Text

Annual Radioactive Effluent Release Report 55, January 1, 2012 Through December 31, 2012
	ML13121A430
Person / Time
Site:	Peach Bottom
Issue date:	04/29/2013
From:	Pat Navin; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML13121A430 (166)
	v • d • e

AExelon Generation.

April 29, 2013 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

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

Facility Operating 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 55 January 1, 2012 through December 31, 2012 Enclosed is the Annual Radioactive Effluent Release Report 55, January 1, 2012, through December 31, 2012, for Peach Bottom Atomic Power Station Units 2 and 3.

This report is being submitted in compliance with 10CFR50.36a (2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of ODCM 3.10.2. Additionally, this report is submitted to satisfy annual effluent reporting requirements for the ISFSI required by the Offsite Dose Calculation Manual (ODCM).

There was one (1) revision made to the ODCM for the 2012 reporting period.

There are no commitments contained in this letter.

If you have any questions or require additional information, please do not hesitate to contact us.

Sincerely, Patrick Navin, Plant Manager Peach Bottom Atomic Power Station PDN/RJR/GRS/EAS/bcb Enclosures (2) cc:

USNRC Region I, Regional Administrator (William Dean)

USNRC Senior Resident Inspector, PBAPS (Sam Hansell)

USNRC Region I Inspector, Joe Furia CCN 13-39

Exelon Generation.

April 29, 2013 U.S. Nuclear Regulatory Commission Annual Radioactive Effluent Release Report 55 January 1, 2012 through December 31, 2012 bcc:

P. Steinhauer, PSEG [patricia.steinhauer@pseg.com]

Susan Grey, State of Maryland [SGray@dnr.state.md.us]

R. R. Janati, Commonwealth of Pennsylvania [rjanati@state.pa.us]

C. Mudrick, Kennett Square M. Massaro, PBAPS, SMB4 P. Navin, PBAPS, A4-1S T. Moore, PBAPS, SMB3-2A J. Bowers, PBAPS, PB-TC M. Jesse, Kennett Square J. Armstrong, PBAPS, SMB4 D. P. Helker, Kennett Square R. Salvador, PBAPS, SMB4-5 W. R. Nelle, PBAPS Records Management 2C. 111

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. 55 JANUARY 1, 2012 THROUGH DECEMBER 31, 2012 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC 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 Intro d uctio n....................................................................................................................................

5 : Supplemental Information.................................................................................

7 Regulatory Limits.....................................................................................................................

8 Maximum Permissible Release Rates..................................................................................

9 Average Energy......................................................................................................................

10 Measures and Approximations of Total Radioactivity......................................................

10 Batch Releases.......................................................................................................................

12 Average Stream Flow.........................................................................................................

12 Abnormal Releases................................................................................................................

13 Changes to the ODCM........................................................................................................

15 Minimum Detectable Concentrations...............................................................................

15 V io latio ns...............................................................................................................................

15 Dose Assessment...................................................................................................................

15 : Effluent Summary.............................................................................................

17 Gaseous Effluents - Summation of All Releases...............................................................

18 Gaseous Effluents for Elevated Release Point - Main Stack.............................................

19 Gaseous Effluents for Ground Level Release Point - Unit 2 and Unit 3 Roof Vents.......... 20 Liquid Effluents - Summation of All Releases....................................................................

21 Abnormal and Normal Liquid Radioactive Releases........................................................

22 : Solid W aste and Irradiated Fuel Shipments......................................................

23 Solid W aste Shipped Offsite for Burial or Disposal (Excluding irradiated fuel)................ 24 Estimate of major nuclide composition (by waste type).................................................

24 Spent resin, filters, sludges, evaporator bottoms, etc......................................................

24 Dry compressible waste, contaminated equipment, etc..................................................

25 Irradiated components, control rods, etc........................................................................

25 Other - Oil.............................................................................................................................

25 Irradiated Fuel Shipments (Disposition)...........................................................................

26 Changes to Process Control Program (PCP)......................................................................

26 : Radiological Impact on Man.............................................................................

27 Radiological Impact on Individual Members of the Public................................................

28 40 CFR 190 Dose Projection...............................................................................................

29 3

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Liquid and Gaseous Effluent Radiation Monitors and Instrumentation..........................

29 Attachm ent 5: M eteorological Data........................................................................................

30 Appendix A: ERRATA Data Section.............................................................................................

87 Recalculation of Noble Gas Doses from a Corrected Change to the ODCM.................... 88 Appendix B: O DCM Revision.....................................................................................................

89 Appendix C: Radioactive Waste Process Control Program Procedure.......................................

155 Technical Concurrence (for accuracy of information):

Chemistry, Enviomental and Radioactive Waste Manager I

I 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, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3 for the period January 1, 2012 through December 31, 2012. The notations "E+" and "E-" are used to denote positive and negative exponents to the base 10, respectively, such that "3,200" would be expressed as "3.20E+03".

The release of radioactive materials during the reporting period was within the Offsite Dose Calculation Manual Specification (ODCMS) limits.

There were four (4) unplanned releases of liquid radioactive material. Two releases were from Residual Heat Removal (RHR) heat exchangers, one was from the auxiliary boiler and the last is the groundwater tritium contamination ('tritium plume').

The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14) and particulates to any individual due to gaseous effluents was 5.45E-01 mrem, which was approximately 3.76E+00% of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 2.32E-01 mrad, which was 1.16E+00% of the annual limit.

There were no gaseous or liquid radioactive releases from the Independent Spent Fuel Storage Installation, NRC Docket No. 72-29 (ISFSI).

Errata data for corrected gamma and beta air doses calculated for ground-level releases in 2009, 2010 and 2011. These recalculations were the result of an unverifiable change to the Offsite Dose Calculation Manual (ODCM) in 2009 which was discovered in 2012.

The ODCM was revised during the 2012 reporting period. A copy of ODCM Revision 14 is provided in Appendix B. ODCM Specifications, as a separate document (Appendix A of the ODCM) was not revised in 2012 and is therefore not included in this report.

The Radioactive Waste Process Control Program (PCP) was revised in 2012. A summary of the changes is provided on page 26 and a copy of the procedure is submitted in Appendix B.

5

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. They are:

CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Program 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-170-3100, Offsite Dose Calculation Manual Revisions 6

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC : Supplemental Information 7

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Regulatory Limits Table 1. Noble Gas Dose Rate and Dose Limits Maximum Value Units Limit Classification Specification 500 mrem/ year total body dose rate limit ODCM Specification 3.8.C.1.a 3000 mrem/ year skin dose rate limit ODCM Specification 3.8.C.l.a 10 mrad gamma radiation air dose ODCM Specification in a calendar quarter 3.8.C.2.a 20 mrad beta radiation in air dose ODCM Specification in a calendar quarter 3.8.C.2.b 20 mrad gamma radiation in air ODCM Specification dose in a calendar year 3.8.C.2.c 40 mrad beta radiation in air dose ODCM Specification L

in a calendar year 3.8.C.2.d Table 2. lodines, Tritium and Particulates (with half-lives > 8 days) Dose Rate and Dose Limits Maximum Value Units Limit Classification Specification 1500 mrem/ year dose rate limit to any ODCM Specification organ 3.8.C.l.b 15 mrem dose limit to a member of ODCM Specification the public in any calendar 3.8.C.3.a quarter 30 mrem dose limit to a member of ODCM Specification the public in any calendar 3.8.C.3.b year 8

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Table 3. Liquid Effluent Activity Concentration and Dose Rate Limits Maximum Value Units Limit Classification Specification 10 times 10 CFR 20, tlCi/ mL activity concentration in ODCM Specification Appendix B, Table 2, all liquid releases at or 3.8.B.1.a Column 2 beyond the site boundary 3.0 mrem total body dose limit in ODCM Specification any calendar quarter 3.8.B.2.a 10 mrem dose limit to any organ in ODCM Specification any calendar quarter 3.8.B.2.a 6.0 mrem total body dose limit in ODCM Specification any calendar quarter 3.8.B.2.b 20 mrem dose limit to any organ in ODCM Specification any calendar year 3.8.B.2.b Table 4. 40 CFR 190 and 10 CFR 72.104 Annual Dose-Equivalent Limits to a Real Individual Located at or Beyond the Site Boundary from all Uranium Fuel-Cycle Sources within 8 km Maximum Value Units Limit Classification Specification 25 mrem total body dose 0DCM Specification 3.8.D.l.a 75 mrem thyroid dose ODCM Specification 3.8.D.l.b 25 mrem dose to any other critical ODCM Specification organ other than thyroid 3.8.D.l.c or total body 3.0 mrem dose from the liquid and ODCM Specification gaseous effluents for 3.8.D.1.d whole body and the critical organ 55 mrem thyroid dose from gaseous ODCM Specification effluent only 3.8.D.l.e Maximum Permissible Release Rates 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.l.b.

The Effluent Concentrations Limits (ECL) specified in 10 CFR 20, Appendix B, Table 2, Column 2 and 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 iaCi/ml (ODCMS 3.8.B.1.b).

9

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.

Measures and Approximations of Total Radioactivity Fission and Activation Gases The method used for Gamma Isotopic Analysis is the Canberra Genie 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 was analyzed to report noble gas effluent activities. When no activity was found in the grab isotopic analysis, the isotopic mixture was assumed to be that specified in ODCM IV.B.

The activity released is listed as "unidentified" in the 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.

lodines The method used is the Canberra Genie 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 Genie System with a particulate filter (47 mm). 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), strontium-90 (Sr-90) and gross alpha.

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 stack (9.7E+01%) with a 10

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC small amount (3.OE+00%) through the plant vents. The effluent in liquid effluents was determined to not be significant. The resulting annual dose to a child from gaseous releases was 5.49E-01 mrem to the bone.

Liquid Effluents Gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release using the Canberra Genie 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, phosphorus-32, strontium-89, strontium-90 and gross alpha.

About 209 gal of water containing a total of 3.09E-03 Ci of tritium was transferred from the decommissioned Peach Bottom Atomic Power Station Unit 1 to Units 2 & 3 Liquid Radioactive Waste system via the Laundry Drain tank for ultimate release. No other radioactive constituents were identified.

Therefore, any contaminated water is always processed through the normal radioactive waste processing system prior to release to the environment. The activity and the dose contributions from Unit 1 are counted in this Radioactive Effluent Release Report for the applicable reporting periods.

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.

11

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Batch Releases Table 5. Quarterly Liquid Batch Release Statistics First Quarter Second Quarter Third Quarter Fourth Quarter Number of Batch 17 1

20 2

Releases Total Time for Batch 1.71E+03 1.17E+02 4.69E+03 2.36E+03 Releases (minutes)

Maximum time period for batch 2.70E+02 1.17E+02 3.35E+02 1.76E+03 release (minutes)

Average time period for batch release 1.01E+02 1.17E+02 2.34E+02 1.18E+03 (minutes)

Minimum time period for batch 3.50E+01 1.17E+02 3.OOE+01 6.00E+02 release (minutes)

Average Stream 4.78E+04 3.48E+04 9.73E+03 3.25E+04 Flow' volume Dilution volume 4.92E+09 5.32E+08 1.70E+10 1.73E+09 (liters)

Table 6. Quarterly Gaseous Batch Release Statistics First Quarter Second Quarter Third Quarter Fourth Quarter Number of batch releases:

Total Time for batch N/A N/A N/A N/A releases (minutes)

Maximum time period for batch N/A N/A N/A N/A release (minutes):

Average time period for batch release N/A N/A N/A N/A (minutes)

Minimum time period for batch N/A N/A N/A N/A release (minutes)

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.

1 Average Stream Flow is not used for dose calculation.

12

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC The Circulation Water flow rate varies from as low as 675,000 gpm in the winter to as high as 1,350,000 gpm in the summer because the thermal cooling needs vary with the temperature of the intake water.

Abnormal Releases Abnormal Liquid Effluent Releases

1. 2A RHR to High Pressure Service Water (HPSW) leak On June 12, 2012, plant operators received indication of a small leak (approximately 1.79E-01 gpm) in the Unit 2 A Residual Heat Removal (RHR) Exchanger. Chemistry sampling confirmed the presence of a leak in the HPSW effluent to the discharge canal detected low-level radioactive contamination. The 2A RHR ceased to be a source of contamination as the leak was repaired sucessfully in September 2012.

Analysis of Release It was estimated that the contaminated water released to the discharge canal for all of 2012 was responsible for 1.71E-04 mrem total body dose (Adult), and 2.68E-04 mrem Critical Organ (Teen Liver) dose. This dose contribution was well below the limits specified in the ODCM.

Samples were analyzed for all the parameters of radioactive effluent releases. Composite liquid radwaste samples counted for tritium and submitted to an offsite vendor laboratory for analyses of Fe-55, P-32, Sr-89, Sr-90 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.

2. 2D RHR to High Pressure Service Water (HPSW) leak On September 5, 2012, sampling of the HPSW effluent to the discharge canal detected low-level radioactive contamination which indicated a small leak (8.50E-02 gpm). Subsequent investigation determined that primary coolant water was leaking through the Unit 2D RHR heat exchanger into the 2D loop of the HPSW system. The 2D RHR ceased to be a source of contamination as the leak was repaired successfully in September 2012.

13

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Analysis of Release It was estimated that the contaminated water released to the discharge canal for all of 2012 was responsible for 3.15E-05 mrem total body dose (Adult), and 4.95E-05 mrem Critical Organ (Teen Liver) dose. This dose contribution was well below the limits specified in the ODCM.

Samples were analyzed for all the parameters of radioactive effluent releases. Composite liquid radwaste samples counted for tritium and submitted to an offsite vendor laboratory for analyses of Fe-55, P-32, Sr-89, Sr-90 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.

3. Ground Water Tritium Plume During 2012, during the sampling and analysis of 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 be discharged into the intake or discharge canal.

Analysis of Release It was estimated that the ground water flowed to the discharge canal at a rate of 175 GPM.

With the concentration ranging from 8.46E-06 IVCi/ml to 2.31E-05 IiCi/ml, the ground water released to the discharge canal was responsible for 4.62E-05 mrem total body dose (Child), and 4.62E-05 mrem Critical Organ dose (Child Liver)2. This dose contribution projection is well below the limit specified in the ODCM.

4. Auxiliary Boiler Contamination In November 2012, a small amount of contamination was found in the B Auxiliary Boiler water during the course of routine sampling by the Licensee. This contamination was found using gamma spectroscopy and indicated the presence of power-production nuclides. A sample of this water was also sent off-site to a contract laboratory for radionuclides that are not detectable by gamma spectroscopy. The analyses indicated that the boiler water had a concentration of 3.57E-07 VICi/ mL Co-60, 4.21E-07 ICi/ mL Mn-54 and 2.36E-06 VICi/ mL.

Because this system is not a system which is designed for radioactive contamination, two blowdowns of the boiler were performed to reduce concentration of these nuclides to below detectable levels.

2 The numerical values for dose are identical because the ingestion dose factors for all organs (except bone) are identical for the child in the liquid pathway.

14

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Analysis of Release These blowdowns were abnormal releases to the Discharge Canal and were subject to further dilution prior to discharge to the unrestricted area beyond the site boundary. The maximum projected organ dose to the public as a result of this release was the Adult GI-LLI at 9.48E-04 mrem, which is 0.34% of the limit; the maximum projected Total Body dose to the limiting receptor (here, calculated to be "Child") was found to be 9.71E-05 mrem, which is 0.081% of the limit. These dose contribution projections are well below the limits specified in the ODCM.

Abnormal Gaseous Effluent Releases No abnormal gaseous effluent releases are reported for 2012.

Changes to the ODCM In November 2012, the ODCM was revised to fix an error found as a result of a preparation of a draft to the ODCM which had been in progress. It was found that the highest annual average noble gas reactor building vent dispersion factor (which is known by the symbol "(X/Q)v") was changed in 2008 but was not communicated to Emergency Preparedness (EP) such that an evaluation on the Site's Emergency Action Levels (EAL) could be performed. The latest validated meteorology data was utilized to determine this constant from the last ten years.

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) as specified in ODCMS Table 4.8.B.1, "Radioactive Liquid Waste Sampling and Analysis" (for liquids) or OCDMS Table 4.8.C.1, "Radioactive Gaseous Waste Sampling and Analysis from Main Stack and Vent Stack" (for gases). In all cases, the LLD requirements were satisfied.

Violations There were no violations for the 2012 reporting period.

Dose Assessment Liquid doses were calculated using the LADTAP function of NRCDOSE, version 2.3.9, for Windows. The average river flow for 2012 of 3.12E+04 cubic feet per second was used in the code. The maximum projected annual doses were 4.57E-06 mrem to the Adult Total Body and 6.51E-06 mrem to the Child Liver. These doses were less than the doses calculated in accordance with the ODCM.

Gaseous doses were calculated using the GASPAR function of NRCDOSE, version 2.3.9, for Windows. The average meteorology for 2012 was used to calculate the doses for noble gases, I-131, 1-133, tritium, C-14 and particulates. The projected doses were calculated for three 15

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC potential nearest MEMBER OF THE PUBLIC. The resident in the SSE sector at 1148 meters (3766 ft, 0.74 mi) was found to be the limiting MEMBER OF THE PUBLIC. The maximum annual doses were 1.59E-01 mrem to the child bone, 4.18E-02 mrad beta air dose, 2.17E-01 mrad gamma air dose.

These doses, using the NRCDOSE code, were less than the doses calculated in accordance with the ODCM, which shows that the ODCM methodology is more limiting.

16

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC : Effluent Summary 17

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents - Summation of All Releases P*_rina".I~nllzrv 1_ 20l12 thrniinh fecember 231 20t2 Unit: Peach Bottom Est. Total A. Fission & Activation Gases Units Quarter I Quarter 2 Quarter 3 Quarter 4 Error %

1. Total Release Ci 1.44E+02 1.15E+02 1.45E+02 1.15E+02 3.51E+01

2. Average release For the Period IJCi/s 1.85E+01 1.46E+01 1.83E+01 1.45E+01

3. Gamma Air Dose mrad 6.07E-02 4.74E-02 5.44E-02 4.25E-02

4. Beta Air Dose mrad 7.91E-02 6.19E-02 7.11E-02 5.56E-02

5. Percent of ODCM limit Gamma Air Dose 6.07E-01 4.74E-01 5.44E-01 4.25E-01 Beta Air Dose 3.96E-01 3.10E-01 3.56E-01 2.78E-01 B. lodines

1. Total 1-131 Ci 1.05E-04 2.OOE-04 2.07E-04 6.03E-05 1.76E+01

2. Average release For the Period PCi/ s 1.35E-05 2.54E-05 2.60E-05 7.59E-06

3. Percent of ODCM limit C. Particulate

1. Particulates with T1/2 > 8 days Ci 4.96E-05 1.97E-04 2.60E-04 1.02E-04 Z 1.94E+01 I

2. Average release For the Period pCi/ s 6.38E-06 2.50E-05 3.27E-05 1.29E-05

3. Percent of ODCM limit D. Tritium

1. Total Release Ci 1.43E+01 2.29E+01 1.33E+01 6.22E+00 1.11E+01I

2. Average release For the Period IpCi/ s 1.84E+00 2.91 E+00 1.67E+00 7.83E-01

3. Percent of ODCM limit E. Gross Alpha

1. Total Release Ci

<LLD

<LLD 4.0E+Oj02j

12. Averaae release For the Period I uCi/ s I

<LLD I

r3. Percent of ODCM limit F. Carbon-14

1. Total Release Ci 8.87E+00 I 8.87E+--00 8.87E+00 8.87E+00

2. Average release For the Period 1C s

1.14E+00 1.13E+00 1.12E+00 1.12E+00 G. Iodine-131,133 and 135, Tritium, Carbon-14 & Particulate

1. Organ Dose mremr 8.17E-02 I 8.17E-02 8.17E-02 8.17E-02

2. Percent ODCM limit 5.45E-01 5.45E-01 5.45E-01 5.45E-01

ODCM Limit is given as the combined total for all 1-131, 1-133, H-3, C-14 and Particulate in Section G.

18

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents for Elevated Release Point - Main Stack Period: January 1, 2012 through December 31, 2012 Nuclides Unit: Peach Bottom Released Continuous Mode Batch Mode

1. Fission Gases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Quarter I Quarter 2 Quarter 3 Quarter 4 Kr-85 Ci

<LLD

<LLD 1.68E+00

<LLD

<LLD Kr-85m Ci

<LLD 3.78E+00 8.40E+00

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD 5.40E+00 1.77E+01

<LLD

<LLD Xe-135 Ci

<LLD 6.39E-01 1.43E+00 5.55E+00

<LLD

<LLD Xe-135m Ci 1.93E+00 3.17E-01

<LLD

<LLD Xe-1i38 Ci

<LLD

<LLD Ar-41 Ci

<LLD

<LLD Unidentified Ci 1.669E+01 5.58E+00 1.42E+00 1.99E+01

<LLD

<LLD Total For Period Ci 1.86E+01 1.57E+01 3.06E+01 2.54E+01

<LLD

2. lodines 1-131 Ci 6.92E-05 6.41E-05 8.07E-05 3.98E-05

<LLD

<LLD 1-133 Ci 9.91 E-05 1.05E-04 2.08E-04 6.39E-05

<LLD

<LLD 1-135 Ci

<LLD

<LLD 3.46E-05

<LLD

<LLD Total For Period Ci 1.68E-04 1.69E-04 3.24E-04 1.04E-04

<LLD

3. Particulates ZIZZ Sr-89 Ci 3.54E-05 4.12E-05 5.55E-05 7.57E-05

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD 2.84E-07

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Ba-140 Ci 2.96E-06 1.07E-05 4.84E-06 2.91E-06

<LLD

<LLD La-140 Ci

<LLD

<LLD Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.25E-06 6.28E-06 2.29E-06

<LLD

<LLD Co-58 Ci

<LLD

<LLD 2.52E-06

<LLD

<LLD Co-60 Ci 3.75E-06 1.90E-05 5.09E-05 1.85E-05

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Ag-110m Ci

<LLD 3.23E-07

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Zn-65 Ci

<LLD 4.21E-06 1.48E-05 2.79E-06

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Total For Period Ci 4.21E-05 7.67E-05 1.35E-04 1.02E-04

<LLD

4. Tritium H-3 Ci 3.33E-01 6.12E-01 2.70E+00 1.99E+00

<LLD

5. Gross Alpha

,77:

77 2

Gross Alpha Ci

<LLD

6. Carbon-14 C-14 Ci 8.61E+00 8.61E+00 8.61E+00 8.61E+00

<LLD

<LLD 19

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Gaseous Effluents for Ground Level Release Point - Unit 2 and Unit 3 Roof Vents Period: January 1, 2012 through December 31, 2012 Nuclides Unit: Peach Bottom Released Continuous Mode Batch Mode

1. Fission Gases Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Quarter I Quarter 2 Quarter 3 Quarter 4 Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Ar-41 Ci

<LLD

<LLD Unidentified Ci 1.26E+02 9.92E+01 1.15E+02 8.96E+01

<LLD

<LLD Total For Period Ci 1.26E+02 9.92E+01 1.15E+02 8.96E+01

<LLD

2. lodines jT T

1-131 Ci 3.55E-05 1.36E-04 1.26E-04 2.06E-05

<LLD

<LLD 1-133 Ci

<LLD 4.50E-04 2.15E-04 8.16E-05

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total For Period Ci 3.55E-05 5.86E-04 3.41 E-04 1.02E-04

<LLD

3. Particulates Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-034 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci 7.56E-06 1.20E-04 1.25E-04

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Total For Period Ci 7.56E-06 1.20E-04 1.25E-04

<LLD

4. Tritium___________

H-3 Ci 1.40E+01 2.23E+01 1.06E+01 4.23E+00

<LLD

5. Gross Alpha Gross Alpha Ci

<LLD

6. Carbon-14 C-14 Ci 2.66E-01 2.66E-01 2.66E-01 2.66E-01

<LLD

<LLD 20

Peach Bottom Atomic Power Station Unit 2 and 3 Liquid Effluents - Summation of All Release PorinjI'.I~nI:zarv 1 2f119 to fletrh*_r :31 2fl12 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Unit: P~ach Bottom Est. Total A. Fission & Activation Gases Units Quarter I Quarter 2 Quarter 3 Quarter 4 Error %

1. Total Release (not including tritium, gases & alpha)

Ci 3.74E-06 4.29E-04 2.28E-03 2.81 E-03 2.11E+01

2. Average diluted concentration for the Period IpCi/mL 8.02E-15 6.46E-13 3.56E-12 4.36E-12

3. Percent of applicable limit Total Body Dose I 1.48E-03 1.03E-03 8.86E-03 1.09E-02 Organ Dose 5.30E-04 4.37E-04 3.79E-03 3.81 E-02 Est. Total B. Tritium Error %

1. Total Release Ci 2.45E+00 8.47E-01 5.41 E+00 9.28E-01 6.40E+00

2. Average diluted concentration for the Period pCi/ mL 5.26E-09 1.28E-09 8.45E-09 1.44E-09

3. Percent of applicable limit 5.26E-05 1.28E-05 8.45E-05 1.44E-05 (10x 10CFR20 Limit of 1.OOE-03 pCi/ mL; ODCMS 3.8.B.1.a)

Est. Total C. Dissolved & Entrained Gases Error %

1. Total Release Ci 2.42E-06 8.17E-04 5.97E-05

<LLD 2.11E+01

2. Average diluted concentration for the Period pCi/ mL 5.20E-15 1.23E-12 9.32E-14

<LLD

3. Percent of ODCM limit 2.60E-09 O.OOE+00 4.66E-08 O.OOE+00 Est. Total D. Gross Alpha Activity Error %

1. Total Release Ci

<LLD

<LLD 2.30E+01 E. Volume of Waste Released (prior to dilution)

Liters 8.70E+07 8.68E+07 8.91 E+07 9.06E+07 F. Volume of Dilution Water Used During Period Liters 4.66E+11 6.64E+11 6.40E+11 6.44E+11 21

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Abnormal and Normal Liquid Radioactive Releases Period: January 1, 2012 through December 13, 2012 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 Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD 1.75E-05 1.32E-04 3.87E-05 3.35E-06 5.58E-07

<LLD

<LLD 1-131 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD 3.52E-04 1.53E-03 4.46E-04

<LLD

<LLD 1.02E-04 1.OOE-03 Fe-59 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Mn-54 Ci

<LLD 5.96E-05 1.95E-04 5.69E-05 1.67E-07

<LLD

<LLD 1.18E-03 Cr-51 Ci

<LLD

<LLD 1.67E-05

<LLD Zr-95 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 2.21E-07

<LLD

<LLD Fe-55 Ci

<LLD

<LLD 2.95E-04 8.62E-05

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 6.84E-06

<LLD H-3 Ci 1.64E+00 8.47E-01 1.37E+00 9.21E-01 8.12E-01 3.86E-04 4.04E+00 6.63E-03 P-32 Ci

<LLD

<LLD Total for Period Ci 1.64E+00 8.47E-01 1.37E+00 9.21E-01 8.12E-01 3.87E-04 4.04E+00 8.81 E-03 Kr-87 Ci

<LLD 8.17E-04

<LLD

<LLD Xe-131m Ci

<LLD

<LLD 3.07E-05

<LLD Xe-133 Ci

<LLD

<LLD 1.86E-05

<LLD Xe-135 Ci

<LLD

<LLD 2.42E-06

<LLD 1.04E-05

<LLD Gross Alpha Ci

<LLD

<LLD 22

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC : Solid Waste and Irradiated Fuel Shipments 23

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Solid Waste Shipped Offsite for Burial or Disposal (Excluding irradiated fuel)

Estimate of major nuclide composition (by waste type)

Total Total Period Est. Total Quantity Activity (ci)

Error (%)

(mi)

1. Types of Waste

a. Spent resin, filters, sludges, evaporator bottoms, etc.

9.26E+01 2.05E+02 2012 2.5E+01

b. Dry compressible waste, contaminated equipment, etc.

2.67E+03 5.79E+00 2012 2.SE+01

c. Irradiated components, control rods, etc.

N/A N/A 2012 N/A

d. Other-oil 2.41E+01 2.17E-05 2012 2.5E+01 Snent resin, filters, sludg s. evanorator bottoms. etc.

S..

Class "A" Waste Class "A" Waste Major Major Nuclide Nuclide Composition Ci Percent Composition Ci Percent H-3 1.46E-02 7.11E-03 1-131 1.34E-27 6.53E-28 C-14 2.94E+00 1.43E+00 1-133 1.71E-88 8.34E-89 Na-22 8.35E-03 4.07E-03 Cs-134 5.11E-01 2.49E-01 Cr-51 2.87E-15 1.40E-15 Cs-137 1.97E+01 9.63E+00 Mn-54 5.52E+00 2.69E+00 Ba-140 1.11E-17 5.41E-18 Fe-55 3.69E+01 1.80E+01 La-140 8.52E-71 4.15E-71 Fe-59 1.15E-04 5.61E-05 Ce-141 3.76E-07 1.83E-07 Co-58 1.58E-01 7.70E-02 Ce-144 1.16E-01 5.66E-02 Co-60 1.24E+02 6.06E+01 Eu-152 1.19E-02 5.80E-03 Ni-63 3.29E+00 1.61E+00 Hf-175 5.94E-09 2.90E-09 Zn-65 1.04E+01 5.06E+00 Hf-181 2.61E-13 1.27E-13 Sr-89 1.46E-02 7.12E-03 Re-188 3.84E-88 1.87E-88 Sr-90 1.07E-01 5.22E-02 Au-199 9.18E-46 4.48E-46 Sr-92 1.43E-88 6.97E-89 TI-208 4.13E-88 2.01E-88 Zr-95 2.14E-02 1.04E-02 Pb-214 1.30E-88 6.34E-89 Nb-95 1.48E-14 7.22E-15 Ra-226 1.09E-02 5.31E-03 Nb-97 7.16E-88 3.49E-88 Pu-238 1.93E-03 9.41E-04 Mo-99 2.03E-62 9.90E-63 Pu-241 2.98E-01 1.46E-01 Tc-99 1.02E-01 4.97E-02 Am-241 1.06E-03 5.15E-04 Ag-110m 5.29E-01 2.58E-01 Cm-242 1.73E-04 8.45E-05 Sb-124 8.94E-03 4.36E-03 Cm-243 2.99E-03 1.46E-03 Te-123m 4.01E-04 1.95E-04 Total I 2.05E+02 I 1.OOE+02 24

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Dry compressible waste, contaminated equipment, etc.

Major Nuclide Composition Class "A" Waste Ci Percent C-14 3.1OE-02 5.35E-01 Cr-51 6.76E-02 1.17E+00 Mn-54 3.32E-01 5.73E+00 Fe-55 1.37E+00 2.36E+01 Co-58 1.86E-02 3.21E-01 Co-60 3.02E+00 5.22E+01 Ni-63 6.OOE-02 1.04E+00 Zn-65 5.81E-01 1.OOE+01 Sr-89 2.25E-03 3.88E-02 Sr-90 2.38E-03 4.11E-02 Y-90 5.OOE-04 8.63E-03 Tc-99 9.98E-04 1.72E-02 Ag-1 lorn 1.12E-02 1.94E-01 Cs-134 6.94E-03 1.20E-01 Cs-137 2.51E-01 4.33E+00 Ba-1 37m 2.07E-02 3.57E-01 Ce-141 2.61 E-03 4.51 E-02 Ce-144 1.06E-02 1.82E-01 Pu-238 1.82E-05 3.14E-04 Pu-241 2.89E-03 4.99E-02 Am-241 1.01E-05 1.74E-04 Cm-242 6.76E-06 1.17E-04 Cm-243 2.87E-05 4.95E-04 Total 5.79E+00 1.OOE+02 Irradiated components, control rods, etc.

No Irradiated components (e.g. control rod blades, etc.) shipped.

Other - Oil Class "A" Waste Major Nuclide Composition Ci Percent Co-60 1.23E-06 5.67E+00 Ni-63 1.22E-05 5.62E+01 Cs-137 1.12E-06 5.16E+00 Ce-144 7.14E-06 3.29E+01 Total 2.17E-05 1.OOE+02 25

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Irradiated Fuel Shipments (Disposition)

No shipment of irradiated fuel was made during the reporting period of 2012.

Changes to Process Control Program (PCP)

Submitted with this report is Revision 8 of RW-AA-100 (Appendix C), Process Control Program for Radioactive Wastes. All changes made to the document are denoted by "Revision Bars" in the right hand margin. The following is a summary of the significant changes made in Revision 8:

Step 4.1.8 was added to allow an Exelon Nuclear plant to store waste from another Exelon Nuclear plant provided formal NRC approval is granted for the transfer of waste. The addition of this procedural step for the transfer and storage of radioactive waste at an Exelon Nuclear plant from another Exelon Nuclear plant to the Process Control Program ensures that if the storage of water from another site is implemented, that a formal NRC review and approval process for the storage of waste from another site will address the site specific effects on the UFSAR and regulatory bases.

Step 4.2.8 was modified to add "in the pool or loading the processed activated hardware into the Dry Cask storage system." to further clarify the storage of activated hardware. The additional wording has been added to clarify the storage of activated hardware are generic and remain consistent with the UFSAR description of the Spent fuel Pool and Dry Cask Storage Systems.

Step 4.4.4 was added to state that, "Shipments sent for offsite storage SHALL meet the storage site's waste acceptance criteria." The addition of this procedural step for the transfer and storage of radioactive waste at an Exelon Nuclear plant from another Exelon Nuclear plant to the Process Control Program ensures that if the storage of waste from another site is implemented, that a formal NRC review and approval process for the storage of waste from another site will address the site specific effects on the UFSAR and regulatory bases.

Numerous minor wording and editorial changes were made throughout the document to correct grammatical errors and to improve document readability.

26

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC : Radiological Impact on Man 27

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Radiological Impact on Individual Members of the Public The following table is a summary of gaseous and liquid radiation annual doses to MEMBERS OF THE PUBLIC as calculated by the ODCM. Direct Radiation as measured by dosimetry, as required by the ODCM, is also provided in Table 7.

Table 7. Radiological Impact on Man and 40 CFR 190 Compliance Summary Location

% of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters)

(toward)

Limit Limit Unit Noble Gas Gamma - Air 2.32E-01 All 1.10E+03 SSE 1.16E+00 2.OOE+01 mrad Dose Noble Gas Beta - Air 1.58E-01 All 1.10E+03 SSE 3.95E-01 4.OOE+01 mrad Dose Noble Gas Total Body 2.24E-01 All 1.10E+03 SSE 2.24E+00 1.00E+01 mrem (gamma)

Noble Gas Skin (Beta) 2.92E-01 All 1.10E+03 SSE 9.73E-01 3.OOE+01 mrem Gaseous

Iodine, Particulate, Bone 5.49E-01 Child 1.10E+03 SSE 1.83E+00 3.OOE+01 mrem Carbon-14 &

Tritium Gaseous

Iodine, Particulate, Thyroid 7.32E-02 Infant 1.10E+03 SSE 2.44E-01 3.OOE+01 mrem Carbon-14 &

Tritium Liquid Total Body 3.36E-04 Child 5.60E-03 6.OOE+00 mrem (gamma)

_Site Boundary Liquid GI-LLI 3.78E-03 Adult 1.89E-02 2.OOE+01 mrem Direct Total Body 1.55E+00 All 1.15E+03 JSSE 7.05E+00 2.20E+01 mrem Radiation II 40 CFR Part 190 Compliance Total Dose Total Body 1.77E+00 All 1.15E+03 SSE 7.10E+00 2.50E+01 mrem Total Dose Thyroid 1.62E+00 All 1.15E+03 SSE 2.16E+00 7.50E+01 mrem Total Dose Bone 2.10E+00 All 1.15E+03 SSE 8.40E+00 2.50E+01 mrem Total Dose Total Body 2.24E-01 All 1.15E+03 SSE 7.48E+00 3.OOE+00 mrem Total Dose Bone 5.49E-01 All 1.15E+03 SSE 1.83E+01 3.OOE+00 mrem Total Dose Thyroid 3.05E-01 All 1.15E+03 SSE 5.55E-01 5.50E+01 mrem 28

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC 40 CFR 190 Dose Projection The annual dose equivalent to a real individual who is located beyond the SITE BOUNDARY from all uranium fuel cycle sources within 8 kilometers were well below limits.

Liquid and Gaseous Effluent Radiation Monitors and Instrumentation No effluent radiation monitors and instrumentation were unavailable for periods beyond the requirements of the ODCM.

29

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC : Meteorological Data 30

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Extremely Unstable 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 0

0 1

3 0

0 0

0 11 4

10 9

7 2

0 0

0 1

1 0

0 0

0 4

0 5

5 0

0 0

2 1

0 0

0 1

0 0

0 11 5

13 9

11 2

7 6

1 0

0 0

0 1

1 0

Total 4

45 14 3

1 0

67 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stabili Hours of missing stability measurements in all sta ty class:

0 bility classes:

1 31

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Moderately Unstable 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

1-3 0

0 4

2 1

0 4-7 8-12 13-18 19-24

> 24 Total 4

6 0

1 7

3 2

0 0

1 2

3 ESE SE 1

SSE S

SSW SW WSW 0

0 0

21 0

0 0

1 6

3 2

0 1

0 2

0 0

0 27 0

0 0

0 W

0 2

0 0

0 1

0 0

4 4

1 5

1 4

3 0

0 0

4 6

4 3

8 4

5 4

7 8

1 6

1 7

6 0

WNW NW NNW Variable Total 8

26 49 15 0

101 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

1 32

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class - Slightly Unstable Winds Measured at 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE 1-3 1

1 5

1 2

1 0

4-7 8-12 13-18 19-24

> 24 Total SE SSE S

SSW SW WSW 0

0 0

0 W

WNW NW NNW Variable Total 1

7 6

2 19 16 2

16 3

0 0

0 3

0 8

0 22 0

14 0

37 0

24 0

0 0

0 11 24 68 30 0

141 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

1 33

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Neutral Winds Measured at 150Ft-33Ft Delta-T (F) 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW 9

30 11 11 30 26 11 38 20 17 37 2

12 0

0 0

0 6

3 21 11 5

31 11 1

30 19 0

50 0

41 0

37 0

58 0

54 0

20 0

35 0

53 0

52 0

20 0

18 0

42 0

127 0

122 0

127 0

1il 1

1 8

7 8

9 SW WSW 1

15 16 W

WNW NW NNW Variable Total 1

20 52 49 6

33 67 15 3

29 71 24 9

27 61 11 5

1 0

3 0

12 0

134 0

361 0

342 0

118 0

0 0

967 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

10 all stability classes:

1 34

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class - Slightly Stable Winds Measured at 150Ft-33Ft Delta-T (F) 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 1-3 8

15 4-7 8-12 13-18 19-24

> 24 Total 1

2 1

4 14 26 0

1 0

0 0

0 1

0 0

0 31 21 32 10 24 28 9

19 37 12 9

24 10 15 14 19 8

28 9

7 1

5 0

18 0

15 0

30 0

52 0

42 0

53 0

68 0

44 0

37 0

34 0

41 0

79 0

53 0

37 0

35 15 42 22 11 32 10 13 16 7

25 8

3 0

79 1

257 0

305 0

1 0

648 Hours of calm in this stability class:

0 stability class:

Hours of missing Hours of missing wind measurements in this 0

stability measurements in all stability classes:

1 35

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class - Moderately Stable Winds Measured at 150Ft-33Ft Delta-T (F) 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 5

2 8

10 17 4

7 4

4 6

5 17 21 9

12 9

0 5

2 8

10 17 6

7 6

6 8

5 27 29 12 14 10 0

Total 140 28 4

0 0

0 172 0

Hours of calm in this stability class:

2 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

1 36

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Extremely Stable 150Ft-33Ft Winds Measured at 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE 1-3 2

8 4

7 4

3 3

4-7 8-12 13-18 19-24

> 24 Total

.SE SSE S

SSW SW WSW W

WNW NW NNW Variable 2

0 0

4 8

8 6

4 3

1 0

10 0

0 0

0 6

4 4

1 Total 67 6

0 0

73 Hours of calm in Hours of missing Hours of missing this stability class:

2 wind measurements in this stability class:

0 stability measurements in all stability classes:

1 37

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

Stability Class - Extremely Unstable Winds Measured at 320 March 2012 316Ft-33Ft Delta-T (F)

Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 1-3 0

0 0

0 4-7 8-12 13-18 19-24

> 24 Total 0

19 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

1 38

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

Stability Class - Moderately Unstable Winds Measured at 320 March 2012 316Ft-33Ft Delta-T (F)

Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE 1-3 0

0 0

0 4-7 8-12 13-18 19-24

> 24 Total S

0 0

2 1

1 0

0 0

0 1

0 0

1 0

3 0

0 0

2 1

0 0

0 3

1 2

2 1

5 1

6 11 0

17 SSW SW WSW W

WNW 0

0 0

2 0

0 0

1 1

0 0

3 0

0 1

0 0

6 2

0 1

0 0

NW NNW Variable Total 7

13 16 4

41 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

I 39

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

Stability Class - Slightly Unstable Winds Measured at 320 March 2012 316Ft-33Ft Delta-T (F)

Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE 1-3 0

0 0

1 1

0 0

4-7 8-12 13-18 19-24

> 24 Total SE SSE S

SSW SW WSW W

0 0

2 1

1 0

3 1

0 0

0 1

0 0

0 1

5 0

0 2

7 4

7 6

1 0

1 1

2 6

0 0

0 2

2 4

2 3

2 9

2 5

4 0

0 0

0 3

2 0

13 1

10 WNW 2

1 2

2 6

0 0

0 0'

0 0

2 14 1

2 5

4 2

2 9

9 0

5 6

3 NW 0

14 7

17 NNW Variable Total 0

0 7

43 35 19 10 116 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

1 40

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Neutral 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Wind Speed (in mph) 1-3 4-7 8-12 13-18 19-24

> 24 Total 18 9

18 18 22 16 11 8

13 5

5 6

6 4

13 11 0

29 33 14 14 27 23 32 20 45 14 10 11 19 17 50 37 0

20 3

2 2

18 18 16 6

37 13 13 17 50 70 74 45 0

5 0

0 0

3 2

1 4

10 7

1 4

42 34 49 10 0

0 0

0 3

0 8

35 14 10 3

0 74 50 40 42 74 64 62 39 106 42 29 46 152 140 196 108 0

Total 37 183 395 404 172 73 1264 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 41

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Class -

Slightly Stable 316Ft-33Ft Delta-T Winds Measured at 320 Feet Stability Wind (F)

Wind Speed (in mph)

Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 9

11 1

8 4

0 5

4 0

10 2

0 9

3 1

8 8

2 18 23 4

18 24 12 16 38 26 6

9 21 5

10 17 8

18 7

1 11 25 4

7 14 4

23 15 5

11 4

0 0

1 0

0 0

0 4

5 2

3 9

4 4

0 0

0 24 13 9

16 16 20 48 54 87 43 35 36 47 30 46 20 0

Total 23 134 206 149 32 0

544 Hours of calm in this stability class:

Hours of missing wind measurements in this Hours of missing stability measurements in 0

stability class:

0 all stability classes:

1 42

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

Stability Class -

Moderately Stable Winds Measured at 320 March 2012 316Ft-33Ft Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE 1-3 2

1 0

1 1

0 1

4-7 8-12 13-18 19-24

> 24 Total SE SSE 2

S 1

3 1

0 3

4 3

2 3

9 3

1 4

7 1

1 2

0 0

1 1

0 2

4 3

0 7

0 0

0 1

0 2

6 2

7 3

1 0

0 0

5 3

1 4

7 7

6 6

SSW SW 4

2 1

WSW W

8 10 5

4 0

2 2

0 0

17 0

19 0

13 0

21 WNW NW NNW Variable Total 3

1 2

0 0

0 7

5 6

0 23 47 49 22 this stability class:

0 wind measurements in this stabil 0

144 Hours of calm in Hours of missing Hours of missing ity class:

0 stability measurements in all stability classes:

1 43

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: January -

March 2012 Stability Class -

Extremely Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW 1-3 0

0 0

0 1

0 0

0 4-7 8-12 13-18 19-24

> 24 Total 0

0 0

1 2

1 1

2 0

0 0

0 3

1 0

3 SW WSW W

WNW 0

0 1

1 0

0 0

0 1

0 0

2 12 5

0 2

3 3

0 2

2 6

0 0

0 16 7

8 3

3 3

0 NW NNW Variable Total 3

10 32 10 0

55 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

1 44

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Class - Extremely Unstable 150Ft-33Ft Stability Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph) 1-3 4-7 8-12 13-18 19-24

> 24 Total 2

8 6

12 7

2 0

0 0

22 8

7 3

19 12 15 2

0 0

1 1

0 0

0 6

0 24 16 13 15 26 18 22 7

3 0

4 2

0 0

2 6

0 Total 37 96 21 4

0 0

158 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:

8 45

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April - June 2012 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

NNE 4

10 NE ENE E

ESE SE SSE 6

6 8

7 3

0 0

5 0

0 2

6 4

6 2

0 0

4 0

1 0

0 0

1 1

6 6

2 5

0 0

0 1

3 8

S 0

0 0

1 0

0 0

1 0

10 0

14 0

12 0

5 0

12 0

0 0

6 8

9 SSW 0

0 0

0 8

2 6

5 SW WSW W

3 12 WNW NW NNW Variable Total 5

9 0

18 0

23 0

36 0

47 0

10 13 13 0

12 25 10 0

0 0

0 34 69 81 36 0

221 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

8 46

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June Class -

Slightly Unstable 15 2012 OFt-33Ft Delta-T (F)

Stability Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Winds Measured at 33 Feet 1-3 2

2 5

2 2

3 0

0 0

0 1

0 0

2 0

Wind Speed (in mph) 4-7 8-12 13-18 5

2 0

1 0

0 1

0 0

0 1

0 0

1 0

0 3

1 0

6 3

1 1

0 0

1 3

0 0

2 5

0 1

7 2

1 3

3 3

21 9

14 21 6

0 0

0 19-24 0

0 0

> 24 0

0 0

Total 9

3 6

2 3

4 4

10 1

4 0

7 11 7

33 43 0

Total 19 41 66 21 0

0 147 0

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

8 47

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Stability Class -

Ne Win Wind utral ds Me 150Ft-33Ft Delta-T (F) 33 Feet asured at Wind Speed (in mph) 4-7 8-12 13-18 19-24

> 24 Total Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 23 15 15 32 15 11 6

12 8

4 4

1 6

9 10 9

0 180 25 5

0 1

8 18 62 58 14 12 8

13 14 21 16 40 0

20 1

0 0

0 2

27 21 6

2 6

8 13 25 44 50 0

3 0

0 0

1 0

0 1

7 1

9 13 0

35 71 21 15 33 23 31 95 91 29 18 18 23 40 56 79 112 0

Total 315 225 0

0 755 Hours of calm in this stability class:

Hours of missing wind measurements in this 0

stability class:

0 stability classes:

Hours of missing stability measurements in all 8

48

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April - June 2012 Stability Class - Slightly Stable Winds Measured at 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

NNE NE ENE E

ESE SE 11 11 8

11 24 18 17 3

0 0

4 6

2 0

0 0

0 1

1 1

6 0

2 5

0 0

SSE S

SSW SW WSW W

WNW NW NNW Variable Total 19 15 30 29 15 30 17 20 15 18 14 24 0

24 0

11 0

24 0

22 0

24 0

35 0

60 0

51 0

37 0

35 0

43 0

84 0

57 0

47 0

40 23 48 13 11 34 12 9

25 13 14 21 0

256 0

288 5

0 61 0

0 0

605 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 2

stability class:

0 all stability classes:

8 49

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Stability Class -

Moderately Stable Winds Measured at 150Ft-33Ft Delta-T (F) 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 7

6 7

7 4

11 4

3 12 8

15 18 14 9

8 4

0 137 0

0 0

0 3

19 25 9

2 0

0 58 7

6 7

7 4

11 4

3 12 8

18 37 42 19 10 4

0 Total 4

0 0

0 199 Hours of calm in this stability class:

Hours of missing wind measurements in this Hours of missing stability measurements in 3

stability class:

0 all stability classes:

8 50

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Stability Class -

Extremely Stable Winds Measured at 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

1-3 1

1 1

2 1

4-7 8-12 13-18 19-24

> 24 Total ESE 2

SE 1

SSE 0

S 1

SSW 3

4 SW WSW W

WNW NW NNW Variable Total 21 26 9

4 1

2 0

3 0

0 0

0 47 0

12 0

0 0

0 4

1 2

0 54 32 0

86 Hours of calm in Hours of missing Hours of missing this stability class:

0 wind measurements in this stability class:

0 stability measurements in all stability classes:

8 51

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

Stability Class - Extremely Unstable Winds Measured at 320 June 2012 316Ft-33Ft Delta-T (F)

Feet Wind Speed (in mph)

Wind Direction N

NNE NE 1-3 0

2 0

4-7 8-12 13-18 19-24

> 24 Total 0

4 6

2 3

3 7

3 ENE 2

13 E

2 9

ESE SE SSE S

SSW SW WSW W

WNW 0

13 12 0

0 0

0 3

17 0

2 0

1 0

0 2

0 0

0 3

6 2

3 1

0 0

5 8

0 0

0 1

1 0

3 6

3 5

0 2

0 0

6 0

1 0

0 0

0 1

0 10 0

23 0

14 2

31 0

26 0

6 0

0 2

9 0

13 0

0 0

0 2

6 1

0 8

7 9

0 NW 1

NNW 0

0 Variable Total 7

53 75 28 2

2 167 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

8 52

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

Stability Class -

Moderately Unstable Winds Measured at 320 June 2012 316Ft-33Ft Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW 1-3 0

0 0

0 4-7 8-12 13-18 19-24

> 24 Total WSW W

WNW NW NNW Variable Total 0

0 0

3 2

2 4

3 8

6 0

5 7

1 0

0 13 2

15 0

21 0

19 2

10 0

0 0

33 38 30 17 3

121 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

8 53

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

Stability Class - Slightly Unstable Winds Measured at 320 June 2012 316Ft-33Ft Delta-T (F)

Feet Wind Speed (in mph)

Wind Direction N

NNE NE 1-3 2

0 1

0 0

0 4-7 8-12 13-18 19-24

> 24 Total ENE 5

4 7

3 1

3 2

3 1

1 4

7 8

5 E

ESE SE 1

0 0

2 1

3 1

3 0

2 3

6 1

1 0

0 0

1 0

0 0

0 5

8 1

13 0

14 0

0 0

10 8

9 4

7 SSE 0

0 9

S 1

2 14 0

20 SSW SW WSW W

0 1

0 0

1 0

0 0

2 4

1 2

4 3

0 0

0 2

5 7

WNW 3

10 0

14 2

25 0

47 0

41 NW 7

20 16 NNW 8

12 13 8

0 Variable Total 0

0 0

6 45 77 64 40 3

235 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

8 54

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Stability Class - Neutral 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 6

6 4

16 14 18 17 13 23 12 7

8 12 10 10 20 0

18 12 9

18 19 27 54 42 45 15 8

8 16 12 29 34 0

30 3

1 2

14 16 20 21 24 1

5 12 18 30 41 25 0

13 0

0 0

0 3

0 2

4 2

0 0

9 14 22 17 0

71 24 21 41 53 72 95 83 99 32 20 29 59 69 107 101 0

Total 53 196 366 263 86 12 976 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:

8 55

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Stability Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Peach Bottom Nuclear Station Period of Record: April -

June 2012 Class - Slightly Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph) 1-3 4-7 8-12 13-18 19-24

> 24 Total 4

5 1

4 4

3 11 14 8

12 8

8 11 9

12 3

0 1i 1

5 3

5 2

13 13 18 22 16 17 9

11 18 16 0

5 0

2 0

3 0

0 5

17 3

9 16 14 23 27 13 0

22 7

9 8

13 6

25 35 45 37 35 43 36 53 65 36 0

Total 18 117 180 137 22 1

475 0

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

8 56

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

Stability Class - Moderately Stable Winds Measured at 320 June 2012 316Ft-33Ft Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

1-3 3

1 2

0 0

4-7 8-12 13-18 19-24

> 24 Total 2

4 3

4 4

2 1

1 4

1 2

1 0

1 2

0 0

3 0

0 0

0 1

4 0

0 0

1 5

1 0

0 0

7 0

0 0

6 7

6 4

5 4

1 1

7 SSW SW WSW W

WNW NW 1

6 12 1

11 1

0 0

1 1

1 0

0 10 1

2 9

17 0

19 0

14 0

15 0

32 0

19 0

23 0

10 7

2 17 8

3 2

0 NNW Variable Total 5

0 2

0 0

0 11 52 68 35 0

173 Hours of calm in Hours of missing Hours of missing this stability class:

0 wind measurements in this stability class:

0 stability measurements in all stability classes:

8 57

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: April -

June 2012 Stability Class - Extremely Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

1-3 0

1 1

0 1

0 0

0 4-7 8-12 13-18 19-24

> 24 Total SSW SW WSW W

0 0

0 WNW NW NNW 1

Variable 0

4 Total 9

13 3

0 0

29 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

8 58

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class -

Extremely Unstable 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 6

7 10 5

3 2

0 0

0 3

0 16 4

5 2

2 6

11 10 1

0 2

1 1

0 0

4 0

8-12 13-18 19-24

> 24 0

0 0

0 5

0 0

0 3

0 0

0 1

0 0

0 Total 22 11 15 7

5 8

16 13 1

0 3

1 1

0 0

7 0

Total 36 65 9

0 0

0 110 0

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

151 59

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 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

NNE NE ENE E

ESE SE SSE S

SSW 1

10 3

9 6

2 0

0 0

0 11 0

9 0

11 0

11 10 1

2 2

1 0

0 0

0 3

2 6

9 0

15 SW 1

WSW W

0 0

0 5

8 6

9 8

WNW NW 0

13 0

29 NNW Variable Total 2

15 12 0

0 0

1 0

0 0

32 72 50 0

155 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

2 all stability classes:

151 60

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

Stability Class - Slightly Unstable Winds Measured at September 2012 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE 1-3 5

2 2

3 2

0 3

1 4-7 8-12 13-18 19-24

> 24 Total 0

0 0

0 7

2 2

3 3

0 7

9 SSE S

1 0

12 SSW SW 0

0 0

0 WSW 0

0 0

1 4

4 5

6 W

WNW 1

NW NNW Variable Total 2

10 4

0 16 10 0

0 0

2 0

0 0

16 0

26 0

0 0

22 59 24 0

107 Hours of calm in Hours of missing Hours of missing this stability class:

0 wind measurements in this stability class:

2 stability measurements in all stability classes:

151 61

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC Peach Bottom Nuclear Period of Record: July -

Stability Class - Neutral Winds Measured at Wind Speed Wind PSEG Nuclear, LLC Station September 2012

- 150Ft-33Ft Delta-T (F) 33 Feet (in mph)

Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 25 27 24 19 12 4

7 7

6 6

11 9

5 6

15 19 0

34 4

1 0

0 0

23 43 22 15 19 15 21 10 37 41 0

0 0

1 0

5 7

4 5

10 7

7 0

13 24 0

83 59 31 25 19 13 4

35 60 32 26 40 31 33 16 65 85 0

Total 202 285 4

0 0

574 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

3 Hours of missing stability measurements in all stability classes:

151 62

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class - Slightly Stable 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 20 16 14 4

12 7

11 11 22 24 28 27 22 26 20 22 1

7 0

1 0

1 1

18 71 37 17 30 35 35 58 29 15 0

1 0

0 0

2 6

2 1

2 2

1 3

7 8

0 28 16 15 4

13 8

31 91 63 42 60 64 58 87 56 45 1

Total 287 355 35 4

1 0

682 9

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

151 63

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC Peach Bottom Nuclear Period of Record: July -

Stability Class - Moderately Stable Winds Measured at Wind Speed Wind PSEG Nuclear, LLC Station September 2012

- 150Ft-33Ft Delta-T (F) 33 Feet (in mph)

Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 3

2 1

3 1

1 2

2 11 11 33 39 28 18 11 1

0 167 0

0 0

1 1

0 6

7 11 10 21 9

12 1

0 0

0 1

0 0

0 3

2 1

3 1

2 3

2 18 18 44 49 49 27 23 2

0 Total 79 1

0 0

0 247 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

5 Hours of missing stability measurements in all stability classes:

151 64

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

Stability Class - Extremely Stable Winds Measured at September 2012 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

1-3 0

0 0

1 1

4-7 8-12 13-18 19-24

> 24 Total 0

0 0

0 ESE SE SSE S

SSW 4

SW WSW W

WNW NW NNW Variable Total 23 18 40 33 13 20 3

3 0

0 1

0 0

0 1

0 0

1 0

0 0

42 0

73 0

33 0

0 0

0 4

3 0

0 88 72 0

161 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

151 65

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 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

NNE 0

0 0

0 5

2 5

9 NE 3

0 2

0 3

0 0

8 2

7 9

ENE E

0 11 ESE SE SSE S

SSW SW WSW 0

0 0

0 6

12 0

15 0

18 0

13 2

0 0

1 0

1 1

2 0

W WNW NW NNW Variable Total 0

45 38 10 0

94 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

83 66

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class - Moderately Unstable 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW 1-3 0

0 0

2 1

0 0

0 4-7 8-12 13-18 19-24

> 24 Total 0

0 0

0 7

4 6

5 0

10 0

0 0

6 5

2 8

7 5

2 W

WNW NW NNW Variable Total 0

0 0

0 2

0 6

1 0

2 0

4 0

6 0

0 0

0 1

0 0

1 0

0 0

0 1

7 4

0 0

10 3

35 35 15 0

89 Hours of calm in Hours of missing Hours of missing this stability class:

0 wind measurements in this stability class:

0 stability measurements in all stability classes:

83 67

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Class - Slightly Unstable 316Ft-33Ft Delta-T Winds Measured at 320 Feet Stability Wind (F)

Wind Speed (in mph)

Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 6

2 0

0 1

1 0

3 0

0 4

3 0

3 1

1 3

4 1

3 1

1 3

14 5

3 6

2 3

8 4

0 5

0 3

2 3

4 8

1 2

10 16 7

18 6

0 0

0 2

0 0

0 1

0 0

0 9

0 3

0 2

0 4

0 13 0

6 0

10 0

5 0

24 0

11 0

15 0

5 0

8 0

13 0

29 0

32 0

0 Total 13 50 83 40 3

0 189 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

3 Hours of missing stability measurements in all stability classes:

83 68

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class -

Neutral 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 2

3 9

10 12 3

4 3

3 0

5 1

2 3

4 4

0 11 5

12 12 21 9

18 17 6

13 13 15 12 11 21 27 0

8 11 12 19 28 15 19 28 44 24 21 13 21 7

48 32 0

350 3

0 0

2 12 6

6 17 20 4

12 4

8 3

21 15 0

28 19 33 43 73 33 48 69 79 42 51 33 44 24 101 81 0

Total 68 223 133 21 6

801 Hours of calm in this stability class:

Hours of missing wind measurements in this Hours of missing stability measurements in 0

stability class:

7 all stability classes:

83 69

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class - Slightly Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 18 9

10 13 5

6 24 13 4

6 12 8

10 11 8

9 0

11 7

1 0

2 4

16 22 20 20 22 16 11 19 22 18 0

211 4

0 0

2 3

17 34 13 16 19 3

9 36 8

0 34 24 14 16 11 16 51 57 62 40 53 50 26 44 75 39 0

Total 59 166 164 12 0

612 11 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

83 70

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class - Moderately Stable 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE 1-3 2

0 3

4-7 8-12 13-18 19-24

> 24 Total 4

1 2

ENE 4

13 E

ESE SE SSE S

SSW SW WSW W

WNW NW 1

2 2

3 1

8 6

2 0

0 0

0 1

3 7

7 2

3 2

8 3

14 4

10 4

10 5

10 0

0 0

2 0

4 4

6 3

1 6

5 0

0 0

1 0

0 0

0 1

0 17 0

12 0

0 4

3 0

0 0

11 0

22 0

25 0

21 0

19 0

13 0

17 0

32 0

27 3

5 3

4 5

2 0

0 7

4 3

5 19 9

13 NNW Variable 0

0 0

0 Total 44 104 73 31 0

253 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

83 71

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: July -

September 2012 Stability Class -

Extremely Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

1-3 1

1 5

1 1

0 4-7 8-12 13-18 19-24

> 24 Total ESE SE SSE S

SSW SW WSW 0

0 1

2 3

1 1

1 0

0 W

WNW NW NNW Variable Total 19 26 18 3

0 0

66 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

83 72

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Stability Class -

Extremely Unstable 150Ft-33Ft Winds Measured at 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total Total 9

12 2

0 0

0 23 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:

9 73

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Stability Class - Moderately Unstable 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 1-3 0

1 3

5 4

0 0

13 4-7 8-12 13-18 19-24

> 24 Total 0

26 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

9 74

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Period of Record: October Stability Class - Slightly Unstable Winds Measured at Wind Speed Wind Station December 2012 150Ft-33Ft 33 Feet (in mph)

Delta-T (F)

Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 0

2 0

0 0

0 1

1 1

0 0

2 0

1 1

0 0

8-12 13-18 19-24

> 24 1

0 0

0 1

0 0

0 1

0 0

0 3

0 0

0 1

0 0

0 1

0 0

0 1

0 0

0 2

0 0

0 2

2 0

0 0

0 Total 1

2 3

4 6

0 2

2 4

1 0

3 1

1 3

4 0

Total 13 9

13 2

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:

9 75

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Stability Wind Directior Peach Bottom Nuclear Period of Record: October Class -

Neutral Winds Measured at Wind Speed 1-3 4-7 8-12 Station December 2012 150Ft-33Ft Delta-T (F) 33 Feet (in mph) 13-18 19-24

> 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 13 16 27 38 38 10 1

1 3

0 0

2 0

0 4

2 0

155 32 40 7

8 5

18 15 15 13 9

3 17 9

18 24 29 0

262 13 10 1

0 0

1 4

8 5

3 2

11 20 37 63 69 0

247 0

0 0

2 0

1 2

0 0

0 19 33 35 16 0

108 58 66 35 46 43 31 21 25 23 12 5

30 48 89 131 116 0

0 779 150 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

9 76

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Stability Period of Record: October Class - Slightly Stable Winds Measured at December 2012 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW 35 26 24 16 45 12 38 5

38 10 37 15 24 19 16 20 22 24 5

7 0

0 1

6 4

1 1

9 0

1 0

0 0

2 0

3 0

0 0

66 0

48 0

57 0

43 0

49 0

52 0

44 0

42 0

50 0

22 0

20 0

41 0

57 0

67 0

66 0

84 12 11 9

8 12 20 W

WNW NW NNW Variable Total 16 29 12 16 43 8

19 36 11 17 58 0

0 382 350 7

0 73 0

0 0

808 Hours of calm in this stability class:

10 Hours of missing wind measurements in this stability class:

23 Hours of missing stability measurements in all stability classes:

9 77

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Stability Wind Directior N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Peach Bottom Nuclear Station Period of Record: October -

Decemb Class -

Moderately Stable 150 Winds Measured at 33 Feet Wind Speed (in mph) er 2012 Ft-33Ft Delta-T (F) 1-3 4-7 8-12 13-18 19-24

> 24 Total 7

6 7

4 16 14 6

6 1

4 7

16 24 33 17 16 0

0 0

0 1

2 1

1 1

3 10 16 7

2 1

0 45 7

6 7

4 16 15 8

7 2

5 10 27 40 40 19 17 0

Total 184 1

0 0

0 230 Hours of calm in this stability class:

7 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

9 78

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Stability Period of Record: October Class -

Extremely Stable Winds Measured at December 2012 150Ft-33Ft 33 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 1-3 1

2 2

2 4

4 2

1 3

2 4

12 4-7 8-12 13-18 19-24

> 24 Total 1

2 2

2 4

5 2

1 3

2 5

20 22 6

3 0

4 0

0 0

19 0

24 0

22 0

0 0

6 3

0 90 13 0

103 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 3

stability class:

0 all stability classes:

9 79

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Stability Class -

Extremely Unstable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 1-3 0

0 0

0 4-7 8-12 13-18 19-24

> 24 Total 0

0 0

0 1

0 2

0 0

1 0

2 1

0 0

7 0

20 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

122 80

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Class -

Moderately Unstable 316Ft-33Ft Winds Measured at 320 Feet Stability Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 0

0 0

1 1

0 0

0 8-12 13-18 19-24

> 24 0

0 0

0 2

0 0

0 1

0 0

0 1

0 0

1 0

0 0

0 2

2 0

0 0

0 Total 0

0 1

3 1

0 1

0 0

1 0

4 0

0 0

Total 0

2 6

3 0

0 11 0

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

Hours of missing stability measurements in all stability classes:

122 81

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Stability C

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable

?eriod of Record: October -

December 2012

'lass - Slightly Unstable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph) 1-3 0

0 0

1 0

0 0

4-7 8-12 13-18 19-24

> 24 Total Total 1

14 13 9

1 0

38 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

3 all stability classes:

122 82

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Stability Class -

Neutral 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Wind Speed (in mph) 1-3 4-7 8-12 13-18 19-24

> 24 Total 12 18 19 38 29 23 26 12 4

4 0

5 3

2 6

12 0

44 36 21 15 15 19 34 12 20 11 10 16 17 21 27 26 0

344 17 13 11 7

1 12 8

6 15 0

2 6

13 26 53 36 0

7 8

3 1

0 1

4 1

0 5

19 31 43 11 0

1 3

0 0

1 3

3 4

0 0

0 1

8 39 21 5

0 84 86 60 64 51 58 72 35 44 17 12 33 61 119 151 91 0

Total 31 213 226 135 89 1038 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

129 Hours of missing stability measurements in all stability classes:

122 83

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Class -

Slightly Stable 316Ft-33Ft Winds Measured at 320 Feet Stability Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24

> 24 Total 11 14 11 15 19 6

21 11 7

0 9

5 3

4 3

9 0

24 14 17 7

6 9

22 15 23 31 12 6

10 12 16 16 0

14 1

2 0

1 3

0 5

6 4

6 9

18 21 25 8

0 51 32 33 31 29 23 44 31 38 36 29 25 42 46 50 36 0

Total 37 148 240 123 22 6

576 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:

122 84

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Stability Period of Record: October -

December 2012 Class -

Moderately Stable 316Ft-33Ft Winds Measured at 320 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

1-3 0

2 0

0 0

4-7 8-12 13-18 19-24

> 24 Total 6

6 2

6 3

4 4

2 5

1 3

5 4

3 0

6 7

2 3

8 ESE SE SSE 0

1 2

0 0

1 3

1 2

S 1

1 0

0 0

0 10 0

12 0

9 0

6 SSW 0

13 6

9 3

SW WSW W

WNW 3

0 0

2 0

1 5

4 5

2 0

9 5

16 7

14 7

11 0

10 0

13 0

22 0

12 0

26 0

25 NW NNW Variable Total 3

4 0

0 0

8 8

0 12 63 80 37 0

192 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

122 85

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Peach Bottom Nuclear Station Period of Record: October -

December 2012 Stability Class - Extremely Stable 316Ft-33Ft Delta-T (F)

Winds Measured at 320 Feet Wind Speed (in mph)

Wind Direction N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

1-3 1

0 0

4-7 8-12 13-18 19-24

> 24 Total 0

13 0

4 WNW NW 2

1 0

0 6

2 4

0 3

0 2

0 NNW Variable Total 3

1 0

0 5

0 0

0 14 4

6 0

4 35 26 0

70 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 2

stability class:

0 all stability classes:

122 86

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Appendix A: ERRATA Data Section 87

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Recalculation of Noble Gas Doses from a Corrected Change to the ODCM In 2009, Peach Bottom Atomic Power Station had approved and implemented a change to the Offsite Dose Calculation Manual (ODCM) involving a key parameter which was derived from meteorological conditions. This value, the 'ground-level noble gas dispersion factor' with symbol (X/Q), was changed without proper documentation and review of the available data could not validate that X/Q value.

Therefore, the noble gas doses from 2009, 2010 and 2011 were recalculated with the best-available number which is a 10-year highest annual average of the dispersion factor for the period 2002 to 2011. Note that no attempt was made to 'reconstruct' existing meteorology data because the 10-year average included this period and it is extremely unlikely that that 2009 and 2010 would vary greatly from the 10-year average.

Because the Annual Effluent Report combines the doses from elevated releases and ground-level releases, the following tables will also combine these doses.

Table 8. 2009 Effluent Report Revision Previously-reported dose Revised dose Dose (mrad)

(mrad)

Percent change Gamma air 1.61E-01 3.34E-01 1.08E+02 Beta air 1.10E-01 2.30E-01 1.09E+02 Table 9. 2010 Effluent Report Revision Previously-reported dose Revised dose Dose (mrad)

(mrad)

Percent change Gamma air 1.76E-01 3.49E-01 9.85E+01 Beta air 1.20E-01 2.38E-01 9.78E+01 Table 10. 2011 Effluent Report Revision Previously-reported dose Revised dose Dose (mrad)

(mrad)

Precent change Gamma air 2.18E-01 2.65E-01 2.16E+01 Beta air 1.49E-01 1.82E-01 2.23E+01 The ground-level release mode is dominated by unidentified noble gases (-99%). Using the ODCM methodology, the doses for unidentified noble gases must use the most-limiting dose factor for that particular release mode. Therefore, as a result of unidentified noble gases alone, the dispersion factor changes are very pronounced and directly affect the dose rates calculated for both gamma air and beta air.

88

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Appendix B: ODCM Revision 89

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC paTc I Ot 65 Rev. 14, C'ttsire Dz~se Calculation Manual 14vi.~iCJII Id P~each uOttom At-,-mi.c Power trai~on 2init u 2 and 3 HINOV1 Docket Noa. 50-277 & 50-278 7QRC Approvald T rnp 1 ean.en t ed ;

PORC. Cba vman/ Patei ?QRC Plant. IN116ag(ar, 90

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 2 of 65 Rev. 14 Table of Contents IV.

III.

IV.

V.

VI.

Purpose, Instrument Setpoints Liquid Pathway Dose Calculations A.

Liquid Radwaste Release Flow Rate Determination B.

ODCM5 4.8.B.2.1 C.

ODCMS 4.8.B.4.1 Gaseous Pathway Dose Calculations A.

ODCMS 4.0.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 Nuclear Fuel Cycle Dose Assessment -. 40 CFR 190 and 10 CFR 72.104 A.

0115 4.8.D.1.1 and 4.8.D.I.2 Radiological Environmental Monitoring Program A.

ODCMS 4.8.E.1.1 and 4.8.E.1.2 VII.

Appendix A Bases Radioactive Effluents Control Program 91

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 3 of 65 Rev. 14 I.

Purpose The purpose of the Offsite Dose Calculation Manual is to establish methodologiesand 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 Nal well counter.

This NaI well counter activity is then converted to an equivalent liquid radwaste monitor reading.

CPS (R/W Monitor)

Where:

CPS (R/W Monitor)

Net CPM/mI (well)

Eff W/RW Background CPS

[Net CPM/ml (well) x Eff W/RW] +

Background CPS liquid radwaste gross activity monitor reading in CPS

=

gross gamma activity for the radwaste sample tank [determined by the well counter]

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

background reading of the liquid radwaste. gross activity monitor in CPS 92

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 4 of 65 Rev. 14 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 setpoinzts 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 2. Sketches of the Ventilation Treatment Systems for Units 2 and 3 are presented in Figures 3 and 4 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.

93

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 5 of 65 Rev.

14 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.l.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.Ci/ml total activity concentration for all noble gases as specified in ODCMS 3.B.B.l. This methodology is consistent with the additional guidance the 94

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Each tank of radioactive waste is sampled prior to release and is quantitatively analyzed for identifiable gamma emitters as specified in Table 4.B.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:

Dilution Factor jCi / mlt 1

10 x ECLL uCi / mli

=

the activity of each identified gamna emitter in pCi/ml ECLA The effluent concentration specified in i0 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases or 2 x 10-i pCi/ml for noble gases.

95

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 7 of 65 Rev. 14 Determine the Maximum Permissible Release Rate with this Dilution Factor by:

A x 2.0 x110 Release Rate f

) =

B x C x Dilution Factor A

=

The number of circulating water pumps running which will provide dilution 2.0 x 10 =

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.l.

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.

CK-i NRC URI 88-33-01, T00353.

D.=

[

At, C1,

]

where:

D

=

The cumulative dose commitment to the total body or any organ, r, from liquid effluents for the total time period A;, 2, in mrem.

I-I 96

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Alt Cit The length of the £th.time period over which C4 and F, are averaged for.the liquid release, in hours.

The.average concentration of radionuclide, i, in undiluted liquid effluent during time period At.

from any liquid release, (determined by the effluent sampling analysis program, ODCMS Table 4.8.B.l), in pCi/ml.

The site related ingestion dose. commitment factor to the total body or organ, x. for each radionuclide listed in Table..III.A.l, in mrem-ml per hr-pCi.

See Site Specific Data.'*

The near field average dilution factor for C~,

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.

F, 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 97

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ALT DOSE FACTOR (MREM-ML PER HR-pCi)

TOTAL BODY RADIO-NUCLIDE 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.OOE+03 1.08+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 ZN-65 3.87E+04 3.95E+04 4.16E+04 SR-89 8.83K+02 9.45E+02 1.48E+03 SR-90 1.8BE+05 1.56E+05 1.72E+05 Y-911 5.85E-13 6.14E-13 9.35E-14 Y-93 1.27E-03 1.34E-03 2.16E-03 NB-95 1.s2E+02 1.56E+02 1.68E+02:

NB-95N no data no data no data ZR-95 1.77E-01 1.72E-01 3.48E-01 ZR-97 1.56E-03 1.56E-0 3.43E-03 H0-99 2..91E+01 3.01E+01 5.53E+01 98

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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.

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At, DOSE FACTOR (MREM-ML PER HR-pCi)

LIVER RADIO-NUCLIDE H-3 NA-24 P-32 CR-51 MN-54 FE-55 FE-59 CO-57 CO-58 CO-60 ZN--65 SR-89 SR-90 Y-91M Y-93 NB-95 NB-95M ZR-95 ZR-97 M0-99 ADULT 2.13E+00 1.65E+02 9.55E+04 no data 5.15E+03 5.62E+02 2.96E+03 2.74E+01 1.16E+02 3.35E+02 8.55E+04 no data no data no data no data 2.83E+02 no data 2.61E-01

8. 43E-03

1. 53E+02 TEEN 1.53E+00 1.70E+02 1.04E+05 no data 5.06E+03

6. 01E+02 3.02E+03 2.81E+01 1.14E+02 3.32E+02 8.46E+04 no data no data no data no data 2.84E+02 no data 2.50E-01 3.39E-03

1. 58E+02 CHILD 2.70E+00

1. 98E+02

1. 01E+05 no data 4.03E+03 6.33E+02 2.73E+03 2.86E+01 1.04E+02 3.07E+02 6.69.+04 no data no data no data no data 2.35E+02 no data 3.91E-01

5. 82E-03 2.23E+02 100

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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.

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14 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)

A,, DOSE FACTOR (MREM-ML PER HR-iCi)

BONE RADIO-NUCLIDE H-3 NA-24 P-32 CR-51 MN-54 FE-55 FE-59 CO-57 CO-58 CO-60 ZN-65 SR-09 SR-90 Y-91H Y-93 NB-95 NB-9514 ZR-95 ZR-97 M10-99 ADULT no data 1.65E+02 2.38E+05 no data no data 8.12E+02

1. 26E+03 no data no data no data 2.69E+04 3.08E+0 4 7.67E+05

1. 51E-11 4.58E702 5.08E+02 no data 8.13E-01 1.69E-02 no data TEEN no data 1.70E+02 2.58E+05 no data no data 8.47E+02

1. 30E+03 no data no data no data 2.43E+04 3.30E+04 6.31E+05 1.61E-11 4.90E-02 5.12E+02 no data 7.94E-01 1.71E-02 no data CHILD no data

1. 98E+02 3.35E+05 no data no data

1. 19E+03 1.68E+03 no data no data no data 2.51K+04 5.19E+04 6.78E+05 2.57E-11 7.77E-02 6.04E+02 no data

1. 78K+00 4.03E-02 no data 102

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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.

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At, DOSE FACTOR (MREM-ML PER HR-pCi)

KIDNEY RADIO-NUCLIDE H-3 NA-24 P-32 CR-51 MN-S4 FE-55 FE-59 CO-57 CO-58 CO-60 ZN-65 SR-89 SR-90 Y-91M Y-93 NB-95 NB-95M ZR-95 ZR-97 MG-99 ADULT 2.13E+00

1. 65E+02 no data 3.28E-01 1.53E+03 no data no data no data no data no data 5.72E+04 no data no data no data no data 2.79E+02 no data 4.09E-01 5.14E-03 3.46E+02 TEEN

1. 53E+00 1.70E+02 no data 3.35E-O1 1.51E+03 no data no data no data no data no data 5.41E+04 no data no data no data no data 2.75E+02 no data 3.68E-01 5.14E-03 3.61E+02 CHILD 2.70E+00 1.98E+02 no data 2.57K-01 1.13E+03 no data no data no data no data no data 4.22E+04 no data no data no data no data 2.21E+02 no data 5.60E-01 8.35E-03 4.77E+02 104

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14 TC-99M 3.96E-02 3.031-02 4.33E-02 RU-103 3.17E+01 2.97E+01 3.91E+01 RU-105 5.68E+00 5.78E+00 7.66E+00 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-*I31M 5.55E+03 6.01E+03 5.22E+03 TE-132 1.43E+04 1.47E+04 1.271+04 SB-124 no data no data no data SB-125 no data no data no data 1-131 5.57E+02 5.73E+02 6.82E+02 1-133 1.12E+02 1.16E+02 1.41E+02 1-135 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 3.92E-09 4.10E-09 3.60E-09 BA-139 1.14E-08 1.18E-08 1.90E1-08 BA-140 2.38E-01 2.34E-01 3.62E-01 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.

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A DOSE FACTOR (IREM-ML PER HR-pCi)

GI-LLI RADIO-NUCLIDE H-3 NA-24 P-32 CR-51 MN-54 FE-55 FE-59 CO-57 CO-58 CO-60 ZN-65 SR-89 SR-90 Y-91i Y-93 NB-95 NB-95H ZR-95 ZR-97 MO-99 ADULT 2.13E+00 1.65E+02 1.73E+05 3.74E+02 1.58E+04 3.22E+02 9.90E+03 6.94E+02

2. 35E+03

6. 30E+03

5. 38E+04 4.94E+03 2.22E+04 4.44E-i1 1.45E+03 1.72E+O6 no data 8.27E+02 1.06E+03 3.54E+02 TEEN 1.53E+00 1.70E+02 1.41E+05 2.57E+02 1.04E+04 2.60E+02

7. 15E+03 5.24E+02 1.56E+03 4.33E+03 3.5BE+04 3.93E+03 1.77E+04 7.58E-10 1.50E+03 1.21E+06 no data 5.70E+02 9.19E+02

2. 82E+02 CHILD 2.70E+00 1.98E+02

5. 98E+04 8.9BE+01 3.38E+03 1.17E-+02

2. 84E+03 2.34E+02 6.04E+02 1.70E+03 1.18E+04 2.01E+03 9.13E+03 5.03E-08 1.18E+03 4.35E+05 no data 4.08E+02

8. 81E+02 1.85E+02 106

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14 TC-99M 1.54E+00 1.69E+00 1.69E+00 RU-l03 9.69E+02 7.041+02 4.01E+02 RU-105 2.69E+02 3.70E+02 5.69E+02 AG-lIOM 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 5B-124 4.53E+04 3.38E+04 1.35E+04 5B-125 5.93E+04 4.85E+04 2.13E+04 1-131 8.58E+01 6.57E+01 3.70E+01 1-133 5.82E+01 5.03E+01 3.40E+01 1-135 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 2.28E-14 2.52E-12 2.36E-09 BA-139 3.04E-05 1.58E-04 2.35E-03 BA-140 1.15E+03 8.69E+02 6.43E+02 LA-140 5.34E+03 4.25E+03 2.30E+03 LA-142 7.22E-04 3.08E-03 2.27k-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.

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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 ODCHS 4.B.C.I.I.

a.

Gross Release Method D_,

V[L.+K 7/-

JQ%

=~~~

[L.1B)+u] ~,+ [1,. +tuliJ~ih~

where:

The location is the site boundary, 1097m SSE from the vents.

This location results in the highest calculated dose to an individual from noble gas releases.

D,

=

total body dose rate, in mremf/yr.

D.

skin dose rate, in mrem/yr.

V 4.72 X 104 mrem/yr per pCi/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.

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

K 1.47 X j04 mrem/yr per pCi/m3 ; the total body dose factor due to gamma emissions for Kr-8S (Reg. Guide 1.109, Table B-I).

16N=2 W/) 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.

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

L=

2.37 a 103 mrem/yr per pCi/rm:. the skin dose factor due to beta emissions for Kr-BB.

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

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

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

/

=9.97 X l0-8 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-' mrad/yr per pCi/sec; the constant for Kr-S7 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 pCi/m3: the air dose factor due to gamma emissions for Kr-B8.

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

1

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

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14 LV.A.1. b.

Isotopic Analysis Method WI+

N where:

The location is the site boundary, 1097m SSE from the vents.

This location results in the highest calculated dose to an individual from noble gas releases.

D,.

= total body dose rate, in mrem/yr.

D.

= skin dose rate, in mrem/yr.

V.=

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.l, in mrem/yr per liCi/sec.

= The release rate of noble gas radionuclide, i,

in gaseous effluents from the stack determined by isotopic analysis averaged over one hour, in iCi/sec.

K, The total body dose factor due to gamma emissions for each identified noble gas radionuclide.

Values are listed on Table IV.A.l, in mremsyr per tiCi/mr.

16N=V12 (Fz/"O) 1.12 X 10-' sec/m3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.

= The release rate of noble gas radionuclide, i,

in gaseous effluents from all vent releases determined by isotopic analysis averaged over one hour, in pCi/sec.

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14 IV.A.l.b (Cont'd)

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

Values are listed on Table IV.A.l, in mrem/yr per pCi/mf.

(7Q) 9.97 X i0-8 sec/ms; the highest calculated annual average relative concentration. from the stack releases for any area at or beyond the SITE BOUNDARY.

B=

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.l, in mrad/yr per pCi/sec.

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

Values are listed on Table IV.A.l, in mrad/yr per pCi/rn.

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

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Constants for Isotopic Analysis Hethod (corrected for decay during.transit)

Plae-Air Total Body 3kin Gal Airz Beta Air plume-Body Dose Factor Do.. Fac.or Doss FaCtoz Dose Factor Dose rartar Doss Facoz B,

r.

L.

HNiV BdO~OL.d

(-.rd/y. per

(-~e/Y,=

Per

(--../Y-per i-rdlye Per

(-.rdlyý per (ees/Y.

per Kr-85m 4.02E-0S I. 17E+03

1. 46E+03 1.23E+03 1.97E+03 3.76E-05 Kr2-87 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 1.48EE03 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-130 1.52E-04 6.98E+03 3.26F+03 7.28E+03 3.75E+03 I. 46E-04.

The values Kt, Lý,

K., and NM are taken from Reg. Guide 1.109, Table B-1.

The values B, and V' were developed using the MARE program with plant specific inputs for PBAPS.

112

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 24 of 65 Rev. 14 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=IP, [w 3 '+w'A+wA'j where:

The location is the site boundary, 1097m SSE from the vents.

D

= dose rate to the critical organ most restrictive age groupi in mrem/yr.

P, 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 pCi/m3 W.

= 1.03 X IF sec/mr; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY from stack releases.

(SSE boundary)

= 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 MCi/sec.

W, 4.78 X 10" sec/r 3; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.

(SSE boundary) 113

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 25 of 65 Rev. 14 IV.A.2.

(Cont'd) 9V The release rate of radionuclide, i,in gaseous effluents from all vent releases, determined by the effluent sampling and analysis program (ODCMS Table 4.B.C.1) in iCi/sec.

q

=

The release rate of radionuclide, i, in gaseous effluents from the auxiliary boiler stack releases, determined by the oil sampling and analysis program (ODCM Specification Table

.4.8.C.1) in pCi/sec as calculated below:

C-v -

3785 x Z i

where:

The location is the site boundary, 1097m SSE from the vents.

CIF

= activity concentration measured in oil for nuclide, i, in jCi/ml.

3795

= milliliters per gallon.

Z

= gallons of oil consumed.

T

= number of seconds used for release Method (a) 60 second Method (b) number of seconds used to burn oil for release.

114

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Exelon Generation Company, LLC PSEG Nuclear, LLC Page 26 of 65 Rev. 14 TABLE IV.A.2 Pi CONSTANTS FOR CRITICAL ORGAN FOR THE MOST RESTRICTIVE AGE GROUP (mrem/yr per pCi/m3 )

H2-C-14 NA-24 P--:32 Cr-].

MR-54 FE-S5 M-56.

Co-se ME-59 CO-61)

NI-62 CU-64

I-65 ZN-6ES Z.N-fiB,

BR-BE4 ER-B5 BR-B6.

BR-B8 tQSE

['FA.rM 6-47E+02

5. a3+-3.

1.

6E+.04 no data 5.75E+01 no data no data no data no dat no data no data no data no data no data no data no data no data no data no dlata no data no data iINl*Arr.

uuM.

Wss FACTO 6.47E+02 5.312+03

1. 06E+04 no data 1.28E+04 1.00E+06 8.69E+04 1.25E+04 7.77E+05 1.02E+06 4.51E+06 2.09E+05 9.20E+03 0.12E+03 6 > 47E+05 1.47E+03 no data no data no data no data no data CnLD FACTOR I -..3,E+Da.

6.73E+03 1.61E+04 no data B.55+01 no data no data no data no data no data no data no data no data no data no. data no data no data no data no data no dat-a no data FACT.OR 1.27E÷03 4.87E+*0

2. 328E+04 no data 2.10E204 1.98E+06 1.24E+05 1.52E+04.

1.34E+Qf0

1. 53E+ 6 3.207E+05

-1.21+04 9.36E+03 1.24E+06 1.-58E03 no data no data no data no data.

no0 data 115

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Exelon Generation Company, LLC PSEG Nuclear, LLC Page 27 of 65 Rev.

14 BR-89 SR-.S9 SR-90 Y-90 SR-91 Y-gzM Y-91 SR-92 Y-92 Y-93 U*B-95 ZR-95 ZR-97 D--99 TC-g9M TC-101 RU-1O32 RU-105 RU-106 AG-.!IDH TE-125K TE-127M TE-127 TE-129M TE-129 120 1-12i TE-1i1M no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data i -62E+03

4. 57E+03 I.

5E+00 5.47E-'-02 6.75E-02

..60E+06

.-4BE+07

5. 92E+01 no data Z.Q3E+06 1.12E+07 2.69E+05 5.26E+04 2.79E+02 2.45E+06

2. 25E+04 2.45E+04 7.64E+04 4.79E+05

.. 75E+D6 1.i.1E+05 1..25E+05 8.1S E+02 S. 54E+02 5.52E+05 1.57E+04 i.16+E07 2.67E+06

4. -7E+05

1. 21E+2406 1.04E+40 1.68E+06 a.o0E+0a no data no data 1.99E+05 no data no data no dcata no data no data no data no data no dLat a no data no data no data no data no da1ta no data no data no data no data no data no data no data

1. 92E+0a 6.07R+02

1. 96E+00 6.22E+03 7.14E-02

1. 85E+06 I.62E+07 9.77E+01 no data 2-42E409 1 - 6524+07 2..932E+05

6. 0 "E+04 3.20E+03 2.94E+06

2. ?4E04 2.6E+-04 9 22E2+04 7.512E+05 2.69E+06

1. 30E+15 1.54E+05 i-I52+02

6. 672+02

'7 - 3E+05

1. 52E+04

1. 61E+(-07

6. 75_+0 G 5.23E+05

1. 662E+06 1.12E+04 1 98E+06 no data no data

2. 328E+05 116

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Exelon Generation Company, LLC PSEG Nuclear, LLC Page 28 of 65 Rev. 14 TE-1a1 1-132 1-122 CS-124 1-124 1-125 CS-1a CS-.aB BA-129 BA-140 LA-140 BA-141 CE-141 BA-142 LA-142 CE-143 ER-143 CE-I44 PR-144 ND-147 W-I7 NP-239,

.5BE-02 1-. 69E+05 2.79E+02 3.56E+06 no data 4A45E+04 6.96E+05O no data; no data no dat a no data no data no data no data no data no data no data no data no data no data no data no data no data.

no data

2. D6E+03 no data 2.40E+06 no data "7.97E+04 no data no data

1. IBE+04 7.12E+,04 6.54E+01 I. 95E+F0

.1. 60E+06 1.6 BE+05 2.97E+02 S. 17E+05 1.55E+03 S.22E+03 1.16E+05 4.23E+05

9. B4E+D6

1. 61E+03 2.- 2E+05 3.96E+04 5.95E+04 1-70E-02*

1. 94E+05 2-10E+02 2.85E+04

0. 00E+0O 5-07E+04 7.92E+05 no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data no data 2-24E+03 no data 4.4gE+05

0. OOE+OO I 4EE+U5 no data no data 1-.SE+04.

1.21E+405.

7.87E-+ai 2-02E+06 2.14E+05 a.29E+0a

1. 91E+0a l.U2E+QO4

1. O0E+05 4.83E-+5

1. 34E+07 1-75E-+02 3.72E+05 4.4E+04 6.49E+04 117

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 29 of 65 Rev. 14 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 4.6.C.1.1.

IV.B.1 for gamma radiation:

a.

Gross Release Method D,= 3.17 x10-'[M F//Q),ov+

Bi where:

The location is the SITE BOUNDARY 1097m SSE from the vents.

This location results in the highest calculated gamma air dose from noble gas releases.

D,

= gamma air dose, in mrad.

3.17 x 10'

= years per second.

M

= 1.52 x 104 mrad/yr per ILCi/m 3; the air dose factor due to gamma emissions for Kr-88.

(Reg. Guide 1.109, Table B-I) 15NOV1

Q,

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

0,

= The gross release of noble gas radionuclides in gaseous effluents from all vents, determined by gross activity vent monitors, in pCi.

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

118

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 30 of 65 Rev. 14 IV.B.1. a (Cont'd)

B

= 4.90 x. i0.0 mrad/year per vCi/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.

0,

=The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitor in gCi.

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

b.

Isotopic Analysis Method D,= 3J.7 x 10-0 Z [ (xlo\\, 6jv+ BnQ-s where:

The location is the SITE BOUNDARY, 1097m SSE from the vents.

This location results in the highest calculated gamma air dose from noble gas releases.

D,

= gamma air dose, in mrad.

3.17 x 10

= years per second..

MH 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 jCci/r.

I1O2

(/7)Qý 1.12 x 10-6 sec/rn: the highest calculated average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY..

= The release of noble gas radionuclides, i,

in gaseous effluents from all vents as determined by isotopic analysis, in gCi.

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

119

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 31 of 65 Rev. 14 B1=

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.l, in mrad/yr per pCi/sec.

IV.B.1. b.

(Cont'd)

A.

The release of noble gas radionuclides, i, in gaseous effluents from the stack determined by isotopic analysis, in pCi.

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

IV.B.2. for beta radiation:

a.

Gross Release Method D,= 3.17 x 10-6 N [(x/k 0 + Fx/o)ý a.]

where:

The location is the SITE BOUNDARY 1097m SSE from the vents.

This location results in the highest calculated gamma air dose from noble gas releases.

Dp

= beta air dose, in mrad.

317 x 104 = years per second.

N

= 1.03 x 10" mrad/yr per pCi/m3; the air dose factor due to beta emissions for Kr-87.

(Reg. Guide 1.109, Table B-1) 16NOV2 (y/O)

= 1.12 x 10-6 sec/mr; 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 pCi.

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

120

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 32 of 65 Rev. 14 xI,

=9.97 x 10l" sec/r 3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

Q3 The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitors, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.

IV.B.2. b.

Isotopic Analysis Method D.=3.17 n 10O' Z N, [tx/oh 6 1y + (,To).t 3.17 x 10"" = years per second.

N1

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

Values are listed on Table IV.A.l, in mrad/yr per pCi/mr.

iwu

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

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

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

Milo 9.97 x 0-8 sec/m3; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.

0,

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

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

121

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 33 of 65 Rev. 14 IV.C ODCMS 4.8.C.3.1 The dose to an individual frai 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.

D = 3I17x1Oj: F. R,[1Q%+ W" ow+ Wvqi]

where:

Location is the critical pathway dairy 1431m WSW from vents.

D

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

3.17 x 10

= years per second.

F.

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

= The dose factor for each identified radionuclide; i, in m2 (mrem/yr) per pCi/sec except tritium, which is in mrem/yr per pCi/m3. The dose factors are for the critical individual organ for the most restrictive age group, infant. Values are listed in Table IV.C.l 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.**

122

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 34 of 65 Rev. 14 IV.C (Continued)

-= 8.78 x 1-10 meters-2: (DQ) for the food pathway for stack releases except tritium which uses a (X/O) of 8.78 x 10-' sec/mr.

91,

= 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 pCi.

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

W,

= 1.58 x 10-' meters-2 ; (FDQ) for the food pathway for vent releases except tritium which uses a (X/)) of 1.58 x i10- sec/m?.

1 See Note 2 and 3 in Bases 91V 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 pCi.

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

qw The release of radionuclide, i, in gaseous effluents from the auxiliary boiler stack releases, determined by the oil sampling and analysis program (ODCHS Table 4.8.C.1) in VCi. Release shall be cumulative over the calendar quarter or year, as appropriate.

123

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Exelon Generation Company, LLC PSEG Nuclear, LLC Page 35 of 65 Rev.

14 TABLE IV.C.1 Ri CONSTANTS INGESTION PATIWA (m,7 (mremlyr) per pCi/sec)*

RatkMise hflflD Bas trtLive Wtant bat leerY Mrat Limg i1nn H-3 C-14 NA-24 P-32 CR-5rn FE-M NU-55 m-65 0t-a FE-69 coaN "43 I*R-fi OR-05 Bme BR-g0 OR-85I mies.-

SR-0 y-qg V-e NB-9g V-03 Y-u ZR-g7 TO-99 TC-g0M rC-101 MI-11]3 RU-105 RU-lot AG-1I1A eu3-r TE-124M 4A8E446 4.74E*1D no dlata 7.09E4t0 nod=

nodata 7.S2E,,W1 m daka 1.88E410 noda 1.03EAE0 2.WgE4 no d=ll rm3d re dab 4&,58E, ffl LSSE410 1.99E~a2 7.94E*M0 1-56E-19 72S4E.O4 1.36Et00 1.57E-iS tflE4O$

1.1ES0 1.iUE4S ro data (L04EH]0 7_44E-Cl 2_97E+03 2.35gE-t.s4E4W

!.871E*W 5.31 E*W1 521541 5.5E807 1143E+03 4*4BE+05 noat3~

9L24E-03 I-W+05 1.17E+]1%

1.154E-01 g22 no 01la no dala

&GDEC-45 nodama no dala Wda1a no Mbl wo dalm no dwaa

&15E+404

&40E-+02 2.0E-01 G.0E+G7 1.65w+(1 nodaal madaa 1.3*E80 7.81E+05

-S BE+05 1..90E+17 1.30*03 t7UE+W M*Odala 32M+04 mda nodala Wdia Idab no daba rMdalW rodaU noddal mal Ro dalb fbo diaa nosda rMdaUa nodaU no daua nodata no didal*

nodala no diaa no dlata flo ala rflada Mdaka no data 1AlIEd(5 65W 4

-1E+0FH7.

Iarias 2.79E+03 wdaWa 7.3,2-+03 no daba Wo data wo data mo daUa 2.31E4.04 no dama nodaba nodsa nn E-0a odal nodaa no d*al no d~aa no dlala rodab 9.7E*04 1.73E+02H 1.11-5M 8i.13E+{]3 1.13+tO5 1..q5-+05 nodala rosa roslal ros(aa 1.30[4*1 4,48E+06 no data 51E404 nodSa 22AE47 is d=

rio data wdaba wodatS no daka no dlata no dlaka rwdaka rosdaa rosdaa rodai re daba red=

nodata ro dat nodS rodak rodSb W it-Ct 3.32E461 rosin nG3EIO' nrMrtc-uj MWa watT SDI Baft

1.3E+03 MoGM 11E+03 4ASE4O on,

4At.05 D.4lES,*

noSa 11459 I

iMN.s

=roaa sl+a4 I

7.09E+06 o saa 43-&OrN 5.81EH)6 Wefau i2.2*Jr?

.IE-01 inol 125,E-2.51507 M dia 22W-+07 6.61E4.0 wl daba SAW+6H) 1.12E8*w rosa 1.11E.0 S.*.07 onMa 65,4E-G08

1. 1 1E+05 wo*ada 2ZfE+M 58!E00 WOn 52ffE-f 7.7lES09 nodaa 425E+09 4.5UE+]*

no(ata 4.14EN]3 ro d=

mWa 120E-Cl rnoa d=

dnab I4E23 wos =a M&r odS oala 1-.IlEi8 rdosa 3,31IE+09 5ASE-4d no a

307T-45 3.-3 ro a M

I79E-9.42E407 roAn3 1.31E4 DietS non i1 l7E.4D I

2.74E*05 Mtoa s5ir*og gAGE4.04 no daa 23TMN]Z 5.E-16 noa 5ASEL-2

.sas Mosda 737E1E2 1.4M+E01 nadd 5DW,--M 3.01E+W

,oda 4A3-cs 4.58503 so a 1.7VE-02 DM.507 nawa 472+04 3.19+505 onla 454E,02 1.30E.H0I nQdaft 9Z,3E--M t.0E-C idala 1.1tE'07 4.da503 woaSa ti14EM2 1 gE-67 Mrosa iz9-8&

3.61E40S M Ma 9_3qX02 9S3E-Gi so lt 74E-M 7.254E1 rosdaS 1.19EG4 7.09E+0G no daia oMEW107

1.Et0 noda Imr+ I i.8E+ta nofal 1-54*57 2.710 Mdab 7.8805 124

Peach Bottom Atomic Power Station Unit 2 and 3 TE-127M TE-127 TE-129M TE-129 1-130 1-131 TE-131M TE-131 1-132 TE-132 1-133 CS-IN

-134 1-135 Cs-135 CS-137 CS-Is M51-139 BA.-IS4 M.140 BA-MI.

CE-141.

BA-t42 LA-t42, CE-143 PRl-143 CE-I1 110147 W-187 NP-M3 NP-23 NP-=*

!.82ESW

&.03+07 LIBEin3 5.118+02 1.84,EW

,5.oi-+

7.9TE-10 trE7-I1 1.04EM15 22M+16 7.97E*08 998+0 878E41 3_7+05 I-WE-1

&T79,U ISLEO-7.4,E-01 6x17E4M6 15E+06 1.05E07 1.54M+07 1.B0E,1f 3.54I+10 4.8E-12, 9.8A-12 321E+04

.6,39+04.

51E408 1.71E81g

.'Etl1O 3.248E10

!2)8-2 42DE-23 126-E-07 82E-11 7.09E807 71M8+04 1.1BE,01 4,6E+00 IA1E-45 9j55E-19 IA2EM.

5.28+03 7.53E.-0 5.168-83 7A3E-I1

!.838-I1 1.16E4,0 7.708+04

&8*4-E.4 1.64E+02 1.14E8i5 4668E+05 1.70E-53 5.,0-54 2.58E-4 265E+12 1.79E84 12AE404 1.060EO1 9.51E-01 533E407 3.53E+06 1.ME814 2.15*,0 526E+07

7D-IdzC 7.08E407

&.7W-10 S3W058+

9.158-33 4.51E+06 2BE1+09 nogaas 2Z30-10

&.73E+06.

noda nasaa nodma no daa nMdala nosMa nodwal no data no dalb Rosa no d~a no data naoa rioas ndasa noasa nf~As 4.51E+13 4.61E+08 2.51E+05 2-73*+06 828-SI 131E+07 1118+407 1.108E-I 7-12E+D4 6ATIE40B 2.t:E-ZS 5.DOE'-11 7458E+04 nodata 56.0E-,0 2.68E+03 3.568--U 6,.098+0O1 1.80E+02 no daba I._90E+00 5A1E+07 5-5E0 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 36 of 65 Rev. 14 nodac 7.348+07 nodwa 2.20 q

T+0 nod=

3.588+04 atno 3.78E+

nroa 1.108+0 iMadc 2J48+07 no asa 6398-.08 incha 1.,17.-10 no da ta

4.

oEsW Maa 9.17E+05 no dsa 3.35E+07 w dn a 4.13E+08 n aa 6.=+i,6 Wn daa

&2..W.0 nasl 4.14E-31 nocd-2.88-33 noe data 68-61 ndaba 255-01 nraa 1.138+]07 nOdnc 2.85E+06 nasda 2.-61E80 nosIa 4152M+06 W.7"8.09 9.51E+07 nAsa 3,78+09 nodata 138-11 nI aa 3.518-12 nasga 2.31E+54 inch 2.338+04 1.39E8E 2.59E+07 noasa 61E,+08

3.

430 1101E+08 W

in da 2.3M8+0 3-27E-U 6.18E-2 nsda 14-2 5.O4E-11 7.58-46 inch 383E-0

&,.3;8+0 1.74E.4f7 Masa 3RW+08 nodaa 5ASE+04 nda 1.20E+00 5.87-49 1.72E-44 inIM 4A4E-47 nr data 4.49E8.

nwasa I12E.3 3.74E-a3 3172 nM caa 3.5M-81 no data 3.11E-D6 nwdaa 429E412 no ama 4.49E4) nw da a.r7a.*+0 no d 2.31E+06 nasa 2.171E+1 no daSa 6.55E+07 noaa 6ADE+04 nodaca 3107E-49 nama 8

.5W84 nodaLa 1.6W8.05 naa 1.38+01 incah 7.31E+0 nasa 4,288+C03 n daa tr7W+a noasa 537E-0 noDS 1data 405 no asa 2238+4 nodaSa 3A.n2E4 nW asa tm."+o

Tritium Rj values in units of mrem/yr per pCi/mn 125

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 37 of 65 Rev.

14 TABLE IV.C. 2 Ri CONSTANTS INHALATII (MreM/yr per PC nmue lirft saow mat Lhw bNOW wadlt KIQ&"

ralu WI'.

H-i' C-14 MK-74 P-32 CR-51 FE-55 OO-58 FE-,S CO-6O cu-"e Z*4 OR-,0 BR-,4 fl,,.0S OR-85 eR-M eR-W SR-,I SR-ID Y-m.

SR-91 V-9iN V-el SR-mi V-mi V-el NO-25 TR-95 RU-193 RU-1013 Mai-IS5 AG-1i1i TE-125M TE-127M TEA27 TE-129M TE-129 ejarn no wam 2.GSEO4M 1.05EMM4 no d~al 1.975404 w dEGA no data 1.3697*H no data 3.39E4MgI no dS 1.9*1E*M re dal4 no ala*

ro data ruin no data 3.2F544 3129E'-0]

9.55E401 125.07E*r l.g*E-01 5.8]E*2W

!.57E.*M 1.1E.,402 no daS 1.22E-0 a.68E404 9.95E403 4975E40 1.6TE-Cl 2.23E+0 1AIEH44 7.lE-C2

&47E+02 S.31E)03 t.IZEtU]4

!.12E+05 no am 253E.04 1.15E+04 1*EW+03 2.042+04 1.8RE40 tHE-C1 9A7E-C M dala no data 3.21E+02 nonda no data rnt)&

no MW fm *lal M* dala nonat no am

&.43E+03 Z752+04 1.65E+02 2552E433 5.23E415 nonl 7-22E(3 1-99E+03 4.43-+03 IqUM 6.47E]22

,.31e+03 1 JDE+G4 in1dat 5.75E+01 no naa nodab noda noada nodaS nodSl nodSl no daS3 nodab nodSb noda nodSi nonda no na noda nodaS no=

nonr no dSl nodS no ne no dda nonal no dSt I.52f+03 4XM7+03 547Z+03

&.75E-02 Krflr 6.47E+112 5.31E-+(3 1.962,+04 no dan 1.32E+01 nondl nodaS no dal 3.9BE+W nod*

3.2Z+D4 nD daba nonM run no S no dala nodala no dala nodaS no dala n *lala nodala nodala 4.72E+a3 3.11E+04 2-592+01 Si-12-43 42A4E+113 9.242+83 8.99201 1.976405 3.75E+D4 3.18E404 1.7501 ON PATHWAY Mlt LLF9 M-dn Gi-LL brit Brd fOSnT Ski Boil Lung GI-LL

-q T 50q 547EA,4 5.47E42, nodS 6A7E,02 5.31E,03 5.31E+03 nona 531r2+03 r.unMM 1.5E1.*4 nonoam 714.

n ¢lata 1.StE+z*4 i (la*

7.74E{]4 12.,04) 3.57E402 non as5.a i

taaE*0C 7.052*03 non 4.dab +03 5.69E404 1.10E+03 Mona 1.25*4 7.17E+"

no aM 221"-(1 7.T7+.5 1.1i+04 n Mdata 12E+03 1.,I.4, 2.4E.04 nondaa 9.A+03

&SIE4,5 3.19E+04 Moda:

1.16E+04 2.ozw45 Z42E.03 no da 1.16E+04.

9.302E0*

.s 0

no E1fam 7.74&-01 8.12E501 5.01*E04 no lam 12X-E.

B.472*45 5.14,44M no dam 3-112.E4 4A7E.0.

1.'*2E+04 M da 7-13E-03 run dab n dar Mno 38IE+02 noDS nvon non C99 I.UE nodSa rond nodan 2M4 01 no data 3.0,4203 no dam 8F4 nodata 3.39W4W2 nona 2.87Ea, non s.BEe+iI M

noa 2a nW I02 2.03E5 6.402*04 nM am 1.14Et64 1.12E407 1.31E*45 ndao 2.5tE.46 zMW92415 1.)4E.W nonm dam l

l01 5-2GE404 7.34204 no n 3.E I0 2.79E*4*

2.3,+03 m

1Aa I392E-22.4W*

7.132*04 runb 15+04.

2naEa4 141 m

.a(

oala 3.912-.. 1 2AM44M 1.27U 05 no daia 461C-01 764W40.

1.5-E72]

non 4M7-+00 47.9*5 127E+

no Wlam

.78E3 1.t75*40 2-17E+04 nona 2Ma 04a 1.10E2*5 1.410EW nodan 1.17E01 1.3,E*5 4.87204 no dama 323E+01

.11E&24 2.0z323 n dala

&7Z-2 5..r.L:4 8.44&E+0 no dab

.1-,04 5.52.*45 1.61E404 non i

6.79E02 1.571.

4.84204 no dam 4,.-rn

.152+07 1.64E+26 nonda 119.04

&67E2*0 3.50404 n1o (a SnZ+03 4472.41 I 29E40M nond~

615Z+02 1.31E4,*

2.T73.04 noa 207M.03 1.O4ET0*

2.442E4 no dam 4.9E-r1 1.6I8.05 6.9ME.0M n ama 223E03 3.0**Eu 2.6M5.04 no a E-]

126

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC I-130 t-131 TE-131M TE-131 1-132 TE-132 t-133 CS-134 1-134 1-135 CS-tM CS,-135 cs-ur CS-138 8k-ISO BA-139 LA-140 BA-to LA-12 CE-143 PR-143 CE-I" PR-14 MD-14" W-187 NP-239 U-=IG.

U-233 LI-M 1L-245 U-237 NP-234 NPL238 P0-20 AM-241 AM-243 AM-242 CM-Zn CM-ZI at-au 6.36eMg 3.79E40 1.74E-2

&.72E442 1.32E404

&.96E+0 4.8,,Eo4.

DII E4R

&5S.42E1 5.05E4W SASE44 SAEE.W MO5E-O=

2.07EW 3_95E-(]*

.93E*E tAOEO1 3.19F*M 7.94E40 1.30E*I 3.71E*4 3&50E*Mi 7.6ZE4.07 7.31 Ee.0 Tin1 Efl 7.O1E*'/

47M1 E4M2

&31EW*

3.74E40*

4.1DE.4.8 ILD.IBE089 4.AIE4.09 4.4,1E4W1 L.O*ES.Ii 1.39EM4 M4E+a4 3.54E+O ZSUEs0l 1-92E+43 7.60E+03 2.1iEtI]2 7fLIM405

&6W01-4 TMBEi04I 1.67E+04 3.77E-01 524E+0 1-21E+05 I9M-(2 8.131E143.

I312E+1*

M data no d=a~

no laE W

lau M data maaia 22W+E09

&24E+02 i2-,3lE Z73E+M In~d 1AE-+07 8-q3E+01 17.5E-02 1.69E+05 no=da no ema nodala raS-ad no ta mddia no *ala no d~k no dtala medift no d~aa

ma no eala r-daa r-mta no da3 mteddia n~o d~aa medaia.

medai fldaba no daba mean nomea

-oau no dala nto dla.

ng daba nodta n-daa nad~

IO ~a*

medaa Page 38 of 65 Rev. 14 153E.04 m

ala I.9E4, malo 3S*,,0S 5.11E.04 w idta lSEO3 mOM 1..-6+04 2.65E+O2 1.55E 1.19E415 m&ida 3.3501 3-99E-02 ZWU 2AMMi4U 5.lEO

&Mti SC-C 369!DE03 mn d I 1.GOEW mala 126E+03 Id*E*.03 3,El 4.41zE.o4 nomdaa

1.

mt, n2AEt+4 Wdi 2t1iEO Calu OSZI 1.IIEaOS 7.97EM4d 1.5,4.3 mCida 7iAM14.

2E-MO3 re data I.E+S mdala "5E5,2 td7E+03 ne da=

I.B3Ee03 mono 2-77E.03 554E-04 1.18EM4 1.43dE.,3 mdaa

&2Zi04.

1.7IE05 7.13Et0 1.31ES no ma=

4,5EC4 10AE+02 E.SE.O0 8.75E402 ma d

a. 3..+,t 5MZ-Cd 5.9M0 5.!-E04 no dama a4i0E-c 1.3E-1 1.ME40 3.-Etd m daa.

zoEt-)3 riodaI t1.E.IM 041,05 m aa

&.1EH]1 6.S0E, M 2.9ME40 4.75E+3 nodata 4.97E-03 5.25E+1E3 5.17E*4 2.16E+ te mda I 9.EO03 Itu-5 i.SIEtO3 5.93E4,2 m daba 196E-noam 8D2M50 5.-tMted nomdak 9t04E-02 SS4Et-U1 t1ttlE*

d.S97E+0 nfl3 221Et01 1.97E+03 4.3iW0 3.72E+"4 m daa 6S9E+42 5.I8E-0S 9AE I MEte no laa 1.7TE0 6.72E-03 1.6E, 0O 42aE4,03 nodaia 2AI4E--03 3.1.5EIH 3.22E+05 3.12Ei04 nodma 5,02 mod=a 3sata4 3.S5Ette m

a a

I.Eg]a 6.62E-01 5.95E 4 2.4SEe4U mda

! irt-at 3.35E+07 2tM4E19 B*.ItE04 ma Z..E+t0 IE407 4d..tEW 5.t6dEte mCia SOjas 1atE+07 eEMAS 5.53E404 m

iaa SlaEtt6 i.41E-t7 49,*0EM 7.035E+,O m

a 4.93E*05 1.44E+97 4.69ES8 5.19E4,04 fma 5B4EM36 1.13E+03 I

.EM.5 1.3E.04 mdla 121EM02 1.1E4 42a 4.9d5E*.

m+0 a nd&

4,Efr6 1,E59 4.M8lE0 7.1M+04 ma 1.76Ea00 2.D0tE-2 1195

3. 1Etd mda 5sE 01 6i50*S t-2DES 6.B5E,4M mdaa 1.T78E68 ss-MEt0a tH9E4W E5.EtI fma I1lMtOB 6.92E+GB

!.19E4M0 5.910E,04 M1 agl 1.8WB*,,Ga 1.61E0?7 1.07E I.WEt3 no a

J 4IEtS6 6585-48 1.14E40 5.88DE+84 mdia iiEtt8 7.A4+08 131E.0 D.75EtO4 mOM 21D7EtG8 1ti!E+09 5S.4OD 5.iEt4d Mdaa I1XtEB 1A.SE,40 5E3MS 7.D4E.,4 mi mt 1.780 2.+7 4.16E40tDE 7.1,4E4.84 ma 7-qihuta 5.47E+08 59lESB 7.a3E*t4 mda 14MEg8 dARES iL71EtS0 aE I

t M lad a 1245E*8 722E-OB SASES0 GWýW OWddt ma isurt-7.2E+05 519M0 6-tE404 mama i _qlW1ce 7.tE+D 5E4*AE BlSEAd m.ta tAine8 5n9W.08

&SI S

t2E.05 ma w

i Isa1-09 moaa I-VES0 lZBtuO mam IAditS 4.34Em.1,

.zcw*EaO

&4245 2-052*09 2S1E4WB 1.74E-M 4.48E50 lU4Et,.S 4.35DO0 2.70E+a 3561E.10D 223F.10 3.rEt, M daft 127

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 39 of 65 Rev.

14 TABLE IV.C.3 Ri CONSTANTS GROUND PLANE PATHWAY (mrem/yr per MCi/ma)

AG-110M AM-241 AM-242M AM-243 BA-139 BA-140 BA-141 BA-142 BR-83 BR-84 BR-85 C-14 CE-141 CE-143 CE-144 CF-252 C4-242 04-243 CM-244 CM-245 cM-246 CM-247 CM-248 C0-58 C0-60 CR-51 CS-134 CS-136 CS-137 CS-138 CU-64 FE-55 FE-59 H-3 1-130 1-131 1-132 1-133 1-134 1-135 LA-140 LA-142 MN-54 MN-56

3. 44E+0 9 6.85E+00 9.61E+07 5.03E+09 1.06E+05 2.05E+07

4. 1SE+04 4.4 9E+04 4.87E+03 2.03E+05 no data no data 1.37E+07 2.331E+06 6.96E+07 4.83E+10 6.85E+05 7.05E+09 7.84E+06 3.67E+09

3. 86E+06 8.51E+09 2.63E+10 3.79E+08 2.32E+10 4.66E+06 6.9 1E+-09 1.50E+08 1.30E+10 3.59E+05 6.07E+05 no data 2.72E+08 no data 5.51E+06 1.73E+07 1.23E+06 2.4 5E+0 6 4.46E+05 2.52E+06 1.92E+07 7.60E+05 1.3BE+09 9.04E+05 128

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC MO-99 NA-24' NB-95 ND-147 NI-63.

NI-65 N1P-237 NP-238 NP-239.

P-32 PR-143.

PR-144 PU-238 2U-239 PU-240 PU-241 PU3-242 PU-244 RB-86 RB-88 RB-89 RU-103 RU-105 RU-106 SB-124 SB-125 SR-89 SR-90 SR-91 SR-92 TC-10 1 TC-99M TE-125M TE-127 TE-127M TE-129 TE-129M TE-131 TE-131M TE-132 U-232 U-233 U-234 U-235 U-236 U-237 U-238 W-187 Y-90 Y-91 Page 40 of 65 Rev. 14 3.99E+06 1.19E+07 1.37E+08 8.40E+06 2.97E+05 5.42E+09 4.53E+06 1.71E+06 no data no data 1.83E+03 4.65E+06 3.06E+06 5.02E+06 1.14E+07 4.26E+06 3.46E+09 8.97E+06 3.31E+04 1.23E+05 1.08E+08 6.36E+05 4.22E+08 5.98E+0.8 2.38E+09 2.16E+04 no data 2.15E+06 7.77E+05 2.04E+04 1.84E+05 1.55E+06 2.98E+03 9.17E+04 2.62E+04 1.98E+07 2.92E+04 8.03E+06 4.23E+06 9.12E+06 8.90E+09 2.45E+06 1.24E+10 8.13E+04 5.16E+07 4.26E+08 2.36E+06 4.49E+03 1.07E+06 129

Peach Bottom Atomic Power Station Unit 2 and 3 Y-91M Y-92 Y-93 ZN-65 ZN-69 ZR-95 ZR-97 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page.41 of 65 Rev.

14 1.00E+05 1.80E+05 1.83E+05 7.46E+08 no data 2.45E+08 2.96E+06 130

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 42 of 65 Rev. 14 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.I

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 for the Whittaker Analyzers is 2%

Hydrogen, Balance Air.

IV.F ODCMS 4.8.C.7.1 and 4.8.C.7.2.

IV.F.1 The dose rate in areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the incineration of waste oil from the auxiliary boilers shall be calculated by the equation in IV.A.2.

The dose rate from radioactive particulate release shall be determined by either of two methods.

Method (a), total instantaneous release assumes that the total activity contained in the waste oil is released in the first minute of incineration.

Method (b) uses the activity release over the entire time of incineration.

For normal operations, it is assumed that Method (a) will be used, since the total activity from the waste oil is expected to contribute an insignificant dose compared to the annual limits.

However, in the event that the activity is significantly higher than administrative or regulatory limits, then Method (b) would be used because it is more accurate in calculating the dose rate.

131

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 43 of 65 Rev. 14 Since the auxiliary boiler stacks are at approximately the same height as the reactor vents and discharge from the auxiliary boilers will also be heated, the use of the reactor vent D/Q value for the. calculations is considered conservative.

IV.F.2 The dose to an individual from 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 from the incineration of contaminated waste oil from the auxiliary boiler stacks shall be calculated by the equation in IV.C.

V.A.

ODCMS 4.8.D.I.l and 4.8.D.1.2 V.A.l 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 TN-60 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.

Whole Body The whole body dose contribution from liquid and gaseous effluents shall be determined by the following method:

D.m = D, + D, where:

D,, = 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).

132

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page.44 of 65 Rev.

14 Critical organ(except thyroid)

The critical organ(except thyroid) dose contribution from.

liquid and gaseous effluents shall be determined by the following method:

D,, = D, + D,. + D where:

D, = 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).

DY

= 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 ODCH Section IV.C).

Thyroid The thyroid dose contribution from gaseous effluents shall be determined by the following method:

D., = D,. + D, + D where:

D1

= thyroid. dose from gaseous effluents, in trem.

D

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

D1.

= gamma air dose, in mrad (Determined by ODOM Section IV.B, with mrad equivalent to trem).

D

= limiting dose to the thyroid, in mrem (Determined by.

ODCM Section IV.C).

133

Peach Bottom Atomic Power Station Licensee:

Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 45 of 65 Rev.

14 V.A.2 ODC4S 4.8.D.I.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.l.l for whole body(D),,,

critical organ(Dc) and thyroid(D ) with the TLD measured dose(mtrem) minus the background dose.

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

D=., + Do where:

D,?

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

Dn

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

D,

= Dose from direct radiation, in mrem(after subtracting background).

Critical Organ(except thyroid)

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

Dnr = D. + DD where:

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

Dc

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

D,

= Dose from direct radiation, in mrem(after subtracting background).

134

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 46 of 65 Rev.. 14 Thyroid The cumulative thyroid dose from gas and direct radiation shall be determined by the following method:

DD"

=D, + D, where:

DT**

= thyroid dose equivalent from all sources, in mtero.

D,*

= thyroid dose from gaseous effluents, in mrem.

D

= Dose from direct radiation, in inrem(after subtracting background).

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.

VI.A ODCMS 4.B.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.l, VII.A.2, and VII.A.3, and shall be analyzed pursuant to the requirements of Table VII.A.l.

135

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 47 of 65 Rev. 14 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program 333)3)*)))3)))*)))) 33)3)3)*))))*))

3)3)3))))*) 3)3))*)))))) ). )33))))))3)33)33) 33))*))))))

Pathway Station Distance and DirectionCollection Method Analyses Code from PBAPS Vents and Discussion D)i)r)c)))

Ri)a)t)

))))i)o)

)3))

)) )))))))))

))))n))3)))3 )))))

3))))))

I.

Direct Radiation Site Boundary Intermediate Distance IL IA 2

11 iC IJ IF 40 INN 1H IG 1B IE 1K 15 22 44 32 45 14 17 31A 4K 23 27 48 3A 49 1,256 feet NE of site 1,396 feet SE of site 4,661 feet SE of site 2,851 feet SSE of site 4,513 feet SSE of site 3,755 feet S of site 2,701 feet SSW of site 7,050 feet SW of site 2,547 feet WSW of site 3,104 feet W of site 3,173 feet WNW of site 2,587 feet NW of site 3,136.. feet NNW of site 4604 feet SW of site 19,449 feet N of site 13,230 feet NNE of site 27,480 feet NE of site 15,213 feet ENE of site 18,524 feet ENE of site 10,397 feet E of site 21,966 feet ESE of site 24,105 feet SE of site 45,721 feet. SE of site 5,276 feet SSE of site 13,859 feet S of site 25,772 feet SSW of site 19,114 feet SW of site 20,673 feet WSW of site 1 set of four (4) TLDs from each location at least quarterly Gamma dose quarterly TLD sites were chosen in accordance with Peach Bottom ODCMS Table 4.8.E.1 Item 1.

Site Boundary stations all sectors except several along Conowingo Pond.

These sectors are monitored by stations on the east side of Conowingo Pond. The 5 mile vicinity stations cover all sectors.

The distant and special interest stations provide information in population centers and control locations.

Gamma Dose quarterly 136

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 48 of.65 Rev. 14 TABLE VII.A-l ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and DirectionCollection Method Analyses Code from PBAPS Vents and Discussion 50 25,677 feet W of site 51 20,511 feet WNW of site 26 22,093 feet NW of site 6B 30,538 feet NW of site 42 21,954. feet NNW of site Distant and Special Interest 43 5

16 24 2B 46 47 1a 19 C 26,931 feet NNE of site 24,482 feet E of site 67,788 feet E of site 58,048 feet ESE of site 3,768 feet SSE of site 23,483 feet SSE of site 22,153 feet S of site 51,413 feet W of site 106,354 feet WNW of site II.

Airborne Particulates IZ lB IC 3A 5H2 C 1,396 2,587 4,513 19,114 162,565 feet SE of site feet NW of site feet SSE of site feet SW of site feet NE of site Approximately 1 cfm continuous flow through glass fiber filter which is collected weekly.

These stations provide for coverage of the highest annual average ground level DJQ near the site Gross beta analysis on each weekly sample.

Gamma spectrometry shall be done when gross beta exceeds ten times the yearly mean of control station value.

Gross beta analysis done )24 hr after 137

Peach Bottom Atomic Power Station Unit 2 and 3 Licensee:

Exelon Generation Company, LLC PSEG Nuclear, LLC Page 49 of 65 Rev. 14 TABLE VII.A-l ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and DirectionCollection Method Analyses Code from PBAPS Vents and Discussion 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 lB IC 3A 512 C 1,396 feet SE of site 2,587 feet NW of site 4,513 feet SSE of site 19,114 feet SW of site 162,565 feet NE of site A TEDA impregnated flow-through cartridge is connected to air sampler and is collected weekly at site filter change.

Iodine 131 weekly III.

Waterborne Surface ILL C

1,256 feet NE of site 110 5,470 feet SE of site Sample collected from a continuous water sampler, monthly.

In event sampler is inoperable, grab samples will be collected each Gamma isotopic analysis monthly; H-3 on quarterly composite 138

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14 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and DirectionCollection Method Analyses Code from PBAPS Vents and Discussion calendar day until sampler returned to service.

Drinking 4L 45,721 feet SE of site 61 C

30,337 feet NW of site Sediment 4J 7,346 feet SE of site IV; Ingestion Sample collected.

from a continuous water sampler monthly.

In event sampler is inoperable,, weekly grab samples will be collected until sampler returned. to service; A sediment sample is taken down stream of discharge semi-annually.

Sample of fresh milk is collected from each farm biweekly when cows are on pasture (April through October), monthly at other times.

Two species of Gross beta and gamma isotopic monthly, H-3 on quarterly composite Gamma isotopic analysis each sample 1-131 analyses on each sample Gamma isotopic analysis or Cs-134, -137 by chemical separation quarterly Gamma isotopic analyses Milk Vc J

RU 32,736 feet 5,119 feet 4,694 feet 11,414 feet

" of site W of site WSW of site SSW of site Fish 4

7,162 feet SE of site 139

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C 57,347 feet NW of site recreationally on edible portions.

important fish (predator and bottom feeder) sampled in season or semiannually if not seasonal.

Food Two offsite locations of Products highest predicted annual average ground level D/Q and one location (15-30 km distance) in the least prevalent wind direction as determined using the results of the most recent annual Land use Survey.

C = Control Location Samples of three (3) different kinds of broad leaf vegetation monthly when available if milk sampling is not performed Gamma isotopic and 1-131 analysis 140

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Exelon Generation Company, LLC PSEG Nuclear, LLC Page 53 of 65 Rev. 14 FIAIVREV.A2 ENVIR3NIENTAL SAWUN STATIN AT INTEIMEDIATE DISTANCES FROM PACH BODT-OM SITE 142

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14 FIGURE VII.A.3 ENVIRONMENTAL SAMPLING STATIONS AT REMOTE DISTANCES FROM PEACH BOTTOM SITE 143

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flKn Ain PFCQFNFRIIW COP4PPNY MOILUNTSOm P8 PS L141 15 Z I. 3 FANS (31 OFFOAS RADWiASTE TREATMENT

11.

SSI EM Figure I 144

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14

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Figure 2 145

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Exelon Generation Company, LLC PSEG Nuclear, LLC Pane 57 of 65 Rev. 14 Pr""L 3L:""-"

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C.I. t':lr 8A'S IJti 3 IIA Y =MI -1 I k11m Figure 3 146

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14 VII.

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,,, for section III.B were developed using the following site specific data.

The liquid pathways involved are drinking water and fish.

4 =fUJ1D,+ Uz-FI)kWxDFxRCxiC2" U.

liters per year; maximum age group usage of drinking water (Reg. Guide 1.109, Table E-5)

.D.

5.4; average annual dilution at Conowingo intake U, =

kg per year; maximum age group usage of fish (Reg. Guide 1.109, Table E-5) 148

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14 BRF bioaccumulation factor for nuclide, i, in freshwater fish.

Reg. Guide 1.109, Table A-i, except P-32 which uses a value of 3.0 x 10, pCi/kg per pCi/liter.

k, 1.14 x 105 = (10 pCi/pCi x. 103 ml/l )/ 8760 hr/yr) units conversion factor.

DF, dose conversion factor for nuclide, i, for the age group in total body or organ, as applicable.

Reg. Guide 1.109, Table E-I1, except P-32 bone which uses a value as indicated below.

3.0 x l0-s mrem/pCi RC

=

1.16; reconcentration from PEAPS discharge back through PBAPS intake.

A, =

decay constant for nuclide i, hr-t The data for D 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.

149

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC Page 61 of 65 Rev. 14 NOTE 2 To develop constant R for the ingestion pathway in section IV.C, the following site specific data were used:

F.((r)D(DFr+ Q.(,

4 fF4

(-,

A f+A, Jr)

L.

where:

17

=

106 pCi/pCi; unit conversion factor Q,.

=

50 kg/day; cow's consumption rate UP 330 I/yr: yearly milk consumption by an infant At radioactive decay constant for nuclide of interest, secl" (e.g. 9.97 x 10-' sec-1 for 1-131)

Aw

=

5.73 x 10W" sec-"; decay constant for removal of activity in leaf and plant surfaces F.

=

stable element transfer coefficient for nuclide of interest, day/liter (e.g. 6.0 x 10-3 day/liter for 1-131) r

=

fraction of deposited nuclide retained in cow's feed grass, 1.0 for radioiodine; 0.2 for particulates DF, =

ingestion dose factor in infant for nuclide of interest, mrem/pCi (e.g. 1.39 x 10-2 mrem/pCi for 1-131) f 0.6; the fraction of the year the cow is on pasture (average of all farms)

S

=

0.487; the fraction of cow feed that is pasture grass while the cow is on pasture (average of all farms)

Y

=

0.7 kg/mr2; the agricultural productivity of pasture feed grass Y

=

2.0 kg/mr; the agricultural productivity of stored feed 150

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14 tf 1.73 x 10 sec (2 days); the transport time from pasture, to cow, to milk, to receptor 4,

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:

(xI Q)rr "

, u (DFL) [0.5(03 /O1 where:

K"

=

103 gm/kg; a constant of unit conversion H

=

14.61 gmi/m3; absolute humidity of the atmosphere 0.75

=

the fraction of total feed that is water 05

=

the ratio of the specific activity of the feed grass water to the atmospheric water 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 4.0.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 151

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14 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.

Dose Rate 1-131, 1-133, 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.

152

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14 Because of good fuel performance the amount of 1-131 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.

ODMS 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 19.77, NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

August 197B, 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.

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 153

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14 Nuclear Power Plants", October 1978, and the atmospheric dispersion model presented in Information Requested in 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 1-131 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.

154

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.i Revision 8 Page 1 of 9 Nuclear Level 3 -Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES 11 PURPOSE 1.1.

The purpose of the Process Control Program (PCP) is to:

1-1.1.

Establish the process and boundary concitions for the preparation of specific procedures for processing, sampling, analysis, packaging, storage, and shipment of solid radwaste in accordance with local, state, and federal requirements. (CM-1) 1-1-2.

Establish parameters which will provide reasonable assurance that all Low Level Radioactive Wastes (LLRWX processed by the in-plant waste process systems on-site OR by on-site vendor supplied waste processing systems, meet the acceptance criteria to a Licensed Burial Facility, as required by 1CFR Part 20.

10CFR Part 61, 10CFR Part 71, 49CFR Pads 171-172, "Technical Position on Waste Form (Revision v 111911 tow-Level Waste Licensing Branch Technical Position on Radioactive Waste Classiflcation" [5183], and the Station Technical Specifications, as applicable.

1-1.3.

Provide reasonable assurance that waste placed in 'on-site storage" meets the requirements as addressed within the Safety Analysis Reports for the low level radwaste storage faclrties for dry andlor processed wet waste.

2.

TERMS AND DEFINITIONS 2.1.

Proces Control Prooram IPCPI: The program which contains the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure the waste meets the stabilization criteria specified in 10CFR Parts 20,61 and 71, state regulations, and burial site requirements.

22.

Solidification: Liquid waste processed to either an unstable or stable form per 10CFR61 requirements-Waste solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a contaie meeting stability criteria (e-g.

High Integrdy Container).

2.3. Stabilization

Liquid waste processed to a 'stable state' per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stablizalion" criteria. This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria-In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabiization formulas, samples, tests, etc.

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Solidification Media: An approved media (e.g. Bamwell - vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives I is solidified in a container with activity greater than 1 micro curie/cc. Waste solidiftedI in a HIC is approved by the commission meeting the IOCFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stabler form and <c0.5% when waste is packaged to an "unstable form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stabiFlty criteria.

2.4.1-Solidification to an unstable or stable state is performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that demonstrates that the process is approved by the NRC or disposal facirdy.

2.5. Dewatering

The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable state, or

E1% by volume when the waste is packaged to a *stable form.

2.6.

High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges filter media, resin, sludges, etc), or dry active waste.

2.7. Encapsulation

The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilizatior media.

such as cement 2.8.

Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drais and Equipment Drain inputs).

2.9.

Incineration. RVR, and/or Glass Vibification of Liquid or Solid: Dry or wet waste processed via incineration and/or therial processing where the volume is reduced by thermal means meets I0CFR61 requirements.

2.10.

Compaction: When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.

2.11.

Waste Streams: Consist of but are not limited to Filter media (powdered, bead resin and fiber),

Filter cartridges, Pre-coat body feed material, Contaminated charcoal, 157

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High activity fitter cartridges, Concentrated liquids, Contaminated waste oil, Dried sewage or wastewater plant waste, Dry Active Waste (DAW): Waste such as ftiers, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.

Other radioactive waste generated from cleanup of inadvertent contamination.

3.

RFSPONSIBILITIS 3.1.

Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.

4.

MAIN BODY 4.1.

Process Control Proqram Requirements 4.1.1.

A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 121, and is approved by the Plant Operations Review Committee (PORC).

4.1.2.

Changes become effective upon acceptance per station requirements.

4.1.3.

A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/umstable state.

4.1.4.

When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:

1.

If the vendor has its own Quality Assurance (QA) Program, then the vendor shat ADHERE to its own QA Program and shall have SUBMITED its process system topical report to the NRC or agreement state.

2.

If the vendor does not HAVE its own Quality Assurance Program, then the vendor shal ADHERE to an approved Quality Assurance Topical Report standard beionging to the Station or to another approved vendor.

158

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The vendor processing system(s) is/are controlled per the foflowing:

1.

A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.

2.

Vendors that process liquid LLRW at the sites shall MEET applicable Quality Assurance Topical Report and Augmented Quality Requirements.

4.1.6.

Vendor processing system(s) operated at the site shagl be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.

4.1.7.

All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).

4.1.8.

An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been RECEIVED for the transfer of waste.

4.2-General Waste Processing Reguirements NOTE:

On-site resin processing involves tank mixing and settling, transfening to the station or vendor processing system via resin water sluny or vacuuming into approved waste containers, and, when applicable, dewatering for burial.

421.

Vendor resin beds may be USED for decontamination of plant systems, such as, SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut Down Cooling). These resins are then PROCESSED via the station or vendor processing system.

4.2.2-Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment Water from these tanks may be SENT through a filter, demineratizer, concentrator or vendor supplied processing systems.

42.3.

Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

424.

Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT to either the site waste processing systems or vendor waste processing systems for further filtration, denineralization for plant re-use, or discharge.

4.2.5.

All dewatering and solidificationlstabidzation will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.

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Dry Active Waste (DAW) wil be HANDLED and PROCESSED per the following:

1 DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.

2.

DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements.

3.

DAW iters may be SURVEYED for release onsite or oTtsite when applicable.

4.

Contaminated filter cartridges wiN be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offslte waste processor in drums, boxes or steel liners per the vendor site crteria for processing and disposal-42.7.

Filtering devices using pre-coat media may be USED for the removal of suspended solids fram liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or LinerIHIC. Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.-8 Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage in the pool or loading the processed activated hardware into the Dry Cask storage system.

4.2.9.

High Integrity Containers (HIC):

1.

For disposal at Bamwell, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.

2.

For disposal at Clive, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.

3.

Vendors supplying HIC's to the station shag PROVIDE a handling procedure which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Confonnance.

4.2.10.

Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting ICFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).

4.2.11.

Fomner in-plant systems GE or Stock D0mm Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byrn-160

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC RW-AA-100 Revision 8 Page 6 of 9 4.2.13 Certain waste. including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of a 10CFR20.2002 permit. Specific requirements associated with the I disposal shall be incorporated into station implementing procedures. (CM-2) 4.3.

Burial Site Reauirements 4.3.1.

Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR171-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.

4.4.

Shipvina and Inspection Reauirements 4.4.1.

All shippingistorage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.

4.4.2-Containers of solidifed liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, ofisite vendor acceptance, or station acceptance criteria, as applicable.

4.4.3.

Shipments sent to an off site processor shal be INSPECTED to ensure that the applicable processors waste acceptance criteria are being met.

4.4.4.

Shipments sent for off site storage shall MEET the storage site's waste acceptance criteria.

4.5.

Inspectin and Corrective Actin 4.5.1.

Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.

4.5.2-Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3.

If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidfication requirements are maintained.

4.6.

Procedure and Process Reviews 4.6.1.

The Exelon Nuclear Process Control Program and subsequent changes (other tha I

editonial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec),

Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),

as applicable, for the respective station and LS-AA-1 06. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.

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Exelon Generation Company, LLC PSEG Nuclear, LLC RW-AA-100 Revision 8 Page7 of 9 4.6.2.

Any changes to the PCP shag be reviewed to determine if reportablity is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMIlTED to the ODCM program owner prior to submittal of the ARERR.

4.6.3.

Station processes, applicable site-specific cask manual procedures, or other vendor waste processingloperating procedures shall be approved per RM-AA-102-1006.

Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).

1.

Site waste processing IS CONTROLLED by site operating procedures.

2.

Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.

4.7.

Waste Types Point of Generation-and Processina Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. I is not intended be all encompassing.

AVAILABLE WASTE WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstabestable stat Equipment Drain, Chemical and T

Processing Volume Control Systems, Floor Drain, Maximum Recycle, BkIwdown, Boric Free Release to a Land Fil Acid Recycling System, Vendor Supplied Processing Systems, and Portpbe Deini System Powdered Resin Systems - (Condensate System, Floor Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel unstable/stable state Pool)

Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain Them P

_____________Systems_____________

Sludge Sedimentalion resulting from vanous Dewateuing, solidification to an sumps, condensers, tanks, cooling unstable*stable state towor, emergency spray pond, holdinag TemlPaes pond, anid city waste-sepmarlorshra Poesn Evaporation on-site or at an offsite processor On-,site disposal per 10CFR2022 permit 162

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Exelon Generation Company, LLC PSEG Nuclear, LLC RW-AA-100 Revision 8 Page8 of 9 AVAILABLE WASTE WASTE STREAM POINTS OF GENERATION POEING M E

PROCESSING METHODS Filter cartridges Systems - FlooilEquipment Drains, Oewatering, solidification to an Fuel Pool; cartridge filters are typically unstablelstable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc redcton Dry Active Waste Paper, wood, plastic, rubber, glass, DeconlSorling for Free Release metal, and etc-resuiting from daily Compaction/Super-comlaclion plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal meltinm to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant systeim Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies

5.

DOCUMENTATION 5-1.1.

Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:

1.

Sufficent information to support the change together with the appropriate analyses or evaluations justifying the change, and

2.

A determination which documents that the change will maintain the overal conformance of waste products to Federal (1CFR61 and the Branch Technical Position), State, or other appicable requirements, including applicable burial site criteria.

6.

HLJLHLUg 6.1.

Technical Specifications:

6.1.1.

The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),

are to be relocated to the Ucensee Controlled Documents. Some faciities have elected to relocate these details into the Operational Requirements Manual (ORM).

Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.

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Exelon Generation Company, LLC Unit 2 and 3 PSEG Nuclear, LLC RW-AA-100 Revision 8 Page 9 of 9 6.2.

WfitersV

References:

6.2.1-Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71. 49 CFR Parts 171-172 6.2.2.

Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983 62.3.

Technical Position on Waste Form (Revision 1), January 1991 6.2.4.

Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5.

Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 6.2.6.

I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.3.

Users'

References:

6.3.1.

Quality Assurance Program (QATR) 6.3.2.

LS-AA-106, Plant Operations Review Committee 6.3.3-RM-AA-102-1006, Processing Vendor Documents 6-3.4.

RP-AA-600 Series, Radioactive Material/Waste Shipments 6.3.5.

CY-AA-170-2000. Annual Radioactive Effluent Release Report 6.4.

Station Commitments:

6.4.1.

Peach Bottom CM-1, T03819, Letter from GA Hunger, Jr., dated Sept 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications).

6.4.-2 Limerick CM-2, T03896, 10CFR20.2002 permit granted to Limerick via letter dated July 10, 1996.

7.

ATTACHMENTS - None 164

ML13121A430

Text

Subject:

2.3. Stabilization

2.5. Dewatering

2.7. Encapsulation

References:

References:

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