ML21118A878

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Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report 63 January 1, 2020 Through December 31, 2020
ML21118A878
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/29/2021
From: Henry D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
CCN 21-33
Download: ML21118A878 (216)
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Text

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=' Exelon Generation~

April 29, 2021 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Peach Bottom Atomic Power Station Units 1, 2 and 3 Independent Spent Fuel Storage Installation (ISFSI)

Facility Operation License DPR-12, DPR-44 and DPR-56 NRC Docket 50-171, 50-277 and 50-278 and ISFSI Docket 72-29 Annual Radioactive Effluent Release Report 63 January 1, 2020 through December 31, 2020 Enclosed is the Annual Radioactive Effluent Release Report 63, January 1, 2020 through December 31, 2020 for Peach Bottom Atomic Power Station, Units 1, 2 and 3.

This report is being submitted in compliance with 10 CFR 50.36a(2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56 and to fulfill the requirements of Offsite Dose Calculation Manual Specifications (ODCMS) 3.10.2. Additionally, this report is submitted to satisfy the annual effluent reporting requirements for the ISFSI required by the ODCM.

The ODCM was revised once during the 2020 reporting period. The revision is attached in Appendix A.

If you have any questions or require additional information, please do not hesitate to contact Dani Brookhart at 717-456-3056.

Sincerely, David A. Henry, Plant Manager Peach Bottom Atomic Power Station DAH/SMO/MKR/T JH/DMJ/DLB Enclosure (1)

Cc: Regional Administrator - NRC Region 1 NRC Senior Resident Inspector - Peach Bottom Atomic Power Station CCN 21-33

PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 Unit Number 1 Docket Number 50-171 PBAPS Independent Spent Fuel Storage Installation Docket Number 72-29 RADIOACTIVE EFFLUENT RELEASE REPORT NO. 63 JANUARY 1, 2020 THROUGH DECEMBER 31, 2020 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC (This page intentionally left blank) 2

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC TABLE OF CONTENTS INTRODUCTION ...................................................................................................................................... 5 ATTACHMENT 1: SUPPLEMENTAL INFORMATION ................................................................................. 7 Regulatory Limits ...................................................................................................................... 8 Maximum Permissible Concentrations..................................................................................... 8 Average Energy ......................................................................................................................... 9 Minimum Detectable Concentrations ...................................................................................... 9 Measures and Approximations of Total Radioactivity .............................................................. 9 Decommissioned Unit 1 Liquid Radioactive Waste Processing .............................................. 10 Batch Releases ........................................................................................................................ 11 Average Stream Flow .............................................................................................................. 11 Abnormal or Unplanned Releases .......................................................................................... 12 Liquid Releases ....................................................................................................................... 12 Gaseous Releases ................................................................................................................... 13 Missed Sampling ..................................................................................................................... 14 Radiation Monitors Out of Service for Greater than 30 days ................................................. 14 Changes to the ODCM ............................................................................................................ 14 Violations .............................................................................................................................. 144 Dose Assessment .................................................................................................................. 155 Introduction.......................................................................................................................... 155 Liquid Dose Assessment ....................................................................................................... 155 Gaseous Dose Assessment ................................................................................................... 166 ATTACHMENT 2: EFFLUENT

SUMMARY

............................................................................................. 188 Gaseous Effluents - Summation of All Releases ...................................................................... 19 Gaseous Effluents Release Point: Elevated (Main Offgas Stack) ........................................... 200 Gaseous Effluents Release Point: Ground-Level (Units 2 and 3 Reactor Building Exhaust Vents and Abnormal Releases) ............................................................................................. 211 Liquid Effluents - Summation of All Releases ........................................................................ 222 Liquid Effluents Release Points - Liquid Radwaste, RHR Leaks and Groundwater ............... 233 ATTACHMENT 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ................................................ 244 Solid Waste Shipped ............................................................................................................. 255 Irradiated Fuel Shipments..................................................................................................... 277 Changes to Process Control Program (PCP) .......................................................................... 277 3

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 4: RADIOLOGICAL IMPACT ON MAN .......................................................................... 288 Radiological Impact on Man ................................................................................................... 29 40 CFR 190 Doses.................................................................................................................... 29 ATTACHMENT 5: METEOROLOGICAL DATA ....................................................................................... 300 APPENDIX A: ODCM REV 1887 Technical Concurrence (for accuracy of information):

Manager, Site Chemistry and Radwaste Date 4

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC INTRODUCTION In accordance with the Reporting Requirements of Technical Specification 5.6.3 applicable during the reporting period, January 1, 2020 through December 31, 2020, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station (PBAPS) Units 1, 2, 3, and ISFSI.

The release of radioactive materials during the reporting period was within the Offsite Dose Calculation Manual Specification (ODCMS) limits. The notations E+ and E- are used to denote positive and negative exponents to the base 10, respectively.

In addition to the normal effluent releases from Units 2 and 3, there were three types of abnormal releases of liquid low-level radioactive material. One from leaking Residual Heat Removal (RHR) heat exchangers, one from releasing contaminated water in the auxiliary boilers, and the last from groundwater tritium contamination ('tritium plume'). These releases were far below regulatory limits.

In addition to the normal effluent releases from Units 2 and 3, there were two abnormal releases of gaseous radioactive material during 2020. The first release was from steam being vented during operation of auxiliary boilers containing low levels of radioactivity. The other release was from positive pressure at an exit doorway on 165 Turbine Building, which was maintained open due to COVID-19. During part of that time, air samples showed detectable isotopic activity.

For all gaseous releases from Units 2 and 3, the maximum calculated organ dose (bone) from iodines (I-131, I-133 and I-135), tritium (H-3), carbon-14 (C-14) and particulates to any individual was 1.40E-01 mrem, which was approximately 4.70E-01% of the annual limit. The maximum calculated air dose in the unrestricted area due to noble gas effluents was 1.60E-01 mrad (gamma) and 1.09E-01 mrad (beta), which was 5.34E-01% and 1.81E-01%, respectively, of the annual limits.

In 2020, there were no direct gaseous or liquid releases or discharges from Unit 1 to the environment. Additionally, there were no gaseous or liquid radioactive releases from the Independent Spent Fuel Storage Installation, NRC Docket No. 72-29 (ISFSI).

No changes were made to RW-AA-100 "Process Control Program for Radioactive Waste" in the 2020 reporting period. There was one revision to the ODCM and the Appendix A during the 2020 reporting period to add new locations for Assessment of Public Dose.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Exelon Nuclear common procedures, which provide consistent expectations and standards for Radioactive Effluents Controls Program (RECP), were used to generate this report. PBAPS site specific procedures used to calculate abnormal/unplanned releases were also used to generate this report. They are:

CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Programs CY-AA-170-100, Radiological Environmental Monitoring Program CY-AA-170-200, Radioactive Effluent Controls Program CY-AA-170-300, Offsite Dose Calculation Manual Administration CY-AA-170-2000, Annual Radioactive Effluent Release Report CY-AA-170-2100, Estimated Errors of Effluent Measurement CY-AA-170-2300, Determination of Carbon-14 in Gaseous Effluents CY-AA-170-3100, Offsite Dose Calculation Manual Revisions CY-PB-170-202, RHR HPSW Leak Rate Calculation CY-PB-170-2020, Radiological Abnormal Gaseous Release Assessment CY-PB-170-210, Gaseous Dose and Dose Rate Calculation CY-PB-170-2000, Annual Radioactive Effluent Release Report CY-PB-170-2300, OpenEMS Effluent Management System Implementation Peach Bottom Atomic Power Station, Offsite Dose Calculation Manual Peach Bottom Atomic Power Station, ODCM Appendix A, Radioactive Effluents Control Program, containing ODCM Specifications and Bases 6

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 1: SUPPLEMENTAL INFORMATION 7

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Regulatory Limits Table 1. Noble Gas Dose Rate and Dose Limits Maximum Value Units Limit Classification Specification 500 mrem/ yr annual total body dose rate ODCM Specification 3.8.C.1.a 3000 mrem/ yr annual skin dose rate ODCM Specification 3.8.C.1.a 10 mrad gamma radiation in air dose per quarter ODCM Specification 3.8.C.2.a 20 mrad beta radiation in air dose per quarter ODCM Specification 3.8.C.2.b 20 mrad gamma radiation in air dose per year ODCM Specification 3.8.C.2.c 40 mrad beta radiation in air dose per year ODCM Specification 3.8.C.2.d Table 2. Iodines, Tritium and Particulates (with half-lives >8 days) Dose Rate and Dose Limits Maximum Units Limit Classification Specification Value 1500 mrem/ yr annual dose rate limit to any organ ODCM Specification 3.8.C.1.b 15 mrem dose limit to any organ per quarter ODCM Specification 3.8.C.3.a 30 mrem dose limit to any organ per year ODCM Specification 3.8.C.3.b Table 3. Liquid Effluent Activity Concentration and Dose Rate Limits Maximum Value Units Limit Classification Specification 10 times 10 CFR 20, Appendix B, Table 2, µCi/ mL Activity Concentration in all liquid releases ODCM Specification 3.8.B.1.a Column 2 total activity concentration for all dissolved and 2E-04 µCi/ mL ODCM Specification 3.8.B.1.b entrained noble gases 3 mrem total body dose limit per quarter ODCM Specification 3.8.B.2.a 10 mrem dose limit per quarter to any organ ODCM Specification 3.8.B.2.a 6 mrem total body dose limit per year ODCM Specification 3.8.B.2.b 20 mrem dose limit to any organ per year ODCM Specification 3.8.B.2.b Maximum Permissible Concentrations Gaseous dose rates, rather than effluent concentrations, are used to calculate permissible release rates for gaseous releases. The maximum permissible dose rates for gaseous releases are defined in ODCMS 3.8.C.1.a and 3.8.C.1.b.

The Effluent Concentrations Limits (ECL) specified in 10 CFR 20, Appendix B, Table 2, Column 2 multiplied by 10, for identified nuclides, are used to calculate permissible release rates and concentrations for liquid release per ODCMS 3.8.B.1.

The total activity concentration for all dissolved or entrained noble gases is limited to < 2E-04

µCi/mL (ODCMS 3.8.B.1.b).

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Average Energy The PBAPS ODCM limits the 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 3000 mrem/year to the skin. Therefore, the average beta and gamma energies of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 1.21, Revision 1, "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," are not applicable to PBAPS.

Minimum Detectable Concentrations If a radionuclide was not detected, "<LLD" was reported as the activity. Samples were analyzed with techniques that achieved the required Lower Limits of Detection (LLD) specified in ODCMS Table 4.8.B.1, "Radioactive Liquid Waste Sampling and Analysis" (for liquids) or ODCMS Table 4.8.C.1, "Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stacks" (for gases). In all cases, the LLD requirements were satisfied.

Measures and Approximations of Total Radioactivity Fission and Activation Gases The method used for gamma isotopic analysis is the Canberra GenieTM System with a gas marinelli beaker. Grab samples are taken and analyzed weekly to determine the isotopic mixture of noble gas activity released for the week. Airborne effluent gaseous activity was continuously monitored and recorded in accordance with ODCMS Table 4.8.C.1. The data from the noble gas radiation monitor were analyzed to report noble gas effluent activities. When no activity was identified in the grab isotopic analysis (un-id(s) or un-id(v)), the entire release must be assumed to be the radionuclide with the most-limiting dose factors for the release pathway (i.e. krypton-88 (Kr-88) for all ground-level releases, Kr-88 for elevated gamma dose and Kr-87 for elevated beta dose; see ODCM IV.B and NUREG-01331). The activity released is listed as "unidentified" in this reports Attachment 2 Tables. If activity was found in the grab isotopic analysis, the isotopic mixture for the Noble Gas Monitor was determined from that isotopic mixture.

Iodines The method used is the Canberra GenieTM System with a charcoal cartridge. Iodine activity was continuously sampled and analyzed in accordance with ODCMS Table 4.8.C.1.

Particulates The method used is the Canberra GenieTM System with a particulate filter (47 mm diameter).

Particulate activity was continuously sampled and analyzed in accordance with ODCM Table 4.8.C.1.

Composite particulate air samples were submitted to an offsite vendor laboratory for analyses of strontium-89 (Sr-89), Sr-90, nickel-63 (Ni-63) and gross alpha.

1 NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications," October 1978.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Carbon-14 The amount of C-14 released was estimated using the guidance from the Electric Power Research Institute (EPRI) Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". The C-14 was released primarily through the Main Offgas Stack (9.70E+01%)

with a small amount (3.00E+00%) through the Reactor Building Exhaust Vents. The C-14 in liquid effluents is not a significant dose pathway, as determined from studies.

Liquid Effluents Gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release using the Canberra GenieTM System in accordance with ODCMS Table 4.8.B.1. The total activity of a released batch is determined by multiplying each nuclide's concentration by the total volume discharged.

Composite liquid radwaste samples are analyzed for tritium on-site and submitted to an offsite vendor laboratory for analyses of iron-55 (Fe-55), phosphorus-32 (P-32), Sr-89, Sr-90, Ni-63, and gross alpha.

Estimate of Total Error Present CY-AA-170-2100, "Estimated Errors of Effluent Measurements", provides the methodology to obtain an overall estimate of the error associated with radioactive effluents, which are listed in of this report.

Decommissioned Unit 1 Liquid Radioactive Waste Processing There were no direct gaseous or liquid releases or discharges from Unit 1 to the environment during 2020. However, during the reporting period, a total of 119 gallons of water with low concentrations of H-3 were collected from Unit 1 and stored at Unit 2 and 3, for processing in a future year. No gamma emitting nuclides were identified above detectable limits in the U1 water collected from the containment or containment sump. During the reporting period, there was one release of Unit 1 water through the Unit 2 and Unit 3 liquid radwaste system. These releases included all U1 water drummed in 2019, (339.6 gallons), and three of the drums from 2020 (119 gallons). The permitted liquid effluent doses for all the Unit 1 water released through the Unit 2 and Unit 3 liquid radwaste system was 1.01E-08 mrem to the child total body and 1.01E-08 mrem to the child lung, 3.36E-07% and 1.68E-07% of quarterly ODCM limit, respectively.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Batch Releases Table 4. Quarterly Liquid Batch Release Statistics First Quarter Second Quarter Third Quarter Fourth Quarter Number of Batch 3* 4 2 8 Releases Total Time for Batch 8.75E+02 3.70E+02 5.80E+01 8.44E+02 Releases (minutes)

Maximum time period for batch release 7.30E+02 1.35E+02 4.30E+01 1.42E+02 (minutes)

Average time period for batch release 2.92E+02 9.25E+01 2.90E+01 1.05E+02 (minutes)

Minimum time period for batch release 6.50E+01 4.00E+01 1.50E+01 3.50E+01 (minutes)

Average Stream Flow 3 2,3 5.58E+04 5.09E+04 8.10E+03 2.39E+04 (ft / s)

Dilution volume 3.42E+09 1.68E+09 2.64E+08 2.47E+09 (liters)

  • Includes one abnormal release from contaminated auxiliary boiler Table 5. Quarterly Gaseous Batch Release Statistics First Quarter Second Quarter Third Quarter Fourth Quarter Number of batch 3* 1^ 0 0 releases:

Total Time for batch 1.80E+04 2.19E+03 0 0 releases (minutes)

Maximum time period for batch release 1.71E+04 2.19E+03 0 0 (minutes)

Average time period for batch release 5.99E+03 2.19E+03 0 0 (minutes)

Minimum time period for batch release 1.45e+02 2.19E+03 0 0 (minutes)

  • Includes two abnormal releases from contaminated auxiliary boiler and one from 165 RAMP positive ventilation

^ abnormal release from 165 RAMP positive ventilation Average Stream Flow The river flow is not used for dose calculations. The actual flow rate of Circulation Water (the water that is circulated within the plant for cooling) is determined for each liquid effluent release because this Circulation Water provides dilution and therefore reduces the projected dose.

2 Average Stream Flow is not used for dose calculation.

3 USGS National Water Information System, Site Name: "Susquehanna River at Marietta, PA", Site Number:

01576000. Data accessed 24 March 2020.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Abnormal or Unplanned Releases

'Abnormal' releases are those releases that are not defined as 'normal' releases in the Licensee's ODCM. Systems with a potential for an unplanned release are monitored to ensure if a release were to occur it would be identified and quantified appropriately. Source terms used for dose calculations utilize direct sampling and the maximum concentrations of nuclides to ensure that the most conservative and bounding estimates are used. Methodologies calculate conservative dose utilizing conservative mathematical models to describe intake and exposure pathways. Therefore, reported doses for these abnormal releases are calculated conservatively.

Liquid Releases Groundwater Tritium Plume During 2020, during the sampling and analysis for the Radiological Ground Water Protection Program (RGPP), tritium was measured at several locations around the site. The ground water that has detectable tritium has been determined to flow into the plant intake where it mixes with cooling water from the river, flows through plant systems and into the normal discharge canal. Details of this program can be found in the Peach Bottom Annual Radiological Environmental Operating Report (AREOR) as an appendix. No other nuclides were detected in monitoring wells.

Analysis of Release It was assumed from the maximum flow rates measured, that ground water flowed to the discharge canal at a steady rate of 3.44E+02 gpm, carrying with it some of the tritium underneath the plant. The ground water flow rate was updated in April 2017, when the new report was provided4. The conservative maximum dose for the entire year from this continuous release is calculated to be 5.74E-05 mrem (to the whole-body) and 5.74E-05 mrem (to any organ, except bone5 which is 0.00E+00 mrem)6. This dose contribution projection is well below the limit specified in the ODCM.

Heat Exchanger Leakage On November 13, 2018 a small leak developed in the Unit 2 'B' RHR. The RHR system is designed to circulate water to remove heat from the reactor unit when necessary by using a heat exchanger with river water as the cooling medium. The dose model assumes that contaminated torus water leaks into the river water running through the heat exchanger, regardless of operating pressure to ensure conservatism in calculated dose. As an additional precaution, installed radiation monitoring instrumentation can indicate an inadvertent release of radioactive material should the heat exchanger develop a large leak unexpectedly.

4 "Estimated Mass Flux Of Tritiated Groundwater To The Conowingo Reservoir And Rock Run Creek, Peach Bottom Atomic Power Station, Delta, Pennsylvania", August 2017, GHD formerly Conestoga-Rovers & Associates.

5 Tritium dose factor for bone is 0.00E+00; therefore, no hypothetical dose is calculated.

6 These doses are identical because the dose factors are identical for the same nuclide and pathway.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Analysis of Release It was assumed that the torus water released to the discharge canal, during 2020, contributed a conservative maximum dose of 5.31E-05 mrem to the total body (receptor child), and a conservative maximum organ dose of 2.58E-04 mrem to the adult gastrointestinal tract-lower large intestine (GI-LLI). This dose contribution is well below the limits specified in the ODCM.

Samples were analyzed for all the parameters of radioactive effluent releases. Composite liquid torus water samples were counted for tritium and submitted to an offsite vendor laboratory for analyses of Fe-55, P-32, Sr-89, Sr-90, Ni-63 and gross alpha. The dose contributions and isotope quantities from the releases were added to this Radioactive Effluent Release Report for the applicable reporting periods.

Contaminated Auxiliary Boiler During 2020, trace amounts of H-3 activity were identified in the auxiliary boiler (IR#

04308811). During operations of the boiler activity was not always detectable, making identifying and fixing the source of contamination challenging. Therefore, sampling and monitoring of the boiler and deaerator water was performed prior to start up, during operations, and after lay-up to identify any potential for release. The liquid release occurred during blow-downs and start-up, when liquid waste is routed to a permitted outfall if activity is identified before or during boiler operation. The source of leakage was identified and fixed in January 2020 (IR #04312479).

Analysis of Release There was one abnormal liquid release due to contamination found in the auxiliary boilers.

Sample was counted to effluent LLDs for gamma and H-3 and any positive activity was used to quantify the release. The release was documented in the effluent management software (OpenEMS) and the total organ dose was determined to be 2.21E-08 mrem to the child Liver (2.21E-07% of quarterly limit) and 2.21E-08 mrem to the child total body (7.38E-07% of quarterly limit).

Gaseous Releases Contaminated Auxiliary Boiler While the boiler was in operation and during startup, the roof vent is opened to maintain system pressure. The conservative assumption is that the steam released through the auxiliary boiler contained whatever activity was identified during liquid sampling and therefore, needed to be documented as a release. The highest H-3 or gamma activity concentration from either the steam/mud drums or the deaerator, identified during the release period, was used to quantify the release. There were two documented releases of the steam from the auxiliary boiler containing activity in 2020. Since there is no measurement of steam flow exiting the roof vent when it is open, the total boiler steam flow was used, which is overly conservative (since the majority of steam is used by the system and returned via condensate instead of released through the roof vent). The exhaust vent was not open during operation when house heat was in service. The total dose to infant thyroid from both releases was 2.27E-04 mrem, 1.51E-03%

of quarterly limit, while the maximum dose rate seen during a release was 3.61E-05 mrem/year 13

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC to the teen lung (2.41E-06% of the 1500 mrem/year limit). The conservative nature of the release assumptions show that the dose impact is minimal to the public.

165 RAMP Positive Ventilation The doors for the 165 Turbine Building ramp were maintained open due to COVID-19, and a continuous air sampler set up to monitor for any potential releases, should building ventilation change. Analysis of the air samples on 3/23/20 positive Cs-138 was identified, and building ventilation was not negative (IR #4328859). Therefore, an assumed release remained, until building ventilation was restored to negative pressure. Since Cs-138 is not tracked in the effluent program, Xe-138 was used to determine dose impacts (Cs-138 is the daughter of Xe-138). The release occurred for 1.7115E+4 minutes, with an assumed air flow of 4.41E+03 ft3/min. The maximum concentration of 1.91E-09µCi/cc. The conservative dose rate (5.012E-05 mrem/year Infant NG Skin) and conservative dose (1.632E-06 mrem to Infant Skin) calculated for this release is well-below the limits in the ODCM. Another instance of a positive Cs-138 result with positive pressure at the 165 ramp occurred from 5/30/20-5/31/20. The release occurred for 2.190E+03minutes, with an assumed air flow of 4.41E+03 ft3/min. The maximum concentration of 9.40E-10µCi/cc. The conservative dose rate (2.469E-05 mrem/year Infant NG Skin) and conservative dose (1.029E-07 mrem to Infant Skin) calculated for this release is well-below the limits in the ODCM.

Missed Sampling There were no missed ODCM samples in 2020.

Radiation Monitors Out of Service for Greater than 30 days There were no Radiation Monitors Out of Service for greater than 30 days in 2020.

Changes to the ODCM There was one revision made to the ODCM and to the ODCM Specifications (Appendix A) during 2020. Values for Ws and Wv were updated for 1100m SSE to better align with the latest 10 year averages. References to burning contaminated oil were deleted since PBAPS no longer burns contaminated oil. Locations within the Site Boundary where Dose Assessments for members of the Public were updated to reflect the abandonment of the old security checkpoint and the implementation of two new locations: Warehouse and Emergency Response Checkpoint. More detail can be found in Appendix A.

Violations There were no effluent release violations for the 2020 reporting period.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Dose Assessment Introduction A dose assessment for PBAPS was conducted with the measured cumulative 2020 radioactive effluent source terms, provided in Attachment 2, "Effluent Summary," and the 2020 meteorological (MET) data. This dose assessment verifies that PBAPS continues to demonstrate compliance with the limits as well as the requirement of maintaining dose "as low as is reasonably achievable" as stated in 10 CFR 50, Appendix I.7 Liquid Dose Assessment Hydrologic Conditions and Receptor Locations of Interest PBAPS is located on the Conowingo Pond formed in the Susquehanna River by the Conowingo Dam. For 2020, the annual average river flow8 was measured as 3.82E+05 ft3/s.

Of the three separate flow regimes that were used in the original Appendix I submittal, the most-limiting of them (<1.50E+04 ft3/s) was used to calculate a dose assessment for this report because this would provide a bounding extreme for all PBAPS liquid effluents. Therefore, although the actual average stream flow for the year was more than double the limiting case, this report will provide an upper limit for the most-limiting dose.

The annual average dilution factor9 at the Conowingo Intake is 5.40E+00 and the assumption for the reconcentration factor9 is 1.16E+00. The PBAPS shorewidth factor10 of 2.00E-01 was also used.

No invertebrate intake was examined because invertebrate ingestion pathways are not considered to be significant in the area close to PBAPS. The pathway factors for the various age groups, used to determine dose to the public from liquid effluents are shown in Table 6.

Table 6. Consumption and Usage Rate Assumptions Pathway Adult Teenager Child Infant Units 10 Eating Fish 2.10E+01 1.60E+01 6.90E+00 0.00E+00 kg/ yr 11 Drinking Water 7.30E+02 5.10E+02 5.10E+02 5.10E+02 L/ yr 12 Swimming 2.80E+02 2.80E+02 0.00E+00 0.00E+00 h/ yr 12 Boating 1.20E+02 1.20E+02 6.70E+01 0.00E+00 h/ yr 12 Shoreline Recreation 3.25E+02 3.25E+02 1.40E+01 0.00E+00 h/ yr 12 Fishing from Conowingo Dam 3.25E+02 3.25E+02 0.00E+00 0.00E+00 h/ yr 7

10 CFR 50 Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low as is Reasonable Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents".

8 USGS National Water Information Service; Monitoring Site 01576000, Susquehanna River at Marietta, PA; http://waterdata.usgs.gov/nwis. Accessed 24 Mar 2020.

9 From original ODCM.

10 RG 1.109, Table A-2.

11 All locations from RG 1.109, Section A-2. Chester Water Authority uses 10% of the RG 1.109 value because it is assumed to have 10% sourced from Conowingo Pond.

12 PBAPS Environmental Report, Supplement No. 3, Page 19. Boating data is a ratio of Adult:Child rates from RG 1.109, Table A-2.

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Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Liquid Effluent Dose Assessment Conclusion For all permitted releases in 2020, the calculated total body dose was 4.33E-05 mrem and 4.66E-05 mrem to the limiting organ of child Liver.

Therefore, PBAPS liquid radioactive effluent controls continue to demonstrate compliance with 10 CFR 50, Appendix I objectives for the purposes of keeping doses to members of the public "as low as is reasonably achievable". These limiting or maximum calculated doses are a small fraction of the limits in Appendix I.

Gaseous Dose Assessment The gaseous dose assessment calculates the conservative dose at the limiting receptor location, as defined in the ODCM and at locations from the land-use census, using the 2020 meteorology to demonstrate compliance with 10 CFR 50, Appendix I. The assessment compares the current ODCM locations to the maximum locations from the land use census to ensure the current ODCM locations are still the most impactful dose locations.

Tables 7 and 8 report the dose calculated with the CY-PB-170-210 spreadsheet using the 2020 MET data and total gaseous activity released (summarized in Attachment 2), including C-14. Table 7 focuses on the two locations with the highest elevated dispersion factor (X/Q) from the Main Offgas Stack, while Table 8 highlights the two locations with the highest ground deposition factor (D/Q) from the Reactor Building Exhaust Vents. The X/Q values are very similar to those used in the ODCM, and therefore the differences in noble gas dose is minimal. The larger discrepancies between Iodine, Particulates, Tritium (I/P/T) organ doses can be explained by the differences in pathways. Tables 7 and 8 assume that there is a milk pathway at each of the listed locations.

The ODCM defines the milk pathway at 1500m SW and the D/Qs are more comparable (2020 vent: 2.03E-09 1/m2 vs. ODCM vent: 1.58E-09 1/m2) and therefore, the dose calculated by ODCM methodology is more accurately representative of the dose to members of the public than the doses reported in Tables 7 and 8.

Table 7. Conservative Maximum Elevated Release Dose from 2020 Source Term and 2020 Meteorology 2020 Gamma Beta Air I/P/T/C-Distance 2020 Vent Total Body Skin Dose Limiting Direction Highest MS Air Dose Dose 14 Dose (m) X/Q (D/Q) Dose (mrem) (mrem) Receptor X/Q (D/Q) (mrad) (mrad) (mrem) 4.66E-08 1.19E-07 4600 N 1.70E-02 2.24E-02 1.76E-02 1.21E-02 1.94E-01 Bone (3.34E-10) (7.38E-10) 3.71E-08 1.10E-07 3800 SW 1.57E-02 2.06E-02 1.63E-02 1.11E-02 1.56E-01 Bone (2.20E-10) (4.85E-10)

Table 8. Ground-Level Dose from 2020 Source Term and 2020 Meteorology 2020 Highest 2020 MS Total Body Skin Gamma Beta Air I/P/T/C-Distance Limiting Direction Vent D/Q X/Q Dose Dose Air Dose Dose 14 Dose (m) Receptor (X/Q) (D/Q) (mrem) (mrem) (mrad) (mrad) (mrem) 1.05E-08 6.64E-10 1200 SSE 1.42E-01 1.86E-01 1.47E-01 9.88E-02 1.41E-01 Bone (1.03E-06) (4.65E-09) 8.00E-09 5.26E-09 900 NW 1.64E-01 2.15E-01 1.70E-01 1.14E-01 1.62E-01 Bone (1.19E-06) (6.28E-10) 16

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Gaseous Radioactive Effluent Dose Assessment Conclusion The conservative maximum dose was 1.40E-01 mrem with the maximum receptor as the child bone which is due to the incorporation of carbon-14 in the calculation. Without C-14, the maximum dose is 4.30E-03 mrem to the infant thyroid. The noble gas limiting air doses were 1.60E-01 mrad (gamma) and 1.09E-01 mrad (beta). Noble gas plume conservative dose was 1.55E-01 mrem to the total body and 2.04E-01 to the skin mrem for the year.

A dose assessment was performed for members of the public due to their activities inside the site boundary, per ODCMS 3.10.2.f. The locations where a member of the public would spend a significant amount of time inside the site boundary are two new vehicle checkpoints, approximately 780 feet ENE (Emergency checkpoint) and 910 feet NNE (Warehouse checkpoint) of the PBAPS Unit 2 and Unit 3 reactor building exhaust vents. Assuming continuous occupancy, the calculated total body and skin doses were 1.08E+00 mrem and 1.42E+00 mrem for the Emergency checkpoint and 2.04E-01 mrem and 2.67E-01 mrem for the Warehouse checkpoint, respectively. The noble gas limiting air doses were 1.12E+00 mrad (gamma) and 7.53E-01 mrad (beta) for the Emergency checkpoint and 2.11E-01 mrad (gamma) and 1.42E-01 mrad (beta) for the Warehouse checkpoint. These doses are overly conservative, as typically vehicles and their drivers are not at the checkpoints 24/7. The maximum organ dose from the inhalation pathway, not including C-14, is 7.17E-02 mrem for the Emergency checkpoint and 1.85E-02 mrem for the Warehouse checkpoint, both to the infant thyroid.

All doses are projected to be much less than the limits, as expected. Again, these dose models incorporate several factors of conservatism including a source term that, by procedure, will use the most dose-limiting noble gas nuclide when no fission gas can be identified by grab sample, but activity is detected from the effluent radiation monitor. Exelon Nuclear uses a detailed C-14 dose projection from the Electric Power Research Institute, Technical Report 1021106. Details for the assumptions used in this calculation may be found there.15 Therefore, PBAPS gaseous radioactive effluent controls continue to demonstrate compliance with 10 CFR 50, Appendix I objectives for the purposes of keeping doses to members of the public "as low as is reasonably achievable". These limiting or maximum calculated dose are a small fraction of the limits in Appendix I.

15 PBAPS uses specific Boiling Water Reactor assumptions because the fraction of C-14 that is in the CO2 form will vary based on general plant design. This is important because the major dose pathway is through photosynthesis and, therefore, only the oxide form is relevant.

17

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 2: EFFLUENT

SUMMARY

18

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Gaseous Effluents - Summation of All Releases Period: January 1, 2020 through December 31, 2020 Unit: Peach Bottom Est. Total A. Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error %

1. Total Release Ci 9.79E+01 8.74E+01 1.07E+02 1.08E+02 4.00E+01
2. Average release For the Period uCi/ s 1.25E+01 1.11E+01 1.35E+01 1.36E+01
3. Gamma Air Dose mrad 4.46E-02 3.52E-02 3.69E-02 4.35E-02
4. Beta Air Dose mrad 3.05E-02 2.42E-02 2.43E-02 2.98E-02
5. Percent of ODCM limit Gamma Air Dose  % 4.46E-01 3.52E-01 3.69E-01 4.35E-01 Beta Air Dose  % 1.53E-01 1.21E-01 1.22E-01 1.49E-01 B. Iodines
1. Total I-131 Ci 4.42E-04 1.25E-03 1.72E-03 6.81E-04 1.90E+01
2. Average release For the Period uCi/ s 5.62E-05 1.59E-04 2.16E-04 8.57E-05
3. Percent of ODCM limit  % * * * *
  • No ODCM defined Curie Limit, therefore a percentage of the limit cannot be calculated.

C. Particulate

1. Particulates with T1/2 > 8 days Ci 7.79E-05 1.01E-04 1.13E-04 1.84E-04 2.80E+01
2. Average release For the Period uCi/ s 9.90E-06 1.28E-05 1.42E-05 2.31E-05
3. Percent of ODCM limit  % * * * *
  • No ODCM defined Curie Limit, therefore a percentage of the limit cannot be calculated.

D. Tritium

1. Total Release Ci 7.59E+00 1.01E+01 5.42E+01 1.02E+01 1.30E+01
2. Average release For the Period uCi/ s 9.66E-01 1.29E+00 6.82E+00 1.28E+00
3. Percent of ODCM limit  % * * * *
  • No ODCM defined Curie Limit, therefore a percentage of the limit cannot be calculated.

E. Gross Alpha

1. Total Release Ci <LLD <LLD <LLD <LLD 4.00E+02
2. Average release For the Period uCi/ s <LLD <LLD <LLD <LLD
3. Percent of ODCM limit  % * * * *
  • No ODCM defined Curie Limit, therefore a percentage of the limit cannot be calculated.

F. Carbon-14

1. Total Release Ci 9.61E+00 9.61E+00 9.61E+00 9.61E+00
2. Average release For the Period uCi/ s 1.26E+00 1.26E+00 1.26E+00 1.26E+00 G. Iodine-131, 133 and 135, Tritium, Carbon-14 & Particulate
1. Organ Dose* mrem 3.56E-02 3.56E-02 3.56E-02 3.56E-02
2. Percent ODCM limit  % 2.37E-01% 2.37E-01% 2.37E-01% 2.37E-01%
  • C-14 contributes most significantly; therefore, the quarterly dose to the child bone is reported 19

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Gaseous Effluents Release Point: Elevated (Main Offgas Stack)

Period: January 1, 2020 through December 31, 2020 Unit: Peach Bottom Nuclides Released Continuous Mode Batch Mode Quarter Quarter Quarter Quarter

1. Fission Gases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 1 2 3 4 Unidentified Ci 1.21E+01 6.51E+00 <LLD 1.06E+01 <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD 2.54E+00 4.05E+00 <LLD <LLD <LLD <LLD <LLD Kr-87 Ci 9.74E-01 6.65E-01 <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD 1.50E+01 1.03E+01 <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD 5.54E+00 <LLD <LLD <LLD <LLD <LLD Xe-135 Ci 2.59E+00 3.18E+00 2.20E+00 2.11E+00 <LLD <LLD <LLD <LLD Xe-138 Ci <LLD 9.55E+00 2.99E+00 5.14E+00 <LLD <LLD <LLD <LLD Total For Period Ci 1.56E+01 2.25E+01 2.98E+01 2.81E+01 <LLD <LLD <LLD <LLD
2. Iodines I-131 Ci 7.38E-05 9.01E-05 9.58E-05 6.29E-05 <LLD <LLD <LLD <LLD I-132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD I-133 Ci 1.93E-04 2.84E-04 2.98E-04 2.20E-04 <LLD <LLD <LLD <LLD I-135 Ci 3.97E-05 1.88E-04 5.20E-05 1.27E-04 <LLD <LLD <LLD <LLD Total For Period Ci 3.06E-04 5.62E-04 4.46E-04 4.11E-04 <LLD <LLD <LLD <LLD
3. Particulates Sr-89 Ci 6.67E-05 7.53E-05 8.49E-05 7.27E-05 <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD 1.59E-07 1.86E-07 <LLD <LLD <LLD <LLD Ba-140 Ci 1.04E-05 2.37E-05 2.76E-05 7.30E-06 <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci 7.59E-07 1.65E-06 2.41E-07 4.08E-06 <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period Ci 7.79E-05 1.01E-04 1.13E-04 8.42E-05 <LLD <LLD <LLD <LLD
4. Tritium H-3 Ci 6.33E-01 1.66E+00 2.81E+01 4.11E+00 <LLD <LLD <LLD <LLD
5. Gross Alpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
6. Carbon-14 C-14 Ci 9.32E+00 9.32E+00 9.32E+00 9.32E+00 <LLD <LLD <LLD <LLD 20

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Gaseous Effluents Release Point: Ground-Level (Units 2 and 3 Reactor Building Exhaust Vents and Abnormal Releases)

Period: January 1, 2020 through December 31, 2020 Unit: Peach Bottom Nuclides Released Continuous Mode Batch Mode Quarter Quarter Quarter Quarter

1. Fission Gases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 1 2 3 4 Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD 1.81E+01 <LLD 4.08E-03 <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Unidentified Ci 8.23E+01 6.50E+01 5.95E+01 8.02E+01 <LLD <LLD <LLD <LLD Total For Period Ci 8.23E+01 6.50E+01 7.76E+01 8.02E+01 <LLD <LLD <LLD <LLD
2. Iodines I-131 Ci 4.96E-06 8.88E-05 1.43E-04 2.08E-05 <LLD <LLD <LLD <LLD I-132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD I-133 Ci 1.30E-04 6.00E-04 1.13E-03 2.50E-05 <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period Ci 1.35E-04 6.89E-04 1.27E-03 2.7E-04 <LLD <LLD <LLD <LLD
3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD 1.08E-05 <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD 1.23E-05 <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD 6.67E-05 <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD 9.55E-06 <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period Ci <LLD <LLD <LLD 9.93E-05 <LLD <LLD <LLD <LLD
4. Tritium H-3 Ci 6.96E+00 8.48E+00 2.61E+01 6.06E+00 1.72E-03 <LLD <LLD <LLD
5. Gross Alpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
6. Carbon-14 C-14 Ci 2.88E-01 2.88E-01 2.88E-01 2.88E-01 <LLD <LLD <LLD <LLD 21

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Liquid Effluents - Summation of All Releases Period: January 1, 2020 to December 31, 2020 Unit: Peach Bottom Est. Total A. Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error %

1. Total Release (not including tritium, gases 7.21E-07 1.49E-05 1.12E-06 3.67E-05 1.60E+01

& alpha) Ci

2. Average diluted concentration for the 2.11E-13 8.87E-12 4.25E-12 1.48E-11 Period Ci/ mL
3. Percent of applicable limit Total Body Dose*  % 1.73E-05% 2.70E-04% 2.49E-05% 6.87E-04%

Organ Dose*  % 8.14E-06% 9.90E-05% 8.00E-06% 2.15E-04%

  • ODCMS 3.8.B.2.a and ODCMS 3.8.B.2.b (page 7) define the dose limit Est. Total B. Tritium Error %
1. Total Release Ci 1.98E-03 6.50E-01 2.23E-03 1.57E+00 6.40E+00
2. Average diluted concentration for the 5.80E-10 3.87E-07 8.45E-09 6.33E-07 Period µCi/ mL
3. Percent of applicable limit*  % 5.80E-06% 3.87E-03% 8.45E-05% 6.33E-04%
  • 10x 10CFR20 Limit of 1.00E-03 µCi/ mL; ODCMS 3.8.B.1.a Est. Total C. Dissolved & Entrained Gases Error %
1. Total Release Ci <LLD <LLD <LLD 3.62E-05 2.80E+01
2. Average diluted concentration for the <LLD <LLD <LLD 1.46E-11 Period Ci/ mL
3. Percent of ODCM limit*  % <LLD <LLD <LLD % 7.30E-06%
  • ODCMS 3.8.B.1.b Limit for all noble gases is 2.00E-04 µCi/ mL Est. Total D. Gross Alpha Activity Error %
1. Total Release Ci <LLD <LLD <LLD <LLD 2.30E+01 E. Volume of Waste Released (prior to 1.71E+08 1.71E+08 1.72E+08 1.73E+08 dilution) Liters F. Volume of Dilution Water Used During 5.96E+11 6.66E+11 5.63E+11 5.83E+11 Period Liters 22

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Liquid Effluents Release Points - Liquid Radwaste, RHR Leaks and Groundwater Period: January 1, 2020 through December 31, 2020 Unit: Peach Bottom Nuclides Released Continuous Mode Batch Mode Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD 5.21E-07 5.93E-07 <LLD 4.36E-07 I-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci 1.35E-05 <LLD <LLD <LLD <LLD <LLD <LLD 6.48E-07 Co-60 Ci 1.68E-03 1.97E-03 2.07E-03 1.39E-03 2.00E-07 3.31E-07 1.12E-06 1.74E-05 Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci 2.11E-04 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci 3.32E-04 2.23E-04 2.34E-04 1.58E-04 <LLD 3.58E-07 <LLD 1.53E-05 Cr-51 Ci 3.60E-04 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD 8.14E-06 <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2.90E-06 Sb-125 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ni-63 Ci 5.33E-05 4.25E-05 4.45E-05 3.00E-05 <LLD <LLD <LLD <LLD H-3 Ci 2.29E+00 1.84E+00 1.00E+00 1.39E+00 1.98E-03 6.50E-01 2.23E-03 1.57E-00 P-32 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 2.29E+00 1.84E+00 1.00E+00 1.39E+00 1.98E-03 6.50E-01 2.23E-03 1.57E-00 Xe-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1.48E-05 Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 2.14E-05 Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 3.62E-05 Total for Period (ex-tritium, Ci 2.19E-03 2.24E-03 2.35E-03 1.58E-03 7.21E-07 1.49E-05 1.12E-06 3.67E-05 gases and alpha) 23

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 24

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Solid Waste Shipped 1.Type of Waste Units 2020 Est. error %

A: Spent Resin, Filters, Sludges, Evaporator Bottoms, etc. m 3 5.05E+01 Ci 4.38E+02 2.50E+01 B: Dry Compressible Waste, Contaminated Equipment, etc. m3 5.96E+02 Ci 2.57E+00 2.50E+01 C: Irradiated Components, Control Rods, etc. m3 0.00E+00 Ci 0.00E+00 2.50E+01 D: Other (Oil, SBLC) m3 1.49E+01 Ci 7.65E-03 2.50E+01 2.Estimate of Major Nuclide Composition (by type of waste)

a. Spent-Resin, Filters, Sludges, Evaporator Bottoms, etc.

Abundance % Abundance %

Nuclide (no cutoff) Activity (Ci) Nuclide (no cutoff) Activity (Ci)

H-3 Ag-110m 0.33% 1.46E+00 0.19% 8.44E-01 C-14 Sb-124 0.00% 1.63E-04 0.20% 8.65E-01 Cr-51 Sb-125 0.02% 8.13E-02 0.00% 1.18E-05 Mn-54 I-131 0.00% 7.10E-03 2.79% 1.22E+01 Fe-55 Cs-134 0.01% 2.40E-02 15.12% 6.62E+01 Fe-59 Cs-137 2.49% 1.09E+01 0.00% 7.88E-05 Co-57 Ba-140 0.01% 2.22E-02 0.00% 1.35E-03 Co-58 La-140 0.00% 6.24E-09 0.08% 3.55E-01 Co-60 Ce-141 0.00% 1.72E-02 74.60% 3.27E+02 Ni-63 Ce-144 0.03% 1.31E-01 0.64% 2.81E+00 Zn-65 Pu-238 0.00% 4.94E-04 3.47% 1.52E+01 Se-75 Pu-239 0.00% 0.00E+00 0.00% 4.43E-04 Sr-89 Pu-241 0.01% 3.01E-02 0.00% 3.42E-03 Sr-90 Am-241 0.00% 1.58E-04 0.01% 2.84E-02 Zr-95 Cm-242 0.00% 0.00E+00 0.00% 5.47E-06 Nb-95 Cm-244 0.00% 1.55E-04 0.00% 1.40E-05 25

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC

b. Dry, Compressible Waste, Contaminated Equipment, etc.

Waste Class A Abundance Abundance Nuclide  % (no cutoff) Activity (Ci) Nuclide  % (no cutoff) Activity (Ci)

H-3 0.00% 7.95E-05 Ce-141 0.02% 4.40E-04 Cr-51 0.89% 2.28E-02 Ce-144 0.22% 5.61E-03 Mn-54 2.95% 7.59E-02 C-14 0.00% 1.90E-05 Fe-55 12.69% 3.27E-01 Sr-89 0.04% 9.68E-04 Fe-59 0.34% 8.73E-03 Sr-90 0.03% 7.63E-04 Co-57 0.03% 8.64E-04 Ag-110m 1.15% 2.95E-02 Co-58 1.11% 2.87E-02 Sb-125 0.00% 1.09E-04 Co-60 71.70% 1.84E+00 Sb-124 0.05% 1.18E-03 Ni-63 2.75% 7.06E-02 Pu-238 0.00% 7.56E-06 Zn-65 4.13% 1.06E-01 Pu-241 0.01% 1.91E-04 Cs-137 1.97% 5.06E-02 Nb-95 0.00% 5.20E-06 Waste Class C Abundance Abundance Nuclide  % (no cutoff) Activity (Ci) Nuclide  % (no cutoff) Activity (Ci)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

c. Irradiated Components, Control Rods, etc.

Abundance Abundance Nuclide  % (no cutoff) Activity (Ci) Nuclide  % (no cutoff) Activity (Ci)

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 26

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC

d. Other: Oil Abundance % Abundance %

Nuclide (no cutoff) Activity (Ci) Nuclide (no cutoff) Activity (Ci)

H-3 0.02% 1.23E-05 Ni-63 0.97% 7.42E-04 Cr-51 11.95% 9.14E-03 Zn-65 7.78% 5.95E-03 Mn-54 2.37% 1.82E-03 Ag-110m 2.93% 2.24E-03 Fe-55 11.91% 9.12E-03 Sb-124 0.41% 3.15E-04 Fe-59 3.75% 2.87E-03 Cs-137 1.33% 1.01E-03 Co-57 0.08% 6.27E-05 Ce-141 0.21% 1.61E-04 Co-58 12.54% 9.60E-03 Ce-144 0.39% 3.00E-04 Co-60 43.36% 3.32E-02

3. Solid Waste Disposition Number of shipments Mode of Transportation Destination Hittman Transport 11 Services Energy Solutions Services (CVRF) Bear Creek Operations Hittman Transport 8 Services Energy Solutions Services (GRF) Gallaher Road Operations Hittman Transport 2 Services Energy Solutions - BWF Hittman Transport Energy Solutions LLC - Clive Disposal Site - Containerized Waste 12 Services Facility 1 Landstar - Ranger Toxco Inc. - Oak Ridge, TN Irradiated Fuel Shipments No shipment of irradiated fuel was made during the reporting period of 2020.

Changes to Process Control Program (PCP)

There were no changes made to RW-AA-100 "Process Control Program for Radioactive Waste" during the 2020 reporting period.

27

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 4: RADIOLOGICAL IMPACT ON MAN 28

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Radiological Impact on Man Location  % of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters) (toward) Limit Limit Unit Gamma -

Noble Gas 1.60E-01 All 1.10E+03 SSE 8.00E-01 2.00E+01 mrad Air Dose Beta - Air Noble Gas 1.09E-01 All 1.10E+03 SSE 2.73E-01 4.00E+01 mrad Dose Total Noble Gas Body 1.55E-01 All 1.10E+03 SSE 1.55E+00 1.00E+01 mrem (gamma)

Skin Noble Gas 2.04E-01 All 1.10E+03 SSE 6.80E-01 3.00E+01 mrem (Beta)

Gaseous Iodine, Particulate, Bone 1.40E-01 Child 1.50E+03 SW 4.67E-01 3.00E+01 mrem Carbon-14 &

Tritium Gaseous Iodine, Thyroid 4.30E-03 Infant 1.50E+03 SW 1.43E-02 3.00E+01 mrem Particulate &

Tritium Total Liquid Body 1.54E-04 Child 4.32E-03 2.57E-03 mrem (gamma) Site Boundary Liquid GI-LLI 3.47E-04 Adult 2.55E-03 1.74E-03 mrem Direct Total 0 All 1.19E+03 SSE 0.00E+00 2.50E+01 mrem Radiation Body 40 CFR 190 Doses Location  % of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters) (toward) Limit Limit Unit Total Total Dose 1.55E-01 All 1.19E+03 SSE 6.21E-01 2.50E+01 mrem Body Total Dose Thyroid 4.30E-03 All 1.19E+03 SSE 5.73E-03 7.50E+01 mrem Total Dose Bone 1.40E-01 All 1.19E+03 SSE 5.61E-01 2.50E+01 mrem Total Total Dose 1.55E-01 All 1.19E+03 SSE 5.17E+00 3.00E+00 mrem Body Total Dose Bone 1.40E-01 All 1.19E+03 SSE 4.68E+00 3.00E+00 mrem Total Dose Thyroid 1.64E-01 All 1.19E+03 SSE 2.99E-01 5.50E+01 mrem 29

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC ATTACHMENT 5: METEOROLOGICAL DATA 30

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 14 1 0 0 0 20 NNE 7 18 1 0 0 0 26 NE 25 6 0 0 0 0 31 ENE 36 4 0 0 0 0 40 E 11 17 0 0 0 0 28 ESE 11 21 1 0 0 0 33 SE 7 10 3 0 0 0 20 SSE 2 15 3 0 0 0 20 S 3 6 9 2 1 0 21 SSW 3 3 0 0 0 0 6 SW 2 2 6 0 0 0 10 WSW 0 0 4 2 0 0 6 W 4 1 3 5 0 0 13 WNW 3 5 3 0 0 0 11 NW 2 12 1 0 0 0 15 NNW 2 6 4 0 0 0 12 Variable 0 0 0 0 0 0 0 Total 123 140 39 9 1 0 312 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 31

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 6 1 0 0 11 NNE 1 9 0 0 0 0 10 NE 2 1 0 0 0 0 3 ENE 9 0 0 0 0 0 9 E 7 3 0 0 0 0 10 ESE 4 5 0 0 0 0 9 SE 2 6 4 0 0 0 12 SSE 0 2 2 0 0 0 4 S 0 0 5 1 0 0 6 SSW 0 3 5 2 0 0 10 SW 0 4 0 1 0 0 5 WSW 0 0 12 0 0 0 12 W 0 0 13 9 1 0 23 WNW 1 2 1 4 0 0 8 NW 0 4 0 4 0 0 8 NNW 0 10 18 16 0 0 44 Variable 0 0 0 0 0 0 0 Total 26 53 66 38 1 0 184 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 32

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 0 0 0 0 3 NNE 4 8 0 0 0 0 12 NE 2 0 0 0 0 0 2 ENE 2 3 0 0 0 0 5 E 4 4 0 0 0 0 8 ESE 2 2 0 0 0 0 4 SE 0 1 0 0 0 0 1 SSE 0 1 1 0 0 0 2 S 0 0 6 0 0 0 6 SSW 0 0 0 0 0 0 0 SW 0 1 3 1 0 0 5 WSW 0 1 5 0 0 0 6 W 0 0 5 3 0 0 8 WNW 1 1 8 2 1 0 13 NW 0 0 3 5 0 0 8 NNW 0 5 21 1 0 0 27 Variable 0 0 0 0 0 0 0 Total 16 29 52 12 1 0 110 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 33

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Neutral- 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 12 26 14 0 0 0 52 NNE 19 16 2 0 0 0 37 NE 14 8 0 0 0 0 22 ENE 32 4 0 0 0 0 36 E 27 18 1 0 0 0 46 ESE 12 24 3 0 0 0 39 SE 8 30 11 0 0 0 49 SSE 6 52 15 0 0 0 73 S 9 32 25 1 0 0 67 SSW 2 12 5 0 0 0 19 SW 0 9 9 3 0 0 21 WSW 4 8 17 0 0 0 29 W 6 25 32 13 1 0 77 WNW 3 24 28 21 0 0 76 NW 5 48 55 20 1 0 129 NNW 5 58 69 31 1 0 164 Variable 0 0 0 0 0 0 0 Total 164 394 286 89 3 0 936 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 34

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 17 2 0 0 0 0 19 NNE 15 0 0 0 0 0 15 NE 16 2 0 0 0 0 18 ENE 12 0 0 0 0 0 12 E 21 7 1 0 0 0 29 ESE 20 3 0 0 0 0 23 SE 22 9 0 0 0 0 31 SSE 9 22 1 0 0 0 32 S 9 13 2 0 0 0 24 SSW 5 2 1 0 0 0 8 SW 6 13 2 0 0 0 21 WSW 8 48 6 0 0 0 62 W 16 35 6 0 0 0 57 WNW 10 28 2 0 0 0 40 NW 14 20 2 0 0 0 36 NNW 13 12 3 0 0 0 28 Variable 0 0 0 0 0 0 0 Total 213 216 26 0 0 0 455 Hours of calm in this stability class: 5 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 35

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 0 0 0 0 2 NNE 3 0 0 0 0 0 3 NE 10 0 0 0 0 0 10 ENE 7 0 0 0 0 0 7 E 5 0 0 0 0 0 5 ESE 7 1 0 0 0 0 8 SE 8 1 0 0 0 0 9 SSE 5 1 0 0 0 0 6 S 4 0 0 0 0 0 4 SSW 3 0 0 0 0 0 3 SW 7 4 0 0 0 0 11 WSW 7 7 1 0 0 0 15 W 6 1 0 0 0 0 7 WNW 7 0 0 0 0 0 7 NW 5 0 0 0 0 0 5 NNW 6 1 0 0 0 0 7 Variable 0 0 0 0 0 0 0 Total 92 16 1 0 0 0 109 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 36

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 0 0 0 0 0 3 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 4 0 0 0 0 0 4 E 11 0 0 0 0 0 11 ESE 7 0 0 0 0 0 7 SE 4 0 0 0 0 0 4 SSE 2 0 0 0 0 0 2 S 2 0 0 0 0 0 2 SSW 2 0 0 0 0 0 2 SW 6 0 0 0 0 0 6 WSW 4 2 0 0 0 0 6 W 8 1 0 0 0 0 9 WNW 2 0 0 0 0 0 2 NW 1 0 0 0 0 0 1 NNW 1 0 0 0 0 0 1 Variable 0 0 0 0 0 0 0 Total 59 3 0 0 0 0 62 Hours of calm in this stability class: 3 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 37

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Extremely Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 1 0 0 0 1 NE 0 1 1 0 0 0 2 ENE 0 1 0 0 0 0 1 E 0 0 2 0 0 0 2 ESE 0 0 4 0 0 0 4 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 2 8 0 0 0 10 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 38

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Moderately Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 2 0 0 0 0 3 E 0 2 0 0 0 0 2 ESE 0 1 0 1 0 0 2 SE 0 0 0 0 0 0 0 SSE 0 0 1 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 1 5 2 1 0 0 9 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 39

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Slightly Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 0 1 NNE 0 3 2 0 0 0 5 NE 0 0 0 0 0 0 0 ENE 0 3 0 0 0 0 3 E 0 2 1 0 1 0 4 ESE 0 0 2 1 1 0 4 SE 0 0 3 0 0 0 3 SSE 0 0 3 1 0 0 4 S 0 0 3 2 0 0 5 SSW 0 0 0 0 0 0 0 SW 0 0 1 4 0 0 5 WSW 0 0 1 5 2 0 8 W 0 0 0 2 0 2 4 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1 Variable 0 0 0 0 0 0 0 Total 0 8 18 15 4 2 47 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 40

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Neutral- 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 23 40 19 0 0 85 NNE 4 19 21 6 0 0 50 NE 10 15 9 2 0 0 36 ENE 10 18 7 0 0 0 35 E 6 23 14 19 3 0 65 ESE 3 15 32 19 7 0 76 SE 3 29 37 24 0 0 93 SSE 0 11 25 15 2 0 53 S 0 10 38 33 9 4 94 SSW 0 4 12 9 4 0 29 SW 2 7 11 14 8 1 43 WSW 0 1 8 28 6 0 43 W 0 3 15 40 23 25 106 WNW 0 3 14 40 48 17 122 NW 1 8 67 77 42 7 202 NNW 0 18 49 59 11 6 143 Variable 0 0 0 0 0 0 0 Total 42 207 399 404 163 60 1275 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 7 Hours of missing stability measurements in all stability classes: 3 41

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Slightly Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 9 2 1 0 0 14 NNE 3 3 3 2 0 0 11 NE 4 6 2 1 0 0 13 ENE 10 17 3 0 0 0 30 E 8 16 8 4 2 0 38 ESE 3 10 13 3 0 0 29 SE 4 23 23 1 0 0 51 SSE 4 15 33 7 1 0 60 S 3 15 43 19 3 1 84 SSW 3 8 8 7 0 0 26 SW 4 8 11 9 5 0 37 WSW 2 9 17 33 5 3 69 W 0 4 28 20 5 0 57 WNW 3 5 9 22 4 1 44 NW 0 10 26 19 2 0 57 NNW 2 7 19 8 0 0 36 Variable 0 0 0 0 0 0 0 Total 55 165 248 156 27 5 656 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 3 42

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Moderately Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 0 0 0 0 2 NNE 1 1 0 0 0 0 2 NE 3 0 0 0 0 0 3 ENE 4 6 0 0 0 0 10 E 3 2 1 0 0 0 6 ESE 1 2 1 0 0 0 4 SE 2 2 3 1 0 0 8 SSE 0 2 2 0 0 0 4 S 2 2 3 1 0 0 8 SSW 1 4 7 7 0 0 19 SW 2 4 3 2 0 0 11 WSW 3 6 6 2 0 0 17 W 1 3 5 1 0 0 10 WNW 3 2 4 1 0 0 10 NW 0 1 0 0 0 0 1 NNW 0 3 0 0 0 0 3 Variable 0 0 0 0 0 0 0 Total 27 41 35 15 0 0 118 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 43

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: January - March 2020 Stability Class - Extremely Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 1 0 0 0 0 1 S 0 1 0 1 0 0 2 SSW 0 3 4 1 0 0 8 SW 1 1 12 5 0 0 19 WSW 0 2 7 0 0 0 9 W 2 2 2 0 0 0 6 WNW 0 1 2 1 0 0 4 NW 0 0 3 2 0 0 5 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 3 13 30 10 0 0 56 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 44

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 16 20 0 0 0 0 36 NNE 6 16 3 0 0 0 25 NE 36 4 0 0 0 0 40 ENE 30 9 0 0 0 0 39 E 25 9 1 0 0 0 35 ESE 5 20 4 0 0 0 29 SE 5 10 11 1 0 0 27 SSE 2 10 14 3 0 0 29 S 2 7 9 4 0 0 22 SSW 1 3 2 3 0 0 9 SW 0 3 8 0 0 0 11 WSW 1 0 5 0 0 0 6 W 0 3 4 0 0 0 7 WNW 4 7 7 5 0 0 23 NW 0 4 2 6 0 0 12 NNW 4 15 20 2 0 0 41 Variable 0 0 0 0 0 0 0 Total 137 140 90 24 0 0 391 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 45

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 10 3 0 0 0 17 NNE 5 4 0 0 0 0 9 NE 7 0 0 0 0 0 7 ENE 13 1 0 0 0 0 14 E 5 2 1 0 0 0 8 ESE 3 0 0 0 0 0 3 SE 2 7 3 0 0 0 12 SSE 1 6 9 0 0 0 16 S 0 7 9 3 0 0 19 SSW 0 1 1 0 0 0 2 SW 0 1 2 0 0 0 3 WSW 0 4 5 1 0 0 10 W 0 4 7 2 0 0 13 WNW 0 9 24 2 2 0 37 NW 0 7 11 7 0 0 25 NNW 4 11 39 15 2 0 71 Variable 0 0 0 0 0 0 0 Total 44 74 114 30 4 0 266 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 46

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 4 1 0 0 0 9 NNE 3 2 2 0 0 0 7 NE 3 0 0 0 0 0 3 ENE 4 1 0 0 0 0 5 E 5 0 0 0 0 0 5 ESE 2 1 0 0 0 0 3 SE 0 5 0 0 0 0 5 SSE 0 6 3 0 0 0 9 S 0 0 7 0 0 0 7 SSW 0 4 1 0 0 0 5 SW 0 1 3 0 0 0 4 WSW 0 3 3 0 0 0 6 W 0 4 7 2 0 0 13 WNW 0 4 6 8 0 0 18 NW 1 4 8 4 0 0 17 NNW 0 7 10 8 2 0 27 Variable 0 0 0 0 0 0 0 Total 22 46 51 22 2 0 143 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 47

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 10 19 6 0 0 0 35 NNE 23 14 1 0 0 0 38 NE 19 3 0 0 0 0 22 ENE 23 2 0 0 0 0 25 E 23 7 0 0 0 0 30 ESE 12 14 3 0 0 0 29 SE 8 18 9 4 0 0 39 SSE 7 34 15 2 0 0 58 S 12 31 16 1 0 0 60 SSW 7 13 2 0 0 0 22 SW 5 16 5 0 0 0 26 WSW 4 9 11 1 0 0 25 W 5 11 8 6 0 0 30 WNW 5 17 35 10 1 0 68 NW 8 35 47 14 1 0 105 NNW 9 21 47 11 0 0 88 Variable 0 0 0 0 0 0 0 Total 180 264 205 49 2 0 700 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 48

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 7 0 0 0 0 20 NNE 19 4 0 0 0 0 23 NE 21 0 0 0 0 0 21 ENE 7 1 0 0 0 0 8 E 14 0 0 0 0 0 14 ESE 10 3 0 0 0 0 13 SE 19 7 0 0 0 0 26 SSE 19 12 1 0 0 0 32 S 15 20 3 0 0 0 38 SSW 17 12 0 0 0 0 29 SW 13 15 2 0 0 0 30 WSW 23 37 4 0 0 0 64 W 18 36 0 0 0 0 54 WNW 15 29 2 0 0 0 46 NW 20 28 2 0 0 0 50 NNW 16 16 7 0 0 0 39 Variable 0 0 0 0 0 0 0 Total 259 227 21 0 0 0 507 Hours of calm in this stability class: 5 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 49

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 0 0 0 0 0 6 NNE 4 0 0 0 0 0 4 NE 4 0 0 0 0 0 4 ENE 0 0 0 0 0 0 0 E 3 1 0 0 0 0 4 ESE 0 0 0 0 0 0 0 SE 3 0 0 0 0 0 3 SSE 1 0 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 3 0 0 0 0 0 3 SW 16 0 0 0 0 0 16 WSW 18 16 2 0 0 0 36 W 13 10 0 0 0 0 23 WNW 1 4 0 0 0 0 5 NW 7 4 0 0 0 0 11 NNW 5 0 0 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 84 36 2 0 0 0 122 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 50

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 0 0 0 0 1 NNE 1 0 0 0 0 0 1 NE 1 0 0 0 0 0 1 ENE 1 0 0 0 0 0 1 E 1 1 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 1 SSE 1 0 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 3 0 0 0 0 0 3 SW 5 1 0 0 0 0 6 WSW 8 1 0 0 0 0 9 W 4 2 0 0 0 0 6 WNW 3 0 0 0 0 0 3 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 32 5 0 0 0 0 37 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 51

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Extremely Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 0 0 0 0 1 NNE 0 1 0 1 0 0 2 NE 0 1 2 3 0 0 6 ENE 0 6 9 5 1 0 21 E 0 11 2 1 0 1 15 ESE 0 2 5 1 0 0 8 SE 0 0 2 0 0 0 2 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 22 20 11 1 1 55 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 52

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Moderately Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 2 0 0 0 4 NNE 0 0 1 1 0 0 2 NE 0 1 0 0 0 0 1 ENE 2 4 1 0 0 0 7 E 0 7 1 2 2 1 13 ESE 0 2 5 1 0 1 9 SE 0 0 0 1 0 0 1 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 2 0 0 2 SW 0 0 0 1 0 0 1 WSW 0 0 0 0 0 0 0 W 0 0 0 1 1 1 3 WNW 0 0 1 0 1 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1 Variable 0 0 0 0 0 0 0 Total 2 16 12 9 4 3 46 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 53

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Slightly Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 5 1 0 0 9 NNE 0 1 0 1 0 0 2 NE 0 2 5 1 0 0 8 ENE 2 1 4 0 1 0 8 E 0 5 3 2 0 0 10 ESE 0 5 3 0 2 0 10 SE 0 0 8 2 0 0 10 SSE 0 0 5 0 1 0 6 S 0 0 2 2 1 0 5 SSW 0 0 0 3 0 0 3 SW 0 0 0 7 0 0 7 WSW 0 0 0 2 0 0 2 W 0 1 0 6 0 1 8 WNW 0 0 0 4 10 0 14 NW 0 0 4 5 1 3 13 NNW 0 2 12 4 0 0 18 Variable 0 0 0 0 0 0 0 Total 2 20 51 40 16 4 133 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 54

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Neutral - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 12 24 14 1 0 54 NNE 1 4 7 6 0 0 18 NE 2 3 30 2 1 0 38 ENE 3 19 36 7 0 0 65 E 4 23 34 11 5 6 83 ESE 4 26 33 11 8 1 83 SE 3 12 36 19 6 3 79 SSE 2 11 29 21 5 2 70 S 1 9 57 32 10 3 112 SSW 0 9 16 2 0 0 27 SW 2 1 18 10 1 0 32 WSW 1 6 8 15 7 0 37 W 0 3 24 27 14 17 85 WNW 0 12 22 39 36 15 124 NW 1 11 54 56 35 25 182 NNW 2 14 40 42 9 5 112 Variable 0 0 0 0 0 0 0 Total 29 175 468 314 138 77 1201 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 55

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Slightly Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 6 11 7 0 0 28 NNE 5 10 2 0 1 0 18 NE 5 6 11 2 0 0 24 ENE 3 6 9 1 0 0 19 E 6 6 14 3 0 0 29 ESE 1 17 13 1 0 0 32 SE 3 8 9 2 0 0 22 SSE 4 7 11 7 3 0 32 S 4 10 27 17 7 1 66 SSW 2 16 21 8 1 0 48 SW 3 14 15 18 0 0 50 WSW 0 5 15 24 3 0 47 W 2 2 12 23 1 0 40 WNW 0 5 17 18 3 0 43 NW 1 8 20 30 4 0 63 NNW 1 3 19 8 0 0 31 Variable 0 0 0 0 0 0 0 Total 44 129 226 169 23 1 592 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 56

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Moderately Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 5 2 0 0 10 NNE 1 1 1 0 0 0 3 NE 0 2 0 0 0 0 2 ENE 0 1 0 0 0 0 1 E 0 1 2 0 0 0 3 ESE 1 1 2 0 0 0 4 SE 1 2 4 0 0 0 7 SSE 2 4 2 0 0 0 8 S 1 0 0 1 0 0 2 SSW 3 6 2 0 0 0 11 SW 0 3 6 4 0 0 13 WSW 0 1 7 10 3 0 21 W 2 4 4 7 0 0 17 WNW 0 2 4 8 0 0 14 NW 1 6 7 2 0 0 16 NNW 0 0 2 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 12 37 48 34 3 0 134 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 57

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: April - June 2020 Stability Class - Extremely Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 1 0 0 0 0 1 S 0 0 0 0 0 0 0 SSW 0 1 1 0 0 0 2 SW 0 2 2 0 0 0 4 WSW 0 2 0 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 1 1 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 1 0 0 0 0 1 Variable 0 0 0 0 0 0 0 Total 0 8 4 1 0 0 13 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 10 58

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 20 21 2 1 0 0 44 NNE 20 14 1 0 0 0 35 NE 13 0 0 0 0 0 13 ENE 13 0 0 0 0 0 13 E 13 3 0 0 0 0 16 ESE 6 3 0 0 0 0 9 SE 2 17 5 0 0 0 24 SSE 9 17 7 0 0 0 33 S 0 9 15 0 0 0 24 SSW 1 4 4 0 0 0 9 SW 1 1 3 0 0 0 5 WSW 1 3 1 0 0 0 5 W 1 3 2 0 0 0 6 WNW 1 1 1 0 0 0 3 NW 1 3 7 1 0 0 12 NNW 5 8 5 2 0 0 20 Variable 0 0 0 0 0 0 0 Total 107 107 53 4 0 0 271 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 59

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 11 2 0 0 0 22 NNE 12 3 0 0 0 0 15 NE 9 0 0 0 0 0 9 ENE 4 0 0 0 0 0 4 E 6 0 0 0 0 0 6 ESE 2 1 0 0 0 0 3 SE 3 2 1 0 0 0 6 SSE 4 24 4 0 0 0 32 S 2 15 4 0 0 0 21 SSW 1 7 3 0 0 0 11 SW 0 8 2 0 0 0 10 WSW 2 10 5 0 0 0 17 W 2 12 1 0 0 0 15 WNW 2 6 0 0 0 0 8 NW 3 3 1 0 0 0 7 NNW 5 15 13 0 0 0 33 Variable 0 0 0 0 0 0 0 Total 66 117 36 0 0 0 219 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 60

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 1 5 0 0 0 11 NNE 10 3 0 0 0 0 13 NE 2 0 0 0 0 0 2 ENE 2 0 0 0 0 0 2 E 2 0 0 0 0 0 2 ESE 1 0 0 0 0 0 1 SE 1 3 0 0 0 0 4 SSE 2 13 2 0 0 0 17 S 1 5 0 0 0 0 6 SSW 4 6 1 0 0 0 11 SW 1 5 3 0 0 0 9 WSW 1 1 7 0 0 0 9 W 1 5 2 0 0 0 8 WNW 0 2 2 0 0 0 4 NW 4 7 1 0 0 0 12 NNW 2 7 6 0 0 0 15 Variable 0 0 0 0 0 0 0 Total 39 58 29 0 0 0 126 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 61

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 30 36 14 0 0 0 80 NNE 11 7 0 0 0 0 18 NE 9 0 0 0 0 0 9 ENE 8 0 0 0 0 0 8 E 6 0 0 0 0 0 6 ESE 7 1 0 0 0 0 8 SE 11 12 11 0 0 0 34 SSE 13 68 17 0 0 0 98 S 17 29 1 0 0 0 47 SSW 11 18 2 0 0 0 31 SW 15 16 9 0 0 0 40 WSW 14 18 4 0 0 0 36 W 16 14 4 0 0 0 34 WNW 14 18 3 0 0 0 35 NW 18 13 2 0 0 0 33 NNW 12 29 11 0 0 0 52 Variable 0 0 0 0 0 0 0 Total 212 279 78 0 0 0 569 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 62

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 35 12 1 0 0 0 48 NNE 18 4 0 0 0 0 22 NE 8 0 0 0 0 0 8 ENE 4 0 0 0 0 0 4 E 10 2 0 0 0 0 12 ESE 13 2 0 0 0 0 15 SE 13 3 0 0 0 0 16 SSE 30 24 4 0 0 0 58 S 30 28 1 0 0 0 59 SSW 55 20 1 0 0 0 76 SW 33 19 5 0 0 0 57 WSW 43 41 4 1 0 0 89 W 43 27 0 0 0 0 70 WNW 37 16 0 1 0 0 54 NW 39 24 2 0 0 0 65 NNW 26 13 1 0 0 0 40 Variable 0 0 0 0 0 0 0 Total 437 235 19 2 0 0 693 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 63

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 1 0 0 0 0 3 NNE 0 0 0 0 0 0 0 NE 2 0 0 0 0 0 2 ENE 1 0 0 0 0 0 1 E 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 1 0 0 0 0 0 1 S 3 4 0 0 0 0 7 SSW 16 4 0 0 0 0 20 SW 19 6 0 0 0 0 25 WSW 34 46 0 0 0 0 80 W 33 24 1 0 0 0 58 WNW 12 11 0 0 0 0 23 NW 7 4 0 0 0 0 11 NNW 6 0 0 0 0 0 6 Variable 0 0 0 0 0 0 0 Total 137 100 1 0 0 0 238 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 64

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 1 0 0 0 0 0 1 SW 11 28 0 0 0 0 39 WSW 24 17 0 0 0 0 41 W 6 3 0 0 0 0 9 WNW 0 1 0 0 0 0 1 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 43 49 0 0 0 0 92 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 65

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Extremely Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 1 0 0 1 NE 0 1 2 2 0 0 5 ENE 0 3 3 0 0 0 6 E 0 7 0 1 0 0 8 ESE 0 1 6 1 0 0 8 SE 0 0 3 1 0 0 4 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 12 14 6 0 0 32 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 66

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Moderately Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 0 1 NNE 0 2 3 0 0 0 5 NE 0 1 1 0 0 0 2 ENE 0 3 1 0 0 0 4 E 0 5 0 0 0 0 5 ESE 0 1 0 0 0 0 1 SE 0 2 5 0 0 0 7 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 14 11 0 0 0 25 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 67

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Slightly Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 1 1 0 0 3 NNE 1 2 0 1 0 0 4 NE 1 7 1 0 0 0 9 ENE 4 4 0 0 0 0 8 E 1 6 1 0 1 0 9 ESE 0 1 1 0 0 0 2 SE 0 3 3 2 0 0 8 SSE 0 1 1 2 0 0 4 S 0 0 10 5 0 0 15 SSW 0 0 2 1 0 0 3 SW 0 0 0 0 0 0 0 WSW 0 0 1 0 1 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 1 0 0 0 1 NNW 0 0 2 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 7 25 24 12 2 0 70 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 68

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Neutral - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 18 15 27 4 0 71 NNE 7 22 13 13 2 1 58 NE 14 12 14 6 1 0 47 ENE 16 25 3 1 0 0 45 E 7 21 16 7 0 0 51 ESE 8 20 21 10 5 0 64 SE 4 19 23 15 1 0 62 SSE 5 28 28 16 0 0 77 S 3 30 60 13 0 0 106 SSW 3 12 30 6 0 0 51 SW 10 24 15 14 0 0 63 WSW 5 18 15 11 5 1 55 W 3 12 25 14 2 0 56 WNW 2 7 11 7 3 0 30 NW 3 16 29 11 4 1 64 NNW 5 19 28 20 3 1 76 Variable 0 0 0 0 0 0 0 Total 102 303 346 191 30 4 976 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 69

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Slightly Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 13 18 8 2 0 47 NNE 5 8 12 3 0 0 28 NE 10 17 6 7 0 0 40 ENE 7 17 7 2 1 0 34 E 4 32 20 0 0 0 56 ESE 6 21 7 5 0 0 39 SE 12 12 5 2 0 0 31 SSE 7 18 23 11 0 0 59 S 5 27 34 23 1 0 90 SSW 9 27 33 19 1 0 89 SW 8 26 26 11 3 0 74 WSW 8 19 12 17 4 0 60 W 2 11 21 23 3 0 60 WNW 3 7 14 19 1 0 44 NW 3 10 15 13 2 0 43 NNW 5 13 11 20 1 0 50 Variable 0 0 0 0 0 0 0 Total 100 278 264 183 19 0 844 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 70

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Moderately Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 4 2 0 0 0 7 NNE 2 3 6 0 0 0 11 NE 3 2 1 0 0 0 6 ENE 2 5 1 1 0 0 9 E 2 1 0 0 0 0 3 ESE 1 2 0 0 0 0 3 SE 3 4 0 0 0 0 7 SSE 2 6 1 0 0 0 9 S 0 4 3 5 0 0 12 SSW 0 5 1 5 0 0 11 SW 0 2 7 2 0 0 11 WSW 0 0 9 13 3 0 25 W 0 6 4 7 5 0 22 WNW 1 0 3 10 4 0 18 NW 2 3 11 18 0 0 34 NNW 5 4 12 4 0 0 25 Variable 0 0 0 0 0 0 0 Total 24 51 61 65 12 0 213 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 71

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Power Atomic Station Period of Record: July - September 2020 Stability Class - Extremely Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 1 0 0 0 5 NNE 1 2 1 0 0 0 4 NE 0 3 1 0 0 0 4 ENE 1 3 0 0 0 0 4 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 3 0 0 0 0 3 SSE 3 1 0 0 0 0 4 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 2 0 0 0 2 WSW 0 0 1 3 0 0 4 W 0 0 0 2 0 0 2 WNW 2 1 0 0 0 0 3 NW 0 0 1 0 0 0 1 NNW 0 4 5 1 0 0 10 Variable 0 0 0 0 0 0 0 Total 7 21 12 6 0 0 46 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 72

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October -

December2020 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 8 1 0 0 0 12 NNE 5 2 1 0 0 0 8 NE 9 1 0 0 0 0 10 ENE 14 2 0 0 0 0 16 E 9 1 0 0 0 0 10 ESE 3 8 1 0 0 0 12 SE 10 6 7 4 0 0 27 SSE 8 8 7 1 0 0 24 S 4 9 13 1 0 0 27 SSW 4 2 5 1 0 0 12 SW 7 3 5 0 0 0 15 WSW 2 2 0 0 0 0 4 W 3 2 1 2 0 0 8 WNW 3 1 1 0 0 0 5 NW 9 6 5 0 0 0 20 NNW 4 8 3 0 0 0 15 Variable 0 0 0 0 0 0 0 Total 97 69 50 9 0 0 225 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 73

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 4 1 0 0 0 10 NNE 1 3 1 0 0 0 5 NE 3 1 0 0 0 0 4 ENE 2 1 0 0 0 0 3 E 8 1 0 0 0 0 9 ESE 3 1 0 0 0 0 4 SE 0 2 0 0 0 0 2 SSE 3 4 2 0 0 0 9 S 2 10 10 1 0 0 23 SSW 0 2 8 0 0 0 10 SW 1 1 3 1 0 0 6 WSW 0 1 2 3 0 0 6 W 0 7 8 3 0 0 18 WNW 1 2 4 2 0 0 9 NW 0 4 6 3 0 0 13 NNW 1 8 15 4 0 0 28 Variable 0 0 0 0 0 0 0 Total 30 52 60 17 0 0 159 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 74

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December 2020 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 3 3 0 0 0 9 NNE 3 2 0 0 0 0 5 NE 2 1 0 0 0 0 3 ENE 2 0 0 0 0 0 2 E 2 0 0 0 0 0 2 ESE 1 0 0 0 0 0 1 SE 0 1 3 0 0 0 4 SSE 0 3 1 0 0 0 4 S 2 4 4 1 0 0 11 SSW 2 1 0 0 0 0 3 SW 0 2 1 0 0 0 3 WSW 2 1 0 1 0 0 4 W 0 4 5 1 0 0 10 WNW 0 4 10 2 0 0 16 NW 0 5 4 7 0 0 16 NNW 0 8 15 7 0 0 30 Variable 0 0 0 0 0 0 0 Total 19 39 46 19 0 0 123 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 75

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 26 7 0 0 0 46 NNE 19 24 0 0 0 0 43 NE 17 17 0 0 0 0 34 ENE 7 0 0 0 0 0 7 E 17 1 0 0 0 0 18 ESE 10 5 0 0 0 0 15 SE 6 30 10 1 0 0 47 SSE 12 68 12 1 0 0 93 S 5 38 10 3 0 0 56 SSW 9 13 7 0 0 0 29 SW 5 12 14 1 0 0 32 WSW 3 11 25 7 0 0 46 W 2 16 33 3 0 0 54 WNW 4 34 28 7 0 0 73 NW 5 33 53 22 0 0 113 NNW 9 57 31 6 0 0 103 Variable 0 0 0 0 0 0 0 Total 143 385 230 51 0 0 809 Hours of calm in this stability class: 4 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 76

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 0 0 0 0 0 11 NNE 5 0 0 0 0 0 5 NE 13 1 0 0 0 0 14 ENE 9 0 0 0 0 0 9 E 24 1 0 1 0 0 26 ESE 26 7 0 0 0 0 33 SE 24 17 2 0 0 0 43 SSE 15 46 0 0 0 0 61 S 26 38 3 0 0 0 67 SSW 17 6 0 0 0 0 23 SW 11 11 0 1 0 0 23 WSW 13 38 8 0 0 0 59 W 16 58 10 1 0 0 85 WNW 17 38 1 0 0 0 56 NW 9 27 6 0 0 0 42 NNW 4 9 2 0 0 0 15 Variable 0 0 0 0 0 0 0 Total 240 297 32 3 0 0 572 Hours of calm in this stability class: 4 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 77

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 2 0 0 0 0 0 2 NE 4 0 0 0 0 0 4 ENE 5 0 0 0 0 0 5 E 12 0 0 0 0 0 12 ESE 13 0 0 0 0 0 13 SE 8 0 0 0 0 0 8 SSE 4 1 0 0 0 0 5 S 6 3 0 0 0 0 9 SSW 9 3 0 0 0 0 12 SW 13 8 0 0 0 0 21 WSW 19 13 1 0 0 0 33 W 16 26 0 0 0 0 42 WNW 5 5 0 0 0 0 10 NW 3 2 0 0 0 0 5 NNW 5 0 0 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 124 61 1 0 0 0 186 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 78

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 0 0 0 0 2 NNE 2 0 0 0 0 0 2 NE 2 0 0 0 0 0 2 ENE 6 0 0 0 0 0 6 E 8 0 0 0 0 0 8 ESE 4 0 0 0 0 0 4 SE 3 0 0 0 0 0 3 SSE 2 0 0 0 0 0 2 S 1 0 0 0 0 0 1 SSW 5 0 0 0 0 0 5 SW 10 5 0 0 0 0 15 WSW 26 7 0 0 0 0 33 W 13 4 0 0 0 0 17 WNW 5 1 0 0 0 0 6 NW 2 0 0 0 0 0 2 NNW 2 0 0 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 93 17 0 0 0 0 110 Hours of calm in this stability class: 12 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 1 79

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Extremely Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 0 0 1 0 0 0 1 SE 0 0 1 1 0 0 2 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 1 2 1 0 0 4 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 80

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Moderately Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 0 0 1 0 0 0 1 SE 0 0 2 1 0 0 3 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 1 0 3 1 0 0 5 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 81

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October -

December2020 Stability Class - Slightly Unstable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 0 1 0 0 0 0 1 ESE 0 2 0 0 0 0 2 SE 0 0 4 0 0 0 4 SSE 0 0 0 0 0 0 0 S 0 0 0 3 2 0 5 SSW 0 0 0 6 1 0 7 SW 0 0 1 1 0 0 2 WSW 0 0 0 0 0 0 0 W 0 0 0 0 3 0 3 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 4 6 10 6 0 26 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 82

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Neutral - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 12 24 21 2 0 62 NNE 6 12 18 9 0 0 45 NE 3 6 24 8 0 0 41 ENE 3 10 17 22 0 0 52 E 3 15 14 1 0 0 33 ESE 0 10 2 1 0 0 13 SE 2 16 12 7 3 2 42 SSE 1 5 37 20 6 1 70 S 3 16 58 39 7 3 126 SSW 2 5 27 16 6 0 56 SW 4 8 15 8 4 0 39 WSW 0 3 8 23 14 2 50 W 0 6 17 31 19 0 73 WNW 0 4 14 42 22 10 92 NW 0 7 25 54 39 14 139 NNW 0 17 80 41 13 0 151 Variable 0 0 0 0 0 0 0 Total 30 152 392 343 135 32 1084 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 83

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Slightly Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 9 8 7 0 0 0 24 NNE 3 7 1 0 0 0 11 NE 5 7 1 1 0 0 14 ENE 5 7 0 1 0 0 13 E 5 7 3 2 1 0 18 ESE 3 10 5 2 1 0 21 SE 3 25 19 3 2 0 52 SSE 3 18 27 17 5 0 70 S 1 26 54 52 0 0 133 SSW 2 13 35 21 0 0 71 SW 4 12 12 12 1 0 41 WSW 1 8 20 14 4 0 47 W 3 4 10 30 9 3 59 WNW 1 5 8 54 3 0 71 NW 4 13 34 45 5 0 101 NNW 1 10 34 9 1 0 55 Variable 0 0 0 0 0 0 0 Total 53 180 270 263 32 3 801 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 84

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Moderately Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 4 0 0 0 0 5 NNE 0 3 0 0 0 0 3 NE 0 0 0 0 0 0 0 ENE 1 0 0 0 0 0 1 E 0 1 1 0 0 0 2 ESE 1 4 1 0 0 0 6 SE 1 9 6 0 0 0 16 SSE 1 7 3 0 0 0 11 S 1 7 21 1 1 0 31 SSW 1 5 9 6 0 0 21 SW 1 15 5 1 0 0 22 WSW 2 4 7 1 0 0 14 W 1 4 5 7 0 0 17 WNW 1 4 5 4 1 0 15 NW 0 4 10 8 0 0 22 NNW 0 3 1 0 0 0 4 Variable 0 0 0 0 0 0 0 Total 12 74 74 28 2 0 190 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 85

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Atomic Power Station Period of Record: October - December2020 Stability Class - Extremely Stable - 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 0 0 0 0 2 NNE 1 0 0 0 0 0 1 NE 0 2 0 0 0 0 2 ENE 2 2 0 0 0 0 4 E 1 0 0 0 0 0 1 ESE 2 1 0 0 0 0 3 SE 0 1 0 0 0 0 1 SSE 2 3 0 0 0 0 5 S 3 2 0 0 0 0 5 SSW 1 2 2 0 0 0 5 SW 2 5 2 0 0 0 9 WSW 0 5 6 0 0 0 11 W 0 4 11 1 0 0 16 WNW 2 7 4 1 0 0 14 NW 0 9 4 0 0 0 13 NNW 1 2 2 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 18 46 31 2 0 0 97 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 86

Peach Bottom Atomic Power Station Licensee: Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Appendix A: ODCM and Appendix A Revisions 87

January 2020 APPENDIX A RADIOACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES FOR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 REVISION 15

January 2020 RADIOACTIVE EFFLUENTS CONTROLS PROGRAM TABLE OF CONTENTS 3.8.A Definitions....................................... ODCM 3.8.A-1 3.8.B Liquid Radwaste Effluents......................... ODCM 3.8.B-1 3.8.C Gaseous Effluents................................. ODCM 3.8.C-1 3.8.D 40 CFR 190 and 10 CFR 72.104...................... ODCM 3.8.D-1 3.8.E Radiological Environmental Monitoring............. ODCM 3.8.E-1 3.10 Reporting Requirements............................ ODCM 3.10-1 B 3.8 ODCM Specifications Bases......................... ODCM B 3.8-1 PBAPS Units 2 and 3 ODCM 3.8 Revision 15

January 2020 ODCMS 3.8.A Definitions

NOTE-----------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual Specifications and Bases.

Term Definition FUNCTIONAL TESTS A FUNCTIONAL TEST is the manual operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).

OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and all necessary attendant instrumentation, controls, normal and emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

GASEOUS RADWASTE Any system designed and installed to reduce TREATMENT SYSTEM radioactive gaseous effluents by collecting primary coolant system off gases from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

INSTRUMENT CALIBRATION An INSTRUMENT CALIBRATION means the adjustment of an instrument signal output so that it corresponds, within acceptable range, and accuracy, to a known value(s) of the parameter, which the instrument monitors. The INSTRUMENT CALIBRATION shall encompass the entire instrument including the sensors and alarm, interlock and/or trip functions and shall include the INSTRUMENT FUNCTIONAL TEST.

The known value of the parameter shall be injected into the instrument as close to the primary sensor as practicable.

PBAPS Units 2 and 3 ODCM 3.8.A-1 Revision 15

January 2020 ODCMS 3.8.A Definitions (continued)

INSTRUMENT CHECK An INSTRUMENT CHECK is a qualitative determination of acceptable FUNCTIONALITY by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.

INSTRUMENT FUNCTIONAL An INSTRUMENT FUNCTIONAL TEST means the TEST injection of a simulated signal into the instrument as close to the primary sensor as practicable to verify the FUNCTIONALITY including alarm and/or trip functions and channel failure trips.

MEMBERS OF THE PUBLIC MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE Contains the current methodology and CALCULATION MANUAL parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program.

FUNCTIONAL-FUNCTIONALITY An attribute of SSCs that is not controlled by TS. An SSC is functional or has functionality when it is capable of performing its specified function, as set forth in the CLB.

Functionality does not apply to specified safety functions, but does apply to the ability of non-TS SSCs to perform other specified functions that have a necessary support function.

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

PBAPS Units 2 and 3 ODCM 3.8.A-2 Revision 15

January 2020 ODCMS 3.8.A Definitions (continued)

SITE BOUNDARY That line beyond which the land is not owned, leased, or otherwise controlled by licensee as defined in Figure 3.8.A.1.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

GRAB SAMPLE A GRAB SAMPLE is a sampling technique in which a single sample or measurement is taken at a specific time. It may include the use of installed available instrumentation that, although potentially inoperable due to failed transmitter, remote indication, recording or alarm function, the component still provides a valid process measurement at a specific point in time.

Figure 3.8.A.1 SITE BOUNDARY (including gaseous and liquid effluent release points)

PBAPS Units 2 and 3 ODCM 3.8.A-3 Revision 15

Liquid Radwaste Effluents January 2020 3.8.B.1 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.1 The concentration of radioactive material released to areas at or beyond the SITE BOUNDARY shall be limited to:

a. 10 times the concentration specified in 10 CFR 20 Appendix B, Table 2, Column 2 for radionuclides other than noble gases; and
b. 2 X 10-4µCi/ml total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Concentration of A.1 Initiate actions to Immediately radioactive material decrease the release released to areas at rate of radioactive or beyond the SITE materials to restore BOUNDARY exceeding concentration to limits. within limits.

OR Immediately A.2 Initiate actions to increase the dilution flow rate to restore concentration within limits.

OR Immediately A.3 Initiate actions to decrease the release rate of radioactive materials and increase the dilution flow rate to restore concentration within limits.

PBAPS Units 2 and 3 ODCM 3.8.B-1 Revision 15

Liquid Radwaste Effluents January 2020 3.8.B.1 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.1.1 Take a sample of each batch of Prior to each liquid effluent and analyze for the release concentration of each significant gamma energy peak. Base the release rate on the circulating water flow rate at the time of discharge.

ODCMS 4.8.B.1.2 Record radioactive concentrations During each and volume before dilution of each release batch of liquid effluent released, the average dilution flow, and length of time over which each discharge occurred.

ODCMS 4.8.B.1.3 Perform radioactive liquid waste In accordance sampling and activity analysis. with Table 4.8.B.1 PBAPS Units 2 and 3 ODCM 3.8.B-2 Revision 15

Liquid Radwaste Effluents January 2020 3.8.B.1 Table 4.8.B.1 (Page 1 of 2)

Radioactive Liquid Waste Sampling and Analysis SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE LOWER FREQUENCY LIMIT OF DETECTION (LLD)

(a),(d),(e)

Waste Tank to Each batch Quantitative 5 X 10-7µCi/ml be released (b) Analysis of Identifiable Gamma Emitters I-131 1 X 10-6µCi/ml Proportional 31 days (c) Fe-55 1 X 10-6µCi/ml Composite of Batches Tritium 1 X 10-5µCi/ml Gross Alpha 1 X 10-7µCi/ml Proportional 31 days (c) Sr-89 5 X 10-8µCi/ml Composite of Batches Sr-90 5 X 10-8µCi/ml One Batch 31 days Dissolved noble 1 X 10-5µCi/ml gases (a) The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. The values for the lower limit of detection are based on a 95% confidence level.

(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure representative sampling.

(c) A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.

PBAPS Units 2 and 3 ODCM 3.8.B-3 Revision 15

Liquid Radwaste Effluents January 2020 3.8.B.1 Table 4.8.B.1 (Page 2 of 2)

Radioactive Liquid Waste Sampling and Analysis (d) The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than required, the reasons shall be documented in the Radioactive Effluent Release Report. The values listed are believed to be attainable.

(e) Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations. Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.

PBAPS Units 2 and 3 ODCM 3.8.B-4 Revision 15

Liquid Radwaste Effluents January 2020 3.8.B.2 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material in liquid effluent releases from the two reactors at the site to the areas at or beyond the SITE BOUNDARY shall be limited to:

a. 3.0 mrem to the total body and 10.0 mrem to any organ during any calendar quarter; and
b. 6.0 mrem to the total body and 20.0 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated dose A.1 Submit a Special report 31 days from the release to the NRC that will of radioactive identify cause(s) for materials in exceeding limits, liquid effluents action(s) taken exceeds required to reduce releases of limits. radioactive materials in liquid effluents, corrective action(s) taken to assure subsequent releases are within limits, results of radiological analyses of the drinking water source, and the radiological impact on the potentially affected drinking water supplies with regard to 40 CFR 141, Safe Drinking Water Act.

PBAPS Units 2 and 3 ODCM 3.8.B-5 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.2.1 Determine cumulative dose contributions 31 days in accordance with the methodology and parameters in the ODCM.

PBAPS Units 2 and 3 ODCM 3.8.B-6 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.3 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.3 The following conditions shall be met:

a. Dilution water flow rates necessary to satisfy requirements of ODCMS 3.8.B.1 shall be maintained;
b. The gross activity monitor and the flow monitor on the waste effluent line shall be FUNCTIONAL; and
c. The liquid effluent control monitor shall be set in accordance with methodology and parameters in the ODCM to alarm and automatically close the waste discharge valve prior to exceeding limits in ODCMS 3.8.B.1; and
d. The service water, emergency service water, and high pressure service water effluent line radiation monitors shall be FUNCTIONAL.

APPLICABILITY: During release of radioactive wastes or with flow present in the system.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gross activity A.1 Initiate action to Immediately monitor on the restore monitor to waste activity FUNCTIONAL status.

line inoperable.

AND A.2 Analyze two Prior to independent samples release of tank's contents.

AND A.3 Perform independent Prior to verification of the release release rate calculations and discharge line valve line-up using at least two technically qualified members of the facility staff.

(Continued)

PBAPS Units 2 and 3 ODCM 3.8.B-7 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.3 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Flow monitor on B.1 Initiate action to Immediately the waste effluent restore monitor to line inoperable. FUNCTIONAL status.

AND B.2 --------NOTE-------

Pump performance curves may be used to estimate flow.

Estimate waste effluent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> line flow rate.

AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter C. Required C.1 Suspend release of Immediately Compensatory radioactive effluents Measures and via this pathway.

associated Completion Time of Condition A or B not met.

OR Dilution water flow rates not satisfying requirements of ODCMS 3.8.B.1.

D. Radiation monitor D.1 Collect grab samples and At least once on service water, analyze for radioactivity per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> emergency service at the lower limit of water, or high detection defined in pressure service Table 4.8.B.1.

water effluent line inoperable.

(Continued)

PBAPS Units 2 and 3 ODCM 3.8.B-8 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.3 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME E. Liquid radwaste E.1 Explain why the In accordance effluents inoperability was not with radiation monitors corrected in a timely Technical inoperable for > manner in the next Specification 30 days. Annual Radioactive 5.6.3 Effluent Release Report.

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.1 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radwaste effluents radiation monitor. during release ODCMS 4.8.B.3.2 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> effluent flow monitor. during release ODCMS 4.8.B.3.3 Perform INSTRUMENT FUNCTIONAL TEST of 31 days liquid radwaste effluents radiation monitor, including FUNCTIONALITY demonstration of the radwaste discharge automatic isolation valve and control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.

ODCMS 4.8.B.3.4 Perform SOURCE CHECK of liquid 92 days radwaste effluents radiation monitor.

ODCMS 4.8.B.3.5 Perform INSTRUMENT CALIBRATION of the 12 months liquid radwaste effluents radiation monitor with a known radiation source positioned in a reproducible geometry with respect to the sensor. (Continued)

PBAPS Units 2 and 3 ODCM 3.8.B-9 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.3 ODCMS REQUIREMENTS (Continued)

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.6 Perform INSTRUMENT CALIBRATION of the 12 months liquid effluents flow monitor.

ODCMS 4.8.B.3.7 Perform INSTRUMENT CHECK of service 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> water effluent line radiation during monitor. release ODCMS 4.8.B.3.8 Perform INSTRUMENT FUNCTIONAL TEST of 92 days service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.

ODCMS 4.8.B.3.9 Perform SOURCE CHECK of service water 31 days effluent line radiation monitor.

ODCMS 4.8.B.3.10 Perform INSTRUMENT CALIBRATION of the 18 months service water effluent line radiation monitor with a known radiation source.

ODCMS 4.8.B.3.11 Perform INSTRUMENT CHECK of emergency 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> service water effluent line radiation during monitor. release ODCMS 4.8.B.3.12 Perform INSTRUMENT FUNCTIONAL TEST of 92 days emergency service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure. (Continued)

PBAPS Units 2 and 3 ODCM 3.8.B-10 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.3 ODCMS REQUIREMENTS (Continued)

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.13 Perform SOURCE CHECK of emergency 31 days service water effluent line radiation monitor.

ODCMS 4.8.B.3.14 Perform INSTRUMENT CALIBRATION of the 18 months emergency service water effluent line radiation monitor with a known radiation source.

ODCMS 4.8.B.3.15 Perform INSTRUMENT CHECK of high 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pressure service water effluent line during radiation monitor. release ODCMS 4.8.B.3.16 Perform INSTRUMENT FUNCTIONAL TEST of 92 days high pressure service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.

ODCMS 4.8.B.3.17 Perform SOURCE CHECK of high pressure 31 days service water effluent line radiation monitor.

ODCMS 4.8.B.3.18 Perform INSTRUMENT CALIBRATION of the 18 months high pressure service water effluent line radiation monitor with a known radiation source.

PBAPS Units 2 and 3 ODCM 3.8.B-11 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.4 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.4 Liquid effluent releases shall be processed through one of the radwaste subsystems or combination of subsystems listed below:

a. waste collector filter and demineralizer;
b. floor drain filter and demineralizer;
c. fuel pool filter demineralizer;
d. chemical/oily waste cleanup subsystem;
e. laundry drain filter APPLICABILITY: Prior to all liquid effluent release(s) whenever the release(s) would cause the projected dose, when it is averaged over 31 days to exceed 0.12 mrem to the total body or 0.4 mrem to any organ (combined total from the two reactors at the site).

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Liquid waste A.1 Submit a Special Report 31 days discharged without to the NRC that includes, required an explanation of why processing. liquid radwaste was discharged without required processing, identification of any inoperable equipment or subsystems and the reason for the inoperability, the action taken to restore the inoperable equipment to FUNCTIONAL status, and the action(s) taken.

PBAPS Units 2 and 3 ODCM 3.8.B-12 Revision 15

January 2020 Liquid Radwaste Effluents 3.8.B.4 ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.4.1 Project doses due to liquid 31 days effluent releases to areas at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

ODCMS 4.8.B.4.2 Demonstrate FUNCTIONALITY of the 92 days waste collector filter and demineralizer and the floor drain filter by analyzing the liquid processed through the subsystem and determining it meets the requirements of ODCMS 3.8.B.1.

ODCMS 4.8.B.4.3 Demonstrate FUNCTIONALITY of the Prior to release fuel pool filter demineralizer of liquid by analyzing the liquid effluents processed through the subsystem processed by this and determining it meets the subsystem requirements of ODCMS 3.8.B.1.

ODCMS 4.8.B.4.4 Demonstrate FUNCTIONALITY of the Prior to release chemical/oily waste cleanup of liquid subsystem by analyzing the effluents liquid processed through the processed by this subsystem and determining it subsystem meets the requirements of ODCMS 3.8.B.1.

ODCMS 4.8.B.4.5 Demonstrate FUNCTIONALITY of the Prior to release laundry drain filter by of liquid analyzing the liquid processed effluents through the subsystem and processed by this determining it meets the subsystem requirements of ODCMS 3.8.B.1.

PBAPS Units 2 and 3 ODCM 3.8.B-13 Revision 15

January 2020 Gaseous Effluents 3.8.C.1 3.8.C Gaseous Effluents ODCMS 3.8.C.1 The dose rate at or beyond the SITE BOUNDARY due to radioactive materials in gaseous effluents released from the two reactors at the site shall be limited to the following:

a. For noble gases, 500 mrem per year to the total body and 3000 mrem per year to the skin; and
b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, 1500 mrem per year to any organ.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Dose rates at or beyond A.1 Initiate actions Immediately the SITE BOUNDARY exceed to decrease limits due to release rates to radioactive material in comply with gaseous effluents. limits.

ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.1.1 Verify the dose rate due to noble In accordance gases in gaseous effluents is with sampling within limits in accordance with and analysis methods and procedures of the program ODCM. specified in Table 4.8.C.1 (continued)

PBAPS Units 2 and 3 ODCM 3.8.C-1 Revision 15

January 2020 Gaseous Effluents 3.8.C.1 ODCMS REQUIREMENTS (Continued)

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.1.2 Obtain representative samples and In accordance verify the dose rate due to with sampling iodine-131, iodine-133, tritium, and analysis and all radionuclides in program particulate form with half lives specified in

> 8 days in gaseous effluents are Table 4.8.C.1 within limits in accordance with the methods and procedures of the ODCM.

PBAPS Units 2 and 3 ODCM 3.8.C-2 Revision 15

January 2020 Gaseous Effluents 3.8.C.1 Table 4.8.C.1 (page 1 of 2)

Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stacks SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE FREQUENCY LOWER LIMIT OF DETECTION (LLD)

(a)(d)

Grab Sample 31 days (b) Quantitative analysis 1 X 10-4µCi/cc(c) of identifiable gamma emitters Grab Sample 92 days Tritium 1 X 10-6µCi/cc Charcoal 7 days (c) I-131 1 X 10-12µCi/cc(c)

Filters Particulate 7 days (c) Quantitative analysis 1 X 10-11µCi/cc(c)

Filters of identifiable gamma emitters I-131 1 X 10-12µCi/cc(c)

Particulate 31 days Gross Alpha 1 X 10-11µCi/cc Filters (composite of weekly filters)

Particulate 31 days Sr-89 1 X 10-11µCi/cc Filters (composite of Sr-90 1 X 10-11µCi/cc weekly filters)

Noble Gas Continuously Noble Gas Gross or 1 X 10-6µCi/cc Monitor (Main Stack)

Noble Gas Continuously Noble Gas Gross or 1 X 10-6µCi/cc Monitor (Roof Vents)

PBAPS Units 2 and 3 ODCM 3.8.C-3 Revision 15

January 2020 Gaseous Effluents 3.8.C.1 Table 4.8.C.1 (page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stacks (a) The sample lower limit of detection is defined as an a priori (before the fact) limit representing the capability of measurement system and not as an a posteriori (after the fact) limit for a particular measurement. The values for the lower limit of detection are based on a 95% confidence level.

(b) Sampling and analysis shall be performed following shutdown, startup or a thermal power change exceeding 15% of rated thermal power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from a steady state condition unless (1) analysis shows that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

(c) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days following each shutdown, startup or thermal power change exceeding 15% of rated thermal power in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD may be increased by a factor of 10. This requirement does not apply if (1) analysis has shown that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(d) Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations. Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides. Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level.

PBAPS Units 2 and 3 ODCM 3.8.C-4 Revision 15

January 2020 Gaseous Effluents 3.8.C.2 3.8.C Gaseous Effluents ODCMS 3.8.C.2 The air dose at or beyond the SITE BOUNDARY due to noble gases in gaseous effluents released from the two reactors at the site shall be limited to the following:

a. For gamma radiation, 10 mrad during any calendar quarter;
b. For beta radiation, 20 mrad during any calendar quarter;
c. For gamma radiation, 20 mrad during any calendar year; and
d. For beta radiation, 40 mrad during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated air dose A.1 Submit a Special 31 days at or beyond the Report to the NRC that SITE BOUNDARY from identifies causes for radioactive noble exceeding limits, gases in gaseous corrective actions effluents exceeds taken to reduce the limits. releases, and corrective actions to assure that subsequent releases are within limits.

PBAPS Units 2 and 3 ODCM 3.8.C-5 Revision 15

January 2020 Gaseous Effluents 3.8.C.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.2.1 Determine cumulative dose contributions 31 days for noble gases in accordance with the methodology and parameters in the ODCM.

PBAPS Units 2 and 3 ODCM 3.8.C-6 Revision 15

January 2020 Gaseous Effluents 3.8.C.3 3.8.C Gaseous Effluents ODCMS 3.8.C.3 The dose to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium and all radionuclides in particulate form, with half lives > 8 days, in gaseous effluents released from the two reactors at the site shall be limited to:

a. 15 mrem during any calendar quarter; and
b. 30 mrem during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated dose from A.1 Submit a Special 31 days the release of Report to the NRC that iodine-131, identifies causes for iodine-133, tritium exceeding limits, and radionuclides in corrective actions particulate form, taken, and proposed with half-lives corrective actions to

> 8 days in gaseous assure that subsequent effluents exceeds releases are within limits. limits.

PBAPS Units 2 and 3 ODCM 3.8.C-7 Revision 15

January 2020 Gaseous Effluents 3.8.C.3 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.3.1 Determine cumulative dose contributions 31 days for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days in accordance with the methodology and parameters in the ODCM.

PBAPS Units 2 and 3 ODCM 3.8.C-8 Revision 15

January 2020 Gaseous Effluents 3.8.C.4 3.8.C Gaseous Effluents ODCMS 3.8.C.4 The following conditions shall be met:

a. Main stack dilution flow shall be 10,000 cfm;
b. One vent stack noble gas monitor and one main stack noble gas monitor shall be FUNCTIONAL and set to alarm in accordance with the methodology and parameters in the ODCM;
c. One vent stack iodine filter and one main stack iodine filter and one vent stack particulate filter and one main stack particulate filter with their respective flow rate monitors shall be FUNCTIONAL; and
d. One vent stack flow rate monitor and one main stack flow rate monitor shall be FUNCTIONAL and set to alarm in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: During release of radioactive wastes.

PBAPS Units 2 and 3 ODCM 3.8.C-9 Revision 15

January 2020 Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES

NOTE-----------------------------------

Separate condition entry is allowed for each instrument.

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One required vent A.1 Collect two 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> stack noble gas independent grab monitor inoperable. samples from the AND affected effluent OR release pathway. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> One required main thereafter stack noble gas AND monitor inoperable.

A.2 -------NOTE---------

Perform independent verification of the release rate calculations using at least two technically qualified members of the facility staff.

Analyze grab samples 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from from the affected time of release pathway for collection activity.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.C-10 Revision 15

January 2020 Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. One required vent B.1 Initiate action to Immediately stack iodine filter collect samples from inoperable. the affected effluent release pathway OR continuously with auxiliary sampling One required vent equipment such that stack particulate each sample period filter inoperable. duration is approximately 7 days.

OR AND One required main 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after stack iodine filter B.2 Analyze collected end of each inoperable. samples. sampling period OR One required main stack particulate filter inoperable.

C. One required vent C.1 Estimate flow rate 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stack flow rate from the affected monitor inoperable. effluent release AND pathway.

OR Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> One required main thereafter stack flow rate monitor inoperable.

D. Main off-gas stack D.1 Initiate action to re- Immediately dilution flow establish main off-gas

< 10,000 cfm. stack flow 10,000 cfm.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.C-11 Revision 15

January 2020 Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME E. One or more E.1 Explain why the In required inoperability was not accordance radioactive corrected in a timely with gaseous effluent manner in the next Annual Technical monitoring Radioactive Effluent Specification instrumentation Release Report. 5.6.3 channels inoperable for

> 30 days.

ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.1 Perform INSTRUMENT CHECK of the vent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> stack and main stack noble gas radiation monitors.

ODCMS 4.8.C.4.2 Perform INSTRUMENT CHECK of the vent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> stack and the main stack flow rate monitors.

ODCMS 4.8.C.4.3 Section Removed ODCMS 4.8.C.4.4 Perform INSTRUMENT FUNCTIONAL TEST of 92 days the vent stack and main stack noble gas radiation monitors, including control room alarm annunciation in response to alarm setpoint being exceeded and an instrument downscale failure.

ODCMS 4.8.C.4.5 Section Removed (Continued)

PBAPS Units 2 and 3 ODCM 3.8.C-12 Revision 15

January 2020 Gaseous Effluents 3.8.C.4 ODCMS REQUIREMENTS (Continued)

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.6 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack noble gas radiation monitors with a known radioactive source positioned in a reproducible geometry with respect to the sensor.

ODCMS 4.8.C.4.7 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack flow rate monitors.

ODCMS 4.8.C.4.8 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack iodine and particulate sample flow rate monitors.

ODCMS 4.8.C.4.9 Section Removed ODCMS 4.8.C.4.10 Perform SOURCE CHECK of vent stack and 92 days main stack noble gas radiation monitors.

ODCMS 4.8.C.4.11 Not Used PBAPS Units 2 and 3 ODCM 3.8.C-13 Revision 15

January 2020 Gaseous Effluents 3.8.C.5 3.8.C Gaseous Effluents ODCMS 3.8.C.5 Gaseous effluents shall be processed through the Gaseous Waste Treatment System described below prior to discharge:

a. Steam jet air ejector discharge shall be processed through the recombiner, holdup pipe, off-gas filter, and off-gas stack;
b. Mechanical vacuum pump and gland steam exhauster discharge shall be processed through the off-gas stack;
c. Deleted
d. Reactor, turbine, radwaste, and recombiner building atmospheres shall be processed through permanently or temporarily installed equipment in the appropriate building ventilation system and the vent stack, with the exception of the following unmonitored exhausts:
1. Recirculation M-G set and reactor building cooling water equipment rooms;
2. Control room utility and toilet rooms;
3. Cable spread room;
4. Emergency switchgear rooms;
5. 125/250 VDC battery rooms and the 250 VDC battery rooms, and
6. Administration building maintenance decontamination area.

APPLICABILITY: Prior to all gaseous release(s) whenever the release(s) would cause the projected dose, when it is averaged over 31 days to exceed 0.6 mrem to any organ, 0.4 mrad for gamma radiation, and 0.8 mrad for beta radiation (combined total from the two reactors at the site).

PBAPS Units 2 and 3 ODCM 3.8.C-14 Revision 15

January 2020 Gaseous Effluents 3.8.C.5 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gaseous waste A.1 Submit a Special Report 30 days discharged without to the NRC that required processing. explains the reasons gaseous radwaste was discharged without processing, identifies inoperable equipment or subsystems and the reasons for the inoperability, identifies actions taken to restore the inoperable equipment to FUNCTIONAL status, and action(s) taken.

ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.5.1 Project doses due to gaseous effluent 31 days releases at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

ODCMS 4.8.C.5.2 Collect and analyze air samples from 31 days each building area with an unmonitored exhaust.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.C-15 Revision 15

January 2020 Gaseous Effluents 3.8.C.5 ODCMS REQUIREMENTS (Continued)

ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.5.3 Demonstrate FUNCTIONALITY of required 92 days gaseous radioactive waste system equipment by analyzing the gaseous waste processed through the required equipment to determine it meets the requirements of ODCMS 3.8.C.1 PBAPS Units 2 and 3 ODCM 3.8.C-16 Revision 15

Gaseous Effluents January 2020 3.8.C.6 3.8.C Gaseous Effluents ODCMS 3.8.C.6 PURGING of the primary containment shall be:

a. Through the Standby Gas Treatment System whenever primary containment is required to be FUNCTIONAL; and
b. Through the Reactor Building Ventilation Exhaust System or the Standby Gas Treatment System whenever primary containment is not required to be FUNCTIONAL.

APPLICABILITY: During PURGING of the primary containment.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirement of A.1 Initiate action to Immediately ODCMS 3.8.C.6 not suspend PURGING.

met.

ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.6.1 Verify primary containment PURGING Prior to is through required effluent release PURGING pathway of ODCMS 3.8.C.6. primary containment PBAPS Units 2 and 3 ODCM 3.8.C-17 Revision 15

January 2020 Gaseous Effluents 3.8.C.7 3.8.C Gaseous Effluents ODCMS 3.8.C.7 Section Removed ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.7.1 Section Removed.

ODCMS 4.8.C.7.2 Section Removed.

PBAPS Units 2 and 3 ODCM 3.8.C-18 Revision 15

January 2020 40 CFR 190 3.8.D.1 3.8.D 40 CFR 190 and 10 CFR 72.104 ODCMS 3.8.D.1 The annual dose equivalent to a real individual who is located beyond the SITE BOUNDARY from all uranium fuel cycle sources within 8 kilometers shall be:

a. 25 mrem to the total body;
b. 75 mrem to the thyroid.
c. 25 mrem to any other critical organ; and
d. 3.0 mrem contribution from liquid and gaseous effluents for whole body and critical organ doses.
e. 55 mrem contribution from gaseous effluents for thyroid dose.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME

NOTE-----------

A. Annual cumulative Immediately Calculations shall include liquid and gaseous direct radiation effluents dose does contributions from reactor not meet ODCMS units and outside storage 3.8.D.1 items d or e. tanks.

A.1 Initiate actions to determine whether the limits in ODCMS 3.8.D.1 items a, b or c have been exceeded.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.D-1 Revision 15

January 2020 40 CFR 190 3.8.D.1 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Dose limits of B.1 Submit a Special Report 31 days ODCMS 3.8.D.1 items to the NRC that a, b or c have been includes the corrective exceeded. action(s) taken, the schedule for achieving conformance with required limits, estimates of radiation exposure to the real individual for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure level or concentrations.

AND

NOTE----------

Only applicable if the release condition resulting in violation of 40 CFR 190 or 10 CFR 72.104 has not been corrected.

B.2 Submit a request for a variance in accordance 31 days with 40 CFR 190 and a request for an exemption from 10 CFR 72.104.

PBAPS Units 2 and 3 ODCM 3.8.D-2 Revision 15

January 2020 40 CFR 190 3.8.D.1 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.D.1.1 Determine total gas and liquid 31 days cumulative dose contributions in accordance with methodology and parameters in the ODCM.

ODCMS 4.8.D.1.2 Determine the cumulative dose 92 days contribution from gas and liquid effluents and the direct radiation from the reactor units and from high and low level radwaste storage in accordance with the methodology and parameters in the ODCM.

PBAPS Units 2 and 3 ODCM 3.8.D-3 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.1 Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 4.8.E.1 and the ODCM.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Milk samples A.1 Identify locations for 31 days permanently obtaining replacement unavailable from any samples and add them of the sample to radiological locations listed in environmental the ODCM. monitoring program.

Delete locations from which samples are unavailable.

AND A.2 Identify in the AREOR Prior to the cause of the submittal in unavailability of next AREOR samples and new locations for obtaining samples and include in the report revised figures and tables for the ODCM reflecting the new locations.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.E-1 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Level of B.1 Submit a Special Report 30 days radioactivity as a to the NRC which result of plant includes an evaluation effluents in an of any release environmental conditions, sampling medium at environmental factors, one or more or other aspects which locations specified caused the action level in the ODCM exceeds of Table 3.8.E.1 to be the action levels of exceeded and the Table 3.8.E.1 when corrective actions to be averaged over the taken to reduce calendar quarter. radioactive effluents so that the potential OR annual dose to a MEMBER OF THE PUBLIC is less Level of than the calendar year radioactivity as a reporting level of result of plant Table 3.8.E.1.

effluents in an environmental sampling medium at one or more locations specified in the ODCM exceeds the action levels of Table 3.8.E.1 when averaged over the calendar quarter and more than one radionuclide from Table 3.8.E.1 is detected and the equation in ODCMS 4.8.E.1.2 is satisfied.

(continued)

PBAPS Units 2 and 3 ODCM 3.8.E-2 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. Radionuclides other C.1 -------NOTE-------

than those in Only required if the Table 3.8.E.1 radionuclides detected and the detected are the potential annual result of plant dose to a MEMBER OF effluents.

THE PUBLIC is --------------------

greater than or equal to the Submit a Special 31 days after calendar year limits Report to the NRC to end of of ODCMS 3.8.B.2, or evaluate any release affected ODCMS 3.8.C.2, or conditions, calendar ODCMS 3.8.C.3, or environmental quarter ODCMS 3.8.D.1. factors, or other aspects which caused the action level of Table 3.8.E.1 to be exceeded; and the corrective actions to be taken to reduce radioactive effluents so that potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of Table 3.8.E.1 AND (continued)

PBAPS Units 2 and 3 ODCM 3.8.E-3 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION TIME MEASURE C. (continued) C.2 ------NOTE--------

Only required if the radionuclides detected are not the result of plant effluents.

Describe the condition Prior to in the Annual submittal of Radiological next Annual Environmental Operating Radiological Report. Environmental Operating Report D. Requirements of D.1 Prepare and submit, in In accordance ODCMS 3.8.E.1 the Annual Radiological with Technical not met. Environmental Operating Specification Report, a description of 5.6.3 the reasons for not conducting the radiological environmental monitoring program as required and the actions taken to prevent recurrence.

PBAPS Units 2 and 3 ODCM 3.8.E-4 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.1.1 -----------NOTES----------------

1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailabilities, malfunction of automatic sampling equipment or other legitimate reasons.
2. If equipment malfunction occurs, an effort shall be made to complete corrective actions prior to the end of the next sampling period.

Collect radiological environmental In accordance monitoring samples at the locations with and analyze as specified in Table 4.8.E.1 Table 4.8.E.1 and the ODCM.

ODCMS 4.8.E.1.2 ------------NOTE----------------

All radionuclides used in this evaluation shall be averaged on a calendar quarterly basis.

Evaluate the concentration of 92 days radioactivity as a result of plant effluents in an environmental sampling medium against the following equation:

concentration(1)

+

reporting level(1) concentration(2)

+

reporting level(2) ... 1.0 PBAPS Units 2 and 3 ODCM 3.8.E-5 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 Table 3.8.E.1 (page 1 of 1)

Reporting Levels for Radioactivity Concentration in Environmental Samples Action Levels ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS (pCi/l) PARTICULATE (pCi/kg, wet) (pCi/l) (pCi/kg, wet)

OR GASES (pCi/m3)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

  • For drinking water samples. This is 40 CFR part 141 value.

PBAPS Units 2 and 3 ODCM 3.8.E-6 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 T able 4.8.E.1 (page 1 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF SAMPLES AND SAMPLE LOCATION(a) SAMPLING AND COLLECTION TYPE AND FREQUENCY OF ANALYSIS FREQUENCY (b),(c)

1. Direct Radiation At least 40 routine monitoring stations either with two or more dosimeters or with Every 31 days Every 31 days (Gamma dose) one instrument for measuring and recording dose rate continuously to be placed as follows: 1) an inner ring of stations in the general area of the SITE BOUNDARY and or or an outer ring in the 3 to 6 mile range from the site. A station is in each sector of each ring except as dictated by local geography. The balance of the stations Every 92 days Every 92 days (Gamma dose) are in special interest areas such as population centers, nearby residences, schools and in areas to serve as control stations.
2. Airborne Continuous sampler Radioiodine canisters: I-131 Samples from 5 locations: operation with sample analysis every 7 days Radioiodine and Particulates collection every 7 days
a. 3 samples from close to the SITE BOUNDARY locations (in different sectors) of or required by dust Particulate sampler: (f) gross the highest calculated annual average ground level D/Q. loading, whichever is beta radioactivity analysis more frequent. following filter change; gamma
b. 1 sample from the vicinity of a community having the highest calculated annual isotopic analysis of composite (by average ground level D/Q. location) 92 days
c. 1 sample from a control location unlikely to be affected by the plant.
3. Waterborne
a. Surface a. 1 sample upstream Composite (b) sample Gamma isotopic (d) analysis every over 31 day period. 31 days. Composite for tritium
b. 1 sample downstream analysis at least every 92 days (continued)

PBAPS Units 2 and 3 ODCM 3.8.E-7 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 2 of 3)

Radiological Environmental Monitoring Program EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF SAMPLES AND SAMPLE LOCATION SAMPLING AND COLLECTION TYPE AND FREQUENCY OF ANALYSIS FREQUENCY (b),(c) 3.Waterborne (cont'd)

b. Drinking
a. 1 sample of each of 1 to 3 of the nearest water supplies that could be affected by its Composite (b) sample over 31 Composite for gross beta and discharge. day composite period gamma (d) isotopic analyses every 31 days. Composite for
b. 1 sample from a control location. tritium analysis at least every 92 days
c. Sediment from 1 sample from downstream area with existing or potential recreational value. Every 6 months Gamma isotopic (d) analysis Shoreline every 6 months
4. Ingestion
a. Samples from milking animals in 3 locations within 3 miles distance having the highest
a. Milk dose potential. Every 14 days when animals are Gamma isotopic (d) analysis or on pasture, every 31 days at 134, 137 Cs by chemical
b. 1 sample from milking animals at a control location (unlikely to be affected by the other times. separation every 92 days. I-plant). 131 analysis of each sample.
b. Fish a. 1 sample of each commercially and recreationally important species in vicinity of Sample in season, or every Gamma isotopic (d) analysis on discharge point when available. 6 months if they are not edible portions.

seasonal.

b. 1 sample of same species in areas not influenced by plant discharge when available.
c. Food Products a. Samples of 3 different kinds of broad leaf vegetation grown nearest offsite garden of Every 31 days when available if Gamma isotopic (d) and I-131 highest annual average ground level D/Q if milk sampling is not performed. milk sampling is not performed. analysis Every 31 days when available if
b. 1 sample of each of the similar broad leaf vegetation grown 15 - 30 km distant in the milk sampling is not performed least prevalent wind direction if milk sampling is not performed. Gamma isotopic (d) and I-131 analysis PBAPS Units 2 and 3 ODCM 3.8.E-8 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 3 of 3)

Radiological Environmental Monitoring Program NOTES (a) Fixed sample locations are shown in the Offsite Dose Calculation Manual, Table VII.A.1 and Figures VII.A.1, VII.A.2, and VII.A.3. At times it may not be possible or practicable to obtain samples of the media of choice at the most desired location or time. In those instances suitable alternative media and locations may be chosen for the particular pathway in question. Such necessary deviations are reported in the Annual Radiological Environmental Operating Report.

(b) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(c) Sample collection frequencies are defined as follows:

7 days 7 calendar days + 2 days 14 days 14 calendar days + 3 days 31 days 31 calendar days + 8 days 92 days 92 calendar days + 10 days 6 months 6 calendar months + 20 days (d) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(e) N/A (f) If the gross beta activity in air attributable to plant operation is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

PBAPS Units 2 and 3 ODCM 3.8.E-9 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.2 (page 1 of 2)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(a)

Lower Limit Of Detection (LLD)(b)

ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS SEDIMENT (pCi/l) PARTICULATE (pCi/kg, (pCi/l) (pCi/kg, wet) (pCi/kg, (pCi/m3) wet) dry)

Gross 4 0.01 Beta H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 - 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 PBAPS Units 2 and 3 ODCM 3.8.E-10 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.2 (page 2 of 2)

Notes:

(a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable at 95% confidence level, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = 4.66S E V 2.22 Y exp (-t)

Where:

LLD is the a priori lower limit of detection as defined above (as picocuries per unit mass or volume),

S is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable) is the radioactive decay constant for the particular radionuclide, and t for the environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

Typical values of E, V, Y, and t should be used in calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

PBAPS Units 2 and 3 ODCM 3.8.E-11 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.2 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.2 A land use census shall be conducted and shall identify the location of the nearest milk animal in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Land use census A.1 Add the new location to 31 days identifies a the radiological location which environmental yields a calculated monitoring program.

dose or dose commitment (via the AND same exposure pathway) that is at least 20% greater than a location from which samples are currently being obtained in accordance with ODCMS 3.8.E.1. (continued)

PBAPS Units 2 and 3 ODCM 3.8.E-12 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.2 COMPENSATORY MEASURES (Continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. (continued) A.2 --------NOTE---------

The indicator sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from the radiological environmental monitoring program after October 31 of the year in which land use census was conducted.

Identify the new In Accordance location in the with Annual Radiological Technical Environmental Specification Operating Report and 5.6.2 include the revised figures and tables for the ODCM reflecting the new location.

B. Land use census B.1 Identify the new In Accordance identifies a location in the Annual with location which Radiological Technical yields a calculated Environmental Operating Specification dose or dose Report. 5.6.2 commitment that is greater than values currently being calculated in ODCMS 3.8.C.3.

PBAPS Units 2 and 3 ODCM 3.8.E-13 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.2.1 Conduct a land use census by a door-to- 12 months door survey or by consulting local agriculture authorities or by some other appropriate means.

PBAPS Units 2 and 3 ODCM 3.8.E-14 Revision 15

January 2020 Radiological Environmental Monitoring 3.8.E.3 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.3 Analyses shall be performed on radioactive materials supplied as part of the EPA Environmental Radioactivity Intercomparison Studies Program, or another Interlaboratory Comparison Program traceable to NIST.

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of A.1 Include corrective In accordance ODCMS 3.8.E.3 not actions to prevent with Technical met. recurrence in the Specification Annual Radiological 5.6.2 Environmental Operating Report.

ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.3.1 Include a summary of the results of In accordance the Interlaboratory Comparison with Technical Program in the Annual Radiological Specification Environmental Operating Report. 5.6.2 PBAPS Units 2 and 3 ODCM 3.8.E-15 Revision 15

January 2020 ODCM Specifications Bases B 3.8 3.10 Reporting Requirements ODCMS 3.10.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include or reference from previous reports:

a. A summary description of the radiological environmental monitoring program including sampling methods for each sample type, size, and physical characteristics of each sample type, sample preparation methods, and measuring equipment used;
b. At least two maps of all sampling locations keyed to a table giving distances and directions from the midpoint between reactor vents;
c. Results of the land use census required by ODCMS 3.8.E.2; and
d. Results of the Interlaboratory Comparison Program required by ODCMS 3.8.E.3 and discussion of all analyses in which the LLD required by Table 4.8.E.2 was not achievable.

ODCMS 3.10.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the requirements of Technical Specification 5.6.3 the Radioactive Effluent Release Report shall include:

a. Information for each class of solid waste (as defined by 10 CFR 61) shipped offsite during the report period:
1. Container volume;
2. Total curie quantity (specify whether determined by measurements or estimate);
3. Principal radionuclides (specify whether determine by measurement of estimate);

PBAPS Units 2 and 3 ODCM B.3.8-1 Revision 15

January 2020 ODCM Specifications Bases B 3.8 3.10.2 Reporting Requirements (Continued)

4. Source of waste and processing employed (e.g.,

dewatered spent resin, compacted dry waste, evaporator bottomed); and

5. Type of container (e.g., LSA, Type A, Type B, Large Quantity).
b. A list and description of unplanned releases from the site to areas at or beyond the SITE BOUNDARY of radioactive materials in gaseous and liquid effluents made during the reporting period.
c. Changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM) and a list of new locations for dose calculations and/or environmental monitoring identified by the land use census required by ODCM 3.8.E.2.
d. Annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. The licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
e. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
f. Radiation doses from radioactive liquid and gaseous effluent to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.
g. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. Approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).

PBAPS Units 2 and 3 ODCM B.3.8-2 Revision 15

January 2020 ODCM Specifications Bases B 3.8 3.10.2 Reporting Requirements (Continued)

h. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Guidance for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.

PBAPS Units 2 and 3 ODCM B.3.8-3 Revision 15

January 2020 ODCM Specifications Bases B 3.8 B 3.8 ODCM SPECIFICATIONS BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.1302 of 10 CFR, Part 20. At the same time, the licensee is permitted the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in Section 20.1302 of 10 CFR, Part 20. It is expected that in using this operational flexibility under unusual operating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.

Liquid Radwaste Effluents Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be within 10 times the concentration levels specified in 10 CFR, Part 20, Appendix B, Table 2, Column 2. This instantaneous limitation provides additional assurance that the levels of radioactive materials in bodies of water in areas at or beyond the SITE BOUNDARY will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR, Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR, Part 20.1302 to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICP) Publication 2.

Dose This specification is provided to implement the requirements of Sections I.E., IXIA and I.E. of Appendix I, 10 CFR Part 50. ODCMS 3.8.B.2 implements the guidance set forth in Section I.E. of Appendix I and provides the required operating flexibility to implement the guides set forth in Section I.E. of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations in the ODCM implement the requirements in Section IXIA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations described in the Offsite Dose Calculation Manual for calculating the doses due to the actual release rates (continued)

PBAPS Units 2 and 3 ODCM B.3.8-4 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued) of radioactive materials in liquid effluents are consistent with the methodology provided 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 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This specification applies to the release of liquid effluents from the site.

Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential release of liquid effluents. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

System Operation The FUNCTIONALITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR, Part 50, for liquid effluents.

The chemical/oily waste cleanup subsystem may include the portable Epicor oil/water emulsion system (as described in RW-625), an installed chemical/oily waste cleanup subsystem, or equivalent chemical/oil waste system.

The laundry drain filter may be used to process liquid wastes containing detergents or similar cleaning agents. Wastewater such as river water that is acceptable for release may be processed through the laundry drain filter.

(continued)

PBAPS Units 2 and 3 ODCM B.3.8-5 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued)

Gaseous Effluents Dose This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, and Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors are given in the ODCM. The specified limits restrict, at all times, the gamma and beta dose rates above background to a MEMBER OF THE PUBLIC, at or beyond the SITE BOUNDARY to 500 mrem/year to the total body or to 3000 mrem/year to the skin.

These dose rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to 1500 mrem/year.

Dose, Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. ODCMS 3.8.C.2 implements the guidance set forth in Section II.B of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." ODCMS 4.8.C.2.1 implements the requirements in Section III.A of Appendix I that conformance with the guidance of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided 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 50, Appendix I," Revision 1, October 1977 and the atmospheric dispersion model submitted on September 30, 1976, in a report titled:

"Information Requested in Enclosure 2 to letter from George Lear to E.

G. Bauer dated February 17, 1976." The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

(continued)

PBAPS Units 2 and 3 ODCM B.3.8-6 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued)

Dose, Iodine-131, Tritium and Radionuclides in Particulate Form This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. ODCMS 3.8.C.3 implements the guidance set forth in Section II.C of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the ODCMS 4.8.C.3.1 implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided 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 and the Atmospheric Dispersion Model submitted on September 30, 1976 in a report titled: "Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17, 1976." These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The FUNCTIONALITY and use of instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR, Part 50.

(continued)

PBAPS Units 2 and 3 ODCM B.3.8-7 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued)

System Operation The FUNCTIONALITY of the Gaseous Radwaste Treatment System ensures that this system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50. The specified limits governing the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a suitable fraction of the guidance set forth in Section II.B and II.C of Appendix I, 10 CFR, Part 50, for gaseous effluents.

To determine if gaseous effluents shall be processed through installed treatment equipment, the average projected dose will be determined. For gaseous effluent pathways other than the specified unmonitored exhausts, treatment and monitoring will only be required for pathways that are significant. Regulatory Guide 1.109, Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, states that a pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways. Therefore, the total dose from all release pathways that do not require treatment or monitoring can not exceed 10 percent of the limit specified in Section II.C of Appendix I, 10 CFR Part 50.

Containment PURGE ODCMS 3.8.C.6 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to release to provide reasonable assurance that PURGING operations will not result in exceeding the annual dose limits of 10 CFR Part 20 for areas at or beyond the SITE BOUNDARY.

(continued)

PBAPS Units 2 and 3 ODCM B.3.8-8 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued) 40 CFR 190 and 10 CFR 72.104 This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301(d) as well as the dose limitations specific to Independent Spent Fuel Storage Installation (ISFSI) operations in accordance with 10 CFR 72.104.

Over the long term, as more ISFSI casks are placed on the ISFSI pad, it is expected that ISFSI operations will become the prominent contributor to the limits in this section. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The 10 CFR 72.212 report prepared in accordance with ISFSI requirements assumes a certain array of casks exists on the pad. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations (e.g. PBAPS 2 & 3) prior to ISFSI operations was analyzed to be within the 40 CFR 190 and 10 CFR 72.104 limits. The difference between 40 CFR 190/10 CFR 72.104 limits and the analyzed ISFSI cask array contribution are identified in ODCMS 3.8.D.1 items d and e. Therefore, these values are used as assumptions in calculating combined ISFSI and PBAPS 2 & 3 doses. If these PBAPS 2 & 3 liquid and gas radiation values are exceeded, an evaluation is performed to determine if the overall 40 CFR 190 and 10 CFR 72.104 limits have been exceeded.

If the dose limits of 40 CFR 190 or 10 CFR 72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption /variance is required to be submitted to the NRC.

The requirement that the dose limits of 10CFR 72.104 apply to "any real individual" are controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose in the south end of the site, the member of the public as defined in 40 CFR 190 at this area is the same as the "real individual" identified in the 72.212 report. The location for the real individual identified in the ISFSI 72.212 report is the limiting individual for calculating dose.

(continued)

PBAPS Units 2 and 3 ODCM B.3.8-9 Revision 15

January 2020 ODCM Specifications Bases B 3.8 BASES (continued)

Radiological Environmental Monitoring Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the two reactors at the sites. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limit of Detection (LLD). The LLD's required by Table 4.8.E.2 of the specifications are considered optimum for routine environmental measurements in industrial laboratories. The monitoring program was developed utilizing the experience of the first seven years of commercial operation. Program changes may be initiated based on the additional operational experience.

Land Use Census This specification is provided to ensure that significant changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

PBAPS Units 2 and 3 ODCM B.3.8-10 Revision 15

Page 2 of 64 Rev. 17 Table of Contents I. Purpose II. Instrument Setpoints III. Liquid Pathway Dose Calculations A. Liquid Radwaste Release Flow Rate Determination B. ODCMS 4.8.B.2.1 C. ODCMS 4.8.B.4.1 IV. Gaseous Pathway Dose Calculations A. ODCMS 4.8.C.1.1 and 4.8.C.1.2 B. ODCMS 4.8.C.2.1 C. ODCMS 4.8.C.3.1 D. ODCMS 4.8.C.5.1 E. Technical Requirements Manual Test Requirement (TR) 3.5.3 F. ODCMS 4.8.C.7.1 and 4.8.C.7.2-Section Removed.

V. Nuclear Fuel Cycle Dose Assessment - 40 CFR 190 and 10 CFR 72.104 A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 VI. Doses Due To Activities Inside the Site Boundary A. ODCMS 3.10.2.f VII. Radiological Environmental Monitoring Program A. ODCMS 4.8.E.1.1 and 4.8.E.1.2 VIII. Bases Appendix A Radioactive Effluents Control Program January 2020

Page 3 of 64 Rev. 17 I. Purpose The purpose of the Offsite Dose Calculation Manual is to establish methodologies and procedures for calculating doses to individuals in areas at and beyond the SITE BOUNDARY due to radioactive effluents from Peach Bottom Atomic Power Station. The results of these calculations are required to determine compliance with the requirements of Specification 5.5.4, "Radioactive Effluent Controls Program" of Appendix A to Operating Licenses DPR-44 and DPR-56, "Technical Specifications for Peach Bottom Atomic Power Station Units No. 2 and 3". The Radioactive Effluents Control Program is located in Appendix A of this Offsite Dose Calculation Manual and contains Offsite Dose Calculation Manual Specifications (ODCMS) and their associated Bases which implement the requirements of Technical Specification 5.5.4.

II. Setpoint Determination for Liquid & Gaseous Monitors II.A Liquid Radwaste Activity Monitor Setpoint A sketch of the Liquid Radwaste System is presented in Figure

4. Each tank of radioactive waste is sampled prior to release. A small liquid volume of this sample is analyzed for gross gamma activity in a NaI well counter. This NaI well counter activity is then converted to an equivalent liquid radwaste monitor reading.

CPS (R/W Monitor) = [Net CPM/ml (well) x Eff W/RW] +

Background CPS Where:

CPS (R/W Monitor) = liquid radwaste gross activity monitor reading in CPS Net CPM/ml (well) = gross gamma activity for the radwaste sample tank [determined by the well counter]

Eff W/RW = conversion factor between well counter and liquid radwaste gross activity monitor [determined by calibrating both detectors with the same liquid radioactive source]

Background CPS = background reading of the liquid radwaste gross activity monitor in CPS January 2020

Page 4 of 64 Rev. 17 Exceeding the expected response would indicate that an incorrect sample had been obtained for that release and the release is automatically stopped.

The alarm and trip pot setpoints for the liquid radwaste activity monitor are determined from a calibration curve for the alarm pot and trip pot. The alarm pot setting includes a factor of 1.25 to allow for analysis error, pot setting error, instrument error and calibration error. The trip pot setting includes a factor of 1.35 to allow for analysis error, pot setting error, instrument error and calibration error.

II.B Liquid Radwaste Release Flowrate Setpoint Determination The trip pot setpoint for the liquid radwaste release flowrate is determined by multiplying the liquid radwaste flowrate (from Section III.A) by 1.2 and using this value on the appropriate calibration curve for the discharge flow meter to be used. The Peach Bottom radwaste system has two flow monitors - high flow (5 to 300 gpm) and low flow (0.8 to 15 gpm). The factor of 1.2 allows for pot setting error and instrument error. The flow rate determination includes a margin of assurance which includes consideration of this error such that the instantaneous release limit of 10 CFR 20 is not exceeded.

II.C Setpoint Determination for Gaseous Radwaste A sketch of the Offgas Radwaste Treatment System is presented in Figure 1. Sketches of the Ventilation Treatment Systems for Units 2 and 3 are presented in Figures 2 and 3 respectively. The high and high-high alarm setpoints for the main stack radiation monitor, Unit 2 roof vent radiation monitor and Unit 3 roof vent radiation monitor are determined as follows:

High Alarm - the high alarm setpoint is set at approximately 3 x background.

January 2020

Page 5 of 64 Rev. 17 High-High Alarm - the high-high alarm setpoint is set at a release rate from this vent of approximately 30% of the instantaneous release limit as specified in ODCMS 3.8.C.1.a for the most restrictive case (skin or total body) on an unidentified basis. To determine these setpoints, solve the gaseous effluent dose rate equations in section IV.A of the ODCM to determine what main stack release rate and roof vent release rate will produce a dose rate of 150 mrem/yr to the total body (30% of the limit of 500 mrem/yr) and a dose rate of 900 mrem/yr to the skin (30% of the limit of 3000 mrem/yr) from each release point. Using the highest (most restrictive) release rate for each release point determine monitor response required to produce this release rate assuming a normal vent flow rate and pressure correction factor. Set the high-high alarm for approximately this monitor response.

II.D. Setpoint Determination for Gaseous Radwaste Flow Monitors The alarm setpoint for the main stack flow monitor is as follows:

Low Flow Alarm - 10,000 CFM. - This setting ensures that the main stack minimum dilution flow as specified in ODCMS 3.8.C.4.a is maintained.

The alarm setpoints for the roof vent flow monitors are as follows:

Low Flow Alarm - 1.5 x 105 cfm High Flow Alarm - 5.4 x 105 cfm III. Liquid Pathway Dose Calculations III.A Liquid Radwaste Release Flow Rate Determination Peach Bottom Atomic Power Station Units 2 and 3 have one common discharge point for liquid releases. The following calculation assures that the radwaste release limits are met.

The flow rate of liquid radwaste released from the site to areas at and beyond the SITE BOUNDARY shall be such that the concentration of radioactive material after dilution shall be limited to 10 times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases and 2E-4 µCi/ml total activity concentration for all noble gases as specified in ODCMS 3.8.B.1. This January 2020

Page 6 of 64 Rev. 17 methodology is consistent with the additional guidance the NRC provided to the industry during the implementation of the updated 10 CFR 20 which changed the criterion for controlling release rate based on Effective Concentration (EC) values in the updated 10 CFR 20 as opposed to the Maximum Permissible Concentration (MPC) values in the former 10 CFR 20.

Each tank of radioactive waste is sampled prior to release and is quantitatively analyzed for identifiable gamma emitters as specified in Table 4.8.B.1 of the ODCMS. While non-gamma emitters are not specifically addressed, the conservatisms inherent in the calculation of the maximum permissible release rate are more than adequate to account for them. From this gamma isotopic analysis the maximum permissible release flow rate is determined as follows:

Determine a Dilution Factor by:

µCi / mli Dilution Factor = i 10 x ECLi 1

µCi / mli = the activity of each identified gamma emitter in µCi/ml ECL i = The effluent concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases or 2 x 10-4 µCi/ml for noble gases.

January 2020

Page 7 of 64 Rev. 17 Determine the Maximum Permissible Release Rate with this Dilution Factor by:

. x 105 A x 20 Release Rate (gpm) =

B x C x Dilution Factor A = The number of circulating water pumps running which will provide dilution 2.0 x 105 = the flow rate in gpm for each circulating water pump running B = margin of assurance which includes consideration of the maximum error in the activity setpoint, the maximum error in the flow setpoint, and possible loss of 5 out of the 6 possible circulating water pumps during a release. The value used for B is 10.0.

C = concentration gradient factor. The value used for C is 5.0 for discharge canal water levels less than 104' and 3.0 for canal water levels greater than 104'. This just adds another factor of conservatism.

III.B ODCMS 4.8.B.2.1 Dose contributions from liquid effluents released to areas at and beyond the SITE BOUNDARY shall be calculated using the equation below. This dose calculation uses those appropriate radionuclides listed in Table III.A.1. These radionuclides account for virtually 100 percent of the total body dose and organ dose from liquid effluents.

The dose for each age group and each organ should be calculated to determine the maximum total body dose and organ dose for each quarter and the year, as appropriate.

Cumulative dose files for quarterly and yearly doses should be maintained separately and the maximum total body and organ dose reported in each case. CM-1 NRC URI 88-33-01, T00353.

m D = A i t Ci F i =1 where:

D = The cumulative dose commitment to the total body or any organ, , from liquid effluents for the total January 2020

Page 8 of 64 Rev. 17 m

time period t

=1 2, in mrem.

t = The length of the th time period over which Ci and F are averaged for the liquid release, in hours.

Ci = The average concentration of radionuclide, i, in undiluted liquid effluent during time period t from any liquid release, (determined by the effluent sampling analysis program, ODCMS Table 4.8.B.1), in µCi/ml.

A i = The site related ingestion dose commitment factor to the total body or organ, , for each radionuclide listed in Table III.A.1, in mrem-ml per hr-µCi. See Site Specific Data.**

F = The near field average dilution factor for Ci during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow through the discharge pathway.

III.C ODCMS 4.8.B.4.1 Projected dose contributions from liquid effluents shall be calculated using the methodology described in section III.B.

    • See Note 1 in Bases January 2020

Page 9 of 64 Rev. 17 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A i DOSE FACTOR (MREM-ML PER HR-µCi)

TOTAL BODY RADIONUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 5.93E+04 6.49E+04 8.33E+04 CR-51 1.49E+00 1.53E+00 1.69E+00 MN-54 9.82E+02 1.00E+03 1.08E+03 FE-55 1.31E+02 1.40E+02 1.96E+02 FE-59 1.14E+03 1.17E+03 1.36E+03 CO-57 4.55E+01 4.71E+01 5.78E+01 CO-58 2.59E+02 2.62E+02 3.17E+02 CO-60 7.40E+02 7.48E+02 9.07E+02 NI-63 1.29E+03 1.34E+03 1.90E+03 ZN-65 3.87E+04 3.95E+04 4.16E+04 SR-89 8.83E+02 9.45E+02 1.48E+03 SR-90 1.88E+05 1.56E+05 1.72E+05 Y-91M 5.85E-13 6.14E-13 9.31E-13 Y-93 1.27E-03 1.34E-03 2.16E-03 NB-95 1.52E+02 1.56E+02 1.68E+02 NB-95M no data no data no data ZR-95 1.77E-01 1.72E-01 3.48E-01 ZR-97 1.56E-03 1.56E-03 3.43E-03 MO-99 2.91E+01 3.01E+01 5.53E+01 TC-99M 3.33E-02 3.33E-02 4.93E-02 RU-103 3.57E+00 3.60E+00 5.97E+00 RU-105 6.55E-03 6.72E-03 1.19E-02 AG-110M 2.13E+00 2.04E+00 4.23E+00 SN-113 no data no data no data TE-129M 2.01E+03 2.17E+03 2.79E+03 TE-131M 4.57E+02 4.81E+02 5.74E+02 TE-132 1.40E+03 1.44E+03 1.65E+03 SB-124 2.27E+01 2.18E+01 5.15E+01 SB-125 8.79E+00 8.47E+00 2.01E+01 I-131 1.86E+02 1.79E+02 2.36E+02 I-133 1.97E+01 2.03E+01 3.20E+01 I-135 2.04E+00 2.06E+00 3.12E+00 CS-134 6.74E+05 3.88E+05 1.49E+05 CS-136 9.79E+04 9.15E+04 7.30E+04 CS-137 3.98E+05 2.20E+05 8.49E+04 CS-138 1.04E-11 1.09E-11 1.27E-11 BA-139 5.01E-07 5.17E-07 1.18E-06 BA-140 3.66E+01 3.62E+01 7.42E+01 January 2020

Page 10 of 64 Rev. 17 LA-140 1.92E-02 1.97E-02 2.78E-02 LA-142 3.62E-08 3.70E-08 5.28E-08 CE-141 1.45E-02 1.46E-02 3.86E-02 CE-143 1.68E-03 1.69E-03 4.44E-03 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.

January 2020

Page 11 of 64 Rev. 17 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A i DOSE FACTOR (MREM-ML PER HR-µCi)

LIVER RADIONUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 9.55E+04 1.04E+05 1.01E+05 CR-51 no data no data no data MN-54 5.15E+03 5.06E+03 4.03E+03 FE-55 5.62E+02 6.01E+02 6.33E+02 FE-59 2.96E+03 3.02E+03 2.73E+03 CO-57 2.74E+01 2.81E+01 2.86E+01 CO-58 1.16E+02 1.14E+02 1.04E+02 CO-60 3.35E+02 3.32E+02 3.07E+02 NI-63 2.66E+03 2.80E+03 2.99E+03 ZN-65 8.55E+04 8.46E+04 6.69E+04 SR-89 no data no data no data SR-90 no data no data no data Y-91M no data no data no data Y-93 no data no data no data NB-95 2.83E+02 2.84E+02 2.35E+02 NB-95M no data no data no data ZR-95 2.61E-01 2.50E-01 3.91E-01 ZR-97 3.40E-03 3.39E-03 5.82E-03 MO-99 1.53E+02 1.58E+02 2.23E+02 TC-99M 2.61E-03 2.57E-03 2.98E-03 RU-103 no data no data no data RU-105 no data no data no data AG-110M 3.58E+00 3.36E+00 5.30E+00 SN-113 no data no data no data TE-129M 4.74E+03 5.09E+03 5.02E+03 TE-131M 5.48E+02 5.77E+02 5.40E+02 TE-132 1.48E+03 1.53E+03 1.36E+03 SB-124 1.08E+00 1.03E+00 1.91E+00 SB-125 4.13E+01 3.96E-01 7.39E-01 I-131 3.25E+02 3.32E+02 4.16E+02 I-133 6.48E+01 6.66E+01 8.45E+01 I-135 5.52E+00 5.55E+00 1.63E+00 CS-134 8.25E+05 8.36E+05 7.06E+05 CS-136 1.36E+05 1.36E+05 1.13E+05 CS-137 6.07E+05 6.32E+05 5.75E+05 CS-138 2.10E-11 2.18E-11 2.01E-11 BA-139 1.22E-08 1.25E-08 2.17E-08 BA-140 7.00E-01 6.90E-01 1.11E+00 January 2020

Page 12 of 64 Rev. 17 LA-140 7.28E-02 7.40E-02 8.25E-02 LA-142 1.45E-07 1.49E-07 1.69E-07 CE-141 1.28E-01 1.27E-01 2.60E-01 CE-143 1.52E+01 1.51E+01 3.07E+01 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.

January 2020

Page 13 of 64 Rev. 17 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A i DOSE FACTOR (MREM-ML PER HR-µCi)

BONE RADIONUCLIDE ADULT TEEN CHILD H-3 no data no data no data NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 2.38E+05 2.58E+05 3.35E+05 CR-51 no data no data no data MN-54 no data no data no data FE-55 8.12E+02 8.47E+02 1.19E+03 FE-59 1.26E+03 1.30E+03 1.68E+03 CO-57 no data no data no data CO-58 no data no data no data CO-60 no data no data no data NI-63 3.84E+04 3.97E+04 5.58E+04 ZN-65 2.69E+04 2.43E+04 2.51E+04 SR-89 3.08E+04 3.30E+04 5.19E+04 SR-90 7.67E+05 6.31E+05 6.78E+05 Y-91M 1.51E-11 1.61E-11 2.57E-11 Y-93 4.58E-02 4.90E-02 7.77E-02 NB-95 5.08E+02 5.12E+02 6.04E+02 NB-95M no data no data no data ZR-95 8.13E-01 7.94E-01 1.78E+00 ZR-97 1.69E-02 1.71E-02 4.03E-02 MO-99 no data no data no data TC-99M 9.24E-04 9.22E-04 1.52E-03 RU-103 8.30E+00 8.43E+00 1.55E+01 RU-105 1.66E-02 1.73E-02 3.29E-02 AG-110M 3.87E+00 3.55E+00 7.84E+00 SN-113 no data no data no data TE-129M 1.27E+04 1.37E+04 1.80E+04 TE-131M 1.12E+03 1.21E+03 1.56E+03 TE-132 2.29E+03 2.42E+03 3.07E+03 SB-124 5.72E+01 5.59E+01 1.47E+02 SB-125 3.69E+01 3.62E+01 9.59E+01 I-131 2.28E+02 2.38E+02 4.13E+02 I-133 3.72E+01 3.92E+01 6.84E+01 I-135 2.11E+00 2.16E+00 3.66E+00 CS-134 3.47E+05 3.55E+05 4.30E+05 CS-136 3.45E+04 3.46E+04 4.10E+04 CS-137 4.44E+05 4.75E+05 6.01E+05 CS-138 1.06E-11 1.14E-11 1.45E-11 BA-139 1.71E-05 1.77E-05 4.07E-05 BA-140 5.57E+02 5.63E+02 1.27E+03 January 2020

Page 14 of 64 Rev. 17 LA-140 1.44E-01 1.51E-01 2.36E-01 LA-142 3.19E-07 3.35E-07 5.29E-07 CE-141 1.89E-01 1.90E-01 5.21E-01 CE-143 2.06E-02 2.07E-02 5.66E-02 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.

January 2020

Page 15 of 64 Rev. 17 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A i DOSE FACTOR (MREM-ML PER HR-µCi)

KIDNEY RADIONUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 no data no data no data CR-51 3.28E-01 3.35E-01 2.57E-01 MN-54 1.53E+03 1.51E+03 1.13E+03 FE-55 no data no data no data FE-59 no data no data no data CO-57 no data no data no data CO-58 no data no data no data CO-60 no data no data no data NI-63 no data no data no data ZN-65 5.72E+04 5.41E+04 4.22E+04 SR-89 no data no data no data SR-90 no data no data no data Y-91M no data no data no data Y-93 no data no data no data NB-95 2.79E+02 2.75E+02 2.21E+02 NB-95M no data no data no data ZR-95 4.09E-01 3.68E-01 5.60E-01 ZR-97 5.14E-03 5.14E-03 8.35E-03 MO-99 3.46E+02 3.61E+02 4.77E+02 TC-99M 3.96E-02 3.83E-02 4.33E-02 RU-103 3.17E+01 2.97E+01 3.91E+01 RU-105 2.14E-01 2.18E-01 2.89E-01 AG-110M 7.04E+00 6.40E+00 9.86E+00 SN-113 no data no data no data TE-129M 5.31E+04 5.74E+04 5.29E+04 TE-131M 5.55E+03 6.01E+03 5.22E+03 TE-132 1.43E+04 1.47E+04 1.27E+04 SB-124 no data no data no data SB-125 no data no data no data I-131 5.57E+02 5.73E+02 6.82E+02 I-133 1.12E+02 1.16E+02 1.41E+02 I-135 8.86E+00 8.77E+00 1.01E+01 CS-134 2.67E+05 2.66E+05 2.19E+05 CS-136 7.57E+04 7.42E+04 6.00E+04 CS-137 2.06E+05 2.15E+05 1.87E+05 CS-138 1.54E-11 1.61E-11 1.41E-11 BA-139 1.14E-08 1.18E-08 1.90E-08 BA-140 2.38E-01 2.34E-01 3.62E-01 January 2020

Page 16 of 64 Rev. 17 LA-140 no data no data no data LA-142 no data no data no data CE-141 5.94E-02 5.98E-02 1.14E-01 CE-143 6.70E-03 6.77E-03 1.29E-02 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.

January 2020

Page 17 of 64 Rev. 17 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A i DOSE FACTOR (MREM-ML PER HR-µCi)

GI-LLI RADIONUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 1.73E+05 1.41E+05 5.98E+04 CR-51 3.74E+02 2.57E+02 8.98E+01 MN-54 1.58E+04 1.04E+04 3.38E+03 FE-55 3.22E+02 2.60E+02 1.17E+02 FE-59 9.90E+03 7.15E+03 2.84E+03 CO-57 6.94E+02 5.24E+02 2.34E+02 CO-58 2.35E+03 1.56E+03 6.04E+02 CO-60 6.30E+03 4.33E+03 1.70E+03 NI-63 5.56E+02 4.46E+02 2.01E+02 ZN-65 5.38E+04 3.58E+04 1.18E+04 SR-89 4.94E+03 3.93E+03 2.01E+03 SR-90 2.22E+04 1.77E+04 9.13E+03 Y-91M 4.44E-11 7.58E-10 5.03E-08 Y-93 1.45E+03 1.50E+03 1.18E+03 NB-95 1.72E+06 1.21E+06 4.35E+05 NB-95M no data no data no data ZR-95 8.27E+02 5.78E+02 4.08E+02 ZR-97 1.06E+03 9.19E+02 8.81E+02 MO-99 3.54E+02 2.82E+02 1.85E+02 TC-99M 1.54E+00 1.69E+00 1.69E+00 RU-103 9.69E+02 7.04E+02 4.01E+02 RU-105 1.01E+01 1.40E+01 2.15E+01 AG-110M 1.46E+03 9.43E+02 6.30E+02 SN-113 no data no data no data TE-129M 6.40E+04 5.15E+04 2.19E+04 TE-131M 5.44E+04 4.63E+04 2.19E+04 TE-132 7.02E+04 4.85E+04 1.37E+04 SB-124 1.62E+03 1.13E+03 9.19E+02 SB-125 4.07E+02 2.82E+02 2.29E+02 I-131 8.58E+01 6.57E+01 3.70E+01 I-133 5.82E+01 5.03E+01 3.40E+01 I-135 6.24E+00 6.16E+00 5.03E+00 CS-134 1.44E+04 1.04E+04 3.80E+03 CS-136 1.55E+04 1.09E+04 3.96E+03 CS-137 1.18E+04 9.00E+03 3.60E+03 CS-138 8.94E-17 9.90E-15 9.25E-12 BA-139 3.04E-05 1.58E-04 2.35E-03 BA-140 1.15E+03 8.69E+02 6.43E+02 January 2020

Page 18 of 64 Rev. 17 LA-140 5.34E+03 4.25E+03 2.30E+03 LA-142 1.06E-03 4.52E-03 3.34E-02 CE-141 4.89E+02 3.63E+02 3.24E+02 CE-143 5.69E+02 4.54E+02 4.49E+02 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account for the time between effluent release and ingestion of fish by the maximum exposed individual.

January 2020

Page 19 of 64 Rev. 17 IV. Gaseous Pathway Dose Calculations IV.A. ODCMS 4.8.C.1.1 and 4.8.C.1.2 The dose rate in areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents shall be determined by the expressions below:

IV.A.1 Noble Gases:

The dose rate from radioactive noble gas releases shall be determined by either of two methods. Method (a), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for total body dose (vent and stack releases) and skin dose (vent releases) and Kr-87 for skin dose (stack releases). Method (b), the Isotopic Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.

a. Gross Release Method DT B = V Q (

NS + K Q ) V NV Q

DS = [L S ( Q) S

+ 11

.B ] NS +

Q [L V + 11

.M ] ( Q) V Q N V where:

The location is the site boundary, 1100m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.

DT B = total body dose rate, in mrem/yr.

DS = skin dose rate, in mrem/yr.

V = 4.72 X 10-4 mrem/yr per µCi/sec; the constant for Kr-88 accounting for the gamma radiation from the elevated finite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.

January 2020

Page 20 of 64 Rev. 17 IV.A.1.a (Cont'd)

Q N S = The gross release rate of noble gases from the stack determined by gross activity stack monitors averaged over one hour, in µCi/sec.

K = 1.47 X 104 mrem/yr per µCi/m3; the total body dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1).

( Q) V

= 1.12 X 10-6 sec/m3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.

Q N V = The gross release rate of noble gases in gaseous effluents from vent releases determined by gross activity vent monitors averaged over one hour, in µCi/sec.

LV = 2.37 x 103 mrem/yr per µCi/m3; the skin dose factor due to beta emissions for Kr-88.

(Reg. Guide 1.109, Table B-1).

LS = 9.73 X 103 mrem/yr per µCi/m3; the skin dose factor due to beta emissions for Kr-87.

(Reg. Guide 1.109, Table B-1).

( Q) S

= 9.97 X 10-8 sec/m3; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

B = 1.74 X 10-4 mrad/yr per µCi/sec; the constant for Kr-87 accounting for the gamma radiation from the elevated finite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.

M = 1.52 X 104 mrad/yr per µCi/m3; the air dose factor due to gamma emissions for Kr-88.

(Reg. Guide 1.109, Table B-1).

11. = Unit conversion, converts air dose to skin dose, mrem/mrad.

January 2020

Page 21 of 64 Rev. 17 IV.A.1. b. Isotopic Analysis Method DT B = (V i

i ( )

QiS + K i Q V

QiV )

DS = (L ( Q) i i S

+ 11 )

. Bi Q iS + (Li + 11 ( )

. Mi ) Q V Q iV where:

The location is the site boundary, 1100m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.

DT B = total body dose rate, in mrem/yr.

DS = skin dose rate, in mrem/yr.

Vi = The constant for each identified noble gas radionuclide for the gamma radiation from the elevated finite plume. The constants were developed using the MARE program with plant specific inputs for PBAPS. Values are listed on Table IV.A.1, in mrem/yr per

µCi/sec.

iS Q = The release rate of noble gas radionuclide, i, in gaseous effluents from the stack determined by isotopic analysis averaged over one hour, in µCi/sec.

Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide. Values are listed on Table IV.A.1, in mrem/yr per µCi/m3.

( Q) V

= 1.12 X 10-6 sec/m3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.

QiV = The release rate of noble gas radionuclide, i, in gaseous effluents from all vent releases determined by isotopic analysis averaged over one hour, in µCi/sec.

January 2020

Page 22 of 64 Rev. 17 IV.A.1.b (Cont'd)

Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide.

Values are listed on Table IV.A.1, in mrem/yr per µCi/m3.

( Q) S

= 9.97 X 10-8 sec/m3; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

Bi = The constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume.

The constants were developed using MARE program with plant specific inputs for PBAPS. Values are listed on Table IV.A.1, in mrad/yr per µCi/sec.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide.

Values are listed on Table IV.A.1, in mrad/yr per µCi/m3.

11

. = Unit conversion, coverts air dose to skin dose, mrem/mrad.

January 2020

Page 23 of 64 Rev. 17 TABLE IV.A.1 - Constants for Isotopic Analysis Method (corrected for decay during transit)

Plume-Air Total Body Skin Gamma Air Beta Air Plume-Body Dose Factor Dose Factor Dose Factor Dose Factor Dose Factor Dose Factor Bi Ki Li Mi Ni Vi Radionuclide (mrad/yr per (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per (mrem/yr per

µCi/m3) µCi/m3) µCi/m3) µCi/m3) µCi/sec)

µCi/sec)

Kr-85m 4.02E-05 1.17E+03 1.46E+03 1.23E+03 1.97E+03 3.76E-05 Kr-87 1.74E-04 5.92E+03 9.73E+03 6.17E+03 1.03E+04 1.66E-04 Kr-88 4.90E-04 1.47E+04 2.37E+03 1.52E+04 2.93E+03 4.72E-04 Xe-133 1.19E-05 2.94E+02 3.06E+02 3.53E+02 1.05E+03 1.11E-05 Xe-133m 1.09E-05 2.51E+02 9.94E+02 3.27E+02 1.48E+03 1.01E-05 Xe-135 6.37E-05 1.81E+03 1.86E+03 1.92E+03 2.46E+03 5.95E-05 Xe-135m 6.61E-05 2.53E+03 5.76E+02 2.72E+03 5.99E+02 6.17E-05 Xe-138 1.52E-04 6.98E+03 3.26E+03 7.28E+03 3.75E+03 1.46E-04 The values K i , L i , M i , and N i are taken from Reg. Guide 1.109, Table B-1. The values B i and V i were developed using the MARE program with plant specific inputs for PBAPS.

January 2020

Page 24 of 64 Rev. 17 IV.A.2 Iodine-131, iodine-133, tritium and radioactive materials in particulate form, other than noble gases, with half-lives greater than eight days:

The dose rate shall be determined for either of two critical organs and most restrictive age group. Child thyroid dose is limiting when iodine releases exceed 10 percent of the total release rates. The teenager lung dose is limiting when iodine is either not present or a small fraction of the total release.

When it is not clear which organ dose will be limiting, doses for both restrictive age group organs will be calculated and the limiting organ dose identified.

[

D = Pi WS Q iS + WV Q iV + WV q iV i

]

where:

The location is the site boundary, 1100m SSE from the vents.

D = dose rate to the critical organ most restrictive age group, in mrem/yr.

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway.

The dose factors are based on the critical organ, and most restrictive age group. All values are from Reg. Guide 1.109 (Tables E-5, E-8, E-9 and E-10). Values are listed on Table IV.A.2, in mrem/yr per µCi/m3 WS = 1.09 X 10-8 sec/m3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY from stack releases. (SSE boundary)

Q iS = The release rate of radionuclides; i, in gaseous effluents from the stack determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in µCi/sec.

WV = 1.32 X 10-6 sec/m3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases. (SSE boundary)

January 2020

Page 25 of 64 Rev. 17 IV.A.2. (Cont'd)

Q iV = The release rate of radionuclide, i, in gaseous effluents from all vent releases, determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in

µCi/sec.

q iv = The release rate of radionuclide, i, in gaseous effluents from abnormal release sources.

January 2020

Page 26 of 64 Rev. 17 TABLE IV.A.2 Pi CONSTANTS FOR CRITICAL ORGAN FOR THE MOST RESTRICTIVE AGE GROUP (mrem/yr per µCi/m3)

INFANT INFANT CHILD TEENAGER RADIONUCLIDE THYROID LUNG DOSE THYROID LUNG DOSE DOSE FACTOR DOSE FACTOR FACTOR FACTOR H-3 6.47E+02 6.47E+02 1.13E+03 1.27E+03 C-14 5.31E+03 5.31E+03 6.73E+03 4.87E+03 NA-24 1.06E+04 1.06E+04 1.61E+04 1.38E+04 P-32 no data no data no data no data Cr-51 5.75E+01 1.28E+04 8.55+01 2.10E+04 MN-54 no data 1.00E+06 no data 1.98E+06 FE-55 no data 8.69E+04 no data 1.24E+05 MN-56 no data 1.25E+04 no data 1.52E+04 CO-58 no data 7.77E+05 no data 1.34E+06 FE-59 no data 1.02E+06 no data 1.53E+06 CO-60 no data 4.51E+06 no data 8.72E+06 NI-63 no data 2.09E+05 no data 3.07E+05 CU-64 no data 9.30E+03 no data 1.11E+04 NI-65 no data 8.12E+03 no data 9.36E+03 ZN-65 no data 6.47E+05 no data 1.24E+06 ZN-69 no data 1.47E+03 no data 1.58E+03 BR-83 no data no data no data no data BR-84 no data no data no data no data BR-85 no data no data no data no data RB-86 no data no data no data no data RB-88 no data no data no data no data RB-89 no data no data no data no data SR-89 no data 2.03E+06 no data 2.42E+06 SR-90 no data 1.12E+07 no data 1.65E+07 Y-90 no data 2.69E+05 no data 2.93E+05 SR-91 no data 5.26E+04 no data 6.07E+04 Y-91M no data 2.79E+03 no data 3.20E+03 Y-91 no data 2.45E+06 no data 2.94E+06 SR-92 no data 2.38E+04 no data 2.74E+04 Y-92 no data 2.45E+04 no data 2.68E+04 Y-93 no data 7.64E+04 no data 8.32E+04 NB-95 no data 4.79E+05 no data 7.51E+05 ZR-95 no data 1.75E+06 no data 2.69E+06 ZR-97 no data 1.10E+05 no data 1.30E+05 MO-99 no data 1.35E+05 no data 1.54E+05 TC-99M no data 8.11E+02 no data 1.15E+03 TC-101 no data 5.84E+02 no data 6.67E+02 January 2020

Page 27 of 64 Rev. 17 RU-103 no data 5.52E+05 no data 7.83E+05 RU-105 no data 1.57E+04 no data 1.82E+04 RU-106 no data 1.16E+07 no data 1.61E+07 AG-110M no data 3.67E+06 no data 6.75E+06 TE-125M 1.62E+03 4.47E+05 1.92E+03 5.36E+05 TE-127M 4.87E+03 1.31E+06 6.07E+03 1.66E+06 TE-127 1.85E+00 1.04E+04 1.96E+00 1.12E+04 TE-129M 5.47E+03 1.68E+06 6.33E+03 1.98E+06 TE-129 6.75E-02 3.00E+03 7.14E-02 3.30E+03 I-130 1.60E+06 no data 1.85E+06 no data I-131 1.48E+07 no data 1.62E+07 no data TE-131M 8.93E+01 1.99E+05 9.77E+01 2.38E+05 TE-131 1.58E-02 2.06E+03 1.70E-02 2.34E+03 I-132 1.69E+05 no data 1.94E+05 no data TE-132 2.79E+02 3.40E+05 3.18E+02 4.49E+05 I-133 3.56E+06 no data 3.85E+06 0.00E+00 CS-134 no data 7.97E+04 0.00E+00 1.46E+05 I-134 4.45E+04 no data 5.07E+04 no data I-135 6.96E+05 no data 7.92E+05 no data CS-136 no data 1.18E+04 no data 1.78E+04 CS-137 no data 7.13E+04 no data 1.21E+05 CS-138 no data 6.54E+01 no data 7.87E+01 BA-139 no data 5.95E+03 no data 6.46E+03 BA-140 no data 1.60E+06 no data 2.03E+06 LA-140 no data 1.68E+05 no data 2.14E+05 BA-141 no data 2.97E+03 no data 3.29E+03 CE-141 no data 5.17E+05 no data 6.14E+05 BA-142 no data 1.55E+03 no data 1.91E+03 LA-142 no data 8.22E+03 no data 1.02E+04 CE-143 no data 1.16E+05 no data 1.30E+05 PR-143 no data 4.33E+05 no data 4.83E+05 CE-144 no data 9.84E+06 no data 1.34E+07 PR-144 no data 1.61E+03 no data 1.75E+03 ND-147 no data 3.22E+05 no data 3.72E+05 W-187 no data 3.96E+04 no data 4.74E+04 NP-239 no data 5.95E+04 no data 6.49E+04 January 2020

Page 28 of 64 Rev. 17 IV.B. ODCMS 4.8.C.2.1 The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous effluents shall be determined by the expressions below.

The air dose shall be determined by either of two methods.

Method (a), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for gamma radiation and Kr-87 for beta radiation. Method (b),

the Isotopic Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.

IV.B.1 for gamma radiation:

a. Gross Release Method D = 317 [ ( )

. x 10 8 M Q V

~ ~

Q V + B QS ]

where:

The location is the SITE BOUNDARY 1100m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.

D = gamma air dose, in mrad.

. x 108 317 = years per second.

M = 1.52 x 104 mrad/yr per µCi/m3; the air dose factor due to gamma emissions for Kr-88.

(Reg. Guide 1.109, Table B-1)

( Q) V

= 1.12 x 10-6 sec/m3; the highest calculated annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.

~

QV = The gross release of noble gas radionuclides in gaseous effluents from all vents, determined by gross activity vent monitors, in µCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

January 2020

Page 29 of 64 Rev. 17 IV.B.1. a (Cont'd)

B = 4.90 x 10-4 mrad/year per µCi/sec; the constant for Kr-88 accounting for the gamma radiation from the elevated finite plume.

The constant was developed using the MARE program with plant specific inputs for PBAPS.

~

QS = The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitor in µCi. Releases shall be cumulative over the calendar quarter or year as appropriate.

b. Isotopic Analysis Method D = 317. x 10 8 [ M ( Q) i i V

~ ~

QiV + Bi QiS ]

where:

The location is the SITE BOUNDARY, 1100m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.

D = gamma air dose, in mrad.

. x 108 317 = years per second.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide.

Values are listed on Table IV.A.1, in mrad/yr per µCi/m3.

( Q) V

= 1.12 x 10-6 sec/m3; the highest calculated average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.

~

Q iV = The release of noble gas radionuclides, i, in gaseous effluents from all vents as determined by isotopic analysis, in µCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

January 2020

Page 30 of 64 Rev. 17 Bi = The constant for each identified noble gas radionuclide accounting for the gamma radiation for the elevated finite plume.

The constants were developed using the MARE program with plant specific inputs for PBAPS. Values are listed on Table IV.A.1, in mrad/yr per µCi/sec.

IV.B.1. b. (Cont'd)

~

Q iS = The release of noble gas radionuclides, i, in gaseous effluents from the stack determined by isotopic analysis, in µCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

IV.B.2. for beta radiation:

a. Gross Release Method D = 317 [(

. x 10 8 N Q ) V

~

( )

QV + Q S

~

QS ]

where:

The location is the SITE BOUNDARY 1100m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.

D = beta air dose, in mrad.

. x 108 317 = years per second.

N = 1.03 x 104 mrad/yr per µCi/m3; the air dose factor due to beta emissions for Kr-87.

(Reg. Guide 1.109, Table B-1)

( Q) V

= 1.12 x 10-6 sec/m3; the highest calculated annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.

~

QV = The gross release of noble gas radionuclides in gaseous effluents from all vents determined by gross activity vent monitors, in µCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

January 2020

Page 31 of 64 Rev. 17

( Q) S

= 9.97 x 10-8 sec/m3; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

~

QS = The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitors, in µCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

IV.B.2. b. Isotopic Analysis Method D = 317 . x 10 8 N [( Q) i i V

~

( )

Q iV + Q S

~

Q iS ]

. x 108 317 = years per second.

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide.

Values are listed on Table IV.A.1, in mrad/yr per µCi/m3.

( Q) V

= 1.12 x 10-6 sec/m3; the highest calculated annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.

~

Q iV = The release of noble gas radionuclide, i, in gaseous effluents from all vents as determined by isotopic analysis, in µCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

( Q) S

= 9.97 x 10-8 sec/m3; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

~

Q iS = The release of noble gas radionuclide, i, in gaseous effluents from the stack as determined by isotopic analysis, in µCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

January 2020

Page 32 of 64 Rev. 17 IV.C ODCMS 4.8.C.3.1 The dose to an individual from iodine-131, iodine-133, tritium and radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY.

The dose shall be determined for the limiting organ. Infant thyroid doses are dominating any time that either iodine-131 release rates are more than two (2) percent of total release rates or iodine-133 exceeds 25 percent of total release rates. In these cases only iodine-131 and iodine-133 are potentially significant.

For cases where there is no detectable iodine releases, doses shall be determined for infant bone and liver. Both bone and liver doses are calculated because the controlling dose is dependent upon the presence of strontium.

When it is not clear whether thyroid, bone, or liver doses are controlling, all three shall be calculated and the limiting dose identified.

~

. x 10 8 Fe R i WS QiS + WV QiV + WV q iV

~ ~

D = 317 i

where:

Location is the critical pathway dairy 1500m SW from vents.

D = limiting dose to the critical infant organ, from the milk, or inhalation, or ground plane pathways, in mrem.

. x 108 317 = years per second.

Fe = Fraction that is elemental (0.5 for iodines and 1.0 for all other elements).

Ri = The dose factor for each identified radionuclide; i, in m2 (mrem/yr) per µCi/sec except tritium, carbon-14, and inhalation pathway, which is in mrem/yr per µCi/m3. The dose factors are for the critical individual organ for the most restrictive age group, infant. Table IV.C.1 list values for the ingestion pathway, Table IV.C.2 for the inhalation pathway, and Table IV.C.3 for the ground plane pathway. See Site Specific Data.**

January 2020

Page 33 of 64 Rev. 17 IV.C (Continued)

WS = 4.19 x 10-10 meters-2 ( D / Q) for the ingestion and ground plane pathway for stack releases.

Tritium, carbon-14, and the inhalation pathway use a ( /Q) of 8.11 x 10-9 sec/m3.

~

QiS = The release of radionuclide, i, in gaseous effluents from the stack determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1), in µCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

WV ( )

= 1.58 x 10-9 meters-2 D Q for the ingestion and ground plane pathway for vent releases.

Tritium, carbon-14, and the inhalation pathway use a ( /Q) of 4.43 x 10-7 sec/m3.

    • See Note 2 and 3 in Bases

~

QiV = The release of radionuclide, i, in gaseous effluents from the vents determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in µCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

~

q iV = The release of radionuclide, i, in gaseous effluents from abnormal release sources in

µCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

January 2020

Page 34 of 64 Rev. 17 TABLE IV.C.1 Ri CONSTANTS INGESTION PATHWAY (m2 (mrem/yr) per µCi/sec)*

Radionuc Infant Bone Infant Infant Infant Kidney Infant Infant GI-LLI Infant Infant T Body lide Liver Thyroid Lung Skin H-3 no data 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.30E+03 no data 1.30E+03 C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 no data 6.89E+05 NA-24 4.48E+06 4.48E+06 4.48E+06 4.48E+06 4.48E+06 4.48E+06 no data 4.48E+06 P-32 4.74E+10 2.79E+09 no data no data no data 6.41E+08 no data 1.84E+09 CR-51 no data no data 3.35E+04 7.32E+03 6.51E+04 1.50E+06 no data 5.13E+04 MN-54 no data 1.93E+07 no data 4.28E+06 no data 7.09E+06 no data 4.38E+06 FE-55 7.09E+07 4.58E+07 no data no data 2.24E+07 5.81E+06 no data 1.22E+07 MN-56 no data 9.24E-03 no data 7.94E-03 no data 8.39E-01 no data 1.59E-03 CO-58 no data 9.57E+06 no data no data no data 2.39E+07 no data 2.39E+07 FE-59 7.92E+07 1.38E+08 no data no data 4.09E+07 6.61E+07 no data 5.45E+07 CO-60 no data 4.69E+07 no data no data no data 1.12E+08 no data 1.11E+08 NI-63 1.88E+10 1.17E+09 no data no data no data 5.80E+07 no data 6.54E+08 CU-64 no data 5.42E+04 no data 9.17E+04 no data 1.11E+06 no data 2.51E+04 NI-65 1.03E+00 1.16E-01 no data no data no data 8.85E+00 no data 5.29E-02 ZN-65 2.69E+09 9.22E+09 no data 4.47E+09 no data 7.78E+09 no data 4.25E+09 ZN-69 3.09E+04 5.56E+04 no data 2.31E+04 no data 4.54E+06 no data 4.14E+03 BR-83 no data no data no data no data no data no data no data 1.20E-01 BR-84 no data no data no data no data no data no data no data 1.64E-23 BR-85 no data no data no data no data no data no data no data no data RB-86 no data 6.69E+09 no data no data no data 1.71E+08 no data 3.31E+09 RB-88 no data 5.60E-45 no data no data no data 5.45E-45 no data 3.07E-45 RB-89 no data 9.86E-53 no data no data no data 3.36E-53 no data 6.79E-53 SR-89 4.58E+09 no data no data no data no data 9.42E+07 no data 1.31E+08 SR-90 6.55E+10 no data no data no data no data 8.18E+08 no data 1.67E+10 Y-90 1.99E+02 no data no data no data no data 2.74E+05 no data 5.33E+00 SR-91 7.94E+04 no data no data no data no data 9.40E+04 no data 2.87E+03 Y-91M 1.66E-19 no data no data no data no data 5.53E-16 no data 5.65E-21 Y-91 2.77E+04 no data no data no data no data 1.98E+06 no data 7.37E+02 SR-92 1.36E+00 no data no data no data no data 1.47E+01 no data 5.05E-02 Y-92 1.57E-04 no data no data no data no data 3.01E+00 no data 4.43E-06 Y-93 6.31E-01 no data no data no data no data 4.98E+03 no data 1.72E-02 NB-95 1.98E+05 8.16E+04 no data 5.85E+04 no data 6.89E+07 no data 4.72E+04 ZR-95 2.62E+03 6.40E+02 no data 6.89E+02 no data 3.19E+05 no data 4.54E+02 ZR-97 1.19E+00 2.04E-01 no data 2.05E-01 no data 1.30E+04 no data 9.31E-02 MO-99 no data 6.07E+07 no data 9.07E+07 no data 2.00E+07 no data 1.18E+07 TC-99M 8.04E+00 1.66E+01 no data 1.78E+02 8.67E+00 4.82E+03 no data 2.14E+02 TC-101 7.44E-60 9.38E-60 no data 1.11E-58 5.11E-60 1.59E-57 no data 9.28E-59 RU-103 2.97E+03 no data no data 6.18E+03 no data 3.61E+04 no data 9.93E+02 RU-105 2.36E-03 no data no data 1.73E-02 no data 9.38E-01 no data 7.94E-04 RU-106 9.54E+04 no data no data 1.13E+05 no data 7.24E+05 no data 1.19E+04 AG-110M 1.87E+08 1.37E+08 no data 1.95E+08 no data 7.09E+09 no data 9.04E+07 SB-124 5.31E+07 7.81E+05 1.41E+05 no data 3.32E+07 1.64E+08 no data 1.64E+07 SB-125 5.23E+07 5.06E+05 6.55E+04 no data 3.03E+07 6.98E+07 no data 1.08E+07 TE-125M 5.68E+07 1.90E+07 1.91E+07 no data no data 2.71E+07 no data 7.68E+06 TE-127M 1.82E+08 6.03E+07 5.26E+07 4.48E+08 no data 7.34E+07 no data 2.20E+07 TE-127 1.85E+03 6.19E+02 1.50E+03 4.51E+03 no data 3.88E+04 no data 3.97E+02 January 2020

Page 35 of 64 Rev. 17 TE-129M 1.84E+08 6.32E+07 7.08E+07 4.61E+08 no data 1.10E+08 no data 2.84E+07 TE-129 7.99E-10 2.76E-10 6.70E-10 1.99E-09 no data 6.39E-08 no data 1.87E-10 I-130 1.04E+06 2.28E+06 2.56E+08 2.51E+06 no data 4.89E+05 no data 9.17E+05 I-131 7.97E+08 9.39E+08 3.08E+11 1.10E+09 no data 3.35E+07 no data 4.13E+08 TE-131M 9.87E+05 3.97E+05 8.05E+05 2.73E+06 no data 6.69E+06 no data 3.28E+05 TE-131 1.03E-32 3.79E-33 9.15E-33 2.62E-32 no data 4.14E-31 no data 2.88E-33 I-132 3.66E-01 7.43E-01 3.48E+01 8.29E-01 no data 6.02E-01 no data 2.65E-01 TE-132 6.17E+06 3.05E+06 4.51E+06 1.91E+07 no data 1.13E+07 no data 2.85E+06 I-133 1.06E+07 1.54E+07 2.81E+09 1.81E+07 no data 2.61E+06 no data 4.52E+06 CS-134 1.90E+10 3.54E+10 no data 9.11E+09 3.73E+09 9.61E+07 no data 3.57E+09 I-134 4.81E-12 9.86E-12 2.30E-10 1.10E-11 no data 1.02E-11 no data 3.51E-12 I-135 3.21E+04 6.39E+04 5.73E+06 7.12E+04 no data 2.31E+04 no data 2.33E+04 CS-136 5.80E+08 1.71E+09 no data 6.80E+08 1.39E+08 2.59E+07 no data 6.37E+08 CS-137 2.77E+10 3.24E+10 no data 8.71E+09 3.53E+09 1.01E+08 no data 2.30E+09 CS-138 2.58E-23 4.20E-23 no data 2.09E-23 3.27E-24 6.71E-23 no data 2.04E-23 BA-139 1.26E-07 8.32E-11 no data 5.00E-11 5.04E-11 7.95E-06 no data 3.63E-09 BA-140 7.09E+07 7.09E+04 no data 1.68E+04 4.35E+04 1.74E+07 no data 3.65E+06 LA-140 1.18E+01 4.67E+00 no data no data no data 5.49E+04 no data 1.20E+00 BA-141 1.41E-45 9.65E-49 no data 5.80E-49 5.87E-49 1.72E-44 no data 4.44E-47 CE-141 1.42E+04 8.69E+03 no data 2.68E+03 no data 4.49E+06 no data 1.02E+03 BA-142 7.43E-80 6.18E-83 no data 3.56E-83 3.74E-83 3.07E-79 no data 3.66E-81 LA-142 4.99E-11 1.83E-11 no data no data no data 3.11E-06 no data 4.39E-12 CE-143 1.16E+02 7.70E+04 no data 2.24E+01 no data 4.49E+05 no data 8.78E+00 PR-143 4.38E+02 1.64E+02 no data 6.09E+01 no data 2.31E+05 no data 2.17E+01 CE-144 1.14E+06 4.68E+05 no data 1.89E+05 no data 6.55E+07 no data 6.40E+04 PR-144 1.70E-53 6.59E-54 no data 2.39E-54 no data 3.07E-49 no data 8.58E-55 ND-147 2.58E+02 2.65E+02 no data 1.02E+02 no data 1.68E+05 no data 1.63E+01 W-187 1.79E+04 1.24E+04 no data no data no data 7.31E+05 no data 4.30E+03 NP-239 1.06E+01 9.51E-01 no data 1.90E+00 no data 2.75E+04 no data 5.37E-01 NP-237 5.33E+07 3.53E+06 no data 1.41E+07 no data 1.83E+06 no data 2.33E+06 NP-238 1.02E+02 2.56E+00 no data 5.58E+00 no data 3.42E+04 no data 1.57E+00

  • Tritium and C-14 R i values in units of mrem/yr per µCi/m3 January 2020

Page 36 of 64 Rev. 17 TABLE IV.C.2 Ri CONSTANTS INHALATION PATHWAY (mrem/yr per µCi/m3)

Radionuclide Infant Bone Infant Liver Infant Infant Kidney Infant Lung Infant GI-LLI Infant Infant T Thyroid Skin Body H-3 no data 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 no data 6.47E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 no data 5.31E+03 NA-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 no data 1.06E+04 P-32 2.03E+06 1.12E+05 no data no data no data 1.61E+04 no data 7.74E+04 CR-51 no data no data 5.75E+01 1.32E+01 1.28E+04 3.57E+02 no data 8.95E+01 MN-54 no data 2.53E+04 no data 4.98E+03 1.00E+06 7.06E+03 no data 4.98E+03 FE-55 1.97E+04 1.18E+04 no data no data 8.69E+04 1.10E+03 no data 3.33E+03 MN-56 no data 1.54E+00 no data 1.10E+00 1.25E+04 7.17E+04 no data 2.21E-01 CO-58 no data 1.22E+03 no data no data 7.77E+05 1.11E+04 no data 1.82E+03 FE-59 1.36E+04 2.35E+04 no data no data 1.02E+06 2.48E+04 no data 9.48E+03 CO-60 no data 8.02E+03 no data no data 4.51E+06 3.19E+04 no data 1.18E+04 NI-63 3.39E+05 2.04E+04 no data no data 2.09E+05 2.42E+03 no data 1.16E+04 CU-64 no data 1.88E+00 no data 3.98E+00 9.30E+03 1.50E+04 no data 7.74E-01 NI-65 2.39E+00 2.84E-01 no data no data 8.12E+03 5.01E+04 no data 1.23E-01 ZN-65 1.93E+04 6.26E+04 no data 3.25E+04 6.47E+05 5.14E+04 no data 3.11E+04 ZN-69 5.39E-02 9.67E-02 no data 4.02E+02 1.47E+03 1.32E+04 no data 7.18E-03 BR-83 no data no data no data no data no data no data no data 3.81E+02 BR-84 no data no data no data no data no data no data no data 4.00E+02 BR-85 no data no data no data no data no data no data no data 2.04E+01 RB-86 no data 1.90E+05 no data no data no data 3.04E+03 no data 8.82E+04 RB-88 no data 5.57E+02 no data no data no data 3.39E+02 no data 2.87E+02 RB-89 no data 3.21E+02 no data no data no data 6.82E+01 no data 2.06E+02 SR-89 3.98E+05 no data no data no data 2.03E+06 6.40E+04 no data 1.14E+04 SR-90 4.09E+07 no data no data no data 1.12E+07 1.31E+05 no data 2.59E+06 Y-90 3.29E+03 no data no data no data 2.69E+05 1.04E+05 no data 8.82E+01 SR-91 9.56E+01 no data no data no data 5.26E+04 7.34E+04 no data 3.46E+00 Y-91M 4.07E-01 no data no data no data 2.79E+03 2.35E+03 no data 1.39E-02 Y-91 5.88E+05 no data no data no data 2.45E+06 7.03E+04 no data 1.57E+04 SR-92 1.05E+01 no data no data no data 2.38E+04 1.40E+05 no data 3.91E-01 Y-92 1.64E+01 no data no data no data 2.45E+04 1.27E+05 no data 4.61E-01 Y-93 1.50E+02 no data no data no data 7.64E+04 1.67E+05 no data 4.07E+00 NB-95 1.57E+04 6.43E+03 no data 4.72E+03 4.79E+05 1.27E+04 no data 3.78E+03 ZR-95 1.15E+05 2.79E+04 no data 3.11E+04 1.75E+06 2.17E+04 no data 2.03E+04 ZR-97 1.50E+02 2.56E+01 no data 2.59E+01 1.10E+05 1.40E+05 no data 1.17E+01 MO-99 no data 1.65E+02 no data 2.65E+02 1.35E+05 4.87E+04 no data 3.23E+01 TC-99M 1.40E-03 2.88E-03 no data 3.11E-02 8.11E+02 2.03E+03 no data 3.72E-02 TC-101 6.51E-05 8.23E-05 no data 9.79E-04 5.84E+02 8.44E+02 no data 8.12E-04 RU-103 2.02E+03 no data no data 4.24E+03 5.52E+05 1.61E+04 no data 6.79E+02 RU-105 1.22E+00 no data no data 8.99E-01 1.57E+04 4.84E+04 no data 4.10E-01 RU-106 8.68E+04 no data no data 1.07E+05 1.16E+07 1.64E+05 no data 1.09E+04 AG-110M 9.98E+03 7.22E+03 no data 1.09E+04 3.67E+06 3.30E+04 no data 5.00E+03 TE-125M 4.76E+03 1.99E+03 1.62E+03 no data 4.47E+05 1.29E+04 no data 6.58E+02 TE-127M 1.67E+04 6.90E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 no data 2.07E+03 TE-127 2.23E+00 9.53E-01 1.85E+00 4.86E+00 1.04E+04 2.44E+04 no data 4.89E-01 TE-129M 1.41E+04 6.09E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 no data 2.23E+03 TE-129 7.88E-02 3.47E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 no data 1.88E-02 I-130 6.36E+03 1.39E+04 1.60E+06 1.53E+04 no data 1.99E+03 no data 5.57E+03 I-131 3.79E+04 4.44E+04 1.48E+07 5.18E+04 no data 1.06E+03 no data 1.96E+04 January 2020

Page 37 of 64 Rev. 17 TE-131M 1.07E+02 5.50E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 no data 3.63E+01 TE-131 1.74E-02 8.22E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 no data 5.00E-03 I-132 1.69E+03 3.54E+03 1.69E+05 3.95E+03 no data 1.90E+03 no data 1.26E+03 TE-132 3.72E+02 2.37E+02 2.79E+02 1.04E+03 3.40E+05 4.41E+04 no data 1.76E+02 I-133 1.32E+04 1.92E+04 3.56E+06 2.24E+04 no data 2.16E+03 no data 5.60E+03 CS-134 3.96E+05 7.03E+05 no data 1.90E+05 7.97E+04 1.33E+03 no data 7.45E+04 I-134 9.21E+02 1.88E+03 4.45E+04 2.09E+03 no data 1.29E+03 no data 6.65E+02 I-135 3.86E+03 7.60E+03 6.96E+05 8.47E+03 no data 1.83E+03 no data 2.77E+03 CS-136 4.83E+04 1.35E+05 no data 5.64E+04 1.18E+04 1.43E+03 no data 5.29E+04 CS-137 5.49E+05 6.12E+05 no data 1.72E+05 7.13E+04 1.33E+03 no data 4.55E+04 CS-138 5.05E+02 7.81E+02 no data 4.10E+02 6.54E+01 8.76E+02 no data 3.98E+02 BA-139 1.48E+00 9.84E-04 no data 5.92E-04 5.95E+03 5.10E+04 no data 4.30E-02 BA-140 5.60E+04 5.60E+01 no data 1.34E+01 1.60E+06 3.84E+04 no data 2.90E+03 LA-140 5.05E+02 2.00E+02 no data no data 1.68E+05 8.48E+04 no data 5.15E+01 BA-141 1.57E-01 1.08E-04 no data 6.50E-05 2.97E+03 4.75E+03 no data 4.97E-03 CE-141 2.77E+04 1.67E+04 no data 5.25E+03 5.17E+05 2.16E+04 no data 1.99E+03 BA-142 3.98E-02 3.30E-05 no data 1.90E-05 1.55E+03 6.93E+02 no data 1.96E-03 LA-142 1.03E+00 3.77E-01 no data no data 8.22E+03 5.95E+04 no data 9.04E-02 CE-143 2.93E+02 1.93E+02 no data 5.64E+01 1.16E+05 4.97E+04 no data 2.21E+01 PR-143 1.40E+04 5.24E+03 no data 1.97E+03 4.33E+05 3.72E+04 no data 6.99E+02 CE-144 3.19E+06 1.21E+06 no data 5.38E+05 9.84E+06 1.48E+05 no data 1.76E+05 PR-144 4.79E-02 1.85E-02 no data 6.72E-03 1.61E+03 4.28E+03 no data 2.41E-03 ND-147 7.94E+03 8.13E+03 no data 3.15E+03 3.22E+05 3.12E+04 no data 5.00E+02 W-187 1.30E+01 9.02E+00 no data no data 3.96E+04 3.56E+04 no data 3.11E+00 NP-239 3.71E+02 3.32E+01 no data 6.62E+01 5.95E+04 2.49E+04 no data 1.88E+01 U-232 3.60E+08 no data no data 3.36E+07 2.09E+09 6.10E+04 no data 2.98E+007 U-233 7.62E+07 no data no data 1.53E+07 4.98E+08 5.64E+04 no data 5.36E+06 U-234 7.31E+07 no data no data 1.50E+07 4.89E+08 5.53E+04 no data 5.25E+06 U-235 7.01E+07 no data no data 1.41E+07 4.59E+08 7.03E+04 no data 4.93E+06 U-236 7.01E+07 no data no data 1.44E+07 4.69E+08 5.19E+04 no data 5.04E+06 U-237 4.55E+02 no data no data 1.13E+03 1.28E+05 1.83E+04 no data 1.21E+02 U-238 6.71E+07 no data no data 1.32E+07 4.28E+08 4.96E+04 no data 4.61E+06 NP-237 4.03E+09 2.39E+09 no data 1.08E+09 4.89E+08 7.14E+04 no data 1.76E+08 NP-238 3.74E+03 8.47E+02 no data 2.06E+02 1.29E+05 3.61E+04 no data 5.82E+01 PU-238 3.77E+09 2.35E+09 no data 6.50E+08 1.26E+09 6.57E+04 no data 1.78E+08 PU-239 4.10E+09 2.46E+09 no data 6.93E+08 1.19E+09 5.99E+04 no data 1.88E+08 PU-240 4.10E+09 2.45E+09 no data 6.92E+08 1.19E+09 6.10E+04 no data 1.88E+08 PU-241 1.18E+08 2.59E+07 no data 1.61E+07 1.07E+06 1.26E+03 no data 4.35E+06 PU-242 3.81E+09 2.37E+09 no data 6.68E+08 1.14E+09 5.88E+04 no data 1.81E+08 PU-244 4.44E+09 2.72E+09 no data 7.64E+08 1.31E+09 8.76E+04 no data 2.07E+08 AM-241 4.41E+09 2.73E+09 no data 1.11E+09 5.68E+08 6.69E+04 no data 1.83E+08 AM-242M 4.55E+09 2.60E+09 no data 1.12E+09 2.30E+08 8.41E+04 no data 1.89E+08 AM-243 4.34E+09 2.63E+09 no data 1.08E+09 5.39E+08 7.84E+04 no data 1.78E+08 CM-242 1.79E+08 1.21E+08 no data 2.37E+07 4.16E+08 7.14E+04 no data 7.98E+06 CM-243 3.46E+09 2.13E+09 no data 5.47E+08 5.94E+08 7.03E+04 no data 1.48E+08 CM-244 2.90E+09 1.78E+09 no data 4.49E+08 5.71E+08 6.80E+04 no data 1.24E+08 CM-245 4.51E+09 2.74E+09 no data 7.32E+08 5.49E+08 6.34E+04 no data 1.90E+08 CM-246 4.48E+09 2.74E+09 no data 7.32E+08 5.59E+08 6.23E+04 no data 1.90E+08 CM-247 4.35E+09 2.70E+09 no data 7.21E+08 5.49E+08 8.19E+04 no data 1.86E+08 CM-248 3.61E+10 2.23E+10 no data 5.94E+09 4.52E+09 1.32E+06 no data 1.54E+09 CF-252 3.32E+09 no data no data no data 1.92E+09 2.59E+05 no data 1.41E+08 January 2020

Page 38 of 64 Rev. 17 TABLE IV.C.3 Ri CONSTANTS GROUND PLANE PATHWAY (m2 (mrem/yr) per µCi/sec)

AG-110M 3.44E+09 AM-241 6.85E+08 AM-242M 9.61E+07 AM-243 5.03E+09 BA-139 1.06E+05 BA-140 2.05E+07 BA-141 4.18E+04 BA-142 4.49E+04 BR-83 4.87E+03 BR-84 2.03E+05 BR-85 no data C-14 no data CE-141 1.37E+07 CE-143 2.31E+06 CE-144 6.96E+07 CF-252 4.83E+10 CM-242 6.85E+05 CM-243 7.05E+09 CM-244 7.84E+06 CM-245 3.67E+09 CM-246 3.86E+06 CM-247 8.51E+09 CM-248 2.63E+10 CO-58 3.79E+08 CO-60 2.32E+10 CR-51 4.66E+06 CS-134 6.91E+09 CS-136 1.50E+08 CS-137 1.30E+10 CS-138 3.59E+05 CU-64 6.07E+05 FE-55 no data FE-59 2.72E+08 H-3 no data I-130 5.51E+06 I-131 1.73E+07 I-132 1.23E+06 I-133 2.45E+06 I-134 4.46E+05 I-135 2.52E+06 LA-140 1.92E+07 LA-142 7.60E+05 MN-54 1.38E+09 MN-56 9.04E+05 MO-99 3.99E+06 January 2020

Page 39 of 64 Rev. 17 NA-24 1.19E+07 NB-95 1.37E+08 ND-147 8.40E+06 NI-63 no data NI-65 2.97E+05 NP-237 5.42E+09 NP-238 4.53E+06 NP-239 1.71E+06 P-32 no data PR-143 no data PR-144 1.83E+03 PU-238 4.65E+06 PU-239 3.06E+06 PU-240 5.02E+06 PU-241 1.14E+07 PU-242 4.26E+06 PU-244 3.46E+09 RB-86 8.97E+06 RB-88 3.31E+04 RB-89 1.23E+05 RU-103 1.08E+08 RU-105 6.36E+05 RU-106 4.22E+08 SB-124 5.98E+08 SB-125 2.38E+09 SR-89 2.16E+04 SR-90 no data SR-91 2.15E+06 SR-92 7.77E+05 TC-101 2.04E+04 TC-99M 1.84E+05 TE-125M 1.55E+06 TE-127 2.98E+03 TE-127M 9.17E+04 TE-129 2.62E+04 TE-129M 1.98E+07 TE-131 2.92E+04 TE-131M 8.03E+06 TE-132 4.23E+06 U-232 9.12E+06 U-233 8.90E+09 U-234 2.45E+06 U-235 1.24E+10 U-236 8.13E+04 U-237 5.16E+07 U-238 4.26E+08 W-187 2.36E+06 Y-90 4.49E+03 Y-91 1.07E+06 Y-91M 1.00E+05 January 2020

Page 40 of 64 Rev. 17 Y-92 1.80E+05 Y-93 1.83E+05 ZN-65 7.46E+08 ZN-69 no data ZR-95 2.45E+08 ZR-97 2.96E+06 January 2020

Page 41 of 64 Rev. 17 IV.D ODCMS 4.8.C.5.1 The projected doses from releases of gaseous effluents to areas at and beyond the SITE BOUNDARY shall be calculated in accordance with the following sections of this manual:

a. gamma air dose - IV.B.1
b. beta air dose - IV.B.2
c. organ dose - IV.C The projected dose calculation shall be based on expected release from plant operation. The normal release pathways result in the maximum releases from the plant. Any alternative release pathways result in lower releases and, therefore, lower doses.

IV.E Technical Requirements Manual Test Requirement (TR) 3.5.3 IV.E.1 The recombiner hydrogen analyzers currently used at Peach Bottom are Whittaker Electrochemical type. (Analyzers 4083A and 4083B on Unit 2. Analyzers 5083A and 5083B on Unit 3.)

IV.E.2 The calibration gas is in accordance with approved procedures.

IV.F ODCMS 4.8.C.7.1 and 4.8.C.7.2 IV.F.1 Section Removed.

IV.F.2 Section Removed.

V.A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 V.A.1 ODCMS 4.8.D.1.1 The total gaseous and liquid cumulative dose contributions are limited by ODCMS 3.8.D.1 to 3.0 mrem for whole body and critical organ, and 55 mrem for the thyroid to preserve assumptions set forth in the 10CFR72.212 report for the spent fuel casks that are stored on the Independent Spent Fuel Storage (ISFSI) pad. Exceeding these action levels does not necessarily result in the overall 40CFR190 or 10CFR72.104 requirements not being met. Further calculations are required to determine compliance.

January 2020

Page 42 of 64 Rev. 17 Whole Body The whole body dose contribution from liquid and gaseous effluents shall be determined by the following method:

DWB = D + D where:

DWB = whole body dose from liquid and gaseous effluents, in mrem.

D = cumulative dose commitment to the total body from liquid effluents, in mrem (Determined by ODCM Section III.B).

D = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem).

Critical organ(except thyroid)

The critical organ(except thyroid) dose contribution from liquid and gaseous effluents shall be determined by the following method:

DCO = D + D + D where:

DCO = critical organ(except thyroid) dose from liquid and gaseous effluents, in mrem.

D = cumulative dose commitment to any organ from liquid effluents, in mrem (Determined by ODCM Section III.B).

D = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem).

D = limiting dose to the critical organ(except thyroid),

in mrem (Determined by ODCM Section IV.C).

January 2020

Page 43 of 64 Rev. 17 Thyroid The thyroid dose contribution from gaseous effluents shall be determined by the following method:

DThy = D + D + D where:

DThy = thyroid dose from gaseous effluents, in mrem.

D = cumulative dose commitment to any organ from liquid effluents, in mrem (Determined by ODCM Section III.B).

D = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem).

D = limiting dose to the thyroid, in mrem (Determined by ODCM Section IV.C).

V.A.2 ODCMS 4.8.D.1.2 The cumulative dose from all sources(i.e. gas and liquid effluents and direct radiation) is calculated by summing the individual doses obtained in ODCMS 4.8.D.1.1 for whole body(

DWB ), critical organ( DCO ) and thyroid( D Thy ) with the dosimeter net dose(mrem).

Whole Body The cumulative whole body dose from liquid, gas and direct radiation shall be determined by the following method:

Total DWB = DWB + D D where:

Total DWB = whole body dose equivalent from all sources, in mrem.

DWB = whole body dose from liquid and gaseous effluents, in mrem.

DD = Net dose from direct radiation, in mrem.

January 2020

Page 44 of 64 Rev. 17 Critical Organ(except thyroid)

The cumulative critical organ(except thyroid) dose from liquid, gas and direct radiation shall be determined by the following method:

Total DCO = DCO + DD where:

Total DCO = critical organ(except thyroid) dose equivalent from all sources, in mrem.

DCO = critical organ(except thyroid) dose from liquid and gaseous effluents, in mrem.

DD = Net dose from direct radiation, in mrem.

Thyroid The cumulative thyroid dose from gas and direct radiation shall be determined by the following method:

Total DThy = DThy + DD where:

Total DThy = thyroid dose equivalent from all sources, in mrem.

DThy = thyroid dose from gaseous effluents, in mrem.

DD = Net dose from direct radiation, in mrem.

The dose contribution is calculated at the discharge point for liquids and in the worst sector for gases. If necessary, the dose contribution from liquid and gas may be calculated for a real individual.

January 2020

Page 45 of 64 Rev. 17 VI.A ODCMS 3.10.2.f In accordance with ODCMS 3.10.2.f the Annual Radioactive Effluent Release Report shall include an assessment of radiation dose from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their acitivies inside the SITE BOUNDARY.

There are two locations within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC for activities unrelated to the operation of Peach Bottom Atomic Power Station. These locations are the Emergency Response Location 800 ft ENE from the vents and the Warehouse Checkpoint 900 ft NNE from the vents.

Annual doses will be calculated in accordance with methodology described in ODCM IV.B and IV.C, assuming inhalation pathway, plume and ground shine doses are the dominate pathway. Continuous occupancy with current year MET data shall also be used. The maximum dose calculated will be reported in the Annual Radioactive Effluent Release Report.

VII.A ODCMS 4.8.E.1.1 and 4.8.E.1.2 The radiological environment monitoring samples shall be collected pursuant to Table VII.A.1 from the locations shown on Figures VII.A.1, VII.A.2, and VII.A.3, and shall be analyzed pursuant to the requirements of Table VII.A.1.

January 2020

Page 46 of 64 Rev. 17 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion I. Direct Radiation Site Boundary 1L 1,100 feet NE of site 1 set of two (2) Gamma Dose quarterly 1A 1,500 feet SE of site Dosimeters from each 2 4,700 feet SE of site location at least 1I 2,900 feet SSE of site quarterly 1C 4,700 feet SSE of site Gamma dose quarterly 1J 4,000 feet S of site 1F 2,900 feet SSW of site 40 8,000 feet SW of site Dosimeter sites were 1NN 2,700 feet WSW of site chosen in accordance 1H 3,200 feet W of site with Peach Bottom 1G 3,100 feet WNW of site ODCMS Table 4.8.E.1 1B 2,500 feet NW of site Item 1. Site Boundary 1E 3,000 feet NNW of site stations all sectors 1K 4,700 feet SW of site except several along Intermediate 1P 2,200 feet ESE of site Conowingo Pond. These Distance sectors are monitored 15 19,300 feet N of site by stations on the 22 12,500 feet NNE of site east side of Conowingo 44 26,700 feet NE of site Pond. The 5 mile 32 14,400 feet ENE of site vicinity stations 45 18,500 feet ENE of site cover all sectors.

14 10,300 feet E of site 17 21,500 feet ESE of site The distant and 31A 24,100 feet SE of site special interest 4K 45,900 feet SE of site stations provide 23 5,500 feet SSE of site information in 27 14,400 feet S of site population centers and 48 26,500 feet SSW of site control locations.

January 2020

Page 47 of 64 Rev. 17 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion 3A 19,300 feet SW of site 49 21,500 feet WSW of site 50 26,400 feet W of site 51 21,000 feet WNW of site 26 21,800 feet NW of site 6B 30,400 feet NW of site 42 21,600 feet NNW of site Distant 43 26,200 feet NNE of site and 5 24,400 feet E of site Special 16 67,100 feet E of site Interest 24 58,200 feet ESE of site 2B 3,900 feet SSE of site 46 23,800 feet SSE of site 47 22,700 feet S of site 18 52,200 feet W of site 19 C 124,000 feet WNW of site 1T 3,100 feet WNW of site II. Airborne Particulates 1Z 1,500 feet SE of site Approximately 1 cfm Gross beta analysis 1B 2,500 feet NW of site continuous flow on each weekly 1C 4,700 feet SSE of site through glass fiber sample. Gamma 3A 19,300 feet SW of site filter which is spectrometry shall be 5H2 C 162,400 feet NE of site collected weekly. done when gross beta exceeds ten times the These stations yearly mean of provide for coverage control station value.

January 2020

Page 48 of 64 Rev. 17 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion of the highest annual average ground level Gross beta analysis D/Q near the site done 24 hr after boundary, the sampling to allow for community with the Radon and Thoron highest annual daughter decay.

average D/Q and a control location.

Gamma Spec on quarterly composite by location.

Iodine 1Z 1,500 feet SE of site A TEDA impregnated Iodine 131 weekly 1B 2,500 feet NW of site flow-through 1C 4,700 feet SSE of site cartridge is 3A 19,300 feet SW of site connected to air 5H2 C 162,400 feet NE of site sampler and is collected weekly at site filter change.

III. Waterborne Surface 1LL C 1,200 feet ENE of site Sample collected Gamma isotopic 1MM 5,500 feet SE of site from a continuous analysis monthly; water sampler, monthly. In event H-3 on quarterly January 2020

Page 49 of 64 Rev. 17 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion sampler is composite inoperable, grab samples will be collected each calendar day until sampler returned to service.

Drinking 4L 45,900 feet SE of site Sample collected Gross beta and gamma 6I C 30,500 feet NW of site from a continuous isotopic monthly, 13B 13,300 feet ESE of site water sampler monthly. In event H-3 on quarterly sampler is composite inoperable, weekly grab samples will be collected until sampler returned to service.

Sediment 4J 7,400 feet SE of site A sediment sample Gamma isotopic analysis is taken down each sample stream of discharge semi-annually.

IV. Ingestion Milk V C 32,600 feet W of site Sample of fresh I-131 analyses on each J 5,100 feet W of site milk is collected sample R 4,900 feet SW of site from each farm U 11,200 feet SSW of site biweekly when cows Gamma isotopic analysis X 9,200 feet NW of site are on pasture or Cs-134, Cs-137 by January 2020

Page 50 of 64 Rev. 17 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion (April through chemical separation October), monthly quarterly at other times.

Fish 4 6,000-10,000 feet SE Two species of Gamma isotopic analyses of site recreationally on edible portions.

6 C 50,000-70,000 feet NNW important fish of site (predator and bottom feeder) sampled in season or semiannually if not seasonal.

Food 1C 4,700 feet SSE of site Samples of three Gamma isotopic and Products 55 C 51,900 feet NE of site (3) different I-131 analysis kinds of broad leaf vegetation monthly when available if milk sampling is not performed C = Control Location January 2020

Page 51 of 64 Rev. 17 FIGURE VII.A.1 ENVIRONMENTAL SAMPLING STATIONS AT SITE BOUNDARY AREA TO PEACH BOTTOM January 2020

Page 52 of 64 Rev. 17 FIGURE VII.A.2 ENVIRONMENTAL SAMPLING STATIONS AT INTERMEDIATE DISTANCES FROM PEACH BOTTOM SITE January 2020

Page 53 of 64 Rev. 17 FIGURE VII.A.3 ENVIRONMENTAL SAMPLING STATIONS AT REMOTE DISTANCES FROM PEACH BOTTOM SITE January 2020

Page 54 of 64 Rev. 17 Figure 1 January 2020

Page 55 of 64 Rev. 17 Figure 2 January 2020

Page 56 of 64 Rev. 17 Figure 3 January 2020

Page 57 of 64 Rev. 17 Figure 4 January 2020

Page 58 of 64 Rev. 17 VIII. Bases Liquid Effluent Release Flow Rate Determination Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected by the effluent monitor and, therefore, are not directly included in the release flow rate determination.

While tritium accounts for nearly all the activity released, it is not a significant contributor when determining the permissible flow rate. Examining releases over the years 2004

- 2006, the average diluted H-3 contribution to its limiting concentration in liquid effluents was 0.03%. This contribution is not expected to change significantly over time, since the concentration of H-3 in effluents can be expected to remain fairly consistent in effluent releases regardless of fuel conditions, activation product releases, and waste processing.

Based on relative abundances, other non-gamma emitting radionuclides only contributed up to nearly 3 % of the concentration limit. It is reasonable to assume that the abundances of these non-gamma will remain the same relative to other fission and/or activation products under varying conditions. Therefore, under conditions of elevated effluent radionuclide levels, the gamma-emitting radionuclides can be expected to be the main contributors to limiting conditions on liquid effluent concentrations. The maximum permissible release flow rate determination methodology presented in III.A offers an additional factor of conservatism of 30 to 50 which is more than adequate to account for the non-gamma emitting radionuclides.

Site Specific Data NOTE 1 Liquid dose factors, A i , for section III.B were developed using the following site specific data. The liquid pathways involved are drinking water and fish.

Ai = (U w Dw + U F x BFi )k 0 x DFi x RC x e 24 i Uw = liters per year; maximum age group usage of drinking water (Reg. Guide 1.109, Table E-5)

Dw = 5.4; average annual dilution at Conowingo intake UF = kg per year; maximum age group usage of fish (Reg. Guide 1.109, Table E-5)

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Page 59 of 64 Rev. 17 BFi = bioaccumulation factor for nuclide, i, in freshwater fish. Reg. Guide 1.109, Table A-1, except P-32 which uses a value of 3.0 x 103 pCi/kg per pCi/liter.

k0 = 1.14 x 105 = (106 pCi/µCi x 103 ml/1 )/ 8760 hr/yr) units conversion factor.

DFi = dose conversion factor for nuclide, i, for the age group in total body or organ, as applicable. Reg. Guide 1.109, Table E-11, except P-32 bone which uses a value as indicated below.

3.0 x 10-5 mrem/pCi RC = 1.16; reconcentration from PBAPS discharge back through PBAPS intake.

i = decay constant for nuclide i, hr-1 The data for D W and RC were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos. 50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data except P-32 BF and DF were used as given in Reg. Guide 1.109, Revision 1, October 1977. The P-32 BF and DF were used in accordance with information supplied in Branagan, E.F., Nichols, C.R., and Willis, C.A., "The Importance of P-32 in Nuclear Reactor Liquid Effluents",

NRC, 6/82. The teen and child dose factors were derived by the ratio of the adult bone dose factors in Reg.

Guide 1.109 and Branagan, et al.

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Page 60 of 64 Rev. 17 NOTE 2 To develop constant R for the ingestion pathway in section IV.C, the following site specific data were used:

R C

( ) F ( r ) ( DFL ) f f + (1 f f ) e QF U ap

( D / Q) = K ' p s p s i t h e i t f i

+ m i Y Y i W p s where:

K' = 106 pCi/µCi; unit conversion factor QF = 50 kg/day; cow's consumption rate U ap = 330 1/yr; yearly milk consumption by an infant i = radioactive decay constant for nuclide of interest, sec-1 (e.g. 9.97 x 10-7 sec-1 for I-131)

W = 5.73 x 10-7 sec-1; decay constant for removal of activity in leaf and plant surfaces Fm = stable element transfer coefficient for nuclide of interest, day/liter (e.g. 6.0 x 10-3 day/liter for I-131) r = fraction of deposited nuclide retained in cow's feed grass, 1.0 for radioiodine; 0.2 for particulates DFLi = ingestion dose factor in infant for nuclide of interest, mrem/pCi (e.g. 1.39 x 10-2 mrem/pCi for I-131) fp = 0.6; the fraction of the year the cow is on pasture (average of all farms) fs = 0.487; the fraction of cow feed that is pasture grass while the cow is on pasture (average of all farms)

Yp = 0.7 kg/m2; the agricultural productivity of pasture feed grass Ys = 2.0 kg/m2; the agricultural productivity of stored feed January 2020

Page 61 of 64 Rev. 17 tf = 1.73 x 105 sec (2 days); the transport time from pasture, to cow, to milk, to receptor th = 7.78 x 106 sec (90 days); the transport time from pasture, to harvest, to cow, to milk, to receptor NOTE 3 To develop constant R for tritium for the ingestion pathway in section IV.C, the following site specific data were used:

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. The following additional constants and formula are used:

RHC 3 ( Q )=K 'K '"Fm QF U ap (DFLi )[0.75(0.5 / H )]

where:

K '" = 103 gm/kg; a constant of unit conversion H = 14.61 gm/m3; absolute humidity of the atmosphere 0.75 = the fraction of total feed that is water 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water NOTE 4 To develop constant R for C-14 for the ingestion pathway in section IV.C, the following site specific data were used:

14 = K K ' " p Fm Q F U ap DFLC 14 [0.11 / 0.16]

RCMilk where:

p = the ratio of the total annual release time (for C-14 atmospheric releases) to the total annual time during photosynthesis occurs.

0.11 = the fraction of total plant mass that is natural carbon.

0.16 = the concentration of natural carbon in the atmosphere, in g/m3.

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Page 62 of 64 Rev. 17 The pathway is the grass-cow-milk ingestion pathway.

These data were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos.

50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data were used as given in Reg. Guide 1.109, Revision 1, October 1977.

ODCMS 4.8.B.2.1, Liquid Pathway Dose Calculations The equations for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided 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 and NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978.

ODCMS 4.8.C.1.1 and 4.8.C.1.2 Dose Rate Noble Gases The equations for calculating the dose rate due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided 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, NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

August 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. The specified equations provide for determining the dose rates in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.

The dose rate due to noble gas release as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method.

Assuming the release rates given in Radioactive Effluent Dose Assessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 6.0 times and 5.7 times, respectively, the values calculated by the Isotopic Analysis Method.

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Page 63 of 64 Rev. 17 Dose Rate I-131, I-133, Tritium and Radioactive Material in Particulate Form.

The model Technical Specification LCO of NUREG-0133 for all radionuclides and radioactive materials in particulate form and radionuclides other than noble gases requires that the instantaneous dose rate be less than the equivalent of 1500 mrem per year.

The release data from 1994 to 1996 were evaluated and the critical organs were determined to be the child thyroid or teenager lung. The child thyroid dose rate is limiting when iodine releases exceed 10 percent of the total release rates. The teenager lung dose rate is limiting when iodine is either not present or a small fraction of the total release.

Because of good fuel performance the amount of I-131 released has decreased. The thyroid may not be the critical organ. When it is not clear which organ dose is limiting, doses for the child thyroid and teenage lung are calculated.

ODCMS 4.8.C.2.1 Dose Noble Gases The equations for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided 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, NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

August 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. The specified equations provide for determining the air doses in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.

January 2020

Page 64 of 64 Rev. 17 The dose due to noble gas releases as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method.

Assuming the releases rates given in Radioactive Effluent Dose Assessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 4.3 times and 7.2 times, respectively, the values calculated by the Isotopic Analysis Method.

ODCMS 4.8.C.3.1 Dose, Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form The equation for calculating the doses due to the actual release of radioiodines, radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days were developed using the methodology provided 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, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to Letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. These equations provide for determining the actual doses based upon the historical average atmospheric conditions.

Compliance with the 10 CFR 50 limits for radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than eight days is to be determined by calculating the infant thyroid, infant liver and infant bone dose. These organs were determined to be the critical organs based on the release data from 1994 to 1996.

Because of a decrease in the amount of I-131 released, the thyroid may not be the critical organ. The isotopic analysis method is used to calculate dose to the infant thyroid, infant liver and infant bone.

January 2020

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