LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
| ML19115A268 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 04/25/2019 |
| From: | Casulli E, Martino P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N19-0042 | |
| Download: ML19115A268 (124) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG APR 2 5 2019 Nuclear LLC TS 6.9.1.8 (Salem)
TS 6.9.1.7 (Hope Creek)
LR-N 19-0042 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
2018 Annual Radioactive Effluent Release Report (ARERR)
As required with Section 6.9.1.8 of Appendix A to Renewed Facility Operating License Nos. DPR-70 (Unit 1) and DPR-75 (Unit 2) for Salem Generating Stations (SGS), and Section 6.9.1.7 of Appendix A to Renewed Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS), PSEG Nuclear hereby transmits one (1) copy of the combined 2018 Annual Radioactive Effluent Release Report (Enclosure 1). Reports SGS RERR-66 and HCGS RERR-40 were combined into one (1) report that summarizes information pertaining to the releases of radioactive materials in liquid, gaseous, and solid form from the SGS and the HCGS for the period January 1, 2018 to December 31, 2018.
There are no regulatory commitments contained in this letter.
If you have any questions or require any additional information, please contact Mr. Rick Heathwaite at (856) 339-2076.
Sincerely,
~A. Martino Plant Manager Edward T. Casulli Plant Manager Salem Generating Stations Hope Creek Generating Station Enclosure 1: 2018 Annual Radioactive Effluent Release Report for Salem and Hope Creek Generating Stations
APR 2 fi 2019 TS 6.9.1.8 (Salem)
TS 6.9.1.7 (Hope Creek)
Page 2 LR-N19-0042 cc: Administrator, Region I, NRC NRC Project Manager, Salem NRC Project Manager, Hope Creek NRC Senior Resident Inspector, Salem NRC Senior Resident Inspector, Hope Creek Mr. J. Furia, Inspector, Region I, NRC Mr. P. Mulligan, Chief, NJ Bureau of Nuclear Engineering (NJBNE)
Mr. L. Marabella, Corporate Commitment Tracking Coordinator- w/o enclosure Mr. T. Cachaza, Salem Commitment Tracking Coordinator- w/o enclosure Ms. K. Stokes, Hope Creek Commitment Tracking Coordinator- w/o enclosure
2 0 1 8 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. Significant Events............................................................................................... 8
- 8. Changes to the Offsite Dose Calculation Manuals ............................................... 9
- 9. Changes to the Process Control Program .......................................................... 9
- 10. Radioactive Effluent Monitoring Instrumentation Out of Service for More than 30 Days ...................................................................................................... 9 A. SGS Unit 1: .................................................................................................. 9 B. SGS Unit 2................................................................................................... 9 C. HCGS:......................................................................................................... 9
- 11. Elevated Gaseous Radiation Monitor Responses ............................................ 10
- 12. Independent Spent Fuel Storage Installation (ISFSI) ....................................... 10
- 13. Effluent Trends ................................................................................................. 11
- 14. Carbon-14 in Gaseous Effluents ...................................................................... 14
- 15. Modification to Previous Radioactive Effluent Release Reports - Errata Data Section..................................................................................................... 16 IV Radiological Impact on Man.................................................................................... 17
- 1. Effluent Doses .................................................................................................... 17 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 ..................... 22
- 2. Total Dose to a Member of the Public, Resulting from Radioactive Effluent Releases and Radiation from Uranium Fuel Cycle Sources ............................... 27
- 3. Dose to Members of the Public Due to Activities Inside the Site Boundary ........ 28 APPENDIX A-1, Effluent and Waste Disposal Summary, Salem Unit 1 ........................ 31 APPENDIX A-2, Effluent and Waste Disposal Summary, Salem Unit 2 ........................ 39 i
2 0 1 8 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)
APPENDIX A-3, Effluent and Waste Disposal Summary, Hope Creek 1....................... 55 APPENDIX B, Meteorological Data ............................................................................... 71 APPENDIX C, Maximum Permissible Concentration (MPC) Data ................................. 79 APPENDIX D, 2018 Radiological Groundwater Protection Program (RGPP) Report .... 87 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) .................................. 15 Table 2 2018 Doses and Percent of the Limits from Gaseous Effluents by Operating Unit ............................................................................................... 18 Table 3 2018 Doses and Percent of the Limits from Liquid Effluents by Operating Unit ................................................................................................................ 21 Table 4 2018 Annual Average Undepleted X/Q, Depleted X/Q and D/Q and Active Exposure Pathways ....................................................................................... 23 Table 5 2018 Total Body and Critical Organ Doses at Receptor Locations Using Annual Average X/Q and D/Q Data by Operating Unit .................................. 25 Table 6 2018 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................................................................................................................. 28 Table 7 Summary of TEDE doses to Members of the Public Due to Activities inside the Site Boundary................................................................................ 29 List of Figures Figure 1 Fission and Activation Gases Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ......................................................... 11 Figure 2 Iodines Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ....................................................................................... 12 Figure 3 Particulates Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ....................................................................................... 12 Figure 4 Tritium Released in Gaseous Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ....................................................................................... 13 Figure 5 Fission and Activation Products Released in Liquid Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ............................................................. 13 Figure 6 Tritium Released in Liquid Effluents, SGS Unit 1, SGS Unit 2 and HCGS, 2005 - 2018 ................................................................................................... 14 Figure 7 Locations of Dose Calculation Receptors with 2018 Wind Rose Overlay ...... 24 ii
2 0 1 8 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 2018, the Salem Generating Station (SGS) and the Hope Creek Generating Station (HCGS) released to the environment through the radioactive liquid and gaseous effluents approximately 2.62 curies of noble gas, 0.12 curies of fission and activation products and 2,231 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 Dose 2.46E-04 0.001% 30 Noble Gas All Site Boundary mRad Beta - Air Dose 2.35E-04 < 0.001% 60 Iodine, Particulate, Bone 3.92E-01 Child 4.6 miles SW 0.87% 45 mrem C-14 & Tritium Total Body 7.58E-03 0.084% 9 0.75 mi. N Liquid Adult mrem of Salem Gi-Lli 2.10E-02 0.070% 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 5.16E-01 mrem. 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 Members of the Public and personnel not having access to the Radiologically Controlled Area (RCA) were calculated as 2.09E-02 mrem and 2.06E+00 mrem, respectively. These doses were a small fraction of the 10 CFR 20.1301 dose limit of 100 mrem.
II. Introduction This report, SGS-RERR-67/HCGS-RERR-41, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid forms from SGS and HCGS for the period January 1, 2018, to December 31, 2018.
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 PSEG 2018 ARERR Page 1 of 118
2 0 1 8 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 MW e. SGS Unit 2 achieved initial criticality on August 2, 1980, and began commercial operation on October 13, 1981.
HCGS is a General Electric Boiling Water Reactor that has an up rated core thermal power rating of 3,902 MWth 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 2018 were received and included in the report calculations. Therefore, the 2018 report is complete and no supplements to the 2018 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)
- 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:
2 0 1 8 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 rates 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.
2 0 1 8 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
- 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 2018, 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 2018, 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.
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.
2 0 1 8 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 detection requirements of Table 4.11-2 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.
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 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 decay tank or 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.
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:
2 0 1 8 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 Liquid LLD (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 Airborne LLD (uCi/cc)
Gross Alpha, Sr-89, Sr-90 1E-11 H-3 1E-06 I-131 1E-12 Principal Gamma Emitters: 1E-11 Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137,Ce-141, 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.
2 0 1 8 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 1 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 0 0 0 0 0 Planned Discharges Number of Unplanned 0 0 1 0 1 Discharges Total Curies Discharged N/A N/A 5.87E-02 N/A 5.87E-02 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 0 0 0 0 0 Planned 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)
An unplanned discharge of a 55 gallon drum of contaminated cooling water prior to chemistry approval occurred on 09/15/2018. No limits were exceeded (Notification 20804781).
SGS Unit 2 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 0 0 0 0 0 Planned 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 0 0 0 0 0 Planned 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)
2 0 1 8 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:
Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 1 0 1 1 3 Planned Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged 8.065E-03 N/A 3.33E-03 3.25E-04 1.17E-02 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Non-Routine 3 3 3 3 12 Planned Discharges Number of Unplanned 0 0 0 0 0 Discharges Total Curies Discharged 1.54E+00 1.15E+00 1.25E+00 1.82E+00 5.76E+00 N/A (Not Applicable)
- 1. Two planned non-routine discharges occurred from pumping the water collected in the roof containment berms in the first and third quarters of 2018. A third planned non-routine discharge occurred in the fourth quarter from discharging water from the dike for the Condensate Storage Tank, due to high organics in the water (Notification 20820792).
- 2. The lubricating oil ventilation system that discharges to the Turbine Building Roof had monthly (3 per quarter) release permits issued for the estimated tritium released via the airborne pathway. This is considered a non-routine planned discharge. The monthly permits were generated to account for the combined gaseous dose from the lube oil roof vents. This activity was calculated as a function of the average monthly RCS tritium concentration and the differential temperature between the lube oil system and the ambient temperature.
- 7. Significant Events SGS Unit 1 None SGS Unit 2 None HCGS An error in the calculation of total volume for a gaseous grab sample was discovered in the gamma spectroscopy software APEX. Although Chemistry entered the correct PSEG 2018 ARERR Page 8 of 118
2 0 1 8 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 dates, times and flowrate, the APEX gamma spectroscopy software used a default flowrate of 2 scfm, resulting in an incorrect total volume being calculated.
The software has been changed to allow the end flow rate to be edited and visible. In most cases, the flow rate at the start and end of the sample will be the same. The APEX software has been in use since May of 2015. This condition is believed to have occurred since that time. (Notification 20806280)
The settings of the software were changed to allow this view to be visible and therefore changeable by the user. This was verified to calculate correct sample volumes via manual calculations.
A review of all gaseous effluent permits since May of 2015 found only one permit G-20161201-127-C that was not calculated conservatively. A revision to the 2016 ARERR is contained in Section 15.
- 8. Changes to the Offsite Dose Calculation Manuals There were no changes made to either the SGS or HCGS ODCMs in 2018.
- 9. Changes to the Process Control Program There were no changes to RW-AA-100, Process Control Program for Radioactive Wastes, during 2018.
- 10. Radioactive Effluent Monitoring Instrumentation Out of Service for More than 30 Days A. SGS Unit 1:
- 1. Containment Fan Coolers - Service Water Line discharge liquid radiation monitors 1R13B was declared out of service on 2/2/2018 and returned to service on 5/1/2018 (Notification 20793185, 20786403). The detector was initially declared inoperable due to an inappropriate interpretation that the RMS was functional.
- 2. Containment Fan Coolers - Service Water Line discharge liquid radiation monitors 1R13A was declared out of service on 2/2/2018 (Notification 20786508, 20788054, 20789469, 20744766, 20789805). Notification 20784795 was written in 2017 to document that detector 1R13A was out of service due to the 22 Circ. Water Standpipe was no longer providing adequate anti vibration support to the detector. The modification that was implemented in 2017 failed within five months. The detector failed low and remained out of service for standpipe replacement. The detector was returned to service on 7/21/2018.
B. SGS Unit 2:
None C. HCGS:
- 3. Cooling Tower Blowdown liquid radiation monitor RE8817, which provides alarm only function was declared out of service on 3/30/2018 (Notification PSEG 2018 ARERR Page 9 of 118
2 0 1 8 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 20789606). The detector failed source check. Significant corrosion on and around the detector was observed. The cause of the corrosion was due to a degraded threaded fitting at the PIG head. The PIG head threads were cleaned and a new fitting was installed. Detector was replaced. A defective submersible pump was also replace. The radiation monitor was returned to service on 5/30/2018.
- 11. Elevated Gaseous Radiation Monitor Responses During the 2018 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.
- 12. 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 and personnel not having access to the Radiologically Controlled Area (RCA) was determined using the dosimetry results from the 2018 Radiological Environmental Monitoring Program (REMP) and the formula provided in ANSI/HPS N13.37-2014 as follows:
Where:
((
D2 = OF
- D1 */ )
R12 R22 )
D1 = Net Dose that was measured from TLD Location 16S2 D2 = Dose that will be extrapolated to Security Checkpoint, Sewage Treatment Plant (STP) and Critical Receptor R1 = Distance from the source to the location where D1 was obtained R2 = Distance to the location that dose will be extrapolated OF = Occupancy Factor (1 = full time, 0.25 = 2000 hrs.)
R2 D1 A B R1 (ft.) (mrem) Gross D2 (ft.) Distance Net Dose Annual Background (mrem)
Location Distance from from of TLD Dose at Dose at 16S2 OF Extrapolated Of Extrapolated ISFSI to ISFSI to 16S2 16S2 (mrem) O ccupancy Dose for Dose TLD 16S2 Location D1 = A - B (mrem) Factor Location Security 203 6,275 59.7 114.3 54.6 0.25 1.56E-02 Checkpoint STP 203 575 59.7 114.3 54.6 0.25 1.86E+00 Critical Receptor 203 24,288 59.7 114.3 54.6 1.00 4.17E-03 Nearest Resident 203 19,536 59.7 114.3 54.6 1.00 6.45E-03 PSEG 2018 ARERR Page 10 of 118
2 0 1 8 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. Effluent Trends The following trend graphs displays the total curies of liquid and gaseous effluents released for SGS and HCGS from 2005 through 2018.
Figure 1 Fision and Activation Gases Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 -
2018 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 PSEG 2018 ARERR Page 11 of 118
2 0 1 8 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 2 Iodines Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2018 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 Figure 3 Particulates Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2018 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 PSEG 2018 ARERR Page 12 of 118
2 0 1 8 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 4 Tritium Released in Gaseous Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2018 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 Figure 5 Fission and Activation Products Released in Liquid Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2018 SGS U1 SGS U2 HCGS 1.0E+00 1.0E-01 Curies 1.0E-02 1.0E-03 1.0E-04 Year PSEG 2018 ARERR Page 13 of 118
2 0 1 8 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 6 Tritium Released in Liquid Effluents, Salem Unit 1, Salem Unit 2 and Hope Creek Unit 1, 2005 - 2018 SGS U1 SGS U2 HCGS 1.0E+03 1.0E+02 Curies 1.0E+01 1.0E+00 Year
- 14. 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.
PSEG 2018 ARERR Page 14 of 118
2 0 1 8 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 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 2018 was as follows:
SGS Unit 1 10,177,507 MW he x SGS Unit 2 8,717,600 MW he x HCGS 9,546,675 MW he x Using scaling factors and the 2018 power generation data, the estimated total C-14 released in 2018 was 11.61 Ci from SGS Unit 1, 9.94 Ci from SGS Unit 2, and 16.34 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.
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) 2018.
Bone Dose from Other Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Radionuclides (mrem)
SGS Unit 1 0.00E+00 0.00E+00 0.00E+00 5.24E-09 5.24E-09 SGS Unit 2 0.00E+00 0.00E+00 0.00E+00 1.83E-07 1.83E-07 HCGS 4.05E-04 8.32E-07 2.60E-05 1.05E-05 4.42E-04 Total Bone Dose from Other 4.05E-04 8.32E-07 2.60E-05 1.07E-05 4.42E-04 Radionuclides (mrem)
Bone Dose from C-14 (mrem) Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total SGS Unit 1 2.95E-02 2.98E-02 3.02E-02 3.02E-02 1.20E-01 SGS Unit 2 2.53E-02 2.56E-02 2.58E-02 2.58E-02 1.03E-01 HCGS 4.15E-02 4.20E-02 4.24E-02 4.24E-02 1.68E-01 Total Dose from C-14 (mrem) 9.63E-02 9.74E-02 9.84E-02 9.84E-02 3.91E-01 Total Dose From All Nuclides 9.67E-02 9.74E-02 9.85E-02 9.85E-02 3.91E-01 (mrem)
Percent of dose from C-14 99.58% 100.00% 99.97% 99.99% 99.89%
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2 0 1 8 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. Errata Data Section: Modifications or Revisions Made to Previous Radioactive Effluent Release Reports A. PSEGs 2016 ARERR Tables 2A-3 and Table 2C-3 were revised to correct the curies released from one gaseous effluent permit that had underestimated the total curies due to a gamma spectroscopy software issue that was discussed in Section 7 of this report. The values that changed are bracketed in [red].
TABLE 2A-3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Facility: Hope Creek Unit 1 Period: [2016]
Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %
Total Release Ci 4.53E-01 9.89E-01 0.00E+00 0.00E+00 1.44E+00 3.400E+01 Average release rate for the period µCi/sec 5.76E-02 1.26E-01 0.00E+00 0.00E+00 4.56E-02 Gamma Air %
Percent of limit (ODCM 3.11.2.2(a)) See Table 3 on page 21 Beta Air %
B. Iodines and Halogens Total Release Ci 9.05E-04 1.05E-03 1.08E-03 4.87E-04 3.52E-03 3.00E+01 Average release rate for the period µCi/sec 1.15E-04 1.34E-04 1.35E-04 6.12E-05 1.11E-04 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- C. Particulates Particulates with half-lives > 8 days Ci 1.80E-03 9.25E-03 5.53E-03 [6.69E-06] 1.66E-02 3.00E+01 Average release rate for the period µCi/sec 2.29E-04 1.18E-03 6.95E-04 [8.41E-07] 5.24E-04 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 3.68E+01 3.67E+01 7.57E+01 3.94E+01 1.89E+02 3.10E+01 Average release rate for the period µCi/sec 4.68E+00 4.67E+00 9.52E+00 4.95E+00 5.96E+00 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- E. Carbon-14 a
Total Release Ci 4.09E+00 4.09E+00 4.13E+00 4.13E+00 1.64E+01 N/A Average release rate for the period µCi/sec 5.19E-01 5.21E-01 5.16E-01 5.19E-01 5.18E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
> 8 day half-life Percent of limit (ODCM 3.11.2.3(a)) % See Table 3 on page 21 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 21 PSEG 2018 ARERR Page 16 of 118
2 0 1 8 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 2C-3 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Facility: Hope Creek Unit 1 Period: [2016]
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 Xe-133 Ci < LLD 9.89E-01 < LLD < LLD 9.89E-01 < LLD < LLD < LLD < LLD < LLD Xe-135 Ci 4.53E-01 < LLD < LLD < LLD 4.53E-01 < LLD < LLD < LLD < LLD < LLD Total Ci 4.53E-01 9.89E-01 < LLD < LLD 1.44E+00 < LLD < LLD < LLD < LLD < LLD
- 2. Iodines and Halogens Br-82 Ci 9.82E-06 < LLD < LLD < LLD 9.82E-06 < LLD < LLD < LLD < LLD < LLD I-131 Ci 1.55E-04 2.10E-04 1.94E-04 1.07E-04 6.66E-04 < LLD < LLD < LLD < LLD < LLD I-133 Ci 7.40E-04 8.43E-04 8.81E-04 3.80E-04 2.84E-03 < LLD < LLD < LLD < LLD < LLD Total Ci 9.05E-04 1.05E-03 1.08E-03 4.87E-04 3.52E-03 < LLD < LLD < LLD < LLD < LLD
- 3. Particulates Na-24 Ci 9.67E-05 2.43E-04 7.98E-05 < LLD 4.20E-04 < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD 1.20E-06 < LLD 1.20E-06 < LLD < LLD < LLD < LLD < LLD Co-60 Ci 4.36E-05 1.62E-05 9.39E-06 6.62E-06 [7.60E-05] < LLD < LLD < LLD < LLD < LLD Y-91m Ci 1.65E-03 8.95E-03 5.44E-03 < LLD 1.60E-02 < LLD < LLD < LLD < LLD < LLD Ce-141 Ci < LLD 3.46E-05 < LLD < LLD 3.46E-05 < LLD < LLD < LLD < LLD < LLD Other Ci 1.12E-05 < LLD < LLD < LLD 1.12E-05 < LLD < LLD < LLD < LLD < LLD Total Ci 1.80E-03 9.25E-03 5.53E-03 6.62E-06 1.66E-02 < LLD < LLD < LLD < LLD < LLD
- 5. Carbon-14 Ci 4.05E+00 4.10E+00 4.14E+00 4.14E+00 1.64E+01 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.
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 EMS database program and HCGSs OpenEMS database program.
The annual doses presented in the tables below represent calculations for the four quarters of 2018. The radiological impacts from gaseous and liquid effluent discharges from SGS Units 1 and 2 and HCGS 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 PSEG 2018 ARERR Page 17 of 118
2 0 1 8 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 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 3) were calculated for the controlling locations described in the SGS and HCGS ODCMs using the methodology in the ODCMs by the SGSs EMS and the HCGS OpenEMS database programs. The dose contribution from C-14 was determined by manual calculations for SGS 1 and 2 and OpenEMS for HCGS using the methodology listed in the stations ODCMs and added to the appropriate organ from the EMS or OpenEMS printouts.
Table 2 2018 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 Gaseous Dose From Dose Limit (mrad) 5.00E+00 1.00E+01 Gamma Air Max Gamma Air Dose (mrad) 1.12E-05 1.86E-05 3.69E-05 3.22E-05 9.89E-05
% Dose Limit < 0.001% < 0.001% < 0.001% < 0.001% < 0.001%
I-131, I-133, H-3, C-14* Gaseous Dose From Noble Dose Limit (mrad) 1.00E+01 2.00E+01 Beta Air Maximum Beta Air Dose (mrad) 5.04E-06 7.74E-06 1.48E-05 1.39E-05 4.14E-05
% Dose Limit < 0.001% < 0.001% < 0.001% < 0.001% < 0.001%
and Particulate Nuclides Gas Organ Dose Limit (mrem) 7.50E+00 1.50E+01
- without ODCM Critical Receptor (mrem) 2.84E-04 1.08E-04 2.44E-04 3.38E-04 9.73E-04 C-14 with half-life > 8 Days Dose % Dose Limit 0.004% 0.001% 0.003% 0.005% 0.006%
- with ODCM Critical Receptor (mrem) 2.95E-02 2.98E-02 3.02E-02 3.02E-02 1.20E-01 C-14 Dose % Dose Limit 0.393% 0.397% 0.403% 0.403% 0.800%
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2 0 1 8 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 2018 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 From Dose Limit (mrad) 5.00E+00 1.00E+01 Gamma Air Max Gamma Air Dose (mrad) 4.57E-05 3.45E-06 3.79E-05 1.25E-05 9.96E-05
% Dose Limit < 0.001% < 0.001% < 0.001% < 0.001% < 0.001%
Dose Limit (mrad) 1.00E+01 2.00E+01 I-131, I-133, H-3, C-14* Gaseous Dose From Noble Beta Air Maximum Beta Air Dose (mrad) 1.80E-05 4.81E-06 2.03E-05 8.82E-06 5.20E-05
% Dose Limit < 0.001% < 0.001% < 0.001% < 0.001% < 0.001%
Organ Dose Limit (mrem) 7.50E+00 1.50E+01 Gas with half-life > 8 Days
- with
- without ODCM Critical Receptor (mrem) 2.17E-04 3.36E-04 3.28E-04 2.93E-04 1.17E-03 and Particulate Nuclides
% Dose Limit 0.003% 0.004% 0.004% 0.004% 0.008%
C-14 Dose C-14 Dose ODCM Critical Receptor (mrem) 2.53E-02 2.56E-02 2.58E-02 2.58E-02 1.03E-01
% Dose Limit 0.337% 0.341% 0.344% 0.344% 0.687%
HCGS Gaseous Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Gaseous Dose From Noble Dose Limit (mrad) 5.00E+00 1.00E+01 Gamma Air Max Gamma Air Dose (mrad) 0.00E+00 1.00E-08 1.72E-05 3.05E-05 4.78E-05
% Dose Limit N/A < 0.001% < 0.001% < 0.001% < 0.001%
Gas Dose Limit (mrad) 1.00E+01 2.00E+01 Beta Air Maximum Beta Air Dose (mrad) 0.00E+00 1.28E-08 5.13E-05 9.08E-05 1.42E-04
% Dose Limit N/A < 0.001% < 0.001% < 0.001% < 0.001%
Organ Dose Limit (mrem) 7.50E+00 1.50E+01 Gaseous Dose From
- with
- without ODCM Critical Receptor (mrem) 1.25E-02 5.43E-03 8.45E-03 1.40E-02 4.04E-02 I-131, I-133, H-3, C-14*
and Particulate
% Dose Limit 0.166% 0.072% 0.113% 0.187% 0.269%
Nuclides C-14 Dose C-14 Dose ODCM Critical Receptor (mrem) 4.46E-02 3.69E-02 4.16E-02 4.54E-02 1.69E-01 with half-life > 8 Days % Dose Limit 0.594% 0.492% 0.555% 0.605% 1.127%
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2 0 1 8 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 2018 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 Dose Limit (mrad) 1.50E+01 3.00E+01 Gamma Air Gaseous Dose From Max Gamma Air Dose (mrad) 5.69E-05 2.21E-05 9.20E-05 7.52E-05 2.46E-04
% Dose Limit < 0.001% < 0.001% 0.001% 0.001% 0.001%
Noble Gas Dose Limit (mrad) 3.00E+01 6.00E+01 Beta Air Maximum Beta Air Dose (mrad) 2.30E-05 1.26E-05 8.64E-05 1.14E-04 2.35E-04
% Dose Limit < 0.001% < 0.001% < 0.001% < 0.001% < 0.001%
Organ Dose Limit (mrem) 2.25E+01 4.50E+01 Gaseous Dose From with half-life > 8 Days
- with
- without ODCM Critical Receptor (mrem) 1.30E-02 5.87E-03 9.02E-03 1.47E-02 4.25E-02 I-131, I-133, H-3, C-14*
% Dose Limit 0.058% 0.026% 0.040% 0.065% 0.094%
and Particulate Nuclides C-14 Dose C-14 Dose ODCM Critical Receptor (mrem) 9.94E-02 9.23E-02 9.76E-02 1.01E-01 3.92E-01
% Dose Limit 0.442% 0.410% 0.434% 0.451% 0.871%
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.
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2 0 1 8 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 2018 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 1.50E+00 3.00E+00 (mrem)
Maximum Total Body Dose 1.30E-07 2.08E-06 1.33E-05 8.36E-06 1.06E-05 (mrem)
% Dose Limit < 0.001 < 0.001 0.001 0.001 < 0.001 Organ Dose Limit 5.00E+00 1.00E+01 (mrem)
Maximum Organ Dose 1.30E-07 2.67E-06 1.94E-05 1.38E-04 1.41E-04 (mrem)
% Dose Limit < 0.001 < 0.001 < 0.001 0.003 0.001 SGS Unit 2 Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit 1.50E+00 3.00E+00 (mrem)
Maximum Total Body Dose 4.78E-06 9.28E-06 1.81E-05 2.92E-05 4.33E-05 (mrem)
% Dose Limit < 0.001 0.001 0.001 0.002 0.001 Organ Dose Limit 5.00E+00 1.00E+01 (mrem)
Maximum Organ Dose 1.73E-05 1.11E-05 1.98E-05 1.17E-04 1.46E-04 (mrem)
% Dose Limit < 0.001 < 0.001 < 0.001 0.002 0.001 HCGS Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit 1.50E+00 3.00E+00 (mrem)
Maximum Total Body Dose 5.10E-05 7.35E-03 8.22E-05 4.46E-05 7.53E-03 (mrem)
% Dose Limit 0.003 0.490 0.005 0.003 0.251 Organ Dose Limit 5.00E+00 1.00E+01 (mrem)
Maximum Organ Dose 9.41E-05 2.02E-02 1.76E-04 1.58E-04 2.07E-02 (mrem)
% Dose Limit 0.002 0.404 0.005 0.003 0.207 PSEG 2018 ARERR Page 21 of 118
2 0 1 8 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 2018 Doses and Percent of the Limits from Liquid Effluents by Operating Unit (cont.)
SGS Units 1&2 + HCGS Site Total Liquid Effluent Parameter Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Annual Total Body Dose Limit 4.50E+00 9.00E+00 (mrem)
Maximum Total Body Dose 5.59E-05 7.36E-03 1.14E-04 8.22E-05 7.58E-03 (mrem)
% Dose Limit 0.001% 0.164% 0.003% 0.002% 0.084%
Organ Dose Limit 1.50E+01 3.00E+01 (mrem)
Maximum Organ Dose 1.12E-04 2.02E-02 2.15E-04 4.13E-04 2.10E-02 (mrem)
% Dose Limit 0.001% 0.135% 0.001% 0.003% 0.070%
C. Doses from Gaseous Effluent using Annual Average Meteorology:
As a check on the use of conservative historical meteorological dispersion (/Q) and deposition values (D/Q), the 2018 gaseous release curies (Tables 1C-1, 1C-2 and 1C-3) for each of the three units and the 2018 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 2018 Land Use Census (LUC). The receptor locations for this dose calculation were plotted with the 2018 wind rose overlay (Figure 7).
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 2018 LUC did not identify any gardens greater than 500 ft2 within five miles producing broadleaf vegetation; however, that pathway was included in the dose analysis. Using the 2018 meteorology data the calculated doses (Table 5).were lower than that reported in Table 2 that used the conservative ODCM default meteorology PSEG 2018 ARERR Page 22 of 118
2 0 1 8 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 2018 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 (1/m2) Pathways (sec./m3) (sec./m3)
Plume Immersion, HCGS Site- Boundary 1.6E-06 1.4E-06 1.1E-08 Ground Deposition, (0.5 mi N) Inhalation Plume Immersion, SGS Site-Boundary 7.3E-07 6.5E-07 4.6E-09 Ground Deposition, (0.83 mi N) Inhalation ODCM Dairy Plume Immersion, (4.9mi W) Ground Deposition, SGS 6.7E-08 5.0E-08 1.6E-10 Inhalation, Milk Ingestion HCGS 6.7E-08 5.0E-08 1.6E-10 Resident (3.7mi NW) Plume Immersion, Ground Deposition, SGS 1.4E-07 1.1E-07 5.7E-10 Inhalation HCGS 1.4E-07 1.1E-07 5.7E-10 Resident-Garden Plume Immersion, (4.4mi WSW) Ground Deposition, SGS 8.4E-08 6.3E-08 2.7E-10 Inhalation Vegetable Ingestion HCGS 8.3E-08 6.3E-08 2.7E-10 Resident-Meat Plume Immersion, (4.2mi NNE) Ground Deposition, SGS 7.5E-08 5.7E-08 2.8E-10 Inhalation, Meat Ingestion HCGS 7.4E-08 5.7E-08 2.8E-10 Resident-Garden-Meat Plume Immersion, (4.6mi SW) Ground Deposition, Inhalation, Meat SGS 8.8E-08 6.6E-08 2.8E-10 Ingestion, Vegetable HCGS 8.8E-08 6.6E-08 2.8E-10 Ingestion PSEG 2018 ARERR Page 23 of 118
2018 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 7 Locations of Dose Calculation Receptors with 2018 Wind Rose Overlay Note: Wind rose depicts fraction of time wind transports gaseous effluents from each of the sixteen compass sectors.
PSEG 2018 ARERR Page 24 of 122
2 0 1 8 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 2018 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)
Operating Excluding C-14 Including C-14 Unit Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 3.19E-03 3.17E-03 3.19E-03 3.17E-03 SGS Unit 2 3.83E-03 3.82E-03 3.83E-03 3.82E-03 HCGS 1.76E-02 1.72E-02 1.76E-02 1.72E-02 Site Total 2.46E-02 2.42E-02 2.46E-02 2.42E-02 ODCM Dairy Critical Organ Doses Inhalation, Ground Plane, Milk (4.9 mi W)
Operating Excluding C-14 Including C-14 Unit Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 6.99E-04 6.98E-04 8.02E-02 1.78E-02 SGS Unit 2 8.41E-04 8.39E-04 6.88E-02 1.55E-02 HCGS 2.31E-03 1.69E-03 1.31E-01 2.58E-02 Site Total 3.85E-03 3.23E-03 2.80E-01 5.91E-02 Nearest Resident Critical Organ Doses Inhalation, Ground Plane (3.7 mi NW)
Operating Excluding C-14 Including C-14 Unit Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 6.12E-04 6.09E-04 6.12E-04 6.09E-04 SGS Unit 2 7.35E-04 7.32E-04 7.35E-04 7.32E-04 HCGS 1.52E-03 1.49E-03 1.52E-03 1.49E-03 Site Total 2.87E-03 2.83E-03 2.87E-03 2.83E-03 Resident - Garden Critical Organ Doses Inhalation, Ground Plane, Vegetation (4.4 mi WSW)
Operating Excluding C-14 Including C-14 Unit Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 1.48E-03 1.48E-03 1.09E-01 2.33E-02 SGS Unit 2 1.78E-03 1.78E-03 9.36E-02 2.05E-02 HCGS 3.81E-03 3.55E-03 1.52E-01 3.39E-02 Site Total 7.07E-03 6.81E-03 3.55E-01 7.77E-02 PSEG 2018 ARERR Page 25 of 118
2 0 1 8 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 2018 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 Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 4.08E-04 4.07E-04 1.47E-02 3.29E-03 SGS Unit 2 4.91E-04 4.90E-04 1.26E-02 2.94E-03 HCGS 9.98E-04 9.78E-04 2.04E-02 4.93E-03 Site Total 1.90E-03 1.88E-03 4.77E-02 1.12E-02 Meat - Garden Critical Organ Doses Inhalation, Ground Plane, Meat, Vegetation 4.6 mi SW Operating Excluding C-14 Including C-14 Unit Organ Total Body Organ Total Body (mrem) (mrem) (mrem) (mrem)
SGS Unit 1 1.62E-03 1.62E-03 1.31E-01 2.80E-02 SGS Unit 2 1.95E-03 1.95E-03 1.13E-01 2.45E-02 HCGS 4.22E-03 3.94E-03 1.85E-01 4.09E-02 Site Total 7.79E-03 7.51E-03 4.29E-01 9.34E-02 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 2018 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 0.48% (Total Body) and less than 0.16% (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 8 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: 2.42E-02 Percent of Appendix I Annual Limit (5 mrem): 0.48%
Skin Dose from Noble Gases, Iodines, Particulates, H-3 and C-14: 2.43E-02 Percent of Appendix I Annual Limit (15 mrem): 0.16%
- 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 10).
The direct shine dose from the ISFSI to the Critical Receptor located at 4.6 miles in the SW sector was conservatively estimated at 4.17E-03 mrem. The doses from the gaseous and liquid radioactive effluents released from SGS Units 1 and Unit 2 and HCGS in 2018 resulted in a calculated total body and an organ dose of 9.94E-02 mrem and 4.13E-01mrem, respectively. The majority of dose was from the gaseous dose pathways from C-14. The total dose was calculated as 5.16E-01mrem, which was below the limits of 40 CFR 190 and 10 CFR 72.104. The results of this analysis are in Table 6.
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2 0 1 8 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 2018 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 (mrem) (mrem) (mrem)
Generating Station Liquid Gaseous* Liquid Gaseous*
SGS Unit 1 1.06E-05 2.49E-02 1.41E-04 1.20E-01 SGS Unit 2 4.33E-05 2.17E-02 1.46E-04 1.03E-01 HCGS 7.53E-03 4.52E-02 2.07E-02 1.69E-01 Total 7.58E-03 9.18E-02 2.10E-02 3.92E-01 Total of Liquid and 9.94E-02 4.13E-01 4.17E-01 Gaseous (mrem)
Total Dose 5.16E-01 (mrem)
- Includes C-14 dose.
- 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 <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> 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 and 0.94 miles E from the HCGS and 1.18 miles from the ISFSI. The STP workers were located about 575 feet 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.
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2 0 1 8 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 2018 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 were as follows:
Table 7 Summary of TEDE doses to Members of the Public Due to Activities Inside the Site Boundary CDE Total Body % of Limit Operating TEDE Location (Thyroid) Dose (100 mrem) per Unit mrem mrem mrem 10 CFR 20.1301 SGS U1 5.82E-04 5.82E-04 SGS U2 7.00E-04 7.00E-04 Security HCGS 1.36E-03 1.33E-03 Checkpoint ISFSI N/A 1.56E-02 Total 2.64E-03 1.82E-02 2.09E-02 0.02%
SGS U1 2.92E-02 2.92E-02 SGS U2 3.50E-02 3.50E-02 STP HCGS 3.51E-02 3.43E-02 ISFSI N/A 1.86E+00 Total 9.93E-02 1.96E+00 2.06E+00 2.06%
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 8 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 2018 ARERR Page 31 of 118
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2 0 1 8 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 .........................34 Table 1C-1 Gaseous Effluents - Ground Level Releases ...............................35 Table 2A-1 Liquid Effluents - Summation of All Releases ..............................36 Table 2B-1 Liquid Effluents .............................................................................37 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) ........................................47 Table 4A-1 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode............................................................................38 Table 4B-1 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode ...........................................................38 PSEG 2018 ARERR Page 33 of 118
2 0 1 8 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: 2018 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %
Total Release Ci 3.30E-02 4.65E-02 8.27E-02 8.70E-02 2.49E-01 3.400E+01 Average release rate for the period µCi/sec 4.24E-03 5.91E-003 1.04E-02 1.09E-02 7.89E-09 Gamma Air %
Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %
B. Iodine Total I-131 Ci < LLD < LLD < LLD < LLD < LLD 3.00E+01 Average release rate for the period µCi/sec N/A N/A N/A N/A N/A 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 µCi/sec N/A N/A N/A N/A N/A Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 5.49E+01 2.08E+01 4.70E+01 6.49E+01 1.88E+02 3.10E+01 Average release rate for the period µCi/sec 7.06E+00 2.65E+00 5.91E+00 8.16E+00 5.94E-06 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- E. C-14 a
Total Release Ci 2.86E+00 2.89E+00 2.93E+00 2.93E+00 1.16E+01 N/A Average release rate for the period µCi/sec 3.682E-01 3.682E-01 3.682E-01 3.682E-01 3.682E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
> 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 8 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: 2018 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 1.66E-02 2.79E-02 5.59E-02 4.81E-02 1.49E-01 Xe-133 Ci < LLD < LLD < LLD < LLD < LLD 1.60E-02 1.86E-02 2.68E-02 3.88E-02 1.00E-01 Xe-135 Ci < LLD < LLD < LLD < LLD < LLD 3.87E-04 < LLD < LLD < LLD 1.49E-01 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 3.30E-02 4.65E-02 8.27E-02 8.70E-02 2.49E-01
- 2. Iodines I-133 Ci < LLD < LLD < LLD 1.83E-05 1.83E-05 < LLD < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD 1.83E-05 1.83E-05 < LLD < LLD < LLD < LLD < LLD
- 3. Particulates As-76 Ci < LLD < LLD < LLD 1.81E-04 1.81E-04 < LLD < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD 1.81E-04 1.81E-04 < LLD < LLD < LLD < LLD < LLD
- 4. Tritium Ci 5.47E+01 2.05E+01 4.50E+01 6.43E+01 1.85E+02 1.61E-01 3.40E-01 1.98E+00 6.17E-01 3.10E+00
- 5. C-14 Ci 2.86E+00 2.89E+00 2.93E+00 2.93E+00 1.16E+01 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.
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2 0 1 8 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: 2018 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 <LLD 7.39E-04 2.65E-03 1.25E-02 1.59E-02 2.70E+01 alpha)
- 2. Average diluted concentration during period µCi/ml N/A 1.50E-12 5.26E-12 2.60E-11 8.15E-12
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
B. Tritium
- 1. Total List Ci 1.01E-01 4.65E+01 2.79E+02 1.53E+02 4.79E+02 2.70E+01
- 2. Average diluted concentration during period µCi/ml 2.13E-10 9.46E-08 5.53E-07 3.18E-07 2.46E-07
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
C. Dissolved & Entrained Gases
- 2. Average diluted concentration during period µCi/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 6.08E-08 < LLD 6.08E-08 2.70E+01 E. Volume Of Waste Released (prior Liters 4.26E+07 1.15E+07 4.30E+07 4.17E+07 1.39E+08 to dilution)
F. Volume Of Dilution Water Used During Liters 4.73E+11 4.91E+11 5.03E+11 4.82E+11 1.95E+12 Period N/A Not Applicable PSEG 2018 ARERR Page 36 of 118
2 0 1 8 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: 2018 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 1.01E-01 1.42E-01 1.60E-01 7.07E-02 4.74E-01 < LLD 4.63E+01 2.78E+02 1.53E+02 4.77E+02 Fission & Activation Products Cr-51 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.79E-03 1.79E-03 Mn-54 Ci < LLD < LLD 4.13E-07 < LLD 4.13E-07 < LLD < LLD 1.06E-05 6.60E-05 7.66E-05 Co-57 Ci < LLD < LLD < LLD < LLD < LLD < LLD 6.69E-06 7.99E-06 4.03E-06 1.87E-05 Co-58 Ci < LLD < LLD 3.80E-07 < LLD 3.80E-07 < LLD 6.19E-04 1.41E-03 6.40E-03 8.43E-03 Co-60 Ci < LLD < LLD 5.96E-06 < LLD 5.96E-06 < LLD 9.26E-05 9.67E-04 3.51E-03 4.57E-03 Ni-63 Ci < LLD < LLD 4.43E-05 < LLD 4.43E-05 < LLD < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD 1.37E-07 < LLD 1.37E-07 < LLD < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD 3.93E-07 < LLD 3.93E-07 < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.72E-04 4.72E-04 Zr-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.60E-04 1.60E-04 Ru-105 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 6.43E-05 6.43E-05 Cs-134 Ci < LLD < LLD 1.54E-06 < LLD 1.54E-06 < LLD 4.06E-08 < LLD < LLD 4.06E-08 Cs-137 Ci < LLD < LLD 1.28E-04 < LLD 1.28E-04 < LLD 2.01E-05 6.66E-05 1.49E-05 1.02E-04 Total for Period Ci < LLD < LLD 1.81E-04 < LLD 1.81E-04 < LLD 7.39E-04 2.47E-03 1.25E-02 1.79E-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 8 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: 2018 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 0 20 21 17 58 Total time period for batch releases (min) N/A 3090 6471 6187 15748 Maximum time period for batch release (min) N/A 524 563 561 563 Average time period for batch release (min) N/A 154 308 364 275 Minimum time period for batch release (min) N/A 3 60 213 3 Average stream flow during periods of release of effluents into a flowing stream N/A 1.59E+08 7.77E+07 7.79E+07 1.24E+08 (Lpm)
TABLE 4B-1
SUMMARY
SHEET FOR GASEOUS RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE Facility: SGS Unit 1 Period: 2018 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 83 111 164 195 553 Total time period for batch releases (min) 8208 9972 15774 21159 55113 Maximum time period for batch release (min) 170 150 185 198 198 Average time period for batch release (min) 99 90 96 109 99 Minimum time period for batch release (min) 56 30 44 14 14 PSEG 2018 ARERR Page 38 of 118
2 0 1 8 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 2018 ARERR Page 39 of 118
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2 0 1 8 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...........................43 Table 1C-2 Gaseous Effluents - Ground Level Releases ................................44 Table 2A-2 Liquid Effluents - Summation of All Releases ...............................45 Table 2B-2 Liquid Effluents ..............................................................................46 Table 3A-2 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal ............................................47 Table 4A-2 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode....................................................................................54 Table 4B-2 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode .............................................................................54 PSEG 2018 ARERR Page 41 of 118
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2 0 1 8 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: 2018 Est. Total A. Fission & Activation Gases Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %
Total Release Ci 9.81E-02 5.76E-02 1.50E-01 8.00E-02 3.86E-01 3.400E+01 Average release rate for the period µCi/sec 1.26E-02 7.33E-03 1.88E-02 1.01E-02 1.22E-02 Gamma Air %
Percent of limit (ODCM 3.11.2.2(a)) See Table 2 on page 18 Beta Air %
B. Iodine Total Iodine - 131. Ci < LLD < LLD < LLD < LLD < LLD 3.00E+01 Average release rate for the period µCi/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 4.65E-06 4.65E-06 3.00E+01 Average release rate for the period µCi/sec < LLD < LLD < LLD 5.85E-07 1.47E-07 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- Gross alpha radioactivity Ci < LLD < LLD < LLD < LLD < LLD D. Tritium Total Release Ci 4.19E+01 6.48E+01 6.32E+01 5.66E+01 2.27E+02 3.10E+01 Average release rate for the period µCi/sec 5.39E+00 8.24E+00 7.95E+00 7.12E+00 7.18E+00 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
- E. C-14 a
Total Release Ci 2.45E+00 2.48E+00 2.51E+00 2.51E+00 9.94E+00 N/A Average release rate for the period µCi/sec 3.153E-01 3.153E-01 3.153E-01 3.153E-01 3.153E-01 Percent of limit (ODCM 3.11.2.3(a)) % * * * *
> 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 2018 ARERR Page 43 of 118
2 0 1 8 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: 2018 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 6.94E-02 3.04E-03 5.22E-02 1.60E-02 1.41E-01 Kr-85m Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 3.08E-04 < LLD 3.08E-04 Kr-88 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 2.97E-04 < LLD 2.97E-04 Xe-133 Ci < LLD < LLD < LLD < LLD < LLD 2.87E-02 5.34E-02 8.43E-02 5.86E-02 2.25E-01 Xe-133m Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.67E-04 8.10E-04 9.77E-04 Xe-135 Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.24E-03 1.23E-02 4.50E-03 1.80E-02 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 9.81E-02 5.76E-02 1.50E-01 8.00E-02 3.86E-01
- 2. Iodines I-131 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD I-132 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 Cr-51 Ci < LLD < LLD < LLD 1.38E-06 1.38E-06 < LLD < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD 4.85E-08 4.85E-08 < LLD < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD 8.68E-07 8.68E-07 < LLD < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD 1.24E-06 1.24E-06 < LLD < LLD < LLD < LLD < LLD Nb-95 Ci < LLD < LLD < LLD 6.99E-07 6.99E-07 < LLD < LLD < LLD < LLD < LLD Zr-95 Ci < LLD < LLD < LLD 4.13E-07 4.13E-07 < 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 4.18E+01 6.47E+01 6.31E+01 5.65E+01 2.26E+02 6.07E-02 1.14E-01 1.32E-01 3.92E-02 3.46E-01
- 5. C-14 Ci 2.45E+00 2.48E+00 2.51E+00 2.51E+00 9.94E+00 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.
PSEG 2018 ARERR Page 44 of 118
2 0 1 8 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: 2018 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 2.77E-03 6.27E-04 6.09E-04 1.56E-02 1.96E-02 2.70E+01 alpha)
- 2. Average diluted concentration during period µCi/ml 5.68E-12 1.25E-12 1.19E-12 4.56E-11 1.06E-11
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
B. Tritium
- 1. Total Release Ci 1.05E+02 1.64E+02 3.72E+02 1.71E+02 8.12E+02 2.70E+01
- 2. Average diluted concentration during period µCi/ml 2.15E-07 3.27E-07 7.27E-07 4.98E-07 4.41E-07
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
C. Dissolved & Entrained Gases
- 3. Percent of applicable limit
% N/A N/A N/A 2.53E-08 4.72E-09 (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 1.34E+07 1.36E+07 1.39E+07 1.02E+07 5.11E+07 to dilution)
F. Volume Of Dilution Water Used During Liters 4.88E+11 5.01E+11 5.11E+11 3.43E+11 1.84E+12 Period N/A Not Applicable PSEG 2018 ARERR Page 45 of 118
2 0 1 8 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: 2018 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 < LLD 6.03E-03 < LLD 2.23E-03 8.26E-03 1.05E+02 1.64E+02 3.72E+02 1.71E+02 8.12E+02 Fission and Activation Products Mn-54 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.42E-05 4.42E-05 Cr-51 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 3.69E-04 3.69E-04 Co-57 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.72E-05 1.72E-05 Co-58 Ci < LLD < LLD < LLD < LLD < LLD 2.33E-03 4.77E-04 2.97E-04 1.11E-02 1.42E-02 Co-60 Ci < LLD < LLD < LLD < LLD < LLD 3.90E-04 1.50E-04 2.74E-04 3.82E-03 4.63E-03 Nb-95 Ci < LLD < LLD < LLD < LLD < LLD 3.19E-05 < LLD < LLD 1.64E-04 1.96E-04 Zr-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 8.30E-05 8.30E-05 Ru-105 Ci < LLD < LLD < LLD < LLD < LLD 1.90E-05 < LLD < LLD 4.86E-05 6.76E-05 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 3.41E-05 < LLD 4.42E-05 Cs-137 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.04E-06 < LLD 1.72E-05 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 2.77E-03 6.27E-04 6.09E-04 1.56E-02 1.96E-02 Dissolved and Entrained Noble Gases Xe-133 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.73E-05 1.73E-05 Total for Period Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.73E-05 1.73E-05 Note: Only radionuclides with positive activity reported in this table.
PSEG 2018 ARERR Page 46 of 118
2 0 1 8 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 Class ft3 m3 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+010 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 2018 ARERR Page 47 of 118
2 0 1 8 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 Resins, Filters and Evaporator Bottoms Waste Class All Nuclide Name Percent Abundance Curies Fe-55 3.50% 1.80E+00 Co-60 14.05% 7.21E+00 Ni-63 74.13% 3.80E+01 Cs-137 5.45% 2.79E+00 N/A Not Applicable PSEG 2018 ARERR Page 48 of 118
2 0 1 8 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)
- b. Waste Stream; Dry Active Waste Waste Volume Curies % Error 3
Class ft m3 Shipped (Activity)
A 1.10E+04 3.11E+02 2.62E+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 1.10E+04 3.11E+02 2.62E+00 +/-25%
Major Nuclides for Above Table: Percent Cutoff 1%
Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 7.58% 1.99E-01 Mn-54 1.02% 2.68E-02 Fe-55 13.45% 3.53E-01 Co-60 27.32% 7.16E-01 Ni-63 47.14% 1.24E+00 Sb-125 1.09% 2.87E-02 Cs-137 1.33% 3.49E-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 7.58% 1.99E-01 Mn-54 1.02% 2.68E-02 Fe-55 13.45% 3.53E-01 Co-60 27.32% 7.16E-01 Ni-63 47.14% 1.24E+00 Sb-125 1.09% 2.87E-02 Cs-137 1.33% 3.49E-02 N/A Not Applicable PSEG 2018 ARERR Page 49 of 118
2 0 1 8 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; 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%
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 2018 ARERR Page 50 of 118
2 0 1 8 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; Other Waste Waste Volume Curies % Error Class ft3 m3 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%
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 2018 ARERR Page 51 of 118
2 0 1 8 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; Sum of All 4 Categories Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)
A 1.17E+04 3.32E+02 1.07E+01 +/-25%
B 1.00E+02 2.83E+00 4.32E+01 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 1.18E+04 3.35E+02 5.39E+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 H-3 2.81% 3.01E-01 Fe-55 10.32% 1.11E+00 Co-58 2.06% 2.21E-01 Co-60 25.95% 2.78E+00 Ni-63 53.09% 5.69E+00 Sb-125 1.65% 1.77E-01 Cs-137 2.10% 2.25E-01 Waste Stream; Sum of All 4 Categories 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 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 3.99% 2.15E+00 Co-60 14.70% 7.92E+00 Ni-63 72.82% 3.93E+01 Cs-137 5.25% 2.83E+00 N/A Not Applicable PSEG 2018 ARERR Page 52 of 118
2 0 1 8 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 3 Hittman Transport Services, Inc. Energy Solutions Services Inc.
1560 Bear Creek Road 2 Interstate Ventures UniTech Processing Facility.
2323 Zirconium Road 1 Landstar Inway For Hittman Energy Solutions Services Inc.
1560 Bear Creek Road PSEG 2018 ARERR Page 53 of 118
2 0 1 8 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: 2018 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 18 20 23 35 96 Total time period for batch releases (min) 7801 9435 9902 13453 40591 Maximum time period for batch release (min) 563 669 1094 1290 1290 Average time period for batch release (min) 433 472 431 384 430 Minimum time period for batch release (min) 292 254 65 8 8 Average stream flow during periods of release 6.26E+07 5.31E+07 5.16E+07 2.55E+07 4.54E+07 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: 2018 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 155 125 112 113 505 Total time period for batch releases (min) 16321 11303 9514 17930 55068 Maximum time period for batch release (min) 240 240 172 1835 1835 Average time period for batch release (min) 105 90 85 158.67 110 Minimum time period for batch release (min) 56 52 55 51 51 PSEG 2018 ARERR Page 54 of 118
2 0 1 8 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 2018 ARERR Page 55 of 118
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2 0 1 8 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...........................59 Table 1C-3 Gaseous Effluents - Ground Level Releases ................................60 Table 2A-3 Liquid Effluents - Summation of All Releases ...............................61 Table 2B-3 Liquid Effluents ..............................................................................62 Table 3A-3 Solid Waste and Irradiated Fuel Shipments Solid Radwaste Shipped Offsite for Burial or Disposal ............................................61 Table 4A-3 Summary Sheet for Liquid Radioactive Effluents Released in a Batch Mode.................................................................................69 Table 4B-3 Summary Sheet for Gaseous Radioactive Effluents Released in a Batch Mode .............................................................69 PSEG 2018 ARERR Page 57 of 118
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2 0 1 8 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 µCi/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 µCi/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 µCi/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 1.34E+02 6.21E+01 9.77E+01 1.62E+02 4.56E+02 3.10E+01 Average release rate for the period µCi/sec 1.72E+01 7.90E+00 1.23E+01 2.04E+01 1.44E+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 µCi/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)) % * * * *
> 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 2018 ARERR Page 59 of 118
2 0 1 8 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: 2018 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 Xe-133 Ci < LLD < LLD 7.20E-01 1.27E+00 1.99E+00 < LLD < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD < LLD < LLD < LLD < LLD 7.69E-05 < LLD < LLD 7.69E-05 Total for Period Ci < LLD < LLD 7.20E-01 1.27E+00 1.99E+00 < LLD 7.69E-05 < LLD < LLD 7.69E-05
- 2. Iodines and Halogens I-131 Ci 1.68E-04 3.00E-05 2.20E-06 7.83E-06 2.08E-04 < LLD < LLD < LLD < LLD < LLD I-133 Ci 1.88E-03 2.15E-04 < LLD < LLD 2.09E-03 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 2.05E-03 2.45E-04 2.20E-06 7.83E-06 2.30E-03 < LLD < LLD < LLD < LLD < LLD
- 3. Particulates Na-24 Ci 1.81E-04 < LLD < LLD < LLD 1.81E-04 < LLD < LLD < LLD < LLD < LLD Mn-54 Ci 4.37E-06 < LLD 1.94E-06 < LLD 6.31E-06 < LLD < LLD < LLD < LLD < LLD Co-58 Ci 3.44E-06 < LLD < LLD < LLD 3.44E-06 < LLD < LLD < LLD < LLD < LLD Co-60 Ci 4.01E-05 < LLD 2.51E-06 < LLD 4.26E-05 < LLD < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD 2.16E-06 2.16E-06 < LLD < LLD < LLD < LLD < LLD Total for Period Ci 2.29E-04 < LLD 4.45E-06 2.16E-06 2.35E-04 < LLD < LLD < LLD < LLD < LLD
- 5. C-14 Ci 4.32E+00 3.58E+00 4.03E+00 4.40E+00 1.63E+01 < LLD < LLD < LLD < LLD < LLD Note: Only radionuclides with positive activity reported in this table.
PSEG 2018 ARERR Page 60 of 118
2 0 1 8 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: 2018 Est. Total A. Fission & Activation Products Unit Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Error %
- 1. Total Release (not including tritium, gases & alpha)
Ci 1.34E-04 7.60E-02 5.22E-04 4.78E-04 7.71E-02 2.70E+01
- 2. Average diluted concentration during period
µCi/ml 2.38E-11 1.43E-08 8.19E-11 7.77E-11 3.29E-09
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
B. Tritium
- 1. Total Release Ci 4.97E+00 3.22E+01 2.24E+01 1.06E+01 7.01E+01 2.70E+01
- 2. Average diluted concentration during period
µCi/ml 8.87E-07 6.07E-06 3.51E-06 1.72E-06 2.99E-06
- 3. Percent of applicable limit Total Body %
See Table 3 on page 21 (ODCM 3.11.1(a) & (b)) Organ %
C. Dissolved & Entrained Gases
- 1. Total Release Ci < LLD 1.14E-05 8.33E-06 3.08E-06 2.28E-05 2.70E+01
- 2. Average diluted concentration during period
µCi/ml < LLD 2.15E-12 1.31E-12 5.00E-13 9.74E-13
- 3. Percent of applicable limit
% See Table 3 on page 21 (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 to dilution)
Liters 4.84E+06 8.44E+06 1.21E+07 1.17E+07 3.71E+07 F. Volume Of Dilution Water Used During Period Liters 5.61E+09 5.29E+09 6.36E+09 6.14E+09 2.34E+10 PSEG 2018 ARERR Page 61 of 118
2 0 1 8 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: 2018 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 2.65E-01 8.14E-01 1.67E+00 1.02E+00 3.77E+00 4.71E+00 3.14E+01 2.07E+01 9.58E+00 6.64E+01 Fission and Activation Products Na-24 Ci < LLD < LLD < LLD < LLD < LLD 9.24E-08 7.68E-05 < LLD < LLD 7.69E-05 Cr-51 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.56E-03 < LLD < LLD 2.56E-03 Mn-54 Ci < LLD < LLD < LLD < LLD < LLD 8.40E-06 1.50E-02 5.83E-05 3.09E-05 1.51E-02 Fe-59 Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.02E-04 < LLD < LLD 1.02E-04 Co-57 Ci < LLD < LLD < LLD < LLD < LLD < LLD 4.85E-06 < LLD < LLD 4.85E-06 Co-58 Ci < LLD < LLD < LLD < LLD < LLD 9.70E-06 9.05E-03 8.82E-06 8.85E-06 9.08E-03 Co-60 Ci < LLD < LLD < LLD < LLD < LLD 1.00E-04 3.11E-02 4.32E-04 4.35E-04 3.20E-02 Zn-65 Ci < LLD < LLD < LLD < LLD < LLD 1.47E-05 2.66E-03 1.93E-05 3.45E-06 2.70E-03 Zr-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.28E-05 < LLD < LLD 2.28E-05 Nb-95 Ci < LLD < LLD < LLD < LLD < LLD < LLD 6.09E-05 < LLD < LLD 6.09E-05 Mo-99 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.87E-06 < LLD 1.87E-06 Tc-99m Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 1.90E-06 < LLD 1.90E-06 Sb-122 Ci < LLD < LLD < LLD < LLD < LLD < LLD 4.79E-04 < LLD < LLD 4.79E-04 Sb-124 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.87E-03 < LLD < LLD 2.87E-03 Sb-125 Ci < LLD < LLD < LLD < LLD < LLD < LLD 3.71E-04 < LLD < LLD 3.71E-04 I-131 Ci < LLD < LLD < LLD < LLD < LLD 2.99E-07 7.40E-07 < LLD < LLD 1.04E-06 Cs-134 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.57E-03 < LLD < LLD 2.57E-03 Cs-137 Ci < LLD < LLD < LLD < LLD < LLD < LLD 9.13E-03 < LLD < LLD 9.13E-03 Total for Period Ci < LLD < LLD < LLD < LLD < LLD 1.34E-04 7.60E-02 5.22E-04 4.78E-04 7.71E-02 Dissolved and Entrained Noble Gases Ar-41 Ci < LLD < LLD < LLD < LLD < LLD < LLD 9.03E-06 < LLD < LLD 9.03E-06 Xe-133 Ci < LLD < LLD < LLD < LLD < LLD < LLD < LLD 4.86E-06 3.08E-06 7.94E-06 Xe-135 Ci < LLD < LLD < LLD < LLD < LLD < LLD 2.39E-06 3.47E-06 < LLD 5.86E-06 Total for Period Ci < LLD < LLD < LLD < LLD < LLD < LLD 1.14E-05 8.33E-06 3.08E-06 2.28E-05 Note: Only radionuclides with positive activity reported in this table.
PSEG 2018 ARERR Page 62 of 118
2 0 1 8 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: 2018
- a. Waste Stream; Resins, Filters, and Evaporator Bottoms Waste Volume Curies % Error 3 3 Class ft m Shipped (Activity)
A 4.12E+03 1.17E+02 7.17E+01 +/-25%
B 0.00E+00 0.00E+00 0.00E+00 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 4.12E+03 1.17E+02 7.17E+01 +/-25%
Major Nuclides for Above Table: Percent Cutoff: 1%
Resins, Filters and Evaporator Bottoms Waste Class A Nuclide Name Percent Abundance Curies C-14 3.57% 2.57E+00 Mn-54 5.34% 3.84E+00 Fe-55 38.42% 2.76E+01 Co-60 41.64% 2.99E+01 Ni-63 5.14% 3.69E+00 Zn-65 1.37% 9.89E-01 Nb-97 1.08% 7.74E-01 Cs-137 1.71% 1.23E+00 Resins, Filters and Evaporator Bottoms Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A 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 3.57% 2.57E+00 Mn-54 5.34% 3.84E+00 Fe-55 38.42% 2.76E+01 Co-60 41.64% 2.99E+01 Ni-63 5.14% 3.69E+00 Zn-65 1.37% 9.89E-01 Nb-97 1.08% 7.74E-01 Cs-137 1.71% 1.23E+00 N/A Not Applicable PSEG 2018 ARERR Page 63 of 118
2 0 1 8 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 7.47E+03 2.11E+02 5.05E+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 7.47E+03 2.11E+02 5.05E+00 +/-25%
Major Nuclides for Above Table: Percent Cutoff: 1%
Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies Mn-54 1.85% 9.29E-02 Fe-55 68.36% 3.43E+00 Co-60 22.85% 1.15E+00 Zn-65 1.74% 8.74E-02 Nb-95 2.62% 1.32E-01 Sb-125 1.10% 5.54E-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 Mn-54 1.85% 9.29E-02 Fe-55 68.36% 3.43E+00 Co-60 22.85% 1.15E+00 Zn-65 1.74% 8.74E-02 Nb-95 2.62% 1.32E-01 Sb-125 1.10% 5.54E-02 N/A Not Applicable PSEG 2018 ARERR Page 64 of 118
2 0 1 8 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 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 2018 ARERR Page 65 of 118
2 0 1 8 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 1.15E+03 3.27E+01 4.03E-02 +/-25%
B 0.00E+00 0.00E+00 0.00E+00 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 1.15E+03 3.27E+01 4.03E-02 +/-25%
Major Nuclides for Above Table: Percent Cutoff: 1%
Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 6.89% 2.77E-03 C-14 22.68% 9.14E-03 Mn-54 1.80% 7.26E-04 Fe-55 32.85% 1.32E-02 Co-60 27.69% 1.12E-02 Ni-63 2.76% 1.11E-03 Cs-137 1.40% 5.63E-04 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 H-3 6.89% 2.77E-03 C-14 22.68% 9.14E-03 Mn-54 1.80% 7.26E-04 Fe-55 32.85% 1.32E-02 Co-60 27.69% 1.12E-02 Ni-63 2.76% 1.11E-03 Cs-137 1.40% 5.63E-04 N/A Not Applicable PSEG 2018 ARERR Page 66 of 118
2 0 1 8 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 Class ft3 m3 Shipped (Activity)
A 1.27E+04 3.61E+02 7.68E+01 +/-25%
B 0.00E+00 0.00E+00 0.00E+00 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 1.27E+04 3.61E+02 7.68E+01 +/-25%
Major Nuclides for Above Table: Percent Cutoff: 1%
Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies C-14 3.34% 2.58E+00 Mn-54 5.11% 3.93E+00 Fe-55 40.37% 3.11E+01 Co-60 40.40% 3.11E+01 Ni-63 4.82% 3.71E+00 Zn-65 1.33% 1.03E+00 Nb-95 1.01% 7.74E-01 Cs-137 1.60% 1.24E+00 Waste Class B Nuclide Name Percent Abundance Curies None N/A N/A Waste Class C Nuclide Name Percent Abundance Curies None N/A N/A Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies C-14 3.34% 2.58E+00 Mn-54 5.11% 3.93E+00 Fe-55 40.37% 3.11E+01 Co-60 40.40% 3.11E+01 Ni-63 4.82% 3.71E+00 Zn-65 1.33% 1.03E+00 Nb-95 1.01% 7.74E-01 Cs-137 1.60% 1.24E+00 N/A Not Applicable PSEG 2018 ARERR Page 67 of 118
2 0 1 8 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 Barnwell Disposal Facility 11 Hittman Transport Services, Inc.
Operated by Chem - Nuclear Systems, Inc.
Energy Solutions - BCO 2 Hittman Transport Services, Inc.
Bear Creek Operations Babcock Services, Inc.
10 R&R Trucking Oak Ridge Service Center Energy Solutions, LLC 1 Hittman Transport Services Inc Barnwell Processing Facility Barnwell Disposal Facility 6 Hittman Transport Services Inc Operated by Chem-Nuclear Systems, Inc.
Energy Solutions - GRF 2 Hittman Transport Services Inc Gallaher Road Facility Energy Solutions, LLC 4 Hittman Transport Services Inc Barnwell Processing Facility UniTech Services - ORSC 2 Tri State Motor Transit Oak Ridge Service Center UniTech Services - ORSC 1 Visionary Solutions LLC Oak Ridge Service Center PSEG 2018 ARERR Page 68 of 118
2 0 1 8 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: 2018 Liquid Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 11 76 35 12 134 Total time period for batch releases (min) 6.980E+02 5.282E+03 2.530E+03 8.630E+02 9.373E+03 Maximum time period for batch release (min) 8.500E+01 8.800E+01 8.600E+01 8.600E+01 8.800E+01 Average time period for batch release (min) 6.345E+01 6.950E+01 7.229E+01 7.192E+01 6.995E+01 Minimum time period for batch release (min) 4.700E+01 3.200E+01 4.200E+01 5.200E+01 3.200E+01 Average stream flow during periods of release 8.04E+06 1.00E+06 2.52E+06 7.13E+06 2.50E+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: 2018 Gaseous Qtr. 1 Qtr. 2 Qtr. 3 Qtr. 4 Total Number of Batch Releases 0 2 0 0 2 Total time period for batch releases (min) 0 2.153E+03 0 0 2.153E+03 Maximum time period for batch release (min) 0 1.528E+03 0 0 1.528E+03 Average time period for batch release (min) 0 1.077E+03 0 0 1.077E+03 Minimum time period for batch release (min) 0 6.250E+02 0 0 6.250E+02 PSEG 2018 ARERR Page 69 of 118
2 0 1 8 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 2018 ARERR Page 70 of 118
2 0 1 8 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 2018 ARERR Page 71 of 118
2 0 1 8 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 300 - 33 Ft. Delta Temperature January - December 2018 PSEG 2018 ARERR Page 72 of 118
2 0 1 8 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 2018 WIND LEVEL: 33 FT DELTA T: (300-33 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 6 22 40 149 95 54 43 22 10 2 443 11.25 - 33.75 NNE 2 6 15 52 174 102 57 21 22 3 0 454 33.75 - 56.25 NE 0 11 38 57 163 121 63 61 26 4 0 544 56.25 - 78.75 ENE 1 12 32 67 150 86 54 34 33 0 0 469 78.75 - 101.25 E 0 12 49 59 121 73 25 6 6 0 0 351 101.25 - 123.75 ESE 0 7 25 52 115 80 44 12 22 3 0 360 123.75 - 146.25 SE 0 12 17 35 99 161 140 118 134 21 3 740 146.25 - 168.75 SSE 0 10 15 48 133 97 89 83 91 21 1 588 168.75 - 191.25 S 0 6 23 50 110 96 68 46 37 6 1 443 191.25 - 213.75 SSW 0 6 31 45 109 99 69 53 29 9 0 450 213.75 - 236.25 SW 0 9 24 62 165 111 54 21 10 5 0 461 236.25 - 258.75 WSW 0 8 11 41 152 112 71 39 15 2 0 451 258.75 - 281.25 W 1 7 9 27 88 84 73 84 75 24 7 479 281.25 - 303.75 WNW 2 6 16 38 117 116 73 77 82 53 11 591 303.75 - 326.25 NW 0 11 19 38 103 120 116 150 131 53 15 756 326.25 - 348.75 NNW 0 7 25 33 108 97 85 78 86 30 16 565 Total 8,145 MISSING HOURS: 615 JOINT DATA RECOVERY: 93.0%
SALEM / HOPE CREEK JOINT FREQUENCY DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS JANUARY - DECEMBER 2018 WIND LEVEL: 33 FT DELTA T: (300-33 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 0.074 0.270 0.491 1.829 1.166 0.663 0.528 0.270 0.123 0.025 5.44 11.25 - 33.75 NNE 0.025 0.074 0.184 0.638 2.136 1.252 0.700 0.258 0.270 0.037 0.000 5.57 33.75 - 56.25 NE 0.000 0.135 0.467 0.700 2.001 1.486 0.773 0.749 0.319 0.049 0.000 6.68 56.25 - 78.75 ENE 0.012 0.147 0.393 0.823 1.842 1.056 0.663 0.417 0.405 0.000 0.000 5.76 78.75 - 101.25 E 0.000 0.147 0.602 0.724 1.486 0.896 0.307 0.074 0.074 0.000 0.000 4.31 101.25 - 123.75 ESE 0.000 0.086 0.307 0.638 1.412 0.982 0.540 0.147 0.270 0.037 0.000 4.42 123.75 - 146.25 SE 0.000 0.147 0.209 0.430 1.215 1.977 1.719 1.449 1.645 0.258 0.037 9.09 146.25 - 168.75 SSE 0.000 0.123 0.184 0.589 1.633 1.191 1.093 1.019 1.117 0.258 0.012 7.22 168.75 - 191.25 S 0.000 0.074 0.282 0.614 1.351 1.179 0.835 0.565 0.454 0.074 0.012 5.44 191.25 - 213.75 SSW 0.000 0.074 0.381 0.552 1.338 1.215 0.847 0.651 0.356 0.110 0.000 5.52 213.75 - 236.25 SW 0.000 0.110 0.295 0.761 2.026 1.363 0.663 0.258 0.123 0.061 0.000 5.66 236.25 - 258.75 WSW 0.000 0.098 0.135 0.503 1.866 1.375 0.872 0.479 0.184 0.025 0.000 5.54 258.75 - 281.25 W 0.012 0.086 0.110 0.331 1.080 1.031 0.896 1.031 0.921 0.295 0.086 5.88 281.25 - 303.75 WNW 0.025 0.074 0.196 0.467 1.436 1.424 0.896 0.945 1.007 0.651 0.135 7.26 303.75 - 326.25 NW 0.000 0.135 0.233 0.467 1.265 1.473 1.424 1.842 1.608 0.651 0.184 9.28 326.25 - 348.75 NNW 0.000 0.086 0.307 0.405 1.326 1.191 1.044 0.958 1.056 0.368 0.196 6.94 Total 100.00 MISSING HOURS: 615 JOINT DATA RECOVERY: 93.0%
PSEG 2018 ARERR Page 73 of 118
2 0 1 8 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 2018 PSEG 2018 ARERR Page 74 of 118
2 0 1 8 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 GROUND LEVEL RELEASE DISPERSION (X/Q) AND DEPOSITION FACTORS (D/Q)
SPECIFIC POINTS OF INTEREST Direction From Distance X/Q (Sec/M3) X/Q (Sec/M3)
Location Site (MI) No Decay Undepleted No Decay Depleted D/Q (1/M2)
Site Boundary S 0.17 1.10E-05 1.00E-05 5.80E-08 Site Boundary SSW 0.13 1.90E-05 1.90E-05 8.70E-08 Site Boundary SW 0.11 2.70E-05 2.60E-05 1.20E-07 Site Boundary WSW 0.11 2.40E-05 2.40E-05 1.00E-07 Site Boundary W 0.12 2.00E-05 1.90E-05 7.10E-08 Site Boundary WNW 0.16 1.20E-05 1.20E-05 5.10E-08 Site Boundary NW 0.28 6.60E-06 6.20E-06 4.30E-08 Site Boundary NNW 0.68 1.10E-06 1.00E-06 8.70E-09 Site Boundary N 0.83 7.30E-07 6.50E-07 4.60E-09 Site Boundary NNE 0.89 6.90E-07 6.10E-07 4.10E-09 Site Boundary NE 1.07 5.90E-07 5.10E-07 3.10E-09 Site Boundary ENE 0.88 6.80E-07 6.00E-07 4.30E-09 Site Boundary E 0.89 5.40E-07 4.80E-07 4.40E-09 Site Boundary ESE 0.24 5.20E-06 4.90E-06 4.40E-08 Site Boundary SE 0.15 1.40E-05 1.40E-05 1.10E-07 Site Boundary SSE 0.15 1.20E-05 1.20E-05 8.60E-08 Dairy & Cattle N 4.00 7.60E-08 5.90E-08 3.00E-10 Dairy & Cattle N 5.70 4.60E-08 3.40E-08 1.60E-10 Dairy & Cattle N 11.5 1.70E-08 1.10E-08 4.90E-11 Dairy & Cattle NNE 4.20 7.50E-08 5.70E-08 2.80E-10 Dairy & Cattle NNE 5.00 5.80E-08 4.30E-08 2.00E-10 Dairy & Cattle NE 3.90 9.20E-08 7.10E-08 3.20E-10 Dairy & Cattle NE 5.60 5.50E-08 4.00E-08 1.70E-10 Dairy & Cattle ENE 3.90 8.00E-08 6.10E-08 3.20E-10 Dairy & Cattle E 5.30 4.10E-08 3.00E-08 1.90E-10 Dairy & Cattle ESE 5.90 4.60E-08 3.40E-08 2.00E-10 Dairy & Cattle SE 9.50 2.70E-08 1.80E-08 1.10E-10 Dairy & Cattle SSE 9.50 2.30E-08 1.60E-08 8.50E-11 Dairy & Cattle S 5.20 5.80E-08 4.30E-08 1.90E-10 Dairy & Cattle SSW 3.90 9.70E-08 7.50E-08 3.20E-10 Dairy & Cattle SSW 8.30 3.40E-08 2.30E-08 8.50E-11 Dairy & Cattle SW 4.30 9.60E-08 7.30E-08 3.20E-10 Dairy & Cattle SW 4.60 8.80E-08 6.60E-08 2.80E-10 Dairy & Cattle WSW 4.40 8.40E-08 6.30E-08 2.70E-10 Dairy & Cattle W 4.00 8.90E-08 6.80E-08 2.40E-10 Dairy & Cattle W 4.90 6.70E-08 5.00E-08 1.60E-10 Dairy & Cattle WNW 3.40 1.10E-07 8.50E-08 3.20E-10 Dairy & Cattle WNW 8.50 3.10E-08 2.20E-08 6.50E-11 Dairy & Cattle NW 3.70 1.40E-07 1.10E-07 5.70E-10 Dairy & Cattle NNW 4.20 7.90E-08 6.10E-08 3.60E-10 Gardens N 0.57 1.30E-06 1.20E-06 8.60E-09 Gardens NNE 7.50 3.30E-08 2.30E-08 9.90E-11 Gardens NE 5.60 5.50E-08 4.00E-08 1.70E-10 Gardens ENE 5.00 5.60E-08 4.20E-08 2.00E-10 Gardens E 6.00 3.40E-08 2.50E-08 1.60E-10 Gardens ESE 6.30 4.20E-08 3.10E-08 1.70E-10 Gardens SSW 3.90 9.70E-08 7.50E-08 3.20E-10 Gardens SW 4.60 8.80E-08 6.60E-08 2.80E-10 Gardens WSW 4.40 8.40E-08 6.30E-08 2.70E-10 Gardens NW 0.58 2.00E-06 1.80E-06 1.40E-08 Gardens NW 5.40 8.60E-08 6.30E-08 2.90E-10 Gardens NNW 0.57 1.50E-06 1.30E-06 1.10E-08 PSEG 2018 ARERR Page 75 of 118
2 0 1 8 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 VENT AND BUILDING PARAMETERS:
Release Height Rep. Wind Height 0.00 10.00 (Meters) (Meters)
Building Height Diameters (Meters) 0.00 61.00 (Meters)
BLDG.MIN.CRS.SEC.
Exit Velocity 0.00 AREA (Square 3720.00 (Meters)
Meters)
Heat Emission Rate 0.00 (Cal/Sec)
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2 0 1 8 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 HOPE CREEK GROUND LEVEL RELEASE DISPERSION (X/Q) AND DEPOSITION FACTORS (D/Q)
SPECIFIC POINTS OF INTEREST DIRECTION FROM Distance X/Q (Sec/M3) No X/Q (Sec/M3)
LOCATION SITE (MI) Decay Undepleted No Decay Depleted D/Q (1/M2)
SITE BOUNDARY S 0.25 5.10E-06 4.80E-06 3.10E-08 SITE BOUNDARY SSW 0.19 9.30E-06 8.90E-06 4.80E-08 SITE BOUNDARY SW 0.17 1.30E-05 1.30E-05 6.80E-08 SITE BOUNDARY WSW 0.17 1.20E-05 1.10E-05 5.90E-08 SITE BOUNDARY W 0.18 9.70E-06 9.30E-06 4.10E-08 SITE BOUNDARY WNW 0.22 6.90E-06 6.60E-06 3.20E-08 SITE BOUNDARY NW 0.31 5.70E-06 5.40E-06 3.80E-08 SITE BOUNDARY NNW 0.55 1.50E-06 1.40E-06 1.20E-08 SITE BOUNDARY N 0.50 1.60E-06 1.40E-06 1.10E-08 SITE BOUNDARY NNE 0.63 1.10E-06 1.00E-06 7.40E-09 SITE BOUNDARY NE 0.74 9.90E-07 8.80E-07 5.80E-09 SITE BOUNDARY ENE 0.94 6.10E-07 5.40E-07 3.80E-09 SITE BOUNDARY E 0.94 5.00E-07 4.40E-07 4.00E-09 SITE BOUNDARY ESE 0.75 9.30E-07 8.30E-07 7.30E-09 SITE BOUNDARY SE 0.47 2.00E-06 1.90E-06 2.00E-08 SITE BOUNDARY SSE 0.42 2.10E-06 1.90E-06 1.80E-08 DAIRY & CATTLE N 4.00 7.60E-08 5.80E-08 3.00E-10 DAIRY & CATTLE N 5.70 4.60E-08 3.40E-08 1.60E-10 DAIRY & CATTLE N 11.50 1.70E-08 1.10E-08 4.90E-11 DAIRY & CATTLE NNE 4.20 7.40E-08 5.70E-08 2.80E-10 DAIRY & CATTLE NNE 5.00 5.80E-08 4.30E-08 2.00E-10 DAIRY & CATTLE NE 3.90 9.20E-08 7.10E-08 3.20E-10 DAIRY & CATTLE NE 5.60 5.50E-08 4.00E-08 1.70E-10 DAIRY & CATTLE ENE 3.90 8.00E-08 6.10E-08 3.20E-10 DAIRY & CATTLE E 5.30 4.10E-08 3.00E-08 1.90E-10 DAIRY & CATTLE ESE 5.90 4.60E-08 3.40E-08 2.00E-10 DAIRY & CATTLE SE 9.50 2.70E-08 1.80E-08 1.10E-10 DAIRY & CATTLE SSE 9.50 2.30E-08 1.60E-08 8.50E-11 DAIRY & CATTLE S 5.20 5.80E-08 4.30E-08 1.90E-10 DAIRY & CATTLE SSW 3.90 9.70E-08 7.50E-08 3.20E-10 DAIRY & CATTLE SSW 8.30 3.40E-08 2.30E-08 8.50E-11 DAIRY & CATTLE SW 4.30 9.60E-08 7.30E-08 3.20E-10 DAIRY & CATTLE SW 4.60 8.80E-08 6.60E-08 2.80E-10 DAIRY & CATTLE WSW 4.40 8.30E-08 6.30E-08 2.70E-10 DAIRY & CATTLE W 4.00 8.90E-08 6.80E-08 2.40E-10 DAIRY & CATTLE W 4.90 6.70E-08 5.00E-08 1.60E-10 DAIRY & CATTLE WNW 3.40 1.10E-07 8.50E-08 3.20E-10 DAIRY & CATTLE WNW 8.50 3.10E-08 2.20E-08 6.50E-11 DAIRY & CATTLE NW 3.70 1.40E-07 1.10E-07 5.70E-10 DAIRY & CATTLE NNW 4.20 7.90E-08 6.00E-08 3.60E-10 GARDENS N 0.57 1.30E-06 1.20E-06 8.60E-09 GARDENS NNE 7.50 3.30E-08 2.30E-08 9.90E-11 GARDENS NE 5.60 5.50E-08 4.00E-08 1.70E-10 GARDENS ENE 5.00 5.60E-08 4.20E-08 2.00E-10 GARDENS E 6.00 3.40E-08 2.50E-08 1.60E-10 GARDENS ESE 6.30 4.20E-08 3.10E-08 1.70E-10 GARDENS SSW 3.90 9.70E-08 7.50E-08 3.20E-10 GARDENS SW 4.60 8.80E-08 6.60E-08 2.80E-10 GARDENS WSW 4.40 8.30E-08 6.30E-08 2.70E-10 GARDENS NW 0.58 2.00E-06 1.80E-06 1.40E-08 GARDENS NW 5.40 8.60E-08 6.30E-08 2.90E-10 GARDENS NNW 0.57 1.50E-06 1.30E-06 1.10E-08 PSEG 2018 ARERR Page 77 of 118
2 0 1 8 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 VENT AND BUILDING PARAMETERS:
Release Height Rep. Wind Height 0.00 10.0 (Meters) (Meters)
Building Height Diameters (Meters) 0.00 61.8 (Meters)
BLDG.MIN.CRS.S Exit Velocity 0.00 EC.AREA 3819.0 (Meters)
(Square Meters)
Heat Emission 0.0 Rate (Cal/Sec)
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2 0 1 8 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 2018 ARERR Page 79 of 118
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2 0 1 8 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.
(µCi/ml) (µCi/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 PSEG 2018 ARERR Page 81 of 118
2 0 1 8 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.
(µCi/ml) (µCi/ml)
Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 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 PSEG 2018 ARERR Page 82 of 118
2 0 1 8 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.
(µCi/ml) (µCi/ml)
In-114m 2E-5 2E-5 In-115m 4E-4 4E-4 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 PSEG 2018 ARERR Page 83 of 118
2 0 1 8 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.
(µCi/ml) (µCi/ml)
Platinum (78) Pt-191 1E-4 1E-4 Pt-193m 1E-3 1E-3 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 PSEG 2018 ARERR Page 84 of 118
2 0 1 8 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.
(µCi/ml) (µCi/ml)
Ag-111 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 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 PSEG 2018 ARERR Page 85 of 118
2 0 1 8 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.
(µCi/ml) (µCi/ml)
U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 µCi/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 8 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 2018 Radiological Groundwater Protection Program (RGPP) Report PSEG 2018 ARERR Page 87 of 118
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2 0 1 8 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 Radiological Groundwater Protection Program (RGPP) Report Results of the Integrated Tritium Management Program With 2018 Radiological Groundwater Protection Program (RGPP)
And 2018 Monitoring Well and Remedial Action Work Plan PSEG 2018 ARERR Page 89 of 118
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2 0 1 8 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 ......................................................................................................... 93 II. Radiological Groundwater Protection Program................................................... 94
- 1. Objectives of the Radiological Groundwater Protection Program.................. 94
- 2. Sample Collection ......................................................................................... 95
- 3. New RGPP Wells .......................................................................................... 95
- 4. Sample Analysis............................................................................................ 95
- 5. Data Evaluation ............................................................................................. 95 A. Detection limits ........................................................................................ 95 B. Laboratory Measurements Uncertainty .................................................... 96
- 6. RGPP Data Quality ....................................................................................... 96 III. Discussion .......................................................................................................... 97
- 1. Groundwater Results - RGPP ....................................................................... 97 A. HCGS RGPP Wells.................................................................................. 97 B. SGS RGPP Wells .................................................................................... 98
- 3. Investigations ................................................................................................ 99 A. Groundwater Monitoring Well Data (Non-RGPP) ..................................... 99 B. Focused Remediation at Well AC ............................................................ 99 C. Past Spills and Leaks: Impacts to Groundwater .................................... 100 IV. RGPP 2019 Status ........................................................................................... 100 V. References ....................................................................................................... 100 List of Tables Table 1. RGPP Well Construction Details, HCGS ....................................................... 101 Table 2. RGPP Well Construction Details, SGS .......................................................... 102 Table 3. Well Construction Details, Investigation and Monitoring Wells .................... 103 Table 4. Relevant Groundwater Evaluation Criteria, SGS and HCGS ....................... 106 PSEG 2018 ARERR Page 91 of 118
2 0 1 8 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............................................. 107 Table 6. Tritium Analytical Results, SGS RGPP Wells ................................................. 109 Table 7. Tritium Analytical Results, Investigation & Monitoring Wells ......................... 111 List of Figures Figure 1. Well Location Map, Hope Creek Generating Station .................................... 117 Figure 2. Well Location Map, Salem Generating Station ............................................. 118 PSEG 2018 ARERR Page 92 of 118
2 0 1 8 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. Introduction This report presents results of the 2018 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.
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2 0 1 8 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 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.
II. Radiological Groundwater Protection Program This section of the annual report is prepared to summarize the status, activities, and groundwater analytical results collected in 2018 at the Site. This report also describes any changes made to the monitoring program during the 2018 reporting year.
- 1. 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.
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2 0 1 8 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. 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.
- 3. New RGPP Wells No new wells were added as part of the RGPP during 2018.
- 4. 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 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.
- 5. 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 PSEG 2018 ARERR Page 95 of 118
2 0 1 8 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 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.
- 6. 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.
- 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, PSEG 2018 ARERR Page 96 of 118
2 0 1 8 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 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.
III. 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 2018 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 2018 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 was detected in the sample collected in February 2018 (258 pCi/L), May 2018 (611 pCi/L), and November 2018 (224 pCi/L).
Tritium was not detected in the sample collected in August 2018. 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 1,650 pCi/L (August 2018) to 2,920 pCi/L (April 2018) and averaged 2,291 pCi/L, during 2018. 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 318 pCi/L (January 2018) to 374 pCi/L (November 2018). Well BM is located northwest of the reactor containment and is a sentinel (source) well for facilities and buried piping.
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2 0 1 8 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 BN: Tritium concentrations detected in well BN ranged from 474 pCi/L (August 2018) to 1,320 pCi/L (February 2018) and averaged 777 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.
- Well BO: Tritium was not detected in the sample collected in May 2018.
Detected concentrations ranged from 199 pCi/L (January 2018) to 657 pCi/L (November 2018). 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 2018.
B. SGS RGPP Wells Tritium analytical results for groundwater samples collected during 2018 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 2018, with results of 539 pCi/L and 636 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 689 pCi/L (February 2018) to 1,830 pCi/L (November 2018) and averaged 1,255 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 423 pCi/L (May 2018) to 780 pCi/L (November 2018) and averaged 548 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 248 pCi/L (November 2018) to 597 pCi/L (May 2018) and averaged 444 pCi/L. Well BE is located to the west of SGS Unit 2 reactor building and is a perimeter well.
- Well BG: Tritium was not detected in the sample collected in May 2018.
Tritium was detected at a concentration of 199 pCi/L, 259 pCi/L, and 208 pCi/L in February 2018, August 2018, and November 2018, respectively.
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2 0 1 8 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 BG is located northwest of SGS Unit 2 reactor building and is a perimeter well.
- Well U: Tritium was detected at concentrations ranging from 280 pCi/L (May 2018) to 327 pCi/L (August 2018). 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 sample collected in May 2018 (360 pCi/L) and in November 2018 (386 pCi/L). 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 2018.
- 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 2018, the mass flux within the shallow, water bearing unit and deeper groundwater was estimated to be 0.0098 Ci and 0.0074 Ci, respectively.
Therefore, the total potential estimated mass flux of tritium in groundwater reaching the Delaware River during 2018 was 0.0172 Ci. The calculated mass flux was included in Salems data tables 2A-1 and 2B-1 of this 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. 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. Focused Remediation at Well AC On April 2, 2018, PSEG resumed the focused remediation at well AC by purging, on average, approximately 550 gallons of groundwater per week.
The focused remediation continued until July 27, 2018 at which time it was PSEG 2018 ARERR Page 99 of 118
2 0 1 8 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 permanently suspended with NJDEP-BNE approval. Purged groundwater was transferred to the non-radiological liquid waste basin for release through the PSEG permitted liquid effluent outfall. During 2018 focused remediation activities, a total of approximately 9,475 gallons were purged and approximately 0.00179 curies of tritium were removed from groundwater.
C. Past Spills and Leaks: Impacts to Groundwater In 2018, there were no known active unmonitored or unevaluated releases into the groundwater at the Station.
IV. RGPP 2019 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;
- RGPP monitoring well sample frequency will be adjusted as needed based on analytical results.
V. References
Salem Generating Station, Hancocks Bridge, New Jersey.
Hope Creek Generating Station, Hancocks Bridge, New Jersey.
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 8 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 2018 ARERR Page 101 of 118
2 0 1 8 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 8 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 PSEG 2018 ARERR Page 103 of 118
2 0 1 8 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) 3 Well AH-Deep Feb-04 Sch-40 PVC 1 40.0 30.0 - 40.0 Shallow 102.70 12.78 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 PSEG 2018 ARERR Page 104 of 118
2 0 1 8 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 DG Nov-10 Sch-40 PVC 2 13.5 11.5 - 13.5 Cofferdam 98.98 9.06 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 2018 ARERR Page 105 of 118
2 0 1 8 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 2018 ARERR Page 106 of 118
2 0 1 8 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 02/05/18 < 187 Well BH 05/07/18 < 176 Well BH 08/06/18 < 194 Well BH 11/06/18 < 189 Well BI 02/05/18 258 Well BI 05/07/18 611 Well BI 08/06/18 < 194 Well BI 11/05/18 224 Well BJ 01/02/18 2,440 Well BJ 02/06/18 2,200 Well BJ 03/06/18 2,320 Well BJ 04/02/18 2,920 Well BJ 05/07/18 2,750 Well BJ 06/04/18 2,700 Well BJ 07/11/18 1,760 Well BJ 08/06/18 1,650 Well BJ 09/04/18 1,820 Well BJ 10/01/18 1,980 Well BJ 11/08/18 2,130 Well BJ 12/03/18 2,610 Well BK 05/07/18 < 180 Well BK 11/06/18 < 190 Well BL 05/07/18 < 179 Well BL 11/07/18 < 191 Well BM 01/02/18 318 Well BM 02/05/18 329 Well BM 05/07/18 322 Well BM 08/06/18 346 Well BM 11/05/18 374 Well BN 01/09/18 594 Well BN 02/06/18 1,320 Well BN 03/05/18 1,270 Well BN 04/05/18 1,020 Well BN 05/08/18 742 Well BN 06/04/18 605 Well BN 07/09/18 477 Well BN 08/06/18 474 Well BN 11/07/18 492 PSEG 2018 ARERR Page 107 of 118
2 0 1 8 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 01/09/18 199 Well BO 02/06/18 337 Well BO 05/08/18 < 173 Well BO 08/06/18 251 Well BO 11/07/18 657 Well BP 05/08/18 < 173 Well BP 11/07/18 < 196 Well BQ 02/06/18 < 181 Well BQ 05/10/18 < 173 Well BQ 08/07/18 < 193 Well BQ 11/05/18 < 195 Well BR 05/09/18 < 175 Well BR 11/07/18 < 188 Well BS 05/09/18 < 177 Well BS 11/07/18 < 195 Well BT 04/05/18 < 190 Well BT 05/08/18 < 175 Well BT 11/07/18 < 194 Notes:
pCi/L Picocuries per liter
< Tritium not detected above indicated concentration 251 Bolded values indicate tritium was detected PSEG 2018 ARERR Page 108 of 118
2 0 1 8 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 05/09/18 539 Well AL 11/08/18 636 Well BA 05/11/18 < 198 Well BA 11/08/18 < 195 Well BB 05/11/18 < 197 Well BB 11/08/18 < 192 Well BC 02/06/18 689 Well BC 05/10/18 1,370 Well BC 08/07/18 1,130 Well BC 11/08/18 1,830 Well BD 02/05/18 455 Well BD 05/09/18 423 Well BD 08/07/18 533 Well BD 11/07/18 780 Well BE 02/05/18 436 Well BE 05/11/18 597 Well BE 08/08/18 495 Well BE 11/07/18 248 Well BF 05/11/18 < 190 Well BF 11/07/18 < 193 Well BG 02/06/18 199 Well BG 05/08/18 < 193 Well BG 08/06/18 259 Well BG 11/08/18 208 Well BU 05/08/18 < 187 Well BU 11/07/18 < 196 Well T 02/05/18 < 183 Well T 05/10/18 < 184 Well T 08/08/18 < 196 Well T 11/07/18 < 197 Well U 02/05/18 281 Well U 05/09/18 280 Well U 08/07/18 327 Well U 11/08/18 322 Well Y 05/11/18 < 186 Well Y 11/08/18 < 196 PSEG 2018 ARERR Page 109 of 118
2 0 1 8 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 05/11/18 360 Well Z 11/08/18 386 Notes:
pCi/L Picocuries per liter
< Tritium not detected above indicated concentration 322 Bolded values indicate tritium was detected PSEG 2018 ARERR Page 110 of 118
2 0 1 8 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 01/10/18 1,350 Well AA 07/09/18 1,090 Well AA-V 01/10/18 806 Well AA-V 04/04/18 < 191 Well AA-V 07/09/18 724 Well AA-V 10/04/18 1,730 Well AB 01/02/18 11,400 Well AB 04/04/18 8,660 Well AB 07/11/18 7,450 Well AB 10/04/18 6,120 Well AC 01/09/18 33,600 Well AC 02/06/18 26,000 Well AC 03/06/18 21,100 Well AC 04/05/18 60,400 Well AC 05/10/18 45,200 Well AC 06/05/18 48,100 Well AC 07/11/18 46,500 Well AC 08/07/18 21,600 Well AC 09/04/18 15,800 Well AC 10/02/18 17,500 Well AC 11/07/18 31,700 Well AC 12/03/18 38,700 Well AC-MT* 04/13/18 55,500 Well AC-MT* 07/27/18 36,300 Well AD 01/02/18 13,900 Well AD 04/04/18 13,500 Well AD 07/11/18 12,800 Well AD 10/04/18 12,300 Well AE 01/11/18 5,210 Well AE 04/02/18 13,300 Well AE 06/04/18 10,200 Well AE 07/11/18 9,720 Well AE 10/04/18 5,700 Well AF 01/10/18 < 190 Well AF 07/12/18 207 Well AF-V 01/10/18 < 163 Well AF-V 04/02/18 < 192 PSEG 2018 ARERR Page 111 of 118
2 0 1 8 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-AF-V 07/12/18 < 198 Well-AF-V 10/01/18 501 Well AG-D 01/10/18 1,110 Well AG-D 07/12/18 697 Well AG-S 01/10/18 229 Well AG-S 08/08/18 456 Well AH-D 01/10/18 701 Well AH-D 07/10/18 454 Well AH-S 01/10/18 2,840 Well AH-S 02/06/18 2,970 Well AH-S 03/06/18 1,830 Well AH-S 07/10/18 864 Well AI 01/08/18 4,050 Well AI 07/09/18 4,010 Well AM 01/09/18 6,570 Well AM 04/05/18 8,390 Well AM 07/02/18 11,800 Well AM 10/02/18 11,000 Well AN 01/02/18 19,100 Well AN 02/05/18 21,300 Well AN 03/06/18 16,800 Well AN 04/04/18 17,600 Well AN 05/24/18 12,000 Well AN 06/06/18 14,700 Well AN 07/11/18 16,800 Well AN 08/08/18 14,300 Well AN 09/04/18 13,600 Well AN 10/04/18 13,000 Well AN 11/08/18 13,500 Well AN 12/03/18 13,500 Well AP 01/08/18 1,400 Well AP 07/10/18 1,360 Well AR 01/11/18 9,460 Well AR 04/02/18 5,490 Well AR 07/10/18 5,260 Well AR 10/03/18 5,900 Well AS 01/08/18 15,600 Well AS 07/11/18 11,800 Well AT 01/02/18 2,250 Well AT 07/11/18 1,770 PSEG 2018 ARERR Page 112 of 118
2 0 1 8 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 BW 05/10/18 847 Well BW 11/08/18 943 Well BX 05/10/18 839 Well BX 11/08/18 503 Well BY 01/02/18 26,900 Well BY 02/05/18 71,300 Well BY 03/05/18 95,800 Well BY 04/02/18 110,000 Well BY 04/05/18 106,000 Well BY 05/07/18 90,600 Well BY 06/04/18 89,500 Well BY 07/02/18 77,500 Well BY 08/06/18 66,900 Well BY 09/04/18 43,600 Well BY 10/01/18 34,700 Well BY 11/05/18 37,800 Well BY 12/03/18 30,200 Well BZ 01/09/18 2,050 Well BZ 02/06/18 1,050 Well BZ 03/06/18 839 Well BZ 04/02/18 845 Well BZ 05/07/18 835 Well BZ 06/04/18 864 Well BZ 07/11/18 950 Well BZ 11/08/18 836 Well CA 01/03/18 2,270 Well CA 07/03/18 1,950 Well DA 01/09/18 3,640 Well DA 04/03/18 3,340 Well DA 07/02/18 2,810 Well DA 10/01/18 2,860 Well DB 01/09/18 4,460 Well DB 04/05/18 3,790 Well DB 07/02/18 4,610 Well DB 10/02/18 13,500 Well DB 11/07/18 10,800 Well DB 12/03/18 9,260 Well DC 01/09/18 2,330 Well DC 07/02/18 1,140 Well DD 01/09/18 6,580 PSEG 2018 ARERR Page 113 of 118
2 0 1 8 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 DD 04/05/18 6,790 Well DD 07/02/18 6,510 Well DD 10/03/18 7,230 Well DE 01/09/18 12,900 Well DE 04/05/18 13,400 Well DE 07/02/18 12,300 Well DE 10/03/18 11,700 Well DF 01/09/18 1,560 Well DF 07/02/18 1,460 Well DG 01/13/18 3,230 Well DG 04/03/18 3,050 Well DG 07/03/18 3,220 Well DG 10/01/18 2,940 Well DH 01/03/18 9,630 Well DH 04/03/18 8,820 Well DH 07/03/18 10,500 Well DH 10/03/18 10,600 Well DI 01/03/18 2,550 Well DI 04/03/18 2,240 Well DI 07/03/18 1,880 Well DI 10/03/18 1,750 Well DJ 01/03/18 1,240 Well DJ 07/03/18 1,030 EOW-4L 01/09/18 < 192 EOW-4L 07/09/18 < 186 Well K 01/02/18 1,970 Well K 02/06/18 < 182 Well K 03/06/18 < 174 Well K 04/03/18 < 177 Well K 07/09/18 < 190 Well L 01/11/18 < 191 Well L 07/09/18 < 194 Well M 01/10/18 4,750 Well M 04/04/18 10,200 Well M 07/09/18 8,330 Well M 10/03/18 8,250 Well N 01/09/18 10,600 Well N 04/05/18 8,000 Well N 07/02/18 10,000 PSEG 2018 ARERR Page 114 of 118
2 0 1 8 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 N 10/02/18 6,240 Well O 01/11/18 6,620 Well O 04/02/18 35,300 Well O 06/04/18 10,800 Well O 07/11/18 3,380 Well O 10/04/18 6,500 Well P 01/10/18 < 192 Well P 07/02/18 < 189 Well R 01/09/18 2,830 Well R 07/09/18 3,330 Well S 01/02/18 7,940 Well S 04/06/18 7,930 Well S-V 01/11/18 1,450 Well S-V 04/04/18 1,490 Well S-V 07/10/18 1,200 Well S-V 10/04/18 2,830 Well T 02/05/18 < 183 Well T 05/10/18 < 184 Well T 08/08/18 < 196 Well T 11/07/18 < 197 Well U 02/05/18 281 Well U 05/09/18 280 Well U 08/07/18 327 Well U 11/08/18 322 Well V 01/10/18 285 Well V 07/03/18 313 Well V 10/01/18 338 Well W 01/08/18 6,770 Well W 04/04/18 3,280 Well W 07/09/18 3,450 Well W 10/03/18 4,730 PSEG 2018 ARERR Page 115 of 118
2 0 1 8 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 Y 05/11/18 < 186 Well Y 11/08/18 < 196 Well Z 05/11/18 360 Well Z 11/08/18 386 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 313 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 2018 ARERR Page 116 of 118
2018 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 1. Well Location Map, Hope Creek Generating Station PSEG 2018 ARERR Page 117 of 118
2018 SGS AND HCGS RADIOACTIVE EFFLUENT RELEASE REPORT Figure 2. Well Location Map, Salem Generating Station PSEG 2018 ARERR Page 118 of 118