Text

ISFSI - Annual Radioactive Effluent Release Report for 2014
	ML15132A140
Person / Time
Site:	Oyster Creek
Issue date:	04/30/2015
From:	Dostal J; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	RA-15-035
	Download: ML15132A140 (300)
	v • d • e

Exelon Generation 10 CFR 50.36a(a)(2) 10 CFR 72.44 (d)(3)

Technical Specification 6.9.1 .d RA-1 5-035 April 30, 2015 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 Independent Spent Fuel Storage Facility NRC Docket No. 72-15

Subject:

Annual Radioactive Effluent Release Report for 2014 Enclosed with this cover letter is the Annual Radioactive Effluent Release Report for the period January 1 to December 31, 2014. This report includes the Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Facility.

If any further information or assistance is needed, please contact John Renda, Chemistry Manager, at 609-971-2572.

Sincerely, Jeff r 5sta Plant Manage'r - Oyster Creek Nuclear Generating Station

Enclosure:

2014 Annual Radioactive Effluent Release Report cc: Administrator, USNRC Region I (w/o attachment)

USNRC Senior Project Manager, Oyster Creek (w/o attachment)

USNRC Senior Resident Inspector, Oyster Creek (w/o attachment)

Craig Stewart, American Nuclear Insurers A-1 vrjý 5 J-

AExelon Generation(O Annual Radioactive Effluent Release Report 2014 Oyster Creek Generating Station

Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2014 through December 31, 2014 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16

Oyster Creek 2014 Annual Radioactive Effluent Release Report TABLE OF CONTENTS SECTION PAGE EXECUTIVE

SUMMARY

1

1. Introduction 3

2. Supplemental Information 4 A Regulatory Limits 4 B Effluent Concentration Limits 5 C Average Energy 5 D Measurements and Approximations of Total Radioactivity 5 E Batch Releases 9 F Abnormal Releases 9 G Revisions to the ODCM 10 H Radiation Effluent Monitors Out of Service More Than 30 Days 10 I Releases from the Independent Spent Fuel Storage Facility 10 J Program Deviations 11 Appendix A - Effluent and Waste Disposal Summary 12 Appendix B - Solid Waste and Irradiated Fuel Shipments 19 Appendix C - Radiological Impact to Man 26 Appendix D - Meteorological Data 29 Appendix E - ODCM Revisions 103 Appendix F - ERRATA 104 ii

Oyster Creek 2014 Annual Radioactive Effluent Release Report (Page Intentionally Left Blank) iii

Oyster Creek 2014 Annual Radioactive Effluent Release Report EXECUTIVE

SUMMARY

Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for the effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

Both radiological environmental and effluent monitoring indicate that the operation of Oyster Creek Generating Station (OCGS) does not result in significant radiation exposure to the people or the environment surrounding OCGS and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

There were liquid radioactive effluent releases during 2014 of concentrations of tritium too low to detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution Discharge Elimination System (NJPDES) permitted main condenser outfall. The releases were part of nearly continuous pumping of groundwater at approximately 70 gpm containing low levels of tritium and no detectable gamma. Exelon and the State of New Jersey Department of Environmental Protection (NJDEP) agreed to this remediation action instead of natural attenuation to address concentrations of tritium in groundwater. Well 73 and supporting equipment and piping were installed to pump groundwater to the intake structure at the inlet of the main circulating water pumps. Provisions were established for both batch and continuous releases of groundwater. Continuous releases occurred approximately 230 days in 2014. The nearly continuous releases occurred from March 12, 2014 through December 31, 2014 with a total of 2.31 E+07 gallons of groundwater pumped resulting in 1.74E-01 Ci of tritium released to the discharge canal. The dose to the most limiting member of the public due to the release of groundwater was 8.28E-07 mrem.

There were no liquid abnormal releases during 2014.

There were two gaseous abnormal releases during 2014. During maintenance of the Old Radwaste Building exhaust fan EF-1 -17 the side panel was removed to access the fan when positive pressure was noted coming from the opening. The side panel was immediately replaced and sealed. During maintenance of the New Radwaste Building exhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.

The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), and particulates to any individual due to gaseous effluents was 4.78E-01 mrem, which was approximately 3.19E+00 percent of the annual limit of 15 mrem. The majority of organ dose from gaseous effluents was due to C-14. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 1.62E-02 mrad, which was 1.62E-01 percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limit of 10 mrad.

For comparison, the background radiation dose averages approximately 300 mrem per year in the Central New Jersey area, which includes approximately 200 mrem from naturally occurring radon gas and 100 mrem from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposure 1

Oyster Creek 2014 Annual Radioactive Effluent Release Report is due to direct radiation. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 2014. Because it is a sealed unit, no radioactive material was released.

Comparison of environmental sampling results to iodine and particulate gaseous effluents released, showed no radioactivity attributable to the operation of OCGS. Both elevated and ground-level release paths were considered in this review, with total iodines released of 5.29E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.33E-02 Ci.

Joint Frequency Tables of meteorological data, per Stability Classification Category, as well as for all stability classes, are included. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 99.9 percent and 99.9 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.

2

Oyster Creek 2014 Annual Radioactive Effluent Release Report Introduction In accordance with the reporting requirements of Technical Specification 6.9.1.d applicable during the reporting period, this report summarizes the effluent release data for OCGS for the period January 1, 2014 through December 31, 2014. This submittal complies with the format described in Regulatory Guide 1.21, "Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974.

Meteorological data was reported in the format specified in Regulatory Guide 1.23, Revision 1, "Meteorological Monitoring Programs for Nuclear Power Plants".

All vendor results were received and included in the report calculations. Therefore the 2014 report is complete.

3

Oyster Creek 2014 Annual Radioactive Effluent Release Report 2 Supplemental Information Oyster Creek Generating Station Exelon Generation Company, LLC A. Regulatory Limits:

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

1. Noble Gases:

a. < 500 mrem/yr Total Body ODCM Control 3.11.2.1

< 3000 mrem/yr Skin

b. <5 mrad Air Gamma Quarterly air dose limits

<10 mrad Air Beta ODCM Control 3.11.2.2 C. <10 mrad Air Gamma Yearly air dose limits

<20 mrad Air Beta ODCM Control 3.11.2.2

d. <5 mrem Total Body 10 CFR 50, Appendix I, (Gamma) Section II.B.2(b)

< 15 mrem Skin (Beta)

2. lodines, Tritium, Particulates with Half Life > 8 days:

a. < 1500 mrem/yr Any Organ ODCM Control 3.11.2.1

b. :< 7.5 mrem Any Organ Quarterly dose limits ODCM Control 3.11.2.3 C. _<15 mrem Any Organ Yearly dose limits ODCM Control 3.11.2.3

3. Liquid Effluents

a. Concentration 10 CFR 20, Appendix B, ODCM Control 3.11.1.1 Table 2 Column 2

b. _<1.5 mrem Total Body Quarterly dose limits

< 5 mrem Any Organ ODCM Control 3.11.1.2 C. _<3 mrem Total Body Yearly dose limits

<10 mrem Any Organ ODCM Control 3.11.1.2 4

Oyster Creek 2014 Annual Radioactive Effluent Release Report B. Effluent Concentration Limits:

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 ODCM Controls 3.11.2.1.

The Effluent Concentration Limit (ECL) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for identified nuclides, were used to calculate permissible release rates and concentrations for liquid release per ODCM Controls 3.11..1.1. The total activity concentration at the Route 9 bridge for all dissolved or entrained gases was limited to < 2E-04 pjCi/ml.

C. Average Energy ()E:

The Oyster Creek ODCM limits the instantaneous dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin. The average beta and gamma energies (-) of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 1.21, "Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant", may be used to calculate doses in lieu of more sophisticated software. The Oyster Creek radioactive effluent program employs the methodologies presented in U.S. NRC Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977. Therefore, average energy

(-) as described in Regulatory Guide 1.21 is not applicable to Oyster Creek.

D. Measurements and Approximations of Total Radioactivity:

1. Fission and Activation Gases The method used for Gamma Isotopic Analysis is the Canberra Gamma Spectroscopy System with a gas Marinelli beaker. Airborne effluent gaseous activity was continuously monitored and recorded in accordance with the Off Site Dose Calculation Manual (ODCM) Table 4.11.2.1.2-1. Additional grab samples were taken from the stack Radioactive and Gaseous Effluent Monitoring System (RAGEMS) sample point and ground-level release sample points and analyzed at least monthly to determine the isotopic mixture of noble gas activity released for the month. If activity was found in the grab isotopic analysis, the results are entered into Simplified Environmental Effluent Dosimetry System (SEEDS) to calculate dose and dose rates. If no activity is detected in the stack grab samples, post treatment or Off Gas Isotopic Analysis data may be used.

2. lodines The method used for Gamma Isotopic Analysis is the Canberra Gamma Spectroscopy System with a charcoal cartridge. Iodine activity was continuously sampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1.

Charcoal samples are taken from the stack RAGEMS sample point and 5

Oyster Creek 2014 Annual Radioactive Effluent Release Report ground-level release sample points and analyzed at least weekly to determine the total activity released from the plant based on the average vent flow rates recorded for the sampling period.

3. Particulates (half-lives > 8 days)

The method used for Gamma Isotopic Analysis is the Canberra Gamma Spectroscopy System with a particulate filter (47 mm). Particulate activity was continuously sampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1. Particulate samples are taken from the stack RAGEMS sample point and ground-level release sample points and analyzed at least weekly to determine the total activity released from the plant based on the average vent flow rates recorded for the sampling period.

4. Tritium A. Gaseous Effluents Air from stack and vent effluents was passed through a desiccant column and distilled to remove the moisture collected. An aliquot of the water from the distillate was analyzed for tritium using a liquid scintillation counter.

B. Liquid Effluents Water from liquid effluents was analyzed for tritium using a liquid scintillation counter.

5. Gross Alpha Gross alpha was measured by an off-site vendor for both the gas and liquid effluent composite samples.

6. Hard-To-Detects Hard-To-Detects was measured by an off-site vendor for one set of gas monthly composites. The analysis included Fe-55, 1-129, Ni-59, Ni-63, Tc-99, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241.

Fe-55 and Ni-63 have been added to the routine monthly composite analysis schedule based on previous sample results for Hard-To-Detects.

6

Oyster Creek 2014 Annual Radioactive Effluent Release Report

7. Carbon-14 (C-14)

The amount of C-14 (Ci) released was estimated using the guidance from EPRI Technical Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. The C-14 was released primarily through the stack (97%) with a small amount (3%) released through plant vents. The activity in liquid effluents was determined to not be significant.

The offsite dose from C-14 was calculated using SEEDS, which uses approved ODCM methodologies. The resulting annual dose to a child from gaseous releases of C-14 is about 4.53E-01 mrem to the bone.

8. Liquid Effluents Groundwater containing tritium was released during 2014. For continuous releases, tritium and principal gamma emitters were determined for a composite sample daily. The concentration of tritium is limited to ensure concentrations were less than 200 pCi/I in the discharge canal. The gamma emitters were limited to less than detectable concentrations. Gross alpha and Hard-to-detect analyses (Fe-55, Ni-63, Sr-89 and Sr-90) were determined for monthly composite samples for each type of release (batch or continuous).

The leaks into the groundwater were reported in the 2009 Annual Radioactive Effluent Release Report as abnormal releases. Estimates of the curies of the tritium releases were reported. Doses due to the release of the groundwater to the discharge canal were included in the report. To ensure that amount of activity discharge is accurate and limiting, the activity and doses as a result of discharges during 2014 from the groundwater remediation project are included in this report.

9. Estimated Total Error Present Procedure CY-AA-170-2100, Estimated Errors of Effluent Measurements, provides the methodology to obtain an overall estimate of the error associated with radioactive effluents.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report

10. Composite Samples and Lower Limit of Detection (LLD)

Particulate air samples were composited monthly and analyzed for gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63. Groundwater batch and continuous releases were composited at least monthly and analyzed for gross alpha, Sr-89, Sr-90, Fe-55 and Ni-63. These composites are submitted to an offsite vendor laboratory for analysis. The ODCM required LLD for liquid and airborne releases are as follows:

Liquid: LLD Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Ce-141, Cs-134, Cs-137) 5E-07 pCi/ml Principal Gamma Emitters (Ce-144) 5E-06 pCi/ml Dissolved and Entrained Gases 1E-05 pCi/ml H-3 1 E-05 pCi/ml Gross Alpha 1 E-07 pCi/ml Sr-89 and Sr-90 5E-08 pCi/ml Fe-55 and Ni-63 1E-06 pCi/ml Airborne LLD Principal Gamma Emitters (Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138) 1E-04 pCi/ml H-3 1 E-06 pCi/ml 1-131 1 E-12 pCi/ml 1-133 1 E-1 0 pCi/ml Principal Gamma Emitters (Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, Ce-141) 1 E-1 I pCi/ml Principal Gamma Emitters (Mo-99, Ce-144) 1E-10 pCi/ml Gross Alpha 1E-11 pCi/ml Sr-89, Sr-90 1E-1i1 pCi/ml 8

Oyster Creek 2014 Annual Radioactive Effluent Release Report E. Batch Releases:

1. Liqu There were no batch releases of liquid effluents during 2014.

2. Gaseous There were no batch releases of gaseous effluents during 2014.

F. Abnormal Releases:

There were no abnormal liquid releases during 2014.

There were two abnormal gaseous releases during 2014.

During the performance of Work Order C2031047, the side panel of exhaust fan EF-1-17 was removed to access the fan when positive pressure was noted coming from the opening. The side panel was immediately replaced and sealed. A tent had been built around the work area but there was no HEPA filter in place to prevent any releases from the fan from going to the atmosphere. Note that the exhaust from EF-1 -17 is normally to the atmosphere but through the monitored stack effluent release point. Engineering performed a calculation to determine a release rate that encompasses the maximum release rate through this opening.

The following assumptions were made when calculating Curies released and dose:

Though the panel was off for less than 15 minutes, 15 minutes was used as the release period.

The activity due to particulates identified from the sample at the time of the release at the opening was released as a ground level release from the exhaust fan opening at the flow rate calculated by Engineering.

Units Quarter 123 Quarter Quarter Quarter 4 1 2 3 Total Release Ci O.OOeO O.OOeO O.OOeO 1.29e-07 Organ Dose mrem O.0Oe0 0.00e0 0.00e0 1.35E-07 During the performance of Work Order R2227008, which is to perform an annual inspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits were discovered in the expansion joint. This is one of the exhaust fans for the New Radwaste Building to the Main Stack. Note that the exhaust from HV-S-54A is normally to the atmosphere but through the monitored stack effluent release point.

Engineering performed a calculation to determine a release rate that encompasses the maximum release rate for both slits. The activity to inspect the exhaust fan is an annual activity.

The following assumptions were made when calculating Curies released and dose:

The exhaust fan has been leaking since the date of the last inspection until the time of the repair, 8/20/13 through 7/25/14.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report

" All of the activity due to particulates reported from the Main Stack was coming from the New Radwaste Building and therefore being released as a ground level release from the exhaust fan leaks at the flow rate calculated by Engineering.

" HV-S-54A was in operation the entire time since the last inspection was performed.

Units Quarter 123 Quarter Quarter Quarter 4 1 2 3 Total Release Ci 8.81 E-05 8.90E-05 2.41 E-05 O.OOeO Organ Dose mrem 4.78E-04 4.63E-04 1.56E-04 0.000e G. Revisions to the ODCM:

Revision 6 of the ODCM, CY-OC-170-301 was implemented 12/16/2014. A list of the major changes is included below. See the complete copy of CY-OC-170-301 Revision 6 attached as part of this report.

" Meteorological data was updated resulting in changes to X/Q and D/Q values. These changes were also used to update the AySi, PySi and DFSi dose factors.

Distances to the site boundary were updated.

AOG/NRW CCW Service Water Effluent was removed from Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program H. Radiation Effluent Monitors Out of Service More Than 30 Days Per ODCM Control 3.3.3.10, "Radioactive Liquid Effluent Monitoring Instrumentation" and 3.3.3.11, Radioactive Gaseous Effluent Monitoring Instrumentation requires:

With less than the minimum number of radioactive liquid/gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The following is a discussion of instrumentation out of service for greater than 30 days:

1. There was no instrumentation out of service for greater than 30 days.

1. Releases from the Independent Spent Fuel Storage Facility:

The ISFSI is a closed system and the only exposure would be due to direct radiation. This includes iodines, particulates, and noble gases. Based on offsite 10

Oyster Creek 2014 Annual Radioactive Effluent Release Report TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 20.14. Because it is a sealed unit, no radioactive material was released.

J. Program Deviations:

1. The groundwater remediation composite sampler was found with no composite collected from August 26, 2014 at 3:47 AM through August 26, 2014 at 10:00 AM (approximately 6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ). The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and is set to obtain a composite sample once per hour.

This issue occurred due to Operations starting the remediation pump per the section of the procedure for by-passing the sample station. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

2. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluent sample was notcollected January 1, 2014 through November 13, 2014. The New Radwaste/Augmented Offgas Service Water Effluent sample was required by Revision 5 of CY-OC-170-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This requirement was removed in Revision 6 of CY-OC-1 70-301. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE 80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system, sampling is still performed quarterly for gamma emitters. The potential pathway for a release from NRW/AOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the Service Water side of the heat exchanger. The system is designed to maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would develop in the heat exchanger it would be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix A Effluent and Waste Disposal Summary 12

Oyster Creek 2014 Annual Radioactive Effluent Release Report LIST OF TABLES PAGE Table A - 1 Gaseous Effluents - Summary of All Releases 14 Table A - 2 Gaseous Effluents Release Point: Elevated Release 14 Table A - 3 Gaseous Effluents Release Point: Ground Level Releases 16 Table A - 4 Liquid Effluents - Summary of All Releases 17 Table A - 5 Liquid Release Point: Groundwater Remediation 18 13

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table A-I: Gaseous Effluents- Summary Of All Releases Period: January 1, 2014 through December 31, 2014 Unit: Oyster Creek A. Fission & Activation Gases 1 Units 1Quarter II1Quarter 21 Quarter3 Quarter 4 Esto tal Error%I

1. Total Release Ci 1.95E+01 2.07E+01 1.45E+01 7.76E+00 I 25.00% I

2. Average Release Rate for Period for Period I pCi/sec I 1.16E-03 I 8.05E-04 I 1.63E-03 I 6.32E-04

ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.

14

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table A-2: Gaseous Effluents Release Point: Elevated Release Period: January 1, 2014 through December 31, 2014 Unit: Oyster Creek Nuclides Released Continuous Mode Batch Mode

1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr- 85m Ci 1.90E+00 1.51 E+00 8.55E-01 4.38E-01 <LLD <LLD <LLD <LLD Kr-87 Ci 3.24E+00 1.08E+00 2.39E+00 <LLD <LLD <LLD <LLD <LLD Kr-88 Ci 2.13E+00 2.26E+00 5.80E-01 1.98E+00 <LLD <LLD <LLD <LLD Xe-133 Ci 1.45E+00 1.70E+00 1.06E+00 5.25E-01 <LLD <LLD <LLD <LLD Xe-135 Ci 5.96E+00 1.11E+01 8.71E+00 4.82E+00 <LLD <LLD <LLD <LLD Xe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-i 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci 4.83E+00 1.71E+00 <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.95E+01 1.94E+01 1.36E+01 7.76E+00 <LLD <LLD <LLD <LLD

2. lodines 1-131 Ci 3.88E-04 6.18E-04 6,19E-04 7.03E-05 <LLD <LLD <LLD <LLD 1-133 Ci 8.14E-04 1.76E-03 9.50E-04 5.20E-05 <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.20E-03 2.38E-03 1.57E-03 1.22E-04 <LLD <LLD <LLD <LLD

3. Particulates Sr-89 Ci 6.68E-04 1.57E-04 2.93E-04 6.45E-05 <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci 1.92E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci 1.13E-03 4.17E-04 7.12E-04 3.70E-04 <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD 7.77E-05 2.09E-05 <LLD <LLD <LLD <LLD Mn-54 Ci 5.40E-04 4.16E-04 1.14E-03 3.98E-04 <LLD <LLD <LLD <LLD Co-58 Ci 2.41E-03 1.97E-03 3.96E-03 2.OOE-03 <LLD <LLD <LLD <LLD Co-60 Ci 3.04E-03 2.30E-03 5.01 E-03 1.88E-03 <LLD <LLD <LLD <LLD Ni-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci 2.46E-04 2.25E-04 3.52E-04 5.20E-05 <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci 8.40E-04 7.41E-04 1.38E-03 2.36E-04 <LLD <LLD <LLD <LLD Total for Period Ci 8.89E-03 6.23E-03 1.29E-02 5.02E-03 <LLD <LLD <LLD <LLD

4. Tritium H-3 Ci 6.17E+00 9 80E+00 7449E+O0 4.40E+00 <LLD <LLD <LLD <LLD

5. Gross Alpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

6. Carbon-14 *.

C-14 Ci 2.32E+00 2.33E+00 1.76E+00 1.98E--+00 <LLD <LLD <LLD <LLD 15

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table A-3: Gaseous Effluent Release Point: Ground Level Releases Period: January 1, 2014 through December 31, 2014 Unit: Oyster Creek Nuclides Released Continuous Mode Batch Mode

1. Fission gases Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD 1.34E+00 9.26E-01 <LLD <LLD <LLD <LLD <LLD

2. lodines j 1-131 Ci <LLD 9.91E-07 1.30E-05 1.52E-06 <LLD <LLD <LLD <LLD 1-133 Ci <LLD 4.86E-06 1.94E-06 <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total fOr Period Ci <LLD 5.85E-06 1.49E-05 1.52E-06 <LLD <LLD <LLD <LLD

3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-i 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-i 37 Ci 8.29E-07 8.38E-07 2.27E-07 <LLD <LLD <LLD <LLD <LLD Ba-140 Ci 1.19E-05 1.20E-05 3.26E-06 <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci 6.72E-06 6.79E-06; 1.84E-06 <LLD <LLD <LLD <LLD <LLD Mn-54 Ci 8.03E-06 8.12E-06 2.20E-06 <LLD <LLD <LLD <LLD <LLD Co-58 Ci 2.30E-05 2.36E-05 6.65E-06 7.76E-07 <LLD <LLD <LLD <LLD Co-60 Ci 2.81E-05 3.78E-05 1.94E-05 2.18E-06 <LLD <LLD <LLD <LLD Ni-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci 2.21E-06 2.24E-06 6.06E-07 <LLD <LLD <LLD <LLD <LLD Ag-11Om Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci 8.71 E-06 8.81 E-06 2.38E-06 <LLD <LLD <LLD <LLD <LLD Am-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 8.95E-05 1.OOE-04 3.66E-05 2.96E-06 <LLD <LLD <LLD <LLD

4. Tritium PX H-3 Ci 2.66E-01 2.03E-01 4.40E-01 1.70E-01 <LLD <LLD <LLD <LLD

5. GrossAlpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

6. Carbon-14 C-14 Ci 7.20E-02 7.21E-02 5.44E-02 6.13E-02 <LLD <LLD <LLD <LLD 16

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table A-4: Liquid Effluents - Summary Of All Releases Period: January 1, 2014 through December 31, 2014 Unit: Oyster Creek Est. Total A. Fission & Activation ProductsI 4 Units IQuarter I Quarter 2 Quarter 3 Quarter Error %I

1. iota! Release not including Ci <LLD <LLD <LLD <LLD 12 5. v/oI tritium, gases, alpha

2. Average Diluted concentration during period II Units Ci IQuarter I <LLD I Quarter 21 Quarter 3 Quarter

<LLD I <LLD 41 Eror ;

<LLD I 25.00%

I Liters I1.04E+1114.85E+1 o 4.09E+112.19E+1 17

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table A-5: Liquid Release Point: Groundwater Remediation Period: January 1, 2014 through December 31, 2014 Unit: Oyster Creek Nuclides Released Continuous Mode Batch Mode Fission & Unit Activation Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Products 1 2 3 4 1 2 3 4 Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-I 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-I 37 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ni-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD A--133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD H-3 Ci 1,59E-02 I6.95E-02 15.85E-02 13.05E-021 <LLD I<LLD I<LLD I<LLD II, Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LD LD 18

Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix B Solid Waste and Irradiated Fuel Shipments 19

Oyster Creek 2014 Annual Radioactive Effluent Release Report A. Solid waste shipped offsite for burial or disposal (not irradiated fuel)

1. Type of waste Types of Waste Total Total Period Est. Total Quantity Activity Error%

(mI) (Ci)

a. Spent resins,filter sludges, evaporator bottom, etc 4.71 E+01 1.55E+02 2014 2.50E+01

b. Dry compressible waste, contaminated equip, etc 5.61E+02 1.09E+0 2014 2.50E+01

c. Irradiated components, control rods,etc 1.66E-01 4.24E+03 2014 2.50E+01

d. Other 1.10E+02 5.06E-01 2014 2.50E+01 20

Oyster Creek 2014 Annual Radioactive Effluent Release Report

1. Estimate of Major Nuclide Composition (By Waste Type)

Category A - Spent Resin, Filters, Sludges, Evaporator Bottoms, etc.

Isotope Ij Waste Class A I Waste Class B I Waste Class C I Curies I Percent I Curies I Percent I (-iiripn I Pprri-Ant I H-3 5.13E-02 8.87E-02 C-14 4.83E-02 8.35E-02 Cr-51 P-32 Mn-54 3.05E+00 5.27E+00 Fe-55 3.05E+01 5.27E+01 Fe-59 Co-57 1.78E-03 3.08E-03 Co-58 1.46E-02 2.52E-02 Co-60 Ni-59 Ni-63 Zn-65 Sr-89 Sr-90 Nb-95 Tc-99 Ag-11 Oin Sb-125 Cs-1 34 Cs-137 Ce-144 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-243 Cm-244 Totals 5.78E+01 I .OOE+02I 9.72E+01 I .OOE+02 0.OOE+00 10.00E+0 Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report 21

Oyster Creek 2014 Annual Radioactive Effluent Release Report Category B - Dry Compressible Waste, Contaminated Equipment, etc.

Isotope Waste Class A Curies Percent C-14 7.28E-06 6.70E-04 P-32 6.1OE-05 5.61E-03 Mn-54 3.67E-02 3.38E+00 Fe-55 7.99E-01 7.35E+01 Co-57 9.24E-05 8.50E-03 Co-58 1.80E-03 1.66E-01 Co-60 1.90E-01 1.75E+01 Ni-63 6.93E-03 6.38E-01 Zn-65 1.82E-02 1.67E+00 Tc-99

Sb-1125

Sr-89 1.50E-04 1.38E-02 Sr-90 1.89E-04 1.74E-02 Cs-1 37 3.29E-02 3.03E+00 Ce-144 5.00E-04 4.60E-02 Pu-238 6.22E-06 5.72E-04 Pu-239 1.90E-06 1.75E-04 Pu-241 2.19E-04 2.02E-02 Amn-241 7.52E-06 6.92E-04 Cm-242 1.24E-06 1. 14E-04 Cm-243 2.43E-06 2.24E-04 Cm-244 2.43E-06 2.24E-04 Totals 1.09E+00 1.OOE+02 22

Oyster Creek 2014 Annual Radioactive Effluent Release Report Category C - Irradiated components, control rods, etc.

Isotope Waste Class C Curies Percent Abundance H-3 1.06E-02 2.50E-04 C-14 1.16E-01 2.73E-03 Cr-51 6.22E-02 1.47E-03 Mn-54 1.83E+01 4.31E-01 Fe-55 4.77E+02 1.12E+01 Fe-59 3.27E-02 7.71E-04 Co-58 1.19E+00 2.81E-02 Co-60 2.75E+03 6.48E+01 Ni-59 2.92E-01 6.88E-03 Ni-63 3.62E+01 8.53E-01 Zn-65 2.83E-01 6.67E-03 Sr-90 2.79E-05 6.58E-07 Zr-95 1.37E+02 3.23E+00 Nb-94 2.60E-03 6.13E-05 Mo-93 2.91 E-05 6.86E-07 Tc-99 3.32E-05 7.83E-07 Sb-125 8.16E+02 1.92E+01 1-129 1.70E-09 4.01E-11 Cs-137 4.52E-05 1.07E-06 Ce-144 1.31E-07 3.09E-09 Hf-1 81 9.68E-01 2.28E-02 Ta-182 4.35E+00 1.03E-01 U-235 3.97E-1 1 9.36E-1 3 Np-237 9.79E-10 2.31 E-11 Pu-238 1.35E-05 3.18E-07 Totals 4.24E+03 1.OOE+02 23

Oyster Creek 2014 Annual Radioactive Effluent Release Report Category D - Other - Scrap Metal Isotope Waste Class A Curies Percent H-3 4.70E-01 9.28E+01 C-14 2.42E-07 4.78E-05 P-32 1.82E-06 3.59E-04 Mn-54 1.23E-03 2.43E-01 Fe-55 2.66E-02 5.25E+00 Co-57 3.27E-06 6.46E-04 Co-58 6.11E-05 1.21E-02 Co-60 6.34E-03 1.25E+00 Ni-63 2.30E-04 4.54E-02 Zn-65 6.11E-04 1.21E-01 Sr-85 5.73E-13 1.13E-10 Sr-89 5.08E-06 1.OOE-03 Sr-90 6.29E-06 1.24E-03 Y-88 9.40E-08 1.86E-05 Cd-109 8.87E-07 1.75E-04 Sn-113 2.62E-08 5.17E-06 Cs-137 1.33E-03 2.63E-01 Ba-133 1.15E-05 2.27E-03 Ce-1 39 3.82E-08 7.54E-06 Ce-144 1.67E-05 3.30E-03 Hg-203 8.55E-1 1 1.69E-08 Pu-238 2.07E-07 4.09E-05 Pu-239 6.30E-08 1.24E-05 Pu-241 7.26E-06 1.43E-03 Am-241 9.89E-06 1.95E-03 Cm-242 4.16E-08 8.21E-06 Cm-243 8.07E-08 1.59E-05 Cm-244 8.06E-08 1.59E-05 Totals 5.06E-01 1.OOE+02 Note: Grey fields are where results were not reported in the NRC Regulatory Guide 1.21 Report

2. Solid Waste (Disposition)

Number of Shipments Mode of Transportation Destination 9 Hittman Transport Co. Barnwell Disposal Facility 16 Hittman Transport Co. Energy Solutions Services, Inc.

B. Irradiated Fuel Shipments (disposition).

There were no irradiated fuel shipments.

24

Oyster Creek 2014 Annual Radioactive Effluent Release Report C. Changes to the Process Control Program Revision 10 of the Process Control Program, RW-AA-1 00 was implemented August 26, 2014. See the complete copy of RW-AA-1 00 Revision 10 attached as part of this report.

25

Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix C Radiological Impact to Man 26

Oyster Creek 2014 Annual Radioactive Effluent Release Report Per ODCM Administrative Control 6.2, an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year must be made to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. For purposes of this calculation the following assumptions were made:

Gaseous

" Nearest member of the public was W sector at 483 meters.

Actual 2014 meteorology and measured gaseous effluent releases were used.

All significant pathways were assumed to be present.

Occupancy factor was considered 22.8% (40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months s/week for 50 weeks).

Ligqui

Doses calculated in the discharge canal at the Route 9 Bridge.

Fish, shellfish and shoreline pathways doses calculated.

40 CFR Part 190 Compliance

" Dosimetry measurements (minus average of control stations) measured direct radiation for the nearest member of the public. The nearest member of the public for direct radiation is considered an individual that works in the warehouse west of the site. As a worker, the individual is assumed to work 2,000 hours0 days 0 hours 0 weeks 0 months per year at this location. Note that for the warehouse worker total dose calculations the full year (8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months ) values for Iodine, Particulate, Carbon-14, Tritium and Liquid are used.

Nearest resident was at SE sector at 937 meters.

The highest calculated dose for gamma air dose and liquid total body were summed for total body dose.

The highest calculated dose for gamma air dose, child bone and liquid organ were summed for organ dose.

The limits for Kr-85, 1-129, Pu-239 and other alpha-emitting transuranic radionuclides with half-lives greater than one year were not exceeded.

The ODCM does not require total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site to be calculated.

27

Oyster Creek 2014 Annual Radioactive Effluent Release Report A summary of gaseous and liquid radiation doses to most likely exposed MEMBER OF THE PUBLIC was as follows:

Location % of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters) (toward) Limit Limit Unit Gamma -

Noble Gas Air Dose 1.62E-02 All 405 E 1.62E-01 10 mrad Beta - Air Noble Gas Dose 1.91 E-02 All 406 E 9.55E-02 20 mrad Total Body Noble Gas (Gamma) 2.18E-03 All 972 ESE 4.36E-02 5 mrem Noble Gas Skin (Beta) 4.86E-03 All 972 ESE 3.24E-02 15 mrem Iodine, Particulate, Bone 4.78E-01 Child 937 SE 3.19E+00 15 mrem Carbon-14 &

Tritium Liquid Total body 8.28E-07 All South Route 9 2.76E-05 3 mrem Liquid Organ 8.28E-07E All Bridge 8.28E-06 10 mrem Direct Radiation Total Body 5.09E+00 All 483 W 2.04E+01 25 mrem Direct Radiation Total Body <LLD All 937 SE <LLD 25 mrem 40 CFR Part 190 Compliance Warehouse Worker Total Dose Total Body 5.09E+00 All 483 W 2.04E+01 25 mremn Total Dose Bone 5.57E+00 All 483 W 2.23E+01 25 mremn Total Dose Thyroid 5.09E+00 All 483 W 6.79E+00 75 mremn Nearest Resident Total Dose Total Body 1.62E-02 All 937 SE 6.48E-02 25 mrem Total Dose Bone 4.94E-01 All 937 SE 1.98E+00 25 mrem Total Dose Thyroid 1.52h-O All 937 SE Z.1_E-02 75 mrem 28

Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix D Meteorological Data 29

Oyster Creek 2014 Annual Radioactive Effluent Release Report LIST OF METEOROLOGICAL DATA TABLES PAGE Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 31 the Oyster Creek Generating Station, January - March, 2014 Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 38 the Oyster Creek Generating Station, January - March, 2014 Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 45 the Oyster Creek Generating Station, April - June, 2014 Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 52 the Oyster Creek Generating Station, April - June, 2014 Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 59 the Oyster Creek Generating Station, July - September, 2014 Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 66 the Oyster Creek Generating Station, July - September, 2014 Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 73 the Oyster Creek Generating Station, October- December, 2014 Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 80 the Oyster Creek Generating Station, October- December, 2014 Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for 87 the Oyster Creek Generating Station, January - December, 2014 Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for 95 the Oyster Creek Generating Station, January - December, 2014 30

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 4 NNE 0 0 1 NE 11 0 15 ENE 7 2 17 E 0 0 2 ESE 0 0 8 SE 5 0 10 SSE 4 0 5 S 7 5 12 SSW 3 5 13 SW 6 0 10 WSW 9 4 19 W 22 8 38 WNW 36 20 66 NW 28 10 47 NNW 17 0 25 Variable 0 0 0 Total 0 83 155 54 0 0 292 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: 4 31

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 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 0 0 0 0 N 0 7 7 0 0 0 0 NNE 0 1 1 2 0 0 0 NE 0 3 5 5 0 0 0 ENE 0 3 8 0 0 0 0 E 0 4 4 0 0 0 0 ESE 0 1 1 1 0 0 0 SE 0 4 5 2 0 0 0 SSE 0 1 3 S 0 0 5 2 0 0 7 SSW 0 2 4 1 0 0 7 SW 0 2 0 0 0 0 2 WSW 0 4 6 0 0 0 10 W 0 4 5 5 0 0 14 WNW 0 10 4 3 0 0 17 NW 0 8 7 2 0 0 17 NNW 0 4 0 0 0 0 4 Variable 0 0 0 0 0 0 0 Total 0 58 41 13 0 0 112 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: 4 32

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 0 N 0 1 0 0 0 0 NNE 1 3 0 0 0 0 NE 3 2 0 0 0 0 ENE 2 1 0 0 0 0 E 1 2 0 0 0 0 ESE 2 4 0 0 0 0 SE 4 4 0 0 0 0 SSE 0 1 1 0 0 0 S 2 1 2 0 0 0 SSW 3 2 0 0 0 0 SW 2 2 0 0 0 0 WSW 2 W 1 3 1 0 0 5 WNW 2 6 2 0 0 10 NW 4 2 4 0 0 10 NNW 3 1 0 0 0 4 Variable 0 0 0 0 0 0 Total 0 29 15 '7 0 0 51 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: 4 33

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 21 17 0 0 0 42 NNE 3 32 33 2 0 0 70 NE 8 33 16 4 0 0 61 ENE 3 19 13 0 0 0 35 E 2 2 1 0 0 0 5 ESE 2 5 0 0 0 0 7 SE 1 5 3 0 0 0 9 SSE 1 7 1 0 0 0 9 S 1 7 6 0 0 0 14 SSW 1 6 12 15 0 0 34 SW 2 7 7 1 0 0 17 WSW 4 13 5 0 0 0 22 W 5 18 13 5 0 0 41 WNW 5 23 21 19 0 0 68 NW 4 31 25 5 0 0 65 NNW 5 33 40 0 0 0 78 Variable 0 0 0 0 0 0 0 Total 51 262 213 51 0 0 577 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: 4 34

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 14 2 0 0 0 19 NNE 4 13 0 0 0 0 17 NE 3 27 2 1 0 0 33 ENE 8 10 5 0 0 0 23 E 5 2 0 0 0 0 7 ESE 2 1 0 0 0 0 3 SE 0 8 1 0 0 0 9 SSE 2 6 9 1 0 0 18 S 5 15 11 12 0 0 43 SSW 5 16 40 11 0 0 72 SW 10 34 6 0 0 0 50 WSW 10 28 3 0 0 0 41 W 9 34 3 1 0 0 47 WNW 13 49 27 1 0 0 90 NW 13 46 22 0 0 0 81 NNW 11 17 13 0 0 0 41 Variable 0 0 0 0 0 0 0 Total 103 320 144 27 0 0 594 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: 4 35

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - I Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Moderately Stable - 15OFt-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 o 0 0 0 9

N 8 1 0 0 0 0 NNE 2 1 3 0 0 0 0 NE 5 0 5 1 0 0 0 0 ENE 2 3, 0 0 0 0 E 1 0 1 0 0 0 0 0 ESE 2 2 0 0 0 0 SE 2 3 5 1 0 0 0 0 SSE 0 1 1 0 0 0 0 S 2 3 0 0 0 0 SSW 2 6 8 0 0 0 0 SW 6 6 12 0 0 0 0 WSW 13 14 27 0 0 0 0 W 28 16 44 0 0 0 0 WNW 11 13 24 0 0 0 0 NW 7 15 22 0 0 0 0 NNW 7 5 12 0 0 0 0 Variable 0 0 0 Total 98 83 0 0 0 0 181 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 36

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 1 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 4 0 0 0 0 0 N 4 4 0 0 0 0 0 NNE 4 6 0 0 0 0 0 NE 6 3 0 0 0 0 0 ENE 3 3 0 0 0 0 0 E 3 4 0 0 0 0 0 ESE 4 SE 3 2 0 0 0 0 5 SSE 4 0 0 0 0 0 4 S 5 0 0 0 0 0 5 SSW 9 0 0 0 0 0 9 SW 27 1 0 0 0 0 28 WSW 72 10 0 0 0 0 82 W 76 18 0 0 0 0 94 WNW 38 3 0 0 0 0 41 NW 31 15 0 0 0 0 46 NNW 2 0 0 0 0 0 2 Variable 0 0 0 0 0 0 0 Total 291 49 0 0 0 0 340 Hours of calm in this stability class: 8 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 37

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Extremely Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 2 0 0 2 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 1 1 W 0 0 0 1 1 1 3 WNW 0 0 0 2 2 4 8 NW 0 0 1 2 0 3 6 NNW 0 0 0 0 1 0 1 Variable 0 0 0 0 0 0 0 Total 0 0 1 7 4 9 21 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabi lity class: 0 Hours of missing stability measurements in all s tability classes: 4 38

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Moderately Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

. Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 0 0 0 1 N 0 1 0 0 0 NNE 0 0 NE 0 0 4 3 0 7 ENE 0 0 0 1 1 2 E 0 0 0 0 0 0 ESE 0 0 0 0 0 0 SE 0 1 0 0 0 1 SSE 0 0 1 0 0 1 S 0 0 1 0 0 1 SSW 0 0 0 2 0 2 SW 0 1 1 0 0 2 WSW 0 0 3 2 2 7 W 0 0 1 2 4 7 WNW 0 2 9 3 4 18 NW 0 1 10 4 5 20 NNW 0 2 4 3 0 9 Variable 0 0 0 0 0 0 Total 0 0 8 34 20 16 78 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: 4 39

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Slightly Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 NNE 0 1 NE 3 8 ENE 0 9 E 0 0 ESE 0 2 SE 0 5 SSE 3 3 S 1 1 SSW 2 6 SW 1 4 WSW 5 10 W 10 21 WNW 7 32 NW 8 29 NNW 7 15 Variable 0 0 Total 0 10 45 47 30 15 147 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: 4 40

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Neutral - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 17 16 19 1 58 NNE 3 5 48 24 0 80 NE 8 21 35 12 5 81 ENE 1 7 27 24 1 60 E 6 4 5 1 0 16 ESE 7 2 0 1 0 10 SE 1 6 5 1 0 13 SSE 0 4 3 0 0 7 S 2 12 8 0 1 23 SSW 0 5 19 22 21 67 SW 1 13 8 8 1 31 WSW 3 11 14 8 0 36 W 3 17 20 11 13 65 WNW 4 10 28 26 34 102 NW 13 26 28 34 32 133 NNW 10 18 31 27 12 99 Variable 0 0 0 0 0 0 Total 2 67 178 218 121 881 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: 4 41

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Slightly Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 1 0 8 NNE 11 0 0 17 NE 5 0 7 22 ENE 10 6 2 23 E 0 0 0 4 ESE 0 0 0 4 SE 4 1 2 14 SSE 0 3 10 18 S 2 3 12 27 SSW 15 32 20 73 SW 9 23 4 43 WSW 17 14 3 41 W 23 13 0 44 WNW 40 38 3 89 NW 36 38 4 84 NNW 18 5 0 29 Variable 0 0 0 0 Total 3 30 69 194 177 67 540 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: 4 42

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Moderately Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 8 8 1 19 NNE 0 1 1 0 0 2 NE 2 1 2 0 0 6 ENE 2 2 5 0 0 9 E 1 4 0 0 0 6 ESE 1 3 2 0 0 8 SE 2 3 3 1 0 10 SSE 2 6 0 1 3 12 S 5 4 2 2 0 14 SSW 1 5 1 1 1 11 SW 4 2 6 5 5 22 WSW 1 4 9 2 5 21 W 1 3 16 8 3 31 WNW 0 7 21 23 2 53 NW 0 6 18 23 0 47 NNW 0 4 10 9 1 24 Variable 0 0 0 0 0 0 Total 8 22 57 104 83 21 295 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: 4 43

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 2 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - March, 2014 Oyster Creek Alpha Period of Record: January - March 2014 Stability Class - Extremely Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 15 NNE 11 NE 4 ENE 6 E 5 ESE 4 SE 11 SSE 17 S 17 SSW 10 SW 14 WSW 16 W 10 WNW 18 NW 20 NNW 14 Variable 0 Total 20 40 48 44 29 11 192 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 44

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 4 0 11 NNE 3 1 0 4 NE 13 8 0 21 ENE 20 33 0 53 E 24 9 0 34 ESE 28 19 0 47 SE 20 42 0 62 SSE 3 39 1 43 S 4 41 13 58 SSW 5 3 6 16 SW 5 2 0 7 WSW 6 11 0 17 W 9 13 0 22 WNW 3 17 11 31 NW 14 50 9 73 NNW 5 18 0 23 Variable 0 0 0 0 Total 1 169 310 2 0 522 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: I 45

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 2 NNE 1 6 0 0 0 0 7 NE 0 ii 0 0 ii ENE 0 13 3 0 20 E 0 5 0 0 5 ESE 1 5 0 0 6 SE 0 14 2 0 16 SSE 0 5 3 0 9 S 0 6 3 0 11 SSW 0 2 1 0 5 SW 0 3 0 0 4 WSW 1 3 4 0 9 W 0 5 4 0 9 WNW 0 3 3 0 7 NW 0 4 7 2 0 0 13 NNW 0 11 1 0 0 0 12 Variable 0 0 0 0 0 0 0 Total 3 97 32 14 0 0 146 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 cl asses: 1 46

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Slightly Unstable - 15OFt-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 NNE 2 0 2 NE 0 0 3 ENE 0 0 5 E 1 0 3 ESE 0 0 2 SE 0 0 4 SSE 0 0 7 S 0 0 8 SSW 0 0 3 SW 0 0 1 WSW 0 0 1 W 0 0 1 WNW 1 0 5 NW 0 0 1 NNW 1 0 1 Variable 0 0 0 Total 5 28 11 4 0 0 48 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all st ability class es:

47

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet qind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 10 1 0 0 0 13 NNE 4 4 0 0 0 0 8 NE 5 48 12 0 0 0 65 ENE 7 38 33 18 0 0 96 E 2 22 5 3 0 0 32 ESE 5 9 4 2 0 0 20 SE 0 20 2 2 0 0 24 SSE 1 21 15 9 0 0 46 S 2 28 15 4 4 0 53 SSW 0 8 8 19 1 0 36 SW 0 7 0 0 0 0 7 WSW 1 3 4 0 0 0 8 W 3 8 5 0 0 0 16 WNW 3 10 10 1 0 0 24 NW 3 16 7 3 0 0 29 NNW 4 20 8 1 0 0 33 Variable 0 0 0 0 0 0 0 Total 42 272 129 62 5 0 510 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 48

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 3 0 10 NNE 7 2 0 9 NE 11 10 2 23 ENE 5 10 7 22 E 5 7 2 14 ESE 4 6 1 11 SE 9 10 1 20 SSE 14 16 4 37 S 19 41 6 67 SSW 12 26 20 67 SW 6 16 1 23 WSW 6 33 2 41 W 13 19 2 34 WNW 11 20 4 35 NW 16 22 8 46 NNW 5 7 2 14 Variable 1 0 0 1 Total 151 248 62 13 0 0 474 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 49

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3. 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 0 N 2 0 2 0 0 0 0 NNE 2 0 2 0 0 0 0 NE 2 1 3 0 0 0 0 ENE 3 0 3 0 0 0 0 E 2 1 3 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 4 0 4 0 0 0 0 SSE 9 0 9 0 0 0 0 S 9 1 10 0 0 0 0 SSW 7 0 7 0 0 0 0 SW 12 5 17 0 0 0 0 WSW 7 17 24 0 0 0 0 W 14 6 20 0 0 0 0 WNW 10 25 35 0 0 0 0 NW 13 7 20 0 0 0 0 NNW 6 0 6 0 0 0 0 Variable 0 0 0 Total 102 63 0 0 0 0 165 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 50

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 3 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 2 NNE 0 1 1 NE 1 0 1 ENE 2 0 2 E 1 0 1 ESE 0 0 0 SE 0 0 0 SSE 1 0 1 S 3 0 3 SSW 11 0 SW 13 1 14 WSW 48 8 56 W 94 4 98 WNW 56 9 65 NW 34 6 40 NNW 15 1 16 Variable 0 0 0 Total 281 30 0 311 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: 1 51

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Extremely Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 5 0 5 ENE 0 0 3 6 1 0 10 E 0 0 3 0 0 0 3 ESE 0 0 2 0 0 0 2 SE 0 0 2 1 0 0 3 SSE 0 0 0 2 0 0 2 S 0 0 0 13 4 0 17 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 2 1 0 0 3 W 0 0 0 2 0 0 2 WNW 0 0 0 2 3 5 10 NW 0 0 2 15 3 8 28 NNW 0 0 0 5 0 0 5 Variable 0 0 0 0 0 0 0 Total 0 0 14 47 16 13 90 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stalbility class: 0 Hours of missing stability measurements in all stability classes: 1 52

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Moderately Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 4 NNE 1 0 2 NE 1 2 4 ENE 11 4 24 E 9 0 9 ESE 13 1 18 SE 16 4 20 SSE 4 6 10 S 2 11 16 SSW 1 3 11 SW 2 0 2 WSW 2 3 6 W 2 2 5 WNW 2 6 9 NW 5 18 31 NNW 2 6 9 Variable 0 0 0 Total 0 4 73 70 25 8 180 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: I 53

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Slightly Unstable - 380Ft-33Ft.Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 5 NNE 0 3 NE 5 9 ENE 9 20 E 12 13 ESE 7 13 SE 11 14 SSE 12 20 S 6 15 SSW 3 10 SW 4 5 WSW 1 6 W 5 12 WNW 1 9 NW 5 20 NNW 3 9 Variable 0 0 Total 1 21 87 53 13 8 183 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 54

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Neutral - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 3 11 7 0 0 22 NNE 1 6 8 1 0 0 16 NE 1 16 33 21 2 2 75 ENE 1 11 25 37 30 30 134 E 0 15 14 9 12 6 56 ESE 0 15 11 7 0 2 35 SE 2 11 19 4 1 0 37 SSE 1 10 41 9 6 9 76 S 0 5 37 29 3 7 81 SSW 1 4 24 25 7 32 93 SW 0 2 14 0 0 0 16 WSW 0 4 3 7 4 2 20 W 0 5 5 8 11 0 29 WNW 0 4 10 8 9 8 39 NW 0 5 17 9 14 4 49 NNW 1 7 10 11 9 5 43 Variable 0 0 0 0 0 0 0 Total 9 123 282 192 108 107 821 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 55

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Slightly Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 3 6 0 0 14 NNE 1 6 2 0 0 9 NE 6 4 4 1 0 15 ENE 2 4 7 2 0 17 E 3 10 4 0 1 18 ESE 2 5 4 1 2 14 SE 1 16 1 2 2 23 SSE 0 10 5 8 7 30 S 3 13 23 3 3 45 SSW 3 17 34 18 4 76 SW 4 10 11 12 0 37 WSW 1 1 10 14 2 28 W 1 3 16 8 1 29 WNW 3 6 12 17 1 39 NW 3 6 14 18 2 43 NNW 3 6 10 4 0 24 Variable 0 0 0 0 0 0 Total 7 38 120 163 108 25 461 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 56

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Moderately Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 4 9 8 0 23 NNE 0 0 0 1 0 0 1 NE 0 0 5 1 0 0 6 ENE 0 0 3 0 0 0 3 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 1 1 1 0 0 0 3 SSE 1 0 1 0 0 0 2 S 0 2 2 5 4 0 13 SSW 0 2 4 9 2 0 17 SW 0 1 4 9 3 0 17 WSW 2 1 3 6 10 11 33 W 0 0 5 8 5 0 18 WNW 0 2 4 6 9 0 21 NW 0 0 4 11 26 0 41 NNW 1 1 1 7 17 1 28 Variable 0 0 0 0 0 0 0 Total 5 12 41 72 84 12 226 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 57

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 4 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, April - June, 2014 Oyster Creek Alpha Period of Record: April - June 2014 Stability Class - Extremely Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in.mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 1 20 NNE 6 3 18 NE 4 0 12 ENE 0 0 2 E 0 0 5 ESE 0 0 1 SE 0 0 9 SSE 0 0 3 S 0 0 5 SSW 10 0 19 SW 5 4 11 WSW 5 8 26 W 4 6 12 WNW 6 3 14 NW 8 4 29 NNW 14 15 36 Variable 0 0 0 Total 10 33 56 73 44 6 222 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 58

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 0 0 5 NNE 5 0 0 5 NE 16 2 0 18 ENE ý37 8 0 45 E 19 5 0 24 ESE 19 2 0 21 SE 12 24 0 36 SSE 5 18 0 23 S 2 36 17 55 SSW 8 12 2 22 SW 11 19 0 30 WSW 3 1 0 4 W 4 9 0 13 WNW 5 4 0 9 NW 13 13 0 26 NNW 5 3 0 8 Variable 0 0 0 0 Total 0 169 156 19 0 0 344 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 59

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 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 1 0 0 0 N 0 4 5 1 0 0 0 NNE 0 7 7 4 0 0 0 11 NE 1 6 3 0 0 0 ENE 0 12 15 E 0 6 0 0 0 0 6 ESE 0 7 0 0 0 0 7 SE 0 7 9 0 0 0 16 SSE 0 4 2 0 0 0 6 S 0 4 12 1 0 0 17 SSW 1 3 6 0 0 0 10 SW 0 7 4 0 0 0 11 WSW 0 12 0 0 0 0 12 W 0 3 3 0 0 0 6 WNW 0 9 2 0 0 0 11 NW 0 7 2 0 0 0 9 NNW 0 13 1 0 0 0 14 Variable 0 0 o 0 0 0 0 Total 2 ill 49 I 0 0 163 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 60

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Slightly Unstable - 15OFt-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 NNE 0 3 NE 1 9 ENE 3 9 E 0 2 ESE 0 2 SE 3 9 SSE 1 3 S 11 12 SSW 3 5 SW 0 7 WSW 1 5 W 0 4 WNW 1 7 NW 1 4 NNW 0 5 Variable 0 0 Total 6 58 25 0 0 0 89 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili ty class: 0 Hours of missing stability measurements in all stability cl asses: 0 61

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 N 6 0 10 0 0 NNE 12 5 22 0 0 NE 27 20 51 0 0 ENE 28 23 55 0 0 E 9 7 17 0 0 ESE 11 0 16 0 0 SE 16 7 25 0 0 SSE 17 3 20 0 0 S 18 16 35 0 0 SSW 11 17 31 0 0 SW 13 4 19 0 0 WSW 11 4 21 0 0 W 9 3 14 0 0 WNW 12 2 16 0 0 NW 17 4 24 0 0 NNW 19 3 26 0 0 Variable 0 0 0 Total 43 236 118 5 0 0 402 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 62

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 11 3 0 0 0 22 NNE 3 4 0 0 0 0 7 NE 15 33 6 0 0 0 54 ENE 4 18 17 0 0 0 39 E 7 7 9 0 0 0 23 ESE 2 8 1 0 0 0 11 SE 4 19 5 3 0 0 31 SSE 13 8 1 0 0 0 22 S 15 59 0 0 0 0 74 SSW 19 51 18 0 0 0 88 SW 18 36 4 0 0 0 58 WSW 22 21 2 0 0 0 45 W 10 12 0 0 0 0 22 WNW 7 21 0 0 0 0 28 NW 9 19 2 0 0 0 30 NNW 10 25 2 0 0 0 37 Variable 0 0 0 0 0 0 0 Total 166 352 70 3 0 0 591 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 63

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 0 0 0 0 0 5 NNE 2 0 0 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 1 1 0 0 0 0 2 E 1 1 0 0 0 0 2 ESE 2 0 0 0 0 0 2 SE 2 0 0 0 0 0 2 SSE 6 0 0 0 0 0 6 S 6 3 0 0 0 0 9 SSW 10 3 0 0 0 0 13 SW 15 1 0 0 0 0 16 WSW 23 8 0 0 0 0 31 W 18 3 0 0 0 0 21 WNW 17 10 0 0 0 0 27 NW 13 3 0 0 0 0 16 NNW 7 6 0 0 0 0 13 Variable 0 0 0 0 0 0 0 Total 128 40 0 0 0 0 168 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 64

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 5 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 NNE. 1 3 NE 0 0 ENE 1 1 E 0 0 ESE 1 1 SE 1 2 SSE 3 3 S 11 11 SSW 7 7 SW 15 15 WSW 75 83 W 149 150 WNW 64 67 NW 62 67 NNW 22 25 Variable 1 1 Total 414 23 0 0 0 0 437 Hours of calm in this stability class: 11 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 65

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Extremely Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

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

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Moderately Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 NNE 0 0 0 NE 2 5 7 ENE 10 0 10 E 5 0 5 ESE 2 0 2 SE 5 0 5 SSE 2 2 4 S 1 11 17 SSW 0 5 8 SW 3 11 16 WSW 0 4 4 W 0 0 1 WNW 0 0 0 NW 0 6 6 NNW 1 1 2 Variable 0 0 0 Total 0 0 31 45 11 0 87 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 67

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Slightly Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 4 1 0 0 5 NNE 0 2 4 0 0 0 6 NE 0 0 16 5 0 0 21 ENE 0 4 16 8 0 0 28 E 0 1 8 0 0 0 9 ESE 0 3 9 0 0 0 12 SE 0 1 15 4 0 0 20 SSE 0 0 9 4 0 0 13 S 0 0 2 9 3 0 14 SSW 0 2 7 6 2 0 17 SW 0 0 10 3 0 0 13 WSW 0 0 1 1 0 0 2 W 0 0 2 7 2 0 11 WNW 0 0 3 5 0 0 8 NW 0 0 13 7 1 0 21 NNW 0 2 4 2 0 0 8 Variable 0 0 0 0 0 0 0 Total 0 15 123 62 8 0 208 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 68

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Neutral - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 7 6 6 0 24 NNE 17 17 8 4 0 47 NE 17 34 33 22 7 114 ENE 9 22 32 22 15 100 E 9 18 2 14 8 51 ESE 11 18 4 0 1 34 SE 13 20 29 1 3 70 SSE 4 20 9 1 0 34 S 5 21 30 4 0 60 SSW 2 15 35 26 2 80 SW 11 9 20 1 0 42 WSW 13 16 8 4 0 41 W 9 11 10 2 0 32 WNW 4 22 11 0 0 37 NW 9 10 9 4 0 33 NNW 7 18 17 0 2 45 Variable 0 0 0 0 0 0 Total 9 145 278 263 ill 38 844 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 69

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Slightly Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 9 2 16 NNE 8 2 0 13 NE 3 1 1 13 ENE 4 2 22 E 5 4 1 13 ESE Ii 1 0 16 SE 8 7 0 19 SSE 12 5 0 22 S 8 19 1 37 SSW 21 68 10 103 SW 16 41 18 79 WSW 9 17 10 41 W 9 6 2 19 WNW 4 4 11 23 NW 3 12 10 31 NNW 3 14 9 28 Variable 0 0 0 0 Total 10 50 128 221 77 9 495 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 70

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Moderately Stable - 38OFt-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8:-12 13-18 19-24 > 24 Total N 10 7 20 NNE 5 0 11 NE 1 0 6 ENE 0 1 11 E 0 0 5 ESE 2 0 4 SE 1 0 9 SSE 0 0 9 S 7 1 20 SSW 10 0 19 SW 10 4 25 WSW 15 11 40 W 8 5 21.

WNW 5 6 13 NW 11 6 26 NNW 5 17 28 Variable 0 0 0 Total 13 38 67 90 58 1 267 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 71

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 6 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, July - September, 2014 Oyster Creek Alpha Period of Record: July - September 2014 Stability Class - Extremely Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 .8-12 13-18 19-24 > 24 Total N 1 1 5 17 0 33 NNE 0 9 2 1 0 13 NE 1 5 7 6 0 19 ENE 1 4 3 2 0 10 E 3 4 0 2 0 9 ESE 0 3 0 0 0 3 SE 0 1 3 0 0 4 SSE 1 5 8 0 0 14 S 0 4 6 2 0 12 SSW 3 4 6 5 0 18 SW 0 2 9 8 0 22 WSW 0 3 10 14 6 3 36 W 0 5 9 7 3 1 25 WNW 2 1 4 9 1 0 17 NW 1 5 7 13 1 0 27 NNW 1 0 4 18 6 0 29 Variable 0 0 0 0 0 0 0 Total 14 56 83 104 30 4 291 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl asses: 0 72

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 NNE 0 0 0 NE 0 0 2 ENE 0 0 4 E 0 0 1 ESE 0 0 1 SE 0 0 2 SSE 0 0 4 S 0 0 7 SSW 0 0 8 SW 0 0 8 WSW 0 9 12 0 21 W 0 9 11 0 22 WNW 0 3 26 3 0 0 32 NW 0 4 33 5 0 0 42 NNW 0 4 3 0 0 0 7 Variable 0 0 0 0 0 0 0 Total 0 43 103 15 0 0 161 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: 5 73

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Moderately Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 5 NNE 0 0 2 NE 0 0 3 ENE 0 0 0 E 0 0 1 ESE 0 0 3 SE 0 0 9 SSE 0 0 4 S 0 0 8 SSW 0 0 5 SW 0 0 6 WSW 0 0 4 W 0 0 11 WNW 0 7 14 0 21 NW 0 4 11 1 0 0 16 NNW 0 4 1 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 0 50 51 2 0 0 103 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: 5 74

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Slightly Unstable - 15OFt-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 8 NNE 1 NE 2 ENE 1 E 0 ESE 0 SE 0 SSE 4 S 0 SSW 2 SW 1 WSW 7 W 4 WNW 15 NW 7 NNW 3 Variable 0 Total 1 23 27 4 0 0 55 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 75

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 26 30 61 NNE 26 26 57 NE 16 19 38 ENE 5 6 12 E 9 1 10 ESE 2 0 3 SE 10 3 15 SSE 12 19 37 S 5 13 26 SSW 7 9 25 SW 18 4 24 WSW 28 9 39 W 20 11 35 WNW 31 32 70 NW 44 48 102 NNW 13 15 35 Variable 0 0 0 Total 49 272 245 23 0 0 589 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 76

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 15 21 10 46 NNE 6 8 0 14 NE 13 20 2 35 ENE 7 7 1 15 E 1 1 0 2 ESE 1 2 0 3 SE 5 10 3 18 SSE 7 24 11 42 S 0 15 19 34 SSW 2 48 15 67 SW 5 41 15 61 WSW 18 46 1 65 W 17 49 5 71 WNW 15 84 20 119 NW 20 35 22 77 NNW 16 32 16 65 Variable 0 0 0 0 Total 148 443 140 0 734 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 77

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 12 1 13 NNE 2 1 3 NE 3 0 3 ENE 1 0 1 E 2 0 2 ESE 0 0 0 SE 3 0 3 SSE 1 0 1 S 4 1 5 SSW 4 10 14 SW 5 14 19 WSW 17 12 29 W 20 26 46 WNW 18 13 31 NW 17 6 23 NNW 9 2 11 Variable 0 0 0 Total 118 86 0 0 0 0 204 Hours of calm in this stability class: 3 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 78

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 7 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 0 0 0 0 0 3 NNE 1 0 o o 0 0 1 NE 1 0 o 0 0 0 1 ENE 1 0 E 2 0 o 0 0 0 2 ESE 0 0 o 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 4 0 o 0 o 0 4 S 7 1 o 0 o 0 8 SSW 5 1 o o 0 0 6 SW 16 3 o 0 0 0 19 WSW 64 4 0 0 0 0 68 W 133 15 o o 0 0 148 WNW 37 8 o 0 0 0 45 NW 21 5 o 0 0 0 26 NNW 7 3 o 0 0 0 10 Variable 0 0 0 0 0 0 0 Total 302 40 0 0 0 0 342 Hours of calm in this stability class: 9 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 79

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October- December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Extremely Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total o 0 0 0 N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 s 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 NW 0 0 0 0 1 0 1 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 0 0 0 0 1 0 1 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: 5 80

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October- December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Moderately Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 NNE 0 NE 0 ENE 1 E 0 ESE 0 SE 0 SSE 0 S 0 SSW 2 SW 0 WSW 2 W 6 WNW 7 NW 16 NNW 0 Variable 0 Total 3 16 10 5 34 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: 5 81

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October- December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Slightly Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 NNE 0 0 0 NE 0 0 4 ENE 0 0 2 E 0 0 2 ESE 0 0 0 SE 1 0 1 SSE 2 1 3 S 4 5 9 SSW 2 0 3 SW 4 0 7 WSW 10 0 15 W 9 1 15 WNW 10 15 31 NW 9 10 23 NNW 0 2 6 Variable 0 0 0 Total 0 2 28 51 34 6 121 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: 5 82

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Neutral - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 5 26 11 31 16 89 NNE 1 6 23 15 18 10 73 NE 1 5 6 14 16 3 45 ENE 1 2 1 1 3 3 11 E 0 4 4 3 0 0 ESE 1 2 3 2 0 0 8 SE 0 4 11 2 2 0 19 SSE 0 2 6 15 21 3 47 S 1 1 2 8 5 2 19 SSW 1 7 7 12 11 6 44 SW 0 4 17 19 6 1 47 WSW 1 4 9 25 7 0 46 W 0 4 25 23 14 2 68 WNW 0 4 19 29 43 16 ill NW 0 5 15 48 60 9 137 NNW 0 3 21 2 12 14 52 Variable 0 0 0 0 0 0 0 Total 7 62 195 229 249 85 827 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: 5 83

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Slightly Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 22 19 1 0 46 NNE 10 13 0 0 32 NE 13 16 2 1 36 ENE 2 10 6 0 23 E 4 1 2 0 10 ESE 1 0 1 0 5 SE 5 8 0 2 16 SSE 4 12 16 3 36 S 9 5 19 1 38 SSW 4 25 38 7 77 SW 4 16 38 10 69 WSW 5 17 19 1 45 W 12 28 22 1 68 WNW 7 38 55 6 107 NW 6 32 39 3 81 NNW 8 14 5 0 31 Variable 0 0 0 0 0 Total 11 41 116 254 263 35 720 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 5 84

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October - December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Moderately Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 19 6 33 NNE 5 0 8 NE 3 0 ENE 1 0 4 E 1 0 5 ESE 0 0 2 SE 4 0 9 SSE 1 1 6 S 2 1 4 SSW 5 3 10 SW 2 20 25 WSW 5 10 25 W 12 16 35 WNW 14 31 56 NW 12 19 42 NNW 7 1 12 Variable 0 0 0 Total 2 16 52 93 108 16 287 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: 5 85

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 8 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, October- December, 2014 Oyster Creek Alpha Period of Record: October - December 2014 Stability Class - Extremely Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 1 21 NNE 0 3 6 NE 0 0 3 ENE 0 0 0 E 0 0 0 ESE 0 0 3 SE 10 2 23 SSE 2 0 10 S 1 1 7 SSW 3 4 13 SW 8 4 16 WSW 5 0 9 W 6 4 13 WNW 10 7 26 NW 15 18 39 NNW 10 4 23 Variable 0 0 0 Total 9 29 34 81 48 11 212 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: 5 86

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - All Stabilities - 15OFt-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 3 45 34 39 91 44 53 4 0 0 313 NNE 3 20 29 40 77 49 30 9 0 0 257 NE 2 28 49 85 162 104 46 4 3 0 483 ENE 1 23 24 36 148 140 80 22 18 0 492 E 1 13 20 25 76 48 12 10 2 0 207 ESE 2 9 18 24 76 48 3 3 0 0 183 SE 1 13 22 29 127 108 36 6 3 0 345 SSE 5 26 32 31 87 93 65 21 11 0 371 S 2 38 46 64 133 94 99 83 34 0 597 SSW 1 40 55 44 146 117 63 64 60 0 594 SW 4 67 76 65 160 88 21 5 2 0 488 WSW 5 142 228 139 157 83 31 6 2 0 793 W 0 234 331 147 160 93 44 25 16 0 1050 WNW 3 135 163 120 234 144 104 65 48 0 1016 NW 4 88 163 140 180 203 116 49 36 0 979 NNW 4 46 80 95 139 83 69 18 1 0 535 Tot 41 967 1370 1123 2153 1539 872 394 236 0 8703 Hours of Calm ........ 45 Hours of Variable Direction 2 Hours of Valid Data . . .. 8750 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 87

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Extremely Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in m/s)

Wind Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 0 13 6 1 0 0 20 NNE 0 0 0 1 8 0 1 0 0 10 NE 0 0 0 4 21 19 11 1 0 56 ENE 0 0 0 2 41 50 21 5 0 119 E 0 0 1 2 31 27 0 0 0 61 ESE 0 0 0 1 39 36 1 0 0 77 SE 0 0 0 0 23 67 20 0 0 110 SSE 0 0 0 0 4 38 26 7 0 75 S 0 0 0 2 1 18 44 46 21 132 SSW 0 0 0 0 13 17 8 10 8 59 Sw 0 0 0 0 16 24 12 3 0 55 WSW 0 0 0 0 14 23 19 3 2 61 W 0 0 0 1 16 42 20 8 8 95 WNW 0 0 0 1 8 43 35 27 24 138 NW 0 0 0 0 26 71 49 21 21 188 NNW 0 0 0 0 15 29 15 4 0 63 Tot 0 0 1 14 289 510 283 135 84 3 0 1319 Hours of Calm 00.......

Hours of Variable Direction 0 Hours of Valid Data . ... 1319 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 88

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Moderately Unstable - 15OFt-33Ft Delta-T (F)

Winds Measured at 33 Feet Wii-id Wind Speed (in m/s)

Di]rection 0.5- 1.1- 1 .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Secctor <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 4 9 2 4 0 0 0 0 19 NN 0 0 1 4 12 0 0 0 0 0 0 17 NE 0 0 1 4 16 7 2 0 0 0 0 30 ENE 0 0 0 3 19 9 7 1 4 0 0 43 E 0 0 0 4 9 3 0 0 0 0 0 16 ESE 0 0 1 3 12 1 0 0 0 0 0 17 SE 0 0 0 1 27 6 1 0 0 0 46 SSE 0 0 0 0 6 7 7 1 1 0 0 22 S 0 0 0 1 6 12 13 10 1 0 0 43 SSW 0 0 0 3 4 8 5 4 3 0 0 27 SW 0 0 0 3 9 9 1 0 1 0 0 23 WSW 0 0 1 4 10 16 2 2 0 0 0 35 W 0 0 0 6 9 10 9 1 5 0 0 40 WNW 0 0 0 2 21 11 15 4 3 0 0 56 NW 0 0 0 3 18 11 14 7 2 0 0 55 NNW 0 0 0 4 27 2 2 0 0 0 0 35 Tot 0 0 4 49 214 119 87 31 20 0 0 524 Hours of Calm ........ 0 Hours of Variable Direction 0 Hours of Valid Data . ... 524 Hours of Missing Data . 10 Hours in Period ... ...... 8760 89

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Slightly Unstable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 2 4 12 NNE 0 0 3 2 1 7 NE 0 0 0 8 8 17 ENE 0 0 0 2 9 17 E 0 0 1 1 4 6 ESE 0 0 0 1 3 6 SE 0 0 1 1 10 17 SSE 0 0 0 0 3 14 S 0 0 1 1 3 22 SSW 0 0 0 1 2 13 SW 0 o I 3 6 11 WSW 0 0 1 4 4 6 0 0 0 0 0 15 W 0 0 0 1 4 3 2 3 1 0 0 14 WNW 0 0 1 6 10 7 5 6 2 0 0 37 NW 0 0 0 2 5 7 3 1 4 0 0 22 NNW 0 0 2 7 1 1 0 1 0 0 13 Tot 0 0 10 37 83 49 35 19 10 0 0 243 Hours of Calm ..... ........ 0 Hours of Variable Direction 0 Hours of Valid Data . . .. 243 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 90

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Neutral - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wirid Wind Speed (in m/s) rection 0.5- 1.1- 1 Dii .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sec-tor <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 1 5 7 12 39 26 32 4 0 0 0 126 NN 2 0 12 21 41 44 28 9 0 0 0 157 NE 0 2 18 28 76 57 30 1 3 0 0 215 ENE 0 5 7 16 49 61 34 13 13 0 0 198 E 0 1 2 12 22 13 8 4 2 0 0 64 ESE 0 3 9 8 15 7 1 3 0 0 0 46 SE 0 0 4 11 35 11 7 4 1 0 0 73 SSE 0 1 4 10 45 16 21 7 8 0 0 112 S 0 3 4 6 42 31 19 13 6 4 0 128 SSW 0 1 4 5 19 25 18 18 35 1 0 126 SW 0 2 4 8 29 17 5 1 1 0 0 67 WSW 0 2 10 18 30 24 5 1 0 0 0 90 W 0 1 12 9 34 27 12 9 2 0 0 106 WNW 0 6 8 15 48 33 28 22 18 0 0 178 NW 0 2 12 27 60 65 31 14 9 0 0 220 NNW 0 2 15 32 45 36 33 9 0 0 0 172 Tot 3 36 132 238 629 493 312 132 98 5 0 2078 Hours of Calm ........ 1 Hours of Variable Direction 0 Hours of Valid Data .... 2079 Hours of Missing Data . 10 Hours in Period .......... 8760 91

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Slightly Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 16 16 19 26 8 12 0 0 0 97 NNE 0 11 9 10 12 5 0 0 0 0 47 NE 1 15 25 40 39 21 2 2 0 0 145 ENE 0 13 10 12 28 20 14 2 0 0 99 E 1 7 10 5 8 5 4 6 0 0 46 ESE 0 1 6 11 7 2 1 0 0 0 28 SE 1 5 10 13 29 16 1 1 2 0 78 SSE 0 12 19 19 29 25 9 4 2 0 119 S 0 11 24 45 79 25 16 12 6 0 218 SSW 0 11 25 27 96 65 29 28 13 0 294 SW 0 11 25 26 89 37 3 1 0 0 192 WSW 0 9 40 44 80 14 5 0 0 0 192 W 0 12 31 42 73 11 1 4 0 0 174 WNW 0 11 32 37 115 49 21 6 1 0 272 NW 0 16 36 46 62 49 19 6 0 0 234 NNW 1 21 19 34 44 15 18 5 0 0 157 Tot 4 182 337 430 816 367 155 77 24 0 2392 Hours of Calm ... ....... 4 Hours of Variable Direction 1 Hours of Valid Data . . .. 2397 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 92

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Moderately Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Wind Speed (in m/s) 0.5- 1.1- 1 Direction .6 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 1 17 9 2 0 29 NNE 0 4 4 2 0 10 NE 1 3 5 1 2 12 ENE 0 2 4 1 2 9 E 0 2 3 1 2 8 ESE 1 2 1 0 0 4 SE 0 4 7 1 2 14 SSE 2 4 9 2 0 17 S 0 8 12 5 2 27 SSW 0 10 13 8 11 42 SW 0 15 19 19 11 64 WSW 0 22 34 37 18 ill W 0 18 57 35 21 131 WNW 1 11 39 35 31 117 NW D 6 38 30 7 81 NNW 0 6 22 13 1 42 Tot 6 134 276 19 2 110 718 Hours o0f Calm ... ........ 5 Hours off Variable Direction 0 Hours olf Valid Data . ... 723 Hours o0f Missing Data . 10 Hours irn Period ... ...... 8760 93

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 9 Wind Speed by Direction Measured at 33 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Extremely Stable - 150Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wir nd Wind Speed (in m/s)

Di:rection 0.5- 1.1- 1 .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Se ctor <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 1 7 2 0 0 0 0 0 10 NN] E 1 5 0 0 3 0 0 0 9 NE 0 8 0 0 0 0 0 0 8 EN]E 1 3 3 0 0 0 0 0 7 E 0 3 3 0 0 0 0 0 6 ES] 1 3 1 0 0 0 0 0 5 SE 0 4 0 2 1 0 0 0 7 SSE 3 9 0 0 0 0 0 0 12 S 2 16 5 4 0 0 0 0 27 SSý 1 18 13 0 1 0 0 0 33 SW 4 39 27 6 0 0 0 0 76 WS' 5 109 142 32 1 0 0 0 289 W 0 203 231 53 3 0 0 0 490 WNW 2 107 83 24 1 0 0 0 218 NW 4 64 77 32 2 0 0 0 179 NNW 3 17 23 10 0 0 0 0 53 Tot 28 615 610 163 12 0 0 0 1429 Hours of Calm ........ 35 Hours of Variable Direction 1 Hours of Valid Data . ... 1465 Hours of Missing Data . 10 Hours in Period ... ...... 8760 94

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - All Stabilities - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 2 6 7 25 34 62 80 127 77 57 477 NNE 0 1 6 9 40 54 43 61 85 48 22 369 NE 0 2 6 13 53 75 78 96 107 65 40 535 ENE 1 5 5 6 32 56 59 78 122 89 88 541 E 0 3 8 13 33 48 59 20 20 25 26 255 ESE 0 4 5 10 37 60 38 21 15 4 6 200 SE 0 5 12 7 37 69 86 51 68 13 10 358 SSE 0 3 4 6 30 63 74 54 59 54 52 399 S 0 1 6 7 32 55 61 108 145 78 32 525 SSW 0 4 7 6 21 38 64 108 226 168 147 789 SW 0 0 1 7 23 41 65 88 135 131 74 565 WSW 0 1 6 10 37 38 46 86 149 112 75 560 W 0 1 2 5 29 40 43 96 184 126 76 602 WNW 0 2 1 3 22 30 62 81 233 242 221 897 NW 1 5 5 6 34 57 74 106 289 300 186 1063 NNW 0 3 5 6 30 57 63 60 173 136 76 609 Tot 2 42 85 121 515 815 977 1194 2137 1668 1188 8744 Hours of Calm 66.......

Hours of Variable Direction 0 Hours of Valid Data . . .. 8750 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 95

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Extremely Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wirnd Wind Speed (in m/s) 7ection 0.5- 1.1- 1 Dir .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sec$tor <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 4 1 7 ENE 0 0 0 5 2 0 10 E 0 0 0 0 0 0 3 ESE 0 0 0 0 0 0 2 SE 0 0 0 0 0 0 3 SSE 0 0 0 2 0 0 2 S 0 0 0 13 13 0 30 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 1 1 4 W 0 0 0 2 2 1 5 WNW 0 0 0 4 4 10 18 15 4 13 35 NW 0 0 0 NNW 0 0 0 4 2 0 6 Tot 0 0 0 1 8 13 45 32 26 125 Hours of Calm ... ........ 0 Hours of Variable Direction 0 Hours of Valid Data . ... 125 Hours of Missing Data . 10 Hours in Period ... ...... 8760 96

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at-380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Moderately Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 0 1 0 4 0 0 5 NNE 0 0 0 0 1 0 0 1 0 2 NE 0 0 0 0 1 10 2 4 1 18 ENE 0 0 0 2 12 10 2 9 2 37 E 0 0 0 2 11 1 0 0 0 14 ESE 0 0 0 7 10 3 0 0 0 20 SE 0 0 0 3 14 7 2 0 0 26 SSE 0 0 0 0 4 5 6 0 0 15 S 0 0 0 0 1 7 17 9 0 34 SSW 0 0 0 0 1 2 8 5 .7 23 SW 0 0 0 1 2 6 6 5 0 20 WSW 0 0 0 0 1 3 7 6 2 19 w 0 0 0 0 1 2 7 3 6 19 WNW 0 0 0 0 0 6 11 7 10 34 NW 0 0 0 0 2 8 34 14 15 73 NNW 0 0 0 0 2 7 5 5 1 20 Tot 0 0 0 15 64 77 111 68 44 379 Hours of Calm ........ 0 Hours of Variable Direction 0 Hours of Valid Data . ... 379 Hours of Missing Data . 10 Hours in Period ... ...... 8760 97

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Slightly Unstable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1 .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 0 0 2 6 2 1 0 0 11 NNE 0 0 0 3 3 3 0 1 0 0 10 NE 0 0 0 3 9 14 11 3 2 0 42 ENE 0 0 0 3 15 15 15 6 4 1 59 E 0 0 0 1 11 11 1 0 0 0 24 ESE 0 0 0 4 13 9 1 0 0 0 27 SE 0 0 1 3 6 19 8 3 0 0 40 SSE 0 0 0 3 0 14 13 8 1 0 39 S 0 0 0 0 0 3 8 19 9 0 39 SSW 0 0 0 0 2 6 8 8 5 7 36 SW 0 0 0 1 5 11 4 8 0 0 29 WSW 0 0 0 1 0 6 8 15 3 0 33 W 0 0 0 1 4 2 14 23 8 7 59 WNW 0 0 0 1 1 9 9 22 15 23 80 NW 0 0 0 0 6 17 16 24 14 16 93 NNW 0 0 0 0 8 4 10 10 3 3 38 Tot 0 0 1 24 85 149 128 151 64 57 659 Hours of Calm. ....... 0 Hours of Variable Direction 0 Hours of Valid Data .... 659 Hours of Missing Data . 10 Hours in Period ... ...... 8760 98

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Neutral - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0. 550 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 1 2 10 19 28 35 24 32 42 193 NNE 0 1 2 5 18 23 22 36 49 38 22 216 NE 0 1 2 4 32 40 34 51 73 48 30 315 ENE 0 0 1 2 16 26 16 35 74 60 75 305 E 0 0 0 7 18 25 17 9 13 21 24 134 ESE 0 0 1 7 19 26 12 9 8 2 3 87 SE 0 2 4 2 16 35 24 15 30 8 3 139 SSE 0 0 1 2 10 31 34 18 26 24 18 164 S 0 0 1 1 9 20 34 48 47 12 183 SSW 0 1 1 2 9 15 19 35 70 53 79 284 SW 0 0 1 3 9 13 22 39 28 15 6 136 WSW 0 0 1 3 20 12 14 28 36 25 4 143 W 0 0 1 3 14 16 24 32 48 29 27 194 WNW 0 0 0 3 10 17 27 30 57 54 91 289 NW 0 0 1 4 17 32 25 42 62 96 73 352 NNW 0 1 2 4 16 25 36 19 49 34 53 239 Tot 0 6 20 54 243 375 388 481 694 551 561 3373 Hours of Calm 0 Hours of Variable Direction 0 Hours of Valid Data . . .. 3373 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 99

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Slightly Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Wind Speed (in m/s)

Direction 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 0 3 2 4 8 12 22 25 8 0 84 NNE 0 0 1 2 10 16 7 14 20 1 0 71 NE 0 0 0 3 11 12 15 15 16 6 8 86 ENE 1 3 1 2 4 5 6 11 30 12 10 85 E 0 0 0 1 6 7 13 7 5 4 2 45 ESE 0 1 1 1 6 12 4 5 4 2 3 39 SE 0 0 1 3 5 10 18 8 18 2 7 72 SSE 0 0 1 1 3 14 10 11 14 24 28 106 S 0 0 2 3 10 17 14 24 34 25 18 147 SSW 0 1 3 1 3 10 20 40 110 89 52 329 SW 0 0 0 0 5 6 19 23 56 76 43 228 WSW 0 1 1 3 3 6 7 22 45 37 30 155 W 0 0 1 0 6 7 9 21 61 48 7 160 WNW 0 0 0 0 7 5 11 14 78 100 43 258 NW 0 1 1 1 4 5 5 18 80 96 28 239 NNW 0 0 1 1 7 9 10 8 45 28 3 112 Tot 1 7 17 24 94 149 180 263 641 558 282 2216 Hours of Calm ... ........ 1 Hours of Variable Direction 0 Hours of Valid Data . . .. 2217 Hours of Missing Data . . 10 Hours in Period ...... .. 8760 100

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Moderately Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Win nd Wind Speed (in m/s)

Dir rection 0.5- 1.1- 1 .6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Secctor <0.50 1 1.5 2 3 4 5 6 8 10 >10.00 Total N 0 1 0 0 8 12 38 22 11 95 NNE 0 0 1 0 4 8 7 0 0 22 NE 0 1 0 1 9 3 5 0 0 29 ENE 0 1 1 1 7 4 5 1 0 27 E 0 1 2 3 5 1 1 0 0 16 ESE 0 0 1 1 2 2 3 0 0 14 SE 0 1 3 1 3 5 8 1 0 31 SSE 0 1 1 2 7 5 0 2 4 29 S 0 1 1 1 5 9 11 8 1 51 SSW 0 1 1 0 11 7 16 10 1 57 SW 0 0 0 4 6 9 17 24 16 89 WSW 0 0 2 4 9 7 29 26 28 119 W 0 1 0 1 5 14 31 26 18 105 WNW 0 0 0 0 8 12 35 50 32 143 NW 0 1 1 0 12 13 41 53 28 156 NNV 0 1 0 0 4 5 22 39 11 92 Tot 0 11 14 19 81 105 116 269 262 150 1075 Hours of Calm 2 Hours of Variable Direction 0 Hours of Valid Data . ... 1077 Hours of Missing Data . 10 Hours in Period ... ...... 8760 101

Oyster Creek 2014 Annual Radioactive Effluent Release Report Table D - 10 Wind Speed by Direction Measured at 380 Feet for various Stability Classes for the Oyster Creek Generating Station, January - December, 2014 Oyster Creek Alpha Period of Record: January - December 2014 Stability Class - Extremely Stable - 380Ft-33Ft Delta-T (F)

Winds Measured at 380 Feet Wind Speed (in m/s)

Wind 0.5- 1.1-Direction 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1-Sector <0.50 1 1.5 2 3 4 5 6 8 10 >10. 00 Total N 0 1 2 3 8 5 7 9 35 15 4 89 NNE 0 0 2 2 9 10 6 3 8 8 0 48 NE 0 0 4 5 5 6 5 4 8 1 0 38 ENE 0 1 2 1 8 2 2 1 0 1 0 18 E 0 2 6 2 7 0 0 1 1 0 0 19 ESE 0 3 2 1 5 0 0 0 0 0 0 11 SE 0 2 3 1 9 10 7 6 7 2 0 47 SSE 0 2 1 1 11 14 5 2 3 3 2 44 S 0 0 2 2 8 9 4 8 4 2 2 41 3 4 6 7 16 14 6 1 60 SSW 0 1 2 SW 0 0 0 0 3 8 5 7 20 11 9 63 WSW 0 0 2 0 8 11 7 18 17 14 10 87 W 0 0 0 1 4 8 2 13 12 10 10 60 WNW 0 2 1 0 2 3 7 10 26 12 12 75 NW 1 3 2 1 11 9 12 7 33 23 13 115 NNW 0 1 2 1 4 8 7 11 38 25 5 102 Tot 1 18 33 24 106 109 83 116 226 133 68 917 Hours of Calm ......... 3 Hours of Variable Directi on 0 Hours of Valid Data . . . 920 Hours of Missing Data . . 10 Hours in Period .......... 8760 102

Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix E ODCM Revisions See attached copy of CY-OC-1 70-301 Revision 6 103

Oyster Creek 2014 Annual Radioactive Effluent Release Report Appendix F ERRATA 104

Oyster Creek 2014 Annual Radioactive Effluent Release Report Corrections to 2013 ARERR

1. A Program Deviation was not reported as required in the 2013 Annual Radiological Effluent release Report in Section J. Program Deviations. A turbine building (TB) effluent noble gas grab sample was not collected for July 2013.

2. A Program Deviation was not reported as required in the 2013 Annual Radiological Effluent release Report in Section J. Program Deviations. The New Radwaste/Augmented Offgas Service Water Effluent sample was not obtained January 1, 2013 through December 31, 2013.

3. An abnormal release was discovered in 2014 after the 2013 ARERR was submitted that was determined to impact the 2013 ARERR. There were multiple pages impacted by this abnormal release and all of the pages are included in this errata section.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2013 through December 31, 2013 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16 106

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report H. Radiation Effluent Monitors Out of Service More Than 30 Days Per ODCM Control 3.3.3.10, "Radioactive Liquid Effluent Monitoring Instrumentation" and 3.3.3.11, "Radioactive Gaseous Effluent Monitoring Instrumentation" requires:

With less than the minimum number of radioactive liquid/gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The following is a discussion of instrumentation out of service for greater than 30 days:

1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitor was out of service from 5/20/2013 through 8/9/2013. The monitor was taken out of service 5/20/2013 for failing the monitor functional test. The original issue for the monitor failing the functional test was a faulty pushbutton on the alarm panel causing the alarm not to function. Parts were ordered and replaced on 6/18/2013 but the alarm still did not function as expected. After multiple troubleshooting attempts it was determined that the annunciator window card wiring was the issue. After changing the wiring in the alarm panel, all alarms responded as expected. The functional test was reperformed 8/9/2013 satisfactorily and the monitor was returned to service. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process. All ODCM required compensatory measures were met.

1. Releases from the Independent Spent Fuel Storage Facility:

The ISFSI is a closed system and the only exposure would be due to direct radiation. This includes iodines, particulates, and noble gases. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive material was released.

J. Program Deviations:

1. The groundwater remediation composite sampler was found with no composite collected on December 27, 2013. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.

A manual sample was obtained per SP 10-003. Operations department was notified that composite sampler was not working and Operations secured discharging from W-73 and Chemistry secured the composite sampler. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report H. Radiation Effluent Monitors Out of Service More Than 30 Days Per ODCM Control 3.3.3.10, "Radioactive Liquid Effluent Monitoring Instrumentation" and 3.3.3.11, Radioactive Gaseous Effluent Monitoring Instrumentation requires:

With less than the minimum number of radioactive liquid/gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.10-1/3.3.3.11-1. Make every reasonable effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The following is a discussion of instrumentation out of service for greater than 30 days:

1. The Offgas Building Exhaust Gaseous Effluent Radioactive Noble Gas Monitor was out of service from 5/20/2013 through 8/9/2013. The monitor was taken out of service 5/20/2013 for failing the monitor functional test The original issue for the monitor failing the functional test was a faulty pushbutton on the alarm panel causing the alarm not to function. Parts were ordered and replaced on 6/18/2013 but the alarm still did not function as expected. After multiple troubleshooting attempts it was determined that the annunciator window card wiring was the issue. After changing the wiring in the alarm panel, all alarms responded as expected. The functional test was reperformed 8/9/2013 satisfactorily and the monitor was returned to service. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process. All ODCM required compensatory measures were met.

I. Releases from the Independent Spent Fuel Storage Facility:

The ISFSI is a closed system and the only exposure would be due to direct radiation. This includes iodines, particulates, and noble gases. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive material was released.

J. Program Deviations:

1. The groundwater remediation composite sampler was found with no composite collected on December 27, 2013. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program.

A manual sample was obtained per SP 10-003. Operations department was notified that composite sampler was not working and Operations secured discharging from W-73 and Chemistry secured the composite sampler. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

2. A turbine building (TB) effluent noble gas grab sample was not collected for July 2013. This sample is a requirement of Table 4.11.2.1.2-1, Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-170-301, ODCM for Oyster Creek. The July sample was originally scheduled to be collected 7/5/13, but was rescheduled to occur the following week so it could be collected in July. The 108

Oyster Creek 2014 Annual Radioactive Effluent Release Report sample was not rescheduled and tracked by the Chemistry Supervisor adequately, and a sample was not collected until the scheduled August sample 8/1113. Historical data from July's TB RAGEMS low range monitor was trended against the data from June and August with no discrepancies noted. There were no isotopes identified in the Noble Gas Grab Samples from June and August.

This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

3. The New Radwaste (NRVV)/Augmented Offgas (AOG) Service Water Effluent sample was not collected January 1, 2013 through December 31, 2013. The New Radwaste/Augmented Offgas Service Water Effluent sample was required by CY-OC-170-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10.

At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters.

AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system sampling is still performed quarterly for gamma emitters. The potential pathway for a release from NRW/AOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the Service Water side of the heat exchanger. The system is designed to maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would develop in the heat exchanger itwould be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

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Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report EXECUTIVE

SUMMARY

Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for the effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

Both radiological environmental and effluent monitoring indicate that the operation of Oyster Creek Generating Station (OCGS) does not result in significant radiation exposure to the people or the environment surrounding OCGS and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

There were liquid radioactive effluent releases during 2013 of concentrations of tritium too low to detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution Discharge Elimination System (NJPDES) permitted main condenser outfall. The releases were part of nearly continuous pumping of groundwater at approximately 70 gpm containing low levels of tritium and no detectable gamma. Exelon and the State of New Jersey Department of Environmental Protection (NJDEP) agreed to this remediation action instead of natural attenuation to address concentrations of tritium in groundwater. Well 73 and supporting equipment and piping were installed to pump groundwater to the intake structure at the inlet of the main circulating water pumps. Provisions were established for both batch and continuous releases of groundwater. Continuous releases occurred approximately 361 days in 2013. The Continuous releases occurred from January 1, 2013 through December 27, 2013 with a total of 3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to the discharge canal. The dose to the most limiting member of the public due to the release of groundwater was 1.37E-06 mrem.

There were no liquid abnormal releases during 2013.

There was one gaseous abnormal release during 2013. During the annual inspection of the Old Radwaste Building exhaust fan connections to the main stack it was discovered that there were three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in the connection of exhaust fan EF-1 -17.

The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), and particulates to any individual due to gaseous effluents was 4.93E-01 mrem, which was approximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dose from gaseous effluents was due to C-14. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02 percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limit of 10 mrad.

For comparison, the background radiation dose averages approximately 300 mrem per year in the Central New Jersey area, which includes approximately 200 mrem from naturally occurring radon gas and 100 mrem from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only 110

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report EXECUTIVE

SUMMARY

Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for the effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

Both radiological environmental and effluent monitoring indicate that the operation of Oyster Creek Generating Station (OCGS) does not result in significant radiation exposure to the people or the environment surrounding OCGS and is well below the applicable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

There were liquid radioactive effluent releases during 2013 of concentrations of tritium too low to detect at an LLD of 200 picocuries per liter (pCi/L) at the New Jersey Pollution Discharge Elimination System (NJPDES) permitted main condenser outfall. The releases were part of nearly continuous pumping of groundwater at approximately 70 gpm containing low levels of tritium and no detectable gamma. Exelon and the State of New Jersey Department of Environmental Protection (NJDEP) agreed to this remediation action instead of natural attenuation to address concentrations of tritium in groundwater. Well 73 and supporting equipment and piping were installed to pump groundwater to the intake structure at the inlet of the main circulating water pumps. Provisions were established for both batch and continuous releases of groundwater. Continuous releases occurred approximately 361 days in 2013. The Continuous releases occurred from January 1, 2013 through December 27, 2013 with a total of 3.50E+07 gallons of groundwater pumped resulting in 2.82E-01 Ci of tritium released to the discharge canal. The dose to the most limiting member of the public due to the release of groundwater was 1.37E-06 mrem.

There were no liquid abnormal releases during 2013.

There were two gaseous abnormal releases during 2013. During the annual inspection of the Old Radwaste Building exhaust fan connections to the main stack it was discovered that there were three slits in the top boot connection of exhaust fan EF-1-16 and a bolt missing in the connection of exhaust fan EF-1-17. During maintenance of the New Radwaste Building exhaust fan HV-S-54A, two slits were identified in the expansion joint and repaired.

The maximum calculated organ dose (Bone) from iodines, tritium, carbon-14 (C-14), and particulates to any individual due to gaseous effluents was 4.94E-01 mrem, which was approximately 3.29E+00 percent of the annual limit of 15 mrem. The majority of organ dose from gaseous effluents was due to C-14. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 3.60E-03 mrad, which was 3.60E-02 percent of the annual 10 CFR 50 Appendix I, As Low As Reasonably Achievable (ALARA) limit of 10 mrad.

For comparison, the background radiation dose averages approximately 300 mrem per year in the Central New Jersey area, which includes approximately 200 mrem from naturally occurring radon gas and 100 mrem from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only 111

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report exposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive material was released.

Comparison of environmental sampling results to iodine and particulate gaseous effluents released, showed no radioactivity attributable to the operation of OCGS. Both elevated and ground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.82E-02 Ci.

Joint Frequency Tables of meteorological data, per Stability Classification Category, as well as for all stability classes, are included. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.

112

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report exposure is due to direct radiation. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mrem for 2013. Because it is a sealed unit, no radioactive material was released.

Comparison of environmental sampling results to iodine and particulate gaseous effluents released, showed no radioactivity attributable to the operation of OCGS. Both elevated and ground-level release paths were considered in this review, with total iodines released of 3.12E-03 Ci and total particulates with half-lives greater than 8 days less C-14 released of 3.84E-02 Ci.

Joint Frequency Tables of meteorological data, per Stability Classification Category, as well as for all stability classes, are included. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 99.4 percent and 99.4 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.

113

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report E. Batch Releases:

1. Liqu There were no batch releases of liquid effluents during 2013.

2. Gaseous There were no batch releases of gaseous effluents during 2013.

F. Abnormal Releases:

There were no abnormal liquid releases during 2013.

There was one abnormal gaseous release during 2013. During the performance of Work Order R2205683, which is to perform an annual inspection of the stack pad exhaust fans, three slits were discovered in the top boot of exhaust fan EF-1-16 and a bolt was missing from exhaust fan EF-1-17. These are the two exhaust fans for the Old Radwaste Building to the Main Stack. One of these two exhaust fans is in operation at all times to maintain a negative pressure in the Old Radwaste Building.

At no times do both of these fans run simultaneously as each fans is designed to provide 100% of the required flow. Engineering performed a calculation to determine a release rate that encompasses the maximum release rate regardless of which exhaust fan is in service. The activity to inspect the exhaust fans is an annual activity.

The following assumptions were made when calculating Curies released and dose:

Both exhaust fans have been leaking since the date of the last inspection until the time of the last repair, 7/29/12 through 7/25/13.

" All of the activity due to particulates reported from the Main Stack was coming from the Old Radwaste Building and therefore being released as a groundlevel release from the exhaust fan leaks at the flow rate calculated by Engineering.

Units Quarter Quarter Quarter Quarter 4 1 2 3 Total Release Ci 4.94E-05 5.OOE-05 1.37E-05 O.OOE+00 G. Revisions to the ODCM:

There were no revisions to the ODCM during 2013.

114

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report E. Batch Releases:

1. Liu There were no batch releases of liquid effluents during 2013.

2. Gaseous There were no batch releases of gaseous effluents during 2013.

F. Abnormal Releases:

There were no abnormal liquid releases during 2013.

There were two abnormal gaseous releases during 2013.

During the performance of Work Order R2205683, which is to perform an annual inspection of the stack pad exhaust fans, three slits were discovered in the top boot of exhaust fan EF-1 -16 and a bolt was missing from exhaust fan EF-1 -17. These are the two exhaust fans for the Old Radwaste Building to the Main Stack. One of these two exhaust fans is in operation at all times to maintain a negative pressure in the Old Radwaste Building. At no times do both of these fans run simultaneously as each fans is designed to provide 100% of the required flow. Engineering performed a calculation to determine a release rate that encompasses the maximum release rate regardless of which exhaust fan is in service. The activity to inspect the exhaust fans is an annual activity.

The following assumptions were made when calculating Curies released and dose:

Both exhaust fans have been leaking since the date of the last inspection until the time of the last repair, 7/29/12 through 7/25/13.

" All of the activity due to particulates reported from the Main Stack was coming from the Old Radwaste Building and therefore being released as a ground level release from the exhaust fan leaks at the flow rate calculated by Engineering.

Units Quarter 11 1 Quarter 22 1 Quarter 33 Quarter 4 Total Release Ci 4.94E-05 5.OOE-05 I 1.37E-05 O.00E+O0 During the performance of Work Order R2227008, which is to perform an annual inspection of the New Radwaste (NRW) exhaust fan HV-S-54A, two slits were discovered in the expansion joint. This is one of the exhaust fans for the New Radwaste Building to the Main Stack. Note that the exhaust from HV-S-54A is normally to the atmosphere but through the monitored stack effluent release point.

Engineering performed a calculation to determine a release rate that encompasses the maximum release rate for both slits. The activity to inspect the exhaust fan is an annual activity.

The following assumptions were made when calculating Curies released and dose:

115

Oyster Creek 2014 Annual Radioactive Effluent Release Report

" The exhaust fan has been leaking since the date of the last inspection until the time of the repair, 8/20/13 through 7/25/14.

All of the activity due to particulates reported from the Main Stack was coming from the New Radwaste Building and therefore being released as a groundlevel release from the exhaust fan leaks at the flow rate calculated by Engineering.

" HV-S-54A was in operation the entire time since the last inspection was performed.

Units Quarter Quarter Quarter Quarter4 1 2 3 Total Release Ci 0.000e 0.OOeO 4.08E-05 9.00E-05 G. Revisions to the ODCM:

There were no revisions to the ODCM during 2013.

116

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Table A-I: Gaseous Effluents- Summary Of All Releases Period: January 1, 2013 through December 31, 2013 Unit: Oyster Creek A. Fission &Activation Gases j Units Quarter I IQuarter 2 1Quarter IEst° 3 Quarter 4 Total Error %

=_. -

1. Total Release Ci 2.06E+01 1.40E+01 7.04E+00 I 8.02E+00 I 25.00% I

2. Average Release Rate for Period SULdI MWVOWC I %A I 0.10UU U.,*r-VwU I.or-w ;.Oe'I-U

12. Average Release Rate for Period IuCi/sec 1 1.12E+00 I 8.14E-01 4.90E-01 I 7.32E-01

12. Percent of ODCM Limit

ODCM Limit is for combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.

117

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Table A-I: Gaseous Effluents - Summary Of All Releases Period: January 1, 2013 through December 31, 2013 Unit: Oyster Creek Y I I -

ESt. Iola, A. Fission & Activation Gases Quarter 4 Error %

'. aI I L".J JD= I ,,,,5,,, I j.wJL_--, I ,

2. Percent of ODCM Limit I % 56.67E-01 1

ODCM Limit is fkr combined Iodine, tritium, Carbon-14 and particulate only, which is shown in Item G.

118

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Table A-3: Gaseous Effluent Release Point: Ground Level Releases Period: January 1, 2013 through December 31, 2013 Unit: Oyster Creek Nuclides Released Continuous Mode Batch Mode

1. Fission gasei Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 33m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-i 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

2. lodines 1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD

3. Particulates Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci 2.57E-07 2.59E-07 7.13E-08 <LLD <LLD <LLD <LLD <LLD Ba-140 Ci 2.62E-05 2.65E-05 7.28E-06 <LLD <LLD <LLD <LLD <LLD La-1 40 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci 5.30E-06 5.35E-06 1.47E-06 <LLD <LLD <LLD <LLD <LLD Mn-54 Ci 4.78E-06 5.64E-06 1.22E-06 1.80E-05 <LLD <LLD <LLD <LLD Co-58 Ci 3.86E-06 1.33E-05 4.02E-06 3.51 E-07 <LLD <LLD <LLD <LLD Co-60 Ci 1.17E-05 2.86E-05 1.69E-05 8.87E-05 <LLD <LLD <LLD <LLD Ni-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci 7.96E-07 8.05E-07 2.21E-07 <LLD <LLD <LLD <LLD <LLD Ag-1I0m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci 2.09E-06 2.11E-06 5.81E-07 <LLD <LLD <LLD <LLD <LLD Am-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 8.24E-05 8.26E-05 3.18E-05 1.07E-04 <LLD <LLD <LLD <LLD

4. Tritium H-3 Ci 2.88E-01 1.22E-01 2.93E-01 2.05E-01 <LLD <LLD <LLD I <LLD

5. Gross Alpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

6. Carbon-14 .....

C-14 Ci 7.40E-02 7.49E-02 I 7.57E-02 17.57E-02 <LLD <LLD <LLD <LLD 119

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Table A-3: Gaseous Effluent Release Point: Ground Level Releases Period: January 1, 2013 through December 31, 2013 Unit Oyster Creek Nuclides Released Continuous Mode Batch Mode

1. Fission gase Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Kr- 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr- 85m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-I 33 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

2. lodines 1-131 Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Pedod Ci 9.94E-08 <LLD 3.73E-08 8.18E-07 <LLD <LLD <LLD <LLD

3. Particulates -

Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-1 37 Ci 2.57E-07 2.59E-07 4.55E-07 8.47E-07 <LLD <LLD <LLD <LLD Ba-140 Ci 2.62E-05 2.65E-05 1.28E-05 1.22E-05 <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cr-51 Ci 5.30E-06 5.35E-06 4.58E-06 6.86E-06 <LLD <LLD <LLD <LLD Mn-54 Ci 4.78E-06 5.64E-06 4.94E-06 2.62E-05 <LLD <LLD <LLD <LLD Co-58 Ci 3.86E-06 1.33E-05 1.47E-05 2.38E-05 <LLD <LLD <LLD <LLD Co-60 Ci 1.17E-05 2.86E-05 2.93E-05 1.16E-04 <LLD <LLD <LLD <LLD Ni-63 Ci 2.74E-05 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci 7.96E-07 8.05E-07 125E-06 2.26E-06 <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci 2.09E-06 2.11 E-06 4.62E-06 8.90E-06 <LLD <LLD <LLD <LLD Am-241 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 8.24E-05 8.26E-05 7.26E-05 l1.97E-04 <LLD <LLD <LLD <LLD

4. Tritium L H-3 Ci 2.88E-01 1.22E-01 2.93E-01 2,05E-01 <LLD <LLD <LLD <LLD

5. Gross Alpha Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

6. Carbon-14 C-14 Ci 7.40E-02 7.49E-02 7.57E-02 7.57E-02 <LLD <LLD <LLD <LLD 120

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Location % of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters) (toward) Limit Limit Unit Gamma -

Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mrad Beta - Air Noble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mrad Total Body Noble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mrem Noble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mrem

Iodine, Particulate, Bone 4.93E-01 Child 937 SE 3.29E+00 15 mrem Carbon-14 &

Tritium Liquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mrem Liquid Organ 1.37E-06 All Bridge 1.37E-05 10 mrem Direct Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mrem Direct Radiation Total Body <LLD All 937 SE <LLD 25 mrem 40 CFR Part 190 Compliance Warehouse Worker Total Dose JTotal Body 5.39E+00 All 483 W 2.16E+01 25 mrem Total Dose Bone 5.50E+00 All 483 W 2.20E+01 J 25 mrem Total Dose Thyroid 5.39E+00 All 483 W 7.19E+00 1 75 mrem Nearest Resident Total Dose Total Dose Total Dose JTotal BodyJ 3.60E-03 Bone Thyroid 4.97E-01 3.60E-03 All All All 937 937 937 SE SE SE 1.44E-02 1.99E+00 4.80h-03 25 25 75 mrem mrem m

121

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2013 Annual Radioactive Effluent Release Report Location % of Applicable Estimated Age Distance Direction Applicable Effluent Organ Dose Group (meters) (toward) Limit Limit Unit Gamma -

Noble Gas Air Dose 3.60E-03 All 500 ESE 3.60E-02 10 mrad Beta - Air Noble Gas Dose 8.44E-04 All 500 ESE 4.22E-03 20 mrad Total Body Noble Gas (Gamma) 1.42E-03 All 937 SE 2.84E-02 5 mrem Noble Gas Skin (Beta) 1.77E-03 All 972 ESE 1.18E-02 15 mrem

Iodine, Particulate, Bone 4.94E-01 Child 937 SE 3.29E+00 15 mrem Carbon-14 &

Tritium Liquid Total body 1.37E-06 All South Route 9 4.57E-05 3 mrem Liquid Organ 1.37E-06 All Bridge 1.37E-05 10 mrem Direct Radiation Total Body 5.39E+00 All 483 W 2.16E+01 25 mrem Direct Radiation Total Body <LLD All 937 SE <LLD 25 mrem 40 CFR Part 190 Compliance Warehouse Worker Total Dose Total Body 5.39E+00 All 483 W 2.16E+01 25 mrem Total Dose Bone 5.50E+00 All 483 W 2.20E+01 25 mrem Total Dose Thyroid 5.39E+00 All 483 W 7.19E+00 75 mrem Nearest Resident Total Dose Total Body 3.60E-03 All 937 SE 1.44E-02 25 mrem Total Dose Bone 4.98E-01 All 937 SE 1.99E+00 25 mrem Total Dose Thyroid I3.E-03 All1 937 SE I4.80E-3 I7 mrem 122

Oyster Creek 2014 Annual Radioactive Effluent Release Report Corrections to 2012 ARERR

1. A Program Deviation was not reported as required in the 2012 Annual Radiological Effluent release Report in Section J. Program Deviations. The New Radwaste/Augmented Offgas Service Water Effluent sample was not obtained January 1, 2012 through December 31, 2012.

123

Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2012 through December 31, 2012 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16 124

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2012 Annual Radioactive Effluent Release Report J. Program Deviations:

1 A turbine building (TB) effluent noble gas grab sample was not collected for September 2012. This sample is a requirement of Table 4.11.2.1.2-1, Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-1 70-301, ODCM for Oyster Creek. The September sample was originally scheduled to be collected 8/31/12, but was rescheduled to occur the following week so it could be collected in September. The sample was not rescheduled and tracked by the Chemistry Supervisor adequately, and a sample was not collected until the scheduled October sample 10/5/12. Historical data from September's TB RAGEMS low range monitor was trended against the data from August and October with no discrepancies noted. There were no isotopes identified in the Noble Gas Grab Samples from August and October.

This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

2. The groundwater remediation composite sampler was found out of service for less than eight hours on October 19, 2012. The composite sampler is required by ODCM Table 4.11.1 .1 .1-1, Radioactive Liquid Waste Sampling and Analysis Program. There was enough sample in the composite sampler to perform the required analyses and the composite sampler was immediately returned to service. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

125

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2012 Annual Radioactive Effluent Release Report J. Program Deviations:

1. A turbine building (TB) effluent noble gas grab sample was not collected for September 2012. This sample is a requirement of Table 4.11.2.1.2-1, Radioactive Gaseous Waste Sampling and Analysis Program, of CY-OC-170-301, ODCM for Oyster Creek. The September sample was originally scheduled to be collected 8/31/12, but was rescheduled to occur the following week so it could be collected in September. The sample was not rescheduled and tracked by the Chemistry Supervisor adequately, and a sample was not collected until the scheduled October sample 10/5/12. Historical data from September's TB RAGEMS low range monitor was trended against the data from August and October with no discrepancies noted. There were no isotopes identified in the Noble Gas Grab Samples from August and October.

This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

2. The groundwater remediation composite sampler was found out of service for less than eight hours on October 19, 2012. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. There was enough sample in the composite sampler to perform the required analyses and the composite sampler was immediately returned to service. This issue was entered into our Corrective Action Program (CAP) and corrective actions taken have been documented per process.

3. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluent sample was not collected January 1, 2012 through December 31, 2012. The New Radwaste/Augmented Offgas Service Water Effluent sample was required by CY-OC-1 70-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE 80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system sampling is still performed quarterly for gamma emitters. The potential pathway for a release from NRWIAOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the Service Water side of the heat exchanger. The system is designed to 126

Oyster Creek 2014 Annual Radioactive Effluent Release Report maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would develop in the heat exchanger it would be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

127

Oyster Creek 2014 Annual Radioactive Effluent Release Report Corrections to 2011 ARERR

1. A Program Deviation was not reported as required in the 2011 Annual Radiological Effluent release Report in Section J. Program Deviations. The New Radwaste/Augmented Offgas Service Water Effluent sample was not obtained January 1,2011 through December 31, 2011.

128

Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2011 through December 31, 2011 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16 129

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2011 Annual Radioactive Effluent Release Report J. Program Deviations:

1. During Augmented Off Gas (AOG) sample line pressue testing conducted February 21, 2011, it was discovered that the sample line was not able to maintain pressure due to the filter assembly not being tight. The filter assembly was tightened and the pressure test was completed SAT. This issue was entered into our Corrective Action Program (CAP) and corrective actions implemented to ensure filter assemblies are tight when installed for sampling. The weekly sample results were evaluated against previous sample results for impact to sampling due to the assembly not being tight with no impact identified.

2. The groundwater remediation composite sampler was found out of service for less than one day on March 29, 2011. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. There was enough sample in the composite sampler to perform the required analyses and the composite sampler was immediately returned to service.

3. The groundwater remediation composite sampler was found out of service for for approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on August 21, 2011. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. The composite sampler was immediately returned to service and enough sample was collected in the composite sampler to perform the required analyses.

130

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2011 Annual Radioactive Effluent Release Report J. Program Deviations:

1. During Augmented Off Gas (AOG) sample line pressue testing conducted February 21, 2011, it was discovered that the sample line was not able to maintain pressure due to the filter assembly not being tight. The filter assembly was tightened and the pressure test was completed SAT. This issue was entered into our Corrective Action Program (CAP) and corrective actions implemented to ensure filter assemblies are tight when installed for sampling. The weekly sample results were evaluated against previous sample results for impact to sampling due to the assembly not being tight with no impact identified.

2. The groundwater remediation composite sampler was found out of service for less than one day on March 29, 2011. The composite sampler is required by ODCM Table 4.11 .1 .1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. There was enough sample in the composite sampler to perform the required analyses and the composite sampler was immediately returned to service.

3. The groundwater remediation composite sampler was found out of service for for approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on August 21, 2011. The composite sampler is required by ODCM Table 4.11.1.1.1.-1, Radioactive Liquid Waste Sampling and Analysis Program. The composite sampler was immediately returned to service and enough sample was collected in the composite sampler to perform the required analyses.

4. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluent sample was not collected January 1, 2011 through December 31, 2011. The New Radwaste/Augmented Offgas Service Water Effluent sample was required by CY-OC-1 70-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE 80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system sampling is still performed quarterly for gamma emitters. The potential pathway for a release from NRW/AOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the 131

Oyster Creek 2014 Annual Radioactive Effluent Release Report Service Water side of the heat exchanger. The system is designed to maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would develop in the heat exchanger it would be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

132

Oyster Creek 2014 Annual Radioactive Effluent Release Report Corrections to 2010 ARERR

1. A Program Deviation was not reported as required in the 2010 Annual Radiological Effluent release Report in Section J. Program Deviations. The New Radwaste/Augmented Offgas Service Water Effluent sample was not obtained January 1, 2010 through December 31, 2010.

133

Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2010 through December 31, 2010 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16 134

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2010 Annual Radioactive Effluent Release Report J. Program Deviations:

1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -

Functional Test was not performed at the frequency required by ODCM Table 4.3.3.11-1. The test was required to be performed by November 13, 2010 and was completed on December 2, 2010.

2. The groundwater remediation composite sampler was found out of service for less than one day on November 30, 2010. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. A grab sample was taken as a compensatory measure and the composite sample was immediately returned to service.

3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor count rate was discovered to be much lower than expected. A valve was found to be out of position causing a dilution in the sample concentration. Based on the stack monitor noble gas monitor readings, the valve had been open for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months . The valve was placed in the correct, closed position, immediately and the count rate returned to normal.

4. The stack sample line was discovered separated on April 7, 2010. A root cause analysis concluded that the sample line was first separated about January 1, 2006. The sample line was returned to service on April 20, 2010.

135

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2010 Annual Radioactive Effluent Release Report J. Program Deviations:

1. Procedure 621.3.037, Turbine Building RAGEMS Noble Gas Monitor -

Functional Test was not performed at the frequency required by ODCM Table 4.3.3.11-1. The test was required to be performed by November 13, 2010 and was completed on December 2, 2010.

2. The groundwater remediation composite sampler was found out of service for less than one day on November 30, 2010. The composite sampler is required by ODCM Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program. A grab sample was taken as a compensatory measure and the composite sample was immediately returned to service.

3. On December 18, 2010 at 04:00 the stack monitor noble gas monitor count rate was discovered to be much lower than expected. A valve was found to be out of position causing a dilution in the sample concentration. Based on the stack monitor noble gas monitor readings, the valve had been open for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months . The valve was placed in the correct, closed position, immediately and the count rate returned to normal.

4. The stack sample line was discovered separated on April 7, 2010. A root cause analysis concluded that the sample line was first separated about January 1, 2006. The sample line was returned to service on April 20, 2010.

5. The New Radwaste (NRW)/Augmented Offgas (AOG) Service Water Effluent sample was not collected January 1, 2010 through December 31, 2010. The New Radwaste/Augmented Offgas Service Water Effluent sample was required by CY-OC-170-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-10. At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE 80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system sampling is still performed quarterly for gamma emitters. The potential pathway for a release from NRW/AOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the Service Water side of the heat exchanger. The system is designed to maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would develop in the 136

Oyster Creek 2014 Annual Radioactive Effluent Release Report heat exchanger itwould be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

137

Oyster Creek 2014 Annual Radioactive Effluent Release Report Corrections to 2009 ARERR

1. A Program Deviation was not reported as required in the 2009 Annual Radiological Effluent release Report in Section J. Program Deviations. The New Radwaste/Augmented Offgas Service Water Effluent sample was not obtained September 29, 2009 through December 31, 2009.

138

Oyster Creek 2014 Annual Radioactive Effluent Release Report 2009 Annual Radioactive Effluent Release Report Oyster Creek Generating Station Revision 2 Issued 2012 139

Oyster Creek 2014 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2009 through December 31, 2009 EXELON GENERATION COMPANY, LLC OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 (Oyster Creek Generating Station)

DOCKET NO. 72-15 (Independent Spent Fuel Storage Facility)

Submitted to The United States Nuclear Regulatory Commission Pursuant to Renewed Facility Operating License DPR-16 140

Oyster Creek 2014 Annual Radioactive Effluent Release Report ORIGINAL PAGE Oyster Creek 2009 Annual Radioactive Effluent Release Report The maximum hypothetical calculated organ dose from iodines, tritium and particulates to any individual due to gaseous effluents was 3.38E-02 mrem, which was approximately 2.25E-01 percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of the annual limit.

For comparison, the background radiation dose averages approximately 300 mRem per year in the Central New Jersey area, which includes approximately 200 mrem per year from naturally occurring radon gas and 100 mrem per year from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposure would be due to direct radiation. This includes iodines, particulates and noble gases. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.

Because it is a sealed unit, no radioactive material was released.

Additionally, comparison of environmental sampling results to iodine and particulate gaseous effluents released, showed no radioactivity attributable to the operation of OCGS. Both elevated and ground-level release paths were considered in this review, with total iodines released of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of 2.50E-02 Ci.

Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stability classes, are included. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.

141

Oyster Creek 2014 Annual Radioactive Effluent Release Report CORRECTED PAGE Oyster Creek 2009 Annual Radioactive Effluent Release Report The maximum hypothetical calculated organ dose from iodines, tritium and particulates to any individual due to gaseous effluents was 3.38E-02 mrem , which was approximately 2.25E-01 percent of the annual limit. The maximum calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 4.55E-03 mrem, which was 4.55E-02 percent of the annual limit.

For comparison, the background radiation dose averages approximately 300 mRem per year in the Central New Jersey area, which includes approximately 200 mrem per year from naturally occurring radon gas and 100 mrem per year from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the only exposure would be due to direct radiation. This includes iodines, particulates and noble gases. Based on offsite TLD readings, dose due to direct radiation from the ISFSI was less than 1 mRem for 2009.

Because it is a sealed unit, no radioactive material was released.

Additionally, comparison of environmental sampling results to iodine and particulate gaseous effluents released, showed no radioactivity attributable to the operation of OCGS. Both elevated and ground-level release paths were considered in this review, with total iodines released of 1.78E-02 Ci and total particulates with half-lives greater than 8 days released of 2.50E-02 Ci.

Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stability classes, are included. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 97.8 percent and 97.8 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG 1.23 requires data recovery of at least 90% on an annual basis.

The New Radwaste (NRW)/Augmented Offas (AOG) Service Water Effluent sample was not collected September 29, 2009 through December 31, 2009. The New Radwaste/Augmented Offas Service Water Effluent sample was required by CY-OC-170-301, Offsite Dose Calculation Manual for Oyster Creek Generating Station Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program and was required to be sampled weekly for principal gamma emitters and 1-131. This issue occurred from the inclusion of this requirement in revision 4 of the ODCM due to a misunderstanding of the system flow path. It was believed that all service water exited the site from the same release point which was evident by the fact that the change paperwork included in the description of this change as being consistent with the practices at Oyster Creek and there was no modification to the sampling schedule. The NRW and AOG Closed Cooling Water systems were reviewed as part of NRC Bulletin IE 80-

10. At that time NRW Closed Cooling Water system was determined to be a potentially contaminated system and was added to the sampling program for NRC Bulletin IE 80-10. The sampling program for IE 80-10 requires all potentially contaminated systems to be sampled quarterly for gamma emitters. AOG Closed Cooling Water system was also reviewed but determined to not be a potentially contaminated system. Even though AOG was found not to be a potentially contaminated system sampling is still performed quarterly for gamma emitters.

The potential pathway for a release from NRW/AOG Service Water Effluent would be from a heat exchanger leak from the NRW Closed Cooling Water system into the Service Water side of the heat exchanger. The system is designed to maintain the Service Water side of the heat exchanger at a higher pressure than the Closed Cooling Water side so that if any leaks would 142

Oyster Creek 2014 Annual Radioactive Effluent Release Report develop in the heat exchanger it would be Service Water leaking into the Closed Cooling Water side. A review was performed for both NRW and AOG quarterly Closed Cooling Water samples for the time that the required samples were not obtained and all samples were less than MDA for gamma emitters for that entire time period.

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CY-OC-1 70-301 Aw"w Exeton Generation. Revision 6 Page I of 140 OFFSITE DOSE CALCULATION MANUAL FOR OYSTER CREEK GENERATING STATION Revision of this document requires PORC approval and changes are controlled by CY-AA-1 70-3100 122014

CY-OC-170-301 Revision 6 Page 2 of140 TABLE OF CONTENTS INTRODUCTION PART 1 - RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY 3/4.3 INSTRUMENTATION 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONTIORING INSTRUMENTATION 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION 3/4.11.1.2 DOSE 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE 3/4.11.2.2 DOSE - NOBLE GASES 3/4.11.2.3 DOSE - IODINE -131, IODINE - 133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM 3/4.11.3 MARK I CONTAINMENT 3/4.11.4 TOTAL DOSE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4.12.2 LAND USE CENSUS 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 3/4.12.4 METEOROLOGICAL MONITORING PROGRAM 122014

CY-OC-170-301 Revision 6 Page 3 of140 BASES FOR SECTIONS 3.0 AND 4.0 3/4.3 INSTRUMENTATION 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION 3/4.11.1.2 DOSE 3/4.11.1.3 LIQUID RADWASTE TREATMENT 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATES 3/4.11.2.2 DOSE - NOBLE GAS 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM 3/4.11.3 MARK I CONTAINMENT 3/4.11.4 TOTAL DOSE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4.12.2 LAND USE CENSUS 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 5.0 DESIGN FEATURES / SITE MAP 6.0 ADMINISTRATIVE CONTROLS 6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) 6.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) 6.3 RESPONSIBILITES 122014

CY-OC-170-301 Revision 6 Page 4 of 140 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLEUNTS 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION 1.2.1 LIQUID EFFLUENT MONITORS 1.2.2 SAMPLE RESULT SET POINTS 1.2.3 ASSUMED DISTRIBUTION SET POINTS 1.3 BATCH RELEASES 1.4 CONTINUOUS RELEASES 1.5 LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 1.5.1 MEMBER OF THE PUBLIC DOSE - LIQUID EFFLUENTS 1.5.2 SHORELINE DEPOSIT DOSE 1.5.3 SHORELINE DOSE EXAMPLE 1 1.5.3.1 SHORELINE DOSE EXAMPLE 2 1.5.4 INGESTION DOSE - LIQUID 1.5.5 INGESTION DOSE CALCULATION EXAMPLE 1 1.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 2 1.5.6 PROJECTED DOSE - LIQUID 1.6 REPRESENTATIVE SAMPLES 2 GASEOUS EFFLUENTS 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 2.2. GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION 2.2.1 PLANT VENT 2.2.2 OTHER RELEASE POINTS 2.2.3 RADIONUCLIDE MIX FOR SET POINTS 2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS 10 CFR 20 2.3.1 SITE BOUNDARY DOSE RATE - NOBLE GASES 2.3.1.1 TOTAL BODY DOSE RATE 2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE 2.3.1.3 SKIN DOSE RATE 122014

CY-OC-170-301 Revision 6 Page 5 ofl140 2.3.1.4 EXAMPLE SKIN DOSE RATE 2.3.2 SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES 2.3.2.1 METHOD - SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES 2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATION 2.4 NOBLE GAS EFFLUENT DOSE CALCULATION - 10 CFR 50 2.4.1 UNRESTRICTED AREA DOSE - NOBLE GASES 2.4.1.1 AIR DOSE METHOD 2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION 2.4.1.3 INDIVIDUAL PLUME DOSE METHOD 2.5 RADIOIODINE PARTICULATE AND OTHER RADIONUCLIDES DOSE CALCULATIONS - 10 CFR 50 2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES,AND OTHER RADIONUCLIDES 2.5.2 EXAMPLE CALCULATION - INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES 2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDES 2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHER THAN TRITIUM 2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION -

OTHER THAN TRITIUM 2.5.3.3 CONCENTRATION OF TRITIUM INANIMAL FORAGE AND VEGETATION 2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION 2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 2.5.3.8 EXAMPLE CALCULATION - DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 2.5.4 GROUND PLANE DEPOSITION IRRADIATION 122014

CY-OC-170-301 Revision 6 Page 6 of 140 2.5.4.1 GROUND PLANE CONCENTRATION 2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATION 2.5.4.3 GROUND PLANE DOSE 2.5.4.4 EXAMPLE GROUND PLANE DOSE 2.6 PROJECTED DOSES - GASEOUS 3 TOTAL DOSE TO MEMBERS OF THE PUBLIC - 40 CFR 190 3.1 EFFLUENT DOSE CALCULATIONS 3.2 DIRECT EXPOSURE DOSE DETERMINATION 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM APPRENDIX A - DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS Table A-I: Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-To-Dose Equivalent Rate Factors Table A-2: Noble Gas Radionuclide-To-Dose Equivalent Rate Factors Table A-3: Air Dose Conversion Factors for Effluent Noble Gas Table A-4: Locations Associated with Maximum Exposure of a Member of The Public Table A-5: Critical Receptor Noble Gas Dose Conversion Factors APPENDIX B - MODELING PARAMETERS Table B-I: OCGS Usage Factors for Individual Dose3 Assessment Table B-2: Monthly Average Absolute Humidity g/m APPENDIX C - REFERENCES Table C-1: REFERENCES APPENDIX D - SYSTEM DRAWINGS Figure D-l-la: Liquid Radwaste Treatment Chem Waste and Floor Drain System Figure D-1-1 b: Liquid Radwaste Treatment - High Purity and Equipment Drain System Figure D-l-lc: Groundwater Remediation System Figure D-1-2: Solid Radwaste Processing System Figure D-2-1: Gaseous Radwaste Treatment - Augmented Offgas System Figure D-2-2: Ventilation System Figure D-2-3: AOG Ventilation System 122014

CY-OC-170-301 Revision 6 Page 7 of 140 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - SAMPLE TYPE AND LOCATION Table E-1: REMP Sample Locations Figure E-1: Oyster Creek Generating Station REMP Sample Locations within a 1 Mile Radius Figure E-2: Oyster Creek Generating Station REMP Sample Locations within a 1 to 5 Mile Radius Figure E-3: Oyster Creek Generating Station REMP Sample Locations over a 5 Mile Radius Figure E-4: Area Plot Plan of Site 122014

CY-OC-170-301 Revision 6 Page 8 of 140 OYSTER CREEK GENERATING STATION OFF SITE DOSE CALCULATION MANUAL INTRODUCTION The Oyster Creek Off Site Dose Calculation Manual (ODCM) is an implementing document to the Oyster Creek Technical Specifications. The previous Limiting Conditions for Operations that were contained in the Radiological Effluent Technical Specifications (RETS) are now included in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts:

Part I - Radiological Effluent Controls, and Part II - Calculational Methodologies.

Part I includes the following:

" The Radiological Effluent Controls and the Radiological Environmental Monitoring Programs required by Technical Specifications 6.8.4

" Descriptions of the information that should be included in the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Operating Report required by Technical Specifications 6.9.1.d and 6.9.1.e, respectively.

Part II describes methodologies and parameters used for:

" The calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip set points; and

" The calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative yearly doses, and projected doses.

Part II also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program (REMP), and the liquid and gaseous waste treatment systems and discharge points.

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CY-OC-170-301 Revision 6 Page 9 of140 PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these CONTROLS may be achieved. The defined terms appear in capitalized type and are applicable throughout these CONTROLS.

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

A verification of OPERABILITY is an administrative check, by examination of appropriate plant records (logs, surveillance test records) to determine that a system, subsystem, train, component or device is not inoperable. Such verification does not preclude the demonstration (testing) of a given system, subsystem, train, component or device to determine OPERABILITY.

1.2 ACTION ACTION shall be that part of a CONTROL that prescribes remedial measures required under designated conditions.

1.3 CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds, with acceptable range and accuracy, to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including equipment actuation, alarm, or trip.

1.4 CHANNEL CHECK A CHANNEL CHECK shall be a qualitative determination of acceptable operability by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel with other independent channels measuring the same variable.

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CY-OC-170-301 Revision 6 Page 10 of 140 1.5 CHANNEL FUNCTIONAL TEST CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel to verify its proper response including, where applicable, alarm and/or trip initiating actions.

1.6 CONTROL The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent Technical Specifications were transferred to the OFF SITE DOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS. This is to distinguish between those LCOs that were retained in the Technical Specifications and those LCOs or CONTROLS that were transferred to the ODCM.

1.7 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

1.8 REPORTABLE EVENT A REPORABLE EVENT shall be any of those conditions specified Section 50.73 to 10CFR Part 50.

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

1.10 AUGMENTED OFF GAS SYSTEM (AOG)

The AUGMENTED OFF GAS SYSTEM is designed and installed to holdup and/or process radioactive gases from the main condenser off gas system for the purpose of reducing the radioactive material content of the gases before release to the environs.

1.11 MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with Exelon Generation and who do not normally frequent the Oyster Creek Generating Station site. This category does not include employees of the utility, its contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on site or for other purposes associated with plant functions. This category does include persons who use portions of the site for recreational, occupational, or other 122014

CY-OC-170-301 Revision 6 Page 11 of 140 purposes not associated with the plant. An individual is not a member of the public during any period in which the individual receives an occupational dose.

1.12 OFF SITE DOSE CALCULATION MANUAL (ODCM)

The OFF SITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of Off Site doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Set points, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radioactive Effluent Release Report AND Annual Radiological Environmental Operating Report required by Technical Specification Sections 6.9.1.d and 6.9.1.e, respectively.

1.13 PURGE-PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement and replacing it with air or gas.

1.14 SITE BOUNDARY The SITE BOUNDARY shall be the perimeter line around OCGS beyond which the land is neither owned, leased, nor otherwise subject to control by Exelon Generation. The area outside the SITE BOUNDARY is termed OFF SITE or UNRESTRICTED AREA.

1.15 OFF SITE The area that is beyond the site boundary where the land is neither owned, leased nor otherwise subject to control by Exelon Generation. Can be interchanged with UNRESTRICTED AREA.

1.16 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. Can be interchanged with OFF SITE.

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CY-OC-170-301 Revision 6 Page 12 of 140 1.17 DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (micro curies per gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating Compliance with 10CFR Part 40 Appendix I."

1.18 DEPOSITION (D/Q)

The direct removal of gaseous and particulate species on land or water surfaces.

DEPOSITION is expressed as a quantity of material per unit area (e.g. m 2).

1.19 DOSE CONVERSION FACTOR (DCF)

A parameter calculated by the methods of internal dosimetry, which indicates the committed dose equivalent (to the whole body or organ) per unit activity inhaled or ingested. This parameter is specific to the isotope and the dose pathway. DOSE CONVERSION FACTORS are commonly tabulated in units of mrem/hr per picocurie/m3 in air or water. They can be found in Reg Guide 1.109 appendices.

1.20 EFFLUENT CONCENTRATION (EC)

The liquid and air concentration levels which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem. LEC refers to liquid EFFLUENT CONCENTRATION.

1.21 ELEVATED (STACK) RELEASE An airborne effluent plume whose release point is higher than twice the height of the nearest adjacent solid structure and well above any building wake effects so as to be essentially unentrained. Regulatory Guide 1.111 is the basis of the definition of an ELEVATED RELEASE. Elevated releases generally will not produce any significant ground level concentrations within the first few hundred yards of the source. ELEVATED RELEASES generally have less dose consequence to the public due to the greater downwind distance to the ground concentration maximum compared to ground releases. All main stack releases at the OCGS are ELEVATED RELEASES.

1.22 FINITE PLUME MODEL Atmospheric dispersion and dose assessment model which is based on the assumption that the horizontal and vertical dimensions of an effluent plume are not necessarily large compared to the distance that gamma rays can travel in air.

It is more realistic than the semi-infinite plume model because it considers the 122014

CY-OC-170-301 Revision 6 Page 13 of 140 finite dimensions of the plume, the radiation build-up factor, and the air attenuation of the gamma rays coming from the cloud. This model can estimate the dose to a receptor who is not submerged in the radioactive cloud. It is particularly useful in evaluating doses from an elevated plume or when the receptor is near the effluent source.

1.23 GROUND LEVEL (VENT) RELEASE An airborne effluent plume which contacts the ground essentially at the point of release either from a source actually located at ground elevation or from a source well above the ground elevation which has significant building wake effects to cause the plume to be entrained in the wake and driven to the ground elevation.

GROUND LEVEL RELEASES are treated differently than ELEVATED RELEASES in that the X/Q calculation results in significantly higher concentrations at the ground elevation near the release point.

1.24 OCCUPATIONAL DOSE The dose received by an individual in a RESTRICTED AREA or in the course of employment in which the individual's assigned duties involve exposure to radiation and to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public 1.25 "OPEN DOSE" A routine effluent dosimetry computer program that uses Reg.

Guides 1.109 and 1.111 methodologies.

1.26 RAGEMS (RADIOACTIVE EMISSIONS MONITORING SYSTEM)

A plant system that monitors gaseous effluent releases from monitored release points. There is a RAGEMS system for the main stack (RAGEMS I) and one for the turbine building (RAGEMS II). They monitor particulates, iodine's, and noble gases.

1.27 SEMI-INFINITE PLUME MODEL Dose assessment model with the following assumptions. The ground is considered to be an infinitely large flat plate and the receptor is located at the origin of a hemispherical cloud of infinite radius. The radioactive cloud is limited to the space above the ground plane. The semi-infinite plume model is limited to immersion dose calculations.

1.28 SOURCE TERM 122014

CY-OC-170-301 Revision 6 Page 14 of 140 The activity release rate, or concentration of an actual release or potential release. The common units for the source term are curies, curies per second, and curies per cubic centimeter, or multiples thereof (e.g., micro curies).

1.29 X/Q - ("CHI over Q")

The dispersion factor of a gaseous release in the environment calculated by a point source Gaussian dispersion model. Normal units of X/Q are sec/m 3 . The X/Q is used to determine environmental atmospheric concentrations by multiplying the source term, represented by Q (in units of ýiCi/sec or Ci/sec).

Thus, the plume dispersion, X/Q (seconds/cubic meter) multiplied by the source term, Q (uCi/seconds) yields an environmental concentration, X (itCi/m 3). X/Q is a function of many parameters including wind speed, stability class, release point height, building size, and release velocity.

1.30 SEEDS (Simplified Effluent Environmental Dosimetry System)

A routine effluent dosimetry computer program that uses Reg. Guides 1.109 and 1.111 methodologies.

TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION

NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

R At least once per 18 months (550 days).

1/24 At least once per 24 months (refueling cycle)

S/U Prior to each reactor startup.

P Prior to each radioactive release.

N.A. Not applicable.

Each surveillance requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

122014

CY-OC-170-301 Revision 6 Page 15 of 140 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the CONTROL, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROL and associated ACTION requirements are not met within the specified time intervals.

If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 Except as provided in the associated ACTION requirements, when a CONTROL is not met or the associated ACTION requirements cannot be satisfied, action shall be initiated to place the unit into COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.

This CONTROL is not applicable in COLD SHUTDOWN or REFUELING.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions of the CONTROLS are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual CONTROLS.

3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to CONTROL 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

122014

CY-OC-1 70-301 Revision 6 Page 16 of 140 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a CONTROL. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the CONTROLS have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

122014

CY-OC-170-301 Revision 6 Page 17 of 140 3/4.3 INSTRUMENTATION 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.10 In accordance with Oyster Creek Technical Specifications 6.8.4.a.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.3.10-1 shall be OPERABLE with their Alarm/Trip set points set to ensure that the limits of CONTROL 3.11.1.1 are not exceeded. The Alarm/Trip set points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM Part II section 1.2.1.

APPLICABILITY: During all liquid releases via these pathways.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip set point less conservative than required by the above CONTROL, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the set point so it is acceptably conservative, or provide for manual initiation of the Alarm/Trip function(s).

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.10-1. Make every reasonable effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1 .d why the inoperability was not corrected in a timely manner.

c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable. Report all deviations in the Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the Frequencies shown in Table 4.3.3.10-1.

122014

CY-OC-1 70-301 Revision 6 Page 18 of 140 TABLE 3.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A

b. Turbine Building Sump No. 1-5 (DELETED) N/A N/A

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Reactor Building Service Water System Effluent Line 1 112

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A

b. Groundwater Remediation Release Path 1 115 122014

CY-OC-170-301 Revision 6 Page 19 of 140 TABLE 3.3.3.10-1 (Continued)

TABLE NOTATIONS ACTION 110 With no channels OPERABLE, effluent releases via this pathway may continue provided that:

a. At least two independent samples are taken, one prior to discharge and one near the completion of discharge and analyzed in accordance with SURVEILLANCE REQUIREMENT 4.11.1.1.1.

b. Before initiating a release, at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 112 With no channels OPERABLE, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for radioactivity at a limit of detection specified by Table 4.11.1.1.1-1.

ACTION 113 With no channel OPERABLE, effluent releases via the affected pathway may continue provided the flow is estimated with the pump curve or change in tank level, at least once per batch during a release.

ACTION 114 With no channel OPERABLE effluent may be released provided that before initiating a release:

a. A sample is taken and analyzed in accordance with SURVEILLANCE REQUIREMENT 4.11.1.1.1.

b. Qualified personnel determine and independently verify the acceptable release rate.

ACTION 115 With no channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

122014

CY-OC-1 70-301 Revision 6 Page 20 of 140 TABLE 4.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSa CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A N/A N/A

b. Turbine Building Sump No. 1-5 (DELETED) N/A N/A N/A N/A

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Reactor Building Service Water System Effluent Line D M Re

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A N/A N/A Df N/A Rf N/A

b. Groundwater Remediation Release path 122014

CY-OC-170-301 Revision 6 Page 21 of 140 TABLE 4.3.3.10-1 (Continued)

TABLE NOTATIONS

a. Instrumentation shall be OPERABLE and in service except that a channel may be taken out of service for the purpose of a check, calibration, test or maintenance without declaring it to be inoperable.

d. The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set point.

2. Instrument indicates a downscale failure.

3. Instrument controls not set in operate mode.

4. Instrument electrical power loss.

e. The CHANNEL CALIBRATION shall be performed according to established calibration procedures.

f. While actively discharging through this pathway.

122014

CY-OC-170-301 Revision 6 Page 22 of 140 3/4.3 INSTRUMENTATION 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.11 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.3.11-1 shall be OPERABLE with their alarm/trip set points set to ensure that the limits of CONTROL 3.11.2.1 are not exceeded. The alarm/trip set points of these channels meeting CONTROLS 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM Part II Section 2.2.

APPLICABILITY: As shown in Table 3.3.3.11-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip set point less conservative than required by the above CONTROL, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the set point so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.11-

1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1 .d why this inoperability was not corrected in a timely manner.

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable. Report all deviations in the Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.3.11-1.

122014

CY-OC-1 70-301 Revision 6 Page 23 of 140 TABLE 3.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERAE3LEa APPLICABILITY ALCTION

1. DELETED

2. STACK MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) 1 b,e 124

b. Iodine Sampler i b,e 127

c. Particulate Sampler 1 b,e 127

d. Effluent Flow Measuring Device 1 b 122

e. Sample Flow Measuring Device 1 b 128

3. TURBINE BUILDING VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) 1 b 123

b. Iodine Sampler 1 b 127

c. Particulate Sampler 1 b 127

d. Effluent Flow Measuring Device 1 b 122

e. Sample Flow Measuring Device 1 b 128 122014

CY-OC-170-301 Revision 6 Page 24 of 140 TABLE 3.3.3.11-1(Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLEa APPLICABILITY ACTION

4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor 1 b 123

b. Iodine Sampler 1 b 127

c. Particulate Sampler 1 b 127

d. Sample Flow Measuring Device 1 b 128 122014

CY-OC-170-301 Revision 6 Page 25 of 140 TABLE 3.3.3.11-1 (Continued)

TABLE NOTATIONS

a. Channels shall be OPERABLE and in service as indicated except that a channel may be taken out of service for the purpose of a check, calibration, test maintenance or sample media change without declaring the channel to be inoperable.

b. During releases via this pathway

e. Monitor / sampler or an alternate shall be OPERABLE to monitor / sample Stack effluent whenever the drywell is being purged.

ACTION 122 With no channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated whenever the exhaust fan combination in this system is changed.

ACTION 123 With no channel OPERABLE, effluent releases via this pathway may continue provided a grab sample is taken at least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and is analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter or provided an alternate monitoring system with local display is utilized.

ACTION 124 With no channel OPERABLE, effluent releases via this pathway may continue provided a grab sample is taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or provided an alternate monitoring system with local display is utilized. Drywell purge is permitted only when the radioactive noble gas monitor is operating.

ACTION 127 With no channel OPERABLE, effluent releases via this pathway may continue provided the required sampling is initiated with auxiliary sampling equipment as soon as reasonable after discovery of inoperable primary sampler(s).

ACTION 128 With no channel OPERABLE, effluent releases via the sampled pathway may continue provided the sampler air flow is estimated and recorded at least once per day.

122014

CY-OC-1 70-301 Revision 6 Page 26 of 140 TABLE 4.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIREDa

1. DELETED

2. MAIN STACK MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qh b

b. Iodine Sampler W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Effluent Flow Measuring Device D N.A. 1/24 Q b

e. Sample Flow Measuring Device D N.A. R Q b

3. TURBINE BUILDING VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qi b

b. Iodine Sampler W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Effluent Flow Measuring Device D N.A. 1/24 Q b

e. Sample Flow Measuring Device D N.A. R Q b 122014

CY-OC-1 70-301 Revision 6 Page 27 of 140 TABLE 4.3.3.11-1 (Continued)

RADIOACTIVE'GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED a

4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor D M Rf Qe b

b. Iodine Sampler W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Sample Flow Measuring Device D N.A. R N.A. b 122014

CY-OC-170-301 Revision 6 Page 28 of 140 TABLE 4.3.3.11-1 (Continued)

TABLE NOTATIONS

a. Instrumentation shall be OPERABLE and in service except that a channel may be taken out of service for the purpose of a check calibration, test or maintenance without declaring it to be inoperable.

b. During releases via this pathway.

e. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm set point.

2. Instrument indicates a downscale failure.

3. Instrument controls not set in operate mode.

4. Instrument electrical power loss.

f. The CHANNEL CALIBRATION shall be performed according to established calibration procedures.

h. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set point.

2. Instrument indicates a low count rate/monitor failure.

3. Switch cover alarm shall be verified to alarm when the cover is opened; and clear when the cover is closed after the faceplate switches are verified in their correct positions.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm set point.

2. Instrument indicates a low count rate/monitor failure.

122014

CY-OC-170-301 Revision 6 Page 29 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION CONTROLS 3.11.1.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.2 and 3, the concentration of radioactive material, other than noble gases, in liquid effluent in the discharge canal at the Route 9 bridge (See Figure E-4) shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The concentration of noble gases dissolved or entrained in liquid effluent in the discharge canal at the Route 9 bridge shall not exceed 2E-4 microcuries/milliliter.

APPLICABILITY: At all times.

ACTION:

a. In the event the concentration of radioactive material in liquid effluent released into the Off Site area beyond the Route 9 bridge exceeds either of the concentration limits above, reduce the release rate without delay to bring the concentration below the limit.

b. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program in Table 4.11.1.1.1-1.

Alternately, pre-release analysis of batches(es) of radioactive liquid waste may be by gross beta or gamma counting provided a maximum concentration limit of 1E-8 gCi/ml in the discharge canal at the Route 9 bridge is applied.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM Part II Section 1.2 to assure that the concentrations at the point of release are maintained within the limits of CONTROL 3.11.1.1 and 3.11.1.2.

4.11.1.1.3 The alarm or trip set point of each radioactivity monitoring channel in Table 3.3.3.10-1 shall be determined on the basis of sampling and analyses results obtained according to Table 4.11.1.1.1-1 and the set point method in ODCM Part 111.2.1 and set to alarm or trip before exceeding the limits of CONTROL 3.11.1.1.

122014

CY-OC-170-301 Revision 6 Page 30 of 140 TABLE 4.11.1.1.1-1: RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit Liquid Release Type Sampling Frequency Analysis Frequency Type of Activity Analysis Detectiona (P.Ci/ml)(LLD)

P pC Principal Gamma Emitters 5E-07

1. Batch Waste Release Tanks Each Batchb Each Batch 1-131 5E-07 M Dissolved and Entrained One Gases (Gamma Emitters) 1E-05 Batch/Mb P M H-3 1E-05 Each Batchb Composited Gross Alpha 1E-07 P Q Sr-89, Sr-90 5E-08 Each Batchb Composited Fe-55 1E-06

2. Continuous W Principal Gamma Emitters 5E-07 Release Grab W 1-131 5E-07

a. Reactor Building Samplee-Service Water H-3 1E-05 Effluent Gross Alpha 1E-07 M

(note f) Compositeg Fe-55 1E-06

3. Groundwater Remediation uoush D Principal Gamma Emitters 5E-07 Pathway ContinuoussteH-"

Composite H-3 E0 1E-05

a. Continuous Gross Alpha 1E-07 M Sr-89, Sr-90 5E-08 M

Compositeg Fe-55 1E-06 Ni-63 1E-06

b. Batch Release P P Principal Gamma Emitters 5E-07 Tank Each Batchb Each Batch H-3 1E-05 Gross Alpha 1E-07 P M Sr-89, Sr-90 5E-08 Each Batchb Composited Fe-55 1E-06 Ni-63 1E-06 122014

CY-OC-170-301 Revision 6 Page 31 of 140 TABLE 4.11.1.1-1 (CONTINUED)

TABLE NOTATIONS

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

The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular sample in the radioactive liquid waste sampling and analyses program.

For a particular measurement system, which may include radiochemical separation:

LLD~ 4.66

Sb E

V

2.22E6

Y

exp(-kAt)

Where:

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

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

E is the counting efficiency, V is the sample size (units of mass or volume),

2.22E+6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, Xkis the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the end of the sample collection and the time of counting.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Ce-141, Cs-134, Cs-137; and an LLD of 5E-6 iýCi/ml should typically be achieved for Ce-144.

122014

CY-OC-170-301 Revision 6 Page 32 of 140 TABLE 4.11.1.1.1-1 (CONTINUED)

TABLE NOTATIONS Occasionally, background fluctuations, interfering radionuclides, or other uncontrollable circumstances may render these LLD's unachievable.

When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the sample. The background count rate of a semiconductor detector (e.g. HPGe) is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for the radionuclide.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall be identified and reported. The LLD for Ce-144 is 5E-6 gCi/mL whereas the LLD for Mo-99 and the other gamma emitters is 5E-7 p.Ci/mL. Nuclides that are below the LLD for the analysis should not be reported.

b. A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analysis, each batch should be thoroughly mixed.

c. In the event a gross radioactivity analysis is performed in lieu of an isotopic analysis before a batch is discharged, a sample will be analyzed for principal gamma emitters afterwards.

d. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

e. Analysis may be performed after release.

f. In the event a grab sample contains more than 5E-7 ýiCi/mL of 1-131 and principal gamma emitters or in the event the Reactor Building Service Water radioactivity monitor indicates more than 5E-7 gCi/mL radioactivity in the effluent, as applicable, sample the elevated activity effluent daily until analysis confirms the activity concentration in the effluent does not exceed 5E-7 ltCi/mL. In addition a composite sample must be made up for further analysis for all samples taken when the activity was > 5E-7 itCi/mL.

g. A composite sample is produced combining grab samples, each having a defined volume, collected routinely from the sump or stream being sampled

h. Aliquot sampling shall be at least hourly to be representative of the quantities and concentrations of radioactive materials in liquid effluent. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

122014

CY-OC-170-301 Revision 6 Page 33 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.2 DOSE CONTROLS 3.11.1.2 In accordance with Oyster Creek Technical Specifications 6.8.4.a.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure E-4) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the Total Body and to less than or equal to 5 mrem to any body organ, and

b. During any calendar year to less than or equal to 3 mrem to the Total Body and to less than or equal to 10 mrem to any body organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days from the end of the quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken and/or will be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 1.5 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

122014

CY-OC-170-301 Revision 6 Page 34 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.6, the liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure E-4) would exceed 0.06 mrem to the Total Body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM Part II Section 1.5 in accordance with Technical Specifications 6.8.4.a.5.

4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting CONTROLS 3.11.1.1, 3.11.1.2, and 3.11.1.3.

122014

CY-OC-170-301 Revision 6 Page 35 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE CONTROLS 3.11.2.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.5 and 7, the dose rate due to radioactive materials released in gaseous effluents in the UNRESTRICTED AREA (see Figure E-4) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any body organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

b. If the gaseous effluent release rate cannot be reduced to meet the above limits, the reactor shall be in at least SHUTDOWN CONDITION within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months unless corrective actions have been completed and the release rate restored to below the above limit.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM Part II Section 2.3.1.

4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM Part II Section 2.3.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.

4,11.2.1.3 Dose rates due to tritium, Sr-89, Sr-90, and alpha-emitting radionuclides are averaged over no more than 3 months and the dose rate due to other radionuclides is averaged no more than 31 days.

122014

CY-OC-1 70-301 Revision 6 Page 36 of 140 TABLE 4.11.2.1.2-1: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit Gaseous Release Sampling Analysis Type of Activity Detectiona- (LLD)

Type Frequency Frequency Analysis (jiCi/ml)

Q Grab Samplef Q H-3 1E-06 M Principal M Gamma Grab Sample Emittersb (Noble 1E-04 c,d,f Gases)

W 1-131 1E-12 Continuousf Charcoal SampleSaplI-133 1E-10 W Principal Stack; Gamma Turbine Building Continuous Particulate Emittersb Exhaust Vents; (particulates)

Augmented Off gas Me Building Vent Continuousf Composite Gross Alpha 1E-11 Particulate Sample Qe Sr-89, Sr-90 1E-11 Continuous Composite Particulate Sample Noble Gas Noble Gases 1E-06 Continuous Gamma Radioactivity 122014

CY-OC-1 70-301 Revision 6 Page 37 of 140 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATIONS

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

The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular sample in the radioactive liquid waste sampling and analyses program.

For a particular measurement system which may include radiochemical separation:

LLD =4.66

Sb E

V

2.22E6

Y

exp(-kAt)

Where:

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

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

E is the counting efficiency, V is the sample size (units of mass or volume),

2.22E+6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, k is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the end of the sample collection and the time of counting.

Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141. Occasionally background fluctuations or other uncontrollable circumstances may render these LLD's unachievable.

When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the samples. The background count rate of a HpGe detector is determined from background 122014

CY-OC-170-301 Revision 6 Page 38 of 140 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATIONS counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for that radionuclide

b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report consistent with CONTROL 3.11.2.1. The LLD for Mo-99 and Ce-144 is 1E-10 ptCi/ml whereas the LLD for other principal gamma emitting particulates is 1E-1 1 jCi/ml.

Radionuclides which are below the LLD for the analysis should not be reported.

c. The noble gas radionuclides in gaseous effluent may be identified by taking a grab sample of effluent and analyzing it.

d. In the event the reactor power level increases more than 15 percent in one hour and the Stack noble gas radioactivity monitor shows an activity increase of more than a factor of three after factoring out the effect due to the change in reactor power, a grab sample of Stack effluent shall be collected and analyzed.

e. A composite particulate sample shall include an equal fraction of at least one particulate sample collected during each week of the compositing period.

f. In the event a sample is collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less, the LLD may be increased by a factor of 10.

122014

CY-OC-170-301 Revision 6 Page 39 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.2 DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with the Oyster Creek Technical Specification 6.8.4.a.5 and 8, the air dose due to noble gases released in gaseous effluents in the UNRESTRICTED AREA (see Figure E-4) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days from the end of the quarter during which the release occurred, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 2.4.1 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

122014

CY-OC-170-301 Revision 6 Page 40 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Oyster Creek Technical Specification 6.8.4.a.5 and 9, the dose to a MEMBER OF THE PUBLIC from iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released in the UNRESTRICTED AREA (see Figure E-4) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any body organ and,

b. During any calendar year: Less than or equal to 15 mrem to any body organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133 and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 2.5 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

122014

CY-OC-170-301 Revision 6 Page 41 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM CONTROLS 3.11.2.4 The AUGMENTED OFF GAS SYSTEM shall be in operation to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figure E-4) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any body organ APPLICABILITY: Whenever the main condenser steam jet air ejector is in operation except during startup or shutdown with reactor power less than 40 percent of rated. In addition, the AUGMENTED OFF GAS SYSTEM need not be in operation during end of cycle coast-down periods when the system can no longer function due to low off gas flow.

ACTION:

a. Every reasonable effort shall be made to maintain and operate charcoal absorbers in the AUGMENTED OFF GAS SYSTEM to treat radioactive gas from the main condenser air ejectors.

b. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 30 consecutive days and either CONTROL 3.11.2.1 or 3.11.2.4 exceeded, prepare and submit to the Commission within 30 days from the end of the quarter during which release occurred, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

122014

CY-OC-170-301 Revision 6 Page 42 of 140 SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Operation of the Augmented Off gas System charcoal absorbers shall be verified by verifying the AOG System bypass valve, V-7-31, alignment or alignment indication closed at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the main condenser air ejector is operating.

4.11.2.4.2 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM Part II Section 1.5 in accordance with Technical Specifications 6.8.4.a.5.

122014

CY-OC-170-301 Revision 6 Page 43 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.3 MARK I CONTAINMENT CONTROLS 3.11.3.1 Venting or purging of the containment Drywell may be through normal Reactor Building Ventilation if the following requirements are met:

APPLICABILITY: If the Station year-to-date radiological effluent releases (either iodine or noble gas) are less than 10% of the ODCM limit, then Standby Gas Treatment is NOT required for purging the contents of the Drywell.

ACTION:

a. If the Station year-to-date radiological effluent releases (either iodine or noble gas) are greater than 10% of the ODCM limit, then the Standby Gas Treatment System must be used for purging the contents of the Drywell.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The Standby Gas Treatment System is OPERABLE and available whenever the purge system is in use.

122014

CY-OC-170-301 Revision 6 Page 44 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4.1 In accordance with Oyster Creek Technical Specifications 6.8.4.a. 10, the annual (calendar year) dose commitment to any MEMBER OFTHE PUBLIC due to radioactive material in the effluent and direct radiation from the OCGS in the UNRESTRICTED AREA shall be limited to less than or equal to 75 mrem to the thyroid or less than or equal to 25 mrem to the total body or any other organ.

APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of CONTROLS 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, perform an assessment to determine whether the limits of CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report shall include information specified in 10CFR20.2203. Ifthe estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SURVEILLANCE REQUIREMENT 4.11.1.2, 4.11.2.2, 4.11.2.3, and in accordance with the methodology and parameters in the ODCM Part II Section 3.0 at least once per year.

4.11.4.2 Cumulative dose contributions from direct radiation from the facility shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 3.2. This requirement is applicable only under conditions set forth in CONTROL 3.11.4, ACTION a.

122014

CY-OC-170-301 Revision 6 Page 45 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1. In accordance with Oyster Creek Technical Specifications 6.8.4.b, the radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

For specific sample locations see Table E-1. Revisions to the non-ODCM required portions of the program may be implemented at any time. Non-ODCM samples are those taken in addition to the minimum required samples listed in Table 3.12.1-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9. 1.e, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 60 days of the end of the quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*

to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to Section 6.1.2.1.

The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

122014

CY-OC-170-301 Revision 6 Page 46 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)

ACTION: (Continued)

C. If garden vegetation samples are unobtainable due to any legitimate reason, it is NOT ACCEPTABLE to substitute vegetation from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

If a permanent sampling location becomes unavailable, follow Table 3.12.1-1 Table Notation (1) to replace the location.

d. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in Table E-1, and shall be analyzed pursuant to the requirements of Table 3.12.1-1, and the detection capabilities required by Table 4.12.1-1.

122014

CY-OC-1 70-301 Revision 6 Page 47 of 140 TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTAIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

1. DIRECT RADIATION(2) Routine monitoring Quarterly Gamma dose quarterly stations with two or more dosimeters placed as follows:

An inner ring of stations one in each meteorological sector in the general area of the SITE BOUNDARY (At least 16 locations);

An outer ring of stations, one in each land-based meteorological sector in the approximately 6- to 8-km range from the site (At least 14 locations); and At least 8 stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

122014

CY-OC-1 70-301 Revision 6 Page 48 of 140 TABLE 3.12.1-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

2. AIRBORNE Radioiodine and Samples from 5 locations: Continuous sampler Radioiodine Canister:

Particulates operation with sample 1-131 analysis weekly Three samples from close to collection weekly or the SITE BOUNDARY in different more frequently if sectors of the highest calculated required by dust Particulate Sampler annual average ground- loading Gross beta radioacti-level D/Q vity analysis follow-ing filter change 3 );

One sample from the vicinity Gamma isotopic of a community having the highest analysis(4) calculated annual average ground- of composites (by level D/Q; and location) quarterly One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction (6) 122014

CY-OC-1 70-301 Revision 6 Page 49 of 140 TABLE 3.12.1-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

3. WATERBORNE

a. Surface One sample upstream Grab sample weekly, Gamma isotopic and One sample downstream Combine into monthly tritium analysis(4) composite.

b. Ground(5) Samples from one or two sources Grab sample quarterly Gamma isotopic and tritium if likely to be affected analysis,4 )

c. Drinking 1 sample of each of 1 to 3 of the Grab sample weekly, Gross beta, gamma nearest water supplies that could combine into a 2-week isotopic and tritium analysis be affected by its discharge composite if 1-131 analysis monthly (4)(7)

Is required; composite monthly otherwise One sample from a background location 122014

CY-OC-1 70-301 Revision 6 Page 50 of 140 TABLE 3.12.1-1 (Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

d. Sediment One sample from downstream area Semiannually Gamma isotopic with existing or potential recreational analysis(4) semiannually value 122014

CY-OC-1 70-301 Revision 6 Page 51 of 140 TABLE 3.12.1-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

4. INGESTION

a. Milk (6) No milking animals Semimonthly when on pasture; Gamma isotopic (4) and Iodine -131 If milk animals are identified: monthly at other times semimonthly when Samples from milking animals in animals are on pasture; three locations within 5km having monthly at other times the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 an 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animal at a control location 15 to 30 km distant and in the least prevalent wind direction

b. Fish One sample of available species Semiannually, Gamma isotopic consumed by man in plant when available analysis (4) discharge canal on edible portions One sample of available species consumed by man not influenced by plant discharge 122014

CY-OC-1 70-301 Revision 6 Page 52 of 140 TABLE 3.12.1-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY OF ANALYSIS

c. Clams One sample of available species Semiannually, Gamma isotopic when available analysis (4) consumed by man within the influence of the facility discharge. on edible portions.

One sample of available species consumed by man not influenced by plant discharge.

d. Vegetation (8) 3 samples of broad leaf Monthly during Gamma isotopic vegetation grown nearest each growing season analysis (4) and 1-131 on of two different Off Site locations of edible portion.

highest predicted annual average combined elevated and ground level release D/Q One sample of each of the similar broad leaf vegetation grown at least 15 to 30 km (9.3-18.6 miles) distant in the least prevalent wind direction.

122014

CY-OC-170-301 Revision 6 Page 53 of 140 TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS Specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 and Table E-1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.4. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Technical specification 6.19, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples. This applies to changes/deletions/additions of permanent sampling locations. This does not apply to one-time deviations from the sampling schedule. In those cases, it is NOT ACCEPTABLE to substitute sample media from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

2 One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. The number of direct radiation monitoring stations has been reduced from the NUREG 1302 recommendation due to geographical limitations; e.g., some sectors are over water and some sectors cannot be reached due to lack of highway access, therefore the number of dosimeters has been reduced accordingly.

3 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

4 Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

5 Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Extensive studies of geology and groundwater in the vicinity of the OCGS (Reference 21 and 31) have demonstrated that there is no plausible pathway for effluents from the facility to contaminate offsite groundwater, including the local 122014

CY-OC-1 70-301 Revision 6 Page 54 of 140 drinking water supplies. Samples of groundwater, including local drinking water wells, are collected in order to provide assurance to the public that these water resources are not impacted.

6 The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted 7 1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year. If garden vegetation samples are unobtainable due to any legitimate reason (see (1) above), it is NOT ACCEPTABLE to substitute vegetation from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

122014

CY-OC-170-301 Revision 6 Page 55 of 140 TABLE 3.12.1-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES - REPORTING LEVELS Surface and Airborne Fish Milk Vegetation Analysis Ground Particulate (pCi/Kg, (pCi/I) (pCi/Kg, Water(pCi/I) and Iodine wet) wet)

(pCi/m 3)

H-3 20000*

Mn-54 1000 30000 Fe-59 400 10000 Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 1-131 2** 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300

For drinking water samples (this is the 40 CFR Part 141 value).

If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

- If no drinking water pathway exists, a value of 20 pCi/L may be used.

122014

CY-OC-1 70-301 Revision 6 Page 56 of 140 TABLE 4.12.1-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1I)(2) LOWER LIMITS OF DETECTION (LLD) (3)

Surface and Air Vegetation Sediment Fish, Clams Analysis Ground Particulate (pCi/Kg, (pCi/Kg, dry) and Crabs Water and Air wet) (pCi/Kg, wet)

(pCi/I) Iodine (pCi/m3)

Gross Beta 4 0.01 H-3 2000(4)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1(4) 0.07(5) 60 Cs-134 15 0.05(6) 60 150 130 Cs-137 18 0.06(6) 80 180 150 La-140 15 Ba-140 60(7) 122014

CY-OC-1 70-301 Revision 6 Page 57 of 140 TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS

1. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.3.

2. Required detection capabilities for dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

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

For a particular measurement system, which may include radiochemical separation:

LLD~ =4.66* Sb E

V

2.22

Y

exp(-AýAt)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per Pico curie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec1 ), and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).

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

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CY-OC-170-301 Revision 6 Page 58 of 140 TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant Technical Specification 6.9.1.e and Control 6.1.2.6.4.

4. If no drinking water pathway exists, a value of 3000 pCi/L for tritium and 15 pCi/L for iodine-131 may be used.

5. For the air iodine sample

6. For the air particulate sample

7. Ba-140 and La-140 are in equilibrium 122014

CY-OC-170-301 Revision 6 Page 59 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 In accordance with the Oyster Creek Technical Specifications 6.8.4.b, a land use census shall be conducted and shall identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 ft 2 producing broad leaf vegetation. The census shall also identify within a distance of 3 miles the location in each of the 16 meteorological sectors all milk animal and all gardens greater than 500 square feet producing broadleaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in SURVEILLANCE REQUIREMENT 4.11.2.3, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to Control 6.2.2.4.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with CONTROL 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from this monitoring. Pursuant to CONTROL 6.2.2.4, identify the new location(s) in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.2.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted elevated release D/Q's in lieu of the garden census. Controls for broadleaf vegetation sampling in Table 3.12.1-1, Part 4.c shall be followed, including analysis of control samples.

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CY-OC-1 70-301 Revision 6 Page 60 of 140 3/412 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4,12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Oyster Creek Technical Specifications 6.8.4.b.3, analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the reason and corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above-required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3.

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CY-OC-1 70-301 Revision 6 Page 61 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.4 METEOROLOGICAL MONITORING PROGRAM CONTROLS 3.12.4 The meteorological monitoring instrumentation channels shown in Table 3.12.4.-I shall be operable.

APPLICABILITY: At all times.

ACTION:

a. With less than the minimum required instrumentation channels OPERABLE for more than 7 days, initiate an Issue Report outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

TABLE 3.12.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT ELEVATION MINIMUM INSTRUMENT OPERABLE

1. Wind Speed a 380 feet 1

b. 150 feet 1 C. 33 feet 1

2. Wind Directi on

a. 380 feet 1

b. 150 feet 1 C. 33 feet 1

3. AT

a. 380-33 1

b. 150-33 1 122014

CY-OC-1 70-301 Revision 6 Page 62 of 140 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE: The BASES contained in the succeeding pages summarize the reasons for the CONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.

3/4,3 INSTRUMENTATION BASES 3/4,3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The reactor service water system discharge line radioactivity monitor initiates an alarm in the Control Room when the alarm set point is exceeded. The alarm/trip set points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip set points for each of the noble gas monitors shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM. This will ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The radioactive gas monitors for the stack effluent and the Augmented Off gas Building exhaust ventilation have alarms which report in the Reactor Control Room. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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CY-OC-170-301 Revision 6 Page 63 of 140 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This CONTROL is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its concentration limit in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

The value 1E-8 is the limit for unidentified gross gamma or beta releases as per 10 CFR 20 Appendix B, Table 2, Column 2 "any single radionuclide ... other than alpha or spontaneous fission ... half life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ". This provides operational flexibility while providing reasonable assurance that dose will remain less than 0.1 rem/yr.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in references 25, 26, and 27.

Weekly grab samples for Service Water Effluent are composited for monthly tritium and gross alpha analysis and quarterly Sr-89/90 and Fe-55 analysis if activity is detected.

While discharging groundwater via the continuous release remediation pathway, the composite sample will be analyzed daily for principal gamma emitters and tritium. A monthly composite sample is analyzed for gross alpha, Sr-89/90, Fe-55, and Ni-63.

While discharging groundwater via the batch release mode remediation pathway, a grab sample is collected from each tank and analyzed for principal gamma emitters and tritium, a composite sample is analyzed monthly for gross alpha, Sr-89/90, Fe-55, and Ni-63.

Circulating Water Effluent is not included in Table 4.11.1.1.1-1, Radioactive Liquid Waste Sampling and Analysis Program since the Circulating Water is sampled as part of the Radiological Environmental Monitoring Program, Table 3.12.1-1, 3a, Waterborne, Surface downstream sample.

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CY-OC-170-301 Revision 6 Page 64 of 140 3/4.11.1.2 DOSE This CONTROL is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.113.

3/4.11.1.3 LIQUID RADWASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to their release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section IL.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents. Figure D-1-la, Liquid Radwaste Treatment Chem Waste and Floor Drain System and Figure D-1 -1b, Liquid Radwaste Treatment - High Purity and Equipment Drain System provides details of the Liquid Radwaste Treatment system.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This CONTROL is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column

1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to 122014

CY-OC-170-301 Revision 6 Page 65 of 140 compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in references 25, 26 and 27.

Tritium is sampled quarterly for gaseous effluents. Based on the consistency of the data from the quarterly sampling, the sampling frequency is adequate.

3/4.11.2.2 DOSE - NOBLE GASES This CONTROL is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.111. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This CONTROL is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix 1,10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRERSTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data 122014

CY-OC-170-301 Revision 6 Page 66 of 140 such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the AUGMENTED OFF GAS TREATMENT SYSTEM (AOG) ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents. Figure D-2-1, Gaseous Radwaste Treatment - Augmented Off gas System, Figure D-2-2, Ventilation System provide details of the Augmented Off Gas Treatment System and Figure D-2-3, AOG Ventilation System.

3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the doses remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the unit, including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a 122014

CY-OC-170-301 Revision 6 Page 67 of 140 variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190 and 10 CFR Part 20, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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CY-OC-170-301 Revision 6 Page 68 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this CONTROL provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Position on Environmental Monitoring, Revision 1, November 1979.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits in references 25, 26, and 27.

Site-specific research, which included the installation of a groundwater monitoring well network, has demonstrated that the groundwater pathway is not a potential pathway to man from the OCGS. The surface water into which the OCGS discharges is a marine estuary containing saline water that is not used as drinking water or irrigation water by man.

3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.

The best information from the door-to-door survey, from aerial survey, from visual survey or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 (500 ft 2 ) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/M 2 .

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CY-OC-1 70-301 Revision 6 Page 69 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.5.0 5.0 DESIGN FEATURES / SITE MAP (Provided FOR INFORMATION ONLY. Technical Specifications are controlling.)

5.1 Site map which will allow identification of structures and release points shall be as shown in Figure E-4.

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CY-OC-170-301 Revision 6 Page 70 of 140 6.0 ADMINISTRATIVE CONTROLS 6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) 6.1.1 In accordance with Oyster Creek Technical Specifications 6.9.1 .e, a routine radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of the following year.

6.1.2 The Annual Radiological Environmental Operating Reports shall include:

6.1.2.1 Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities (Radiological Environmental Monitoring Program -

REMP) for the report period. This will include a comparison with preoperational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

6.1.2.2 The reports shall also include the results of land use censuses required by CONTROL 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

6.1.2.3 The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results similar in format to that in Regulatory Guide 4.8, December 1975 of all the radiological environmental samples taken during the report period.

6.1.2.4 Deviations from the sampling program identified in CONTROL 3.12.1 shall be reported.

6.1.2.5 In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

6.1.2.6 The reports shall also include the following:

a. A summary description of the radiological environmental monitoring Program;

b. Map(s), covering sampling locations, keyed to a table giving distances and directions from the reactor;

c. The results of licensee participation in the Inter-laboratory Comparison Program, as required by CONTROL 3.12.3;

d. Identification of environmental samples analyzed when the analysis instrumentation was not capable of meeting the detection capabilities in Table 4.12.1-1.

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CY-OC-1 70-301 Revision 6 Page 71 of 140 6.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) 6.2.1 Routine radioactive effluent release reports covering the operation of the unit shall be submitted prior to May 1 of each year and in accordance with the requirements of 10CFR50.36a and section IV.B.1 of 10CFR 50 Appendix I.

6.2.2 The Radioactive Effluent Release Report shall include:

6.2.2.1 A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

6.2.2.2 An annual summary of hourly meteorological data collected over the previous year. This annual summary may be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. Alternatively, summary meteorological data may be retained and made available to the NRC upon request.

6.2.2.3 An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this OFF SITE DOSE CALCULATION MANUAL (ODCM).

6.2.2.4 Identify those radiological environmental sample parameters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway and the new location(s) for obtaining replacement samples should be identified. The report should also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

6.2.2.5 An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. The assessment of radiation doses shall be performed in accordance with this OFF SITE DOSE CALCULATION MANUAL (ODCM)

Part II Sections 1.5, 2.4, 2.5 and 3.2.

6.2.2.6 The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped Off Site during the report period (see Figure D-1-2):

a. Total volume shipped

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

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CY-OC-170-301 Revision 6 Page 72 of 140

d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms) 6.2.2.7 Unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents on a quarterly basis.

6.2.2.8 Changes to the PROCESS CONTROL PROGRAM (PCP) 6.2.2.9 Changes to the OFF SITE DOSE CALCULATION MANUAL (ODCM) in the form of a complete, legible copy of the ODCM.

6.3 RESPONSIBILITIES

6.3.1 Chemistry / Radwaste - Responsible for:

6.3.1.1 Implementing approval.

6.3.1.2 Compliance with specifications regarding routine dose assessment.

6.3.1.3 Radiological Environmental Monitoring Program 6.3.1.4 Technical consultation and review 6.3.2 Operations - Responsible for compliance with specifications regarding operation of the OCGS.

6.3.3 Engineering - Responsible for compliance with specifications regarding set point determination and implementation 6.3.4 Radiological Engineering - Responsible for technical consultation and review.

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CY-OC-170-301 Revision 6 Page 73 of 140 PART II - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS The liquid effluent monitoring instrumentation and controls at Oyster Creek for controlling and monitoring normal radioactive material releases in accordance with the Oyster Creek Radiological Effluent Technical Specifications are summarized as follows:

Reactor Building Service Water Effluent - The Reactor Building Service Water Effluent Line Monitor provides an alarm function only for releases into the environment.

Liquid radioactive waste flow diagrams are presented in Figures D-1-la, D-1-lb, and D-1-1c.

1.2 LIQUID EFFLUENT MONITOR SET POINT DETERMINATION Per the requirements of CONTROL 3.3.3.10, alarm set points shall be established for the liquid monitoring instrumentation to ensure that the release concentration limits of CONTROL 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS at the U.S. route 9 bridge over the discharge canal shall not exceed the concentrations specified in 10 CFR 20 Appendix B. Table 2, Column 2, for radionuclides and 2E-04 pCi/ml for dissolved or entrained noble gases).

1.2.1 LIQUID EFFLUENT MONITORS The set points for the liquid effluent monitors at the Oyster Creek Generating Station are determined by the following equation:

A F2 +BKG FLEC FI Where:

S = radiation monitor alarm set point (cpm)

A = activity concentration (ptCi/ml) of sample in laboratory: A = Y.Ci g = the primary conversion factor for the instrument - the ratio of effluent radiation monitor counting rate to laboratory activity concentration in a sample of liquid (cpm per pCi/mL).

F1 = flow in the batch release line (e.g. gal/min). Value not greater than the discharge line flow alarm maximum set point.

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CY-OC-170-301 Revision 6 Page 74 of 140 F2. = flow in the discharge canal (e.g. gal/min). Value not less than the discharge canal minimum flow.

BKG = Monitoring instrument background (cpm)

FLEC = fraction or multiple of unrestricted area LEC in aqueous effluent based on sample analysis. FLEC is the ratio between the LECi and Ci. FLEC is unitless. For example: LEC for Co-60 is 3E-6 ýiCi/mL. If the concentration in a expected release is 6E-6 j.LCi/mL; then FLEC is 6E-6/3E-6 = 2.

The term A represents the count rate of a solution having the same nuclide FLEC distribution as the sample and the LEC of that mixture.

Ci = concentration of radionuclide i in effluent, i.e., in a liquid radwaste sample tank, in reactor building service water (pCi/mL).

LEC, =the unrestricted area liquid effluent concentration (LEC) of radionuclide i, i.e., 10 CFR 20, Appendix B, Table 2, Column 2 quantity for radionuclide i (p.Ci/mL).

In the event gross radioactivity analysis alone is used to determine the radioactivity in an effluent stream or batch, FLEC is C/1E-8 (see 4.11.1.1.1),

Where:

C = the gross radioactivity concentration in effluent (ltCi/mL).

1E-8 = the unrestricted area LEC for unidentified radionuclides (jtCi/mL) from 4.11.1.1 .1.

If the gross activity concentration, C, is below the lower limit of detection for gross activity, the value, 1E-8 j+/-Ci/mL, or the equivalent counting rate (cpm/mL) may be substituted for the factor A FLEC A = 1 E-8 ICi/mL FLEC 1.2.2 SAMPLE RESULT SET POINTS Usually, when the concentration of specific radionuclides is determinable in a sample(s),

i.e., greater than the LLD, the alarm/trip set point of each liquid effluent radioactivity monitor is based upon the measurement of radioactive material in a batch of liquid to be released or in a continuous aqueous discharge.

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CY-OC-170-301 Revision 6 Page 75 of 140 1.2.3 ASSUMED DISTRIBUTION SET POINTS Alternatively, a radionuclide distribution that represents the distribution expected to be in the effluent if the concentration were high enough to be detectable, i.e., greater than the LLD, may be assumed. The representative distribution may be based upon past measurements of the effluent stream or upon a computed distribution.

1.3 BATCH RELEASES A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters or for gross beta or gross gamma activity before release. The result of the analysis is used to calculate the trip set point of the radioactivity monitor on the liquid radwaste effluent line to apply to release of the batch.

1.4 CONTINUOUS RELEASES The Reactor Building Service Water Effluent is sampled and analyzed weekly for 1-131, other principal gamma emitters. Results of analyses for the preceding week or for a period as long as the preceding 3 months are used to calculate the alarm/trip set point of the corresponding effluent radioactivity monitor in order to determine a representative value. In each case, whether batch or continuous, the monitor alarm/trip set point may be set at lower activity concentration than the calculated set point.

1.5 LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 Doses resulting from the release of radioiodines and particulates must be calculated to show compliance with Appendix I of 10CFR50. Calculations will be performed at least monthly for all liquid effluents as stated in SURVEILLANCE REQUIREMENT 4.11.1.2 and SURVEILLANCE REQUIREMENT 4.11.1.3.1 to verify that the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.1.2 The maximum dose to an individual from radioiodines, tritium, and radioactive particulates with half-lives of greater than eight days in liquid effluents released to unrestricted areas is determined as described in Reg. Guide 1.109. Environmental pathways that radioiodine, tritium, and particulates in liquid effluent follow to the maximally exposed MEMBER OF THE PUBLIC are assumed to be: exposure to shoreline deposits, ingestion of fish, and ingestion of shellfish. To assess compliance with CONTROL 3.11.1.2, the dose due to radioactive iodine, tritium, and particulates in liquid effluent is calculated to a person at the Route 9 bridge who consumes fish and shellfish harvested at that location.

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CY-OC-1 70-301 Revision 6 Page 76 of 140 1.5.1 MEMBER OF THE PUBLIC DOSE - LIQUID EFFLUENTS CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Oyster Creek Generating Station to those listed in Table 1.5.1-1.

TABLE 1.5.1-1 LIQUID PATHWAY DOSE LIMITS During Any Calendar Quarter During Any Calendar Year

< 1.5 mrem to total body < 3.0 mrem to total body

< 5.0 mrem to any organ < 10.0 mrem to any organ Per the SURVEILLANCE REQUIREMENTS of 4.11.1.2, the following calculation methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Oyster Creek. Applicable liquid pathways to man for Oyster Creek include shoreline exposure, and ingestion of saltwater fish and shellfish. The receptor location is provided in Table A-4.

1.5.2 SHORELINE DEPOSIT DOSE The shoreline exposure pathway dose is calculated generally in the form (based on Reg. Guide 1.109):

Rapj = 110000 UapWM F QiTiDaipj (1 - exp(-XiTb))

Where:

110000 = a constant that accounts for time and flow conversions Rapj = the annual dose to organ j (including the total body), through pathway p, to age group a Uap = the age dependent usage factor for the specific pathway. Usage factors for shoreline exposure are residence time on the shoreline (hours). Usage factors are provided in Reg. Guide 1.109 Table E-5. Usage factors specifically selected for Oyster Creek are presented in Table B-I.

W = the shore width factor. This adjusts the infinite plane gamma or beta dose factors for the finite size and shape of the shoreline. Different factors apply to different bodies of water. A factor of 0.1 is used for OC for 'discharge canal bank'.

M = the recirculation factor. The recirculation factor is a multiplier of 3.76 to account for recirculation of discharge water back into the intake. Although this occurs infrequently, it is assumed to occur for each liquid release.

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CY-OC-170-301 Revision 6 Page 77 of 140 F = the flow rate in the discharge canal in cubic feet per second Qi = the activity of the ith isotope in the release in curies Ti = the half life of the ith isotope in days Daipj =the age a, isotope i, pathway p, and organ j, specific dose conversion factor.

Pathway, isotope, age, and organ specific dose factors are obtained from Regulatory Guide 1.109 Appendix E, Tables E-6 through E-14 Xi = the decay constant of the ith isotope in years Tb = the long term buildup time, assumed to be 30 years Note: ki and Tb can use any time units as long as they are both the same. No transit delay (Tp from Reg. Guide 1.109) is assumed.

1.5.3 SHORELINE DOSE EXAMPLE 1 The following provides an example of the liquid dose calculation:

Initial parameters:

Canal flow rate 1E6 gpm (typical of normal full power operation)

Release: 10,000 gallons of water at 1E-3 LCi/ml Co-60 Problem: calculate shoreline whole body dose Uap = 67 (teenager) hours W =0.1 M = 3.76 F = 2228 [1E6 gpm *3785 ml /gal/ (60 sec/min

28316 ml/ft3) = 2228 CFS]

Qi = 0.03785 Ci [1E-3uCi/ml

10000gal

3785ml/gal/1E6 uCi/Ci = 0.03785 Ci]

Ti = 1920 [5.27 years*365 days/yr = 1.92E3 days)

Mi = 1.31E-1 [0.693/(5.27yrs)]

Tb = 30 years Daipj = 1.7E-8 mrem/hr / pCi/m 2 Gamma dose factor Calculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope Rapj = 110000-67.0.l*3.76 - 0.03785" 1920* 1.7E- 8 * (I - exp(-1.3E - I

30))

2228 1 Rapj =1.5 IE -3 mrem: teen: wholebody 122014

CY-OC-1 70-301 Revision 6 Page 78 of 140 1.5.3.1 SHORELINE DOSE EXAMPLE 2 The following provides an example of the liquid dose calculation for groundwater remediation discharge:

Initial parameters:

Canal flow rate 1E6gpm (typical of normal full power operation)

Release: 50 gpm for 7 days at 1E-8 pCi/mI Co-60 Problem: Calculate shoreline whole body dose Uap = 67 (teenager) hours W =0.1 M = 3.76 F = 2228 [1E6 gpm *3785 ml / gal / (60 sec/min

28316 ml/ft3) = 2228 CFS]

Qi = 1.91E-5 Ci [1E-08 pCi/ml*50gpm*7days*24hr/day*60 min/hr*3785ml/gal/1E+6 pCi/Ci]

Ti = 1920 [5.27 years*365 days/yr = 1.92E+03 days)

Xi = 1.31E-1 [0.693 /(5.27 yrs)]

Tb = 30 years Daipj = 1.7E-8 mrem/hr / pCi/m 2 External Dose factor Calculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope Rapj 110000 67*0.1*376

37 - 1.9 1E- 5"*1920"*1.7E -8"* (1- exp(-l1.31E - 1*30))

2228 j Rapj = 7.60E- 7 mrem: teen: wholebody 1.5.4 INGESTION DOSE - LIQUID Ingestion dose pathway calculations are similar to those for the shoreline dose, with minor changes in constants, removal of the shore width factor, and inclusion of the bioaccumulation factor:

Rapj = 1100 UapMQiBipDaipj F

Where:

Bip = the stable element bioaccumulation factor for pathway p for the ith isotope No transit delay is assumed Pathway, isotope, age, and organ specific dose factors are obtained from Regulatory Guide 1.109 Appendix E Tables E-7 through E-14. Bioaccumulation factors are 122014

CY-OC-1 70-301 Revision 6 Page 79 of 140 provided in Reg. Guide 1.109 Table A-1. Usage factors are provided in Reg. Guide 1.109 Table E-5. Usage factors specifically selected for Oyster Creek are presented in Table B-1.

The radionuclides included in the periodic dose assessment per the requirements of CONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of CONTROL 3/4.11 .1.1, Table 4.11.1.1.1-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Table 4.11.1.1.1-1.

1.5.5 INGESTION DOSE CALCULATION EXAMPLE 1 The following provides an example of the liquid dose calculation:

Initial parameters:

Canal flow rate 1 E6 gpm (typical of normal full power operation)

Release: 10000 gallons of water at 1E-3 .tCi/mL Co-60 Problem: calculate teen whole body dose from saltwater fish ingestion Rapj = 100 UapM QiBipDaipj F

Uap = 16 (teenager) Kg M = 3.76 F = 2228 [1E6 gpm *3785 ml/gal/(60 sec/min

28316 ml/ft3) = 2228 CFS]

Qi = 0.03785 Ci [1E-3uCi/mL

10000gal

3785mL/gal /1 E6 uCi/Ci = 0.03785 Ci]

Bip = 100 Daipj = 6.33E-6 mrem / pCi Calculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotope Rap

~10016*3. 76 Rapj =I100 12 37 0.03785 *100 6.33E-6 2228 h Rapj = 7.12 E - 4 mrem *teen *wholebody 122014

CY-OC-1 70-301 Revision 6 Page 80 of 140 1.5.5.1 INGESTION DOSE CALCULATION EXAMPLE 2 The following provides an example of the liquid dose calculation for ground water remediation discharge:

Initial parameters:

Canal flow rate 1E6 gpm (typical of normal full power operation)

Release: 50 gpm for 7 days at 700,000 pCi/I H-3 Problem: calculate teen whole body dose from saltwater fish ingestion Rap] = 1100 Uap QiBipDaipj F

Uap = 16 (teenager) Kg M = 3.76 F = 2228 [1E6 gpm *3785 ml /gal /(60 sec/min

28316 mlI/ft3) = 2228 CFS]

Qi = 1.34 Ci [7E+5 pCi/l*50gpm*7days*24hr/day*60 min/hr*3.785 I/gall 1E+12 pCi/Ci]

Bip = 0.90 (Regulatory Guide 1.109, Table A-I)

Daipj = 1.06E-07 mrem / pCi Calculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotope Rapj =100 163.76 1.340.9 .06E-7 2228 i Rapj = 3.80 E - 6 mrem :teen : wholebody 1.5.6 PROJECTED DOSE - LIQUID The projected doses in a 31 day period are equal to the calculated doses from the current 31 day period.

1.6 REPRESENTATIVE SAMPLES A sample should be representative of the bulk stream or volume of effluent from which it is taken. Prior to sampling, large volumes of liquid waste should be mixed in as short a time interval as practicable to assure that any sediments or particulate solids are distributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks (collection or sample test tanks) should be capable of recirculating at a rate of not less than two tank volumes in eight hours. Minimum recirculation times and methods of recirculation are controlled by specific plant procedures.

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CY-OC-170-301 Revision 6 Page 81 of 140 2.0 GASEOUS EFFLUENTS 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS The gaseous effluent monitoring instrumentation and controls at Oyster Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent CONTROLS are summarized as follows:

(1) Main Stack The main stack receives normal ventilation flow from the reactor building, new radwaste, old radwaste, process discharge flow from the augmented off gas system (AOG), condenser off gas flow if AOG is not in service, and normal ventilation flow from portions of the turbine building, predominantly the condenser bay area. Reactor building and turbine building flow is not normally processed or filtered. Reactor Building flow may be manually or automatically directed through the Standby Gas Treatment System (SBGTS) which has particulate and charcoal filtration. Off gas flow is processed through AOG or through a 30-minute delay pipe prior to release. Flow from the 'new' and 'old' radwaste buildings is HEPA filtered. Releases through the main stack are monitored for noble gases using the RAGEMS I system and sampled for iodine, particulates and tritium. The plant stack is considered to be a true elevated release point.

(2) Turbine Building Vent The Turbine building vent is monitored for noble gases by the RAGEMS II system and sampled for iodine, particulates and tritium. It discharges on the west side of the turbine building approximately at roof height and is considered to be a ground level release. It ventilates the turbine floor and other areas of the turbine building. Flow through this release point is not filtered.

(3) Feed Pump Room Vent The feed pump room vent is monitored by RAGEMS II. It discharges on the east side of the turbine building below roof height and is considered to be a ground level release. It ventilates the reactor feed pump room. Flow through this release point is not filtered.

(4) Augmented Off Gas Building Vent Off gas Building HVAC is released through a ground level release from the building. Off Gas process flow is not released through the building ventilation, but is routed to the stack plant. A ventilation monitoring system monitors for noble gas and samples for particulate and iodine.

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CY-OC-1 70-301 Revision 6 Page 82 of 140 (5) Isolation Condensers The isolation condensers are a ground level release. The predominant isotope through this potential release point is tritium as a consequence of the forced evaporation of condensate transfer water when the isolation condensers are initiated. Releases are neither monitored nor is the release process flow sampled. Releases of tritium are evaluated based on liquid samples of the input and the volume used.

Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation controls are presented in Figures D-2-1 and D-2-2.

2.2 GASEOUS EFFLUENT MONITOR SET POINT DETERMINATION 2.2.1 PLANT VENT Per the requirements of CONTROL 3.3.3.11, alarm set points shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of CONTROL 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin. Based on a grab sample analysis of the applicable release (i.e., of the Stack, Off gas process flow, etc.), the radiation monitoring alarm set points may be established by the following calculation methods. A set point of a monitor of an elevated release, e.g., from the stack, may be calculated using the equation:

s = 1.6 Z Ci S=1.6~f Z (CiDFSi)+Bg Where:

S = the alarm set point (cpm) h = primary conversion factor of the instrument - monitor response to activity concentration of effluent being monitored, cpm/(pLCi/cm 3 ). Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Ci = relative concentration of noble gas radionuclide i in effluent at the point of monitoring (gCi/cm 3) 1.06 = 500 mrem/year /472 (conversion of cfm to cc/sec)

DFSi = factor converting elevated release rate of radionuclide i to total body dose equivalent rate at the location of potential exposure. Units are: mrem/(yr(jiCi/sec)).

From Table A-I.

f = flow of gaseous effluent stream being monitored, i.e., stack flow, vent flow, etc.

(ft3 /min) 122014

CY-OC-1 70-301 Revision 6 Page 83 of 140 BKG = Monitoring instrument background (cpm or mR/hr) 2.2.2 OTHER RELEASE POINTS The set point of a monitor of a ground-level or vent release, e.g., from the turbine building vent or the AOG building, may be calculated with the equation:

h

Ci S = 1.06 [h ]) + Bkg Where:

DFVi = factor converting ground-level or vent release of radionuclide i to the total body dose equivalent rate at the location of potential exposure. Units are: mrem-m 3/p.Ci-year From Table A-I.

X/Q = atmospheric dispersion from point of ground-level or vent release to the location of potential exposure (sec/m 3) from Table 2.2.2-1.

The atmospheric dispersion, X/Q, and the dose conversion factor, DFSi, depend upon local conditions. For the purpose of calculating radioactive noble gas effluent monitor alarm set points appropriate for the OCGS, the locations of maximum potential Off Site exposure and the reference atmospheric dispersion factors applicable to the derivation of set points are given in Table 2.2.2-1.

Symbols for this equation were defined in Section 2.2.1.

TABLE 2.2.2-1 RECEPTOR LOCATIONS AND DISPERSION FOR GASEOUS MONITOR SET POINTS Discharge Point Receptor Location Atm. Dispersion Sector Distance(m) (sec/mi3)

Ground-level or vent ENE 338 4.59 E-5 Stack SW 229 N/A 2.2.3 RADIONUCLIDE MIX FOR SET POINTS For the purpose of deriving a set point, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:

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CY-OC-170-301 Revision 6 Page 84 of 140 2.2.3.1 Preferably, the radionuclide distribution is obtained by gamma isotopic analysis of identifiable noble gases in effluent gas samples. Results of the analyses of one or more samples may be averaged to obtain a representative spectrum.

2.2.3.2 In the event a representative distribution is unobtainable from recent measurements by the radioactive gaseous waste sampling and analysis program, it may be based upon past measurements.

2.2.3.3 Alternatively, the total activity concentration of radioactive noble gases may be assumed to be Xenon-1 33 as found in Reg Guide 1.97.

2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS - 10 CFR 20 2.3.1 SITE BOUNDARY DOSE RATE - NOBLE GASES CONTROL 3.11.2.1a limits the dose rate at the SITE BOUNDARY due to noble gas releases to < 500 mrem/yr, total body and < 3000 mrem/yr, skin. Radiation monitor alarm set points are established to ensure that these release limits are not exceeded.

In the event any gaseous releases from the station results in an alarm set point (as determined in Section 2.2) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed.

2.3.1.1 TOTAL BODY DOSE RATE The total body dose equivalent rate from radioactive noble gases discharged from an elevated point (stack above building wake) is calculated with the equation:

DG- Z** i'si From a ground-level release (building vent) the total body dose equivalent rate is:

DG= QiPYVi QV, Where:

DG = total body dose equivalent rate due to irradiation by radioactive noble gas (mrem/hr)

Qi = average discharge rate of noble gas radionuclide i released during the averaging time (p.Ci/hr)

PyVi = factor converting time integrated ground-level concentration of noble gas nuclide i to total body dose mrem - m3. See Table A-2.

pCi - sec xX = atmospheric dispersion factor from the OCGS to the Off Site location of interest QV (sec/m 3) from Table 2.3.1.3-1 122014

CY-OC-170-301 Revision 6 Page 85 of 140 PySi factor converting unit noble gas nuclide i stack release to total body dose at ground level received outdoors from the overhead plume (mrem/[tCi). See Table A-2 The noble gas plume gamma-to-total body dose factors, PSi at designated locations are derived from meteorological dispersion data with the USNRC RABFIN software computer code or similar computer program implementing Reg Guide 1.109, Appendix B. The noble gas semi-infinite cloud gamma-to-total body dose factors, P',Vi, are derived from Reg Guide 1.109, Revision 1, Table B-I, Column 5.

2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE Calculate the dose from a release of 100 Ci of Xe1 33 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release DG = X QiPyVi QV, X/Qv =4.59E-5 sec/m3 (Table 2.3.1.3-1)

Qi 1 E8 gCi/hr [1 00Ci*1 E6 gCi/Ci]

P'yVi 3 9.33E-6 mrem-m / ltCi-sec DG = 4.59E-5Z 1E8*9.33E-6 DG = 0.043 mrem /hr 2.3.1.3 SKIN DOSE RATE The dose equivalent rate to skin from radioactive noble gases is calculated by assuming a person at ground level is immersed in and irradiated by a semi-infinite cloud of the noble gases originating in airborne effluent. It is calculated for each air effluent discharge point with the equation:

DB = X . Qi(SBi+1.11AyVi)

Q where:

DB dose rate to skin from radioactive noble gases (mrem/hr)

X

-- :=Atmospheric dispersions from gaseous effluent discharge point to ground-level location of interest (sec/m 3) from Table 2.3.1.3-1.

Qi discharge rate of noble gas radionuclide i (liCi/hr) 122014

CY-OC-1 70-301 Revision 6 Page 86 of 140 SBi = factor converting time integrated ground-level concentration of noble gas radionuclide i to skin dose from beta radiation mrem - m3 from Table A-2.

pCi

sec AyVi = factor for converting time integrated, semi-infinite concentration of noble gas radionuclide i to air dose from its gamma mrad - m from Table A-2.

pCi

sec The noble gas beta radiation-to-skin-dose factors, SBj and the noble gas gamma-to-air dose factors, AyV1 , are derived from Reg Guide 1.109, Revision 1, Table B-i, columns 3 and 4 respectively. A tabulation of these factors used to compute noble gas-to-dose equivalent rate at 338 meters ENE for ground-level or vent and 544 meters SE for stack from the OCGS is in Table A-2.

The dose equivalent rate is calculated with the meteorological dispersion data given in Table 2.3.1.3-1.

TABLE 2.3.1.3-1 RECEPTOR LOCATIONS AND DISPERSION FOR SITE BOUNDARY DOSE RATES Discharge Point Receptor Location Atm. Dispersion Sector Distance (m) (sec/m3)

Ground Level ENE 338 4.59 E-5 or Vent Stack SE 544 1.05 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") that implements the requirements of Regulatory Guide 1.109 may be used.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented above may be used for evaluating the gaseous effluent dose rate.

2.3.1.4 EXAMPLE SKIN DOSE RATE Calculate the skin dose from a release of 100 Ci of Xel 33 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release:

x DB = - Qi(SBi + 1.llAyVi)

QI X/Q =4.59 E-5 sec/m3 Qi = 1E8 itCi/hr SBi = 9.71 E-6 mrem/ýtCi/ m3/sec3 A'yVi = 1.12E-5 mrad/yr per p.Ci/m 122014

CY-OC-170-301 Revision 6 Page 87 of 140 DB = 4.59E- 51 lE8(9.71E-6+ 1.11 *1.12E -5)

DB = O.102mrad / hr 2.3.2 SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES 2.3.2.1 METHOD - SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES The dose rate Off Site due to the airborne release of 1-131, 1-133, tritium, and particulates with half-lives greater than 8 days is limited to no more than 1500 mrem/yr to any organ in CONTROL 3.11.2.1 b. Evaluation of compliance with CONTROL 3.11.2.1 b is based on the sampling and analyses specified in TABLE 4.11.2.1.2-1.

Since the dose rate cannot be resolved within less than the sample integration or compositing time, the contribution of each radionuclide to the calculated dose rate will be averaged no more than 3 months for H-3, Sr-89, Sr-90, and alpha-emitting radionuclides and no more than 31 days for other radionuclides. These are their usual sample integration or compositing times. The equation used to assess compliance of radioiodine, tritium, and radioactive particulate releases with the dose rate limit is:

11X DRp = 1E6- I RaDFAijaQe X e iQe Where:

1E6 = conversion pCi/jiCi DRp = the average dose rate to an organ via exposure pathway, p (mrem/yr).

DFAija = inhalation dose factors due to intake of radionuclide i, to organ j age group a (mrem/pCi) from Reg. Guide 1.109 Appendix E.

Ra = age group dependent inhalation respiratory rate (usage factor) m3/yr from Table B-1 x = annual average relative airborne concentration at an Off Site Qe location due to a release from either the Stack or a vent, i.e. release point, e (sec/m 3) from Table 2.3.2.1-1.

Qei = release rate of radionuclide i from release point, e during the period of interest (p.Ci/sec).

For real-time meteorology and on an annual average basis, the location of the maximum ground-level concentration originating from a vent release will differ from the maximum ground-level concentration from a stack release. When assessing 122014

CY-OC-1 70-301 Revision 6 Page 88 of 140 compliance with CONTROL 3.11.2.1 b for tritium, iodine, and particulate, the air dispersion (X/Q) values are provided in Table 2.3.2.1-1.

TABLE 2.3.2.1-1 LOCATION OF MAXIMUM EXPOSURE RE BY INHALATION Discharge Point Receptor Location Atm. Dispersion Sector Distance (m) (sec/m3)

Ground Level or Vent ENE 338 4.59 E-5 Stack SE 937 1.25 E-8 Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closest hypothetical individual located at:

Stack SE 805 1.29 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") that implements the methods of Regulatory Guide 1.109, may be used.

2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATION Calculate the child thyroid dose rate from a release of 100 jtCi/hr of 1131 from a ground level release:

I17 DRp = 1E6-YRaDFA~iaQeiX e

Qe Ra = 3700 m3/yr DFAija = 4.39E-3 mrem/pCi Qei = 0.028 ýtCi/sec 3 [1 00tpCi/hr /3600 sec/hr = 0.02778]

X/Qe = 4.59 E-5 sec/mi DRp = IE6Z3700* 4.39E - 3

0.028* 4.59E - 5 DRp = 20.9mrem / yr 2.4 NOBLE GAS EFFLUENT DOSE CALCULATIONS - 10 CFR 50 Doses resulting from the release of noble gases must be calculated to show compliance with Appendix I of 10CFR50. Calculations will be performed at least monthly for all gaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2 to verify that the dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.

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CY-OC-170-301 Revision 6 Page 89 of 140 2.4.1 UNRESTRICTED AREA DOSE - NOBLE GASES CONTROL 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly air dose limits shown in Table 2.4.1-1.

TABLE 2.4.1-1 ANNUAL AIR DOSE LIMITS During any calendar quarter During any calendar year

_ 5 mrad gamma-air < 10 mrad gamma-air

_ 10 mrad beta-air *20 mrad beta-air The method used to calculate the air dose at the critical location due to noble gas is described by the following equations. The limits are provided in CONTROL 3.11.2.2 for air dose Off Site due to gamma and beta radiations from effluent noble gas.

2.4.1.1 AIR DOSE METHOD For Gamma Radiation:

Dose Y

= AyVi y -vQvi + A ySiQsi i=1 Q For Beta Radiation Dosep1 =I JAP~i~-eQei e =1 Q Where:

Dose y =the gamma dose during any specified time period (mrad).

Dose f3 =the beta dose during any specified time period (mrad).

AyVj = the air dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per [tCi/m 3 ). Table A-2 AySi = the factor for air dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per pCi), Table A-3.

Ap3 = the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per jiCi/m 3). Table A-3 X--e X1

-- =the annual average relative concentration for areas at or beyond the site boundary for Q Q releases from either the Stack or ground vent at the critical location (sec/m 3), Table 2.4.1.1-1 122014

CY-OC-170-301 Revision 6 Page 90 of 140 Qvi = amount of radionuclide i released from vents (ljCi).

Qsi = amount of radionuclide i released from the Stack (ltCi).

Qei = amount of radionuclide i released from release point e(pLCi).

Noble gases may be released from the ground level vents and stack. The quantity of noble gas radionuclides released will be determined from the continuous noble gas monitors and periodic isotopic analyses. The maximum Off Site gamma radiation dose rate to air from noble gases discharged from either the stack or from building vents occurs at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGS for building vents. Values of AySi depend upon the meteorological conditions and the location of exposure and are calculated using the NRC RABFIN code or similar one in accordance with Reg. Guide 1.109, Appendix B, Section 1. AyVi and ABi are derived from Reg. Guide 1.109, Table B-1 for a semi-infinite cloud, independent of meteorology or location. Values of AySi, AyVi and ABi used to calculate the noble gas radiation dose to air at 805 meters SE of the OCGS for the stack and 338 meters ENE of the OCGS for building vents are in Table A-3. Reference atmospheric dispersion from the OCGS to 805 meters SE for the stack and 338 meters ENE for building vents is given in Table 2.4.1.1-1.

TABLE 2.4.1.1-1 RECEPTOR LOCATIONS AND DISPERSION FOR AIR DOSE Discharge Point Receptor Location Atm. Dispersion Sector Distance (W) (sec/m3)

Ground Level ENE 338 4.59 E-5 or Vent Stack SE 805 1.29 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") that implements the requirements of Reg. Guide 1.109 may be used.

2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION Calculate the gamma air dose from a release of 1 Ci per hour of Xe133 for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release and 10OCi per hour for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from an elevated release:

Dose'y = AyVi-vQvi + AySiQsi i1 Q AyVi = 1.12E-5 mrad - 3 m3 /Ci - sec X/Q = 4.59 E-5 sec/mi Qvi = 1E7 RCi [lCi/hr*10hrs*lE6 RCi/Ci]

A7Si = 1.03E-1 2 mrad / jiCi Qsi = 1E9 piCi [10OCi/hr*10hrs*lE6 tiCi/Ci]

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CY-OC-170-301 Revision 6 Page 91 of 140 n

Dose' = -1.12E-5*4.59E-5*1E7+1 .03E-12*IE9 i=1 Dose' =Z15.14E- 3 +1.03E- 3 i=1 Dosey = 6.17E - 3mrad Note how the ground level portion has a higher dose contribution per unit activity than the elevated portion.

2.4.1.3 INDIVIDUAL PLUME DOSE METHOD The method for dose to an individual from noble gases is essentially identical with the air dose method except that different dose factors apply. Also, since dose to the skin combines the contribution from gamma and beta emissions, the gamma dose must be added to the beta dose to obtain a total skin dose.

For Total Body:

Dose(t) = IPyVivQvi+PY.SiQsi 11 Q For Skin Dose(s)= e Spi.-eQei + Dose(t) e 11 Q Where:

Dose(t) =the total body dose during any specified time period (mrem).

Dose(s) = the skin dose during any specified time period (mrem).

PyVi = the plume dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per 4Ci/m 3). Table A-5 PYS, = the factor for plume dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per jiCi), Table A-5.

Spi = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per p.Ci/m 3) from Table A-5.

122014

CY-OC-170-301 Revision 6 Page 92 of 140 X X = the annual average relative concentration for areas Q Q at or beyond the site boundary for releases from either the Stack or ground vent at Table 2.5.1. the critical location (sec/m 3

) from Qvi = amount of radionuclide i released from vents (gCi).

Qsi = amount of radionuclide i released from the Stack

(ýCi).

Qei = amount of radionuclide i released from release point e (GtCi).

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CY-OC-1 70-301 Revision 6 Page 93 of 140 2.5 RADIOIODINE, PARTICULATE AND OTHER RADIONUCLIDES DOSE CALCULATIONS - 10 CFR 50 Doses resulting from the release of radioiodines and particulates must be calculated to show compliance with Appendix I of 10CFR50. Calculations will be performed at least monthly for all gaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2 and SURVEILLANCE REQUIREMENT 4.11.2.3 to verify that the dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.

The maximum dose to an individual from radioiodines, tritium, and radioactive particulates with half-lives of greater than eight days in gaseous effluents released to unrestricted areas is determined as described in Reg. Guide 1.109. Environmental pathways that radioiodine, tritium, and particulates in airborne effluent follow to the maximally exposed MEMBER OF THE PUBLIC as determined by the annual land use survey and reference meteorology will be evaluated. The seasonality of exposure pathways may be considered. For instance, if the most exposed receptor has a garden, fresh and stored vegetables are assumed to be harvested and eaten during April through October. Fresh vegetables need not be considered as an exposure pathway during November through March. To assess compliance with CONTROL 3.11.2.3, the dose due to radioactive iodine, tritium, and particulates in airborne effluent is calculated to a person residing 972 meters ESE of the OCGS for ground-level or vent and 937 meters SE of the OCGS for stack. Reference atmospheric dispersion and deposition factors are given in Table 2.5-1.

TABLE 2.5-1 DISPERSION FOR 10CFR50 DOSES Discharge Point Dispersion Deposition X/Q (sec/m )3 D/Q(1/m 2)

Ground Level or Vent 5.13 E-6 1.68 E-8 Stack 1.25 E-8 2.39 E-9 The environmental pathways of exposure to be evaluated are: inhalation, irradiation from ground deposition, and ingestion of milk (cow and goat are treated separately), meat, and vegetables. Eight organs are considered: Bone, Liver, Total Body, Thyroid, Kidney, Lung, GI-LLI (Gastro-Intestinal tract / Lower Large Intestine), and Skin. Four different age groups are considered: Infants, Children, Teens, and Adults. Doses are calculated to a 'receptor' - a person who inhales the airborne activity and resides in a location with ground deposition, and eats and drinks the foodstuffs produced. The maximally exposed individual is conservatively assumed to reside at the location of the highest sum of the inhalation and ground plane doses, while eating and drinking foodstuffs transported from the locations that are highest for those pathways. Receptor locations are provided in Table A-4.

Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") that implements the requirements of Reg Guide 1.109 may be used.

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CY-OC-170-301 Revision 6 Page 94 of 140 2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES.

Dose from the inhalation pathway is generally in the form:

Dja = RaT L-QiDFAi/aExp(-)uTr) iQ Where:

Dja = the dose to the organ j (of eight) of age group a (of four)

Ra = the respiration rate for age group a from Table B-1 T = the duration of the release in fraction of a year X = The atmospheric dispersion to the point of interest (the 'receptor') in sec/m 3 from Table 2.5-1 Qi = The release rate of radionuclide i (pCi/sec)

DFAija = The inhalation dose conversion factor (mrem per pCi) for radionuclide i to organ j of age group a from Reg. Guide 1.109 Appendix E.

Xi = decay constant of isotope i: 0.693/ Half life in years Tr = plume transit time from release to receptor in years Mi and Tr may be in any time units as long as they are the same Note that a 'depleted X/Q' (dX/Q) is applicable to particulates only, which accounts for the natural settling and lack of surface reflection of particulates to estimate the downwind concentration accounting for these removal processes. Depleted X/Q will be slightly smaller than the X/Q. This is not used in the ODCM for simplicity. Using the X/Q is therefore slightly conservative compared to the dX/Q.

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CY-OC-1 70-301 Revision 6 Page 95 of 140 2.5.2 EXAMPLE CALCULATION - INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES Calculate the dose to child lung from inhalation from a ground level release of 100 pLCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-AiTr)=1).

Dja = RaT -- QiDFAija Dja = the dose to the organ j (of eight) of age group a (of four)

Ra = 3700 m3/yr T = 0.00114 yrs [10 hrs / 8760 hrs / yr]

X 5.13 E-6 sec/m3 s

Qi = 2.78E3 pCi/sec [100 pCi

1E6 pCi/jiCi / (10 hrs*3600 sec hr)]

DFAija =1.91 E-3 mrem / pCi Dja = 3700* 0.00114* 5.13E- 6 *2.78E3

1.91E - 3 Dja = 1. 15E - 4mrem 2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDES Dose from the ingestion pathways is more complex and is broken out here into multiple steps:

2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHER THAN TRITIUM The concentration of a radionuclide in a foodstuff (other than tritium - see section 2.5.3.3 for tritium) is dependent on the atmospheric deposition, the biological uptake into the food, various decay times (plume travel, harvest to table, etc.) and is generally of the form:

Where:

Civ = the concentration (pCi/kg) of radionuclide i in vegetation Qi = the release rate of isotope i in pCi/hr D =The atmospheric deposition to the point of interest (the 'receptor') in 1/M2 from Q

Table 2.5-1.

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CY-OC-170-301 Revision 6 Page 96 of 140 Civ D Qi{r(l - EXP(-MEiTe)) + Biv(1 - EXP(-AiTb)) EXP(-ATh)EXP(--IiTr)

Q Yv),Ei PMi r = the retention coefficient for deposition onto vegetation surfaces (1.0 for iodines, 0.2 for particulates) ki = the decay constant of radionuclide i; 0.693/half life in hours XEi =the effective removal constant which is the sum of Xi + ?,w where Xw is the weathering constant, 0.0021/hr Te = duration of crop exposure during the growing season in hours. This is not the entire duration of the growing season, and is different for leafy vegetable and fruit/grain/vegetables. Provided in Table E-15 of Reg. Guide 1.109 or Table B-1.

2 Yv = agricultural yield Kg of vegetation per m 2 , typically 0.7 kg/M Biv = soil uptake concentration factor for transfer of the radionuclide i from the soil to the vegetation through normal root uptake processes in pCi/kg in vegetation per pCi/Kg in soil. Values are provided in Reg. Guide 1.109 Table E-1.

Tb = the length of time the soil is exposed to contaminated inputs - nominally 30 years (2.63E5 hr) 2 P = effective soil density in kg/mi2 normally 240 kg/M Th = holdup time, the time the foodstuff is in transit between harvest and consumption in hours Tr = plume transit time from release to receptor in hours 2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHER THAN TRITIUM.

Calculate the forage and vegetation concentration from a ground level release of 100 ptCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (plume transit time is ignored Tr=0, EXP(-XiTr)=I):

Civ D Qi{ r(1 - EXP(-MiTe)) + Biv(1 - EXP(-).iTb)) EXP(_XiTh)EXP(_XiTr)

QYvmEi PM 2

D/Q = 1.67E-8 m Qi = 1E7 pCi/hr [100.pLCi

1E6 pCi/iCi / 10 hr]

r = 0.2 Xi = 1.5E-5/hr [0.693 / (5.27yr

8760 hr/yr)]

XEi = 2.12E-3 /hr [1.5E-5 + 0.0021]

Te = 720 hr [grass-cow-milk-man pathway value]

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CY-OC-170-301 Revision 6 Page 97 of 140 2

Yv = 0.7 kg/mr Biv = 9.4E-3 Tb = 2.63E5 hr2 P = 240 kg/mr Th = 24.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Civ = 1.67E - 8 *1E7

{ 0.2* (1- EXP(-2.12E -3*720)) +

9.4E - 3 * (1 - EXP(-1.5E - 5

2.63E5))

EXP(-1.5E.-75**.O) 1 240

1.5E - 5 Civ =1.67E-8*1E7{

0.2 * (1 - EXP (- 1.53))

1.48E - 3 9.4E - 3 * (1 - EXP (-3 .95))

3.6E - 3

+

}EXP (-0 )

105 Civ =1.67E-1{. *1" Civ = 18.0 pCi / Kg 2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION Since tritium is assumed to be released as tritiated water (HTO), the concentration of tritium in a foodstuff is dependent on atmospheric dispersion like a gas, rather than particulate deposition as for other radionuclides for foodstuff uptake. Further, the concentration of tritium in food is assumed to be based on equilibrium between the concentration of the tritium in the atmospheric water and the concentration of tritium in the water in the food. Concentration of tritium in vegetation can be calculated generally in the form (a plume transit decay term: EXP(-XiTr) is ignored since plume travel times are very short compared to the half life):

Ctv = 1000Qt x *0.75

0.5 Q H Where:

Ctv = the concentration (pCi/kg) of tritium in vegetation 1000 =g per kg Qt = the release rate of the tritium in pCi/ sec 122014

CY-OC-1 70-301 Revision 6 Page 98 of 140 X/Q = the atmospheric dispersion at the vegetation point, sec/mr3 from Table 2.5-1 0.75 = the fraction of vegetation that is water 0.5 = the effective ratio between the atmospheric water concentration and the vegetation concentration H = the absolute humidity g/m 3 . Absolute humidity is seasonally dependent, varying from as little as 1 in the winter to as much as 20 in the summer. Monthly average values derived from historical data are provided in Table B-2.

2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION.

Calculate the forage and vegetation concentration from a ground level release of 100 1iCi of H-3 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-XiTr)=1):

0.5 Ctv = I000Qt X *0.75*

Q H Qt = 2778 pCi/sec [1 0OuCi

1E6 pCi/uCi / (1Ohrs*3600sec/hr)]

X/Q = 5.13E-6 sec/m3 H = 5 g/m 3 (assumed for this example) 0.5 Ctv = 2778

1000 *5.13E - 6

0.75*

5 Ctv = 1.07 pCi / kg 2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT Meat and milk animals are assumed to eat both pasture grass and stored feed. During a fraction of the year, they may be assumed to be exclusively on stored feed, outside of the growing season. If using annual average release, the fraction of stored and fresh feed must be accounted for with fractions, otherwise (as in this ODCM), the fresh pasture pathway is turned on or off depending on the growing season.

The concentration of a radionuclide in the animal feed is calculated as follows:

Civ = FpCis+ (1- Fp)Cis(l - Fs) + CipFs(l- Fp)

Where:

Fp = the growing season pasture factor: 1 if not growing season, 0 if in growing season 122014

CY-OC-170-301 Revision 6 Page 99 of 140 Fs = the fraction of the daily feed from fresh pasture from Table B-1 or Exhibit E-15 from Reg. Guide 1.109.

Cip = the concentration in the fresh pasture feed (Civ from section 2.5.3.2 with Th = 0 for immediate consumption)

Cis = the concentration in stored feed (Civ from section 2.5.3.2 with Th = 90 days)

The concentration in the milk is then based on this feed concentration:

Cim = FmCivQfEXP (-)LiTf)

Where:

Cim = the concentration in milk pCi/I Fm = the transfer coefficient of intake to concentration in the milk (dIl) from Reg. Guide 1.109 Table E-1.

Qf = feed intake rate Kg/d from Reg. Guide 1.109 Table E-3.

2X = radionuclide i decay constant in 1/days Tf = transport time from milk production to consumption (2 days for milk)

The Goat milk pathway may be similarly evaluated:

Cim = FgCivQIfEP (-2iTf)

Where:

Fg = the transfer coefficient of intake to concentration in the milk (d/I) for goats from Reg. Guide 1.109 Table E-2.

And for meat:

CO = FfCivQJEXP(-XiTs)

Where:

Ff = the transfer coefficient of intake to concentration in the meat d/kg from Reg.

Guide 1.109 Table E-1.

Ts = the transport time from slaughter to consumption (20 days) 122014

CY-OC-170-301 Revision 6 Page 100 of 140 2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT Calculate the concentration in cow milk from a ground level release of 100 liCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-XiTr)=l):

Civ = FpCis+ (l- Fp)Cis(1- Fs) + CipFs(l- Fp)

Assume animals are on pasture and receive half of their food from stored feed.

Cip = 18.0 pCi/kg as previously calculated in section 2.5.3.2 Fp =0 Fs = 0.5 Cis is calculated by applying a 90 day decay term to the Cip value previously calculated, since the previous decay correction was for 0 time as shown in 2.5.3.2.

Cis = 18.0 * (exp(-0.693

90 /(5.27

365)))

Cis = 17.4pCi / kg Civ is then:

Civ =0*17.4+ (1-0)17.4 (1-0.5) +18.0

0.5 * (1-0)

Civ = 17.7pCi/kg The concentration in milk is given by:

Cim = FmCivQEXP (-AiTf)

Fm =1.OE-3 d/I Qf = 50 Kg/d Xi = 3.6E-4/d [0.693 / (5.27 yrs*365 days/yr)]

Cim = .OE - 3

17.7

50

EXP(-3.6E - 4

2)

Cim = 0.88pCi/l The concentration in meat given by:

Cif = FfCivQJEXP (-tiTs)

Ff =1.3E-2 d/kg 122014

CY-OC-1 70-301 Revision 6 Page 101 of 140 Qf = 50 Kg/d Xi = 3.6E-4/d Cf = 1.3E - 2

17.7 *50* EXP(-3.6E- 4

20)

Cif = 11.5pCi/ kg 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES The environmental pathway ingestion dose is the sum of the milk, meat, and vegetation ingestion pathways. There are two separate pathways for vegetation: fresh leafy vegetables and a combination of fruits, non-leafy vegetables, and grains. These differ only in the decay and buildup processes applied to account for the environmental exposure, and transportation delay decay represented by Te and Th as shown in section 2.5.3.1. For long half-life isotopes (e.g. Co-60) the decay differences have little impact on the dose.

Dose from the environmental ingestion pathways is generally of the form:

Dja = T DFiija[UavFgCiv+UamCim+ UafCif + UalFlCil]

Where:

Dja = the dose to organ j of age group a - mrem T = fraction of year of release duration DFlija = the ingestion dose factor for isotope i to organ j for age group a - mrem/pCi from Reg.

Guide 1.109 Appendix E Uav = Ingestion rate (usage factor) for non-leafy vegetables, grains, and fruits for age group a from Reg. Guide 1.109 Table E-5 or Table B-I.

Fg = the fraction of vegetables, grains, and fruits from the location of interest : 0.76 in Reg.

Guide 1.109.

Civ = the concentration of isotope i in the vegetables, fruits, and grains calculated from section 2.5.3.2.

Uam = Ingestion rate (usage factor) for milk for age group a: from Table B-1 or Reg. Guide 1.109 Table E-5.

Cim = the concentration of isotope i in milk calculated from section 2.5.3.5.

Uaf = the ingestion rate for meat for age group a: from Table B-1 or Reg. Guide 1.109 Table E-5.

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CY-OC-170-301 Revision 6 Page 102 of 140 Cif = the concentration of isotope i in meat calculated from section 2.5.3.2.

Ual = the ingestion rate for leafy vegetables for age group a: from Table B-1 or Reg. Guide 1.109 Table E-5.

FI = the fraction of annual leafy vegetable ingestion from the location of interest : 1.0 in Reg. Guide 1.109.

Cil = concentration of isotope i in the leafy vegetables for direct human consumption: Civ calculated from section 2.5.3.2 with Th=0.

2.5.3.8 EXAMPLE CALCULATION - DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES Calculate the ingestion dose to child whole body from a ground level release of 100 gCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-kiTr)=1):

Dja = TZ DFIija[UavFgCiv+ UamCim + UafCif+ UalFlCil]

Where:

T = 0.00114 yr [10hrs / 8760 hrs/yr)

DFlija = 1.56E-5 mrem/pCi Uav = 520 Fg = 0.76 Civ = 17.6 [18.0*EXP(-X*60) using 60 day delay for ingestion]

Uam = 330 Cim = 0.88 Uaf = 41 Cif = 11.5 Ual = 26 FI =1 Cil = 17.7 Dja=.0011411.56E- 5[520*0.76* 17.6+330*0.88+41* 11.5 +26*1*17.7]

Dja= .0011411.56E - 5[6956+ 290+472+ 460]

Dja = 1.45E - 4mrem: child: wholebody 2.5.4 GROUND PLANE DEPOSITION IRRADIATION Dose from ground plane deposition is estimated by determining the surface activity resulting from the release.

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CY-OC-170-301 Revision 6 Page 103 of 140 2.5.4.1 GROUND PLANE CONCENTRATION The ground surface activity is estimated as:

Cig = D Q xi (1- EXP(-2iTb))

Where:

2 Cig = ground plane concentration of radionuclide i in pCi/mr D = local atmospheric release deposition factor in 1/mi2 from Table 2.5-1 Qi = release rate in pCi/sec Xi = radiological decay constant in 1/sec Tb = long term buildup time 30 years (9.46E8 sec)

Note: Qi, Mi and Tb can utilize any time units as long as they are all the same 2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATION Calculate the ground plane concentration from a 100 jtCi release of Co-60 over 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release point.

Cig = D (1- EXP(-),iTb))

Q xi D 1.67E-8 /mf2 Q

Qi = 2778 pCi/sec [100pCi/10hrs/3600sec/hr]

ki = 4.17E-9/sec [0.693/(5.27yr*8760hr/yr*3600sec/hr)]

Tb = 9.46E8 sec Cig=167E-8 2778 Cig = 1.67E 8 (l EXP(-4.17E -9* 9.46E8))

4.17E -99 Cig = 1.09E4pCi/ m2 122014

CY-OC-170-301 Revision 6 Page 104 of 140 2.5.4.3 GROUND PLANE DOSE Annual dose from the ground plane deposition is of the form:

Djg= 8760

T *Sf CigDFGi Where:

Djg = the annual dose (mrem) from ground plane pathway (g) to the total body or skin (j) 8760 = hours in a year T = fraction of year release is in progress Sf = shielding factor accounting for shielding from dwelling from Table B-1 DFGij = Ground plane dose factor for skin or total body (j) for radionuclide i from Table E-6 of Reg. Guide 1.109 in mrem/hr / pCi/m 2 .

2.5.4.4 EXAMPLE GROUND PLANE DOSE Calculate the ground plane Total Body dose from a 100 p.Ci release of Co-60 over 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release point.

Djg = 8760

T

SfCigDFGij T = 0.00114 [10/8760]

Sf = 0.7 DFGij = 1.7E-8 Cig = 1.09E4 Djg = 8760* 0.00114 0.711.09E4 *1.7E- 8 i

Djg = 1.30E - 3mremTotalB ody 2.6 PROJECTED DOSES - GASEOUS The projected doses in a 31 day period are equal to the calculated doses from the current 31 day period.

3.0 TOTAL DOSE TO MEMBERS OF THE PUBLIC - 40 CFR 190 The Radiological Environmental Monitoring Report (REMP) submitted by May 1st of each year shall include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle 122014

CY-OC-170-301 Revision 6 Page 105 of 140 sources (including dose contributions from effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Oyster Creek, the sources of exposure need only consider the Oyster Creek Generating Station.

No other fuel cycle facilities would contribute significantly to the MEMBER OF THE PUBLIC dose for the Oyster Creek vicinity, however, both plant operation and ISFSI sources must be included in the dose assessment.

To assess compliance with CONTROL 3.11.4, calculated organ and total body doses from effluents from liquid pathways and atmospheric releases as well as any dose from direct radiation will be summed.

As appropriate for demonstrating/evaluating compliance with the limits of CONTROL 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radiation and / or radioactive material and resultant dose to the MEMBER OF THE PUBLIC in the actual pathways of exposure.

3.1 EFFLUENT DOSE CALCULATIONS For purposes of implementing the surveillance requirements of CONTROL 3/4.11.4 and the reporting requirements of Technical Specification 6.9.1 .d (ARERR), dose calculations for the Oyster Creek Generating Station may be performed using the calculation methods contained within the ODCM; the conservative controlling pathways and locations from the ODCM or the actual pathways and locations as identified by the land use census (CONTROL 3/4.12.1) may be used. Average annual meteorological dispersion parameters provided herein or meteorological conditions concurrent with the release period under evaluation may be used.

3.2 DIRECT EXPOSURE DOSE DETERMINATION Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of environmental measurements (e.g., dosimeter) and/or by the use of radiation transport and shielding calculation methodologies.

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of CONTROL 3.12.1. The objectives of the program are:

- To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Oyster Creek

- To determine if the operation of the Oyster Creek Generating Station has resulted in any increase in the inventory of long lived radionuclides in the environment;

- To detect any changes in the ambient gamma radiation levels; and

- To verify that OCGS operations have no detrimental effects on the health and safety of the public or on the environment.

The REMP sample locations are presented in Appendix E.

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CY-OC-170-301 Revision 6 Page 106 of 140 APPENDIX A - DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS 122014

CY-OC-1 70-301 Revision 6 Page 107 of 140 Table A-1 Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-to-Dose Equivalent Rate Factors* I Radionuclide Factor DFSi for Factor DFVi for Stack Release* Ground-level or Vent Release**

mrem-sec mrem-m 3 pCi-year pCi-year Kr83m 9.21E-10 7.56E-02 Kr85m 1.46E-04 1.17E+03 Kr85 2.58E-06 1.61 E+01 Kr87 8.65E-04 5.92E+03 Kr88 2.16E-03 1.47E+04 Kr89 2.06E-03 1.66E+04 Kr90 1.56E+04 Xe131m 3.13E-05 9.15E+01 Xe133m 2.50E-05 2.51E+02 Xe133 2.15E-05 2.94E+02 Xe135m 4.81E-04 3.12E+03 Xe135 2.51E-04 1.81E+03 Xe137 1.79E-04 1.42E+03 Xe138 1.37E-03 8.83E+03 Xe139 2.14E-04 5.02E+03 Ar4l 1.67E-03 8.84E+03

Based on meteorology applicable at 229 meters SW of stack.

- For exposure to a semi-infinite cloud of noble gas.

122014

CY-OC-1 70-301 Revision 6 Page 108 of 140 Table A-2 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors*

Radionuclide PSi** PVi*** A7Vi*** 3 SBi*** 3 mrem mrem-m 3 mrad-m mrem-m

ýCi ýiCi-sec (Ki) ý.Ci-sec (Mi) jiCi-sec (Li)

Kr83m 2.92E-17 2.40E-09 6.13E-07 -

Kr85m 4.64E-12 3.71E-05 3.90E-05 4.63E-05 Kr85 8.18E-14 5.11E-07 5.46E-07 4.25E-05 Kr87 2.74E-11 1.88E-04 1.96E-04 3.09E-04 Kr88 6.84E-1 1 4.67E-04 4.83E-04 7.52E-05 Kr89 6.53E-1 1 5.27E-04 5.49E-04 3.21E-04 Kr90 4.95E-04 5.17E-04 2.31E-04 Xe131m 9.92E-13 2.90E-06 4.95E-06 1.51E-05 Xe133m 7.94E-13 7.97E-06 1.04E-05 3.16E-05 Xe133 6.83E-13 9.33E-06 1.12E-05 9.71E-06 Xe135m 1.53E-11 9.90E-05 1.07E-04 2.26E-05 Xe135 7.97E-12 5.75E-05 6.1OE-05 5.90E-05 Xe137 5.69E-12 4.51E-05 4.79E-05 3.87E-04 Xe138 4.34E-11 2.80E-04 2.92E-04 1.31 E-04 Xe139 6.79E-12 - -

Ar4l 5.30E-11 2.81E-04 2.95E-04 8.54E-05

All of these dose factors apply out-of-doors.

- Based on meteorology at 229 meters SW of effluent stack.

Derived from Reg Guide 1.109, Revision 1, Table B-1.

122014

CY-OC-170-301 Revision 6 Page 109 of 140 I Table A-3 Air Dose Conversion Factors for Effluent Noble Gas Radionuclide AySi** AyVi*** Ap3i***

mrad mrad-m3 mrad-m3 pCi p.Ci-sec(M1 ) pCi-sec (Ni)

Kr83m 1.33E-16 6.13E-07 9.14E-06 Kr85m 6.89E-12 3.90E-05 6.25E-05 Kr85 1.24E-13 5.46E-07 6.19E-05 Kr87 4.13E-11 1.96E-04 3.27E-04 Kr88 1.03E-10 4.83E-04 9.30E-05 Kr89 9.82E-1 1 5.49E-04 3.37E-04 Kr90 5.17E-04 2.49E-04 Xel31 m 1.50E-12 4.95E-06 3.52E-05 Xe133m 1.23E-12 1.04E-05 4.70E-05 Xe133 1.03E-12 1.12E-05 3.33E-05 Xel35m 2.31E-11 1.07E-04 2.35E-05 Xe135 1.20E-11 6.1OE-05 7.81 E-05 Xe137 8.59E-12 4.79E-05 4.03E-04 Xel 38 6.51E-11 2.92E-04 1.51E-04 Xe139 1.02E-11 -

Ar4l 7.94E-11 2.95E-04 1.04E-04

- Based on meteorology at 229 meters SW of effluent stack.

- - Derived from Reg Guide 1.109, Revision 1, Table B-I.

122014

CY-OC-1 70-301 Revision 6 Page 110 of 140 Table A-4 Locations Associated with Maximum Exposure of a Member of the Public*

Effluent Location Distance Direction (meters) (to)

Liquid U.S. Route 9 Bridge at Discharge Canal Airborne Iodine and Particulates 937 SE Tritium 937 SE Noble Gases 937 SE Irradiation by OCGS Site Boundary All Noble Gas g Air Dose 937 SE Noble Gas B Air Dose 937 SE Note: the nearby resident experiencing the maximum exposure to airborne effluent from the Station is located 937 meters SE of the OCGS. The nearby resident (part-time) experiencing the maximum exposure to gamma radiation directly from the Station is located 618 meters WSW of the OCGS. The most exposed member of the public is assumed to be exposed by irradiation from the OCGS, by inhaling airborne effluent, by irradiation by the airborne effluent, by irradiation by the airborne plume of the noble gas, by radionuclides deposited onto the ground, by irradiation by shoreline deposits, and by eating fish and shellfish caught in the discharge canal.

The age group of the most exposed member of the public is based on Reg. Guide 1.109, Revision 1.

122014

CY-OC-170-301 Revision 6 Page 111 of 140 Table A-5 Critical Receptor Noble Gas Dose Conversion Factors* I Radionuclide PySi** PyVi*** AyVi*** AySi** SBi***

mrem mrem-m 3 mrad-m 3 mrad mrem-m 3

ýLCi gCi-sec(Ki) ptCi-sec(Mi) ptCi ýtCi-sec(Lj)

Kr83m 4.61E-17 2.40E-09 6.13E-07 1.77E-14 Kr85m 2.13E-12 3.71E-05 3.90E-05 3.16E-12 4.63E-05 Kr85 3.38E-14 5.11E-07 5.46E-07 5.12E-14 4.25E-05 Kr87 1.08E-11 1.88E-04 1.96E-04 1.63E-11 3.09E-04 Kr88 2.76E-11 4.67E-04 4.83E-04 4.14E-11 7.52E-05 Kr89 2.02E-11 5.27E-04 5.49E-04 3.03E-11 3.21E-04 Kr9O 4.95E-04 5.17E-04 2.31E-04 Xel31 m 5.05E-13 2.90E-06 4.95E-06 8.03E-13 1.51 E-05 Xe133m 3.95E-13 7.97E-06 1.04E-05 6.50E-13 3.16E-05 Xe133 3.88E-13 9.33E-06 1.12E-05 6.13E-13 9.71E-06 Xe135m 5.82E-12 9.90E-05 1.07E-04 8.80E-12 2.26E-05 Xel35 3.51E-12 5.75E-05 6.1OE-05 5.25E-12 5.90E-05 Xe137 1.74E-12 4.51E-05 4.79E-05 2.64E-12 3.87E-04 Xel38 1.72E-11 2.80E-04 2.92E-04 2.58E-11 1.31E-04 Xel39 9.30E-13 - 1.40E-12 -

Ar4l 2.07E-11 2.81E-04 2.95E-04 3.1OE-11 8.54E-05

All of these dose factors apply out-of-doors.

- Based on meteorology at 937 meters SE of effluent stack.

Derived from Reg Guide 1.109, Revision 1, Table B-1 122014

CY-OC-1 70-301 Revision 6 Page 112 of 140 APPENDIX B - MODELING PARAMETERS 122014

CY-OC-1 70-301 Revision 6 Page 113 of 140 Table B-I- OCGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Fraction Of Produce From Local Garden 7.6E-1 Soil Density In Plow Layer (Kg/m2) 2.4E+2 Fraction Of Deposited Activity Retained On Vegetation 2.5E-1 Shielding Factor For Residential Structures 7.0E-1 Period Of Buildup Of Activity In Soil (hr) 1.31 E+5 Period of Pasture Grass Exposure to Activity (hr) 7.2E+2 Period Of Crop Exposure to Activity (hr) 1.44E+3 Delay Time For Ingestion Of Stored Feed By Animals (hr) 2.16E+3 Delay Time For Ingestion Of Leafy Vegetables By Man (hr) 2.4E+1 Delay Time For Ingestion Of Other Vegetables By Man (hr) 1.44E+3 Transport Time Milk-Man (hr) 4.8E+1 Time Between Slaughter and Consumption of Meat Animal (hr) 4.8E+2 Grass Yield Wet Weight (Kg/mi2 ) 7.0E-1 Other Vegetation Yield Wet-Weight (Kg/m 2 ) 2.0 Weathering Rate Constant For Activity on Veg. (hr- 1) 2.1 E-3 Milk Cow Feed Consumption Rate (Kg/day) 5.0E+1 Goat Feed Consumption Rate (Kg/day) 6.0 Beef Cattle Feed Consumption Rate (Kg/day) 5.0E+1 Milk Cow Water Consumption Rate (L/day) 6.0E+1 Goat Water Consumption Rate (L/day) 8.0 Beef Cattle Water Consumption Rate (L/day) 5.0E+1 Environmental Transit Time For Water Ingestion (hr) 1.2E+1 Environmental Transit Time For Fish Ingestion (hr) 2.4E+1 Environmental Transit Time For Shore Exposure (hr) 0 Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1 122014

CY-OC-170-301 Revision 6 Page 114 of 140 Table B-1 (Continued)

OCGS Usage Factors for Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Water Ingestion (L/yr)

a. Adult 7.3E+2

b. Teen 5.1E+2

c. Child 5.1E+2

d. Infant 3.3E+2 Shore Exposure (hr/yr)

a. Adult 1.2E+1

b. Teen 6.7E+1

c. Child 1.4E+1

d. Infant 0 Salt Water Sport Fish Ingestion (Kg/yr)

a. Adult 2.1EE+1

b. Teen 1.6E+1

c. Child 6.9

d. Infant 0 Salt Water Commercial Fish Ingestion (Kg/yr)

a. Adult 2.1E+1

b. Teen 1.6E+1

c. Child 6.9

d. Infant 0 Salt Water Invertebrate Ingestion (Kg/yr)

a. Adult 5.0

b. Teen 3.8

c. Child 1.7

d. Infant 0 Irrigated Leafy Vegetable Ingestion (Kg/yr)

a. Adult 6.4E+1

b. Teen 4.2E+1

c. Child 2.6E+1

d. Infant 0 122014

CY-OC-170-301 Revision 6 Page 115 of 140 Table B-1 (Continued)

OCGS Usage Factors for Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Irrigated Other Vegetable Ingestion (Kg/yr)

a. Adult 5.2E+2

b. Teen 6.3E+2

c. Child 5.2E+2

d. Infant 0 Irrigated Root Vegetable Ingestion (Kg/yr)

a. Adult 5.2E+2

b. Teen 6.3E+2

c. Child 5.2E+2

d. Infant 0 Irrigated Cow and Goat Milk Ingestion (L/yr)

a. Adult 3.1E+2

b. Teen 4.0E+2

c. Child 3.3E+2

d. Infant 3.3E+2 Irrigated Beef Ingestion (Kg/yr)

a. Adult 1.1E+2

b. Teen 6.5E+1

c. Child 4.1E+1

d. Infant 0 Inhalation (m3/yr)

a. Adult 8.0E+3

b. Teen 8.0E+3

c. Child 3.7E+3

d. Infant 1.4E+3 Cow and Goat Milk Ingestion (L/yr)

a. Adult 3.1E+2

b. Teen 4.01E+2

c. Child 3.3E+2

d. Infant 3.3E+2 Meat Ingestion (Kg/yr)

a. Adult 1.1E+2

b. Teen 6.5E+1

c. Child 4.1E+1

d. Infant 0 122014

CY-OC-1 70-301 Revision 6 Page 116 of 140 Table B-1 (Continued)

OCGS Usage Factors for Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Leafy Vegetable Ingestion (Kg/yr)

a. Adult 6.4E+1

b. Teen 4.2E+1

c. Child 2.6E+1

d. Infant 0 Fruits, Grains, & Other Vegetable Ingestion (Kg/yr)

a. Adult 5.2E+2

b. Teen 6.3E+2

c. Child 5.2E+2

d. Infant 0 122014

CY-OC-170-301 Revision 6 Page 117 of 140 3

Table B-2 Monthly Average Absolute Humidity g/m (derived from historical climatological data)

Average Absolute Month Humidity (q/m 3)

January 3.3 February 3.3 March 4.5 April 6.1 May 9.4 June 12.8 July 15.2 August 15.6 September 12.4 October 7.9 November 5.9 December 3.8 122014

CY-OC-170-301 Revision 6 Page 118 of 140 APPENDIX C - REFERENCES 122014

CY-OC-170-301 Revision 6 Page 119 of 140 Table C REFERENCES

1) Oyster Creek Updated Final Safety Analysis Report

2) Oyster Creek Facility Description and Safety Analysis Report

3) Oyster Creek Operating License and Technical Specifications

4) NUREG 1302 "Off Site Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors" - Generic Letter 89-10, Supplement No. 1,April 1991

5) Reg 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" Rev.1, June 1974

6) Reg Guide 1.23

7) Reg Guide 1.97

8) Reg Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I", Rev 1, October, 1977

9) Reg Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors", Rev. 1, July, 1977

10) Reg Guide 4.8" Environmental Technical Specifications for Nuclear Power Plants"

11) NRC Radiological Assessment Branch Technical Position, Rev 1, November 1979 (Appendix A to NUREG1302)

12) NUREG-0016

13) NUREG-0133

14) Licensing Application, Amendment 13, Meteorological Radiological Evaluation for the Oyster Creek Nuclear Power Station Site.

15) Licensing Application, Amendment 11, Question IV-8.

16) Evaluation of the Oyster Creek Nuclear Generating Station to Demonstrate Conformance to the Design Objectives of 10CFR50, Appendix I, May, 1976, Tables 3-10

17) XOQDOQ Output Files for Oyster Creek Meteorology, Murray and Trettle, Inc.

122014

CY-OC-1 70-301 Revision 6 Page 120 of 140

18) Hydrological Information and Liquid Dilution Factors Determination to Conform with Appendix I Requirements: Oyster Creek, correspondence from T. Potter, Pickard, Lowe and Garrick, Inc. to Oyster Creek, July, 1976.

19) Carpenter, J. J. "Recirculation and Effluent Distribution for Oyster Creek Site", Pritchard-Carpenter Consultants, Baltimore, Maryland, 1964.

20) Nuclear Regulatory Commission, Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section and Relocation of the Procedural Details of RETS to the ODCM or PCP", January, 1989.

21) Ground Water Monitoring System (Final Report), Woodward-Clyde Consultants, March, 1984.

22) Meteorology and Atomic Energy, Department of Energy, 1981.

23) SEEDS Code Documentation through V & V of Version 98.8F (Radiological Engineering Calculation No. 2820-99-005, Dated 3/23/99)

24) Lynch, Giuliano, and Associates, Inc., Drawing Entitled, "Minor Subdivision, Lots 4 and 4.01 Block 1001", signed 13 Sep 99.

25) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements".

26) NUREG/CR-4007 (September 1984).

27) HASL Procedures Manual, HASL-300 (revised annually).

28) Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I,"April 1977

29) Reg. Guide 4.13

30) 10CFR20, Appendix B, Table 2, Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage

31) Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleet wide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No.

045136(18), September, 2006.

32) Letter date April 23, 2013 from Murray and Trettel, Incorporated

33) Letter dated January 10, 2013 titled "Meteorology and Dose Factor Update - ODCM Revision 6" 122014

CY-OC-170-301 Revision 6 Page 121 of 140 APPENDIX D - SYSTEM DRAWINGS 122014

CY-OC-170-301 Revision 6 Page 122 of 140 FIGURE D-1-la: LIQUID RADWASTE TREATMENT CHEM WASTE AND FLOOR DRAIN SYSTEM

.C>

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122014

CY-OC-170-301 Revision 6 Page 123 of 140 FIGURE D-1-lb: LIQUID RADWASTE TREATMENT - HIGH PURITY AND EQUIPMENT DRAIN SYSTEM I.-

z z z'

0

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COC 0~

co a.

E WWL U)~ C (0- .

.- ,-z co M a.. o.,T1 I >"

_ A 8 -- * ° -lE

,o i-I 1 <0 122014

CY-OC-1 70-301 Revision 6 Page 124 of 140 FIGURE D-1-lc: GROUNDWATER REMEDIATION SYSTEM Composite Flow Monitor Sampler 122014

CY-OC-170-301 Revision 6 Page 125 of 140 FIGURE D-1-2: SOLID RADWASTE PROCESSING SYSTEM Temp Mod Process WC-T-I A/B/C Filter Sludge Option A 122014

CY-OC-170-301 Revision 6 Page 126 of 140 FIGURE D-2-1: GASEOUS RADWASTE TREATMENT - AUGMENTED OFF GAS SYSTEM 122014

CY-OC-170-301 Revision 6 Page 127 of 140 FIGURE D-2-2: VENTILATION SYSTEM V-7-31 l

V-1161 1

OYSTI ER CREEK TUBVENT PATHS lae STACK ICond

~~I SI-Ii I.-

CE CODN. R V7s (1-6)

TURBINE BUILDING I V-28-2 I V.~-23-14 V-29-21 I

I U -

STANDBY GAS TREATMENT SYSTEM V-28-19 V-28-17 N V.RA7 Torus 122014

CY-OC-1 70-301 Revision 6 Page 128 of 140 Figure D-2-3 AOG Ventilation System HV-S-1O 122014

CY-OC-1 70-301 Revision 6 Page 129 of 140 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - SAMPLE TYPE AND LOCATION All sampling locations and specific information about the individual locations are given in Table E-1. Figures E-1, E-2 and E-3 show the locations of sampling stations with respect to the site. Figure E-4 shows the site layout.

122014

CY-OC-1 70-301 Revision 6 Page 130 of 140 TABLE E-1: REMP SAMPLE LOCATIONS(1 )

1. Direct Radiation DOS - Inner Ring at or near site boundary Code (miles) (degrees) Description 1 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ 51 0.4 358 North of site, on the access road to Forked River Site, Forked River, NJ 52 0.3 333 NNW of site, on the access road to Forked River Site, Forked River, NJ 53 0.3 309 NW of site, at sewage lift station on the access road to the Forked River Site, Forked River, NJ 54 0.3 288 WNW of site, on the access road to Forked River Site, Forked River, NJ 55 0.3 263 West of site, on Southern Area Stores security fence, west of OCGS Switchyard, Forked River, NJ 56 0.3 249 WSW of site, on utility pole east of Southern Area Stores, west of the OCGS Switchyard, Forked River, NJ 57 0.2 206 SSW of site, on Southern Area Stores access road, Forked River, NJ 58 0.2 188 South of site, on Southern Area Stores access road, Forked River, NJ 59 0.3 166 SSE of site, on Southern Area Stores access road, Waretown, NJ 61 0.3 104 ESE of site, on Route 9 south of OCGS Main Entrance, Forked River, NJ 62 0.2 83 East of site, on Route 9 at access road to OCGS Main Gate, Forked River, NJ 63 0.2 70 ENE of site, on Route 9, between main gate and OCGS North Gate access road, Forked River, NJ 64 0.3 42 NE of site, on Route 9 North at entrance to Finninger Farm, Forked River, NJ 65 0.4 19 NNE of site, on Route 9 at Intake Canal Bridge, Forked River, NJ 66 0.4 133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ 112 0.2 178 S of site, along Southern access road, Lacey Township, NJ 122014

CY-OC-170-301 Revision 6 Page 131 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)

1. Direct Radiation (Continued)

DOS - Inner Ring at or near site boundary Code (miles) (dearees) Description 113 0.3 90 E of site, along Rt. 9 North, Lacey Township, NJ T1 0.4 219 SW of site, at OCGS Fire Pond, Lacey Township, NJ DOS -Outer Ring at 6 - 8 km 4 4.6 213 SSW of Site, Garden State Parkway and Route 554, Barnegat, NJ 5 4.2 353 North of Site, Garden State Parkway Rest Area, Forked River, NJ 6 2.1 13 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ 8 2.3 177 South of site, Route 9 at the Waretown Substation, Waretown, NJ 9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, Waretown, NJ 22 1.6 145 SE of site, on Long John Silver Way, Skippers Cove, Waretown, NJ 46 5.6 323 NW of Site, on Lacey Road adjacent to Utility Pole BT 259 65 47 4.6 26 NNE of Site, Route 9 and Harbor Inn Road, Berkeley Township, NJ 48 4.5 189 South of Site, Intersection of Brook and School Streets, Barnegat, NJ 68 1.3 266 West of site, on Garden State Parkway North at mile marker 71.7, Lacey Township, NJ 73 1.8 108 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ 74 1.8 88 East of site, Orlando Drive and Penguin Court, Forked River, NJ 75 2.0 71 ENE of site, Beach Blvd. and Maui Drive, Forked River, NJ 78 1.8 2 North of site, 1514 Arient Road, Forked River, NJ 79 2.9 160 SSE of site, Hightide Drive and Bonita Drive, Waretown, NJ 82 4.4 36 NE of site, Bay Way and Clairmore Avenue, Lanoka Harbor, NJ 84 4.4 332 NNW of site, on Lacey Road, 1.3 miles west of the Garden State Parkway on siren pole, Lacey Township, NJ 122014

CY-OC-1 70-301 Revision 6 Page 132 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)

1. Direct Radiation (continued)

DOS - Outer Ring at 6 - 8 km (continued)

Code (miles) (degrees) Description 85 3.9 250 WSW of site, on Route 532, just east of Wells Mills Park, Waretown, NJ 86 5.0 224 SW of site, on Route 554, 1 mile west of the Garden State Parkway, Barnegat, NJ 98 1.6 318 NW of site, on Garden State Parkway at mile marker 73.0, Lacey Township, NJ 99 1.5 310 NW of site, on Garden State Parkway at mile marker 72.8, Lacey Township, NJ 100 1.4 43 NE of site, Yacht Basin Plaza South off Lakdeside Dr., Lacey Township, NJ 101 1.7 49 NE of site, end of Lacey Rd., East, Lacey Township, NJ 102 1.6 344 NNW of site, end of Sheffield Dr., Barnegat Pines, Lacey Township, NJ 103 2.4 337 NNW of site, Llewellyn Parkway, Barnegat Pines, Lacey Township, NJ 104 1.8 221 SW of site, Rt. 532 West, before Garden State Parkway, Ocean Township, NJ 105 2.8 222 SW of site, Garden State Parkway North, beside mile marker 69.6, Ocean Township, NJ 106 1.2 288 NW of site, Garden State Parkway North, beside mile marker 72.2 Lacey Township, NJ 107 1.3 301 NW of Site, Garden State Parkway North, beside mile marker 72.5, Lacey Township, NJ 109 1.2 141 SE of site, Lighthouse Dr., Waretown, Ocean Township, NJ 110 1.5 127 SE of site, Tiller Drive and Admiral Way, Waretown, Ocean Township, NJ DOS - Special Interest 11 8.2 152 SSE of site, 8 0 th and Anchor Streets, Harvey Cedars, NJ 71 1.6 164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ 72 1.9 25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ 122014

CY-OC-1 70-301 Revision 6 Page 133 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)

1. Direct Radiation (continued)

DOS - Special Interest (continued)

Code (miles) (dearees) Description 81 3.5 201 SSW of site, on Rose Hill Road at intersection with Barnegat Boulevard, Barnegat, NJ 88 6.6 125 SE of site, eastern end of 3 rd Street, Barnegat Light, NJ 89 6.1 108 ESE of site, Job Francis residence, Island Beach State Park 90 6.3 75 ENE of site, parking lot A-5, Island Beach State Park 92 9.0 46 NE of site, at Guard Shack/Toll Booth, Island Beach State Park 3 6.0 97 East of site, near old Coast Guard Station, Island Beach State Park Special Interest Area DOS - Background C 24.7 313 NW of site, JCP&L office in rear parking lot, Cookstown, NJ 14 20.8 2 North of site, Larrabee Substation on Randolph Road, Lakewood, NJ

2. Airborne - Radioiodines and Particulates APT, AIO - At or near site boundary in highest DIQ Sectors 20 0.7 95 East of site, on Finninger Farm on south side of access road, Forked River, NJ 66 0.4 133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ 111 0.3 64 ENE of site, Finninger Farm property along access road, Lacey Township, NJ APT, AIO -Special Interest 71 1.6 164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ 72 1.9 25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ 73 1.8 108 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ APT, AIO - Backgound C 24.7 313 NW of site, JCP&L office in rear parking lot, Cookstown, NJ 122014

CY-OC-1 70-301 Revision 6 Page 134 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)

2. Airborne - Radioiodines and Particulates (continued)

APT, AIO - Backgound(continued)

Code (miles) (dearees) Description 3 6.0 97 East of site, near old Coast Guard Station, Island Beach State Park Special Interest Area

3. Waterborne SWA - Surface 23 3.6 64 ENE of site, Barnegat Bay off Stouts Creek, approximately 400 yards SE of "Flashing Light 1" 24 2.1 101 East of site, Barnegat Bay, approximately 250 yards SE of "Flashing Light 3" 33 0.4 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal SWA - Backgound 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor GW - Ground W-3C 0.4 112 ESE of site on Finninger Farm adjacent to Station 35, Lacey Township, NJ MW-24-3A 0.8 97 E of site on Finninger Farm on South side of access road, Lacey Township, NJ DW - Drinking 1s 0.1 209 On-site southern domestic well at OCGS, Forked River, NJ 1N 0.2 349 On-site northern domestic well at OCGS, Forked River, NJ 38 1.6 197 SSW of Site, on Route 532, at Ocean Township MUA Pumping Station, Waretown, NJ DW - Backgound 37 2.2 18 NNE of Site, off Boox Road at Lacey MUA Pumping Station, Forked River, NJ 39 3.5 353 N of Site, Trenton Ave. off Lacey Road Lacey Twp., MUA Pump Station, Forked River, NJ AQS - Sediment 23 3.6 64 ENE of site, Barnegat Bay off Stouts Creek, approximately 400 yards SE of "Flashing Light 1" 24 2.1 101 East of site, Barnegat Bay, approximately 250 yards SE of "Flashing Light 3" 33 0.4 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal 122014

CY-OC-170-301 Revision 6 Page 135 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (CONTINUED)

3. Waterborne (continued)

AQS - Backgound Code (miles) (dearees) Description 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor

4. Ingestion FISH - Fish 93 0.1 242 WSW of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ FISH - Backgound 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor CLAM - Clams 23 3.6 64 ENE of site, Bamegat Bay off Stouts Creek, approximately 400 yards SE of "Flashing Light 1" 24 2.1 101 East of site, Barnegat Bay, approximately 250 yards SE of "Flashing Light 3" CLAM - Backgound 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor CRAB - Crabs 33 0.4 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal 93 0.1 242 WSW of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ VEG - Vegetation 35 0.4 111 ESE of site, east of Route 9 and north of the OCGS Discharge Canal, Forked River, NJ 66 0.4 133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ 115 0.3 96 East of Site, on Finninger Farm VEG - Backgound 36 23.1 319 NW of site, at "U-Pick" Farm, New Egypt, NJ 122014

CY-OC-1 70-301 Revision 6 Page 136 of 140 SAMPLE MEDIUM IDENTIFICATION KEY APT = Air Particulate SWA = Surface Water DOS = Dosimeter AIO = Air Iodine AQS = Aquatic Sediment FISH = Fish CLAM = Clams CRAB =Crab VEG = Vegetables DW = Drinking Water GW = Ground Water (1) Samples may not be collected from some locations listed in this table, as long as the minimum number of samples listed in Table 3.12.1-1 is collected.

122014

CY-OC-1 70-301 Revision 6 Page 137 of 140 FIGURE E-1 ENE Oyster Creek Generating Station REMP Sample Locations within a I Mle Radius 03 11.15 O b 0.3 l" DWe. 094t12 122014

CY-OC-1 70-301 Revision 6 Page 138 of 140 Oyster Creek Generating Station REMP Sample Locations within a 1 to 5 Mile Radius Date: 08/27/12 122014

CY-OC-1 70-301 Revision 6 Page 139 of 140 FIGURE E-3

.7 fc) 2011 S,,bo()

Oyster Creek Generating Station REMP Sample Locations over a 5 Mile Radius 5.5 2.75 0 &5 Ws5 Date: 08127/12 122014

CY-OC-1 70-301 Revision 6 Page 140 of 140 FIGURE E-4 AREA PLOT PLAN OF SITE SITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS Site Boundary Distances Sector Distance in meters Sector Distance in meters S 348 N 584 SSW 291 NNE 621 SW 229 NE 373 WSW 260 ENE 338 W 239 E 360 WNW 284 ESE 491 NW 364 SE 544 NNW 474 SSE 395 122014

Exeton Generation, Exeo S

eeRW-AA-100 Revision 10 Page 1 of 12 Level 3 - Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES

1. PURPOSE 1.1. The purpose of the Process Control Program (PCP) is to:

1.1.1. Establish the process and boundary conditions 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 (LLRW), 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 10CFR Part 20, 10CFR Part 61, 10CFR Part 71, 49CFR Parts 171-172, "Technical Position on Waste Form (Revision 1)" (1/91], "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification" [5/83], 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 facilities for dry and/or processed wet waste.

2. TERMS AND DEFINITIONS 2.1. Process Control Program (PCP): 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.

2.2. Solidification

Liquid waste processed to either an unstable or stable form per 10 CFR61 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 container meeting stability criteria (e.g.

High Integrity 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 "stabilization" 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 stabilization formulas, samples, tests, etc.

RW-AA-100 Revision 10 Page 2 of 12 2.4. Solidification Media: An approved media (e.g. Barnwell - vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives is solidified in a container with activity greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability 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 facility.

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

_<1% 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. 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 Drains and Equipment Drain inputs).

2.8. Incineration, RVR. and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 10CFR61 requirements.

2.9. Compaction

When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.

I

RW-AA-100 Revision 10 Page 3 of 12 2.10. 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,

- Fuel pool activated hardware,

- Oil Dry absorbent material added to a container to absorb liquids

- Fuel Pool Crud

- Sump and tank sludges,

- High activity filter cartridges,

- Concentrated liquids,

- Contaminated waste oil,

- Dried sewage or wastewater plant waste,

- Dry Active Waste (DAW): Waste such as filters, 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.

2.11. Concentration Averaging: Concentration averaging is either: a) the mathematical averaging of waste concentrations, based on the size, geometry, type of radioactive emission, and observed dose rates, or b) the combining of radioactive components in a single container and how their radioactivity may be averaged over the volume of the container. Concentration averaging is subject to constraints identified in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation and may also be constrained by Agreement States or Disposal Facilities.

2.12. Encapsulation: Encapsulation is the surrounding of a radioactive source or component with a nonradioactive material. Encapsulation involves a radioactive core surrounded by a non-radioactive matrix.

2.13. Blending: The intentional mixing of different, but miscible waste streams (such as resins, filter media, etc.) from different batches or systems for the purpose of operational efficiency or ALARA. Blending applies to LLRW streams only. The addition of non-radioactive materials or fillers is not considered blending.

3. RESPONSIBILITIES 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.

RW-AA-100 Revision 10 Page 4 of 12

4. MAIN BODY 4.1. Process Control Program 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 1.21, 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/unstable 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 shall ADHERE to its own QA Program and shall have SUBMITTED 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 shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another approved vendor.

4.1.5. The vendor processing system(s) is/are controlled per the following:

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 shall 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.

RW-AA-100 Revision 10 Page 5 of 12 4.2. General Waste Processing Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.

4.2.1. 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, demineralizer, concentrator or vendor supplied processing systems.

4.2.3. 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.

4.2.4. 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, demineralization for plant re-use, or discharge.

4.2.5. All dewatering and solidification/stabilization 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.

4.2.6. Dry Active Waste (DAW) will 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 items may be SURVEYED for release onsite or offsite when applicable.

4. Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.

RW-AA-100 Revision 10 Page 6 of 12 4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from 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 Liner/HIC. 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 Barnwell, 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 or WCS, 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 shall 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 Conformance.

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 10CFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).

4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.

4.2.12. 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 disposal shall be incorporated into station implementing procedures. (CM-2)

RW-AA-100 Revision 10 Page 7 of 12 4.2.13. Concentration averaging may be PERFORMED to combine LLRW having different concentrations of radionuclides to form a homogeneous mixture in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation-1995:

- For homogeneous waste types such as resins and filter media, the concentration of the mixture for classification purposes may be based on either the highest radionuclide concentration in any of the individual waste types contributing to the mixture or the volumetric or weight-averaged nuclide concentrations in the mixture provided that the concentrations of the individual waste type contributors to the mixture are within a factor of 10 of the average concentration of the resulting mixture. (NOTE: a designed collection of homogeneous waste types (from different sources within a facility) is not considered 'mixing' and the concentration for classification purposes may be the average concentration of the combination).

- For non-homogeneous waste types such as activated metals, cartridge filters or components incorporating radioactivity in their design, the concentration should be determined from the total weight or displaced volume (excluding major void spaces) of the component. Mixtures of components in a disposal container is permissible. Concentration averaging of a mixture of components of similar types can be performed in accordance with the NRC's Branch Technical Position on Concentration Averaging and Encapsulation and any State or Disposal Site specific requirements.

4.2.14. Blending may be PERFORMED for routine LLRW such as resins and filter media in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation as further clarified in SECY 2010-0043.

The concentration of the mixture may be determined based on the total activity of all components in the mixture divided by the total volume or mass of the mixture.

Reasonable effort should be made to mix blended LLRW so that activity is evenly distributed.

4.2.15. Encapsulation may be PERFORMED for routine wastes such as filters, filter cartridges, or sealed sources centered in an encapsulated mass, in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation. Classification may be based on the overall volume of the final solidified mass provided that;

- The minimum solidified volume or mass should be reasonably difficult to move by hand.

- The maximum solidified volume or mass used for determining concentration for any single discrete source should be no more than 0.2 m 3 or 500Kg (typically 55-gallon drum).

- The maximum amount of gamma-emitting radioactivity or radioactive material is <0.02 mrem/hr on the surface of the encapsulation over a 500-year decay period.

RW-AA-100 Revision 10 Page 8 of 12 The maximum amount of any radionuclide in a single encapsulation, when averaged over the waste and encapsulating media, does not exceed the maximum concentration limits for Class C waste.

Written procedures should be established to ensure that the radiation source(s) is reasonably centered (or distributed) within the encapsulating media.

All other disposal facility requirements for encapsulated material are met.

4.3. Burial Site Requirements 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. Shippinq and Inspection Requirements 4.4.1. All shipping/storage 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 solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.

4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's 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. Inspection and Corrective Action 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 solidification requirements are maintained.

RW-AA-100 Revision 10 Page 9 of 12 4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other than editorial/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-106. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.

4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.

4.6.3. Procedures shall be IMPLEMENTED as follows:

- Station processes or other vendor waste processing/operating procedures shall be technically reviewed and 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).

- Site waste processing IS CONTROLLED by site operating procedures.

- Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.

- The dewatering procedures implemented by Vendor for the purpose of compliance to the Process Control Program SHALL BE REVIEWED and APPROVED in accordance with the plant specific TRM or ORM (either Current Technical Specifications (CTS) or Improved Technical Specifications (ITS), as applicable for the respective stations).

4.7. Waste Types, Point of Generation, and Processing Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.

RW-AA-100 Revision 10 Page 10 of 12 AVAILABLE WASTE POEING ME WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin 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 Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit Filter cartridges Systems - Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release metal, and etc. resulting from daily Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system. 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

RW-AA-100 Revision 10 Page 11 of 12

5. DOCUMENTATION 5.1. Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:

1. Sufficient 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 overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.

6. REFERENCES 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 Licensee Controlled Documents. Some facilities 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.

6.2. Writers'

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 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. USNRC 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 6.2.7. Amendment No. 202 to Facility Operating License No. NPF-1 1 and Amendment No.

189 to Facility Operating License (FOL) No. NPF-18 for the LaSalle County Station (LSCS), Units 1 and 2

RW-AA-100 Revision 10 Page 12 of 12 6.2.8. NRC Branch Technical Position on Blending of Low-Level Radioactive Waste, SECY-10-0043 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 G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications). (Step 1.1.1,4.5.2) 6.4.2. Limerick CM-2, T03896, 10CFR20.2002 permit granted to Limerick via letter dated July 10, 1996. (Step 4.2.12)

7. ATTACHMENTS - None

RA-15-035, ISFSI - Annual Radioactive Effluent Release Report for 2014

Contents

Text

Subject:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

6.3 RESPONSIBILITIES

2.2. Solidification

2.3. Stabilization

2.5. Dewatering

2.9. Compaction

References:

References:

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RA-15-035, ISFSI - Annual Radioactive Effluent Release Report for 2014

Text

Subject:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

6.3 RESPONSIBILITIES

2.2. Solidification

2.3. Stabilization

2.5. Dewatering

2.9. Compaction

References:

References:

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