Text

Annual Radioactive Effluent Release Report for 2002
	ML031120599
Person / Time
Site:	Harris
Issue date:	04/16/2003
From:	Caves J; Progress Energy Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-nr, HNP-03-046
	Download: ML031120599 (38)
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.,

n Progress Energy APR 1 6 2003 SERIAL: HNP-03-046 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:

In accordance with Technical Specification 6.9.1.4 for the Harris Nuclear Plant, Progress Energy Carolinas, Inc. (also known as Carolina Power & Light Company) is providing the enclosed Annual Radioactive Effluent Release Report for 2002.

If you have questions regarding this information, please contact me at (919) 362-3137.

Sincerely, J. R. Caves Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant MGW Enclosure c:

Mr. J. B. Brady (NRC Senior Resident Inspector, HNP)

Mr. C. P. Patel (NRR Project Manager, HNP)

Mr. L. A. Reyes (NRC Regional Administrator, Region II)

Progress Energy Carolinas, Inc.

Harris Nuclear Plant P.O. Box 165 New Hill, NC 27562

Progress Energy Carolinas, Inc.

Shearon Harris Nuclear Power Plant Docket No. 50-400 Facility Operating License No. NPF-063 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2002 to December 31, 2002

Table of Contents Section Introduction Discussion Appendix 1.

Supplemental Information Appendix 2.

Effluent and Waste Disposal Report

1.

Lower Limits of Detection (LLDs)

2.

Effluents Released

3.

Solid Waste Disposal Appendix 3.

Changes to Offsite Dose Calculation Manual (ODCM)

Appendix 4.

Changes to the Environmental Monitoring Program

1.

Environmental Monitoring Program

2.

Land Use Census Appendix 5.

Additional Operational Requirements

1.

Inoperability of Liquid Effluent Monitors

2.

Inoperability of Gaseous Effluent Monitors

3.

Unprotected Outdoor Tanks Exceeding Limits

4.

Gas Storage Tanks Exceeding Limits Appendix 6.

Major Modifications to Radwaste System Appendix 7.

Meteorological Data Appendix 8.

Assessment of Radiation Doses Appendix 9.

Corrections to 2001 Annual Radioactive Effluent Release Report Current Revision of the ODCM Page No.

3 3

7 1 1 13 22 28 30 30 31 31 31 31 32 33 34 36 37 Introduction This Annual Radioactive Effluent Release Report is prepared in accordance with Shearon Harris Nuclear Power Plant's Operational Requirements -Offsite Dose Calculation Manual (ODCM), Section F.2, Technical Specification 6.9.1.4, Operating License No. NPF-63.

The Shearon Harris Nuclear Power Plant (SHNPP) achieved initial criticality on January 3, 1987. This Report covers the period from January 1, 2002 to December 31, 2002. During this period, the plant operated in Cycle 11. Steam generator replacement was completed in January, 2002.

Discussion I1.

Protection Standards The main objective in the control of radiation is to ensure that any exposure is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA concept applies to reducing radiation exposure both to workers at Harris Nuclear Plant and to the general public. "Reasonably Achievable" means that radiation exposure reduction is based on sound environmental practices, economic decisions, and operating practices. By practicing ALARA, Harris Nuclear Plant and Progress Energy Carolinas, Inc. minimize health risk, environmental detriment, and ensure that exposures are maintained well below regulatory limits.

2.

Sources of Radioactivity Released During normal operations of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small quantities of radioactive fission and activation products are present in the primary coolant water. The types of radioactive material released are noble gases, iodines and particulates, and tritium.

The noble gas fission products in the primary coolant are collected by a system designed for collection and storage for radioactive decay prior to release.

Small releases of radioactivity in liquids may occur from equipment associated with the primary coolant system. These liquids are collected and processed for radioactivity removal prior to release.

3.

Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as krypton and xenon. Noble gases are by nature inert and do not concentrate in humans or other organisms; therefore internal exposure is negligible. Their contribution to human radiation exposure is as an external exposure. Xenon-133 and Xenon-135, with half-lives of approximately 5 days and 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> respectively, are the major isotopes released. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay. Noble gases are readily dispersed in the atmosphere.

4.

lodines and Particulates Annual releases of iodines, and those particulates with half-lives greater than 8 days are small. Factors such as chemical reactivity and solubility in water, combined with high processing efficiencies, minimize their discharge. The main contribution of radioactive iodine to human exposure is to the thyroid gland, where the body concentrates iodine. The principal radioactive particulates are Cobalt-58 and Cobalt-60 which contribute to internal exposure of tissues such as the muscle, liver, and intestines. These particulates can also be a source of exposure if deposited on the ground.

5.

Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid and gaseous effluents.

Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) and boron, both of which are present in the primary coolant. Tritium contributes very little radiation exposure to the human body, and when it is inhaled or ingested, is dispersed throughout the body until eliminated.

6.

Processing and Monitoring Effluents are strictly controlled and monitored to ensure that radioactivity released to the environment is minimal and within regulatory limits. Effluent control includes the operation of radiation monitoring systems, in-plant and environmental sampling and analyses, quality assurance programs for both in-plant and environmental sampling and analyses, and procedures that address effluent and environmental monitoring.

The plant radiation monitoring system has monitors that are designed to ensure that all releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set lower than the ODCM Operational Requirements to ensure the limits are not exceeded. If a monitor alarms, a release from a tank is automatically suspended. Additionally, batch releases are sampled and analyzed in the laboratory prior to discharge. The sampling and analysis done in the laboratory provides a more sensitive and precise method of determining effluent composition than in-plant monitoring instruments.

The plant has a meteorological tower, which is linked to computers that record the meteorological data. The meteorological data and the release data can be used to assess the dose to the public. The doses reported in this report use twelve-year average (1976 through 1987) data from the onsite meteorological program.

In addition to in-plant equipment the company maintains a Radiological Environmental Monitoring Program, which consists of devices used to constantly sample the air and water in the environment. The samples collected from the surrounding environment are analyzed to determine any presence of radioactive material in the environment.

7.

Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material. The major pathways of concern are those that could cause the highest calculated radiation dose.

The projected pathways are determined from the type and amount of radioactive material that may have been released, the environmental transport mechanism, and the use of the environment. Environmental transport mechanisms include, but are not limited to, local hydrology (water) and meteorology (weather).

The release of radioactive gaseous effluents can impact the public via pathways such as external whole body exposure, deposition on plants and soils, and human inhalation. The release of radioactive material in liquid effluents can impact the public via pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and submersion dose while swimming.

Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure that will provide, for a specific radionuclide, the greatest exposure to a population, or a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, and other cultural factors. The exposure may be received to the whole body or to a specific organ, with the organ receiving the largest fraction of the exposure called the critical organ.

8.

Results The quantities of radioactive gaseous and liquid effluents and solid waste are reported using the format per Regulatory Guide 1.21 (Rev. 1) Appendix B.

The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the Harris Nuclear Plant during the period from January 1, 2002 through December 31, 2002. The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant are estimated using the methodology in the ODCM.

During the period of January 1, 2002 through December 31, 2002, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

Limit 2.23 E-03 mrem, Total Body 3.0 E+00 mrem 3.71 E-03 mrem, Max Organ (GI-LLI) 1.0 E+01 mrem Gaseous Effluents:

Limit Noble Gases 3.21 E-04 mrad, Beta 2.0 E+01 mrad 1.06 E-04 mrad, Gamma 1.0 E+01 mrad Tritium, Radioiodine 131, 133, and Particulates with greater than an 8 Day Half Life:

1.49 E-01 mrem, Critical Organ (Lung) 1.5 E+01 mrem(*)

(*) Limit applies to Tritium, Radioiodines, and Particulates with greater than an 8-Day Half Life:

These doses are in addition to what is received from natural background in the area surrounding the Harris Nuclear Plant (approximately 300 mrem per year).

Appendix 1: Supplemental Information Regulatory Limits A.

Fission and Activation Gases:

ODCM Operational Requirements Maximum Insiantaneous Release Rate Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr IOCFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table 2, Column 1. This is based on 100 mrem/yr.

10CFR50, Appendix I For Calendar Quarter Gamma Dose <5 mrad (Used for calculating percent of applicable limit.)

Beta Dose <10 mrad (Used for calculating percent of applicable limit.)

For Calendar Year Gamma Dose <10 mrad Beta Dose <20 mrad B.

Iodine - 131 and 133, Tritium, and Particulates >8 day half-lives:

ODCM Operational Requirements Maximum Instantaneous Release Rate is and inhalation dose (only) to a child to any organ

<1500 mremlyr IOCFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table 2, Column

1. This is based on 50 mrem/yr.

I0CFR50, Appendix I (Organ Doses)

For Calendar Quarter <7.5 mrem (Used for calculating percent of applicable limit.)

For Calendar Year <15 mrem C.

Liquids:

ODCM Operational Requirements Maximum Instantaneous Release Rate is ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.

ODCM Operational Requirements For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 VCi/ml total activity.

IOCFR20 Limits The annual average concentrations to be less than the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2.(Used for calculating percent of applicable limit.) This is based on 50 mrem/yr.

10CFR50, Appendix I For Calendar Quarter Total Body Dose <1.5 mrem Any Organ Dose <5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 mrem D.

Average Energy (E):

None applicable at HNP. HNP determines dose and dose rate based on actual releases. not on an average energy value.

Appendix 1: Supplemental Information (Continued)

Measurements and Approximations of Total Radioactivity A.

Continuous Gaseous Releases

1.

Fission and activation gases The total activity released is determined from the net activity of gaseous monitors times the total stack flow. The activity of each radionuclide is determined by the fraction of that radioactive gas in the isotopic analysis for that sampling period (typically weekly). If no activity is detected for the sampling period, the mix is based on historical data.

2.

lodines The activity released as iodine-131, 133, and 135 is based on isotopic analysis of the charcoal cartridge plus the particulate filter times the total vent flow for each sample period (typically weekly).

3.

Particulates The activity released as particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters times the total vent flow for each sample period.

The sample period is at a minimum weekly or more frequently if plant conditions require.

4.

Tritium The activity released as tritium is based on grab sample analysis using liquid scintillation times total stack flow. Grab sampling is typically performed weekly.

B.

Batch Gaseous Releases

1.

Fission and activation gases The activity released is based on the volume released times the activity of the individual nuclides obtained from an isotopic analysis of the grab sample taken prior to the release.

2.

lodines The iodine activity released from Waste Gas Decay Tank (WGDT) batch releases is included in the iodine determination from the continuous releases.

3.

Particulates The particulate activity released from Waste Gas Decay Tank (WGDT) batch releases is included in the particulate determination from the continuous releases.

4.

Tritium The activity released as tritium is based on the grab sample analysis using liquid scintillation of each batch times the batch volume.

C.

Liquid Releases

1.

Fission and Activation Products The total activity released (excluding tritium, strontium, iron-55, alpha, and nickel-63) is comprised of the sum of the products of the individual radionuclide concentrations in each batch (identified using gamma spectroscopy) times the volume of the batch.

2.

Alpha and Tritium The alpha activity released is the monthly composite alpha concentration times the volume released for the month.

The tritium activity released is the concentration of tritium in each batch release times the volume of the batch release.

The tritium activity released through the continuous pathways (turbine building drains and secondary waste) is the concentration from monthly composite samples (corrected for makeup water concentrations) times the volume released for the month. Makeup water is from the lake and has detectable tritium.

3.

Strontium-89, 90, Iron-55, and Nickel-63 Analyses are performed on quarterly composite samples times the volume released during the quarter to calculate the activity released.

D.

Estimated Total Errors

1.

Estimated total errors for gaseous effluents are based on uncertainties in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

2.

Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, sampling, and volume determinations.

.9-

Appendix 1: Supplemental Information (Continued)

II.

Batch Releases (2002)

A.

Liquid Batch Releases Jan - June 2002 f

July - Dec 2002 Number of batch releases 2.70 E+01 1.30 E+01 Total time period for batch releases 1.97 E+04 minutes 9.39 E+03 minutes Maximum time of a batch release 8.07 E+02 minutes 7.75 E+02 minutes Average time for a batch release 7.28 E+02 minutes 7.22 E+02 minutes Minimum Time for a batch release 6.35 E+02 minutes 6.05 E+02 minutes Average stream flow during periods of release 1.42 E+04 gpm 1.37 E+04 gpm B.

Gaseous Batch Releases I

Jan - June 2002 July - Dec 2002 Number of batch releases 4.00 E+00 0.00 E+00 Total time period for batch releases 9.47 E+02 minutes 0.00 E+00 minutes Maximum time of a batch release 4.79 E+02 minutes 0.00 E+00 minutes Average time for a batch release 2.37 E+02 minutes 0.00 E+00 minutes Minimum Time for a batch release 1.70 E+01 minutes 0.00 E+00 minutes C.

Abnormal Releases

a.

Liquid No abnormal liquid releases were made during 2002.

b.

Gaseous No abnormal gaseous releases were made during 2002.

Appendix 2: Effluent and Waste Disposal Report Enclosure I: LOWER LIMITS OF DETECTION (LLDs)

LLDs for Gaseous Effluents Nuclide MCikcc Gross Alpha 5.53 E-15 H-3 2.87 E-09 Ar-41 4.68 E-08 Kr-85 4.02 E-06 Kr-85m 5.45 E-09 Kr-87 1.10 E-08 Kr-88 2.55 E-08 Xe-131m 2.66 E-07 Xe-133 2.00 E-08 Xe-133m 5.70 E-08 Xe-135 7.48 E-09 Xe-135m 5.38 E-09 Xe-138 5.61 E-07 1-131 3.64 E-13 1-133 7.63 E-13 1-135 9.16 E-12 Cr-51 3.86 E-12 Mn-54 7.62 E-13 Co-58 7.42 E-13 Fe-59 6.80 E-13 Co-60 4.72 E-13 Zn-65 7.67 E-13 Sr-89 2.35 E-15 Sr-90 1.16 E-15 Nb-95 6.94 E-13 Zr-95 4.53 E-13 Mo-99 1.99 E-12 Cs-134 3.11 E-13 Cs-137 6.86 E-13 Ba-140 2.35 E-12 La-140 6.32 E-13 Ce-141 4.55 E-13 Ce-144 2.28 E-12

- II -

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure I: LOWER LIMITS OF DETECTION (LLDs)

2.

LLDs for Liquid Effluents Nuclide uCi/ml Gross Alpha 8.99 E-08 H-3 1.86 E-06 Na-24 3.00 E-08 Cr-51 2.50 E-07 Mn-54 4.91 E-08 Fe-55 2.12 E-08 Co-57 2.79 E-08 Co-58 4.81 E-08 Fe-59 4.12 E-08 Co-60 2.78 E-08 Ni-63 4.23 E-08 Zn-65 4.65 E-08 Sr-89 2.86 E-08 Sr-90 1.72 E-08 Nb-95 4.02 E-08 Zr-95 8.10 E-08 Mo-99 3.47 E-07 Tc-99m 2.69 E-08 Ru-106 3.80 E-07 Sb-124 7.02 E-08 Sb-125 8.82 E-08 Sb-126 2.96 E-08 1-131 2.73 E-08 1-133 5.61 E-08 Te-132 2.81 E-08 Xe-133 6.54 E-08 Xe-133m 2.25 E-07 Xe-135 2.36 E-08 Cs-134 2.02 E-08 Cs-137 1.70 E-08 Ba-140 4.77 E-08 La-140 3.49 E-08 Ce-141 4.11 E-08 Ce-144 1.68 E-07 Appendix 2: Effluent and Waste Disposal Report (Continued) : Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

[ Unit Quarter Quarter Est. Total 2

Error %

A.

Fission and activation gases

1.

Total release Ci 4.64 E-0l

<LLD 5.27 E+01 l

2.

Average release rate for period pCi/sec 5.96 E-02

<LLD

3.

Percent of ODCM Operational Requirement limit 9.67 E-04

<LLD B.

lodines I

I.

Total iodine-131 Ci I

<LLD I

<LLD 3.04 E+i lI

2.

Average release rate for period pci/sec

<LLD

<LLD 4

4

3.

Percent of ODCM Operational Requirement limit*

2.36 E-01 4.03 E-01 C.

Particulates

1.

Particulates with half-lives >8 days Ci 1.47 E-05 3.24 E-06 3.38:E+01:l

2.

Average release rate for period pCi/sec 1.89 E-06 4.12 E-07

3.

Percent of ODCM Operational Requirement limit*

2.36 E-01 4.03 E-01

4.

Gross alpha radioactivity Ci

<LLD

<LLD D.

Tritium I

I.

Total release I

Ci l

1.31 E+01 l

2.24 E+01 l

5.22 E+01

2.

Average release rate for period pCi/sec 1.68 E+00 2.85 E+00

3.

Percent of ODCM Operational Requirement limit* j

% I 2.36 E-0l l

4.03 E-01 The Percent of ODCM Operational Requirement limits applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the lung.

Appendix 2: Effluent and Waste Disposal Report (Continued) : Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

[ Unit Quarter Quarter l

Est. Total l

l 3

4

[ Error%

A.

Fission and activation gases

1.

Total release Ci 4.09 E-01 6.98 E-01 5.27 E+01 l

2.

Average release rate for period pCilsec 5.14 E-02 8.78 E-02

3.

Percent of ODCM Operational Requirement limit I8.30 E-04 1.42 E-03 B.

lodines I

1. Total iodine-131 I

Ci I

<LLD I

<LLD l

3.04 E+I1

2.

Average release rate for period pCi/sec

<LLD

<LLD I

t

3.

Percent of ODCM Operational Requirement limit*

5.77 E-01 7.73 E-01 Particulates

1.

Particulates with half-lives >8 days Ci 3.29 E-05

<LLD i3.38 E+01

2.

Average release rate for period pCi/sec 4.14 E-06

<LLD

3.

Percent of ODCM Operational Requirement limit*

5.77 E-01 7.73 E-01

4.

Gross alpha radioactivity Ci

<LLD

<LLD D.

Tritium I

1.

Total release I

Ci l

3.19 E+01 l

4.30 E+01 l

5.22 E+01 I

2.

Average release rate for period pCi/sec 4.01 E-00 5.40 E-00

3.

Percent of ODCM Operational Requirement limit*

5.77 E-01 7.73 E-01 The Percent of ODCM Operational Requirement limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the lung.

Appendix 2: Effluent and Waste Disposal Report (Continued) : Effluents Released Table IB: GASEOUS EFFLUENTS -ELEVATED RELEASES All releases at Shearon Harris Nuclear Power Plant are considered ground releases.

Appendix 2: Effluent and Waste Disposal Report (Continued) : Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 1]

Nuclides Released Unit Quarter I Quarter 2 Quarter I Quarter 2 I. Fission Gases Xenon-131 m Ci

<LLD

<LLD Note 2 Xenon-133 Ci 4.49 E-01

<LLD

<LLD Note 2 Xenon-133m Ci

<LLD

<LLD Note 2 Xenon-135 Ci

<LLD

<LLD Note 2 Xenon-135m Ci

<LLD

<LLD Note 2 Xenon-138 Ci

<LLD

<LLD Note 2 Argon-41 Ci

<LLD

<LLD Note 2 Krypton-85 Ci

<LLD

<LLD 1.47 E-02 Note 2 Krypton-85m Ci

<LLD

<LLD Note 2 Krypton-87 Ci

<LLD

<LLD Note 2 Krypton-88 Ci

<LLD

<LLD Note 2 Totalforperod l

Ci l

4.49 E-01 l

<LLD 1.47 E-02 Note 2

2. lodines Iodine-1 31 Ci

<LLD

<LLD l

Note I l

Note 2 Iodine-1 33 Ci

<LLD

<LLD Note I Note 2 Iodine-135 Ci

<LLD

<LLD Note I Note 2 Total for period Ci

<LLD

<LLD Note I Note 2

3. Particulates Chromium-51 Ci

<LLD

<LLD Note I Note 2 Manganese-54 Ci

<LLD

<LLD Note I Note 2 Cobalt-58 Ci

<LLD

<LLD Note I Note 2 Iron-59 l

Ci

<LLD

<LLD Note I Note 2 Cobalt-60 Ci 1.47 E-05 3.24 E-06 Note I Note 2 Zinc-65 Ci

<LLD

<LLD Note I Note 2 Strontium-89 Ci

<LLD

<LLD Note I Note 2 Strontium-90 Ci

<LLD

<LLD Note I Note 2 Niobium-95 Ci

<LLD

<LLD Note I Note 2 Zirconium-95 Ci

<LLD

<LLD Note I Note 2 Molybdenum-99 Ci l

<LLD

<LLD Note I Note 2 Cesium-934 Ci

<LLD

<LLD Note I Note 2 Cesium-137 Ci

<LLD

<LLD Note I Note 2 Barium-140 Ci

<LLD

<LLD Note I Note 2 Lanthanum-140 Ci

<LLD

<LLD Note I Note 2 Cerium-141 Ci

<LLD

<LLD Note I Note 2 Cerium-144a Ci

<LLD

<LLD Note I Note 2 Total for period Ci 1.47 E-05

[

3.24 E-06 J

Note I Note 2 ote I -The particulate and iodine activities released from Waste Gas Decay Tank and Containment Purge batch releases are included in the determinations

,rom the continuous releases. Those detectable particulalte radionuclides in this column are due to the refueling outage and were not released via the stacks Note 2 - No Batch Gaseous Releases were made during the Seconid Quarter Appendix 2: Effluent and Waste Disposal Report (Continued)

Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Ii Nuclides Released Unit

[

Quarter 3 Quarter 4 l

Quarter 3 Quarter 4

1. Fission Gases Xenon-131m Ci

<LLD

<LLD Note 2 Note 2 Xenon-133 Ci 4.09 E-01 6.98 E-01 Note 2 Note 2 Xenon-133m Ci

<LLD

<LLD Note 2 Note 2 Xenon-135 Ci

<LLD

<LLD Note 2 Note 2 Xenon-135m Ci

<LLD

<LLD Note 2 Note 2 Xenon-138 Ci

<LLD

<LLD Note 2 Note 2 Argon-41 Ci

<LLD

<LLD Note 2 Note 2 Krypton-85 Ci

<LLD

<LLD Note 2 Note 2 Krypton-85m Ci

<LLD

<LLD Note 2 Note 2 Krypton-87 Ci

<LLD

<LLD Note 2 Note 2 Krypton-88 Ci

<LLD

<LLD Note 2 Note 2 Total for period Ci 4.09 E-1 J

6.98 E-01 l

Note 2 Note 2

2. lodines Iodine-131 Ci

<LLD

<LLD Note 2 Note 2 Iodine-133 Ci

<LLD

<LLD Note 2 Note 2 lodine-135 Ci

<LLD

<LLD Note 2 Note 2 Total for period Ci l

<LLD

<LLD l

Note 2 Note 2

3. Particulates Chromium-51 Ci

<LLD

<LLD Note 2 Note 2 Manganese-54 Ci

<LLD

<LLD Note 2 Note 2 Cobalt-58 Ci

<LLD

<LLD Note 2 Note 2 Iron-59 Ci

<LLD

<LLD Note 2 Note 2 Cobalt-60 Ci 3.29 E-05

<LLD Note 2 Note 2 Zinc-65 Ci

<LLD

<LLD Note 2 Note 2 Strontium-89 Ci

<LLD l

<LLD Note 2 Note 2 Strontium-90 Ci

<LLD

<LLD Note 2 Note 2 Niobium-95 Ci

<LLD

<LLD Note 2 Note 2 Zirconium-95 Ci

<LLD l

<LLD Note 2 Note 2 Molybdenum-99 Ci

<LLD

<LLD Note 2 Note 2 Cesium-134 Ci

<LLD

<LLD Note 2 Note 2 Cesium-137 Ci

<LLD

<LLD Note 2 Note 2 Barium-140 Ci

<LLD

<LLD Note 2 Note 2 Lanthanum-140 Ci

<LLD

<LLD Note 2 Note 2 Cerium-141 Ci

<LLD

<LLD Note 2 Note 2 Cerium-144 Ci

<LLD

<LLD Note 2 Note 2 Total for period

[

Ci 3.29 E-05

<LLD l

Note 2 Note 2 ote I -The particulate and iodine activities released from Waste (has Decay Tank and Containment Purge hatch releases are included in the determinations

-_Om the continuous releases. Those detectable particulate radionuclides in this column are due to the retieling outage and were not released via the stacks Note 2 - No Batch Gaseous Releases were made during the Third or Fourth Quarter 17 -

Appendix 2 (Continued): Effluent and Waste Disposal Report : Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UIt urter Q2 Error % -

Unit I

Qua I

Quarter Est. Total 1

2 ro A.

Fission and Activation products I

Total release (not including tritium, gases, Ci 1.92 E-02 6.32 E-03 3.28 E+01 I

~~~alpha)__

2 Averge diluted concentration during PCi/mi 2.72 E-09 8.86 E-10 peZY 3

Percent of applicable limit 6.40 E-02 1.90 E-02 B.

Tritium I

Total release Ci 3.37 E+01 1.16 E+01 5.43 E+O1 l

2 Average diluted concentration during pCi/ml 4.79 E-06 1.63 E-06 periocf 3

Percent of applicable limit 4.80 E-0I 1.60 E-01 C.

Dissolved and entrained gases I

Total release Ci

<LLD

<LLD 3.28 E+01j 2

Average diluted concentration during pCi/ml

<LLD

<LLD 3

Percent of applicable limit 0.00 E+00 0.00 E+00 D.

Gross alpha radioactivity l

I Total release Ci 4.12 E+04

<LLD 3.28 E+01 E.

Volume of waste released I

Continuous Releases liters 2.-10 E+07 l

1.47 E+07 2.00 E+01 2

Batch Releases l

liters 1.18 E+06 8.33 E+05 2.00 E+01 l

F.

Volume of dilution water I

Continuous Releases liters 7.04 E+09 7.13 E+09 2.00 E+0l B 2

Batch Releases liters 7.04 E+09 7.13 E+09 2.00 E+0I

- IS -

Appendix 2 (Continued): Effluent and Waste Disposal Report : Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Toa A.

Fission and Activation products I

Total release (not including tritium, gases, Ci 1.13 E-02 3.94 E-03 3.28 E+0 I I

~alpha)I 2

Average diluted concentration during pCi/ml 1.74 E-09 5.56 E-10 I

~~~period__

3 Percent of applicable limit 3.77 E-02 2.78 E-02 B.

Tritium I

Total release Ci 1.31 E+01 1.22 E+01 5.43 E+01 2

Average diluted concentration during pCi/ml 2.01 E-06 1.73 E-06 peri 3

Percent of applicable limit 2.00 E-01 1.70 E-01 C.

Dissolved and entrained gases 1

Total release Ci

<LLD

<LLD 3.28 E+j1 2

Averadge diluted concentration during pCi/ml

<LLD

<LLD I

~~~perio c[_

l 3

Percent of applicable limit j

0.00 E+00 0.00 E+00 D.

Gross alpha radioactivity I

Total release Ci

<LLD

<LLD 3.28 E+01 E.

Volume of waste released I

Continuous Releases liters 2.13 E+07 1.94 E+07 2.00 E+01 2

Batch Releases l

liters 5.97 E+05 l

3.62 E+05 2.00 E+01 F.

Volume of dilution water I I Continuous Releases liters 6.52 E+09 J 7.08 E+09 2.00 E+01 2

Batch Releases liters 6.52 E+09 7.08 E+09 2.00 E+01 Appendix 2 (Continued): Effluent and Waste Disposal Report : Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released l

Unit l

Quarter I J

Quarter 2 j

Quarter I Quarter 2 Sodium-24 Ci

<LLD

<LLD 9.24 E-06

<LLD Chromium-51 Ci

<LLD

<LLD 3.55 E-04

<LLD Manganese-54 Ci

<LLD

<LLD 6.95 E-06

<LLD Iron-55 Ci

<LLD

<LLD 7.40 E-04 1.06 E-03 Cobalt-57 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD

<LLD 4.70 E-03 5.93 E-04 Iron-59 Ci

<LLD

<LLD Cobalt-60 Ci

<LLD

<LLD 2.14 E-03 2.67 E-03 Nickel-63 Ci

<LLD

<LLD 1.93 E-03 1.03 E-03 Strontium-89 Ci

<LLD

<LLD Strontium-90 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Zirconium-97 Ci

<LLD

<LLD Niobium-95 Ci

<LLD

<LLD Niobium-97 Ci

<LLD

<LLD Technicium-99m Ci

<LLD

<LLD Ruthenium-106 Ci

<LLD

<LLD Antimony-124 Ci

<LLD

<LLD 7.37 E-05 1.15 E-05 Antimony-125 Ci

<LLD

<LLD 9.19 E-03 9.52 E-04 Antimony-126 Ci

<LLD

<LLD Tellurium-132 Ci

<LLD

<LLD Iodine-131 Ci

<LLD

<LLD Iodine-132 Ci

<LLD

<LLD Iodine-133 Ci

<LLD

<LLD 7.49 E-06

<LLD Cesium-134 Ci

<LLD

<LLD Cesium-137 Ci

<LLD

<LLD 7.46 E-06

<LLD Barium-140 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Cerium-141 Ci

<LLD

<LLD Cerium-144 Ci

<LLD

<LLD TOTAL Ci

<LLD

<LLD 1.92 E-02 6-32 E-03 Xenon-133 Ci J

<LLD

<LLD Xenon-133m Ci J

<LLD

<LLD Xenon-1335 Ci l

<LLD

<LLD TOTAL Ci J

<LLD

<LLD Tritium Ci 1.01 E-01 1.62 E-01 3.37 E+01 J 1.16 E+01 Appendix 2 (Continued): Effluent and Waste Disposal Report : Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released 1 Unit Quarter 3 l

Quarter 4 j

Quarter 3 l

Quarter 4 Sodium-24 Ci

<LLD

<LLD Chromium-51 Ci

<LLD

<LLD Manganese-54 Ci

<LLD

<LLD 1.60 E-05 Iron-55 Ci

<LLD

<LLD 3.97 E-04 1.56 E-04 Cobalt-57 Ci

<LLD

<LLD Cobalt-58 Ci

<LLD

<LLD 4.95 E-05 1.06 E-04 Iron-59 Ci

<LLD

<LLD Cobalt-60 Ci

<LLD

<LLD 4.74 E-03 1.54 E-03 Nickel-63 Ci

<LLD

<LLD 5.13 E-03 1.47 E-03 Strontium-89 Ci

<LLD

<LLD Strontium-90 Ci

<LLD

<LLD Zirconium-95 Ci

<LLD

<LLD Zirconium-97 Ci

<LLD

<LLD Niobium-95 Ci

<LLD

<LLD 8.94 E-06 Niobium-97 Ci

<LLD

<LLD Technicium-99m Ci

<LLD

<LLD Ruthenium-106 Ci

<LLD

<LLD Antimony-124 Ci

<LLD

<LLD Antimony-125 Ci

<LLD

<LLD 9.94 E-04 6.09 E-04 Antimony-126 Ci

<LLD

<LLD Tellurium-132 Ci

<LLD

<LLD Iodine-131 Ci

<LLD

<LLD Iodine-132 Ci

<LLD

<LLD Iodine-133 Ci

<LLD

<LLD Cesium-134 Ci

<LLD

<LLD Cesium-137 Ci

<LLD

<LLD 2.99 E-05 Barium-140 Ci

<LLD

<LLD Lanthanum-140 Ci

<LLD

<LLD Cerium-141 Ci

<LLD

<LLD Cerium-144 Ci

<LLD

<LLD TOTAL Ci

<LLD

<LLD 1.13 E-02 3.94 E-03 Xenon-133 Ci

<LLD

<LLD Xenon-133m Ci

<LLD

<LLD Xenon-135 Ci

<LLD

<LLD TOTAL Ci

<LLD

<LLD Tritium Ci 2.51 E-0 I 1.43 E-01 l

1.31 E+01 l

1.22 E+01 Appendix 2: Effluent and Waste Disposal Report (Continued) Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS NOTE: Table 3 includes Harris Environmental Energy Center (HEEC) solid radioactive wastes processed and commingled with HNP solid radioactive wastes.

A.

Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)

NOTE: Values reported in Table 3 section A. I.a. refer to radioactive solid waste materials processed and buried during 2002.

1.

Type of Waste

a.

Dry Compressible Waste (DAW), Contaminated Equipment, etc.

Note: Waste processed and buried during 2002.

Number of Shipments 60 Activity Shipped 5.47E+00 Curies Estimated Total Error 96.05%

Quantity Shipped 2.42E+01 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

b.

Irradiated Components, Control Rods, etc.

No waste of this type was shipped during this Report Period.

c.

Other (Describe)

No waste of this type was shipped during this Report Period.

22 -

Appendix 2: Effluent and Waste Disposal Report (Continued) Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

2.

Estimate of Major Nuclide Composition (by type of Waste)

a.

Dry Compressible Waste (DAW), Contaminated Equipment. etc.

Note: Waste processed and buried during 2002.

ercent otal Activity Nuclide Composition Curies Am-241 1.84E-04 1.0 IE-03

-14 3.01E-03 1.65E-0 e-144 1.OIE-03 5.52E-03 m-242 4.66E-06 2.73E-05 m-243 2.26E-05 1.24E-04 o-57 2.37E-04 1.30E-03 o-58 9.79E-03 5.35E-02

_o-60 3.88E-0I 2.12E+OC

-s-134 1.77E-04 9.69E-04 Is-137 1.64E-03 8.98E-03 le-55 4.5 IE-OI 2.46E+OC 4-3 9.53E-03 5.21E-02 1-129 O.OOE+O(

O.OOE+OC n-54 1.68E-02 9.19E-02 b-95 1.62E-02 8.87E-0 Nil-63 8.40E-02 4.60E-0 I Pu-238 1.18E-05 6.48E-05 PU-239 4.64E-01 2.54E-05 Pu-241

1. IIE-03 6.06E-03 Sb-125 6.17E-03 3.37E-02 n-113 2.40E-04 1.31E-03 r-90 1.29E-04 7.03E-c-99 O.OOE+00 O.OOE+

r-95 1.14E-02 6.22E-O, otal l

1.OOE+O 5.47E+OO

3.

Solid Waste Disposal Number of Shipments

60 Mode of Transportation Truck Destination Envirocare Facility, Utah Destination Barnwell Facility, South Carolina Two shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell. Fifty-eight shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Envirocare. One shipment from GTS/Duratek to Barnwell contained both waste class A and waste class C.

23 -

Appendix 2: Effluent and Waste Disposal Report (Continued) : Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B.

Solid Waste Shipped for Burial or Disposal (WASTE CLASS B)

NOTE: Values reported in Table 3 section B. L.a. refer to radioactive solid waste materials processed and buried during 2002.

1.

Type of Waste

a.

Dry Compressible Waste (DAW), Contaminated Equipment, etc.

Note: Waste processed and buried during 2002.

Number of Shipments 3

Activity Shipped 6.44E+00 Curies Estimated Total Error 96.05%

Quantity Shipped 6.30E-01 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

b.

Irradiated Components, Control Rods, etc.

No waste of this type was shipped during this Report Period.

c.

Other (Describe)

No waste of this type was shipped during this Report Period.

24 -

Appendix 2: Effluent and Waste Disposal Report (Continued) Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

2.

Estimate of Major Nuclide Composition (by type of Waste)

a.

Dry Compressible Waste (DAW), Contaminated Equipment, etc.

Note: Waste processed and buried during 2002.

Percent Total Activit Nuclide Composition Curies C-14 4.94E-03 3.18E-02 Ce-144 2.67E-03 1.72E-0 m-242 7.92E-07 5.IOE-06 m-243 1.23E-06 7.90E-0 o-58 9.80E-03 6.3 1E-02 o-60 2.81E-0 I 1.81E+0(

s-134 4.27E-02 2.75E-01 s-137 1.66E-01 1.07E+0(

Fe-55 3.23E-01 2.08E+0(

H-3 1.55E-02 9.97E-02 I-129 3.57E-05 2.30E-0' Mn-54 4.60E-02 2.96E-01 Ni-63 9.86E-02 6.35E-01 Pu-238 9.63E-07 6.20E-0 Pu-239 1.54E-06 9.90E-01 Pu-241 2.80E-04 1.80E-03 b-125 8.88E-03 5.72E-02 r-89 3.12E-05 2.01E-0 r-90 3.90E-04 2.5 IE-03 c-99 1.99E-05' 1.28E-04 otal l

I.00E+00l 6.44E+00

3.

Solid Waste Disposal Number of Shipments

3 Mode of Transportation Truck Destination Barnwell Facility, South Carolina One shipment was made from the Studsvik facility in Oak Ridge, Tennessee to Barnwell.

Two shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell.

25 -

Appendix 2 (Continued): Effluent and Waste Disposal Report : Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C.

Solid Waste Shipped for Burial or Disposal (WASTE CLASS C)

NOTE: Values reported in Table 3 section C. I.a. refer to radioactive solid waste materials processed and buried during 2002.

1.

Type of Waste

a.

Dry Compressible Waste (DAW), Contaminated Equipment, etc.

Note: Waste processed and buried during 2002.

Number of Shipments 2

Activity Shipped 1.66E+02 Curies Estimated Total Error 96.05%

Quantity Shipped 1.02E+00 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

b.

Irradiated Components, Control Rods, etc.

No waste of this type was shipped during this Report Period.

c.

Other (Describe)

No waste of this type was shipped during this Report Period.

26 -

Appendix 2 (Continued): Effluent and Waste Disposal Report : Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

2.

Estimate of Major Nuclide Composition (by type of Waste)

a.

Dry Compressible Waste (DAW), Contaminated Equipment, etc.

Note: Waste processed and buried during 2002.

Percent Total Activit Nuclide Composition Curies Am-241 1.45E-05 2.41E-0

-14 2.32E-04 3.86E-0:

e-144 2.15E-05 3.58E-03 m-242 3.75E-07 6.23E-05 m-243 9.85E-0 1.64E-03 o-57 1.62E-05 2.70E-03 o-58 3.93E-0' 6.53E-02 o-60 4.15E-01 6.89E+01 s-134 2.32E-0' 3.86E-02 ls-137 6.09E-0, 1.O1E+01 e-55 4.47E-02 7.43E+0(

H-3 2.80E-0' 4.65E-02 I-129 6.1OE-0 l.OIE-03 n-54 1.95E-03 3.24E-01 Nb-95 1.29E-0' 2.14E-02 Nil-63 4.75E-01 7.89E+01 Pu-238 8.29E-01 1.37E-03 Pu-239 6.12E-01 1.02E-03 Pu-241 3.21E-04 5.33E-02 Sb-125 4.59E-0' 7.63E-02 n-113 1.87E-05 3.1IE-03 Sr-90 3.85E-0' 6.40E-02 Tc-99 2.56E-0 4.21 E-04 Zr-95 7.01E-0' 1.17E-02 Total

[

1.00E+01 1.66E+02

3.

Solid Waste Disposal Number of Shipments 2

Mode of Transportation Truck Destination Barnwell Facility, South Carolina One shipment was made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell. One shipment was made from the Studsvik facility in Oak Ridge, Tennessee to Barnwell. The shipment from GTS/Duratek to Barnwell contained both waste class A and waste class C.

27 -

Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)

ODCM Operational Requirement 6.14.c During 2002, the ODCM was revised two times as Revision 15 and 16. A copy of the ODCM Revision 16 is included as an Attachment 1 to this submittal. Summary descriptions of the changes to the ODCM are provided below.

ODCM REV. 15 CHANGE

SUMMARY

Section Page Description Title Page Revised to Rev. 15 LEP vi, vii, ix Changed revision numbers as appropriate 2.1.1 2-6 Added a NOTE in the definition for the term known as (r). "NOTE:

CRC-001 has a target limit of 2.0 E-04 VCi/ml."

Table 2.1-1 2-19 Changed the Pump Design Capacity for the TL&HS from 35 gpm to l

100 gpm.

Table 2.1-4 2

Corrected the radionuclide half lives from minutes to hours, It to A, 2-23 and corrected e&X1 values.

3.1.2 3-6 Added details for batch gaseous releases (Waste Gas Decay Tanks, Containment Normal Purge, and Containment Preentry Purge) for 3-7 setpoint determinations.

Table 3.2-2 3-19 Corrected the Nearest Special Locations for the Shearon Harris Nuclear Power Plant based on the 2001 Land Use Census.

5.0 5-1 Redefined the acceptance criteria for the Environmental interlaboratory comparison program.

6.0 6-1 Clarified the details required by ODCM Operational Requirement 3.11.4 to perform a dose assessment to demonstrate compliance with 40 CFR 190.

6-1 6-1 Clarified the details required by ODCM Operational Requirement F.2 to perform a dose assessment to demonstrate compliance with 40 CFR 190.

6-2 6-2 Deleted section 6-2 which matches with ODCM Operational Requirement F.2.

3.12.3 D-40 Changed "an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1" to "an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1" and added "The laboratory used for the Interlaboratory Comparison Program is to participate in the National Institute of Standard and Technology (NIST) program."

28 -

Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)

ODCM Operational Requirement 6.14.c ODCM REV. 16 CHANGE

SUMMARY

Section Page Description Title Page Revised to Rev. 16 Table of Contents i

Changed to "ODCM REV. 16 CHANGE

SUMMARY

LEP vi, vii, viii Changed revision numbers as appropriate ODCM REV. 16 ix Changed to reflect Rev. 16 revisions CHANGE

SUMMARY

Table 3.2-2 3-19 Corrected the Nearest Special Locations for the Shearon Harris Nuclear Power Plant based on the 2002 Land Use Census.

Table 4.1 4-3 Corrected TLD #3 distance to 1.9 mi from site.

Table 4.1 4-4 Changed name of business for TLD #29 location to Dynea USA, Inc.

Table 4.1 4-5 Added TLD #67 at HE&EC.

29 -

Appendix 4: Changes to the Environmental Monitoring Program : Environmental Monitoring Program Offsite Dose Calculation Manual Operational Requirement 3.12.1.c TLD #67 was added to the environmental monitoring program with Revision 16 of the ODCM. TLD #67 is located in the ENE sector along with TLD #3. The decision was made to retain both TLD's in the environmental monitoring program since TLD #3 is closest to HE&EC and would be the best indicator of dose received by the personnel at HE&EC. TLD #3 is close to the border of the sector; therefore, TLD #67 was added closer to the center of the sector. These changes were incorporated into Revision 16 of the ODCM which is included as. : Land Use Census Offsite Dose Calculation Manual Operational Requirements 3.12.2.a and 3.12.2.b The land-use census that was completed in September 2002 resulted in no changes to the Environmental Monitoring.

Program. The 2002 Land Use Census found meat animals and a garden in the E Sector at 1.7 miles where no meat animals or gardens were found in that sector in 2001. Additionally, the garden in the W sector was found at 3.0 miles in 2002 versus 3.1 miles in 2001.

30 -

Appendix 5 : Additional Operational Requirements : Inoperability of Liquid Effluent Monitors ODCM Operational Requirement 3.3.3. 10.b Radioactivity Liquid Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2002 by the Condition Reporting Process pursuant to ODCM Operational Requirement 3.3.3.10.b. None were inoperable for greater than 30 continuous days during the reporting period. : Inoperability of Gaseous Effluent Monitors ODCM Operational Requirement 3.3.3.11.b Radioactivity Gaseous Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2002 by the Condition Reporting Process pursuant to ODCM Operational Requirement 3.3.3.11.b. None were inoperable for greater than 30 continuous days during the reporting period. : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4.

No unprotected outdoor tank exceeded the Technical Specification limit of 10 Curies, excluding tritium or dissolved noble gases during this report period. : Gas Storage Tanks Exceeding Limits PLP-1 14, Attachment 5, Operational Requirement 1.1 No gas storage tank exceeded the PLP-I 14, Attachment 5 Operational Requirement limit of 1.05 E+05 Curies during this report period.

31 -

Appendix 6: Major Modifications to Radwaste System ODCM Operational Requirement F.3 No major modifications were made to the Radwaste System during this report period.

32 -

Appendix 7: Meteorological Data ODCM Operational Requirement F.2 As allowed by the Footnote to Operational Requirement F.2, the annual summary of meteorological data will be retained electronically on file. This data will be provided to the NRC upon request.

33 -

Appendix 8: Assessment of Radiation Doses ODCM Operational Requirement F.2 An Assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is in pursuant to the Operational Requirement F.2. Since I0CFR50, Appendix I is more restrictive than 40CRF190 for a single unit site, the assessment for 40CFR190 is performed when any of the IOCFR50, Appendix I limits are exceeded by a factor of 2 using LADTAP, XOQDOQ, and GASPAR II (NRC computer codes). The ODCM software is more conservative and is used for annual effluent dose assessment for demonstration of compliance with I0CFR50, Appendix I and 40CFR 190.

Gaseous The dose from the gaseous pathway is based on the highest calculated twelve-year annual average relative concentration (X/Q) and deposition factor ((D/Q) for particulates) at the most restrictive location at the site boundary.

Y

,'i QST Quarter 2 nd Quarter 3rd Quarter 4Q h Quarter Annual Total Noble Gas Gamma Dose 3.07 E-05

<LLD 2.79 E-05 4.76 E-05 1.06 E-04 (mrad)

IOCFR50 Appendix I Limit (mrad) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+01 Noble Gas Beta Dose 9.67 E-05

<LLD 8.30 E-05 1.42 E-04 3.21 E-04 (mrad)

IOCFR50 Appendix I Limit (mrad) 1.00 E+01 1.00 E+01 1.00 E+01 1.00 E+01 2.00 E+01 Critical Organ Dose for 1-131, I-1.77 E-02 3.03 E-02 4.32 E-02 5.79 E-02 1.49 E-01 133,and Particulates With Tl/2

> 8 days (mrem) 10CFR50 Appendix I Limit (mrad) 7.5 E+00 7.5 E+00 7.5 E+00 7.5 E+00 1.50 E+0t 34 -

Appendix 8: Assessment of Radiation Doses ODCM Operational Requirement F.2 Liquid The dose from the liquid pathway is based on fish consumption from Harris Lake (parts of the lake are within the site boundary) plus drinking water from Lillington.

SrTr Quarter 2nd Quarter 3rd Quarter 4 th Quarter Annual Total Total Body Dose (mrem) 9.59 E-04 2.85 E-04 5.65 E-04 4.17 E-04 2.23 E-03 IOCFR50 Appendix I Limit (mrem) 1.50 E+00 1.50 E+00 1.50 E+00 1.50 E+00 3.00 E+00 Critical Organ Dose (mrem) 1.41 E-03 6.02 E-04 1.14 E-03 5.51 E-04 3.71 E-03 IOCFR50 Appendix I Limit (mrem) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+OI 40CFR190 Uranium Fuel Cycle Dose Calculation Results Maximum Total Body Dose = 1.5 lE-0I mrem Liquid and Gas Effluent Contribution to Maximum Total Body Dose Liquid Effluent Dose = 2.23 E-03 mrem Gas Effluent Dose = 1.49 E-01 mrem 40CFR 190 Limit = 25 mrem Maximum Organ Dose = 1.53 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 3.71 E-03 mrem Gas Effluent Dose = 1.49 E-01 mrem 40CFR190 Limit = 75 mrem 35 -

Appendix 9: Corrections to Previous Annual Reports 2001 Annual Radioactive Effluent Release Report The following corrections to the 2001 Annual Radioactive Effluent Release Report are submitted:

On page 1/4 under Liquid Batch Releases, the Average Stream Flow Values for Jan-June 2001 and July-Dec 2001 were reported in error as 2.28 E+04 gpm and 2.17 E+04 gpm, respectively. The correct values were as follows:

Jan-June 2001 1.52 E+04 gpm July-Dec 2001 1.42 E+04 gpm On page 2/3, under Fission and Activation Gases, Percent of ODCM Operational Requirement Limit was incorrectly reported as 9.09 E-03%. The correct value is 9.90 E-03%.

On page 5/1, under Enclosure 3: Unprotected Outdoor Tanks Exceeding Limits, the 2001 Report incorrectly references ODCM Operational Requirement 3.11.1.4. Action a. The correct reference is Technical Specification 3.11.1.4.

On page 5/1, under Enclosure 4: Gas Storage Tanks Exceeding Limits, the 2001 Report incorrectly references ODCM Operational Requirement 3.11.2.6. Action a. The correct reference is PLP-114,, Operational Requirement 1.1. : Current Revision of ODCM Offsite Dose Calculation Manual, Revision 16 37 -

ML031120599

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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