Text

2019 Annual Radioactive Effluent Release Report (Rerr)
	ML20115E576
Person / Time
Site:	Salem, Hope Creek
Issue date:	04/27/2020
From:	Poorman S, Sharbaugh D; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N20-0025
	Download: ML20115E576 (121)
	v • d • e

April 27, 2020 SGS RERR-68 HCGS RERR-42 Unit 1 Unit 2 Unit 1 DOCKET NO 50-272 DOCKET NO 50-311 DOCKET NO. 50-354 OPERATING LICENSE NO DPR-070 OPERATING LICENSE NO DPR-075 OPERATING LICENSE NO. NPF-057 Report Prepared by: ____________________________________ 04/06/2020 Date__________

Rick Heathwaite (REMP/REC Program Manager)

Station Reviews and Approvals Salem Hope Creek

__________________________ Date ________ __________________________ Date ________

Shane Howe (R.P. Manager) Harold Trimble (RP Manager)

__________________________ Date ________ __________________________ Date ________

William Gropp (Chem. Manager) Ronald Rattigan (Chem. Manager)

__________________________ Date ________ __________________________ Date ________

Richard DeSanctis (Sr. Dir. Operations) James Priest (Sr. Dir. Operations)

__________________________ Date ________ __________________________ Date ________ 4/16/20 David Sharbaugh (Plant Manager) Steven Poorman (Plant Manager)

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Page Intentionally Left Blank

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table of Contents I Executive Summary .............................................................................................................................. 1 II Introduction............................................................................................................................................ 1 III Supplemental Information ..................................................................................................................... 2

1. Regulatory Limits .......................................................................................................................... 2

2. Maximum Permissible Concentration (MPC) Limits ..................................................................... 3

3. Average Energy ............................................................................................................................ 3

4. Measurements and Approximations of Total Radioactivity ........................................................... 4 A. Liquid Effluents ....................................................................................................................... 4 B. Gaseous Effluents .................................................................................................................. 4

5. Estimated Total Error .................................................................................................................... 6

6. Non-Routine Planned Discharges and Unplanned Discharges ................................................... 6

7. Other Events ................................................................................................................................. 8

8. Changes to the Offsite Dose Calculation Manuals ......................................................................... 8

9. Changes from the Annual Land Use Survey Affecting ODCM ..................................................... 8

10. Changes to the Process Control Program .................................................................................... 8

11. Radioactive Effluent Monitoring Instrumentation Out of Service for More than 30 Days ............. 8 A. SGS Unit 1: ......................................................................................................................... 8 B. SGS Unit 2 .......................................................................................................................... 8 C. HCGS: ................................................................................................................................. 8

12. Elevated Gaseous Radiation Monitor Responses ........................................................................ 8

13. Independent Spent Fuel Storage Installation (ISFSI) ................................................................... 9

14. Effluent Trends .............................................................................................................................. 9

15. Carbon-14 in Gaseous Effluents ................................................................................................. 13

16. Modification to Previous Radioactive Effluent Release Reports - Errata Data Section .............. 14 IV Radiological Impact on Man ................................................................................................................ 18

1. Effluent Doses ............................................................................................................................. 18 A. Doses from Gaseous Effluent using Default Conservative Meteorology ............................. 18 B. Doses from Liquid Effluent ................................................................................................... 20 C. Doses from Gaseous Effluent using Annual Average Meteorology ..................................... 21

2. Total Dose to a Member of the Public, Resulting from Radioactive Effluent Releases and Radiation from Uranium Fuel Cycle Sources .............................................................................. 26

3. Dose to Members of the Public Due to Activities Inside the Site Boundary ............................... 27 APPENDIX A-1, Effluent and Waste Disposal Summary, Salem Unit 1 ..................................................... 29 APPENDIX A-2, Effluent and Waste Disposal Summary, Salem Unit 2 ..................................................... 37 APPENDIX A-3, Effluent and Waste Disposal Summary, Hope Creek 1 ................................................... 53 APPENDIX B, Meteorological Data ............................................................................................................. 69 APPENDIX C, Maximum Permissible Concentration (MPC) Data .............................................................. 79 APPENDIX D, 2019 Radiological Groundwater Protection Program (RGPP) Report ................................ 87 PSEG Nuclear: 2019 AREOR i of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table of Contents (continued)

List of Tables Table 1 Quarterly and Annual Bone Doses from Radioactive Gaseous Effluent Releases from the Site to the Critical Receptor (Child) and Pathway (Inhalation, Meat, Food Products and Ground Shine) ................................................................................................................. 14 Table 2 2019 Doses and Percent of the Limits from Gaseous Effluents by Operating Unit ................. 18 Table 3 2019 Doses and Percent of the Limits from Liquid Effluents by Operating Unit ..................... 20 Table 4 2019 Annual Average Undepleted X/Q, Depleted X/Q and D/Q and Active Exposure Pathways ................................................................................................................................. 22 Table 5 2019 Total Body and Critical Organ Doses at Receptor Locations Using Annual Average X/Q and D/Q Data by Operating Unit ...................................................................................... 24 Table 6 2019 Total Body and Organ Doses due to Liquid and Gaseous Effluents and Direct Shine ISFSI Dose to the Critical Receptor Located at 4.6 miles SW ...................................... 26 Table 7 Summary of TEDE doses to Members of the Public Due to Activities inside the Site Boundary.................................................................................................................................. 27 List of Figures Figure 1 Fission and Activation Gases Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2019 ............................................................................................................ 9 Figure 2 Iodines Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 -

2019 ......................................................................................................................................... 10 Figure 3 Particulates Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 -

2019 ......................................................................................................................................... 11 Figure 4 Tritium Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2019 ... 11 Figure 5 Fission and Activation Products Released in Liquid Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2019 .......................................................................................................... 12 Figure 6 Tritium Released in Liquid Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2019 ........ 12 Figure 7 Locations of Dose Calculation Receptors with 2019 Wind Rose Overlay ............................... 23 PSEG Nuclear: 2019 AREOR ii of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T I. Executive Summary In 2019, Salem Generating Station (SGS) Unit 1 and Unit 2 and Hope Creek Generating Station (HCGS) Unit 1 released to the environment through the radioactive liquid and gaseous effluents 32.15 curies of noble gas, 0.04 curies of fission and activation products, and 2,286 curies of tritium.

The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:

Gaseous and liquid radiation doses to members of the public at the highest dose receptor

% of Applicable Estimated Age Receptor Effluent Applicable Limit Units Organ Dose Group Location Limit Gamma - Air 3.36E-04 0.11% 30 Dose Noble Gas All Site Boundary mRad Beta - Air Dose 1.42E-04 0.02% 60 Iodine, Particulate, Bone 3.22E-01 Child 4.6 miles SW 0.72% 45 mrem C-14 & Tritium Total Body 1.83E-02 0.41% 9 0.75 mi. N Liquid Adult mrem of Salem Gi-Lli 4.51E-02 0.15% 30 The calculated doses from the radiological effluents released from the three units were a very small percentage of the allowable limits.

The Total Dose to the Critical Receptor as required by section 3.11.4 of the SGS and HCGS ODCMs was determined to be 5.69E-01 mrem (Table 6). The dose calculated was below the limits of 40 CFR 190 and 10 CFR 72.104 (25 mrem) to the total body and critical organ other than the thyroid.

Maximum TEDE doses to groups of Members of the Public (Sewage Treatment Plant Worker and Security Checkpoint) not having access to the Radiologically Controlled Area (RCA) were calculated as 2.47E+00 mrem and 2.90E-02 mrem, respectively (Table 7). These doses were a small fraction of the 10 CFR 20.1301 dose limit of 100 mrem.

II. Introduction This report, SGS-RERR-68/HCGS-RERR-42, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid forms from SGS and HCGS for the period January 1, 2019, to December 31, 2019.

SGS Unit 1 is a Westinghouse Pressurized Water Reactor that has a licensed core thermal power rating of 3,459 MW th and an approximate net electrical output of 1,180 MW e. SGS Unit 1 achieved initial criticality on December 11, 1976, and began commercial operation on June 30, 1977.

SGS Unit 2 is a Westinghouse Pressurized Water Reactor that has a licensed core thermal power rating of 3,459 MW th and an approximate net electrical output of 1,178 MW e. SGS Unit 2 achieved initial criticality on August 2, 1980, and began commercial operation on October 13, 1981.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T HCGS is a General Electric Boiling Water Reactor that has an up rated core thermal power rating of 3,902 MW th and an approximate net electrical output of 1,212 MW e. The HCGS achieved initial criticality on June 28, 1986 and began commercial operation on December 20, 1986.

This report complies with the format described in Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Revision 1, June, 1974, as required by Control 6.9.1.8 of the SGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM) and Control 6.9.1.7 of the HCGS ODCM. Revision 2, June 2009 of this Guide permits data tables to be supplied as annual tables.

Meteorological data was obtained in the format specified in Regulatory Guide 1.23, Revision 1 Meteorological Monitoring Programs for Nuclear Power Plants, and retained on site. Detailed meteorological data was not presented in this report.

All vendor results for samples obtained in 2019 were received and included in the report calculations. Therefore, the 2019 report is complete and no supplements to the 2019 evaluating period will be required.

III. Supplemental Information

1. Regulatory Limits The same regulatory limits apply to SGS Unit 1, SGS Unit 2 and HCGS. The limits were as follows:

ODCM and 10 CFR 50, Appendix I Limit Units Receptor Design Objective Limits

1. Noble Gases:

< 500 Total Body

a. mrem/yr ODCM Control 3.11.2.1.a

< 3000 Skin

<5 Air Gamma Quarterly air dose limits:

b. mRad

< 10 Air Beta ODCM Control 3.11.2.2.a

< 10 Air Gamma Yearly air dose limits:

c. mRad

< 20 Air Beta ODCM Control 3.11.2.2.b

< 10 Total Body (Gamma)

d. mrem 10 CFR 50, Appendix I, Section II.B.2(b)

< 30 Skin (Beta)

2. Iodines, Tritium, Particulates with Half-Lives > 8 days:

a. < 1500 mrem/yr Any Organ ODCM Control 3.11.2.1.b Quarterly dose limits:

b. < 7.5 mrem Any Organ ODCM Control 3.11.2.3.a Yearly dose limits:

c. < 15 mrem Any Organ ODCM Control 3.11.2.3.b PSEG 2019 ARERR Page 2 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T ODCM and 10 CFR 50, Appendix I Limit Units Receptor Design Objective Limits

3. Liquid Effluents The concentration limits in 10 CFR 20, Appendix B, Table II Col. 2 (pre 1994). For dissolved or

a. ODCM Control 3.11.1.1 entrained noble gases, the concentration shall be limited to 2E-04 uCi//ml.

< 1.5 Total Body Quarterly dose limits

b. mrem

<5 Any Organ ODCM Control 3.11.1.2.a

<3 Total Body Yearly dose limits

c. mrem

< 10 Any Organ ODCM Control 3.11.1.2.b

4. Total Dose Limits

< 25 Total Body or Organ Yearly dose limits

a. mrem ODCM Control 3.11.4

< 75 Thyroid 40 CFR 190 and 10 CFR 72.104

b. < 100 mrem Site TEDE Dose 10 CFR 20.1301

2. Maximum Permissible Concentration (MPC) Limits Gaseous dose rate limits rather than maximum permissible concentration limits were used to calculate permissible release rates for gaseous releases. The maximum permissible dose rates for gaseous releases were defined in ODCM Controls 3.11.2.1.a and 3.11.2.1.b.

The Maximum Permissible Concentration Limit specified in 10 CFR 20, Appendix B, Table II, Column 2 (pre 1994) for identified nuclides, were used to calculate permissible release rates and concentrations for liquid release in accordance with the SGS Unit 1 and Unit 2 and the HCGS Offsite Dose Calculation Manual Control 3.11.1.1. The total activity concentration for all dissolved or entrained gases was limited to < 2.00E-04 uCi/ml.

3. Average Energy The SGS ODCM and the HCGS ODCM limit the instantaneous dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem/year to the total body and less than or equal to 3,000 mrem/year to the skin. The average beta and gamma energies of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," may be used to calculate doses in lieu of more sophisticated software. The SGS and HCGS radioactive effluent programs employ the methodologies presented in U.S.

NRC Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978. Therefore, average energies were not applicable to SGS and HCGS.

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4. Measurements and Approximations of Total Radioactivity A. Liquid Effluents:

Liquid effluents were monitored in accordance with Table 4.11-1 of the SGS ODCM and Table 4.11.1.1.1-1 of the HCGS ODCM.

During 2019, all routine batch liquid wastes were routed to sampling tanks for monitoring prior to release. The ODCMs require these tanks to be uniformly mixed for sampling and analysis before being released.

Batch releases were defined as:

For SGS, releases from the Service Water Drums, which were collected and disposed via the Chemical Waste Basin, and the Chemical Volume Control System (CVCS)

Monitor Tanks. During 2019, all batch liquid wastes from the Chemical Drain Tank and Laundry and Hot Shower Tanks were routed to Waste Monitor Holdup Tanks for monitoring prior to release. For flexibility in processing liquid effluents, the SGS Units 1 and 2 Liquid Radwaste Systems were cross-connected.

For HCGS, releases from the Equipment Sample Tanks, Floor Drain Sample tanks, and Detergent Drain Tanks and Condensate Storage Tank Dike.

Continuous releases were defined as:

For SGS, continuous liquid release pathways include Secondary System Leakage from the Condensate system and the Unit 1 Groundwater Recovery System through the Chemical Waste Basin.

For HCGS, a continuous liquid effluent release path exists through the Circulating Water Dewatering Sump Discharge.

Representative samples were obtained in accordance with Table 4.11-1 of the SGS ODCM for SGS and Table 4.11.1.1.1-1 of the HCGS ODCM for HCGS. The total liquid activity discharged was determined by multiplying specific activities from the analyses by the volume of effluent discharged to the environment.

The detection requirements of Table 4.11-1 (SGS) and Table 4.11.1.1.1-1 (HCGS) of the ODCM were achieved. Radionuclides that were measured at concentrations below the ODCM-specified lower limit of detection (LLD) were considered present. A radionuclide for which no activity was detected while meeting the required LLD was considered absent.

B. Gaseous Effluents:

SGS Units 1 and 2:

Gaseous effluent streams at SGS were monitored and sampled in accordance with Table 4.11-2 of the ODCM. Each plant vent was the final release point for planned gaseous effluent releases and was continuously monitored by installed radiation monitors. The vent was also continuously sampled for iodine and particulates with fixed particulate and charcoal filters. The filter and charcoal were normally changed weekly, and analyzed on a multi-channel analyzer.

Sampling was also performed on all gas decay tanks and the containment atmosphere prior to release to the environment. The plant vent for each unit was normally sampled weekly for noble gases, particulates, iodine, and tritium.

The detection requirements of Table 4.11-2 of the ODCM were achieved. A positive detection of a radionuclide a concentration below the ODCM LLD was considered present. A radionuclide for which no positive activity was detected while meeting the required LLD was considered absent. Only plant produced radionuclides were reported in this report.

Continuous gaseous releases were quantified by routine sampling and isotopic analyses of the plant vent for each unit, as required by the ODCM. Specific activities for detected isotopes PSEG 2019 ARERR Page 4 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T were multiplied by the total vent flow volume for the entire sampling period in order to determine the normal continuous release of radioactivity through each plant vent.

Batch noble gas releases were quantified by sampling each waste gas decay tank, pressurizer relief tank, reactor coolant drain tank, volume control tank or by containment atmosphere prior to release. The total activity in a batch release was determined by multiplying the specific activities for detected isotopes by the total volume of the gas discharged in that batch release.

Elevated plant vent radiation monitoring system readings while the channel was in an alarm state were treated as batch mode releases. If specific activity data from grab samples were not available, then the release was quantified by the use of the plant vent radiation monitors.

The monitor response was converted to specific activity using historical efficiency factors.

The total activity discharged was determined by multiplying the specific activity by the volume of effluent discharged while the channel was in an alarm state.

HCGS:

Gaseous effluent streams at HCGS were monitored and sampled in accordance with Table 4.11.2.1.2-1 of the ODCM. The North Plant Vent (NPV) and South Plant Vent (SPV) were the final release points for planned gaseous effluent releases. The NPV and SPV were continuously monitored for iodine, particulates and noble gases. These monitors have fixed particulate and charcoal filters. The particulate filters and charcoal cartridges were normally replaced and analyzed weekly. These analyses were performed on a multi-channel analyzer.

The NPV and SPV were also normally sampled weekly for noble gases and tritium.

A small quantity of gaseous effluent was released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during FRVS testing periods. The FRVS was continuously monitored for noble gases when in service, and has fixed particulate and charcoal filters.

When the system was in vent mode for greater than two hours, samples were collected at the end of the release period. During periods of extended runs, samples were normally taken weekly.

A small quantity of gaseous tritium was released via the Turbine Lube Oil Vapor Extraction (TLOVE) system. The TLOVE is comprised of the 3-inch Reactor Feedwater Pump Turbine (RFPT) Vent Line, 3-inch and 10-inch Generator Hydrogen Seal Oil (GHSO) Vent Lines, and the 8-inch Main Turbine Lube Oil (MTLO) Vent Line.

The detection requirements of Tables 4.11.2.1.2-1 of the ODCM were achieved or exceeded.

A radionuclide detected at a concentration below the ODCM LLD was considered present. A radionuclide for which no activity was detected while meeting the required LLD was considered absent.

Batch noble gas releases (i.e. primary containment purge) were quantified by pre-release sampling and isotopic analysis. The total radioactivity released was estimated by multiplying the specific activities for detected isotopes by the containment volume.

The SGS and HCGS ODCMs required LLD for airborne and liquid releases were as follows:

LLD Liquid (uCi/ml)

Principal Gamma Emitters:

5E-07 Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 Ce-144 - HCGS 5E-06 Ce-144 - SGS 2E-06 I-131 1E-06 Entrained Gases 1E-05 H-3 1E-05 Gross Alpha 1E-07 Sr-89, Sr-90 5E-08 Fe-55 1E-06 PSEG 2019 ARERR Page 5 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T LLD Airborne (uCi/cc)

Gross Alpha, Sr-89, Sr-90 1E-11 H-3 1E-06 I-131 1E-12 Principal Gamma Emitters:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, 1E-11 Ce-144 Noble Gas:

1E-04 Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138

5. Estimated Total Error The estimated total error reported for continuous and batch liquid releases for all three stations was within 27%. The estimated total error for continuous and batch gaseous releases, and solid waste was within 35%.

6. Non-Routine Planned Discharges and Unplanned Discharges Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2 defines a non-routine, planned discharge as an effluent release from a release point that is not defined in the ODCM, but that has been planned, monitored, and discharged in accordance with 10 CFR 20.2001. The regulatory guide defines an unplanned discharge as the unintended or unexpected discharge of liquid or airborne radioactive material to the unrestricted area.

SGS Unit 1 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 0 0 0 0 0 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged N/A N/A N/A N/A N/A Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 0 0 0 0 0 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged N/A N/A N/A N/A N/A N/A (Not Applicable)

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T SGS Unit 2 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 0 0 0 0 0 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged N/A N/A N/A N/A N/A Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 0 0 0 0 0 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged N/A N/A N/A N/A N/A N/A (Not Applicable)

HCGS:

Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 8 3 1 0 12 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged 2.53E-03 7.54E-04 4.51E-04 0.00E+00 3.74E-03 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine Planned 3 3 3 3 12 Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged 3.35E+00 5.73E+00 4.52E+00 3.15E+00 1.67E+01 N/A (Not Applicable)

1. Twelve planned non-routine discharges occurred from pumping the water collected in the Condensate Storage Tank dike that contained small quantities of tritium. This water was discharged via the cooling tower blowdown to the Delaware River.

2. The TLOVE system that discharges gaseous effluents through vents on top of the Turbine Building Roof had monthly release permits issued for the estimated tritium released via the airborne pathway. This is considered a non-routine planned discharge. Each monthly permit represents the combined gaseous curies from the TLOVE system. This activity was calculated using the maximum design flow for each vent, average monthly RCS tritium concentration and the differential temperature between each vent line and the ambient temperature.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T

7. Other Events SGS Unit 1 The 2019 Radiological Groundwater Protection Program (RGPP) tritium mass flux calculation determined 0.057 curies was discharged to the Delaware River. A discussion of the RGPP program is detailed in Appendix D.

SGS Unit 2 None HCGS The Circulating Water Dewatering Sump compositor was found de-energized on 11/11/2019. This compositor is used to collect a weekly composite water sample for tritium and other hard-to-detect radionuclides analyses required by the ODCM. There was approximately 1.5 liters of water that had been collected for the week prior to being de-energized. (Notification 20839328)

8. Changes to the Offsite Dose Calculation Manuals There were no changes made to either the SGS or HCGS ODCMs in 2019.

9. Changes from the Annual Land Use Survey Affecting ODCM The 2019 Land Use Survey (LUC) identified that the ODCM critical receptor in the SW sector at 4.6 miles is no longer present. This receptor included the dose pathways of meat, vegetation, inhalation and ground plane. Doses to this receptor will continue to be calculated until that receptor is removed from the stations ODCMs.

10. Changes to the Process Control Program There were no changes to RW-AA-100, Process Control Program for Radioactive Wastes, during 2019.

11. Radioactive Effluent Monitoring Instrumentation Out of Service for More than 30 Days A. SGS Unit 1:

None B. SGS Unit 2:

None C. HCGS:

None

12. Elevated Gaseous Radiation Monitor Responses During the 2019 reporting period, none of the effluent radiation monitors elicited an elevated response during the discharge of liquid and gaseous effluent from either of the SGS Units 1 and 2 or from the HCGS.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T

13. Independent Spent Fuel Storage Installation (ISFSI)

There have been no gaseous or liquid releases from the Independent Spent Fuel Storage Installation (ISFSI) since it was placed in service in the summer of 2006. The direct dose from the ISFSI pad to the Critical Receptor located at 4.6 miles in the SW sector, Members of the Public not having access to the Radiologically Controlled Area (RCA) was determined using the dosimetry results from the 2019 Radiological Environmental Monitoring Program (REMP) and the formula provided in ANSI/HPS N13.37-2014 as follows:

Where:

D2 OF

D1

R1 2 / R22 D2 = Dose that will be extrapolated to Security Checkpoint, Sewage Treatment Plant (STP) and Critical Receptor OF = Occupancy Factor (1 = full time, 0.25 = 2000 hrs.)

D1 = Net Dose that was measured from TLD Location 01S1 R1 = Distance from the source to the location where D1 was obtained R2 = Distance to the location that dose will be extrapolated There are two dosimetry locations (01S1 and 16S2) that measure dose (above background) from the ISFSI.

R1 R1 R2 D2 D2 (ft.) (ft.) (ft.) D1 D1 (mrem) (mrem)

Location Distance Distance Distance (mrem) (mrem) 01S1 16S2 Max D2 Of from from from Net Dose Net Dose OF Extrapolate Extrapolate (mrem)

Extrapolated ISFSI to ISFSI to ISFSI to of TLD 01S1 of TLD 16S2 Occupancy d Dose for d Dose for Extrapolate Dose TLD 01S1 TLD 16S2 Location D1 D1 Factor Location Location d Dose Members of the Public - off Site Critical 171 203 24,288 91.5 71.9 1.00 4.54E-03 5.02E-03 5.02E-03 Receptor Nearest 171 203 19,536 91.5 71.9 1.00 7.01E-03 7.76E-03 7.76E-03 Resident Members of the Public - on Site Security 171 203 6,275 91.5 71.9 0.25 1.70E-02 1.88E-02 1.88E-02 Checkpoint Sewage Treatment 171 203 575 91.5 71.9 0.25 2.02E+00 2.24E+00 2.24E+00 Plant Worker Wind Turbine 171 203 1304 91.5 71.9 .25 3.93E-01 4.36E-01 4.36E-01 Laydown Area

14. Effluent Trends The following trend graphs displays the total curies of liquid and gaseous effluents released for SGS and HCGS from 2005 through 2019.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Figure 1 Fision and Activation Gases Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 1.00E+03 1.00E+02 Curies 1.00E+01 1.00E+00 1.00E-01 1.00E-02 Year Figure 2 Iodines Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 1.0E-02 1.0E-04 1.0E-06 Curies 1.0E-08 1.0E-10 1.0E-12 1.0E-14 Year PSEG 2019 ARERR Page 10 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Figure 3 Particulates Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 1.0E-01 1.0E-02 1.0E-03 Curies 1.0E-04 1.0E-05 1.0E-06 1.0E-07 Year Figure 4 Tritium Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 5.0E+02 4.5E+02 4.0E+02 3.5E+02 Curies 3.0E+02 2.5E+02 2.0E+02 1.5E+02 1.0E+02 5.0E+01 0.0E+00 Year PSEG 2019 ARERR Page 11 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Figure 5 Fission and Activation Products Released in Liquid Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 1.0E+00 1.0E-01 Curies 1.0E-02 1.0E-03 1.0E-04 Year Figure 6 Tritium Released in Liquid Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2019 SGS U1 SGS U2 HCGS 1.0E+03 1.0E+02 Curies 1.0E+01 1.0E+00 Year PSEG 2019 ARERR Page 12 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T

15. Carbon-14 in Gaseous Effluents The NRC has identified Carbon-14 (C-14) as a potential principal radionuclide for gaseous effluent (refer to Regulatory Position 1.9 in Revision 2 of Regulatory Guide 1.21). Since the publication of Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 1, June 1974, the radioactive effluents from commercial nuclear power plants have decreased to the point that C-14 was likely to be a principal radionuclide in gaseous effluents. Gaseous effluent releases from a boiling water reactor (BWR), such as the HCGS, and pressurized water reactor (PWR),

such as the SGS Units 1 and 2, can contain significant quantities of C-14, the NRC has recommended that licensees evaluate C-14 as a potential principal radionuclide for gaseous releases from their facility. Those evaluations have determined that C-14 was a principal radionuclide in gaseous effluent from each of the three stations.

The assessment methodology used to estimate the quantity of C-14 discharged in gaseous effluent from the SGS and HCGS involved the use of a normalized C-14 source term and scaling factors based on power generation from EPRI Technical Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. This method was selected based on guidance offered in Regulatory Guide 1.21, and incorporates dose models described in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.

The following assumptions were incorporated into the method:

Only C-14 in the form of CO2 was incorporated into vegetation through photosynthesis, which causes dose via the ingestion exposure pathways.

The concentration of C-14 in vegetation was proportional to the concentration of C-14 in air (per equation C-8 in Regulatory Guide 1.109).

95% of C-14 released from a BWR (i.e., HCGS) and 30% of C-14 released from a PWR (i.e., SGS Units 1 and 2) was in the form of CO2 (EPRI Technical Report 1021106).

The total MW he electrical output by unit for 2019 was as follows:

x SGS Unit 1 7,944,369 MW he x

SGS Unit 2 9,966,009 MW he x

HCGS 8,726,946 MW he Using scaling factors and the 2019 power generation data, the estimated total C-14 released in 2019 was 9.06 Ci from SGS Unit 1, 11.37 Ci from SGS Unit 2, and 14.93 Ci from the HCGS.

The calculated dose contribution of C-14 was determined using the methodology detailed in the HCGSs and SGSs ODCMs. The calculated maximum total body and organ (bone) doses from C-14 occurred for a child receptor at 4.6 miles SW (Table 1) using the pathways of inhalation, meat and vegetation. The calculated doses from the estimated C-14 in gaseous effluents represent about 100% of the total bone dose from both SGS and HCGS.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 1 Quarterly and Annual Bone Doses from Radioactive Gaseous Effluent Releases from the Site to the Critical Receptor (Child) and Pathway (Inhalation, Meat, Food Products and Ground Shine) 2019.

Bone Dose all Radionuclides Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total except C-14 (mrem)

SGS Unit 1 2.66E-07 4.22E-06 0.00E+00 0.00E+00 4.49E-06 SGS Unit 2 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HCGS 4.05E-04 8.32E-07 2.60E-05 1.05E-05 4.42E-04 Total Bone Dose from Other 4.05E-04 5.05E-06 2.60E-05 1.05E-05 4.46E-04 Radionuclides (mrem)

Bone Dose Including C-14 Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total (mrem)

SGS Unit 1 2.29E-02 2.22E-02 2.40E-02 2.44E-02 9.35E-02 SGS Unit 2 2.83E-02 2.81E-02 2.93E-02 3.14E-02 1.17E-01 HCGS 2.51E-02 2.74E-02 2.76E-02 3.11E-02 1.11E-01 Total Dose (mrem) 7.63E-02 7.77E-02 8.09E-02 8.69E-02 3.22E-01 Total Dose From C-14 (mrem) 7.59E-02 7.77E-02 8.09E-02 8.69E-02 3.21E-01 Percent of dose from C-14 99.5% 100.0% 100.0% 100.0% 99.9%

16. Errata Data Section: Modifications or Revisions Made to Previous Radioactive Effluent Release Reports

1. In 2019 the calculation performed to determine the amount of tritium being released from the lubricating oil ventilation system that discharges to the Turbine Building Roof was modified to use the maximum design flow for the four release points (8 MTLO Vent, 3 RFPT Vent, 3 GHSO Vent and the 10 GHSO Vent) in the calculation of tritium released to the atmosphere. Using this new calculation, the non-routine planned discharges from the TLOVE system reported in the 2017 and 2018 ARERR were revised as follows:

2017 Reported Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 3 3 3 3 12 Planned Discharges Total Curies Discharged 1.44E+00 1.58E+00 1.12E+00 1.51E+00 5.65E+00 2017 Revised Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 3 3 3 3 12 Planned Discharges Total Curies Discharged 2.89E+00 3.43E+00 2.52E+00 3.15E+00 1.20E+01 PSEG 2019 ARERR Page 14 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 2018 Reported Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 3 3 3 3 12 Planned Discharges Total Curies Discharged 1.54E+00 1.15E+00 1.25E+00 1.82E+00 5.76E+00 2018 Revised Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 3 3 3 3 12 Planned Discharges Total Curies Discharged 3.05E+00 1.69E+00 2.85E+00 3.79E+00 1.14 E+01 The revised calculation determined that an additional 6.35 curies of tritium was released in 2017 and an additional 5.64 curies of tritium was released in 2018 from the TLOVE system.

These revisions represent an increase of 1.7% and 1.2% of the 2017 and 2018 total gaseous tritium releases, respectively. In addition to updating the above tables the summary tables for gaseous releases for both 2017 and 2018 tritium values were updated.

TABLE 2A-3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: HCGS Period: 2017 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

Total Release Ci < LLD < LLD < LLD < LLD < LLD 3.400E+01 Average release rate for the period Ci/sec < LLD < LLD < LLD < LLD < LLD Gamma Air %

Percent of limit (ODCM 3.11.2.2(a)) See Table 3 on page 20 Beta Air %

B. Iodines and Halogens Total Release Ci 5.66E-04 1.92E-03 1.75E-03 1.59E-03 5.83E-03 3.00E+01 Average release rate for the period Ci/sec 7.28E-05 2.44E-04 2.21E-04 2.00E-04 1.85E-04 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

C. Particulates Particulates with half-lives > 8 days Ci 3.31E-04 7.49E-04 3.12E-04 6.75E-04 2.07E-03 3.00E+01 Average release rate for the period Ci/sec 4.25E-05 9.53E-05 3.93E-05 8.49E-05 6.55E-05 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 9.96E+01 9.81E+01 1.09E+02 6.79E+01 3.75E+02 3.10E+01 Average release rate for the period Ci/sec 1.28E+01 1.25E+01 1.37E+01 8.54E+00 1.19E+01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

E. C-14 Total Release Ci 4.53E+00 4.53E+00 4.58E+00 4.58E+00 1.82E+01 N/A Average release rate for the period Ci/sec 5.83E-01 5.77E-01 5.77E-01 5.77E-01 5.77E-02 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

F. I-131, I-133, H-3 & Particulates > 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 3 on page 20 G. I-131, I-133, H-3, Particulates > 8 day half-life & C-14 Percent of limit (ODCM 3.11.2.3(a)) % See Table 3 on page 20 PSEG 2019 ARERR Page 15 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1A-3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: HCGS Period: 2018 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

Total Release Ci < LLD 7.69E-05 7.20E-01 1.27E+00 1.99E+00 3.40E+01 Average release rate for the period Ci/sec < LLD 9.78E-06 9.06E-02 1.60E-01 6.32E-02 Gamma Air %

Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %

B. Iodines and Halogens Total Release Ci 2.05E-03 2.45E-04 2.20E-06 7.83E-06 2.30E-03 3.00E+01 Average release rate for the period Ci/sec 2.63E-04 3.11E-05 2.77E-07 9.85E-07 7.29E-05 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

C. Particulates Particulates with half-lives > 8 days Ci 2.29E-04 < LLD 4.45E-06 2.16E-06 2.35E-04 3.00E+01 Average release rate for the period Ci/sec 2.94E-05 < LLD 5.60E-07 2.72E-07 7.46E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 1.35E+02 6.27E+01 9.93E+01 1.65E+02 4.62E+02 3.10E+01 Average release rate for the period Ci/sec 1.74E+01 7.97E+00 1.25E+01 2.07E+01 1.46E+01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

E. C-14 Total Release Ci 4.32E+00 3.58E+00 4.03E+00 4.40E+00 1.63E+01 N/A Average release rate for the period Ci/sec 5.56E-01 4.55E-01 5.07E-01 5.53E-01 5.18E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

F. I-131, I-133, H-3 & Particulates > 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18 G. I-131, I-133, H-3, Particulates > 8 day half-life & C-14 Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18

2. The total cubic meters shipped in 2018 from SGS Units 1 and 2 Table 3A-2 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal was reported as 2.44E+010. The correct value was 2.44E+01. (Notification 20836989) The revised table is included below.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Facility: SGS Units 1 and 2 Period: 2018

a. Waste Stream; Resins, Filters, and Evaporator Bottoms Liquid Waste Processing Resin Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 7.60E+02 2.15E+01 8.10E+00 +/-25%

B 1.00E+02 2.83E+00 4.32E+01 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 8.60E+02 2.44E+01 5.13E+01 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Percent Abundance Curies H-3 1.26% 1.02E-01 Fe-55 9.30% 7.53E-01 Co-58 2.60% 2.11E-01 Co-60 25.50% 2.06E+00 Ni-63 55.02% 4.46E+00 Sb-125 1.84% 1.49E-01 Cs-137 2.34% 1.90E-01 Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies Fe-55 2.42% 1.04E+00 Co-60 11.91% 5.14E+00 Ni-63 77.71% 3.36E+01 Cs-137 6.03% 2.60E+00 Resins, Filters and Evaporator Bottoms Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A PSEG 2019 ARERR Page 17 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T IV. Radiological Impact on Man

1. Effluent Doses The doses from gaseous and liquid effluent represent the maximum potential radiation dose for a member of the general public following the methodology in the stations ODCM and reported by the SGSs and HCGSs OpenEMS database programs.

The annual doses presented in the tables below represent calculations for the four quarters of 2019. The radiological doses from SGS Units 1 and 2 and HCGS from gaseous and liquid effluent discharges are presented in Tables 2 and 3, respectively, and demonstrate compliance with applicable regulatory limits. Dose limit values presented in bold font are regulatory limits.

The quarterly doses must not exceed the quarterly limit in any quarter and the summation of two or more quarterly doses must not exceed the annual dose limit.

A. Doses from Gaseous Effluent using Default Conservative Meteorology:

Quarterly doses from gaseous effluent were calculated using the methodology described in the SGS and HCGS ODCMs. Usage factors and dose conversion factors used in the gaseous dose calculations were those presented in the SGS and HCGS ODCMs.

The individual doses from radioactive gaseous effluents (presented in Table 2) were calculated for the controlling locations described in the SGS and HCGS ODCMs using the methodology in the ODCMs by the SGSs OpenEMS and the HCGS OpenEMS database programs. The dose contribution from C-14 was determined by OpenEMS using the methodology listed in the stations ODCM.

Table 2 2019 Doses and Percent of the Limits from Gaseous Effluents by Operating Unit SGS Unit 1 Gaseous Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Beta Gamm Dose Limit (mrad) 5.00E+00 1.00E+01 Gaseous Dose Max Gamma Air Dose (mrad) 3.74E-05 1.04E-05 2.36E-05 2.97E-05 1.01E-04

% Dose Limit < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 From I-131, I-133, H-3, Gaseous Dose Air a Air Dose Limit (mrad) 1.00E+01 2.00E+01 Maximum Beta Air Dose (mrad) 1.57E-05 1.10E-05 8.95E-06 1.14E-05 4.70E-05

% Dose Limit < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 C-14* and Particulate From Noble Organ Dose Limit (mrem) 7.50E+00 1.50E+01

no ODCM Critical Receptor (mrem) 4.34E-03 7.68E-03 5.19E-03 3.83E-03 2.10E-02 Nuclides Gas C-14 Dose % Dose Limit 0.06 0.10 0.07 0.05 0.14

with ODCM Critical Receptor (mrem) 2.29E-02 2.22E-02 2.40E-02 2.44E-02 9.35E-02 with half-life > 8 Days C-14 Dose % Dose Limit 0.31 0.30 0.32 0.33 0.62 PSEG 2019 ARERR Page 18 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 2 2019 Doses and Percent of the Limits from Gaseous Effluents by Operating Unit (cont.)

SGS Unit 2 Gaseous Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Gaseous Dose Dose Limit (mrad) 5.00E+00 1.00E+01 Gamma Max Gamma Air Dose (mrad) 3.05E-05 2.86E-05 2.54E-05 4.90E-05 1.33E-04 Air

% Dose Limit < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 From I-131, I-133, H-3, Dose Limit (mrad) 1.00E+01 2.00E+01 Beta Air Gaseous Dose From Maximum Beta Air Dose (mrad) 1.11E-05 1.01E-05 9.88E-06 1.73E-05 4.83E-05 C-14* and Particulate

% Dose Limit < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 Noble Gas Organ Dose Limit (mrem) 7.50E+00 1.50E+01 Nuclides

no ODCM Critical Receptor (mrem) 3.27E-04 3.40E-03 2.67E-03 3.29E-03 9.69E-03 C-14 Dose % Dose Limit < 0.01 0.05 0.04 0.04 0.06 with half-life > 8 Days

with ODCM Critical Receptor (mrem) 2.83E-02 2.81E-02 2.93E-02 3.14E-02 1.17E-01 C-14 Dose % Dose Limit 0.38 0.38 0.39 0.42 0.78 HCGS Gaseous Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Gaseous Dose From Dose Limit (mrad) 5.00E+00 1.00E+01 Gamma Max Gamma Air Dose (mrad) 2.69E-04 6.08E-07 1.39E-03 2.37E-04 1.90E-03 Air

% Dose Limit 0.01 < 0.01 0.03 0.00 0.02 I-131, I-133, H-3, C-14*

Dose Limit (mrad) 1.00E+01 2.00E+01 Beta Air Gaseous Dose From Maximum Beta Air Dose (mrad) 2.93E-04 1.79E-06 2.47E-03 4.38E-04 3.21E-03 and Particulate

% Dose Limit < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 Noble Gas Organ Dose Limit (mrem) 7.50E+00 1.50E+01 Nuclides

no ODCM Critical Receptor (mrem) 1.25E-02 5.43E-03 8.45E-03 1.40E-02 4.03E-02 C-14 Dose % Dose Limit 0.17 0.07 0.11 0.19 0.27 with half-life > 8 Days

with ODCM Critical Receptor (mrem) 2.51E-02 2.74E-02 2.76E-02 3.11E-02 1.11E-01 C-14 Dose % Dose Limit 0.33 0.36 0.37 0.41 0.74 PSEG 2019 ARERR Page 19 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 2 2019 Doses and Percent of the Limits from Gaseous Effluents by Operating Unit (cont.)

SGS-HCGS Site Total Gaseous Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Gaseous Dose Dose Limit (mrad) 1.50E+01 3.00E+01 Gamma Max Gamma Air Dose (mrad) 3.37E-04 3.96E-05 1.44E-03 3.15E-04 2.13E-03 Air

% Dose Limit < 0.01 < 0.01 0.01 < 0.01 0.01 From I-131, I-133, H-3, Dose Limit (mrad) 3.00E+01 6.00E+01 Beta Air Gaseous Dose From Maximum Beta Air Dose (mrad) 3.19E-04 2.29E-05 2.49E-03 4.67E-04 3.30E-03 C-14* and Particulate

% Dose Limit < 0.01 < 0.01 0.01 < 0.01 0.01 Noble Gas Organ Dose Limit (mrem) 2.25E+01 4.50E+01 Nuclides with half-life

no ODCM Critical Receptor (mrem) 1.71E-02 1.65E-02 1.63E-02 2.11E-02 7.10E-02 C-14 Dose % Dose Limit 0.08 0.07 0.07 0.09 0.16

> 8 Days

with ODCM Critical Receptor (mrem) 7.63E-02 7.77E-02 8.09E-02 8.69E-02 3.22E-01 C-14 Dose % Dose Limit 0.34 0.35 0.36 0.39 1.43 B. Doses from Liquid Effluent:

Quarterly and Annual Total Body and Critical Organ doses from liquid effluent were calculated using the methodology described in the SGS and HCGS ODCMs at the controlling receptor location of 0.75 miles N of SGS. Usage factors and dose conversion factors used in the liquid dose calculations were those presented in the SGS and HCGS ODCMs.

Table 3 2019 Doses and Percent of the Limits from Liquid Effluents by Operating Unit SGS Unit 1 Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit (mrem) 1.50E+00 3.00E+00 Maximum Total Body Dose (mrem) 3.42E-03 3.14E-03 1.93E-03 4.99E-03 1.35E-02

% Dose Limit 0.23 0.21 0.13 0.33 0.45 Organ Dose Limit (mrem) 5.00E+00 1.00E+01 Maximum Organ Dose (mrem) 4.11E-03 5.01E-03 2.52E-03 5.11E-03 1.67E-02

% Dose Limit 0.08 0.10 0.05 0.10 0.17 SGS Unit 2 Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit (mrem) 1.50E+00 3.00E+00 Maximum Total Body Dose (mrem) 1.27E-03 1.01E-03 5.58E-04 1.15E-03 3.99E-03

% Dose Limit 0.08 0.07 0.04 0.08 0.13 Organ Dose Limit (mrem) 5.00E+00 1.00E+01 Maximum Organ Dose (mrem) 3.53E-03 1.89E-02 1.62E-03 1.94E-03 2.60E-02

% Dose Limit 0.07 0.38 0.03 0.04 0.26 PSEG 2019 ARERR Page 20 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 3 2019 Doses and Percent of the Limits from Liquid Effluents by Operating Unit (cont.)

HCGS Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit (mrem) 1.50E+00 3.00E+00 Maximum Total Body Dose (mrem) 2.15E-05 5.47E-05 3.99E-05 6.75E-04 7.92E-04

% Dose Limit < 0.01 < 0.01 < 0.01 0.05 0.03 Organ Dose Limit (mrem) 5.00E+00 1.00E+01 Maximum Organ Dose (mrem) 2.37E-05 2.80E-04 7.44E-05 2.04E-03 2.41E-03

% Dose Limit < 0.01 0.01 < 0.01 0.04 0.02 SGS Units 1&2 + HCGS Site Total Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit (mrem) 4.50E+00 9.00E+00 Maximum Total Body Dose (mrem) 4.71E-03 4.21E-03 2.53E-03 6.82E-03 1.83E-02

% Dose Limit 0.10 0.09 0.06 0.15 0.41 Organ Dose Limit (mrem) 1.50E+01 3.00E+01 Maximum Organ Dose (mrem) 7.66E-03 2.41E-02 4.21E-03 9.09E-03 4.51E-02

% Dose Limit 0.05 0.16 0.03 0.06 0.30 C. Doses from Gaseous Effluent using 2019 Annual Average Meteorology:

As a check on the use of conservative historical meteorological dispersion (/Q) and deposition values (D/Q), the 2019 gaseous release curies (Tables 1C-1, 1C-2 and 1C-3) for each of the three units and the 2019 annual average dispersion and deposition data (Table 4) were entered into the NRC approved GASPAR computer program to calculate doses to the critical receptors and pathways identified by the 2019 Land Use Census (LUC). The receptor locations for this dose calculation were plotted with the 2019 wind rose overlay (Figure 7). The 2019 annual joint frequency data and calculated /Q and D/Q values for SGS and HCGS are detailed in Appendix B. The PSEG meteorological monitoring program achieved 96.0% joint frequency data recovery.

The methods used to determine gaseous doses were consistent with the methods described in SGS and HCGS ODCMs and in NRC Regulatory Guide 1.109. The 2019 LUC 2

did not identify any gardens greater than 500 ft within five miles producing broadleaf vegetation; however, that pathway was included in the dose analysis.

Using the 2019 meteorology data the GASPAR calculated doses (Table 5) were lower than those reported in Table 2 for the critical receptor located at 4.6 miles SW using the default ODCM meteorology, except for C-14. The 2019 /Q value was higher than that in the ODCM.

Organ Dose Organ Dose Excluding C-14 Including C-14 Critical Receptor 4.6 mi SW Table 2 page 20 7.10E-02 3.22E-01 Critical Receptor 4.6 mi SW Table 5 page 25 1.76E-02 4.14E-01 PSEG 2019 ARERR Page 21 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 4 2019 Annual Average Undepleted X/Q, Depleted X/Q and D/Q and Active Exposure Pathways Undepleted Depleted D/Q Active Exposure Receptor Location X/Q X/Q 2 3 3 (1/m ) Pathways (sec./m ) (sec./m )

Plume Immersion, HCGS Site- Boundary 1.7E-06 1.6E-06 1.1E-08 Ground Deposition, (0.5 mi N)

Inhalation Plume Immersion, SGS Site-Boundary 7.9E-07 7.0E-07 4.9E-09 Ground Deposition, (0.83 mi N)

Inhalation ODCM Dairy (4.9mi W) Plume Immersion, SGS 8.2E-08 6.1E-08 1.5E-10 Ground Deposition, Inhalation, Milk Ingestion HCGS 8.1E-08 6.1E-08 1.5E-10 Resident (3.7mi NW) Plume Immersion, SGS 1.4E-07 1.1E-07 5.9E-10 Ground Deposition, Inhalation HCGS 1.4E-07 1.1E-07 5.9E-10 Resident-Garden Plume Immersion, (5.0mi ENE) Ground Deposition, SGS 7.0E-08 5.3E-08 2.1E-10 Inhalation HCGS 7.0E-08 5.2E-08 2.1E-10 Vegetable Ingestion Resident-Meat Plume Immersion, (4.2mi NE) Ground Deposition, SGS 1.1E-07 8.1E-08 3.0E-10 Inhalation, Meat HCGS 1.1E-07 8.1E-08 3.0E-10 Ingestion Resident-Garden-Meat Plume Immersion, (4.6mi SW) Ground Deposition, SGS 1.0E-07 7.6E-08 2.7E-10 Inhalation, Meat Ingestion, Vegetable HCGS 1.0E-07 7.5E-08 2.7E-10 Ingestion PSEG 2019 ARERR Page 22 of 116

2019 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 7 Locations of Dose Calculation Receptors with 2019 Wind Rose Overlay Note: Wind rose depicts fraction of time wind transports gaseous effluents from each of the sixteen compass sectors.

The 2019 Joint Frequency Data recovery rate = 96.0%

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 5 2019 Total Body and Critical Organ Doses at Receptor Locations Using Annual Average X/Q and D/Q Data by Operating Unit ODCM Site Boundary Critical Organ Doses Inhalation, Ground Plane (0.5 / 0.8 mi N)

Excluding C-14 Including C-14 Operating Total Body Organ Total Body Organ Unit (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 4.33E-03 4.34E-03 5.44E-03 8.18E-03 SGS Unit 2 2.01E-03 2.03E-03 3.70E-03 1.03E-02 HCGS 1.64E-02 1.80E-02 2.03E-02 3.05E-02 Site Total 2.27E-02 2.44E-02 2.94E-02 4.90E-02 ODCM Dairy Critical Organ Doses Inhalation, Ground Plane, Milk (4.9 mi W)

Excluding C-14 Including C-14 Operating Total Body Organ Total Body Organ Unit (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 1.08E-03 1.08E-03 1.76E-02 7.73E-02 SGS Unit 2 4.96E-04 4.98E-04 2.13E-02 9.73E-02 HCGS 1.77E-03 2.31E-03 2.87E-02 1.26E-01 Site Total 3.35E-03 3.90E-03 6.75E-02 3.01E-01 Nearest Resident Critical Organ Doses Inhalation, Ground Plane (3.7 mi NW)

Operating Excluding C-14 Including C-14 Unit Total Body Organ Total Body Organ (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 7.66E-04 7.69E-04 9.63E-04 1.45E-03 SGS Unit 2 3.57E-04 3.60E-04 6.57E-04 1.83E-03 HCGS 1.34E-03 1.47E-03 1.66E-03 2.49E-03 Site Total 2.47E-03 2.60E-03 3.28E-03 5.77E-03 Resident - Garden Critical Organ Doses Inhalation, Ground Plane, Vegetation (4.4 mi WSW)

Operating Excluding C-14 Including C-14 Unit Total Body Organ Total Body Organ (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 1.56E-03 1.56E-03 1.59E-02 7.18E-02 SGS Unit 2 1.78E-04 1.80E-04 3.28E-04 9.12E-04 HCGS 6.66E-04 7.32E-04 8.28E-04 1.25E-03 Site Total 2.40E-03 2.47E-03 1.70E-02 7.40E-02 PSEG 2019 ARERR Page 24 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 5 2019 Total Body and Critical Organ Doses at Receptor Locations Using Annual Average X/Q and D/Q Data by Each Operating Unit (continued)

Meat Critical Organ Doses Inhalation, Ground Plane, Meat 4.2 mi NNE Operating Excluding C-14 Including C-14 Unit Total Body Organ Total Body Organ (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 7.52E-04 7.55E-04 4.23E-03 1.80E-02 SGS Unit 2 3.49E-04 3.51E-04 4.81E-03 2.26E-02 HCGS 1.29E-03 1.39E-03 7.04E-03 2.99E-02 Site Total 2.39E-03 2.50E-03 1.61E-02 7.05E-02 Meat - Garden Critical Organ Doses Inhalation, Ground Plane, Meat, Vegetation 4.6 mi SW Operating Excluding C-14 Including C-14 Unit Total Body Organ Total Body Organ (mrem) (mrem) (mrem) (mrem)

SGS Unit 1 3.08E-03 1.26E-02 2.13E-02 9.67E-02 SGS Unit 2 8.78E-04 8.80E-04 2.52E-02 1.22E-01 HCGS 3.83E-03 4.08E-03 4.29E-02 1.95E-01 Site Total 7.79E-03 1.76E-02 8.93E-02 4.14E-01 As set forth in 10CFR50 Appendix I, ALARA requirements for gaseous effluent were met if a licensee demonstrates that the estimated annual external dose from gaseous effluents to any individual in unrestricted areas does not exceed 5 mrem to the total body or 15 mrem to the skin. Compliance with these limits was demonstrated for 2019 gaseous effluents by the calculated total body and skin doses from external exposure pathways (i.e., plume and ground deposition) at the controlling site boundary location in the north sector. The calculated total body dose and skin dose from the combined gaseous releases for the site represent less than 0.46% (Total Body) and less than 0.32% (Organ) of the respective dose limits (Table 5 Site Boundary Location). This confirms that no single units radioactive gaseous effluent releases exceeded the Appendix I dose limits. These doses (presented below) were calculated using the GASPAR computer program, which was consistent with the methods described in Regulatory Guide 1.109.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Dose Parameter from Table 5 Site Boundary Annual Dose (mrem)

Total Body Dose from Noble Gases, Iodines, Particulates, H-3 and C-14: 2.28E-02 Percent of Appendix I Annual Limit (5 mrem): 0.46%

Organ Dose from Noble Gases, Iodines, Particulates, H-3 and C-14: 4.75E-02 Percent of Appendix I Annual Limit (15 mrem): 0.32%

2. Total Dose to a Member of the Public, Resulting from Radioactive Effluent Releases and Radiation from Uranium Fuel Cycle Sources 40 CFR 190 and 10 CFR 72.104 limit the total dose to a Real Individual to 25 mrem to the total body, 75 mrem to the thyroid and 25 mrem to other organs other than the thyroid. The maximum annual total body and organ doses from gaseous and liquid pathways with all other uranium fuel cycle sources present on site were calculated as required by section 3.11.4 of the SGS and HCGS ODCMs. The direct dose from the ISFSI pad was determined using the Radiological Environmental Monitoring Program (REMP) and the guidance provided in ANSI/HPS N13.37-2014 (see page 9).

The direct shine dose from the ISFSI to the Critical Receptor located at 4.6 miles in the SW sector was conservatively estimated at 4.54E-03 mrem. The doses from the gaseous and liquid radioactive effluents released from SGS Units 1 and Unit 2 and HCGS in 2019 resulted in a calculated total body and an organ dose of 1.06E-01 mrem and 4.58E-01 mrem, respectively. The majority of dose was from the gaseous dose pathways from C-14. The total dose was calculated as 5.68E-01mrem, which was below the limits of 40 CFR 190 and 10 CFR 72.104. The results of this analysis are in Table 6.

Table 6 2019 Total Body and Organ Doses due to Liquid and Gaseous Effluents and Direct Shine ISFSI Dose to the Critical Receptor Located at 4.6 miles SW Total Body Dose Critical Organ Dose ISFSI Generating Station (mrem) (mrem) (mrem)

Liquid Gaseous Liquid Gaseous SGS Unit 1 1.35E-02 2.13E-02 1.67E-02 9.67E-02 SGS Unit 2 3.99E-03 2.52E-02 2.60E-02 1.22E-01 HCGS 7.92E-04 4.11E-02 2.41E-03 1.94E-01 Total 1.83E-02 8.76E-02 4.51E-02 4.13E-01 Total of Liquid and 1.06E-01 4.58E-01 5.02E-03 Gaseous (mrem)

Total Dose 5.69E-01 (mrem)

Includes C-14 dose.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T

3. Dose to Members of the Public Due to Activities inside the Site Boundary In accordance with 10 CFR 20.1301 Members of the Public may receive up to a limit of 100 mrem Total Effective Dose Equivalent (TEDE) in a year. The TEDE dose is the combined organ Committed Dose Equivalent (CDE) and the Total Body Dose. The Total Body Dose includes the direct shine dose from the ISFSI. There were no liquid or airborne releases from the ISFSI. The dose from radioactive liquid and gaseous effluents to a Member of the Public performing activities inside the site boundary are to be calculated as required by ODCM 6.9.1.8 (SGS) and 6.9.1.7 (HCGS).

Two sets of TEDE doses were calculated to two different members of the public. The first TEDE dose calculation assumes that an adult emergency worker (i.e. National Guard, Police, etc.) was located at the site vehicle Security Checkpoint entrance. The second calculation was to an adult contract worker stationed at the Sewage Treatment Plant (STP). Both sets of members of the public have assigned duties that do not involve exposure to radiation or to radioactive material.

Neither group have Radiation Control Access. In addition, exposure time was limited to 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months in a year (0.25 occupancy).

The vehicle Security Checkpoint was located at 0.89 miles E from the gaseous release points for SGS Units 1 and 2, 0.94 miles E from the HCGS and 1.18 miles from the ISFSI. The STP workers were located about 575 feet SW from the ISFSI pad.

The active exposure pathways at both locations were plume immersion, ground deposition and inhalation of airborne radioactivity in gaseous effluent. There was no liquid dose pathway to Members of the Public on site.

The 2019 atmospheric dispersion factors were imputed into the GASPAR computer program to calculate the gaseous effluent doses. For purposes of these calculations the gaseous doses for the STP worker used the highest site boundary sector doses located in the SW sector.

The calculated TEDE dose from gaseous effluents from the three reactors for each location was calculated by summing the total body and highest organ doses from SGS U1, SGS U2 and HCGS. The ISFSI dose was then added to each and then compared to the 10 CFR 20.1301 limit of 100 mrem. The results of this analysis are in Table 7.

Table 7 Summary of TEDE doses to Members of the Public Due to Activities Inside the Site Boundary CDE Total Body % of Limit TEDE Location Operating Unit (Thyroid) Dose (100 mrem) per mrem mrem mrem 10 CFR 20.1301 SGS U1 1.67E-03 1.67E-03 SGS U2 8.96E-04 8.96E-04 Security HCGS 2.51E-03 2.50E-03 Checkpoint ISFSI N/A 1.88E-02 Total 5.08E-03 2.39E-02 2.90E-02 0.03%

SGS U1 5.76E-03 5.75E-03 SGS U2 3.08E-03 3.08E-03 STP HCGS 1.07E-01 1.06E-01 ISFSI N/A 2.24E+00 Total 1.15E-01 2.35E+00 2.47E+00 2.47%

N/A Not Applicable The calculated doses were well below the 100 mrem limit of 10 CFR 20.1301.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX A-1 Effluent and Waste Disposal Summary, SGS Unit 1 PSEG 2019 ARERR Page 29 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T List of Tables Table 1A-1 Gaseous Effluents - Summation of All Releases ............................................... 32 Table 1C-1 Gaseous Effluents - Ground Level Releases .................................................... 33 Table 2A-1 Liquid Effluents - Summation of All Releases ................................................... 34 Table 2B-1 Liquid Effluents ................................................................................................... 35 Table 3A-2 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal (Note SGS Unit 1 and Unit 2 data is found in APPENDIX A-2) .............................................................................................. 45 Table 4A-1 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode ................................................................................................................... 36 Table 4B-1 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode ................................................................................................................... 36 PSEG 2019 ARERR Page 31 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1A-1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: SGS Unit 1 Period: 2019 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

Total Release Ci 9.43E-02 1.10E-01 4.56E-02 5.92E-02 3.09E-01 3.400E+01 Average release rate for the period Ci/sec 1.21E-02 1.40E-02 5.74E-03 7.44E-03 9.81E-03 Gamma Air %

Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %

B. Iodine and Halogens Total Ci 1.12E-04 7.24E-06 < LLD < LLD 1.20E-04 3.00E+01 Average release rate for the period Ci/sec 1.45E-05 9.20E-07 N/A N/A 3.79E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

C. Particulates Particulates with half-lives > 8 days Ci 3.75E-05 2.23E-05 < LLD < LLD 5.97E-05 3.00E+01 Average release rate for the period Ci/sec 4.82E-06 2.83E-06 N/A N/A 1.89E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 4.87E+01 8.67E+01 5.86E+01 4.32E+01 2.37E+02 3.10E+01 Average release rate for the period Ci/sec 6.27E+00 1.10E+01 7.37E+00 5.43E+00 7.52E+00 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

E. C-14 a

Total Release Ci 2.22E+00 2.15E+00 2.33E+00 2.37E+00 9.07E+00 N/A Average release rate for the period Ci/sec 2.85E-01 2.74E-01 2.93E-01 2.98E-01 2.88E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

F. I-131, I-133, H-3 & Particulates

> 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18 G. I-131, I-133, H-3, Particulates >

8 day half-life & C-14 Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18 N/A Not Applicable

Iodine, Tritium, C-14, and Particulates were treated as a group. Although listed separately in the above table, the percent ODCM Limit is based on most limiting nuclide and organ dose for the group (even in cases when a sub-group member was not identified in effluents).

a.

It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty. (Regulatory Guide 1.21 revision 2)

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1C-1 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Facility: SGS Unit 1 Period: 2019 Nuclides Released Continuous Mode Batch Mode 1.Fission gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Ar-41 Ci < LLD < LLD < LLD < LLD < LLD 5.62E-02 9.81E-03 3.61E-02 4.52E-02 1.47E-01 Kr-85m Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.36E-04 < LLD < LLD 2.36E-04 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.37E-03 < LLD < LLD 1.37E-03 Xe-133 Ci < LLD < LLD < LLD < LLD < LLD 3.80E-02 8.49E-02 9.55E-03 1.40E-02 1.46E-01 Xe-135 Ci < LLD < LLD < LLD < LLD < LLD 1.08E-04 1.38E-02 < LLD < LLD 1.39E-02 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 9.43E-02 1.10E-01 4.56E-02 5.92E-02 3.09E-01

2. Iodines and Halogens Br-82 Ci < LLD 7.24E-06 < LLD < LLD 7.24E-06 < LLD < LLD < LLD < LLD < LLD I-131 Ci 1.15E-06 < LLD < LLD < LLD 1.15E-06 < LLD < LLD < LLD < LLD < LLD I-133 Ci 1.11E-04 < LLD < LLD < LLD 1.12E-04 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 1.12E-04 7.24E-06 < LLD < LLD 1.20E-04 < LLD < LLD < LLD < LLD < LLD

3. Particulates LLD Co-58 Ci < LLD 2.22E-05 < LLD < LLD 2.22E-05 < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD 3.09E-08 < LLD < LLD 3.09E-08 < LLD < LLD < LLD < LLD < LLD As-76 Ci 3.75E-05 < LLD < LLD < LLD 3.75E-05 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 3.75E-05 2.23E-05 < LLD < LLD 5.97E-05 < LLD < LLD < LLD < LLD < LLD

4. Tritium Ci 4.84E+01 8.65E+01 5.70E+01 4.16E+01 2.34E+02 3.25E-01 1.29E-01 1.55E+00 1.54E+00 3.54E+00

5. C-14 Ci 2.22E+00 2.15E+00 2.33E+00 2.37E+00 9.07E+00 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2A-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Facility: SGS Unit 1 Period: 2019 Est. Total A. Fission & Activation Products Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

1. Total Release (not including tritium, gases &

Ci 2.18E-03 4.55E-03 1.39E-03 1.31E-04 8.25E-03 2.70E+01 alpha)

2. Average diluted concentration during period Ci/ml 3.74E-11 8.03E-11 2.86E-11 2.57E-12 3.84E-11

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

B. Tritium

1. Total List Ci 4.01E+02 4.21E+02 5.76E+01 1.13E+02 9.92E+02 2.70E+01

2. Average diluted concentration during period Ci/ml 6.87E-06 7.43E-06 1.19E-06 2.20E-06 4.62E-06

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

C. Dissolved & Entrained Gases

1. Total Release Ci < LLD < LLD < LLD < LLD < LLD 2.70E+01

2. Average diluted concentration during period Ci/ml N/A N/A N/A N/A N/A

3. Percent of applicable limit

% N/A N/A N/A N/A N/A (ODCM 3.11.1.1)

D. Gross Alpha Activity Total Release Ci < LLD < LLD < LLD < LLD < LLD 2.70E+01 E. Volume Of Waste Released (prior Liters 4.07E+07 3.12E+07 2.88E+07 4.31E+07 1.44E+08 to dilution)

F. Volume Of Dilution Water Used During Liters 5.83E+10 5.66E+10 4.85E+10 5.11E+10 2.14E+11 Period N/A Not Applicable PSEG 2019 ARERR Page 34 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2B-1 LIQUID EFFLUENTS Facility: SGS Unit 1 Period: 2019 Nuclides Unit Continuous Mode Batch Mode Released Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total H-3 Ci 3.09E-02 1.89E-02 3.57E-02 9.72E-02 1.83E-01 4.01E+02 4.21E+02 5.76E+01 1.12E+02 9.92E+02 Fission & Activation Products Co-58 Ci < LLD < LLD < LLD < LLD < LLD 9.05E-04 3.62E-03 7.96E-04 1.91E-05 5.34E-03 Co-60 Ci < LLD < LLD < LLD < LLD < LLD 7.65E-04 8.94E-04 5.92E-04 1.11E-04 2.36E-03 Nb-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.32E-05 1.32E-05 < LLD 1.32E-05 Nb-97 Ci < LLD < LLD < LLD < LLD < LLD 5.11E-06 < LLD < LLD < LLD 5.11E-06 Ag-110m Ci < LLD < LLD < LLD < LLD < LLD 5.20E-06 < LLD < LLD < LLD 5.20E-06 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD 2.29E-05 2.02E-05 < LLD < LLD 4.30E-05 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD 2.33E-05 < LLD < LLD < LLD 2.33E-05 Cs-137 Ci < LLD < LLD < LLD < LLD < LLD 4.43E-04 < LLD < LLD 9.93E-07 4.54E-04 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 2.18E-03 4.55E-03 1.39E-03 1.31E-04 8.25E-03 Dissolved and Entrained Noble Gases None Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 4A-1

SUMMARY

SHEET FOR LIQUID RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: SGS Unit 1 Period: 2019 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 24 38 10 12 84 Total time period for batch releases (min) 9.80E+03 1.99E+04 3.80E+03 5.03E+03 3.85E+04 Maximum time period for batch release (min) 6.92E+02 1.96E+03 5.37E+02 6.86E+02 1.96E+03 Average time period for batch release (min) 4.08E+02 5.23E+02 3.80E+02 4.19E+02 4.59E+02 Minimum time period for batch release (min) 2.27E+02 6.70E+01 2.51E+02 1.50E+01 1.50E+01 Average stream flow during periods of release of effluents into a flowing stream 5.95E+06 2.85E+06 1.28E+07 1.02E+07 5.56E+06 (Lpm)

TABLE 4B-1

SUMMARY

SHEET FOR GASEOUS RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: SGS Unit 1 Period: 2019 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 17 19 14 5 55 Total time period for batch releases (min) 1.25E+05 3.09E+04 1.19E+05 1.33E+05 4.08E+05 Maximum time period for batch release (min) 3.45E+04 2.58E+04 4.64E+04 4.46E+04 4.46E+04 Average time period for batch release (min) 7.33E+03 1.63E+03 8.51E+03 2.66E+04 7.42E+03 Minimum time period for batch release (min) 3.90E+01 4.80E+01 2.20E+01 1.04E+02 3.90E+01 PSEG 2019 ARERR Page 36 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX A-2 Effluent and Waste Disposal Summary, SGS Unit 2 PSEG 2019 ARERR Page 37 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T List of Tables Table 1A-2 Gaseous Effluents - Summation of All Releases ................................................ 41 Table 1C-2 Gaseous Effluents - Ground Level Releases ...................................................... 42 Table 2A-2 Liquid Effluents - Summation of All Releases ..................................................... 43 Table 2B-2 Liquid Effluents ..................................................................................................... 44 Table 3A-2 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal ................................................................................ 45 Table 4A-2 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode ..... 51 Table 4B-2 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode .................................................................................................................... 51 PSEG 2019 ARERR Page 39 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1A-2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: SGS Unit 2 Period: 2019 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

Total Release Ci 5.17E-02 4.42E-02 5.23E-02 7.55E-02 2.24E-01 3.400E+01 Average release rate for the period Ci/sec 6.65E-03 5.62E-03 6.59E-03 9.49E-03 7.09E-03 Gamma Air %

Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %

B. Iodine and Halogens Total Ci < LLD < LLD < LLD < LLD < LLD 3.00E+01 Average release rate for the period Ci/sec < LLD < LLD < LLD < LLD < LLD Percent of limit (ODCM 3.11.2.3(a)) % * * * *

C. Particulates Particulates with half-lives > 8 days Ci < LLD < LLD < LLD < LLD < LLD 3.00E+01 Average release rate for the period Ci/sec < LLD < LLD < LLD < LLD < LLD Percent of limit (ODCM 3.11.2.3(a)) % * * * *

Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 3.69E+00 3.84E+01 3.01E+01 3.72E+01 1.09E+02 3.10E+01 Average release rate for the period Ci/sec 4.75E-01 4.88E+00 3.79E+00 4.68E+00 3.47E+00 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

E. C-14 a

Total Release Ci 2.75E+00 2.73E+00 2.84E+00 3.05E+00 1.14E+01 N/A Average release rate for the period Ci/sec 3.53E-01 3.47E-01 3.58E-01 3.83E-01 3.60E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

F. I-131, I-133, H-3 & Particulates

> 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18 G. I-131, I-133, H-3, Particulates

> 8 day half-life & C-14 Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18

Iodine, Tritium, C-14, and Particulates were treated as a group. Although listed separately in the above table, the percent ODCM Limit is based on most limiting nuclide and organ dose for the group (even in cases when a sub-group member was not identified in effluent).

a.

It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty. (Regulatory Guide 1.21 revision 2)

PSEG 2019 ARERR Page 41 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1C-2 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Facility: SGS Unit 2 Period: 2019 Nuclides Released Continuous Mode Batch Mode

1. Fission gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Ar-41 Ci < LLD < LLD < LLD < LLD < LLD 4.69E-02 4.42E-02 3.85E-02 7.55E-02 2.05E-01 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.65E-04 < LLD 4.65E-04 Xe-133 Ci < LLD < LLD < LLD < LLD < LLD 4.86E-03 < LLD 1.29E-02 < LLD 1.78E-02 Xe-135 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.64E-04 < LLD 4.64E-04 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 5.17E-02 4.42E-02 5.23E-02 7.55E-02 2.24E-01

2. Iodines and Halogens None Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD

3. Particulates None Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 < LLD < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD 4.65E-06 4.65E-06 < LLD < LLD < LLD < LLD < LLD

4. Tritium Ci 3.65E+00 3.83E+01 3.01E+01 3.68E+01 1.09E+02 3.74E-02 1.75E-02 6.47E-02 3.98E-01 5.17E-01

5. C-14 Ci 2.75E+00 2.73E+00 2.84E+00 3.05E+00 1.14E+01 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2A-2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Facility: SGS Unit 2 Period: 2019 Est. Total A. Fission & Activation Products Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

1. Total Release (not including tritium, gases &

Ci 1.48E-03 8.08E-03 2.31E-03 1.26E-03 1.31E-02 2.70E+01 alpha)

2. Average diluted concentration during period Ci/ml 4.23E-10 1.34E-09 8.55E-11 3.73E-10 3.29E-10

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

B. Tritium

1. Total Release Ci 1.29E+02 8.67E+01 6.75E+01 1.63E+02 4.46E+02 2.70E+01

2. Average diluted concentration during period Ci/ml 3.69E-05 1.44E-05 2.50E-06 4.83E-05 1.12E-05

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

C. Dissolved & Entrained Gases

1. Total Release Ci < LLD < LLD < LLD < LLD < LLD 2.70E+01

2. Average diluted concentration during period Ci/ml < LLD < LLD < LLD < LLD < LLD

3. Percent of applicable limit

% N/A N/A N/A N/A N/A (ODCM 3.11.1.1)

D. Gross Alpha Activity Total Release Ci < LLD < LLD < LLD < LLD < LLD 2.70E+01 E. Volume Of Waste Released (prior Liters 1.32E+07 1.43E+07 1.61E+07 2.37E+07 6.73E+07 to dilution)

F. Volume Of Dilution Water Used During Liters 3.48E+09 6.01E+09 2.70E+10 3.35E+09 3.98E+10 Period N/A Not Applicable PSEG 2019 ARERR Page 43 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2B-2 LIQUID EFFLUENTS Facility: SGS Unit 2 Period: 2019 Unit Continuous Mode Batch Mode Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total H-3 Ci 7.93E-03 < LLD 2.14E-03 < LLD 1.01E-02 1.29E+02 8.67E+01 6.75E+01 1.63E+02 4.46E+02 Fission and Activation Products Cr-51 Ci < LLD < LLD < LLD < LLD < LLD 3.27E-05 1.26E-04 < LLD < LLD 1.59E-04 Mn-54 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.72E-05 < LLD < LLD 2.72E-05 Co-57 Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.74E-05 < LLD < LLD 1.74E-05 Co-58 Ci < LLD < LLD < LLD < LLD < LLD 6.76E-04 5.77E-03 9.97E-04 6.91E-05 7.51E-03 Co-60 Ci < LLD < LLD < LLD < LLD < LLD 6.94E-04 1.74E-03 1.31E-03 1.19E-03 4.93E-03 Zr-95 Ci < LLD < LLD < LLD < LLD < LLD 2.46E-05 1.03E-04 < LLD < LLD 1.28E-04 Nb-95 Ci < LLD < LLD < LLD < LLD < LLD 4.96E-05 2.17E-04 < LLD < LLD 2.67E-04 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD < LLD 8.11E-05 < LLD < LLD 8.11E-05 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 1.48E-03 8.08E-03 2.31E-03 1.26E-03 1.31E-02 Dissolved and Entrained Noble Gases None Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.

PSEG 2019 ARERR Page 44 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Facility: SGS Units 1 and 2 Period: 2019

b. Waste Stream; Resins, Filters, and Evaporator Bottoms Liquid Waste Processing Resin Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 5.50E+02 1.56E+01 8.49E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 5.50E+02 1.56E+01 8.49E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Percent Abundance Curies Fe-55 4.34% 3.68E-01 Co-58 47.53% 4.03E+00 Co-60 11.14% 9.45E-01 Ni-63 30.89% 2.62E+00 Sb-125 2.39% 2.03E-01 Cs-137 1.52% 1.29E-01 Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies None Resins, Filters and Evaporator Bottoms Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Resins, Filters and Evaporator Bottoms Waste Class All Nuclide Name Percent Abundance Curies Fe-55 4.34% 3.68E-01 Co-58 47.53% 4.03E+00 Co-60 11.14% 9.45E-01 Ni-63 30.89% 2.62E+00 Sb-125 2.39% 2.03E-01 Cs-137 1.52% 1.29E-01 N/A Not Applicable PSEG 2019 ARERR Page 45 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

c. Waste Stream; Dry Active Waste Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 1.94E+04 5.49E+02 1.74E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 1.94E+04 5.49E+02 1.74E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 1% 1.75E-02 Cr-51 2.64% 4.61E-02 Mn-54 1.68% 2.94E-02 Fe-55 10.71% 1.87E-01 Co-58 23.46% 4.09E-01 Co-60 31.63% 5.52E-01 Ni-63 16.64% 2.90E-01 Zr-95 4.95% 8.63E-02 Nb-95 2.52% 4.40E-02 Sb-125 2.1% 3.66E-02 Cs-137 1.15% 2.01E-02 Dry Active Waste Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Dry Active Waste Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 1% 1.75E-02 Cr-51 2.64% 4.61E-02 Mn-54 1.68% 2.94E-02 Fe-55 10.71% 1.87E-01 Co-58 23.46% 4.09E-01 Co-60 31.63% 5.52E-01 Ni-63 16.64% 2.90E-01 Zr-95 4.95% 8.63E-02 Nb-95 2.52% 4.40E-02 Sb-125 2.1% 3.66E-02 Cs-137 1.15% 2.01E-02 N/A Not Applicable PSEG 2019 ARERR Page 46 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

d. Waste Stream; Irradiated Components Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Irradiated Components Waste Class A Nuclide Name Percent Abundance Curies None N/A N/A Irradiated Components Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Irradiated Components Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Irradiated Components Waste Class All Nuclide Name Percent Abundance Curies None N/A N/A N/A Not Applicable PSEG 2019 ARERR Page 47 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

e. Waste Stream; Other Waste Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Other Waste Waste Class A Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class All Nuclide Name Percent Abundance Curies None N/A N/A N/A Not Applicable PSEG 2019 ARERR Page 48 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

f. Waste Stream; Sum of All 4 Categories Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 1.99E+04 5.64E+02 1.02E+01 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 1.99E+04 5.64E+02 1.02E+01 +/-25%

Major Nuclides for Above Table: Percent Cutoff 1%

Waste Stream; Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies Fe-55 5.43% 5.55E-01 Co-58 43.43% 4.44E+00 Co-60 14.64% 1.50E+00 Ni-63 28.46% 2.91E+00 Sb-125 2.34% 2.40E-01 Cs-137 1.46% 1.49E-0 Waste Stream; Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies None Waste Stream; Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Waste Stream; Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies Fe-55 5.43% 5.55E-01 Co-58 43.43% 4.44E+00 Co-60 14.64% 1.50E+00 Ni-63 28.46% 2.91E+00 Sb-125 2.34% 2.40E-01 Cs-137 1.46% 1.49E-0 N/A Not Applicable PSEG 2019 ARERR Page 49 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

Number of Mode Of Transportation Destination Shipments 1 Hittman Transport Services, Inc. Barnwell Disposal Facility Operated by Chem-Nuclear Systems, Inc.

4 Hittman Transport Services, Inc. Barnwell Processing Facility Energy Solutions, LLC 4 Hittman Transport Services, Inc. Energy Solutions Services Inc.

1560 Bear Creek Road 4 Interstate Ventures UniTech Processing Facility.

2323 Zirconium Road PSEG 2019 ARERR Page 50 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 4A-2

SUMMARY

SHEET FOR LIQUID RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: SGS Unit 2 Period: 2019 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 15 16 10 11 52 Total time period for batch releases (min) 4.61E+03 8.10E+03 4.72E+03 4.51E+03 2.19E+04 Maximum time period for batch release (min) 5.48E+02 7.73E+02 6.66E+02 5.43E+02 7.73E+02 Average time period for batch release (min) 3.07E+02 5.06E+02 4.72E+02 4.10E+02 4.22E+02 Minimum time period for batch release (min) 1.00E+00 3.24E+02 3.37E+02 1.62E+02 1.00E+00 Average stream flow during periods of release 7.57E+05 7.44E+05 5.72E+06 7.49E+05 1.82E+06 of effluents into a flowing stream (Lpm)

TABLE 4B-2

SUMMARY

SHEET FOR GASEOUS RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: SGS Unit 2 Period: 2019 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 14 7 8 3 32 Total time period for batch releases (min) 1.23E+05 1.03E+05 1.23E+05 1.33E+05 4.82E+05 Maximum time period for batch release (min) 3.85E+04 3.33E+04 4.46E+04 4.46E+04 4.46E+04 Average time period for batch release (min) 8.79E+03 1.47E+04 1.54E+04 4.42E+04 1.51E+04 Minimum time period for batch release (min) 1.90E+01 3.50E+01 5.80E+01 4.32E+04 1.90E+01 PSEG 2019 ARERR Page 51 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX A-3 Effluent and Waste Disposal Summary, HCGS PSEG 2019 ARERR Page 53 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T List of Tables Table 1A-3 Gaseous Effluents - Summation of All Releases ................................................ 57 Table 1C-3 Gaseous Effluents - Ground Level Releases ...................................................... 58 Table 2A-3 Liquid Effluents - Summation of All Releases ..................................................... 59 Table 2B-3 Liquid Effluents ..................................................................................................... 60 Table 3A-3 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal ................................................................................ 59 Table 4A-3 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode .................................................................................................................... 67 Table 4B-3 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode .................................................................................................................... 67 PSEG 2019 ARERR Page 55 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1A-3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: HCGS Period: 2019 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

Total Release Ci 2.50E+00 2.51E-02 2.45E+01 4.56E+00 3.16E+01 3.40E+01 Average release rate for the period Ci/sec 3.21E-01 3.19E-03 3.09E+00 5.74E-01 1.00E+00 Gamma Air %

Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %

B. Iodines and Halogens Total Release Ci 3.80E-04 4.08E-06 6.62E-05 1.21E-04 5.72E-04 3.00E+01 Average release rate for the period Ci/sec 4.89E-05 5.18E-07 8.33E-06 1.53E-05 1.81E-05 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

C. Particulates Particulates with half-lives > 8 days Ci 4.26E-06 < LLD 6.39E-06 4.31E-05 5.38E-05 3.00E+01 Average release rate for the period Ci/sec 5.48E-07 < LLD 8.04E-07 5.43E-06 1.71E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 1.12E+02 1.15E+02 1.16E+02 4.09E+01 3.84E+02 3.10E+01 Average release rate for the period Ci/sec 1.71E-06 1.71E-06 1.71E-06 1.71E-06 1.71E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

E. C-14 Total Release Ci 3.38E+00 3.69E+00 3.71E+00 4.18E+00 1.50E+01 N/A Average release rate for the period Ci/sec 4.35E-01 4.69E-01 4.67E-01 5.26E-01 4.74E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *

F. I-131, I-133, H-3 & Particulates

> 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18 G. I-131, I-133, H-3, Particulates

> 8 day half-life & C-14 Percent of limit (ODCM 3.11.2.3(a)) % See Table 2 on page 18

Iodine, Tritium, C-14, and Particulates were treated as a group. Although listed separately in the above table, the percent ODCM Limit is based on most limiting nuclide and organ dose for the group (even in cases when a sub-group member was not identified in effluent).

a.

It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty. (Regulatory Guide 1.21 revision 2)

PSEG 2019 ARERR Page 57 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 1C-3 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Facility: HCGS Period: 2019 Nuclides Unit Continuous Mode Batch Mode Released

1. Fission gases Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Ar-41 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.87E-03 1.87E-03 Kr-85m Ci 7.49E-02 < LLD < LLD < LLD 7.49E-02 < LLD < LLD < LLD 3.41E-05 3.41E-05 Kr-87 Ci 4.99E-02 < LLD < LLD < LLD 4.99E-02 < LLD < LLD < LLD 6.43E-04 6.43E-04 Kr-88 Ci 9.98E-02 < LLD < LLD < LLD 9.98E-02 < LLD < LLD < LLD 4.29E-04 4.29E-04 Xe-133 Ci 1.52E+00 < LLD < LLD < LLD 1.52E+00 1.57E-03 2.50E-02 < LLD 9.72E-04 2.75E-02 Xe-135m Ci 4.99E-02 < LLD < LLD < LLD 4.99E-02 < LLD < LLD < LLD < LLD < LLD Xe-135 Ci 6.99E-01 < LLD 7.58E+00 1.16E+00 9.44E+00 9.17E-05 7.31E-05 < LLD 4.16E-04 5.81E-04 Xe-138 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 2.85E-03 2.85E-03 Total for Period Ci 2.50E+00 < LLD 2.45E+01 4.56E+00 3.16E+01 1.66E-03 2.51E-02 < LLD 7.22E-03 3.39E-02

2. Iodines and Halogens I-131 Ci 1.12E-04 4.08E-06 1.55E-05 8.17E-05 2.13E-04 < LLD < LLD < LLD < LLD < LLD I-133 Ci 2.69E-04 < LLD 5.07E-05 3.96E-05 3.59E-04 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 3.80E-04 4.08E-06 6.62E-05 1.21E-04 5.72E-04 < LLD < LLD < LLD < LLD < LLD

3. Particulates Co-60 Ci 4.26E-06 < LLD 6.39E-06 4.31E-05 5.38E-05 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 4.26E-06 < LLD 6.39E-06 4.31E-05 5.38E-05 < LLD < LLD < LLD < LLD < LLD

4. Tritium Ci 1.12E+02 1.15E+02 1.16E+02 4.09E+01 3.84E+02 1.70E-03 < LLD < LLD 2.02E-03 3.72E-03

5. C-14 Ci 3.38E+00 3.69E+00 3.71E+00 4.18E+00 1.50E+01 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.

PSEG 2019 ARERR Page 58 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2A-3 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Facility: HCGS Period: 2019 Est. Total A. Fission & Activation Products Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %

1. Total Release Ci 1.28E-05 9.33E-04 1.75E-04 1.55E-02 1.66E-02 2.70E+01 (not including tritium, gases & alpha)

2. Average diluted concentration Ci/ml 2.10E-12 1.66E-10 2.77E-11 2.37E-09 6.76E-10 during period

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

B. Tritium

1. Total Release Ci 1.15E+01 1.05E+01 2.72E+00 9.23E+01 1.17E+02 2.70E+01

2. Average diluted concentration Ci/ml 1.89E-06 1.87E-06 4.32E-07 1.41E-05 4.77E-06 during period

3. Percent of applicable limit Total Body %

See Table 3 on page 20 (ODCM 3.11.1(a) & (b)) Organ %

C. Dissolved & Entrained Gases

1. Total Release Ci 1.44E-03 2.63E-04 5.62E-05 2.78E-04 2.03E-03 2.70E+01

2. Average diluted concentration Ci/ml 2.36E-10 4.69E-11 8.92E-12 4.25E-11 8.29E-11 during period

3. Percent of applicable limit

% See Table 3 on page 20 (ODCM 3.11.1.1)

D. Gross Alpha Activity Total Release Ci < LLD < LLD < LLD < LLD < LLD 2.70E+01 E. Volume Of Waste Released Liters 1.60E+07 2.12E+06 2.01E+07 1.41E+07 5.23E+07 (prior to dilution)

F. Volume Of Dilution Water Used Liters 6.08E+09 5.62E+09 6.28E+09 6.52E+09 2.45E+10 During Period PSEG 2019 ARERR Page 59 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 2B-3 LIQUID EFFLUENTS Facility: HCGS Period: 2019 Continuous Mode Batch Mode Nuclides Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Released H-3 Ci 3.09E-02 1.89E-02 3.57E-02 9.72E-02 1.83E-01 4.01E+02 4.21E+02 5.76E+01 1.12E+02 9.91E+02 Fission and Activation Products Cr-51 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.58E-05 4.58E-05 Mn-54 Ci < LLD < LLD < LLD < LLD < LLD 8.02E-08 3.49E-05 1.30E-05 2.49E-03 2.54E-03 Co-58 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 9.53E-06 1.91E-03 1.92E-03 Co-60 Ci < LLD < LLD < LLD < LLD < LLD 1.27E-05 8.74E-04 1.34E-04 4.81E-03 5.84E-03 Zn-65 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.79E-05 1.50E-04 1.68E-04 Sb-122 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.39E-04 1.39E-04 Sb-124 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 3.27E-03 3.27E-03 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 6.48E-04 6.48E-04 I-131 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 3.40E-04 3.40E-04 I-133 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.42E-07 1.42E-07 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 8.66E-04 8.66E-04 Cs-136 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 2.18E-05 2.18E-05 Cs-137 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.45E-05 < LLD 7.97E-04 8.21E-04 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 1.28E-05 9.33E-04 1.75E-04 1.55E-02 1.66E-02 Dissolved and Entrained Noble Gases Xe-133 Ci < LLD < LLD < LLD < LLD < LLD 1.41E-03 2.63E-04 4.38E-05 2.76E-04 1.99E-03 Xe-135 < LLD < LLD < LLD < LLD < LLD 2.70E-05 0.00E+00 1.24E-05 1.61E-06 4.10E-05 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 1.44E-03 2.63E-04 5.62E-05 2.78E-04 2.03E-03 Note: Only radionuclides with positive activity reported in this table.

PSEG 2019 ARERR Page 60 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Facility: HCGS Period: 2019

a. Waste Stream; Resins, Filters, and Evaporator Bottoms Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 2.85E+03 8.06E+01 5.93E+01 +/-25%

B 9.30E+01 2.63E+00 7.13E+01 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 2.94E+03 8.33E+01 1.31E+02 +/-25%

Major Nuclides for Above Table: Percent Cutoff: 1%

Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Percent Abundance Curies C-14 6.26% 3.71E+00 Mn-54 8.3% 4.92E+00 Fe-55 19.92% 1.18E+01 Co-60 55.06% 3.26E+01 Ni-63 6.01% 3.56E+00 Zn-65 1.56% 9.24E-01 Cs-137 1.39% 8.24E-01 Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies Fe-55 59.69% 4.25E+01 Co-60 29.6% 2.11E+01 Ni-63 9.47% 6.75E+00 Cs-137 1% 7.13E-01 Resins, Filters and Evaporator Bottoms Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Resins, Filters and Evaporator Bottoms Waste Class All Nuclide Name Percent Abundance Curies C-14 2.84% 3.71E+00 Mn-54 3.77% 4.92E+00 Fe-55 41.64% 5.44E+01 Co-60 41.16% 5.37E+01 Ni-63 7.9% 1.03E+01 Cs-137 1.18% 1.54E+00 N/A Not Applicable PSEG 2019 ARERR Page 61 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

b. Waste Stream; Dry Active Waste Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff: 1%

Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies None N/A N/A Dry Active Waste Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Dry Active Waste Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies None N/A N/A N/A Not Applicable PSEG 2019 ARERR Page 62 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

c. Waste Stream; Irradiated Components Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 1.58E+01 4.48E+01 2.68E+04 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All +/-25%

Major Nuclides for Above Table: Percent Cutoff: 1%

Irradiated Components Waste Class A Nuclide Name Percent Abundance Curies None N/A N/A Irradiated Components Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Irradiated Components Waste Class C Nuclide Name Percent Abundance Curies Mn-54 2.24% 6.02E+02 Fe-55 54.12% 1.45E+04 Co-60 36.88% 9.90E+03 Ni-63 6.39% 1.72E+03 Irradiated Components Waste Class All Nuclide Name Percent Abundance Curies Mn-54 2.24% 6.02E+02 Fe-55 54.12% 1.45E+04 Co-60 36.88% 9.90E+03 Ni-63 6.39% 1.72E+03 N/A Not Applicable PSEG 2019 ARERR Page 63 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

d. Waste Stream; Other Waste Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Major Nuclides for Above Table: Percent Cutoff: 1%

Other Waste Waste Class A Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Other Waste Waste Class All Nuclide Name Percent Abundance Curies None N/A N/A N/A Not Applicable PSEG 2019 ARERR Page 64 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

e. Waste Stream; Sum of All 4 Categories Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)

A 2.85E+03 8.06E+01 5.93E+0 +/-25%

B 9.30E+01 2.63E+00 7.13E+01 +/-25%

C 1.58E+01 4.48E-01 2.68E+04 +/-25%

Unclassified 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 2.96E+03 8.37E+01 2.70E+04 +/-25%

Major Nuclides for Above Table: Percent Cutoff: 1%

Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies C-14 6.26% 3.71E+00 Mn-54 8.3% 4.92E+00 Fe-55 19.92% 1.18E+01 Co-60 55.06% 3.26E+01 Ni-63 6.01% 3.56E+00 Zn-65 1.56% 9.24E-01 Cs-137 1.39% 8.24E-01 Waste Class B Nuclide Name Percent Abundance Curies Fe-55 59.69% 4.25E+01 Co-60 29.6% 2.11E+01 Ni-63 9.47% 6.75E+00 Cs-137 1% 7.13E-01 Waste Class C Nuclide Name Percent Abundance Curies Mn-54 2.24% 6.02E+02 Fe-55 54.12% 1.45E+04 Co-60 36.88% 9.90E+03 Ni-63 6.39% 1.72E+03 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies Mn-54 2.25% 6.07E+02 Fe-55 54.06% 1.46E+04 Co-60 36.9% 9.95E+03 Ni-63 6.4% 1.73E+03 N/A Not Applicable PSEG 2019 ARERR Page 65 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 3A-3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (continued)

(Not Irradiated Fuel)

Number of Mode Of Transportation Destination Shipments Energy Solutions - BDF 8 Hittman Transport Services, Inc.

Barnwell Disposal Facility.

Energy Solutions, LLC 1 Hittman Transport Services Inc Barnwell Processing Facility Energy Solutions - BDF 8 Hittman Transport Services, Inc. Barnwell Disposal Facility Energy Solutions, LLC 5 Hittman Transport Services Inc Barnwell Processing Facility PSEG 2019 ARERR Page 66 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T TABLE 4A-3

SUMMARY

SHEET FOR LIQUID RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: HCGS Period: 2019 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 14 12 29 84 139 Total time period for batch releases (min) 1.07E+03 9.05E+02 2.20E+03 8.79E+03 1.30E+04 Maximum time period for batch release (min) 8.60E+01 8.60E+01 8.90E+01 1.03E+03 1.03E+03 Average time period for batch release (min) 7.62E+01 7.54E+01 7.59E+01 1.05E+02 9.32E+01 Minimum time period for batch release (min) 3.80E+01 4.00E+01 4.10E+01 3.80E+01 3.80E+01 Average stream flow during periods of release 5.71E+06 6.21E+06 2.86E+06 7.44E+05 1.89E+06 of effluents into a flowing stream (Lpm)

TABLE 4B-3

SUMMARY

SHEET FOR GASEOUS RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: HCGS Period: 2019 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 1 1 0 2 4 Total time period for batch releases (min) 1.20E+03 7.26E+02 0.00E+00 1.69E+03 3.62E+03 Maximum time period for batch release (min) 1.20E+03 7.26E+02 0.00E+00 1.25E+03 1.25E+03 Average time period for batch release (min) 1.20E+03 7.26E+02 0.00E+00 8.47E+02 9.05E+02 Minimum time period for batch release (min) 1.20E+03 7.26E+02 0.00E+00 4.41E+02 4.41E+02 PSEG 2019 ARERR Page 67 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX B Meteorological Data PSEG 2019 ARERR Page 69 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Salem/Hope Creek Meteorological Tower Joint Frequency Distribution of Wind Direction and Speed All Stability Classes Total Hours and Frequency (%)

33 Ft. Wind Level 150 - 33 Ft. Delta Temperature January - December 2019 PSEG 2019 ARERR Page 71 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY - DECEMBER 2019 WIND LEVEL: 33 FT DELTA T: (150-33 FT)

ALL STABILITY CLASSES TOTAL HOURS WIND SPEED GROUPS (m/sec)

WIND DIRECTION (blowing from) < 0.5 0.5 - 1.0 1.1 - 1.5 1.6 - 2.0 2.1 - 3.0 3.1 - 4.0 4.1 - 5.0 5.1 - 6.0 6.1 - 8.0 8.1 - 10.0 > 10.0 Total Degrees Sect.

348.75 - 11.25 N 0 12 42 53 177 142 77 26 15 2 0 546 11.25 - 33.75 NNE 1 13 42 48 192 117 67 58 36 0 0 574 33.75 - 56.25 NE 0 14 42 85 199 113 38 30 4 0 0 525 56.25 - 78.75 ENE 0 24 65 89 115 60 28 19 2 0 1 403 78.75 - 101.25 E 0 19 75 68 109 35 13 3 1 0 0 323 101.25 - 123.75 ESE 0 11 26 46 140 57 17 8 5 1 0 311 123.75 - 146.25 SE 0 7 17 31 133 125 148 138 152 18 1 770 146.25 - 168.75 SSE 0 7 22 46 110 92 111 83 78 7 3 559 168.75 - 191.25 S 0 9 22 52 113 90 79 61 44 13 6 489 191.25 - 213.75 SSW 0 5 30 50 114 89 50 38 25 6 1 408 213.75 - 236.25 SW 0 9 22 47 186 138 58 29 10 1 1 501 236.25 - 258.75 WSW 0 7 21 45 179 142 57 13 13 0 1 478 258.75 - 281.25 W 1 9 25 50 124 115 69 34 57 31 11 526 281.25 - 303.75 WNW 0 9 32 48 125 81 60 51 106 34 9 555 303.75 - 326.25 NW 1 13 27 52 189 155 127 121 150 46 4 885 326.25 - 348.75 NNW 0 9 34 52 155 109 88 70 38 0 0 555 Total 8,408 MISSING HOURS: 352 JOINT DATA RECOVERY: 96.0%

SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY - DECEMBER 2019 WIND LEVEL: 33 FT DELTA T: (150-33 FT)

ALL STABILITY CLASSES FREQUENCY (%)

WIND SPEED GROUPS (m/sec)

WIND DIRECTION (blowing from) < 0.5 0.5 - 1.0 1.1 - 1.5 1.6 - 2.0 2.1 - 3.0 3.1 - 4.0 4.1 - 5.0 5.1 - 6.0 6.1 - 8.0 8.1 - 10.0 > 10.0 Total Degrees Sect.

348.75 - 11.25 N 0.000 0.143 0.500 0.630 2.105 1.689 0.916 0.309 0.178 0.024 0.000 6.49 11.25 - 33.75 NNE 0.012 0.155 0.500 0.571 2.284 1.392 0.797 0.690 0.428 0.000 0.000 6.83 33.75 - 56.25 NE 0.000 0.167 0.500 1.011 2.367 1.344 0.452 0.357 0.048 0.000 0.000 6.24 56.25 - 78.75 ENE 0.000 0.285 0.773 1.059 1.368 0.714 0.333 0.226 0.024 0.000 0.012 4.79 78.75 - 101.25 E 0.000 0.226 0.892 0.809 1.296 0.416 0.155 0.036 0.012 0.000 0.000 3.84 101.25 - 123.75 ESE 0.000 0.131 0.309 0.547 1.665 0.678 0.202 0.095 0.059 0.012 0.000 3.70 123.75 - 146.25 SE 0.000 0.083 0.202 0.369 1.582 1.487 1.760 1.641 1.808 0.214 0.012 9.16 146.25 - 168.75 SSE 0.000 0.083 0.262 0.547 1.308 1.094 1.320 0.987 0.928 0.083 0.036 6.65 168.75 - 191.25 S 0.000 0.107 0.262 0.618 1.344 1.070 0.940 0.725 0.523 0.155 0.071 5.82 191.25 - 213.75 SSW 0.000 0.059 0.357 0.595 1.356 1.059 0.595 0.452 0.297 0.071 0.012 4.85 213.75 - 236.25 SW 0.000 0.107 0.262 0.559 2.212 1.641 0.690 0.345 0.119 0.012 0.012 5.96 236.25 - 258.75 WSW 0.000 0.083 0.250 0.535 2.129 1.689 0.678 0.155 0.155 0.000 0.012 5.69 258.75 - 281.25 W 0.012 0.107 0.297 0.595 1.475 1.368 0.821 0.404 0.678 0.369 0.131 6.26 281.25 - 303.75 WNW 0.000 0.107 0.381 0.571 1.487 0.963 0.714 0.607 1.261 0.404 0.107 6.60 303.75 - 326.25 NW 0.012 0.155 0.321 0.618 2.248 1.843 1.510 1.439 1.784 0.547 0.048 10.53 326.25 - 348.75 NNW 0.000 0.107 0.404 0.618 1.843 1.296 1.047 0.833 0.452 0.000 0.000 6.60 Total 100.00 MISSING HOURS: 352 JOINT DATA RECOVERY: 96.0%

PSEG 2019 ARERR Page 72 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Salem and Hope Creek Ground Level Release Dispersion (X/Q) and Deposition Factors (D/Q)

January - December 2019 PSEG 2019 ARERR Page 73 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 2019 SALEM GROUND LEVEL RELEASE DISPERSION (X/Q) AND DEPOSITION FACTORS (D/Q)

SPECIFIC POINTS OF INTEREST 3 3 3 X/Q (Sec/M ) X/Q (Sec/M ) X/Q (Sec/M )

Direction From Distance No Decay No Decay No Decay D/Q 2

Location Site (MI) Undepleted Undepleted Depleted (1/M )

SITE BOUNDARY S 0.17 1.70E-05 1.70E-05 1.60E-05 6.90E-08 SITE BOUNDARY SSW 0.13 2.80E-05 2.80E-05 2.70E-05 1.10E-07 SITE BOUNDARY SW 0.11 3.20E-05 3.20E-05 3.10E-05 1.10E-07 SITE BOUNDARY WSW 0.11 3.10E-05 3.10E-05 3.10E-05 8.70E-08 SITE BOUNDARY W 0.12 2.50E-05 2.50E-05 2.40E-05 6.30E-08 SITE BOUNDARY WNW 0.16 1.30E-05 1.30E-05 1.20E-05 4.30E-08 SITE BOUNDARY NW 0.28 6.40E-06 6.40E-06 6.10E-06 4.40E-08 SITE BOUNDARY NNW 0.68 1.20E-06 1.20E-06 1.00E-06 8.00E-09 SITE BOUNDARY N 0.83 7.90E-07 7.90E-07 7.00E-07 4.90E-09 SITE BOUNDARY NNE 0.89 6.50E-07 6.50E-07 5.70E-07 3.60E-09 SITE BOUNDARY NE 1.07 6.80E-07 6.80E-07 5.90E-07 3.30E-09 SITE BOUNDARY ENE 0.88 7.80E-07 7.80E-07 6.90E-07 4.40E-09 SITE BOUNDARY E 0.89 7.50E-07 7.50E-07 6.60E-07 4.70E-09 SITE BOUNDARY ESE 0.24 5.50E-06 5.50E-06 5.20E-06 4.00E-08 SITE BOUNDARY SE 0.15 2.20E-05 2.20E-05 2.10E-05 1.30E-07 SITE BOUNDARY SSE 0.15 1.80E-05 1.80E-05 1.70E-05 8.20E-08 NEAREST RES S 5.22 9.00E-08 9.00E-08 6.70E-08 2.20E-10 NEAREST RES SSW 3.85 1.30E-07 1.30E-07 1.00E-07 4.00E-10 NEAREST RES SW 4.29 1.10E-07 1.10E-07 8.40E-08 3.00E-10 NEAREST RES WSW 4.41 1.00E-07 1.00E-07 7.90E-08 2.20E-10 NEAREST RES W 3.98 1.10E-07 1.10E-07 8.30E-08 2.10E-10 NEAREST RES WNW 3.42 1.10E-07 1.10E-07 8.20E-08 2.70E-10 NEAREST RES NW 3.67 1.40E-07 1.40E-07 1.10E-07 5.90E-10 NEAREST RES NNW 4.23 8.80E-08 8.80E-08 6.70E-08 3.30E-10 NEAREST RES N 5.65 5.50E-08 5.50E-08 4.00E-08 1.70E-10 NEAREST RES NNE 4.97 6.00E-08 6.00E-08 4.40E-08 1.80E-10 NEAREST RES NE 3.85 1.20E-07 1.20E-07 9.20E-08 3.50E-10 NEAREST RES ENE 3.85 1.00E-07 1.00E-07 7.80E-08 3.30E-10 NEAREST RES E 5.28 6.30E-08 6.30E-08 4.70E-08 2.10E-10 NEAREST RES ESE 5.84 5.00E-08 5.00E-08 3.60E-08 1.80E-10 NEAREST RES SE 9.44 4.30E-08 4.30E-08 2.90E-08 1.30E-10 NEAREST RES SSE 9.44 3.50E-08 3.50E-08 2.40E-08 8.20E-11 GARDENS NNW 0.57 1.50E-06 1.50E-06 1.40E-06 1.10E-08 GARDENS SE 0.18 1.60E-05 1.60E-05 1.50E-05 9.90E-08 GARDENS N 0.57 1.40E-06 1.40E-06 1.30E-06 9.20E-09 GARDENS NW 0.58 1.90E-06 1.90E-06 1.80E-06 1.40E-08 GARDENS SSW 3.9 1.30E-07 1.30E-07 1.00E-07 3.90E-10 GARDENS NE 4.9 8.60E-08 8.60E-08 6.40E-08 2.30E-10 GARDENS ENE 5 7.00E-08 7.00E-08 5.30E-08 2.10E-10 GARDENS NE 5 8.40E-08 8.40E-08 6.20E-08 2.20E-10 GARDENS E 6 5.30E-08 5.30E-08 3.80E-08 1.70E-10 GARDENS ENE 6 5.50E-08 5.50E-08 4.00E-08 1.50E-10 GARDENS ESE 6.3 4.50E-08 4.50E-08 3.20E-08 1.60E-10 GARDENS NW 7 6.00E-08 6.00E-08 4.30E-08 1.80E-10 GARDENS NNE 7.5 3.40E-08 3.40E-08 2.40E-08 8.70E-11 GARDENS NW 8.3 4.80E-08 4.80E-08 3.30E-08 1.40E-10 GARDENS NE 9.3 3.60E-08 3.60E-08 2.50E-08 7.60E-11 PSEG 2019 ARERR Page 75 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 3 3 3 X/Q (Sec/M ) X/Q (Sec/M ) X/Q (Sec/M )

Direction From Distance No Decay No Decay No Decay D/Q 2

Location Site (MI) Undepleted Undepleted Depleted (1/M )

GARDENS N 10.9 2.30E-08 2.30E-08 1.50E-08 5.70E-11 GARDENS NNE 13.2 1.60E-08 1.60E-08 1.00E-08 3.40E-11 GARDENS WNW 12.1 2.00E-08 2.00E-08 1.30E-08 3.00E-11 GARDENS NE 23.3 1.10E-08 1.10E-08 6.10E-09 1.60E-11 GARDENS SW 4.6 1.00E-07 1.00E-07 7.60E-08 2.70E-10 DAIRY & CATTL W 4.9 8.20E-08 8.20E-08 6.10E-08 1.50E-10 DAIRY & CATTL WNW 8.5 3.20E-08 3.20E-08 2.20E-08 5.40E-11 DAIRY & CATTL NE 11.3 2.80E-08 2.80E-08 1.90E-08 5.50E-11 DAIRY & CATTL N 11.7 2.10E-08 2.10E-08 1.30E-08 5.10E-11 DAIRY & CATTL NNE 11.8 1.80E-08 1.80E-08 1.20E-08 4.20E-11 DAIRY & CATTL NE 4.2 1.10E-07 1.10E-07 8.10E-08 3.00E-10 DAIRY & CATTL NE 5.8 6.90E-08 6.90E-08 5.00E-08 1.70E-10 DAIRY & CATTL SSW 8.3 4.80E-08 4.80E-08 3.30E-08 1.00E-10 DAIRY & CATTL N 11.5 2.10E-08 2.10E-08 1.40E-08 5.20E-11 DAIRY & CATTL NE 17.7 1.60E-08 1.60E-08 9.40E-09 2.50E-11 VENT AND BUILDING PARAMETERS:

Release Height Rep. Wind Height (Meters) 0.00 10.00 (Meters)

Building Height Diameters (Meters) 0.00 61.00 (Meters)

BLDG.MIN.CRS.

Exit Velocity (Meters) 0.00 SEC.AREA 3720.00 (Square Meters)

Heat Emission 0.00 Rate (Cal/Sec)

PSEG 2019 ARERR Page 76 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 2019 HOPE CREEK GROUND LEVEL RELEASE DISPERSION (X/Q) AND DEPOSITION FACTORS (D/Q)

SPECIFIC POINTS OF INTEREST 3 3 3 X/Q (Sec/M ) X/Q (Sec/M ) X/Q (Sec/M )

DIRECTION Distance D/Q LOCATION No Decay No Decay No Decay 2 FROM SITE (MI) (1/M )

Undepleted Undepleted Depleted SITE BOUNDARY S 0.25 8.00E-06 8.00E-06 7.60E-06 3.70E-08 SITE BOUNDARY SSW 0.19 1.30E-05 1.30E-05 1.30E-05 5.90E-08 SITE BOUNDARY SW 0.17 1.50E-05 1.50E-05 1.50E-05 6.40E-08 SITE BOUNDARY WSW 0.17 1.50E-05 1.50E-05 1.50E-05 4.90E-08 SITE BOUNDARY W 0.18 1.20E-05 1.20E-05 1.20E-05 3.60E-08 SITE BOUNDARY WNW 0.22 7.10E-06 7.10E-06 6.70E-06 2.70E-08 SITE BOUNDARY NW 0.31 5.60E-06 5.60E-06 5.20E-06 3.90E-08 SITE BOUNDARY NNW 0.55 1.60E-06 1.60E-06 1.40E-06 1.10E-08 SITE BOUNDARY N 0.5 1.70E-06 1.70E-06 1.60E-06 1.10E-08 SITE BOUNDARY NNE 0.63 1.10E-06 1.10E-06 9.60E-07 6.50E-09 SITE BOUNDARY NE 0.74 1.10E-06 1.10E-06 1.00E-06 6.10E-09 SITE BOUNDARY ENE 0.94 7.00E-07 7.00E-07 6.20E-07 3.90E-09 SITE BOUNDARY E 0.94 6.90E-07 6.90E-07 6.10E-07 4.30E-09 SITE BOUNDARY ESE 0.75 8.90E-07 8.90E-07 7.90E-07 6.70E-09 SITE BOUNDARY SE 0.47 2.90E-06 2.90E-06 2.60E-06 2.30E-08 SITE BOUNDARY SSE 0.42 2.80E-06 2.80E-06 2.60E-06 1.70E-08 NEAREST RES S 5.22 9.00E-08 9.00E-08 6.70E-08 2.20E-10 NEAREST RES SSW 3.85 1.30E-07 1.30E-07 1.00E-07 4.00E-10 NEAREST RES SW 4.29 1.10E-07 1.10E-07 8.40E-08 3.00E-10 NEAREST RES WSW 4.41 1.00E-07 1.00E-07 7.80E-08 2.20E-10 NEAREST RES W 3.98 1.10E-07 1.10E-07 8.30E-08 2.10E-10 NEAREST RES WNW 3.42 1.10E-07 1.10E-07 8.20E-08 2.70E-10 NEAREST RES NW 3.67 1.40E-07 1.40E-07 1.10E-07 5.90E-10 NEAREST RES NNW 4.23 8.80E-08 8.80E-08 6.70E-08 3.30E-10 NEAREST RES N 5.65 5.50E-08 5.50E-08 4.00E-08 1.70E-10 NEAREST RES NNE 4.97 5.90E-08 5.90E-08 4.40E-08 1.80E-10 NEAREST RES NE 3.85 1.20E-07 1.20E-07 9.20E-08 3.50E-10 NEAREST RES ENE 3.85 1.00E-07 1.00E-07 7.80E-08 3.30E-10 NEAREST RES E 5.28 6.30E-08 6.30E-08 4.70E-08 2.10E-10 NEAREST RES ESE 5.84 5.00E-08 5.00E-08 3.60E-08 1.80E-10 NEAREST RES SE 9.44 4.30E-08 4.30E-08 2.90E-08 1.30E-10 NEAREST RES SSE 9.44 3.50E-08 3.50E-08 2.40E-08 8.20E-11 GARDENS NNW 0.57 1.50E-06 1.50E-06 1.40E-06 1.10E-08 GARDENS SE 0.18 1.60E-05 1.60E-05 1.50E-05 9.90E-08 GARDENS N 0.57 1.40E-06 1.40E-06 1.30E-06 9.20E-09 GARDENS NW 0.58 1.90E-06 1.90E-06 1.70E-06 1.40E-08 GARDENS SSW 3.9 1.30E-07 1.30E-07 1.00E-07 3.90E-10 GARDENS NE 4.9 8.60E-08 8.60E-08 6.40E-08 2.30E-10 GARDENS ENE 5 7.00E-08 7.00E-08 5.20E-08 2.10E-10 GARDENS NE 5 8.40E-08 8.40E-08 6.20E-08 2.20E-10 GARDENS E 6 5.30E-08 5.30E-08 3.80E-08 1.70E-10 GARDENS ENE 6 5.50E-08 5.50E-08 4.00E-08 1.50E-10 GARDENS ESE 6.3 4.50E-08 4.50E-08 3.20E-08 1.60E-10 GARDENS NW 7 6.00E-08 6.00E-08 4.30E-08 1.80E-10 GARDENS NNE 7.5 3.40E-08 3.40E-08 2.40E-08 8.70E-11 GARDENS NW 8.3 4.80E-08 4.80E-08 3.30E-08 1.40E-10 GARDENS NE 9.3 3.60E-08 3.60E-08 2.50E-08 7.60E-11 PSEG 2019 ARERR Page 77 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 3 3 3 X/Q (Sec/M ) X/Q (Sec/M ) X/Q (Sec/M )

DIRECTION Distance D/Q LOCATION No Decay No Decay No Decay 2 FROM SITE (MI) (1/M )

Undepleted Undepleted Depleted GARDENS N 10.9 2.30E-08 2.30E-08 1.50E-08 5.70E-11 GARDENS NNE 13.2 1.60E-08 1.60E-08 1.00E-08 3.40E-11 GARDENS WNW 12.1 2.00E-08 2.00E-08 1.30E-08 3.00E-11 GARDENS NE 23.3 1.10E-08 1.10E-08 6.10E-09 1.60E-11 GARDENS SW 4.6 1.00E-07 1.00E-07 7.50E-08 2.70E-10 DAIRY & CATTL W 4.9 8.10E-08 8.10E-08 6.10E-08 1.50E-10 DAIRY & CATTL WNW 8.5 3.20E-08 3.20E-08 2.20E-08 5.40E-11 DAIRY & CATTL NE 11.3 2.80E-08 2.80E-08 1.80E-08 5.50E-11 DAIRY & CATTL N 11.7 2.10E-08 2.10E-08 1.30E-08 5.10E-11 DAIRY & CATTL NNE 11.8 1.80E-08 1.80E-08 1.20E-08 4.20E-11 DAIRY & CATTL NE 4.2 1.10E-07 1.10E-07 8.10E-08 3.00E-10 DAIRY & CATTL NE 5.8 6.80E-08 6.80E-08 5.00E-08 1.70E-10 DAIRY & CATTL SSW 8.3 4.80E-08 4.80E-08 3.30E-08 1.00E-10 DAIRY & CATTL N 11.5 2.10E-08 2.10E-08 1.40E-08 5.20E-11 DAIRY & CATTL NE 17.7 1.60E-08 1.60E-08 9.30E-09 2.50E-11 VENT AND BUILDING PARAMETERS:

Rep. Wind Height Release Height (Meters) 0.00 10.0 (Meters)

Diameters (Meters) 0.00 Building Height (Meters) 61.8 BLDG.MIN.CRS.SEC.AR Exit Velocity (Meters) 0.00 EA 3819.0 (Square Meters)

Heat Emission Rate 0.0 (Cal/Sec)

PSEG 2019 ARERR Page 78 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX C Maximum Permissible Concentration (MPC)

Data PSEG 2019 ARERR Page 79 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Page Intentionally Left Blank PSEG 2019 ARERR Page 80 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991.

Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 1E-4 1E-4 Am-243 4E-6 3E-5 Am-244 5E-3 5E-3 Antimony (51) Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 1E-4 Sb-126 3E-6 3E-6 Arsenic (33) As-73 5E-4 5E-4 As-74 5E-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Br-83 3E-6 3E-6 Cadmium (48) Cd-109 2E-4 2E-4 Cd-115m 3E-5 3E-5 Cd-115 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Cf-250 1E-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 1E-7 1E-7 Carbon (6) C-14 8E-4 -------

Cerium (58) Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 1E-5 1E-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 PSEG 2019 ARERR Page 81 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

Cs-135 1E-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) Cl-36 8E-5 6E-5 Cl-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 1E-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 1E-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy-165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 1E-5 1E-5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 1E-4 1E-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 1E-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 Fluorine (9) F-18 8E-4 5E-4 Gadolinium (64) Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au-196 2E-4 1E-4 Au-198 5E-5 5E-5 Au-199 2E-4 2E-4 Hafnium (72) Hf-181 7E-5 7E-5 Holmium (67) Ho-166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-113m 1E-3 1E-3 In-114m 2E-5 2E-5 In-115m 4E-4 4E-4 PSEG 2019 ARERR Page 82 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

In-115 9E-5 9E-5 Iodine (53) I-125 2E-7 2E-4 I-126 3E-7 9E-5 I-129 6E-8 2E-4 I-130 3E-6 3E-6 I-131 3E-7 6E-5 I-132 8E-6 2E-4 I-133 1E-6 4E-5 I-134 2E-5 6E-4 I-135 4E-6 7E-5 Iridium (77) Ir-190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La-140 2E-5 2E-5 Lead (82) Pb-203 4E-4 4E-4 Pb-210 1E-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu-177 1E-4 1E-4 Manganese (25) Mn-52 3E-5 3E-5 Mn-54 1E-4 1E-4 Mn-56 1E-4 1E-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 5E-4 Hg-203 2E-5 1E-4 Molybdenum (42) Mo-99 2E-4 4E-5 Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 1E-4 1E-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd-103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt-191 1E-4 1E-4 Pt-193m 1E-3 1E-3 PSEG 2019 ARERR Page 83 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

Pt-193 9E-4 2E-3 Pt-197m 1E-3 9E-4 Pt-197 1E-4 1E-4 Plutonium (94) Pu-238 5E-6 3E-5 Pu-239 5E-6 3E-5 Pu-240 5E-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 Praseodymium(59) Pr-142 3E-5 3E-5 Pr-143 5E-5 5E-5 Promethium (61) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium(91) Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 1E-4 1E-4 Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 5E-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75) Re-183 6E-4 3E-4 Re-186 9E-5 5E-5 Re-187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45) Rh-103m 1E-2 1E-2 Rh-105 1E-4 1E-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 Ru-103m 3E-6 3E-6 Ru-105 1E-4 1E-4 Ru-106 1E-5 1E-5 Samarium (62) Sm-147 6E-5 7E-5 Sm-151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5 Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 Silver (47) Ag-105 1E-4 1E-4 Ag-110m 3E-5 3E-5 Ag-111 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 PSEG 2019 ARERR Page 84 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E-4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) S-35 6E-5 3E-4 Tantalum (73) Ta-182 4E-5 4E-5 Technetium (43) Tc-96m 1E-2 1E-2 Tc-96 1E-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52) Te-125m 2E-4 1E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Tb-160 4E-5 4E-5 Thallium (81) Tl-200 4E-4 2E-4 Tl-201 3E-4 2E-4 Tl-202 1E-4 7E-5 Tl-204 1E-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 1E-5 Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm-171 5E-4 5E-4 Tin (50) Sn-113 9E-5 8E-5 Sn-124 2E-5 2E-5 Tungsten (74) W-181 4E-4 3E-4 W-185 1E-4 1E-4 W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 PSEG 2019 ARERR Page 85 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Maximum Permissible Concentrations Element Isotope Soluble Conc. Insoluble Conc.

(Ci/ml) (Ci/ml)

U-natural 3E-5 3E-5 Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 1E-4 1E-4 Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 1E-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radionuclide not listed above with decay mode other than alpha emission or 3E-6 3E-6 spontaneous fission and with radioactive half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Any single radionuclide not listed above, which decays by alpha emission or spontaneous 3E-8 3E-8 fission.

Notes:

1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be:

3E-8 Ci/ml.

2. If the identity and concentration of each radionuclide were known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed 1 (i.e. unity).

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T APPENDIX D 2019 Radiological Groundwater Protection Program (RGPP) Report PSEG 2019 ARERR Page 87 of 116

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T 2019 Radiological Groundwater Protection Program (RGPP) Report Results of the Integrated Tritium Management Program With 2019 Radiological Groundwater Protection Program (RGPP)

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table of Contents I. Introduction .................................................................................................................................... 92 II. Radiological Groundwater Protection Program ............................................................................. 93

1. Objectives of the Radiological Groundwater Protection Program ........................................... 93

2. Sample Collection .................................................................................................................... 93

3. New RGPP Wells .................................................................................................................... 93

4. Sample Analysis ...................................................................................................................... 93

5. Data Evaluation ....................................................................................................................... 94 A. Detection limits .................................................................................................................. 94 B. Laboratory Measurements Uncertainty ............................................................................. 94

6. RGPP Data Quality .................................................................................................................. 94 III. Discussion ...................................................................................................................................... 95

1. Groundwater Results - RGPP ................................................................................................. 95 A. HCGS RGPP Wells ........................................................................................................... 95 B. SGS RGPP Wells.............................................................................................................. 96

2. Mass Flux Estimation of Tritium to the Delaware River .......................................................... 97

3. Investigations ........................................................................................................................... 97 A. Groundwater Monitoring Well Data (Non-RGPP) ............................................................. 97 B. Past Spills and Leaks: Impacts to Groundwater IV. RGPP 2020 Status ......................................................................................................................... 97 V. References ..................................................................................................................................... 98 List of Tables Table 1. RGPP Well Construction Details, HCGS ...................................................................................... 99 Table 2. RGPP Well Construction Details, SGS ....................................................................................... 100 Table 3. Well Construction Details, Investigation and Monitoring Wells ................................................... 101 Table 4. Relevant Groundwater Evaluation Criteria, SGS and HCGS ..................................................... 104 Table 5. Tritium Analytical Results, HCGS RGPP Wells .......................................................................... 105 Table 6. Tritium Analytical Results, SGS RGPP Wells ............................................................................. 107 Table 7. Tritium Analytical Results, Investigation & Monitoring Wells ...................................................... 109 List of Figures Figure 1. Well Location Map, Hope Creek Generating Station ................................................................. 115 Figure 2. Well Location Map, Salem Generating Station .......................................................................... 116 PSEG 2019 ARERR Page 91 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Introduction This report presents results of the 2019 groundwater monitoring activities performed by PSEG Nuclear at both the Hope Creek Generating Station (HCGS) and Salem Generating Station (SGS); collectively referred to as the Station. Well locations at the Station are shown on Figures 1 and 2, respectively. To link the various groundwater monitoring programs at the Station, PSEG implemented the Integrated Tritium Management Program (ITMP) which integrates the following four broad programs:

The Radiological Groundwater Protection Program (RGPP) is a program that was developed to ensure the timely detection of an unpermitted release of radioactive material; The Remedial Action Work Plan (RAWP) is a program that monitors the remediation of the historical release from the SGS Unit 1 Spent Fuel Pool; Investigation wells were installed as part of independent investigations into groundwater quality, that are not included as part of the RGPP or RAWP; and Early Site Permit (ESP) wells which are periphery wells that were installed outside of the protected area to support the potential licensing of a new nuclear plant.

Well construction details for the Stations RGPP wells are presented on Tables 1 and 2, respectively. Well construction details for the wells that are not specifically part of the RGPP are presented on Table 3.

PSEG initiated the RGPP in 2006 to characterize groundwater at, and in the vicinity of, the Station with respect to historical releases of radionuclides and to provide the mechanism to detect such releases, if one were to occur. The RGPP is a voluntary program implemented by PSEG in conjunction with the nuclear industry initiatives and associated guidance (NEI 2007). The other key elements that comprise the RGPP and contribute to public safety are spill/leak prevention, effective remediation of spills and leaks, and effective stakeholder communication.

In 2002, PSEG operations personnel at SGS identified a release of tritiated water from the SGS Unit 1 Spent Fuel Pool to the environment. PSEG developed a RAWP to remediate the tritium in groundwater, which was reviewed by the United States Nuclear Regulatory Commission (USNRC) and approved by the New Jersey Department of Environmental Protection (NJDEP)

Bureau of Nuclear Engineering (BNE). A Groundwater Recovery System (GRS) was installed to control the migration of groundwater in the shallow, water-bearing unit and to reduce the remaining mass of tritiated groundwater. The operation and performance of the GRS is documented in the Remedial Action Progress Reports (RAPRs) provided to the NRC and NJDEP-BNE by PSEG. PSEG generates an effluent release permit for the residual tritium in groundwater discharging to the Delaware River. The permit values are included in the liquid effluent data reported earlier in this document.

The Station is located in a flat, largely undeveloped region of southern New Jersey, which is bordered to the west and south by the Delaware River and to the east and north by extensive marshlands. The Station obtains cooling water from the Delaware River.

The Station is underlain by over 1,000 feet of inter-layered sand, silt and clay. PSEG owns seven production/potable wells, which range in depth from 270 feet below ground surface (bgs) to 1135 feet bgs. These wells are installed in deeper formations isolated by confining units beneath the Vincentown Formation.

The results from a computer based well search identified the nearest off-site permitted potable well is located approximately 3.5 miles away. Shallow groundwater and the Vincentown aquifer (the two most shallow water bearing units underlying the Station) flow toward and discharge to the Delaware River, thus reducing the potential that Station operations have or will influence off-site potable wells.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T I. Radiological Groundwater Protection Program This section of the annual report is prepared to summarize the status, activities, and groundwater analytical results collected in 2019 at the Site. This report also describes any changes made to the monitoring program during the 2019 reporting year.

4. Objectives of the Radiological Groundwater Protection Program The long-term sampling program objectives are as follows:

Identify suitable locations to monitor and evaluate potential impacts from Station operations before significant radiological impact to the environment or potential drinking water sources can occur.

Refine the conceptual understanding of local hydrogeology and maintain current knowledge of potential flow paths on the surface and in groundwater beneath the Station.

Evaluate systems, structures, components (SSCs) and work practices, which have the potential to release licensed radioactive material to the groundwater and develop strategies to mitigate potential releases to the environment.

Perform routine groundwater monitoring and evaluate analytical results.

Report any leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.

Take necessary corrective actions to protect groundwater resources.

5. Sample Collection In 2006, the RGPP monitoring wells (Tables 1 and 2) were installed at the Station as part of site investigation activities. Details pertaining to these activities are documented in the Site Investigation Reports (Arcadis 2006A and 2006B). Groundwater samples are collected from all RGPP monitoring wells at least semi-annually, with additional monitoring conducted as appropriate. The groundwater sample collection schedule is adaptively managed to ensure that representative data are collected to provide the information necessary to evaluate groundwater quality conditions. Monitoring wells are sampled following the low-flow purging and sampling techniques in accordance with the Field Sampling Procedures Manual (NJDEP 2005). This methodology is consistent with protocols established in the RAWP.

6. New RGPP Wells No new wells were added as part of the RGPP during 2019.

7. Sample Analysis Groundwater samples collected from RGPP wells are analyzed for plant-related gamma emitting radionuclides (semi-annually), strontium (annually), iron 55 (biennially) and tritium (every sample) by an off-site radiochemical analytical laboratory.

The samples are maintained under chain of custody procedures throughout sample handling, screening, shipping and laboratory analysis process. Samples are submitted to the respective PSEG 2019 ARERR Page 93 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Stations on-site chemistry laboratory for radiological analysis screening prior to shipment to Teledyne Brown Engineering (TBE) located in Knoxville, Tennessee, for radiological analysis.

Analytical laboratories are subject to internal quality assurance programs and inter-laboratory cross-check programs. Station personnel review and evaluate analytical data obtained from the laboratory.

8. Data Evaluation Analytical results are reviewed for adverse trends or anomalies. Investigations and corrective action program notifications (Notification) are made as required by program procedures. The radiological data collected since the inception of the RGPP program is the basis for the baseline statistical evaluation to which current operational data are compared. Several factors are important in the interpretation and evaluation of the radiological data:

A. Detection limits The Offsite Dose Calculation Manual (ODCM) specifies detection capabilities for each isotope that may be produced by the Station. While the detection capability for tritium specified in the ODCM is 3,000 picocuries per liter (pCi/L) in water, RGPP tritium analyses are performed to a lower value of 200 pCi/L. Lower values for LLDs are used to be consistent with the State of New Jersey where PSEG conducts split samples with the NJDEP-BNE for specific wells. Each well has a statistically derived action level. When an action level is exceeded, PSEG may increase monitoring frequency and evaluates potential sources of the elevated tritium. Relevant groundwater evaluation criteria are listed in Table 4.

B. Laboratory Measurements Uncertainty Statistically, the value of a measurement is expressed as a range with a stated level of confidence. PSEG is required to report results with a 95% level of confidence.

Analytical uncertainties are reported at the 95% confidence level in this report and are consistent with the methodologies used to report data in the Annual Radiological Environmental Operating Report.

9. RGPP Data Quality Groundwater samples consist of up to four aliquots. One of the aliquots is submitted to the respective Sites on-site chemistry laboratory for initial screening, which includes tritium and gamma spectroscopy analysis. The second aliquot is sent to TBE for tritium analysis. In accordance with NJDEP request, the third aliquot is collected from specific wells and submitted for split sample analysis to GEL Laboratories located in Charleston, South Carolina. The fourth aliquot is held as a back-up, retained sample until all the analytical results are received and determined to be valid.

All radionuclide results are compared to the following limitations defined as part of the RGPP:

Internal Administrative Control Limits are defined within the RGPP procedures. They are developed based on a statistical analysis of the historical baseline concentrations of tritium in each specific well and are used to identify tritium concentrations that warrant further investigation for that specific well. Solely exceeding an Administrative Control Limit does not initiate external communication, unless the external reporting limit is also exceeded.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T The Courtesy Communication Limit is a tritium concentration, below regulatory requirements, based on agreements with NJDEP-BNE, USNRC and other stakeholders ensuring the stakeholders are cognizant of potential issues. If a confirmed tritium result, collected from a RGPP well, exceeds the Courtesy Communication Limit of 3,000 pCi/L, PSEG provides a courtesy communication by telephone no later than the end of the next business day to NJDEP-BNE. The NRC Site Resident is also informed. This is not a regulatory required communication.

Voluntary Communication Limits are those concentrations of radionuclides that require voluntary communication and reporting to regulators and/or stakeholders based on NEI 07-07, the ODCMs, and Site procedures.

II. Discussion The locations of the RGPP monitoring wells located at HCGS and SGS are depicted on Figures 1 and 2, respectively. Additionally, well construction details for the HCGS RGPP wells and SGS RGPP wells are presented on Tables 1 and 2, respectively. The relevant radiological parameters used to evaluate the groundwater analytical results are provided in Table 4. The groundwater tritium analytical results for HCGS and SGS are shown on Tables 5 and 6, respectively.

1. Groundwater Results - RGPP Groundwater samples were collected from all RGPP monitoring wells during 2019 in accordance with the Station and PSEGs Laboratory and Testing Services (LTS) procedures for the RGPP. Sample results are discussed below.

A. HCGS RGPP Wells Tritium analytical results for groundwater samples collected during 2019 from HCGS RGPP monitoring wells are summarized below and are presented in Table 5.

Tritium was not detected in groundwater samples collected from 8 of the 13 HCGS RGPP wells (wells BH, BK, BL, BP, BQ, BR, BS, and BT).

Well BI: Tritium concentrations detected in well BI ranged from 254 pCi/L (November 2019) to 1,350 pCi/L (May 2019) and averaged 692 pCi/L, during 2019. Well BI is located west of the reactor containment and is a sentinel (source) well for facilities and buried piping.

Well BJ: Tritium concentrations detected in well BJ ranged from 2,770 pCi/L (June 2019) to 5,140 pCi/L (December 2019) and averaged 3,411 pCi/L, during 2019. Well BJ is located near the HCGS main permitted gaseous effluent vent (i.e., south plant vent).

Well BM: Tritium was detected at concentrations ranging from 420 pCi/L (February 2019) to 529 pCi/L (August 2019) and averaged 477 pCi/L, during 2019. Well BM is located northwest of the reactor containment and is a sentinel (source) well for facilities and buried piping.

Well BN: Tritium concentrations detected in well BN ranged from 393 pCi/L (October 2019) to 2,270 pCi/L (February 2019) and averaged 1,003 pCi/L. Well BN is located northeast of the Materials Control Center and is a sentinel (source) well for the Auxiliary Boiler building and buried piping.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Well BO: Tritium concentrations detected in well BO ranged from 437 pCi/L (November 2019) to 1,290 pCi/L (May 2019). Tritium was not detected in the sample collected in August 2019. Well BO is located northeast of the Materials Control Center and is a sentinel (source) well for the Auxiliary Boiler building and buried piping.

There were no analytical results for which a Courtesy Communication (greater than 3,000 pCi/L tritium) was required as part of the HCGS RGPP.

With the exception of tritium, no plant-related radionuclides were detected in any HCGS RGPP well sampled in 2019.

B. SGS RGPP Wells Tritium analytical results for groundwater samples collected during 2019 from SGS RGPP monitoring wells are summarized below and are presented on Table 6.

Tritium was not detected in groundwater samples collected from 6 of the 13 SGS RGPP wells (wells BA, BB, BF, BU, T, and Y).

Well AL: Well AL was sampled in May and November 2019, with results of 398 pCi/L and 697 pCi/L respectively. Well AL is located south of the SGS Unit 1 reactor building and is a sentinel (source) well.

Well BC: Tritium was detected at concentrations ranging from 1,270 pCi/L (February 2019) to 4,780 pCi/L (December 2019) and averaged 2,743 pCi/L. Well BC is a sentinel (source)/perimeter well located southwest of Facilities, Refueling Water Storage Tank, Auxiliary Feedwater Storage Tank and Primary Water Storage Tank (RAP) tanks and piping.

Well BD: Tritium was detected at concentrations ranging from 384 pCi/L (February 2019) to 592 pCi/L (August 2019) and averaged 465 pCi/L. Well BD is located to the west of SGS Unit 2 reactor building and is a sentinel (source) well for Facilities, RAP tanks, and piping.

Well BE: Tritium was detected at concentrations ranging from 291 pCi/L (February 2019) to 755 pCi/L (May 2019) and averaged 532 pCi/L. Well BE is located to the west of SGS Unit 2 reactor building and is a perimeter well.

Well BG: Tritium was detected at concentrations ranging from 191 pCi/L (May 2019) to 254 pCi/L (August 2019) and averaged 219 pCi/L. Well BG is located northwest of SGS Unit 2 reactor building and is a perimeter well.

Well U: Tritium was detected at concentrations ranging from 227 pCi/L (August 2019) to 497 pCi/L (February 2019) and averaged 362 pCi/L. Well U is located north of SGS Unit 2 reactor building and is a sentinel (source) well for the House Heating Boilers.

Well Z: Tritium was detected in the samples collected in May 2019 (514 pCi/L) and November 2019 at concentrations of 514 pCi/L and 545 pCi/L, respectively. Well Z is located west of the SGS Unit 1 & 2 reactor buildings and is a perimeter well.

There were no analytical results for which a Courtesy Communication (greater than 3,000 pCi/L tritium) was required as part of the SGS RGPP.

With the exception of tritium, no plant-related radionuclides were detected in any SGS RGPP well sampled in 2019.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T

2. Mass Flux Estimation of Tritium to the Delaware River PSEG uses transect methods to calculate the mass flux of tritium to the Delaware River in the shallow, water bearing unit and the deeper basal sand unit and Vincentown Formation. To calculate the mass flux, the tritium concentration was conservatively estimated using the average concentration detected in monitoring wells located nearest to the Delaware River during each quarter. During 2019, the mass flux within the shallow, water bearing unit and deeper groundwater was estimated to be 0.016 Ci and 0.041 Ci, respectively. Therefore, the total potential estimated mass flux of tritium in groundwater reaching the Delaware River during 2019 was 0.057 Ci.

The calculated mass flux of 0.057 Ci (total of four quarterly estimates) was included in the Stations liquid effluent discharge and reported in the data tables of the Annual Radiological Effluent Release Report.

3. Investigations A. Groundwater Monitoring Well Data (Non-RGPP)

As previously discussed, PSEG monitors a series of wells located at the Station. The ITMP is comprised of the RGPP wells, the RAWP wells, the ESP wells and a series of monitoring wells that were installed to investigate groundwater quality, but are not included as part of the RGPP, RAWP, or ESP. Three new monitoring wells (wells BH-V, BM-V, and BY-V) were installed within the Vincentown Formation to refine the conceptual site model at HCGS. Well construction details and tritium analytical results for the wells described above that are not specifically part of the RGPP are presented on Table 3 and Table 7, respectively.

B. Past Spills and Leaks: Impacts to Groundwater In 2019, there were no known active unmonitored or unevaluated releases into the groundwater at the Station.

III. RGPP 2020 Status The RGPP long-term sampling program will be modified as required to meet the RGPP objectives. Baseline sampling and analysis of groundwater is planned to continue on the following schedule:

Tritium will be analyzed at least semi-annually each calendar year to a detection capability less than or equal to 200 pCi/L; Plant-related gamma emitters will be analyzed at least semi-annually to the environmental detection limits specified in the ODCM; Nickel 63 will be analyzed biennially starting in 2020; RGPP monitoring well sample frequency will be adjusted as needed based on analytical results.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T IV. References

1. Arcadis, 2004. Remedial Investigation Work Plan. PSEG Nuclear LLC. Salem Generating Station, Hancocks Bridge, New Jersey.

2. Arcadis, 2006A. Site Investigation Report July 2006. PSEG Nuclear LLC. Hope Creek Generating Station, Hancocks Bridge, New Jersey.

3. Arcadis, 2006B. Site Investigation Report July 2006. PSEG Nuclear LLC. Salem Generating Station, Hancocks Bridge, New Jersey.

4. Arcadis, 2013. Revised Salem Unit 2 Remedial Investigation Work Plan Addendum.

PSEG Nuclear LLC. December 2013.

5. Arcadis, 2014. Remedial Action Work Plan Addendum. PSEG Nuclear LLC. Salem, Hancocks Bridge, New Jersey. April 10, 2014.

6. NEI, 2007. NEI 07-07, Industry Groundwater Protection Initiative - Final Guidance Document, Nuclear Energy Institute, Washington, DC, June 2007.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 1. RGPP Well Construction Details, HCGS Total Monitoring MP MP Installation Construction Diameter Monitoring Depth Interval Elevation Elevation Source Targets Well ID Date Details (inches) Purpose (feet bgs) (feet bgs) (feet RPD) (feet amsl)

Well BH May-06 Sch-40 PVC 4 37.0 27.0 - 37.0 101.16 11.24 Perimeter NA Well BI May-06 Sch-40 PVC 4 37.0 27.0 - 37.0 103.07 13.15 Source Facilities; Piping Condensate Storage &

Well BJ May-06 Sch-40 PVC 4 38.0 28.0 - 38.0 102.97 13.05 Source Transfer; Facilities; Piping Well BK May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 101.42 11.50 Perimeter NA Well BL May-06 Sch-40 PVC 4 37.0 27.0 - 37.0 102.69 12.77 Perimeter NA Well BM May-06 Sch-40 PVC 4 37.5 27.5 - 37.5 102.75 12.83 Source Facilities; Piping Auxiliary Boiler Building; Well BN May-06 Sch-40 PVC 4 12.5 7.5 - 12.5 102.64 12.72 Source Piping Well BO May-06 Sch-40 PVC 4 35.0 25.0 - 35.0 97.98 8.06 Perimeter/Source Building Sewage Well BP May-06 Sch-40 PVC 4 38.0 28.0 - 38.0 99.06 9.14 Perimeter/Source Building Sewage Auxiliary Boiler Building; Well BQ May-06 Sch-40 PVC 4 42.0 32.0 - 42.0 105.62 15.70 Source Dry Cask Storage Building; Piping Piping; Dry Cask Well BR May-06 Sch-40 PVC 4 40.5 30.5 - 40.5 104.28 14.36 Perimeter/Source Storage Building Well BS May-06 Sch-40 PVC 4 35.0 25.0 - 35.0 100.55 10.63 Upgradient NA Well BT May-06 Sch-40 PVC 4 38.5 28.5 - 38.5 99.60 9.68 Upgradient NA Notes:

MP Measuring Point bgs Below ground surface RPD Relative to plant datum amsl Above mean sea level (NAVD 1988)

NA Not applicable PSEG 2019 ARERR Page 99 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 2. RGPP Well Construction Details, SGS MP MP Installation Construction Diameter Total Depth Monitoring Interval Monitoring Elevation Elevation Source Targets Well ID Date Details (inches) (feet bgs) (feet bgs) Purpose (feet RPD) (feet amsl)

Well T Jun-03 Sch-40 PVC 2 31.2 21.2 - 31.2 104.13 14.21 Source Facilities; House Heating Boiler 1

Well U May-03 Sch-40 PVC 2 32.2 27.2 - 32.2 101.46 11.54 Source Facilities; House Heating Boiler Well Y Sep-03 Sch-40 PVC 2 37.0 27.0 - 37.0 101.81 11.89 Perimeter NA Well Z Sep-03 Sch-40 PVC 2 37.5 27.5 - 37.5 101.86 11.94 Perimeter NA Well AL Jan-04 Sch-40 PVC 2 25.3 15.3 - 25.3 99.13 9.21 Perimeter NA Well BA May-06 Sch-40 PVC 4 39.5 29.5 - 39.5 101.07 11.15 Perimeter NA 1

Well BB May-06 Sch-40 PVC 4 47.0 37.0 - 47.0 102.18 12.26 Perimeter NA Well BC May-06 Sch-40 PVC 4 38.0 28.0 - 38.0 98.78 8.86 Source / Perimeter Facilities; RAP Tanks; Piping Well BD May-06 Sch-40 PVC 4 40.5 30.5 - 40.5 98.78 8.86 Source Facilities; RAP Tanks; Piping Well BE May-06 Sch-40 PVC 4 37.0 27.0 - 37.0 98.31 8.39 Perimeter NA 1

Well BF May-06 Sch-40 PVC 4 42.0 32.0 - 42.0 101.45 11.53 Perimeter NA 1

Well BG May-06 Sch-40 PVC 4 37.0 27.0 - 37.0 103.34 13.42 Perimeter NA Well BU May-06 Sch-40 PVC 4 36.0 26.0 - 36.0 100.16 10.24 Upgradient NA Notes:

MP Measuring Point bgs Below ground surface RPD Relative to plant datum amsl Above mean sea level (NAVD 1988)

NA Not applicable 1

Monitoring wells U, BB, BF, and BG were surveyed in July/August 2013 following retrofitting or repair activities.

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2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 3. Well Construction Details, Investigation and Monitoring Wells Installation Construction Diameter Total Depth Monitoring Monitored MP MP Well ID Date Details (inches) (feet bgs) Interval Hydrogeologic Elevation Elevation (feet bgs) Unit (feet RPD) (feet amsl) 1 Well K Feb-03 Sch-40 PVC 2 80.0 70.0 - 80.0 Vincentown 102.00 12.08 1

Well L Jan-03 Sch-40 PVC 2 80.0 70.0 - 80.0 Vincentown 101.46 11.54 2

Well M May-03 Sch-40 PVC 1 20.0 10.0 - 20.0 Cofferdam 102.17 12.25 2

Well N Jan-03 Sch-40 PVC 2 20.0 10.0 - 20.0 Cofferdam 101.65 11.73 2

Well O Jan-03 Sch-40 PVC 2 20.0 10.0 - 20.0 Cofferdam 101.33 11.41 1

Well P Mar-03 Sch-40 PVC 2 80.0 70.0 - 80.0 Vincentown 101.13 11.21 1

Well Q Mar-03 Sch-40 PVC 2 80.0 70.0 - 80.0 Vincentown 106.59 16.67 1

Well EOW-4L Jan-09 Sch-40 PVC 2 120.2 110.2-120.2 Vincentown 112.23 22.31 2

Well R Jun-03 Sch-40 PVC 1 19.0 9.0 - 19.0 Cofferdam 102.35 12.43 4 3 Well S May-03 Sch-40 PVC 2 34.7 24.7 - 34.7 Shallow 99.04 9.12 1

Well S-V May-14 Sch-40 PVC 4 85.0 75.0 - 85.0 Vincentown 101.00 11.08 6 1 Well V Jun-03 Sch-40 PVC 2 79.5 69.5 - 79.5 Vincentown 101.72 11.80 6 3 Well W Jun-03 Sch-40 PVC 2 35.0 25.0 - 35.0 Shallow 98.49 8.57 4 3 Well AA Sep-03 Sch-40 PVC 2 36.0 26.0 - 36.0 Shallow 99.07 9.15 1

Well AA-V May-13 Sch-40 PVC 2 85.0 75.0 - 85.0 Vincentown 100.80 10.88 4 3 Well AB Oct-03 Sch-40 PVC 2 42.0 32.0- 42.0 Shallow 98.93 9.01 4 2 Well AC Sep-03 Sch-40 PVC 2 24.0 14.0 - 24.0 Cofferdam 98.77 8.85 4 3 Well AD Oct-03 Sch-40 PVC 6 43.0 33.0 - 43.0 Shallow 98.99 9.07 2

Well AE Oct-03 Sch-40 PVC 2 27.5 17.5 - 27.5 Cofferdam 101.54 11.62 3

Well AF Oct-03 Sch-40 PVC 2 45.0 35.0 - 45.0 Shallow 101.61 11.69 1

Well AF-V Nov-16 Sch-40 PVC 4 91.0 71.0 - 91.0 Vincentown 101.38 11.46 3

Well AG-Shallow Feb-04 Sch-40 PVC 1 24.2 14.2 - 24.2 Shallow 99.29 9.37 3

Well AG-Deep Feb-04 Sch-40 PVC 1 40.0 30.0 - 40.0 Shallow 99.20 9.28 3

Well AH-Shallow Feb-04 Sch-40 PVC 1 24.5 14.5 - 24.5 Shallow 102.58 12.66 3

Well AH-Deep Feb-04 Sch-40 PVC 1 40.0 30.0 - 40.0 Shallow 102.70 12.78 PSEG 2019 ARERR Page 101 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 3. Well Construction Details, Investigation and Monitoring Wells Installation Construction Diameter Total Depth Monitoring Monitored MP MP Well ID Date Details (inches) (feet bgs) Interval Hydrogeologic Elevation Elevation (feet bgs) Unit (feet RPD) (feet amsl) 2 Well AI Jan-04 Sch-40 PVC 4 22.0 12.0 - 22.0 Cofferdam 98.79 8.87 3

Well AJ Jan-04 Sch-40 PVC 4 35.3 15.3 - 35.3 Shallow 98.85 8.93 2

Well AM Jan-04 Sch-40 PVC 4 20.9 10.9 - 20.9 Cofferdam 98.55 8.63 2

Well AN Jun-04 Sch-40 PVC 4 25.0 10.0 - 25.0 Cofferdam 98.76 8.84 2

Well AO Jun-04 Sch-40 PVC 4 21.0 11.0 - 21.0 Cofferdam 98.82 8.90 3

Well AP Jun-04 Sch-40 PVC 4 40.0 15.0 - 40.0 Shallow 98.65 8.73 5 3 Well AQ Jun-04 Sch-40 PVC 4 45.0 20.0 - 45.0 Shallow 99.05 9.13 3

Well AR Jun-04 Sch-40 PVC 4 43.0 18.0 - 43.0 Shallow 99.22 9.30 3

Well AS Jun-04 Sch-40 PVC 4 41.5 16.5 - 41.5 Shallow 99.44 9.52 3

Well AT Jun-04 Sch-40 PVC 4 44.0 19.0 - 44.0 Shallow 99.25 9.33 6 3 Well BW Dec-06 Sch-40 PVC 1 10.0 5.0 - 10.0 Shallow 101.62 11.70 6 3 Well BX Dec-06 Sch-40 PVC 1 10.0 5.0 - 10.0 Shallow 101.79 11.87 3

Well BY Nov-10 Sch-40 PVC 4 40.0 35.0 - 40.0 Shallow 103.36 13.44 3

Well BZ Nov-10 Sch-40 PVC 4 36.0 31.0 - 36.0 Shallow 104.29 14.37 6 3 Well CA Dec-06 Sch-40 PVC 4 38.0 28.0 - 38.0 Shallow 101.96 12.04 7 1 Well CB Dec-06 Sch-40 PVC 2 80.0 70.0 - 80.0 Vincentown 98.98 9.06 6 2 Well DA Nov-10 Sch-40 PVC 4 17.0 12.0 - 17.0 Cofferdam 99.04 9.12 2

Well DB Nov-10 Sch-40 PVC 4 21.0 16.0 - 21.0 Cofferdam 101.69 11.77 2

Well DC Nov-10 Sch-40 PVC 4 22.0 17.0 - 22.0 Cofferdam 100.90 10.98 2

Well DD Nov-10 Sch-40 PVC 4 19.0 14.0 - 19.0 Cofferdam 101.23 11.31 2

Well DE Nov-10 Sch-40 PVC 4 18.0 13.0 - 18.0 Cofferdam 101.43 11.51 2

Well DF Nov-10 Sch-40 PVC 4 19.0 14.0 - 19.0 Cofferdam 101.32 11.40 2

Well DG Nov-10 Sch-40 PVC 2 13.5 11.5 - 13.5 Cofferdam 98.98 9.06 PSEG 2019 ARERR Page 102 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 3. Well Construction Details, Investigation and Monitoring Wells Installation Construction Diameter Total Depth Monitoring Monitored MP MP Well ID Date Details (inches) (feet bgs) Interval Hydrogeologic Elevation Elevation (feet bgs) Unit (feet RPD) (feet amsl) 2 Well DH Oct-10 Sch-40 PVC 4 21.0 16.0 - 21.0 Cofferdam 101.54 11.62 2

Well DI Oct-10 Sch-40 PVC 4 18.0 13.0 - 18.0 Cofferdam 101.64 11.72 2

Well DJ Oct-10 Sch-40 PVC 2 11.0 6.0 - 11.0 Cofferdam 99.03 9.11 Notes:

MP Measuring point bgs Below ground surface RPD Relative to plant datum amsl Above mean sea level (NAVD 1988) 1 Monitoring well is screened in the Vincentown Formation.

2 Monitoring well is screened in the shallow, water-bearing unit at a location within the limits of the cofferdam.

3 Monitoring well is screened in the shallow, water-bearing unit at a location outside the limits of the cofferdam.

4 The surface completions of Monitoring Wells S, AA, AB, AC, and AD were converted from above-grade to flush-grade in February 2004.

5 Monitoring well AQ was abandoned in November 2016.

6 Monitoring wells BW, BX, CA, DA, V, and W were surveyed in July/August 2013 following retrofitting or repair activities.

7 Monitoring well CB was abandoned in May 2013 PSEG 2019 ARERR Page 103 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 4. Relevant Groundwater Evaluation Criteria, SGS and HCGS RGPP LLD PSEG Reporting Level Isotope (pCi/L) (pCi/L)

Tritium 200 30,000 Total Strontium 2 8 Mn-54 15 1,000 Fe-59 30 400 Co-60 15 300 Zn-65 30 300 Nb-95 15 400 Zr-95 15 400 Cs-134 15 30 Cs-137 18 50 Ba-140 60 200 La-140 15 200 Notes:

LLD Lower Limit of Detection pCi/L Picocuries per liter PSEG 2019 ARERR Page 104 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 5. Tritium Analytical Results, HCGS RGPP Wells Tritium Result Well ID Sample Date (pCi/L)

Well BH 2/6/2019 <191 Well BH 5/6/2019 <192 Well BH 8/7/2019 <186 Well BH 11/6/2019 <192 Well BI 2/7/2019 567 Well BI 5/6/2019 1,340 Well BI 6/13/2019 1,050 Well BI 7/2/2019 775 Well BI 8/5/2019 469 Well BI 9/5/2019 392 Well BI 11/6/2019 254 Well BJ 1/7/2019 2,810 Well BJ 2/7/2019 3,010 Well BJ 3/4/2019 3,110 Well BJ 4/1/2019 3,570 Well BJ 4/11/2019 3,130 Well BJ 5/9/2019 2,990 Well BJ 6/5/2019 2,770 Well BJ 7/3/2019 2,990 Well BJ 8/6/2019 3,810 Well BJ 9/5/2019 3,600 Well BJ 9/30/2019 3,690 Well BJ 11/5/2019 3,720 Well BJ 12/3/2019 5,140 Well BK 5/6/2019 <189 Well BK 11/6/2019 <192 Well BL 5/6/2019 <188 Well BL 11/6/2019 <190 Well BM 2/6/2019 420 Well BM 5/6/2019 466 Well BM 8/7/2019 529 Well BM 11/6/2019 494 Well BN 2/5/2019 2,270 Well BN 5/7/2019 1,530 Well BN 8/8/2019 546 Well BN 9/3/2019 781 Well BN 9/30/2019 393 Well BN 11/7/2019 500 PSEG 2019 ARERR Page 105 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 5. Tritium Analytical Results, HCGS RGPP Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well BO 2/5/2019 1,070 Well BO 5/7/2019 1,290 Well BO 8/8/2019 <198 Well BO 11/7/2019 437 Well BP 5/7/2019 <188 Well BP 11/8/2019 <187 Well BQ 2/5/2019 <193 Well BQ 5/9/2019 <187 Well BQ 8/7/2019 <196 Well BQ 11/6/2019 <192 Well BR 5/7/2019 <191 Well BR 11/7/2019 <193 Well BS 5/7/2019 <191 Well BS 11/7/2019 <195 Well BT 5/7/2019 <190 Well BT 11/7/2019 <188 Notes:

pCi/L Picocuries per liter

< Tritium not detected above indicated concentration 251 Bolded values indicate tritium was detected PSEG 2019 ARERR Page 106 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 6. Tritium Analytical Results, SGS RGPP Wells Tritium Result Well ID Sample Date (pCi/L)

Well AL 5/8/2019 398 Well AL 11/7/2019 697 Well BA 5/8/2019 <186 Well BA 11/5/2019 <185 Well BB 5/8/2019 <186 Well BB 11/5/2019 <185 Well BC 2/5/2019 1,270 Well BC 5/9/2019 1,750 Well BC 8/7/2019 4,180 Well BC 9/5/2019 3,190 Well BC 10/1/2019 2,280 Well BC 11/7/2019 1,750 Well BC 12/3/2019 4,780 Well BD 2/4/2019 384 Well BD 5/7/2019 471 Well BD 8/6/2019 592 Well BD 11/4/2019 411 Well BE 2/6/2019 291 Well BE 5/9/2019 755 Well BE 8/5/2019 558 Well BE 11/5/2019 523 Well BF 5/9/2019 <182 Well BF 11/5/2019 <194 Well BG 2/7/2019 217 Well BG 5/9/2019 191 Well BG 8/8/2019 254 Well BG 11/5/2019 214 Well BU 5/7/2019 <181 Well BU 11/7/2019 <187 Well T 2/7/2019 <196 Well T 5/8/2019 <193 Well T 8/5/2019 <192 Well T 11/5/2019 <188 Well U 2/4/2019 497 Well U 5/8/2019 376 Well U 8/8/2019 227 Well U 11/5/2019 348 Well Y 5/8/2019 <191 Well Y 11/6/2019 <186 PSEG 2019 ARERR Page 107 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 6. Tritium Analytical Results, SGS RGPP Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well Z 5/8/2019 514 Well Z 11/5/2019 545 Notes:

pCi/L Picocuries per liter

< Tritium not detected above indicated concentration 545 Bolded values indicate tritium was detected PSEG 2019 ARERR Page 108 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells Tritium Result Well ID Sample Date (pCi/L)

Well AA 2/5/2019 1,120 Well AA 7/11/2019 1,300 Well AA-V 1/11/2019 4,270 Well AA-V 4/4/2019 4,310 Well AA-V 7/11/2019 5,680 Well AA-V 9/30/2019 5,410 Well AB 1/9/2019 5,800 Well AB 10/16/2019 6,730 Well AC 1/7/2019 27,300 Well AC 2/4/2019 21,300 Well AC 3/4/2019 33,200 Well AC 4/2/2019 47,800 Well AC 5/7/2019 62,600 Well AC 6/4/2019 35,500 Well AC 7/8/2019 52,600 Well AC 8/6/2019 38,100 Well AC 9/4/2019 34,600 Well AC 10/1/2019 48,300 Well AC 11/4/2019 16,900 Well AC 12/3/2019 29,400 Well AD 1/9/2019 11,100 Well AD 4/3/2019 7,170 Well AD 10/16/2019 9,630 Well AE 1/8/2019 8,110 Well AE 4/3/2019 9,410 Well AE 7/10/2019 12,000 Well AE 10/1/2019 9,750 Well AF 1/8/2019 232 Well AF 7/11/2019 240 Well AF-V 1/8/2019 472 Well AF-V 4/3/2019 313 Well AF-V 7/11/2019 426 Well AF-V 9/30/2019 252 Well AG-D 1/9/2019 834 Well AG-D 7/9/2019 964 PSEG 2019 ARERR Page 109 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well AG-S 1/9/2019 847 Well AG-S 7/9/2019 944 Well AH-D 1/8/2019 932 Well AH-D 7/11/2019 879 Well AH-S 1/8/2019 792 Well AH-S 7/11/2019 1,080 Well AI 1/7/2019 1,970 Well AI 7/9/2019 4,310 Well AJ 10/16/2019 4,970 Well AM 1/7/2019 37,100 Well AM 2/4/2019 13,100 Well AM 3/4/2019 15,600 Well AM 4/2/2019 14,300 Well AM 5/7/2019 7,030 Well AM 6/4/2019 33,400 Well AM 7/8/2019 10,900 Well AM 8/6/2019 13,200 Well AM 9/4/2019 5,470 Well AM 10/1/2019 6,140 Well AN 1/9/2019 11,600 Well AN 2/6/2019 21,100 Well AN 3/4/2019 17,000 Well AN 4/3/2019 22,200 Well AN 5/7/2019 23,800 Well AN 6/4/2019 21,800 Well AN 7/9/2019 21,400 Well AN 8/7/2019 3,670 Well AN 9/4/2019 22,300 Well AN 10/16/2019 24,600 Well AN 11/7/2019 24,600 Well AN 12/4/2019 22,700 Well AP 1/9/2019 4,310 Well AP 4/4/2019 1,840 Well AP 5/8/2019 1,530 Well AP 6/5/2019 1,960 Well AP 7/12/2019 1,700 Well AP 8/6/2019 1,630 Well AP 9/5/2019 1,200 Well AP 10/3/2019 1,200 PSEG 2019 ARERR Page 110 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well AR 1/11/2019 6,540 Well AR 4/4/2019 6,380 Well AR 7/11/2019 6,810 Well AR 9/30/2019 6,010 Well AS 1/11/2019 3,460 Well AS 7/11/2019 5,520 Well AT 1/9/2019 1,680 Well AT 7/9/2019 2,030 Well BH-V 7/2/2019 321 Well BH-V 7/2/2019 194 Well BH-V 7/2/2019 <192 Well BH-V 7/2/2019 <190 Well BH-V 8/7/2019 <182 Well BH-V 9/5/2019 211 Well BH-V 10/2/2019 <193 Well BH-V 7/2/2019 321 Well BM-V 7/3/2019 <195 Well BM-V 7/3/2019 <192 Well BM-V 7/3/2019 <194 Well BM-V 7/3/2019 <192 Well BM-V 8/7/2019 <186 Well BM-V 9/5/2019 <193 Well BM-V 10/2/2019 <193 Well BW 5/8/2019 660 Well BW 11/4/2019 636 Well BX 5/8/2019 656 Well BX 11/4/2019 350 Well BY 1/7/2019 64,700 Well BY 2/4/2019 178,000 Well BY 3/4/2019 301,000 Well BY 4/1/2019 322,000 Well BY 4/11/2019 329,000 Well BY 5/6/2019 316,000 Well BY 5/9/2019 264,000 Well BY 6/5/2019 249,000 Well BY 6/13/2019 215,000 Well BY 7/1/2019 190,000 Well BY 7/15/2019 180,000 Well BY 8/5/2019 187,000 PSEG 2019 ARERR Page 111 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well BY 9/4/2019 159,000 Well BY 10/2/2019 154,000 Well BY 11/6/2019 184,000 Well BY 12/3/2019 189,000 Well BY-V 6/7/2019 <873 Well BY-V 6/7/2019 <858 Well BY-V 6/7/2019 <834 Well BY-V 6/7/2019 <829 Well BY-V 6/7/2019 <840 Well BY-V 7/1/2019 3,040 Well BY-V 7/1/2019 1,990 Well BY-V 7/1/2019 479 Well BY-V 7/1/2019 271 Well BY-V 8/5/2019 4,400 Well BY-V 9/4/2019 6,390 Well BY-V 10/2/2019 7,200 Well BZ 5/9/2019 977 Well BZ 11/6/2019 1,030 Well CA 1/8/2019 1,480 Well CA 7/12/2019 1,470 Well DA 1/7/2019 4,170 Well DA 4/3/2019 3,970 Well DA 7/8/2019 3,830 Well DA 9/30/2019 2,720 Well DB 1/7/2019 8,220 Well DB 2/4/2019 9,090 Well DB 3/4/2019 9,200 Well DB 4/2/2019 9,330 Well DB 5/7/2019 12,200 Well DB 6/4/2019 15,900 Well DB 7/10/2019 18,400 Well DB 8/6/2019 16,400 Well DB 9/4/2019 13,900 Well DB 9/30/2019 10,300 Well DB 11/4/2019 8,910 Well DB 12/3/2019 11,400 Well DC 1/10/2019 7,090 Well DC 5/7/2019 6,130 Well DC 6/4/2019 3,740 Well DC 7/10/2019 3,190 PSEG 2019 ARERR Page 112 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well DC 8/6/2019 3,630 Well DC 9/4/2019 5,340 Well DC 9/30/2019 3,920 Well DC 11/4/2019 3,150 Well DC 12/3/2019 3,620 Well DD 1/10/2019 6,230 Well DD 4/2/2019 5,760 Well DD 7/10/2019 6,260 Well DD 9/30/2019 6,360 Well DE 1/10/2019 10,900 Well DE 4/2/2019 15,000 Well DE 7/10/2019 20,600 Well DE 9/4/2019 20,600 Well DE 9/30/2019 19,100 Well DE 11/4/2019 17,800 Well DE 12/3/2019 18,200 Well DF 1/10/2019 1,340 Well DF 7/10/2019 1,150 Well DG 1/10/2019 4,170 Well DG 4/2/2019 4,400 Well DG 7/8/2019 3,360 Well DG 9/30/2019 3,620 Well DH 1/8/2019 9,630 Well DH 4/1/2019 7,670 Well DH 7/12/2019 9,540 Well DH 10/2/2019 10,400 Well DI 1/8/2019 3,030 Well DI 4/1/2019 2,270 Well DI 7/12/2019 2,100 Well DI 10/2/2019 2,090 Well DJ 1/8/2019 1,250 Well DJ 7/12/2019 1,450 Well K 1/10/2019 <197 Well K 7/9/2019 <198 Well EOW-4L 1/9/2019 <195 Well EOW-4L 7/1/2019 <188 Well L 1/8/2019 <193 Well L 7/9/2019 <189 Well M 1/11/2019 5,430 Well M 4/3/2019 5,920 PSEG 2019 ARERR Page 113 of 116

2 0 1 9 S G S A N D H C G S A N N U AL R A D I O A C T I V E E F F L U E N T R E L E A S E R E P O R T Table 7. Tritium Analytical Results, Investigation & Monitoring Wells (cont.)

Tritium Result Well ID Sample Date (pCi/L)

Well M 7/8/2019 6,090 Well M 10/3/2019 6,580 Well N 1/7/2019 6,150 Well N 4/2/2019 5,770 Well N 7/8/2019 7,910 Well N 10/1/2019 7,120 Well O 1/8/2019 15,400 Well O 4/3/2019 39,900 Well O 7/10/2019 16,700 Well O 10/1/2019 10,200 Well P 1/9/2019 <198 Well P 7/2/2019 <189 Well R 1/8/2019 3,100 Well R 7/15/2019 3,970 Well S 1/9/2019 22,700 Well S 4/3/2019 17,800 Well S 7/9/2019 21,500 Well S 10/16/2019 10,500 Well S-V 1/9/2019 2,600 Well S-V 4/4/2019 3,090 Well S-V 7/15/2019 2,920 Well S-V 10/1/2019 3,040 Well V 1/10/2019 334 Well V 7/10/2019 291 Well W 1/10/2019 4,210 Well W 4/2/2019 4,090 Well W 7/9/2019 2,650 Well W 10/3/2019 2,340 Notes:

pCi/L Picocuries per liter AC-MT samples are collected from a mobile water tank during purge activities associated with well AC.

EOW-4L is presented as supplemental data for Well Q

< Tritium not detected above indicated concentration 545 Bolded values indicate tritium was detected 20,000 Tritium was detected above the New Jersey Department of Environmental Protection (NJDEP)

Class II-A Groundwater Quality Standard (GWQS) of 20,000 pCi/L.

PSEG 2019 ARERR Page 114 of 116

2019 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 1. Well Location Map, Hope Creek Generating Station PSEG 2019 ARERR Page 115 of 116

2019 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 2. Well Location Map, Salem Generating Station PSEG 2019 ARERR Page 116 of 116

LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)

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