Oyster Creek - Revised Annual Radioactive Effluent Release ... · C Average Energy 4 D Measurements...

Exelon Generation.Oyster Creek Generating Station www.exeloncorp.comRoute 9 SouthPO Box 388Forked River, NJ 08731

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

Technical Specification 6.9.1.d

RA-12-004CDecember 5, 2012

U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555 - 0001

Oyster Creek Nuclear Generating StationRenewed Facility Operating License No. DPR-16NRC Docket No. 50-219

Subject: Revised Annual Radioactive Effluent Release Report for 2008

Enclosed with this cover letter is the revised copy of the Annual Radioactive EffluentRelease Report for 2008. The report includes the Oyster Creek Nuclear GeneratingStation Independent Spent Fuel Storage Facility. Revision bars have been used toindicate where changes were made to the reports.

If any further information or assistance is needed, please contact Dave Chernesky,Chemistry Manager, at 609-971-4217.

Sincerely,

Michael J. MassaroSite Vice PresidentOyster Creek Nuclear Generating Station

Enclosures: 2008 Annual Radioactive Effluent Release Report (Revision 3)

cc: Administrator, USNRC Region IUSNRC Senior Project Manager, Oyster CreekUSNRC Senior Resident Inspector, Oyster CreekCraig Stewart, American Nuclear Insurers

2008

Annual Radioactive Effluent Release Report

Oyster Creek Generating Station

Revision 3

Issued 2012

Revised 2008 Annual Radioactive Effluent Release Report

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

January 1, 2008 through December 31, 2008

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 toThe United States Nuclear Regulatory Commission

, Pursuant toRenewed Facility Operating License DPR-16

I

! Revised 2008 Annual Radioactive Effluent Release Report

TABLE OF CONTENTS

SECTION PAGE

1. Executive Summary 1

2. Introduction 3

3. Supplemental Information 4

A Regulatory Limits 4

B Effluent Concentration Limits 4

C Average Energy 4

D Measurements and Approximations of Total Radioactivity 5

E Abnormal Releases 6

F Revisions to the ODCM 6

G Radiation Effluent Monitors Out of Service More Than 30 Days 6

H Changes to the Process Control Plan 7

I Releases from the Independent Spent Fuel Storage Facility 7

Appendix A - Effluent and Waste Disposal Summary 8

Appendix B - Solid Waste and Irradiated Fuel Shipments 13

Appendix C - Radiological Impact to Man 17

Appendix'D - Meteorological Data** Not changed and not included

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EXECUTIVE SUMMARY

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

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

There were no liquid radioactive effluent releases above ODCM LLDs during 2008.Therefore there was no dose due to radiological liquid releases. Utilizing gaseouseffluent data, the maximum hypothetical dose to any individual was calculated using amathematical model, which is based on the methods defined by the U.S. NuclearRegulatory Commission. These methods accurately determine the types and quantitiesof radioactive materials being released to the environment.

The maximum hypothetical calculated organ dose (bone) from iodines, particulates andtritium to any individual due to gaseous effluents was 3.31 E-02 mrem (0.0331 mrem),which was approximately 2.21 E-01 percent of the annual limit. The maximum calculatedgamma air dose in the UNRESTRICTED AREA due to noble gas effluents was4.98E-03 mrem (0.00498 mrem), which was 4.98E-02 percent of the annual limit.

The total maximum hypothetical organ dose (bone) received by any individual fromgaseous effluents from OCGS for the reporting period due to all radiological effluents is3.81 E-2 mrem (0.0381 mrem). This value is more than 7,500 times lower than the dosethe average individual in the Oyster Creek area received from background radiation,including that from radon during the same time period. The background radiation doseaverages approximately 300 mRem per year in the Central New Jersey area, whichincludes approximately 200 mRem/year from naturally occurring radon gas and 100mRem from background radiation.

The Independent Spent Fuel Storage Installation (ISFSI) is a closed system and the onlyexposure would be due to direct radiation. This includes iodines, particulates and noblegases. Based on offsite TLD readings, dose due to direct radiation from the ISFSI wasless than 1 mRem for 2008. Because it is a sealed unit, no radioactive material wasreleased.

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Additionally, comparison of environmental sampling results to iodine and particulategaseous effluents released, showed no radioactivity attributable to the operation ofOCGS. Both elevated and ground-level release paths were considered in this review,with total iodines released of 7.55 mCi and total particulates with half-lives greater than 8days released of 18.5 mCi (1 mCi is one/one-thousandth of a Ci.).

Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for allstability classes, were included in the original submittal and did not change. All data wascollected from the on-site Meteorological Facility. Data recoveries for the 380-foot dataand the 33-foot data were 97.9 percent and 97.8 percent, respectively. The UFSARcommits to Regulatory Guide (RG) 1.23 for Meteorological Facility data recovery. RG1.23 requires data recovery of at least 90% on an annual basis.

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1. Introduction

In accordance with the reporting requirements of Technical Specification 3.6.E.1applicable during the reporting period, this report summarizes the effluent releasedata for Oyster Creek Generating Station for the period January 1, 2008 throughDecember 31, 2008. This submittal complies with the format described inRegulatory Guide 1.21, "Measuring, Evaluating and Reporting Radioactivity inSolid Wastes and Releases of Radioactive Materials in Liquid and GaseousEffluents from Light-Water Cooled Nuclear Power Plants", Revision 1, June,1974.

Meteorological data was reported in the format specified in Regulatory Guide1.23, Revision 1, "Meteorological Monitoring Programs For Nuclear PowerPlants".

On April 7, 2010, the main stack Radioactive Gaseous Effluent MonitoringSystem (RAGEMS) sample line was discovered separated at a Swagelok unionat the 260 foot elevation. The sample line was disconnected with the two endsseparated by a distance of several inches, such that the sample line was open tothe atmosphere. Subsequent investigations revealed a second sample lineseparation at a Swagelok union lower in the stack sample line. The tubing washeld in place by the insulation and the heat trace. A root cause analysisconcluded that the sample line was first separated about January 1, 2006. Sincethe insulation was in place, the sample line continued to provide a partial sampleof the stack gas. Over the four years, the data indicates that the sample lineseparation increased slowly.

This report estimates the 2008 releases based on the 2010 May to Novemberreleases that are corrected for 2008 power (all nuclides), 2008 AugmentedOffgas System availability (nobles gases) and 2008 Offgas release rate (noblesgases and short lived fission products).

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2. Supplemental Information

A. Regulatory Limits

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

1. Noble Gases:a. < 500

< 3000

b. <5<10

C. <10< 20

d. <5<15

mrem/Yrmrem/Yr

mRadmRad

mRadmRad

Total BodySkin

Air GammaAir Beta

Air GammaAir Beta

Total Body (Gamma)Skin (Beta)

mremmrem

2. lodines, Tritium, Particulates with Half Life > 8 days:a. < 1500 mrem/Yr Any Organ

ODCM Control 3.11.2.1

Quarterly air dose limitsODCM Control 3.11.2.2

Yearly air dose limitsODCM Control 3.11.2.2

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


Quarterly dose limitsODCM Control 3.11.2.3

Yearly dose limitsODCM Control 3.11.2.3


Quarterly dose limitsODCM Control 3.11.1.2

Yearly dose limitsODCM Control 3.11.1.2

b. <7.5

c. <_15

mrem

mrem

Any Organ

Any Organ

3. Liquid Effluentsa. Concentration 10 CFR 20,

Column 2Appendix B, Table 2

b. <1.5_5

mremmrem

mremmrem

Total BodyAny Organ

Total BodyAny Organ

C. <_3<_10

B. Effluent Concentration Limits:

Gaseous dose rates rather than effluent concentrations are used to calculatepermissible release rates for gaseous releases. The maximum permissibledose 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 permissiblerelease rates and concentrations for liquid release per the Oyster CreekOffsite Dose Calculation Manual Control 3.11.1.1. The total activityconcentration at the Route 9 bridge for all dissolved or entrained gases waslimited to < 2E-04 p.Ci/mL.

C. Average Energy (-):

The Oyster Creek ODCM limits the instantaeneous dose equivalent rates dueto the release of noble gases to less than or equal to 500 mrem/year to thetotal body and less than or equal to 3000 mrem/year to the skin. Theaverage beta and gamma energies (T) of the radionuclide mixture inreleases of fission and activation gases as described in Regulatory Guide

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1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastesand Releases of Radioactive Materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants," may be used to calculate dosesin lieu of more sophisticated software. The Oyster Creek radioactive effluentprogram employs the methodologies presented in U.S. NRC RegulatoryGuide 1.109 "Calculation of Annual Doses to Man from Routine Releases ofReactor Effluents for the Purpose of Evaluating Compliance with 10 CFRPart 50, Appendix I," Revision 1, October 1977 and NUREG-01 33,"Preparation of Radiological Effluent Technical Specifications for NuclearPower Plants, October 1978. Therefore, average energies are not applicableto Oyster Creek.

D. Measurements and Approximations of Total Radioactivity:

1. Fission and Activation Gases

The method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a gas Marinelli beaker. Airborne effluentgaseous activity was continuously monitored and recorded inaccordance with ODCM Table 4.11.2.1.2-1. Additional grab sampleswere taken from the stack RAGEMS sample point and ground-levelrelease sample points and analyzed at least monthly to determine theisotopic mixture of noble gas activity released for the month. The datafrom the noble gas radiation monitor were analyzed to report net noblegas effluent activity. If activity was found in the grab isotopic analysis,the isotopic mixture for the Noble Gas Monitor was determined fromthat isotopic mixture.

The stack sample line was degraded during 2008. The 2008 stackreleases were based on the last half of 2010 adjusted for known plantvariables such as AOG system availability, plant power level and offgas release rates.

2. Particulates and lodines

The method used for Gamma Isotopic Analysis is the Canberra GammaSpectroscopy System with a particulate filter (47 mm) and/or charcoalcartridge, respectively. Particulate and iodine activity was continuouslysampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1.Charcoal and particulate samples are taken from the stack RAGEMSsample point and ground-level release sample points and analyzed atleast weekly to determine the total activity released from the plantbased on the highest vent flow rates recorded for the sampling period.

The stack sample line was degraded during 2008. The 2008 stackreleases were based on the last half of 2010 adjusted for known plantvariables such as AOG system availability, plant power level and offgas release rates.

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3. Liquid Effluents

During 2008, there were no radiological liquid releases. Since therewere no liquid discharges in 2008, there was no dose attributable toliquid effluents.

4. Tritium in Gaseous Effluents:

Air from stack effluents was passed through a desiccant column anddistilled to remove the tritiated water collected. An aliquot of the waterfrom the distillate was analyzed using a liquid scintillation counter.

The stack sample line was degraded during 2008. The 2008 stacktritium releases were based on the last half of 2010 adjusted for plantpower level.

5. Comoosite Samples and Lower Limit of Detection (LLD)

Particulate air samples were composited monthly and analyzed forgross alpha, Sr-89 and Sr-90. These composites are submitted to anoffsite vendor laboratory for analysis.

6. Estimated Total Error Present

Procedure CY-AA-170-2100, Estimated Errors of EffluentMeasurements, provides the methodology to obtain an overall estimateof the error associated with radioactive effluents.

E. Abnormal Releases: There were no abnormal releases during 2008.

F. Revisions to the ODCM

There were no changes to the ODCM in 2008.

G. Radiation Effluent Monitors Out of Service More Than 30 Days

Per ODCM Control 3.11, "Radioactive Liquid Effluent MonitoringInstrumentation" and Table 3.3.3.11-1 Radioactive Gaseous EffluentMonitoring Instrumentation", instrumentation requires:

With less than the minimum number of radioactive gaseous effluentmonitoring instrumentation channels OPERABLE, take the ACTION shown inTable 3.3.3.11-1. Restore the inoperable instrumentation to OPERABLEstatus within the time specified in the ACTION or explain in the next AnnualRadioactive Effluent Release Report why this inoperability was not correctedwithin the time specified.

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

The Service Water radiation monitor was out of service from 09/25/2008 to12/31/2008 due to inoperable instrumentation. An investigation revealed thatthe monitor could not be repaired and that new components had to bemanufactured.

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H. Changes to the Process Control Plan

Revisions 6 and 7 of the Process Control Plan (PCP) (RW-AA-100) wereapproved June 2008 and December 2008 respectively. Complete copies ofthe procedures, along with a summary of changes were included in theoriginal submittal.

1. Releases from the Independent Spent Fuel Storage Facility

The Independent Spent Fuel Storage Installation (ISFSI) is a closed systemand the only exposure would be due to direct radiation. This includesiodines, particulates, and noble gases. Based on offsite TLD readings, dosedue to direct radiation from the ISFSI was less than 1 mRem for 2008.Because it is a sealed unit, no radioactive material was released.

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Appendix AEffluent and Waste Disposal Summary

LIST OF TABLES

PAGE

Table A - 1 Gaseous Effluents - Summation of All Releases 9

Table A - 2 Gaseous Effluents for Release Point - Elevated 10

Table A - 3 Gaseous Effluents for Release Point - Ground Level 11

Table A - 4 Liquid Effluents - Summation of All Releases 12

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TABLE A -1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES PERIOD 2008

I A. FISSION AND ACTIVATION GASES

Est. TotalUnits Qtr 1 Qtr 2 Qtr 3 Qtr 4 Erroral

Error %

1. Total Release Ci 1.87E+01 1.42E+01 1.55E+01 9.02E+00 2.50E+012. Average Release Rate for Period uCi/sec 2.38E+00 1.81E+00 1.95E+00 1.13E+003. Dose m rad 8.05E-04 3.84E-04 4.44E-04 3.75E-03- Gamma Air Dose

- Beta Air Dose mrad 3.21 E-04 1.95E-04 2.33E-04 4.62E-034. Percent of ODCM Limit % 1.61 E-02 7.68E-03 8.88E-03 7.50E-02

- Gamma Air Dose- Beta Air Dose % 3.21 E-03 1.95E-03 2.33E-03 4.62E-02

B. IODINES


Error %

1. Total - 1-131 Ci 7.27E-04 5.46E-04 5.88E-04 4.91E-04 2.50E+012. Average Release Rate for Period uCi/sec 9.25E-05 6.94E-05 7.40E-05 6.18E-05

C. PARTICULATES


Error %

1. Particulates with T 1/2 > 8 days Ci 5.34E-03 5.13E-03 5.51E-03 2.51E-03 2.50E+012. Average Release Rate for Period uCi/sec 6.80E-04 6.53E-04 6.94E-04 3.16E-043. Gross Alpha Radioactivity Ci 1.75E-06 1.76E-06 1.89E-06 7.29E-07

D. TRITIUMUnits Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Total

Error %

1. Total Release Ci 1.51E+01 1.51E+01 1.63E+01 6.73E+00 2.50E+01

2. Average Release Rate for Period uCi/sec 11.90E+06 1.89E+06 12.01E+06 18.09E+05

E. Iodine 131 & 133, Tritium & Particulate

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4

1. OrganDose mrem 7.57E-03 1.27E-02 1.20E-02 4.50E-032. Percent of ODCM Limit % 1.01 E-01 1.69E-01 1.60E-01 6.OOE-02* ODCM Limit is for combined Iodine, tritium and particulate only, which is shown in Item E.

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TABLE A - 2 GASEOUS EFFLUENTS FOR RELEASE POINT - ELEVATED

1. FISSION AND ACTIVATION GASES

PERIOD 2008

Nuclide Released Continuous ModeUnits Qtr 1 Qtr 2 Qtr 3 Qtr 4

Kr-85 Ci <LLD <LLD <LLD <LLDKr-85m Ci 7.52E-01 5.71 E-01 6.23E-01 3.37E-01Kr-87 Ci 3.27E+00 2.49E+00 2.71 E+00 1.47E+00Kr-88 Ci 2.18E+00 1.65E+00 1.80E+00 9.77E-01Xe-131m Ci <LLD <LLD <LLD <LLDXe-1 33 Ci <LLD <LLD <LLD <LLDXe-1 33m Ci <LLD <LLD <LLD <LLDXe-135 Ci 1.25E+01 9.51 E+00 1.04E+01 5.62E+00Xe-135m Ci <LLD <LLD <LLD <LLDXe-138 Ci <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLDTotal for Period Ci 1.87E+01 1.42E+01 1.55E+01 8.40E+00

2. IODINES


1-131 Ci 7.27E-04 5.46E-04 5.88E-04 4.74E-041-133 Ci 1.68E-03 1.26E-03 1.36E-03 8.95E-041-135 <LLD <LLD <LLD <LLDTotal for Period Ci 2.41 E-03 1.81 E-03 1.95E-03 1.37E-03

3. PARTICULATES (T 1/2 > 8 DAYS)


Sr-89 Ci 1.58E-03 1.60E-03 1.72E-03 6.62E-04Sr-90 Ci 5.60E-06 5.65E-06 6.07E-06 2.34E-06Cs-1 34 Ci <LLD <LLD <LLD <LLDCs-137 Ci 2.58E-05 2.61E-05 2.80E-05 1. .13E-05Ba-140 Ci 9.61 E-04 7.22E-04 7.76E-04 5.50E-04La-1 40 Ci <LLD <LLD <LLD <LLDCr-51 Ci <LLD <LLD <LLD <LLDMn-54 Ci 8.02E-04 8.09E-04 8.69E-04 3.71 E-04Co-58 Ci 4.49E-04 4.53E-04 4.87E-04 1.92E-04Co-60 Ci 1.20E-03 1.21 E-03 1.30E-03 5.72E-04Mo-99 Ci 7.22E-05 5.42E-05 5.83E-05 3.81 E-05Ag-110m Ci <LLD <LLD <LLD <LLDCe-141 Ci <LLD <LLD <LLD <LLDCe-144 Ci <LLD <LLD <LLD <LLDFe-59 Ci <LLD <LLD <LLD <LLDZn-65 Ci 2.47E-04 2.49E-04 2.67E-04 1.09E-04Total for Period Ci 5.34E-03 5.13E-03 5.51 E-03 2.51E-03

4. TRITIUM

Total For Peroid Ci 1.47E+01i 1.49E+01i 1.60E+01i 6.43E+0010

V N


TABLE A - 3 GASEOUS EFFLUENTS FOR RELEASE POINT - GROUND LEVEL

1. FISSION AND ACTIVATION GASSES

PERIOD 2008


Kr-85 Ci <LLD <LLD <LLD <LLDKr-85m Ci <LLD <LLD <LLD <LLDKr-87 Ci <LLD <LLD <LLD <LLDKr-88 Ci <LLD <LLD <LLD <LLDXe-131m Ci <LLD <LLD <LLD <LLDXe-133 Ci <LLD <LLD <LLD <LLDXe-133m Ci <LLD <LLD <LLD 6.15E-1Xe-1 35 Ci <LLD <LLD <LLD <LLDXe-1 35m Ci <LLD <LLD <LLD <LLDXe-138 Ci <LLD <LLD <LLD <LLDAr-41 Ci <LLD <LLD <LLD <LLDTotal for Period Ci <LLD <LLD <LLD 6.15E-1

2. IODINES


1-131 Ci <LLD <LLD <LLD 1.71 E-51-133 Ci <LLD <LLD <LLD <LLD

Total for Period Ci <LLD <LLD <LLD 1.71 E-5

3. PARTICULATES (T 1/2 > 8 DAYS)


Sr-89 Ci < LLD < LLD < LLD < LLDSr-90 Ci < LLD < LLD < LLD < LLDCs-134 Ci < LLD < LLD < LLD < LLDCs-137 Ci < LLD < LLD < LLD < LLDBa-140 Ci < LLD < LLD < LLD < LLDLa-140 Ci < LLD < LLD < LLD < LLDCr-51 Ci < LLD < LLD < LLD < LLDMn-54 Ci < LLD < LLD < LLD < LLDCo-58 Ci < LLD < LLD < LLD < LLDCo-60 Ci < LLD < LLD < LLD < LLDMo-99 Ci < LLD < LLD < LLD < LLDA -11Om Ci < LLD < LLD < LLD < LLDCe-141 Ci < LLD < LLD < LLD < LLDCe-144 Ci < LLD < LLD < LLD < LLDFe-59 Ci < LLD < LLD < LLD < LLDZn-65 Ci < LLD < LLD < LLD <LLDTotal for Period Ci < LLD < LLD < LLD < LLD

4. TRITIUM

Total For Peroid Ci 3.49E-01 2.02E-01i 2.75E-01 I 3.03E-0111


TABLE A - 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES PERIOD 2008

A. FISSION AND ACTIVATION PRODUCTS

Est. TotalUnits Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error %

1. Total release (not including tritium, Ci <LLD <LLD <LLD <LLD N/Agasses & alpha)

2. Average diluted concentration during uCi/mI <LLD <LLD <LLD <LLDbatch discharge for the period

3. Dose - Whole Body mrem N/A N/A N/A N/A- Organ mrem N/A N/A N/A N/A

4. % of ODCM Limit - Whole Body Dose* % N/A N/A N/A N/A- Organ Dose* % N/A N/A N/A N/A

B. TRITIUM


Error %

1. Total Release Ci <LLD <LLD <LLD <LLD N/A2. Average diluted concentration during uCi/mI N/A N/A N/A N/A

batch discharge for the period% of ODCM Limit - ECL % N/A N/A N/A N/A

C. DISSOLVED AND ENTRAINED GASSES

Es.TotalUnits Qtr 1 Qtr 2 Qtr 3 Qtr 4 Erroral

Error %

1. Total release Ci <LLD <LLD <LLD <LLD N/A2. Average diluted concentration during uCi/mI N/A N/A N/A N/A

batch discharge for the period.%of ODCM Limit - ECL % N/A N/A N/A N/A

D. GROSS ALPHA RADIOACTIVITY

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. TotalError %

1. Total release Ci <LLD <LLD <LLD <LLD N/A2. Average diluted concentration during uCi/ml N/A N/A N/A N/A

batch discharge for the period

Units Qtr 1 Qtr 2 Qtr ,3 Qtr 4 Est. TotalError %

E. Volume of waste released (prior to Liters N/A N/A N/A N/A N/Adilution)

F. Volume of dilution water used during Liters N/A N/A N/A N/A N/Aperiod I

* Percent of limit includes tritium.

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Appendix BSolid Waste and Irradiated Fuel Shipments

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A. Solid waste shipped offsite for burial or disposal (not irradiated fuel) 1/1/08 - 12/31/08

1. Type of waste

Type of waste Uniý 12 Month Period Estimated Error %a. Spent resin, filters sludges, evaporator bottoms, m3 2.14E+01 2.50E+01 J

etc Ci 4.53E+01

b. Dry compressible waste, contaminated equipment, m3 4.43E+02 2.50E+01etc. Ci 1.93E-01

Irradiated components, control rods, etc. 1 2M3 1 1.52E-01 I 2.50E+01

I Ci I 82.06E+04 I

.OiFilter Media I ml 1.18E+01 I 2.50E+01rt ICi I 5.66E+01

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

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

Waste Class Waste ClassA Percent B Percent

Isotope Curies * Abundance Curies * AbundanceCo-60 1.46E+00 3.48E+01 1.29E+01 3.14E+01

Cs-137 1.26E+00 3.01 E+01 1.93E+01 4.70E+01

Fe-55 1.03E+00 2.46E+01 5.99E+00 1.46E+01Mn-54 2.15E-01 5.13E+00 1.07E+00 2.60E+00Zn-65 1.01 E-01 2.41 E+00 2.42E-01 5.89E-01

C-14 6.73E-02 1.61 E+00 7.88E-01 1.92E+00Ni-63 2.88E-02 6.87E-01 3.89E-01 9.46E-01

Cs-134 1.21E-02 2.89E-01 2.70E-01 6.57E-01H-3 4.14E-03 9.88E-02 7.27E-02 1.77E-01Sr-90 3.84E-03 9.16E-02 5.91 E-02 1.44E-01

Ag-i 1 Om 3.51 E-03 8.37E-02 <LLD N/A

Ce-144 3.48E-03 8.30E-02 1.62E-02 3.94E-02

Pu-241 2.39E-03 5.70E-02 <LLD N/A

Co-57 5.25E-04 1.25E-02 <LLD N/A

Totals 4.19E+00 1.OOE+02 4.11 E+01 1.OOE+02

* Activity is estimated

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I Category B - Dry Compressible Waste, Contaminated Equipment, etc.

Waste Class A PercentIsotope Curies * Abundance

Fe-55 9.03E-02 4.65E+01

Co-60 4.34E-02 2.24E+01

Mn-54 2.62E-02 1.35E+01

Cs-137 1.89E-02 9.74E+00

Zn-65 1.25E-02 6.44E+00

Ni-63 8.05E-04 4.15E-01

Co-58 6.22E-04 3.20E-01

Ag-110m 6.04E-04 3.11E-01

Cs-134 2.08E-04 1.07E-01

Ce-144 1.58E-04 8.14E-02

Other 3.83E-04 1.97E-01

Totals 1.94E-01 1.OOE+02

* Activity is estimated

Category C - Irradiated components, control rods, etc.

Waste Class C PercentIsotope Curies * Abundance

Co-60 1.OOE+04 4.83E+01

Fe-55 9.48E+03 4.58E+01

Ni-63 9.43E+02 4.56E+00

Mn-54 2.62E+02 1.27E+00

Ni-59 4.86E+00 2.35E-02

C-14 1.46E+00 7.06E-03Co-58 1.46E+00 7.06E-03

H-3 7.OOE-01 3.38E-03

Nb-94 2.04E-02 9.86E-05

Cs-137 1.89E-02 9.13E-05Tc-99 1.06E-02 5.12E-05

Ce-144 1.58E-04 7.64E-07

Sr-90 5.91 E-05 2.86E-07Pu-241 3.52E-05 1.70E-07

Am-241 1.04E-06 5.03E-09

Pu-238 9.39E-07 4.54E-09

Cm-243 7.55E-07 3.65E-09

Cm-242 5.71 E-07 2.76E-09

Pu-239 3.12E-07 1.51 E-09

Totals 2.07E+04 1.OE+02

* Activity is estimated15


Category D - Oil Filter Media

Isotope Waste Class A Percent Waste Class A PercentCuries * Abundance Curies * Abundance

Cm-242 3.76E-04 4.72E+01 2.24E+01 3.96E+01Sr-89 1.74E-04 2.18E+01 1.79E+01 3.17E+01Co-58 1.06E-04 1.33E+01 2.86E+00 5.06E+00Pu-239 8.36E-05 1.05E+01 1.02E+01 1.80E+01Pu-238 4.74E-05 1.53E+00 1.53E+00 2.71 E+00Am-241 2.73E-06 3.42E-01 2.27E-04 4.01 E-04Cm-243 2.62E-06 3.29E-01 1.14E-02 2.02E-02C-14 2.26E-06 2.83E-01 1.43E+00 2.53E+00Ag-i 1 Om 7.57E-07 9.49E-02 1.01 E-01 1.79E-01Pu-241 6.54E-07 8.20E-02 1.34E-03 2.37E-03Sr-90 5.33E-07 6.68E-02 4.81 E-02 8.51 E-02Ce-144 1.70E-07 2.13E-02 4.12E-02 7.29E-02Cs-1 34 1.54E-07 1.93E-02Ni-63 1.48E-07 1.86E-02 2.69E-02 4.76E-02Zn-65 1.39E-07 1.74E-02 4.86E-05 8.59E-05Mn-54 8.34E-08 1.05E-02Cs-137 7.04E-08 8.83E-03Co-60 4.01 E-09 5.03E-04 1.15E-03 2.03E-03Fe-55 3.75E-09 4.70E-04 9.03E-04 1.60E-03H-3 2.53E-09 3.17E-04 1.15E-03 2.03E-03Co-57 2.07E-09 2.60E-04 3.78E-05 6.68E-05Tc-99 1.28E-09 1.61 E-04 2.74E-04 4.84E-04

Totals 7.97E-04 1.OOE+02 5.66E+01 1.OOE+02

3. Solid Waste (Disposition)

Number of Shipments Mode of Transportation Destination8 Hitman Transport Co. IBarnwell Waste Management7 Hitman Transport Co. Duratek3 Hitman Transport Co. IDuratek Radwaste Processing, Inc.

B. Irradiated Fuel Shipments (disposition). There were no irradiated fuel shipments.

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Appendix CRadiological Impact to Man

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Per ODCM Administrative Control 6.2, an assessment of radiation doses to the likely most exposedMEMBER 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 yearmust 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 assumptionswere made:

Gaseous0 Nearest resident was SE sector at 925 meters0

0

0

Actual meteorology and actual gaseous effluent releases were usedAll significant pathways were assumed to be presentOccupancy factor was considered 100%

I Liquid - There was no dose due to liquid releases

I A summary of gaseous and liquid radiation doses to most likely exposed MEMBER OF: THEPUBLIC was as follows:

Applicable Estimated Age Location % ofEffluent Distance Direction Applicable Limit Unit

Efflt Organ Dose Group (meters) (toward) Limit

Noble Gas Gamma- All 10 mradAir Dose 4.98E-03 405 E 4.98E-02 1 mSNoble Gas Beta - Air

Dose 5.17E-03 All 405 E 2.59E-02 20 mrad

Noble Gas Total Body All mrem(Gamma) 8.80E-04 925 SE 1.76E-02

Noble Gas Skin (Beta) 1.73E-03 All 925 SE 1.15E-02 15 mremIodine,

Particulate Bone 3.31E-02 Child 1169 ESE 2.21E-01 15 mrem& Tritium

Liquid Total body 0.OOE+00 N/A N/A 0.OOE+00 3 mremLiquid Organ 0.OOE+00 N/A N/A 0.OOE+00 10 mremDirect Total Body 0.OOE+00 All 925 SE <LLD 25 mremRadiation

40 CFR Part 190 Coi pliance 25 mremTotal Total Body 1.74E-02 All 925 SE 6.95E-02 25 mremDose

Dosetal Bone 3.81 E-02 All 925 SE 1.52E-01 25 mrem

Total Thyroid 2.32E-02 All 925 SE 3.09E-02 75 mremDose I _ _ _ _ I__ _ _ I___

Doses calculated were well below all ODCM and 40 CFR Part 190 limits of 75 mrem to the thyroidand 25 mrem to the total body and any other organ.

Total body doses to the population and average doses to individuals in the population fromgaseous effluents to a distance of 50 miles from the site is not required by technical Specificationsor ODCM.

No Members of the Public were active within the Site Boundary for a significant portion of theyear. 18


Appendix DMeteorological Data

Provided in original Submittal

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Oyster Creek - Revised Annual Radioactive Effluent Release ... · C Average Energy 4 D Measurements...

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