 11 27 18 123 57 Co-60 3.5 4.8 12 4.8 12 7.5 59 24 Zn-65 8.9 11 27 11 27 17 162 55 Nb-95 9.8 4.5 13 4.5 13 9.5 73 25 Zr-95 11 7.9 18 7.9 18 14 117 34 Ru-106 43 38 111 38 111 62

  • 624 174 Ag-1 l0m 4.2 4.3 11 4.3 11 6.0 65 20 Te-129m 101 56 118 56 118 90 833 263 I-131 90 0.8 11 6.4 11 0.8 58 42 Cs-134 4.7 4.7 11 4.7 11 6.7 66 18 Cs-137 4.2 5.1 11 5.1 11 6.9 78 21 Ba-140 47 23 39 23 39 46 103 111 La-140 47 9.2 15 9.2 15 13 103 30 Ce-144 15 23 45 23 45 37 288 70
  • The LLD for 1-131 measured on a charcoal cartridge is 5.3 x10-2 pCi/m3 64

Table B-12 Direct Radiation (Results in Units of mR/91 days+/- 2o') Site Code Location First Quarter Second Quarter DR0l On Site, along Cliffs 6.58 +/- 0.94 13.60 +/- 1.02 DR02 Route 765, Auto Dump 5.29 +/- 0.49 10.00 +/- 1.07 DR03 Route 765, Giovanni's Tavern 4.99 +/- 0.39 9.51 +/- 0.74 DR04 Route 765, across from 6.69 +/- 0.58 11.80 +/- 0.65 Vera's Beach Club DR05 Route 765, John's Creek 6.45 +/- 0.80 12.00 +/- 0.78 DR06 Route 765 at Lusby 4.68 +/- 0.52 9.95 +/- 0.68 DR07 Entrance to Camp Conoy 5.22 +/- 0.79 10.00 +/- 0.69 DR08 Camp Conoy Rd at Emergency Siren 8.70 +/- 0.88 13.30 +/- 0.84 DR09 Bay Breeze Rd 5.04+/- 0.58 10.20 +/- 0.76 DRl0 Calvert Beach Rd and Decatur Street 5.41 +/- 0.49 10.50 +/- 0.83 DR11 Dirt road off Mackall & Parren Rd 7.05 +/- 1.46 10.30 +/- 0.66 DR12 Mackall & Bowen Rds 5.36 +/- 0.64 10.40+/- 0.68 DR13 Mackall Rd, near Wallville 6.18 +/- 0.57 12.10 +/- 0.76 DR14 Rodney Point 6.22 +/- 0.58 11.20 +/- 0.76 DR15 Mill Bridge & Turner Rds 6.15+/-0.41 11.20 +/- 0.65 65 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Third Quarter Fourth Quarter 15.30+/- 1.13 14.30 +/- 1.71 11.50 +/- 0.64 10.80 +/- 0.41 12.00 +/- 0.84 10.60 +/- 0.61 14.00 +/- 1.14 12.50 +/- 0.53 13.40+/- 0.67 12.20 +/- 0.72 11.70 +/- 0.64 10.80 +/- 0.47 12.30 +/- 0.39 10.90 +/- 0.55 16.80 +/- 0.88 14.50 +/- 0.55 11.70 +/- 0.49 10.80 +/- 0.66 12.50 +/- 0.82 10.90 +/- 0.46 13.00+/- 0.62 11.40 +/- 0.55 12.10+/-0.77 11.00 +/- 0.71 13.70 +/- 0.50 12.60 +/- 0.59 13.50 +/- 0.61 12.10 +/- 3.24 13.20 +/- 1.01 11.60 +/- 0.47

Table B-12 Direct Radiation (Results in Units of mR/91 days+/- 2a) Site Code Location First Quarter Second Quarter DR16 Across from Appeal School 6.08 +/- 0.56 11.40 +/- 1.04 DR17 Cove Point & Little Cove Point Rds 7.24+/- 0.70 12.10 +/- 0.89 DR18 Cove Point 4.50 +/- 0.65 9.65 +/- 0.87 DRl9 Long Beach 5.02 +/- 0.50 10.40 +/- 1.00 DR20 On site, near shore 7.61 +/- 0.71 11.00 +/- 0.59 DR21 1 EOF 7.12 +/- 0.53 12.60 +/- 1.07 DR221 Solomons Island 5.64 +/- 0.78 10.70 +/- 0.81 DR23 1 Taylors Island 8.96 +/- 0.91 13.20+/- 0.63 DR30 MET Station 6.25 +/- 0.57 10.30 +/- 0.71 SFDR0I SW ofISFSI 10.80 +/- 1.02 14.50 +/- 0.82 SFDR02 NNWofISFSI 11.60 +/- 0.75 15.90 +/- 0.97 SFDR03 North ofISFSI 25.00 +/- 3.08 27.40 +/- 1.52 SFDR04 NE ofISFSI 23.30 +/- 1.21 26.20+/- 1.09 SFDR05 East ofISFSI 15.00 +/- 1.01 18.80 +/- 0.65 SFDR06 ESE ofISFSI 12.60 +/- 1.29 16.50 +/- 1.01 SFDR071 Visitor's Center 8.02 +/- 0.58 12.80 +/- 0.86 66 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Third Quarter Fourth Quarter 12.00 +/- 0.53 10.90 +/- 0.53 15.90 +/- 0.53 13.40+/-0.69 11.10 +/- 0.41 9.92+/- 0.45 11.90 +/- 1.08 17.60 +/- 1.22 12.40 +/- 0.70 14.60+/- 1.15 12.40 +/- 0.38 12.30 +/- 0.34 11.00 +/- 0.57 20.50+/- 0.71 17.60 +/- 0.89 12.00+/- 0.79 10.90+/- 0.55 20.10 +/- 1.63 17.00 +/- 0.90 25.50+/- 4.77 18.20 +/- 1.28 40.60+/- 3.97 37.60+/- 2.89 41.70 +/- 3.12 35.60+/- 2.09 28.50 +/- 5.15 23.40 +/- 0.99 23.60 +/- 2.06 19.90 +/- 1.11 16.40 +/- 0.83 14.10+/-0.74

Site Code Location SFDR08 NNW ofISFSI SFDR09 SSE ofISFSI SFDRlO NW ofISFSI SFDRl 1 WNW ISFSI SFDR12 WSWofISFSI SFDR13 South ofISFSI SFDR14 SE ofISFSI SFDR15 ENEofISFSI SFDR16 SSWofISFSI SFDRI7 NNEofISFSI SFDR18 West ofISFSI 1 Control Location

  • Damaged TLDs, data rejected Table B-12 Direct Radiation (Results in Units of mR/91 days+/- 2a)

First Quarter Second Quarter 17.60 +/- 1.75 21.50+/- 1.76 29.70 +/- 2.15 39.40 +/- 12.11 17.70 +/- 1.47 21.40+/- 1.41 16.10+/- 1.17 23.50+/- 1.72 35.30 +/- 5.48 33.60+/- 3.58 19.80 +/- 3.02 24.40 +/- 2.40 47.20 +/- 6.83 43.90 +/- 2.42 18.20 +/- 1.50 20.60 +/- 1.06 37.10+/-4.06 38.80+/- 3.50 30.60+/- 3.78 31.30 +/- 1.39 29.80 +/- 0.98 31.80 +/- 1.58 67 January I - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Third Quarter Fourth Quarter 26.30 +/- 1.95 24.20 +/- 1.75 47.50+/- 4.34 47.60+/- 15.33 36.40+/- 4.56 26.80+/- 1.68 31.60 +/- 2.19 27.30+/-4.32 49.10 +/- 7.10 40.60+/- 2.27 42.60 +/- 9.38 33.40 +/- 3.45 63.70+/- 8.96 61.60 +/- 16.34 31.20 +/- 2.18 25.50 +/- 2.48 58.90+/- 7.95 47.60+/- 3.56 44.00+/-4.09 40.30 +/- 1.98 46.90+/- 2.62 41.20 +/- 1.92

APPENDIXC Quality Assurance Program January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Appendix C is a summary of Exelon Industrial Services (EIS) laboratory's quality assurance program. It consists of Table C-1 which is a compilation of the results of the EIS laboratory's participation in an interlaboratory comparison program with Environmental Resource Associates (ERA) located in Arvada, Colorado and Eckert and Ziegler Analytics, Inc. (EZA) located in Atlanta, Georgia. It also includes Table C-2, which is a compilation of the results of the EIS laboratory's participation in a split sample program with Teledyne Brown Engineering located in Knoxville, Tennessee. Finally, Table C-3, is a list of the power plant's ODCM required LLDs, all of which are achieved by both EIS laboratory and Teledyne Brown Engineering for the analyses reported. All the EIS laboratory's results contained in Table C-1, intercomparison results, are in full agreement when they were evaluated using the NRC Resolution Test Criteria 1* The EIS laboratory's results are provided with their analytical uncertainties of 2 sigma. When evaluating with the NRC Resolution Test a one sigma uncertainty is used_to determine Pass or Fail and noted accordingly. The EIS laboratory results contained in Table C-2 are intercomparison results for routine samples analyzed for replicate and split analyses and evaluated for beta and non-natural gamma emitters. The EIS laboratory's results are provided with their analytical uncertainties of 2 sigma. When evaluating with the NRC Resolution Test a one sigma uncertainty is used to determine Pass or Fail and noted accordingly. In the event there are no non-natural isotopes detected, the samples are reported <MDA and designated as Pass. All the results contained in Table C-2 agree with their respective EIS laboratory original, replicate and/or Teledyne Brown Engineering's split laboratory samples, except for the comparisons of Beta emitters in a particulate sample with poor resolution at A2 collected on 06/10/19 and one sample involving the Cs-137 results for a bottom sediment sample at WBS4 collected on 6/25/19. The original and replicate analysis of the air particulate sample from A2 collected on 06/10/19 failed the NRC Resolution test criteria due to low volume collected resulting from a power outage to the air sampler. Poor resolution of these results is attributed to the low volume collected resulting in insufficient counting statistics. A nonconformance was issued on this event and recorded in the corrective action program. In the bottom sediment sample, WBS2 collected on 6/25/19, the original and replicate analysis do pass NRC Resolution test criteria however the result does not agree within the required resolution for the split lab result. These minor discrepancies, which have been observed in previous reporting periods, are most probably due to counting statistics and/or the non-homogeneous nature of this type of sample. All air particulate samples contain Beta emitters and are reported with a 2sigma uncertainty. The original and replicate analyses are evaluated for agreement using the NRC Resolution Test Criteria 1* These samples must be composited for further analysis and this precludes them from being split for analysis of beta emitters. Filters and other samples whose nature generally preclude sample splitting are marked"**" in the Split Analysis column. 1 NRC Inspection Manual, Inspection Procedure 84750, March 15, 1994 68

Table January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 TABLE OF CONTENTS - ANALYTICAL RESULTS Title Page C-1 Results of Participation in Cross Check Programs................................................................ 70 C-2 Results of Quality Assurance Program.................................................................................. 75 C-3 Calvert Cliffs Nuclear Power Plant ODCM Required LLDs................................................. 85 69

January 1-December31,2019 Docket Nos. 50-317 /50-318/72-8 Table C-1 Results of Participation in Cross Check Programs Sample Type and Reported Cross Check Lab Pass/ Fail 1 Sample Date Units Isotope Observed Laboratory's Results Results 03/14/19 Air Iodirie - pCi 1-131 73.0 +/- 11.0 75.6

  • Pass 03/14/19 Milk-pCi/L Fe-59 149 +/- 25.0 159 Pass Mn-54 141 +/- 16.0 143 Pass Co-60 262 +/- 16.0 299 Pass Co-58 128+/-17.0 143 Pass Cr-51 227 +/- 101.0 293 Pass Ce-141 101 +/- 20.0 117 Pass Cs-137 184+/-18.0 196 Pass Cs-134 138 +/- 10.0 160 Pass I-131 92.0 +/- 36.0 89.5 Pass Zn-65 177 +/- 32.0 220 Pass 03/14/19 Water - pCi/L Gross Beta 264 +/- 4.84 28.8 Pass 04/08/19 Water - pCi/L 1-131 25.3 +/- 8.0 28.4 Pass Ba-133 23.0 +/- 2.7 24.1 Pass Cs-137 34.4 +/- 3.4 33.1 Pass Cs-134 10.8 +/- 1.7 12.l Pass Zn-65 88.0 +/- 9.3 89.2 Pass Co-60 11.3 +/- 1.8 11.5 Pass 04/08/19 Water - pCi/L Gross Beta 28.8 +/- 2.09 299 Pass 06/06/19 Air Iodine - pCi Cs-134 80.9 +/- 4.4 93.0 Pass Zn-65 185+/-18.0 164 Pass Co-60 139 +/- 7.0 131 Pass Co-58 77.7 +/- 7.4 74.1 Pass Fe-59 121+/-13.0 93.5 Pass Mn-54 142 +/- 8.9 126 Pass Cs-137 119 +/- 7.7 111 Pass Cr-51 222 +/- 50.6 223 Pass Ce-141 97.7+/- 7.7 88.3 Pass 70

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table C-1 Results of Participation in Cross Check Programs Sample Type and Reported Cross Check Lab Pass/ Fail 1 Sample Date Units Isotope Observed Laboratory's Results Results 06/06/19 Water Mn-54 214+/-17.6 207 Pass Fe-59 154 +/- 22.5 154 Pass Co-58 115 +/- 15.6 122 Pass Co-60 216 +/- 12.8 216 Pass Zn-65 257 +/- 31.6 270 Pass 1-131 115 +/- 77.0 89.1 Pass Cs-134 139 +/- 8.8 153 Pass Cs-137 186 +/- 15.7 184 Pass Ce-141 142 +/-22.7 145 Pass Cr-51 327 +/- 117 368 Pass 06/06/19 Water - pCi/L Gross Beta 199 +/- 4.2 199 Pass 09/12/19 Air Filter - pCi/m3 Gross Beta 271 +/- 3.42 221 Pass 09/16/19 Air Iodine - pCi Am-241 28.4 +/- 9.9 32.0 Pass Cs-137 440 +/- 20.0 437 Pass Cs-134 60.7 +/- 5.2 59.0 Pass Zn-65 381+/-31.0 364 Pass Co-60 57.5 +/- 6.1 58.4 Pass 10/04/19 Water - pCi/L Cs-137 80.3 +/- 7.2 78.7 Pass Ba-133 37.2 +/- 5.4 43.8 Pass Cs-134 52.2 +/- 4.2 55.9 Pass Zn-65 39.3 +/- 10.0 34.0 Pass 1-131 25.4 +/- 8.3 23.9 Pass Co-60 54.8 +/- 5.1 53.4 Pass 71

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table C-1 Results of Participation in Cross Check Programs Sample Type and Reported Cross Check Lab Pass/ Fail 1 Sample Date Isotope Observed Laboratory's Units Results Results 12/05/19 Air Filter pCi (Det 2) Mn-54 170 +/- 13.0 155 Pass Fe-59 124 +/- 14.3 104 Pass Co-58 117 +/- 11.7 107 Pass Co-60 139 +/- 9.1 138 Pass Zn-65 194 +/- 24.8 190 Pass Cs-134 123 +/- 7.4 135 Pass Cs-137 128 +/- 11.6 121 Pass Ce-141 98.5 +/- 6.4 99.1 Pass Cr-51 246 +/- 46.6 288 Pass 12/05/19 Air Filter - pCi (Det 3) Mn-54 173 +/- 11.3 155 Pass Fe-59 122 +/- 10.8 104 Pass Co-58 111 +/- 8.9 107 Pass Co-60 148 +/- 7.9 138 Pass Zn-65 203 +/-20.9 190 Pass Cs-134 128 +/- 5.7 135 Pass Cs-137 128 +/- 8.9 121 Pass Ce-141 95.7 +/- 7.0 99.1 Pass Cr-51 257 +/-40.6 288 Pass 12/05/19 Air Filter pCi (Det 4) Mn-54 167 +/- 9.1

  • 155 Pass Fe-59 132 +/- 10.3 104 Pass Co-58 102 +/- 7.3 107 Pass Co-60 146 +/- 7.2 138 Pass Zn-65 195 +/- 17.3 190 Pass Cs-134 122+/-4.9 135 Pass Cs-137 122 +/- 7.6 121 Pass Ce-141 102 +/- 6.1 99.l Pass Cr-51 299 +/- 29.9 288 Pass 72

Sample Date 12/05/19 12/05/19 12/05/19 Table C-1 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Results of Participation in Cross Check Programs Sample Type and Units Air Iodine - pCi (Det 4) (Det 2) (Det 3) Milk pCi/L (DET2) Milk pCi/L (DET 3) Isotope Observed I-131 1-131 I-131 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 73 Reported Cross Check Lab Laboratory's Results Results Pass/ Fail 1 79.2 +/- 5.7 88.2 Pass 79.0 +/- 6.3 88.2 Pass 79.1 6.0 88.2 Pass 100 +/- 16.9 94.5 Pass 82.4 +/- 15.9 83.0 Pass 271 +/- 76.7 241 Pass 112 +/- 11.9 113 Pass 123 +/- 17.9 102 Pass 84.9 +/- 14.6 89.9 Pass 128+/- 17.4 130 Pass 95.5 +/- 20.2 87.1 Pass 148 +/- 34.3 159 Pass 119+/- 13.3 115 Pass 99.3 +/- 15.0 94.5 Pass 80.7 +/- 12.5 83.0 Pass 228 +/- 63.0 241 Pass 103 +/- 9.6 113 Pass 109 +/- 12.2 102 Pass 102 +/- 12.2 89.9 Pass 141 +/- 15.2 130 Pass 102 +/- 15.7 87.1 Pass 166 +/- 28.4 159 Pass Ill+/- 10.8 115 Pass

Sample Date 12/05/19 12/05/19 Table C-1 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Results of Participation in Cross Check Programs Sample Type and Units Isotope Observed MilkpCi/L (DET4) I-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Water - pCi/L Gross Beta Reported Laboratory's Results 104 +/- 13.5 78.3 +/- 12.7 235 +/- 68.0 114 +/- 8.3 105 +/- 13.2 92.0 +/- 11.4 143 +/- 13.8 104 +/- 14.9 164 +/- 27.2 123 +/- 10.2 260 +/- 4.76 Cross Check Lab . Results 94.5 83.0 241 113 102 89.9 130 87.1 159 115 269 Pass I Fail 1 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1 See discussion at the beginning of the Appendix describes Acceptance Criteria 74

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table C-2 Results of Quality Assurance Program SampleType and Sample Type of . Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Iodine - A 1 01/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A2 01/07/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 01/07/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 01/07/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A5 01/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF Al 01/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Filter - A 1 02/11/19 Gross Beta pCi/m3 2.3 +/- 0.1 2.3 +/- 0.1 PASS NA Air Filter - A2 02/11/19 Gross Beta pCi/m3 2.4 +/- 0.1 2.3 +/- 0.1 PASS NA Air Filter - A3 02/11/19 Gross Beta pCi/m3 2.1 +/- 0.1 2.1 +/- 0.1 PASS NA Air Filter - A4 02/11/19 Gross Beta pCi/m3 2.1+/-0.1 2.2 +/- 0.1 PASS NA Air Filter - A5 02/11/19 Gross Beta pCi/m3 2.4+/-0.1 2.3 +/- 0.1 PASS NA Air Filter - SF A 1 02/11/19 Gross Beta pCi/m3 2.2 +/- 0.1 2.2 +/- 0.1 PASS NA Air Filter - SF A2 02/11/19 Gross Beta pCi/m3 2.3 +/- 0.1 2.2 +/- 0.1 PASS NA Air Filter - SF A3 02/11/19 Gross Beta pCi/m3 2.5 +/- 0.1 2.2 +/- 0.1 PASS NA Air Filter - SFA4 02/11/19 Gross Beta pCi/m3 2.2 +/- 0.1 2.4 +/- 0.1 PASS NA Air Iodine - A 1 02/11/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A2 02/11/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 02/11/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 02/11/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A5 02/11/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF A 1 02/11/19 1-131 pCi/m3 <MDA <MDA PASS NA 75

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Filter - Al 03/04/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.7+/-0.1 PASS NA Air Filter - A2 03/04/19 Gross Beta pCi/m3 1.8 +/- 0.1 2.0 +/- 0.1 PASS NA Air Filter - A3 03/04/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.7+/-0.1 PASS NA Air Filter - A4 03/04/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.8 +/- 0.1 PASS NA Air Filter - AS 03/04/19 Gross Beta pCi/m3 1.8 +/- 0.1 1.9 +/- 0.1 PASS NA Air Filter - SF A I 03/04/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.6 +/- 0.1 PASS NA Air Filter - SF A2 03/04/19 Gross Beta pCi/m3 1.5 +/- 0.1 1.6 +/- 0.1 PASS NA Air Filter - SF A3 03/04/19 Gross Beta pCi/m3 1.7+/-0.1 1.7 +/- 0.1 PASS NA Air Filter - SFA4 03/04/19 Gross Beta pCi/m3 1.7+/-0.1 1.6 +/- 0.1 PASS NA Air Iodine - Al 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Iodine - A2 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Iodine - A3 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Iodine -A4 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Iodine - AS 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Iodine - SF A I 03/04/19 1-131 pCi/m3 <l\\1DA <l\\1DA PASS NA Air Filter -Al 04/08/19 Gross Beta pCi/m3 2.1+/-0.1 2.1 +/- 0.1 PASS NA Air Filter - A2 04/08/19 Gross Beta pCi/m3 1.9 +/- 0.1 1.9 +/- 0.1 PASS NA Air Filter - A3 04/08/19 Gross Beta pCi/m3 2.0 +/- 0.1 2.0 +/- 0.1 PASS NA Air Filter - A4 04/08/19 Gross Beta pCi/m3 1.8 +/- 0.1 1.8 +/- 0.1 PASS NA Air Filter - AS 04/08/19 Gross Beta pCi/m3 2.0 +/- 0.1 2.0 +/- 0.1 PASS NA Air Filter - SFAI 04/08/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.9 +/- 0.1 PASS NA 76

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Filter - SF A2 04/08/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.6 +/- 0.1 PASS NA Air Filter - SF A3 04/08/19 Gross Beta pCi/m3 1.9 +/- 0.1 1.8 +/- 0.1 PASS NA Air Filter - SFA4 04/08/19 Gross Beta pCi/m3 1.9 +/- 0.1 1.9 +/- 0.1 PASS NA Air Iodine - Al 04/15/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A2 04/15/19 1-131 pCi/m3 <MDA <MDA PASS NA Shoreline Sediment -WBI 4/29/19 Gamma pCi/kg <MDA <MDA <MDA PASS PASS Air Filter - A 1 05/07/19 Gross Beta pCi/m3

  • 1.2 +/- 0.1 1.1 +/- 0.1 PASS NA Air Filter - A2 05/07/19 Gross Beta pCi/m3 1.2 +/- 0.1 1.2 +/- 0.1 PASS NA Air Filter - A3 05/07/19 Gross Beta pCi/m3 1.3+/-0.1 1.2 +/- 0.1 PASS NA Air Filter - A4 05/07/19 Gross Beta pCi/m3 1.2 +/- 0.1 1.3 +/- 0.1 PASS NA Air Filter - A5 05/07/19 Gross Beta pCi/m3 1.3 +/- 0.1 1.2 +/- 0.1 PASS NA Air Filter - SF A 1 05/07/19 Gross Beta pCi/m3 1.2 +/- 0.1 1.3 +/- 0.1 PASS NA Air Filter - SF A2 05/07/19 Gross Beta pCi/m3 1.1 +/- 0.1 1.1 +/- 0.1 PASS NA Air Filter - SF A3 05/07/19 Gross Beta pCi/m3 1.2 +/- 0.1 1.1 +/- 0.1 PASS NA Air Filter - SFA4 05/07/19 Gross Beta pCi/m3 1.0 +/- 0.1 1.0 +/- 0.1 PASS NA Air Iodine - A I 06/03/19 I-131 pCi/m3

<MDA <MDA PASS NA Air Iodine - A2 06/03/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 06/03/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 06/03/19 I-131 pCi/m3 <MDA <MDA PASS NA 77

January 1 -December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Iodine - AS 06/03/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF A 1 06/03/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Filter - A 1 06/10/19 Gross Beta pCi/m3 1.8+/-0.1 1.7+/-0.1 PASS NA Air Filter - A2 06/10/19 Gross Beta pCi/m3 1.6 +/- 0.4 0.9 +/- 0.3 FAIL I NA Air Filter - A3 06/10/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.7 +/- 0.1 PASS NA Air Filter - A4 06/10/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.8 +/- 0.1 PASS NA Air Filter - AS 06/10/19 Gross Beta pCi/m3 1.8 +/- 0.1 1.7+/-0.1 PASS NA Air Filter - SF Al 06/10/19 Gross Beta pCi/m3 1.8 +/- 0.1 1.8+/-0.1 PASS NA Air Filter - SF A2 06/10/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.6 +/- 0.1 PASS NA Air Filter - SFA3 06/10/19 Gross Beta pCi/m3 1.7 +/- 0.1 1.7+/-0.1 PASS NA Air Filter - SFA4 06/10/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.5 +/- 0.1 PASS NA Soil-SFS2 06/12/19 GAMMA pCi/kg <MDA <MDA <MDA PASS PASS Soil - SFSS 06/12/19 Cs-137 pCi/kg 96.3 +/- 25.1 75.2 +/- 21.3 <MDA PASS PASS Oysters - IA3 06/25/19 GAMMA pCi/kg <MDA <MDA <MDA PASS PASS Oysters - IA6 06/25/19 GAMMA pCi/kg <MDA <MDA <MDA PASS PASS 78

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Passi Passi Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Bottom sediment - 06125/19 Cs-137 pCi/kg 91.4 +/- 79.2 149 +/- 72.3 341+/-189 PASS FAIL 1 WBS2 Bottom sediment - 06125/19 Cs-137 pCilkg 113+/-73.8 <MDA <MDA PASS PASS WBS4 Air Filter - A 1 07101/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - A2 07101/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - A3 07101/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - A4 07101/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - AS 07/01/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - SF Al 07101/19 GAMMA pCilm3 <MDA <MDA <MDA PASS PASS Air Filter - SF A2 07101/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - SF A3 07101/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - SFA4 07/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Gamma field - DR0S 07/01/19 TLD mR/Qtr 12.1+/-0.7 10.8 +/- 1.3 PASS NA Gamma field - DR06 07/01/19 TLD mR/Qtr 10.3+/-0.7 10.0 +/- 0.9 PASS NA Gamma field - DR07 07/01/19 TLD mR/Qtr 10.2 +/- 0.6 10.0 +/- 1.1 PASS NA Gamma field - DR08 07/01/19 TLD mR/Qtr 13.3 +/- 1.2 12.8 +/- 1.2 PASS NA Gamma field - DR09 07/01/19 TLD mR/Qtr 10.3 +/- 0:9 10.4 +/- 0.7 PASS NA Gamma field - DRl 0 07/01/19 TLD mR/Qtr 10.6+/- 1.1 10.7 +/- 1.7 PASS NA Gamma field - DRl 1 07/01/19 TLD mR/Qtr 10.6 +/- 0.4 10.4 +/- 0.6 PASS NA Gamma field - SFDR14 07/01/19 TLD mR/Qtr 40.9 +/- 2.8 46.4 +/- 5.1 PASS NA Gamma field - SFDRl 5 07/01/19 TLD mR/Qtr 20.l +/- 2.8 24.0 +/- 6.8 PASS NA Gamma field - DR23 07/01/19 TLD mR/Qtr 14.6 +/- 1.1 13.5 +/- 1.1 PASS NA 79

Sample Type and Location Air Iodine -Al Air Iodine - A2 Air Iodine - A3 Chard - IB5 Cabbage - IB4 Collards - IB 10 Cabbage - IB 12 Air Filter - Al Air Filter - A2 Air Filter - A3 Air Filter - A4 Air Filter - AS Air Filter - SF A I Air Filter - SFA2 Air Filter - SF A3 Air Filter - SFA4 Air Iodine - Al Air Iodine - A2 Sample Date 07/15/19 07/15/19 07/15/19 07/22/19 07/22/19 07/22/19 07/22/19 08/05/19 08/05/19 08/05/19 08/05/19 08/05/19 08/05/19 08/05/19 08/05/19 08/05/19 08/12/19 08/12/19 Table C-2 Results of Quality Assurance Program Type of Analysis I-131 I-131 I-131 Cs-137 GAMMA GAMMA GAMMA Gross Beta Gross Beta Gross Beta Gross Beta Gross Beta Gross Beta Gross Beta Gross Beta Gross Beta I-131 I-131 Result Units pCi/m3 pCi/m3 pCi/m3 pCi/kg pCi/kg pCi/kg pCi/kg pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 Original Analysis <MDA <MDA <MDA 18.6 +/- 13.9 80 <MDA <MDA <MDA 2.7+/- 0.2 2.8 +/- 0.2 2.6 +/- 0.2 2.5 +/- 0.2 2.4 +/- 0.2 2.7+/- 0.2 2.5 +/- 0.2 2.6 +/- 0.2 2.4 +/- 0.2 <MDA <MDA Replicate Analysis <MDA <MDA <MDA <MDA <MDA <MDA <MDA 2.4 +/- 0.2 2.6 +/- 0.2 2.6 +/- 0.2 2.5.+/- 0.2 2.4 +/- 0.2 2.6 +/- 0.2 2.4 +/- 0.2 2.5 +/- 0.2 2.5 +/- 0.2 <MDA <MDA January 1 ~ December 31, 2019 Docket Nos. 50-317/50-318/72-8 Split Analysis 18.2 +/- 5.6 <MDA <MDA <MDA Pass/ Fail (Replicate) PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS PASS Pass/ Fail (Split) NA NA NA PASS PASS PASS PASS NA NA NA NA NA NA NA NA NA NA NA

. January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Iodine - A3 08/12/19 1-131 pCi/m3 <MDA <MDA PASS NA Spanish Mackerel - IAS 8/12/19 Gamma pCi/kg <MDA <MDA <MDA PASS PASS Spot - IAl 8/12/19 Gamma pCi/kg <MDA <MDA <MDA PASS PASS Spanish Mackerel -IA2 8/12/19 Gamma pCi/kg <MDA <MDA <MDA PASS PASS Air Iodine - Al 09/09/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A2 09/09/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 09/09/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 09/09/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - AS 09/09/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF A 1 09/09/19 I-131 pCi/m3 <MDA <MDA PASS NA Water-WA2 9/27/19 Gamma pCi/L <MDA <MDA <MDA PASS PASS Water-WAI 9/27/19 Gamma pCi/L <MDA <MDA <MDA PASS PASS Air Filter - A I 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - A2 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - A3 10/01/19 GAMMA pCi/m3 <MDA .<MDA <MDA PASS PASS Air Filter - A4 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - AS 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - SFAI 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - SF A2 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - SF A3 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS 81

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis

  • Fail Fail (Replicate)

(Split) Air Filter - SF A4 10/01/19 GAMMA pCi/m3 <MDA <MDA <MDA PASS PASS Air Filter - A 1 10/07/19 Gross Beta pCi/m3 2.0 +/- 0.1 2.1 +/- 0.2 PASS NA Air Filter - A2 10/07/19 Gross Beta pCi/m3 1.9 +/- 0.1 1.8 +/- 0.1 PASS NA Air Filter - A3 10/07/19 Gross Beta pCi/m3 2.1+/-0.1 2.1 +/- 0.2 PASS NA Air Filter - A4 10/07/19 Gross Beta pCi/m3 2.1 +/- 0.1 2.0 +/- 0.1 PASS NA Air Filter - AS 10/07/19 Gross Beta pCi/m3 2.1+/-0.1 2.1+/-0.2 PASS NA Air Filter - SF Al . 10/07/19 Gross Beta pCi/m3 2.2+/- 0.2 1.9 +/- 0.1 PASS NA Air Filter - SF A2 10/07/19 Gross Beta pCi/m3 1.9 +/- 0.1 1.9 +/- 0.1 PASS NA Air Filter - SF A3 10/07/19 Gross Beta pCi/m3 2.0 +/- 0.1 2.0 +/- 0.2 PASS NA Air Filter - SFA4 10/07/19 Gross Beta pCi/m3 2.0 +/- 0.1 1.8 +/- 0.1 PASS NA Air Iodine - A 1 10/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A2 10/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 10/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 10/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - AS 10/07/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF A 1 10/07/19 I-131 pCi/m3 <MDA <MDA PASS NA Oysters - IA3 10/23/19 GAMMA pCi/kg <MDA <MDA <MDA PASS PASS Oysters - IA6 10/23/19 GAMMA pCi/kg <MDA <MDA <MDA PASS PASS Air Filter - A 1 11/04/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.6 +/- 0.1 PASS NA Air Filter - A2 11/04/19 Gross Beta pCi/m3 1.4 +/- 0.1 1.4 +/- 0.1 PASS NA 82

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Filter - A3 11/04/19 Gross Beta pCi/m3 1.4 +/- 0.1 1.3 +/- 0.1 PASS NA Air Filter - A4 11/04/19 Gross Beta pCi/m3 1.4+/-0.1 1.4 +/- 0.1 PASS NA Air Filter - AS 11/04/19 Gross Beta pCi/m3 1.5 +/- 0.1 1.7 +/- 0.1 PASS NA Air Filter - SF A 1 11/04/19 Gross Beta pCi/m3 1.5+/-0.1 1.5+/-0.1 PASS NA Air Filter - SFA2 11/04/19 Gross Beta pCi/m3 1.5 +/- 0.1 1.4 +/- 0.1 PASS NA Air Filter - SFA3 11/04/19 Gross Beta pCi/m3 1.4 +/- 0.1 1.4 +/- 0.1 PASS NA Air Filter-SFA4 ll/04/19 Gross Beta pCi/m3 1.6 +/- 0.1 1.3 +/- 0.1 PASS NA Air Iodine - A 1 11/04/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine -A2 11/04/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A3 11/04/19 1-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - A4 11/04/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - AS 11/04/19 I-131 pCi/m3 <MDA <MDA PASS NA Air Iodine - SF Al 11/04/19 I-131 pCi/m3 <MDA <MDA PASS NA Vegetation-SFB2 11/18/19 Gamma pCi/kg <MDA <MDA <MDA PASS PASS Vegetation - SFB5 11/18/19 Cs-137 pCi/kg <MDA <MDA 19.5 +/- 8.9 PASS PASS Water-WAI 12/2/2019 Gamma pCi/L <MDA <MDA <MDA PASS PASS Water-WA2 12/2/2019 Gamma pCi/L <MDA <MDA <MDA PASS PASS Air Iodine - A 1 12/09/19 I-131 pCi/m3 <MDA

  • <MDA PASS NA Air Iodine - A2 12/09/19 I-131 pCi/m3

<MDA <MDA PASS NA 83

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table C-2 Results of Quality Assurance Program Sample Type and Sample Type of Result Original Replicate Split Pass/ Pass/ Location Date Analysis Units Analysis Analysis Analysis Fail Fail (Replicate) (Split) Air Iodine - A3 12/09/19 1-131 pCi/m3 <l'vIDA <l'vIDA PASS NA Air Iodine - A4 12/09/19 1-131 pCi/m3 <l'vIDA <l'vIDA PASS NA Air Iodine - A5 12/09/19 1-131 pCi/m3 <l'vIDA <l'vIDA PASS NA Air Iodine - SFAI 12/09/19 1-131 pCi/m3 <l'vIDA <l'vIDA PASS NA Gamma field - DR05 01/21/20 TLD mR/Qtr 15.3 +/- 1.6 15.1 +/- 1.0 PASS NA Gamma field - DR06 01/21/20 TLD mR/Qtr 13.6+/- 0.8 13.2+/- 0.5 PASS NA Gamma field - DR07 01/21/20 TLD mR/Qtr 13.6 +/- 1.0 13.9 +/- 1.2 PASS NA Gamma field - OROS 01/21/20 TLD mR/Qtr 18.2 +/- 1.0 18.2 +/- 1.8 PASS NA Gamma field - DR09 01/21/20 TLD mR/Qtr 13.6+/-1.4 13.5 +/- 1.1 PASS NA Gamma field - ORIO 01/21/20 TLD mR/Qtr 13.7 +/- 0.7 14.6 +/- 3.7 PASS NA Gamma field - DR! I 01/21/20 TLD mR/Qtr 14.3 +/- 1.0 14.1+/-0.9 PASS NA Gamma field - SFDRl4 01/21/20 TLD mR/Qtr 76.1 +/- 40.2 83.0 +/- 55.5 PASS NA Gamma field - SFDRl 5 01/21/20 TLD mR/Qtr 31.7+/-6.0 33.9 +/- 5.8 PASS NA Gamma field - DR23 01/21/20 TLD mR/Qtr 21.9 +/- 2.1 20.3 +/- 1.0 PASS NA 1 See discussion at the beginning of the Appendix

    • The nature of these samples precluded splitting them with an independent laboratory.

84

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 TABLEC-3 Calvert Cliffs Nuclear Power Plant ODCM Required LLDs Selected Water Fish/Shellfish Milk Sediment Vegetation Particulates 1 Nuclides pCi/1 pCi/kg pCi/L pCi/kg pCi/kg pCi/m3 H-3 2000 Mn-54 15 130 Co-58 15 130 Fe-59 30 260 Co-60 15 130 Zn-65 30 260 Zr-95/Nb-95 15 1-131 152 60 0.073 Cs-134 15 130 15 150 60 0.05 Cs-137 18 150 18 180 80 0.06 BaLa-140 15 15 1Gross Beta activity LLD= 0.0lpCi/m3 2 In accordance with the ODCM no drinking water pathway exists so the Gamma Isotopic LLD is used. 3 Air samples for I-131 are collected separately on a charcoal radioiodine cannister 85

APPENDIXD Land Use Survey January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Appendix D contains the results of a Land Use Survey conducted around Calvert Cliffs Nuclear Power Plant during this operating period. A table listing the raw data of this survey and a discussion of the results are included in this appendix. Discussion A Land Use Survey was conducted to identify, within a distance of 5 miles, the location of the nearest milk animal, the nearest residence, and the nearest garden greater than 50 m2 in each of the nine sectors over land. A detailed description of the Land Use Survey is given in a separate document (Ref. 9). The position of the nearest residence and garden in each sector out to 5 miles is given in the adjacent table. An "*" denotes a change in this sector since the 2018 Land Use Census. Sector SE SSE s SSW SW WSW w WNW NW Table D-1 Land Use Survey Distance from Plant (miles) Residence Garden 1.5 4.5* 1.6 3.8* 1.6 1.9* 1.5 1.6 1.1 2.4 1.2 1.5* 1.3 1.6* 2.7 2.7 2.0 2.1 The closest residence is situated in the SW sector and the nearest garden is in the WSW sector. There are no animals producing milk for human consumption within the 5-mile radius. The closest beef cattle for meat consumption are 1.6 miles in the South Sector. Discussion with a local waterman indicate that oysters are still harvested in the vicinity of CCNPP. 86

APPENDIXE January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Additional Samples and Analysis Results Appendix Eis a presentation of the analytical results for additional samples collected in the environs of CCNPP. These extra samples are not required by the ODCM (Ref. 6). Table E-1 lists the locations of all the additional samples and groundwater samples discussed below. The remaining tables in this appendix provide the results. Some of these samples were collected and analyzed to maintain the historical continuity for samples and sampling pathways discontinued when the Environmental Technical Specifications were changed in March,1985. Table E-4 through E-5 contain analytical results for samples taken from aquatic and atmospheric radiological pathways surrounding the plant. In general, these results continue the historical trends previously observed in the official sites of the CCNPP REMP and ISFSI. The NEI Industry Groundwater Protection Initiative was established to determine the potential impact nuclear power plants may have on the surrounding environment due to unplanned releases of radioactive liquids. Under the Groundwater Protection Initiative, groundwater monitoring is accomplished through routine sampling of the water table around the plant (Ref. 16). Analysis is performed for gamma, tritium, alpha, beta, and various other radiological isotopes. Tables E-6 through E-12 contain the analytical results for samples taken from the various groundwater monitoring wells, subsurface drains, and rainwater. In 2019 MH24 was renamed to MH66/SSD3 and maps have been updated accordingly. Groundwater samples were collected from 16 of 17 on-site piezometer tubes and three subsurface manholes in 201.9. These locations are listed in Table E-1 and on Figure E-1, Site Map Groundwater Monitoring Wells. Figure E-2, Site Map RW Locations, shows precipitation collection sites. A piezometer tube is a shallow monitoring well which allows access to groundwater at a depth of approximately 40 feet beneath the site. Of the piezometer tubes sampled, only #11 piezometer and MH28 and MH30 showed any results greater than MDAs. This activity was previously identified and evaluated in December of 2005. The activity consists of tritium originating from normal radiological waste discharges and was previously reported in the Annual Radioactive Release Reports. The tritium contamination is contained on site. No drinking water has been affected; the groundwater at this location does not impact any drinking water pathway. 87

Table January 1 -December 31, 2019 Docket Nos. 50-317 /50-318/72-8 TABLE OF CONTENTS - ANALYTICAL RESULTS Title Page E-1 Locations of Non-Tech Spec and Radiological Groundwater Environmental Sampling Stations for Calvert Cliffs Nuclear Power Plant................................................................ 89 E-2 Synopsis of 2019 Calvert Cliffs Nuclear Power Plant Non-Tech Spec Radiological Environmental Monitoring Program.................................................................................. 90 E-3 Annual Summary for Calvert Cliffs Nuclear Power Plant Units 1 & 2 Non-Tech Spec Radiological Environmental Monitoring Program............................................................ 91 E-4 Concentration of Gamma Emitters in Bottom Sediment................................................... 92 E-5 Concentration oflodine-131 in Filtered Air...................................................................... 93 E-6 Alpha Isotopic and Pu-241 in Groundwater............................................ :......................... 95 E-7 Gross Alpha and Gross Beta Activity in Groundwater... :.................................................. 96 E-8 Concentration ofRadiostrontium in Groundwater............................................................ 97 E-9 Concentration of Tritium in Groundwater......................................................................... 98 E-10 Concentration of Tritium in Surface Water, Precipitation, and Subsurface Drainage....... 99 E-11 Gross Concentration of Gamma Emitters in Groundwater.............................................. 100 E-12 Gross Concentration of Gamma Emitters in Surface Water, Precipitation and MH.......101 Figure Title Page E-1 Site Map Groundwater Monitoring Wells....................................................................... 102 E-2 Site Map Rainwater Monitoring Locations.............................................................. :....... I 02 88

TABLEE-1 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Locations of Non-Tech Spec and Radiological Groundwater Environmental Sampling Stations for Calvert Cliffs Nuclear Power Plant Non-Tech Description Distance1 Spec (KM) Station WBS2 Discharge Area 0.3 WBS4 Camp Conov/Rockv Point 3.0 SFA2 Visitors Center 0.8 2 RGPP Description Station PZll 45' - North side of Unit 1 near roll-uo door PZ12 NW corner of Unit I PZ13 Unit I RWT PZ15 Unit2RWT PZ18 45' - South side near stairwell to waterfront (idle) PZ19 IO' - Southside near travelimi screen trouflh PZ20 10' -Northside of MMD Shon PZ21 10' - In flrass West of STP PZ22 10' - In g:rass West of STP PZ23 45' - S of SSB doors PZ24 45' - East of SSB near Unit 2 roll-un door PZ25 45' - South side near stairwell to waterfront PZ26 45' -SW of Snare Transformer PZ27 45' -SW of Snare Transformer PZ28 45' - SW corner of NRC Bldfl PZ29 45' - East ofNitroflen Tank in road PZ30 45' -NE Corner of Turbine Blde RWl Met Tower RW2 Lower Lav Down Area RW3 Visitor's Center Overlook RW4 Waterfront MH28 12'- Unitl next to Feed Water Heater MH30 12'- Unit 2 next to elevator MH66/SSD3 45'- East of SSB and South of Turbine Bldg: SW003 Waterfront south of Sewag-e Treatment Plant SW004 Waterfront Barge Dock Rd 1 Distance and direction from the central point between the two containment buildings 2* Distance and direction from the central point of the ISFSI 89 (Miles)* 0.2 1.9 0.5 2 Direction1 (Sector) N SE N2

Table E-2 January I - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Synopsis of 2019 Calvert Cliffs Nuclear Power Plant Non-Tech Spec Radiological Environmental Monitoring Program Sample Type Aquatic Environment Bottom Sediment Atmospheric Environment Air Iodine1. Sampling Frequency1 SA w Number of Locations 2 1 Number Collected 4 52 1 W=weekly, M=monthly, Q=quarterly, SA=semiannual, A=annual, C=composite 2 The collection device contains Charcoal 90 Analysis Gamma I-131 Analysis Frequency1 SA w Number Analyzed 4 52

Medium or Pathway Sampled (Unit of Measurement) Aquatic Environment Bottom Sediment (pCi/kg) Table E-3 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Annual Summary for Calvert Cliffs Nuclear Power Plant Units 1 & 2 Non-Tech Spec Radiological Environmental Monitoring Program Type and Total Lower Limit of Indicator Location with Highest Annual Control Locations Number of Detection (LLD) Locations Mean Highest Annual Mean (F) / Range1 Mean (F)/Range Analyses (F)/Range1 Mean Performed Name/Distance & Direction2 Gamma (4) 111 (2/2) Camp Conoy/ 120 (2/2) 120 (2/2) Cs-137 (91-130) Rocky Point (113-128) (113-128) WBS4 3.0 kin SE 1 Mean and range based upon detectable measurements only. Fraction (F) of detectable measurements at specified location is indicated in parentheses. 2 Distance and direction from the central point between the two containment buildings. 91

Sample Code WBS2 Discharge Area WBS41 Camp Conoy/ Rocky Point 1 Control Location TableE-4 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Concentration of Gamma Emitters in Bottom Sediment (Results in units of pCi/kg (dry)+/- 2cr) Sample Date Cs-137 Gamma Emitters 6/25/2019 91 +/- 79 10/23/2019 130 +/- 71 6/25/2019 113 +/- 74 10/23/2019 128 +/- 63

  • All Non-Natural Gamma Emitters <MDA 92

Start Date 12/31/2018 1/7/2019 1/14/2019 1/22/2019 1/28/2019 2/4/2019 2/11/2019 2/18/2019 2/26/2019 3/4/2019 3/12/2019 3/19/2019 3/26/2019 4/2/2019 4/8/2019 4/15/2019 4/23/2019 4/29/2019 5/7/2019 5/13/2019 5/20/2019 5/28/2019 6/3/2019 6/10/2019 6/17/2019 6/24/2019 7/1/2019 7/8/2019 7/15/2019 7/22/2019 7/30/2019 8/5/2019 8/12/2019 8/19/2019 8/26/2019 9/3/2019 9/9/2019 9/16/2019 9/23/2019 Table E-5 January 1 - December 31, 2019 Docket Nos, 50-317 /50-318/72-8 Concentration of Iodine-131 in Filtered Air (Results in units of 10-3 pCi/m3 +/- 2cr) Stop Date 1/7/2019 1/14/2019 1/22/2019 1/28/2019 2/4/2019 2/11/2019 2/18/2019 2/26/2019 3/4/2019 3/12/2019 3/19/2019 3/26/2019 4/2/2019 4/8/2019 4/15/2019 4/23/2019 4/29/2019 5/7/2019 5/13/2019 5/20/2019 5/28/2019 6/3/2019 6/10/2019 6/17/2019 6/24/2019 7/1/2019 7/8/2019 7/15/2019 7/22/2019 7/30/2019 8/5/2019 8/12/2019 8/19/2019 8/26/2019 9/3/2019 9/9/2019 9/16/2019 9/23/2019 10/1/2019 93 SFA21 Visitors Center

Start Date 10/1/2019 10/7/2019 10/14/2019 10/21/2019 10/28/2019 11/4/2019 11/11/2019 11/18/2019 11/25/2019 12/2/2019 12/9/2019 12/16/2019 12/23/2019 1 Control Location

  • <MDA Table E-5 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Concentration oflodine-131 in Filtered Air (Results in units of 10-3 pCi/m3 +/- 2o")

Stop Date 10/7/2019 10/14/2019 10/21/2019 10/28/2019 11/4/2019 11/11/2019 11/18/2019 11/25/2019 12/2/2019 12/9/2019 12/16/2019 12/23/2019 12/30/2019 94 SFA2 1 Visitors Center

SAMPLE Station DATE PZl 1 9/11/2019 Table E-6 Alpha Isotopic and Pu-241 in Groundwater (Results in units of pCi/L +/- 2o') CM-243/244 AM-241 {AS} CM-242 {AS} {AS} <0.08083 <0.04002 . <0.1058 U-233/234 {AS} U-235 {AS} U-238 {AS} <0.06137 <0.04381 <0.01902 95 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 PU-238 {AS} PU-239/240 {AS} <0.1412 <0.07059 Fe-55 Ni-63 <54.49 <4.47

TableE-7 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Gross Alpha and Gross Beta Activity in Groundwater (Results in units of pCi/L +/- 2o') Station Sample Date MH66/SSD3 2/13/2019 PZ19 6/11/2019 PZ20 6/11/2019 PZ21 6/11/2019 PZ22 6/11/2019 PZ25 6/12/2019 PZ15 6/12/2019 PZ13 6/12/2019 PZ12 6/12/2019 PZ29 6/12/2019 PZ30 6/12/2019 PZ24 6/12/2019 MH28 8/14/2019 MH30 8/14/2019 PZl 1 9/11/2019

  • All Non-Natural Gamma Emitters <MDA ND No Data samples obtained as required.

GR-A(DIS) (pCi/L) <2.03 <0.514 <6.3 <1.36 <0.966 <1.13 <1.12 <1.05 <1.01 <1.81 2.21 +/- 1.19 <2.26 <0.901 <0.932 <0.751 96 GR-A(SUS) GR-B (DIS) GR-B (SUS) (pCi/L) (pCi/L) (pCi/L) <0.503 ND ND <0.518 <0.854 <1.45 <2.37 15.9 +/- 6.44 <7.37 <0.901 4.26+/- 1.15 <1.52 <0.944 3.39 +/- 1.03 <1.55 <1.14 3.5 +/- 1.09 <1.67 <0.363 3.07 +/- 1.05 <1.49 <0.931 4.5 +/- 1.11 <l.54 <1.53 6.65 +/- 1.19 <2.31 <1.34 4.91 +/- 1.27 <2.21 <1.36 11.5 +/- 1.43 <2.22 1.36 +/- 0.72 4.55 +/- 2.22 <1.88 <1.04 ND ND <1.03 ND ND <0.507 ND ND

Station MH66/SSD3 PZ19 PZ20 PZ21 PZ22 PZ25 PZ15 PZ13 PZ12 PZ29 PZ30 PZ24 MH28 MH30 PZl 1 Table E-8 January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Concentration ofRadiostrontium in Groundwater (Results in units of pCi/L :I: 2a) Sample Date SR-89 (pCi/L) SR-90 (pCi/L) 2/13/2019 <3.21 <0.S39 6/11/2019 <7.19 <0.671 6/11/2019 <7.16 <0.443 6/11/2019 <7.34 <0.318 6/11/2019 <9.76 <0.48 6/12/2019 <5.73 <0.609 6/12/2019 <6.76 <0.816 6/12/2019 <8.08 <0.454 6/12/2019 <6.57 <0.575 6/12/2019 <5.82 <0.7 6/12/2019 <6.81 <0.745 6/12/2019 <8.92 <0.593 8/14/2019 <6.01 <0.992 8/14/2019 <7.6 <0.743 9/11/2019 <9.69 <0.839 97

January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Table E-9 Concentration of Tritium in Groundwater (Results in units of pCi/L +/- la) By Piezometer Tube Locations SAMPLE DATE 11 12 13 15 19 20 21 22 23 24 25 26 27 28 29 30 3/12/2019 ND ND ND ND <175 <171 <175 <176 ND ND ND ND ND ND ND ND 3/13/2019 1070 +/- 185 <175 <176 <175 ND ND ND ND ND <177 <173 ND ND ND <173 <179 6/11/2019 ND ND ND ND <195 <196 <196 <195 <192 ND ND <193 <198 ND ND ND 6/12/2019 219+/- 133 <196 <193 <195 ND ND ND ND ND <196 <193 ND ND <193 <193 <194 9/10/2019 ND ND ND ND <177 <180 <189 <181 ND ND ND ND ND ND ND ND 9/11/2019 198+/-125 <178 <180 <181 ND ND ND ND ND <180 <181 ND ND ND <191 <181 (repeat) <187 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 12/18/2019 ND <181 <182 <190 ND ND ND ND ND <187 <184 ND ND ND <188 ND 12/20/2019 448 +/- 133 ND ND ND <188 <189 <188 <188 ND ND ND ND ND ND ND <192 ND No Data Sample obtained as required 98

January 1 - December 31, 2019 Docket Nos. 50-317/50-318/72-8 Table E-10 Concentration of Tritium in Surface Water, Precipitation, and Subsurface Drainage (Results in units of pCi/L +/- 2a) SAMPLE DATE

  • MH-66/S8D3 MH28 MH30 SW003 SW004 RWl RW2 RW3 RW4 1/31/2019 ND 2430+/-304 1400 +/- 210 ND ND ND ND ND ND 2/12/2019 ND ND ND

<191 <188 ND ND ND ND 2/13/2019 <187 ND ND ND ND ND ND ND ND 3/29/2019 ND ND ND ND ND <195 <196 <195 <195 5/7/2019 ND 1840 +/- 256 2070+/- 278 <195 <196 ND ND ND ND 8/14/2019 ND 1830 +/- 252 1710 +/- 241 ND ND ND ND ND ND 9/27/2019 ND ND ND 252 +/- 126 <190 <193 <188 <189 <191 (Confinnation / (214+/-127/ Repeat) 246+/- 127) 9/27/2019 ND ND ND 218 +/- 128 214 +/-127 ND ND ND ND (Confirmation/ (<193/ (<192/ Repeat) 288+/- 127) 298+/-128) 9/30/2019 <192 ND ND ND ND ND ND ND ND 11/19/2019 ND 2150 +/- 282 1690 +/- 239 ND ND ND ND ND ND 12/31/2019 ND ND ND <181 <186 <189 <188 <184 <188

  • MH24 Renamed MH-66/SSD3 99

Table E-11 Gross Concentration of Gamma Emitters in Groundwater SAMPLE DATE 11 12 13 6/11/2019 ND ND ND 6/12/2019 ND ND 9/10/2019 ND ND ND 9/11/2019 12/20/2019 ND ND

  1. Tritium Less than minimum Detectable Activity(<MDA)

ND No Data - Quarterly sample obtained as required. (Results in units of pCi/L +/- 2o-) By Piezometer Tube Locations 15 19 20 21 22 23 24 25 , ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 100 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 26 27 28 29 30 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND

Table E-12 January 1 - December 31, 20 I 9 Docket Nos. 50-317/50-318/72-8 Gross Concentration of Gamma Emitters in Surface Water, Precipitation and MH (subsurface drains) (Results in units of pCi/L +/- 2a) SAMPLE DATE

  • MH66/SSD3 MH28 2/12/2019 ND ND 2/13/2019 ND 8/14/2019 ND

'MH24 Renamed as MH66/SSD3

  1. All Non-Natural Gamma Emitters <MDA ND No Data Sample obtained as required.

MH30 SW003 SW004 RWl RW2 RW3 RW4 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 101

Figure E-1 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8 Site Map Groundwater Monitoring Wells 0 200 Explanation: Surface Waler Maniloring Location e Groundwater Moniloring l.ocalion MH-28 e MH-30 e 102

Figure E-2 Site Map Rainwater Locations 103 January 1 - December 31, 2019 Docket Nos. 50-317 /50-318/72-8}}