RA-12-004, Revised Annual Radioactive Effluent Release Report for 2008

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Revised Annual Radioactive Effluent Release Report for 2008
ML12363A020
Person / Time
Site: Oyster Creek
Issue date: 12/05/2012
From: Massaro M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-12-004C
Download: ML12363A020 (23)
v • d • e


Text

Exelon Generation.

Oyster Creek Generating Station www.exeloncorp.com Route 9 South PO Box 388 Forked River, NJ 08731 10 CFR 50.36a(a)(2) 10 CFR 72.44 (d)(3)

Technical Specification 6.9.1.d RA-12-004C December 5, 2012 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

Subject:

Revised Annual Radioactive Effluent Release Report for 2008 Enclosed with this cover letter is the revised copy of the Annual Radioactive Effluent Release Report for 2008. The report includes the Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Facility. Revision bars have been used to indicate 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. Massaro Site Vice President Oyster Creek Nuclear Generating Station

Enclosures:

2008 Annual Radioactive Effluent Release Report (Revision 3) cc: Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek Craig 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 to The United States Nuclear Regulatory Commission

, Pursuant to Renewed 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 ii

~, n Revised 2008 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 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 of 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 no liquid radioactive effluent releases above ODCM LLDs during 2008.

Therefore there was no dose due to radiological liquid releases. Utilizing gaseous effluent data, the maximum hypothetical dose to any individual was calculated using a mathematical model, which is based on the methods defined by the U.S. Nuclear Regulatory Commission. These methods accurately determine the types and quantities of radioactive materials being released to the environment.

The maximum hypothetical calculated organ dose (bone) from iodines, particulates and tritium 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 calculated gamma air dose in the UNRESTRICTED AREA due to noble gas effluents was 4.98E-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 from gaseous effluents from OCGS for the reporting period due to all radiological effluents is 3.81 E-2 mrem (0.0381 mrem). This value is more than 7,500 times lower than the dose the average individual in the Oyster Creek area received from background radiation, including that from radon during the same time period. The background radiation dose averages approximately 300 mRem per year in the Central New Jersey area, which includes approximately 200 mRem/year 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 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 2008. Because it is a sealed unit, no radioactive material was released.

1

Revised 2008 Annual Radioactive Effluent Release Report 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 7.55 mCi and total particulates with half-lives greater than 8 days 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 all stability classes, were included in the original submittal and did not change. All data was collected from the on-site Meteorological Facility. Data recoveries for the 380-foot data and the 33-foot data were 97.9 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.

2

Revised 2008 Annual Radioactive Effluent Release Report

1. Introduction In accordance with the reporting requirements of Technical Specification 3.6.E.1 applicable during the reporting period, this report summarizes the effluent release data for Oyster Creek Generating Station for the period January 1, 2008 through December 31, 2008. 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".

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

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

3

Revised 2008 Annual Radioactive Effluent Release Report

2. Supplemental Information A. Regulatory Limits Limit Units Receptor ODCM and 10 CFR 50, Appendix I Desiqn 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 (Gamma) 10 CFR 50, Appendix I,

<15 mrem Skin (Beta) Section II.B.2(b)

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, Table 2 ODCM Control 3.11.1.1 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 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 the Oyster Creek Offsite Dose Calculation Manual Control 3.11.1.1. The total activity concentration at the Route 9 bridge for all dissolved or entrained gases was limited to < 2E-04 p.Ci/mL.

C. Average Energy (-):

The Oyster Creek ODCM limits the instantaeneous 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 (T) of the radionuclide mixture in releases of fission and activation gases as described in Regulatory Guide 4

I Revised 2008 Annual Radioactive Effluent Release Report 1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," may be used to calculate doses in lieu of more sophisticated software. The 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 and NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978. Therefore, average energies are 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 ODCM Table 4.11.2.1.2-1. Additional grab samples were taken from the stack 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. The data from the noble gas radiation monitor were analyzed to report net noble gas effluent activity. If activity was found in the grab isotopic analysis, the isotopic mixture for the Noble Gas Monitor was determined from that isotopic mixture.

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

2. Particulates and lodines The method used for Gamma Isotopic Analysis is the Canberra Gamma Spectroscopy System with a particulate filter (47 mm) and/or charcoal cartridge, respectively. Particulate and iodine activity was continuously sampled and analyzed in accordance with ODCM Table 4.11.2.1.2-1.

Charcoal and 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 highest vent flow rates recorded for the sampling period.

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

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Revised 2008 Annual Radioactive Effluent Release Report

3. Liquid Effluents During 2008, there were no radiological liquid releases. Since there were no liquid discharges in 2008, there was no dose attributable to liquid effluents.
4. Tritium in Gaseous Effluents:

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

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

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

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

6. 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.

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 Monitoring Instrumentation" and Table 3.3.3.11-1 Radioactive Gaseous Effluent Monitoring Instrumentation", instrumentation requires:

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. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

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

The Service Water radiation monitor was out of service from 09/25/2008 to 12/31/2008 due to inoperable instrumentation. An investigation revealed that the monitor could not be repaired and that new components had to be manufactured.

6

Revised 2008 Annual Radioactive Effluent Release Report H. Changes to the Process Control Plan Revisions 6 and 7 of the Process Control Plan (PCP) (RW-AA-100) were approved June 2008 and December 2008 respectively. Complete copies of the procedures, along with a summary of changes were included in the original submittal.

1. Releases from the Independent Spent Fuel Storage Facility 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 1mRem for 2008.

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

7

Revised 2008 Annual Radioactive Effluent Release Report Appendix A Effluent 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 8

Revised 2008 Annual Radioactive Effluent Release Report TABLE A -1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES PERIOD 2008 I A. FISSION AND ACTIVATION GASES Qtr 4 Est. Total Erroral Units Qtr 1 Qtr 2 Qtr 3 Error %

1. Total Release Ci 1.87E+01 1.42E+01 1.55E+01 9.02E+00 2.50E+01
2. Average Release Rate for Period uCi/sec 2.38E+00 1.81E+00 1.95E+00 1.13E+00
3. 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-03

4. 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 Est. Total Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Erroral Error %

1. Total 131 Ci 7.27E-04 5.46E-04 5.88E-04 4.91E-04 2.50E+01
2. Average Release Rate for Period uCi/sec 9.25E-05 6.94E-05 7.40E-05 6.18E-05 C. PARTICULATES Est. Total Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Erroral Error %
1. Particulates with T 1/2 > 8 days Ci 5.34E-03 5.13E-03 5.51E-03 2.51E-03 2.50E+01
2. Average Release Rate for Period uCi/sec 6.80E-04 6.53E-04 6.94E-04 3.16E-04
3. Gross Alpha Radioactivity Ci 1.75E-06 1.76E-06 1.89E-06 7.29E-07 D. TRITIUM Units 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-03
2. 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.

9 I I

Revised 2008 Annual Radioactive Effluent Release Report TABLE A - 2 GASEOUS EFFLUENTS FOR RELEASE POINT - ELEVATED PERIOD 2008

1. FISSION AND ACTIVATION GASES Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci 7.52E-01 5.71 E-01 6.23E-01 3.37E-01 Kr-87 Ci 3.27E+00 2.49E+00 2.71 E+00 1.47E+00 Kr-88 Ci 2.18E+00 1.65E+00 1.80E+00 9.77E-01 Xe-131m Ci <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD Xe-1 33m Ci <LLD <LLD <LLD <LLD Xe-135 Ci 1.25E+01 9.51 E+00 1.04E+01 5.62E+00 Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD Total for Period Ci 1.87E+01 1.42E+01 1.55E+01 8.40E+00
2. IODINES Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 1-131 Ci 7.27E-04 5.46E-04 5.88E-04 4.74E-04 1-133 Ci 1.68E-03 1.26E-03 1.36E-03 8.95E-04 1-135 <LLD <LLD <LLD <LLD Total for Period Ci 2.41 E-03 1.81 E-03 1.95E-03 1.37E-03
3. PARTICULATES (T 1/2 > 8 DAYS)

Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Sr-89 Ci 1.58E-03 1.60E-03 1.72E-03 6.62E-04 Sr-90 Ci 5.60E-06 5.65E-06 6.07E-06 2.34E-06 Cs-1 34 Ci <LLD <LLD <LLD <LLD Cs-137 Ci 2.58E-05 2.61E-05 2.80E-05 1..13E-05 Ba-140 Ci 9.61 E-04 7.22E-04 7.76E-04 5.50E-04 La-1 40 Ci <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci 8.02E-04 8.09E-04 8.69E-04 3.71 E-04 Co-58 Ci 4.49E-04 4.53E-04 4.87E-04 1.92E-04 Co-60 Ci 1.20E-03 1.21 E-03 1.30E-03 5.72E-04 Mo-99 Ci 7.22E-05 5.42E-05 5.83E-05 3.81 E-05 Ag-110m Ci <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Zn-65 Ci 2.47E-04 2.49E-04 2.67E-04 1.09E-04 Total 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+00 10

V N Revised 2008 Annual Radioactive Effluent Release Report TABLE A - 3 GASEOUS EFFLUENTS FOR RELEASE POINT - GROUND LEVEL PERIOD 2008

1. FISSION AND ACTIVATION GASSES Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Kr-85 Ci <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD 6.15E-1 Xe-1 35 Ci <LLD <LLD <LLD <LLD Xe-1 35m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 6.15E-1
2. IODINES Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 1-131 Ci <LLD <LLD <LLD 1.71 E-5 1-133 Ci <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD 1.71 E-5
3. PARTICULATES (T 1/2 > 8 DAYS)

Nuclide Released Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD < LLD < LLD Ba-140 Ci < LLD < LLD < LLD < LLD La-140 Ci < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD Mo-99 Ci < LLD < LLD < LLD < LLD A -11Om Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD <LLD Total 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-01 11

Revised 2008 Annual Radioactive Effluent Release Report TABLE A - 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES PERIOD 2008 A. FISSION AND ACTIVATION PRODUCTS Qtr 4 Est.

ErrorTotal Units Qtr 1 Qtr 2 Qtr 3

1. Total release (not including tritium, Ci <LLD <LLD <LLD <LLD N/A gasses & alpha)
2. Average diluted concentration during uCi/mI <LLD <LLD <LLD <LLD batch 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 Est. Total Erroral Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error %

1. Total Release Ci <LLD <LLD <LLD <LLD N/A
2. 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 Qtr 4 Es.Total Erroral Units Qtr 1 Qtr 2 Qtr 3 Error %

1. Total release Ci <LLD <LLD <LLD <LLD N/A
2. 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. Total Error %

1. Total release Ci <LLD <LLD <LLD <LLD N/A
2. 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. Total Error %

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

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

12

Revised 2008 Annual Radioactive Effluent Release Report Appendix B Solid Waste and Irradiated Fuel Shipments 13

Revised 2008 Annual Radioactive Effluent Release Report 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+01 etc. Ci 1.93E-01 Irradiated components, control rods, etc. 1 31 1.52E-01 2M I 2.50E+01 I Ci I 82.06E+04 I

.OiFilter Media Iml 1.18E+01 I 2.50E+01 rt 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 Class A Percent B Percent Isotope Curies

  • Abundance Curies
  • Abundance Co-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+01 Mn-54 2.15E-01 5.13E+00 1.07E+00 2.60E+00 Zn-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+00 Ni-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-01 H-3 4.14E-03 9.88E-02 7.27E-02 1.77E-01 Sr-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 14

Revised 2008 Annual Radioactive Effluent Release Report I Category B - Dry Compressible Waste, Contaminated Equipment, etc.

Waste Class A Percent Isotope 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 Percent Isotope 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-03 Co-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-05 Tc-99 1.06E-02 5.12E-05 Ce-144 1.58E-04 7.64E-07 Sr-90 5.91 E-05 2.86E-07 Pu-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 estimated 15

Revised 2008 Annual Radioactive Effluent Release Report Category D - Oil Filter Media Isotope Waste Class A Percent Waste Class A Percent Curies

  • Abundance Curies
  • Abundance Cm-242 3.76E-04 4.72E+01 2.24E+01 3.96E+01 Sr-89 1.74E-04 2.18E+01 1.79E+01 3.17E+01 Co-58 1.06E-04 1.33E+01 2.86E+00 5.06E+00 Pu-239 8.36E-05 1.05E+01 1.02E+01 1.80E+01 Pu-238 4.74E-05 1.53E+00 1.53E+00 2.71 E+00 Am-241 2.73E-06 3.42E-01 2.27E-04 4.01 E-04 Cm-243 2.62E-06 3.29E-01 1.14E-02 2.02E-02 C-14 2.26E-06 2.83E-01 1.43E+00 2.53E+00 Ag-i 1Om 7.57E-07 9.49E-02 1.01 E-01 1.79E-01 Pu-241 6.54E-07 8.20E-02 1.34E-03 2.37E-03 Sr-90 5.33E-07 6.68E-02 4.81 E-02 8.51 E-02 Ce-144 1.70E-07 2.13E-02 4.12E-02 7.29E-02 Cs-1 34 1.54E-07 1.93E-02 Ni-63 1.48E-07 1.86E-02 2.69E-02 4.76E-02 Zn-65 1.39E-07 1.74E-02 4.86E-05 8.59E-05 Mn-54 8.34E-08 1.05E-02 Cs-137 7.04E-08 8.83E-03 Co-60 4.01 E-09 5.03E-04 1.15E-03 2.03E-03 Fe-55 3.75E-09 4.70E-04 9.03E-04 1.60E-03 H-3 2.53E-09 3.17E-04 1.15E-03 2.03E-03 Co-57 2.07E-09 2.60E-04 3.78E-05 6.68E-05 Tc-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 Destination 8 Hitman Transport Co. IBarnwell Waste Management 7 Hitman Transport Co. Duratek 3 Hitman Transport Co. IDuratek Radwaste Processing, Inc.

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

16

Revised 2008 Annual Radioactive Effluent Release Report Appendix C Radiological Impact to Man 17

Revised 2008 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 0 Nearest resident was SE sector at 925 meters 0 Actual meteorology and actual gaseous effluent releases were used 0 All significant pathways were assumed to be present 0 Occupancy factor was considered 100%

I Liquid - There was no dose due to liquid releases I Asummary of gaseous and liquid radiation doses to most likely exposed MEMBER OF: THE PUBLIC was as follows:

Applicable Estimated Age Location  % of Effluent Distance Direction Applicable Limit Unit Organ Efflt Dose Group (meters) (toward) Limit Noble Gas Gamma- All 10 mrad Air Dose 4.98E-03 405 E 4.98E-02 1 m SNoble 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 mrem Iodine, 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 mrem Liquid Organ 0.OOE+00 N/A N/A 0.OOE+00 10 mrem Direct Total Body 0.OOE+00 All 925 SE <LLD 25 Radiation mrem 40 CFR Part 190 Coi pliance 25 mrem Total Total Body 1.74E-02 All 925 SE 6.95E-02 25 Dose mrem 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 mrem Dose I _ _ _ _ _ _ I__ I___

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

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 is not required by technical Specifications or ODCM.

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

Revised 2008 Annual Radioactive Effluent Release Report Appendix D Meteorological Data Provided in original Submittal 19

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