HNP-06-046, Annual Radioactive Effluent Release Report

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Annual Radioactive Effluent Release Report
ML061150347
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 04/17/2006
From: Corlett D
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
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HNP-06-046
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Progress Energy APR 1 7 2006 SERIAL: HNP-06-046 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, Carolina Power

& Light Company, doing business as Progress Energy Carolinas, Inc., is providing the enclosed Annual Radioactive Effluent Release Report for 2005.

A correction to the Annual Radioactive Effluent Release Report for 2004 to include a discussion of radiological doses due to direct radiation from the Harris Nuclear Plant is included as Appendix 9 of the enclosed report.

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

Sincerely, 7-' f D. H.efett' Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/rnigw Enclosure c: Mr. R. A. Musser (NRC Senior Resident Inspector, HNP)

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

Dr. W. D. Travers (NRC Regional Administrator, Region II)

Progress Energy Carolinas, Inc.

Ha ris Nuclear Plant P.1) Box 165 NeN Hill, NC 27562 I ce (4

I-Carolina Power & Light Company, Doing Business as Progress Energy Carolinas, Inc.

Shearon Harris Nuclear Power Plant Facility Operating License No. NPF-063 Docket No. 50-400 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2005 to December 31, 2005

Table of Contents Section Pace No.

Introduction 3 Discussion 3 Appendix 1. Supplemental Information 7 Appendix 2. Effluent and Waste Disposal Report

1. Lower Limits of Detection (LLDs) 12
2. Effluents Released 14
3. Solid Waste Disposal 23 Appendix 3. Changes to Offsite Dose Calculation Manual (ODCM) 31 Appendix 4. Changes to the Environmental Monitoring Program
1. Environmental Monitoring Program 32
2. Land Use Census 32 Appendix 5. Additional Operational Requirements
1. Inoperability of Liquid Effluent Monitors 33
2. Inoperability of Gaseous Effluent Monitors 33
3. Unprotected Outdoor Tanks Exceeding Limits 33
4. Gas Storage Tanks Exceeding Limits 33 Appendix 6. Major Modifications to Radwaste System 34 Appendix 7. Meteorological Data 35 Appendix 8. Assessment of Radiation Doses 36 Appendix 9. Correction to 2004 Annual Radiological Effluent Release Report 38 Assessment of Radiation Doses

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), Appendix F Seclion F.2, and 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, 2005 to December 31, 2005. During this period, the plant operated in Cycle 13 for the entire year. There was no Refueling Outage scheduled for 2005.

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 tte 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. Iodines 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-plaat 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 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 tmnk is automatically suspended. Additionally, batch releases are sampled and analyzed in the laboratory pri )r 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.

I

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 I, 2005 through December 31, 2005. 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, 2005 through December 31,2005, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents: Limit 5.73 E-03 mrem, Total Body 3.0 E+00 mrem 6.23 E-03 mrem, Max Organ (GI-LLI) 1.0 E+01 mrem Gaseous Effluents: Limit Noble Gases 1.53 E-04 mrad, Beta 2.0 E+01 mrad 1.28 E-04 mrad, Gamma 1.0 E+01 mrad Tritium, Radioiodine 131, 133, and Particulates with greater than an 8 Day Half Life:

1.93 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 Instantaneous Release Rate Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr I OCFR20 Limits Annual Average Concentrations as specified in IOCFR20, Appendix B, Table 2, Column 1. This is based on 100 mrem/yr.

10CFR5O, 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 mnrem/yr 10CFR20 Limits Annual Average Concentrations as specified in I OCFR20, Appendix B, Table 2, Column

1. This is based on 50 mrem/yr.

IOCFR5O, 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 I OCFR2O, 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.OOE-04 iCi/ml total activity.

I OCFR20 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 ba;ed on 50 mrem/yr.

IOCFR5O, 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)

II. Measurements and Approximations of Total Radioactivity A. Continuous Gaseous Releases I. Fission and activation gases The total activity released is determined from the net activity of gaseous monitors tirnes 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 I. 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. Iodines 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.

('. 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 ir.

each batch (identified using gamma spectroscopy) times the volume of the batch.

Appendix 1: Supplemental Information (Continued)

II. Measurements and Approximations of Total Radioactivity C'. Liquid Releases

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.

Appendix 1: Supplemental Information (Continued)

III. Batch Releases (2005)

A.. Liquid Batch Releases Jan - June 2005 July - Dec 2005 Number of batch releases 1.6 E+01 1.80 E+01 Total time period for batch releases 1.19 E+04 minutes 1.21 E+04 minutes Maximum time of a batch release 8.67 E+02 minutes 8.98 E+02 minutes Average time for a batch release 7.44 E+02 minutes 6.74 E+02 minutes Minimum Time for a batch release 6.92 E+02 minutes 3.30 E+02 minutes Ae e stream flow during periods of release 3.38 E+03 cf/s 1.22 E+03 cf/s B. Gaseous Batch Releases Jan - June 2005 J July - Dec 2005 ]

Number of batch releases 0.00 E+00 2.00 E+00 Total time period for batch releases 0.00 E+00 minutes 2.04 E+03 minutes Maximum time of a batch release 0.00 E+00 minutes 1.62 E+03 minutes Average time for a batch release 0.00 E+00 minutes 1.02 E+03 minutes Minimum Time for a batch release 0.00 E+00 minutes 4.19 E+02 minutes C. Abnormal Releases

a. Liquid There were no abnormal liquid releases in 2005.
b. Gaseous Eight unplanned gaseous releases occurred during 2005. The first seven of these weie from identified leakage from the Reactor Coolant System (RCS) past I CS-752 valve to the Refueling Water storage Tank (RWST). These permits were performed due to the venting of the tank during this time. The RCS stripped gas concentration was used for effluent accountability on these releases. The total of these seven releases was 5.867 E-03 curies with the offsite dose being well below the administrative limits for all vital organs.

The other unplanned gaseous release was from the Waste Gas System. The Radwastc Control Room operator noticed a sudden drop in pressure in the J Waste Gas DecayTank.

A leak was discovered & subsequently repaired. A permit was performed bracketing the

Appendix 1: Supplemental Information (Continued) time that the leak started through the time that the leak was discovered & isolated. The total curies released from this Waste Gas Decay Tank permit was 5.20 E-02 with the offsite dose being well below the administrative limits for all vital organs.

-I I-

Appendix 2: Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLDs)

LLDs for Gaseous Effluents Nuclide ILCi/cc Gross Alpha 5.64 E-15 H-3 3.13 E-09 Ar41 1.27 E-08 Kr-85 2.97 E-06 Kr-85m 6.76 E-09 Kr-87 4.34 E-08 Kr-88 2.65 E-08 Xe-131m 1.63 E-07 Xe-133 4.02 E-09 Xe-133m 5.92 E-08 Xe-135 9.40 E-09 Xe-135m 1.30 E-08 Xe-138 5.80 E-07 I-131 4.84 E-13 I-133 8.20 E-13 1-135 6.34 E-12 Cr-51 2.54 E-12 Mn-54 7.45 E-13 Co-58 4.81 E-13 Fe-59 1.19 E-12 Co-60 2.96 E-13 Zn-65 1.32 E-12 Sr-89 3.92 E-15 Sr-90 1.74 E-15 Nb-95 4.51 E-13 Zr-95 2.95 E-13 Mo-99 1.29 E-12 Cs-134 2.01 E-13 Cs-137 7.31 E-13 Ba-140 4.49 E-13 La-140 3.97 E-13 Ce-141 3.05 E-13 Ce-144 1.24 E-12

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 1: LOWER LIMITS OF DETECTION (LLDs)

2. LLDs for Liquid Effluents Nuclide UCi/mi Gross Alpha 6.30 E-08 H-3 1.97 E-06 Na-24 2.67 E-08 Cr-51 1.89 E-07 Mn-54 4.41 E-08 Fe-55 7.46 E-08 Co-57 1.16 E-08 Co-58 1.59 E-08 Fe-59 1.27 E-07 Co-60 2.48 E-08 Ni-63 2.09 E-07 Zn-65 4.16 E-08 Sr-89 3.73 E-08 Sr-90 1.26 E-08 Nb-95 5.15 E-08 Zr-95 2.68 E-08 Mo-99 1.15 E-07 Tc-99m 2.75 E-08 Ru-106 3.41 E-07 Sb-124 6.24 E-08 Sb-125 9.96 E-08 Sb-126 2.69 E-08 I-131 3.57 E-08 1-133 3.01 E-08 Te-132 1.76 E-08 Xe-133 1.37 E-08 Xe-133m 2.32 E-07 Xe-135 2.99 E-08 Cs-134 1.82 E-08 Cs-137 1.53 E-08 Ba-140 1.22 E-07 La-140 3.10 E-08 Ce-141 3.95 E-08 Ce-144 1.27 E-07

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total l 1 2 l Error %

A. Fission and activation gases

1. Tota.l release Ci 6.53 E-03 9.83 E-02 52 +oiill
2. Average release rate for period ,gCi/sec 8.40 E-04 1.25 E-02
3. Percent of ODCM Operational Requirement limit  % 1.33 E-05 3.19 E-04 B. Iodines
1. Total iodine-131 Ci <LLD <LLD 3 +oi l
2. Average release rate for period gCi/sec <LLD <LLD
3. Percent of ODCM Operational Requirement limit* 7.28 E-01 5.09 E-01 C. Particulates
1. Particulates with half-lives >8 days Ci <LLD 2.10 E-05 3 +O7Jl
2. Average release rate for period giCi/sec <LLD 2.67 E-06
3. Percent of ODCM Operational Requirement limit*  % 7.28 E-01 5.09 E-01
4. Gro:;s alpha radioactivity Ci <LLD <LLD D. Tritium 1.Total release l Ci J 4.05 E+01 2.82 E+01 5.22 E+01
2. Average release rate for period pCi/sec 5.20 E+00 3.59 E+00
3. Percent of ODCM Operational Requirement limit* J  % l 7.28 E-01 j 5.09 E-01
  • The Percent of ODCM Operational Requirement limits applies to Iodines, 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)

Enclosure 2: Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit l

Quarter 3

Quarter 4

1l Est. Total Error %

A. Fission and activation gases

1. Total release Ci 2.07 E-01 2.49 E-01 5 +j1
2. Average release rate for period pCi/sec 2.60 E-02 3.14 E-02
3. Percent of ODCM Operational Requirement limit  % 4.38 E-04 7.55 E-04 B. Iodines
1. Total iodine-131 - Ci <LLD <LLD 34+01Il
2. Average release rate for period ptCi/sec <LLD <LLD
3. Percent of ODCM Operational Requirement limit*  % 5.45 E-01 7.91 E-01 C. Particulates l1. Part iculates with half-lives >8 days Ci <LLD 1.16 E-05 3 +oi l
2. Average release rate for period [tCi/sec <LLD 1.46 E-06
3. Percent of ODCM Operational Requirement limit*  % 5.45 E-01 7.91 E-01
4. Gross alpha radioactivity Ci <LLD <LLD D. Tritium
1. Total release J Ci J 3.03 E+01 J 4.39 E+01 l5.22 E+0
2. Average release rate for period iCi/sec 3.81 E+00 5.53 E+00
3. Percent of ODCM Operational Requirement limit*  % J 5.45 E-01 7.91 E-01
  • The Percent of ODCM Operational Requirement limit applies to Iodines, 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)

Enclosure 2: Effluents Released Table lB: GASEOUS EFFLUENTS - ELEVATED RELEASES All releases at Shearon Harris Nuclear Power Plant are considered ground releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2 : Effluents Released Table CI GASEOUS EFFLUENTS - GROUND LEVEL RELEASES iil

-.. 11 KA, vullulluuua lvluuv 1~:

I Batch Mode 11 II ecidesReleased Unit ] Quarter I Quarter 2 Quarter I Quarter2

1. Fission Gases Xenon-131mr Ci <LLD <LLD <LLD <LLD Xenon-133 Ci 6.53 E-03 5.57 E-02 <LLD 5.39 E-05 Xenon-133rm Ci <LLD 3.87 E-03 <LLD <LLD Xenon-135 Ci <LLD 2.88 E-02 <LLD 1.12 E-04 Xenon-135m Ci <LLD <LLD <LLD 8.87 E-06 Xenon-138 Ci <LLD <LLD <LLD 1.93 E-04 Argon41 Ci <LLD 5.88 E-03 <LLD 1.71 E-04 Krypton-85 Ci <LLD <LLD <LLD <LLD Krypton-85r.i Ci <LLD 1.67 E-03 <LLD 1.62 E-05 Krypton-87 Ci <LLD <LLD <LLD 4.91 E-05 Krypton-88 Ci <LLD 1.66 E-03 <LLD 4.62 E-05 Total forperiod Ci 6.53 E-03 9.77 E-02 T <LLD 6.50 E-04
2. lodines Iodine-131 Ci <LLD <LLD Note I Note I Iodine-133 Ci <LLD <LLD Note I Note I Iodine-135 Ci <LLD <LLD Note I Note I Total forperiod Ci <LLD <LLD Note I 'Note I
3. Particulates Chromium-f I Ci <LLD <LLD Note I Note I Manganese-54 Ci <LLD <LLD Note I Note I Cobalt-58 Ci <LLD <LLD Note I Note I Iron-59 Ci <LLD <LLD Note I Note I Cobalt-oO Ci <LLD 2.10 E-05 Note I Note I Zinc-65 Ci <LLD <LLD Note I Note I Strontium-89 Ci <LLD <LLD Note I Note I Strontium-9() Ci <LLD <LLD Note I -Note I Niobium-95 Ci <LLD <LLD Note I Note I Zirconium-95 Ci <LLD <LLD Note I Note I Molybdenuri-99 Ci <LLD <LLD Note I Note I Cesium-134 Ci <LLD <LLD Note I Note I Cesium-137 Ci <LLD <LLD Note I Note I Barium-140 Ci <LLD <LLD Note I Note I Lanthanum-140 Ci <LLD <LLD Note I Note I Cerium-141 Ci <LLD <LLD Note I Note I Cerium-144 Ci <LLD <LLD Note I Note I Totalforpeiod Ci l <LLD J 2.10E-05 l Note I Note I Note I -The particulate and iodine activities released trom Waste Gas Decay I ank and Containment rurge batch releases are ,ncluded in the ueterrnna'ions from the continuous releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2 : Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES - - - - - -- - -

"i, . 11 Continuous Mode Batch Mode 1I l Nuclies ased Unit Quarter 3 Quarter 4 1 Quarter 3 Qurter 4

1. Fission Gases Xenon-131m Ci <LLD <LLD <LLD <lLD Xenon-133 Ci 2.03 E-01 1.35 E-01 2.77 E-04 5.92 E-02 Xenon-133m Ci <LLD <LLD <LLD 1.32 E-03 Xenon-135 Ci <LLD <LLD 4.34 E-04 2.1:; E-02 Xenon-135m Ci <LLD <LLD 3.87 E-05 4.3()E-04 Xenon-138 Ci <LLD <LLD 5.26 E-04 7.13 E-03 Argon-41 Ci <LLD <LLD 2.35 E-03 2.04 E-02 Krypton-85 Ci <LLD <LLD <LLD <LLD Kiypton-85rn Ci <LLD <LLD 4.10 E-05 L56iE-03 Krypton-87 Ci <LLD <LLD 1.66 E-04 2.54 E-03 Krypton-88 Ci <LLD <LLD 6.13 E-05 7.2 E-04 Total for period Ci 2.03 E-01 1.35 E-01 3.89 E-03 1.1: E-01
2. lodines l Iodine-131 Ci <LLD <LLD Note I Nite I Iodine-133 Ci <LLD <LLD Note I Nate 1 Iodine-135 Ci <LLD <LLD Note I Note I Total forper.od Ci <LLD <LLD Note I Nate I
3. Particulatms Chromium-51 Ci <LLD <LLD Note I Note I Manganese-'4 Ci <LLD <LLD Note I Note I Cobalt-58 Ci <LLD <LLD Note I Note I Iron-59 Ci <LLD <LLD Note I Note I Cobalt-60 Ci <LLD 1.16 E-05 Note I Note I Zinc-65 Ci <LLD <LLD Note I Note I Strontium-89 Ci <LLD <LLD Note I Note I Strontium-91 Ci <LLD <LLD Note I Note I Niobium-95 Ci <LLD <LLD Note I Note I Zirconium-95 Ci <LLD <LLD Note I Note I Molybdenum-99 Ci <LLD <LLD Note I Note I Cesium-134 Ci <LLD <LLD Note I Note I Cesium-137 Ci <LLD <LLD Note I Note I Barium-140 Ci <LLD <LLD Note I Note I Lanthanum-'140 Ci <LLD <LLD Note I Note I Cerium-141 Ci <LLD <LLD Note I Note I Cerium-144 Ci <LLD <LLD Note I Note I lTotal forperiod l Ci i <LLD 1.16 E-05 [ Note I Note I Note I -The particulate and iodine activities released from Waste Gas Decay Tank and Containment Purge batch releases are included in the determinat ions from the continuous releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES IUnit uarter Q uarter Est. Total I I I 1 2 l Error A. Fission and Activation products I Total release (not including tritium, gases, Ci 7.97 E-03 5.66 E-03 3.28 ]

alpha) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . 0 2 Avera ge diluted concentration during l Ci/ml 1.24 E-09 8.87 E-10 3 Percent of applicable limit  % .403E-02 1.59 E-01 B. Tritium I Total release Ci 7.48 E+01 1.57 E+02 5.431 2 Average diluted concentration during 11Ci/ml 1.16 E-05 2.47 E-05 3 Percent of applicable limit  % 1.16 E+00 2.47 E+00 C. Dissolved and entrained gases I Total release Ci <LLD <LLD 3.28 :3 2 Average diluted concentration during l1Ci/ml <LLD <LLD

. . Pen o d_ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

3 Percent of applicable limit  % 0.00 E+00 0.00 E+00 D. Gross alpha radioactivity 1- Total release l Ci <LLD <LLD 3.28 3 E. Vo'.ume of waste released 1 Continuous ReleasesJ liters 1.14 E+07 1.07 E+07 [ 2.00 E+01 2 Batch Releases j liters 6.87 E+05 l 5.38 E+05 l 2.00 E+01 F. Volume of dilution water 1 Continuous Releases 2 Batch Releases

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2 : Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit l Quarter l Quarter l Erst.oi I1 3 4 Est.ota A. Fission and Activation products 1

2 Total release (not including tritium, gases, alpha)

Average diluted concentration during

_ _

Ci

_

pCi ml

_ _

6.52 E-03

_ _

9.93 E-10

_ _ _ _

7.39 E-03

_ _ _

1.09 E-09

_ _

3.28 1 111 3 Percent of applicable limit 4.19 E-02 6.21 E-02 B. Tritium I Total release Ci 5.25 E+01 4.61 E+01 5.431 2 Average diluted concentration during pCi/ml 7.99 E-06 6.80 E-06 3 Percent of applicable limit  % 0.80 E+00 0.68 E+00 C. Dissolved and entrained gases I Total release Ci <LLD <LLD 3.28 2 Average diluted concentration during piCi/ml <LLD <LLD 3 Percent of applicable limit  % 0.00 E+00 0.00 E+00 D. Gross alpha radioactivity Total release Ci <LLD <LLD 3.28 E. Volume of waste released A

1 Continuous Releases 2 Batch Releases F. Volume of dilution water I Continuous Releases l 2 Batch Releases

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table2B: LIQUID EFFLUENTS Ii, Continuous Mode Batch Mode Nuclides Released l Unit J Quarter 1 Quarter 2 JQuarter I Quarter 2 Sodium-24 Ci <LLD <LLD <LLD <]LD Chromium-51 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD 1.80 E-05 3.17 E-05 Iron-55 Ci <LLD <LLD 1.52 E-04 3.0:1 E-04 Cobalt-57 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD <LLD 2.83 E-03 1.36 E-03 Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LID <LLD 1.07 E-03 1.03 E-03 Nickel-63 Ci <LLD <LLD 9.48 E-04 1.90)E-03 Strontium -89 Ci <LLD <LLD <LLD <'LLD Strontium 90 Ci <LLD <LLD <LLD <LLD Zirconiurrn-95 Ci <LLD <LLD <LLD <LLD Zirconiurri-97 Ci <LLD <LLD <LLD <LLD Niobium-95 Ci <LLD <LLD <LLD <'LLD Niobium-97 Ci <LLD <LLD <LLD <'LLD Technicium-99m Ci <LLD <LLD <LLD <'LLD Rutheniura-106 Ci <LLD <LLD <LLD <LLD Antimony-124 Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD <LLD 2.95 E-03 1.04 E-03 Antimony-126 Ci <LLD <LLD <LLD <LLD Tellurium-132 Ci <LLD <LLD <LLD <:LLD Jodine-131 Ci <LLD <LLD <LLD <LLD Iodine-132 Ci <LLD <LLD <LLD <:LLD Iodine-133 Ci <LLD <LLD <LLD <LLD Cesium-134 Ci <LLD <LLD <LID <LLD Cesium-137 Ci <LLD <LLD <LLD <LLD Barium-I40 Ci <LLD <LLD <LLD <LLD Lanthanumn-140 Ci <LID <LLD <LLD <LLD Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD TOTAL Ci <LLD <LLD 7.97 E-03 5.6'E-03 Xenon-133 Ci <LLD <LLD <LLD <LLD Xenon-133m Ci <LLD <LLD <LLD <LLD Xenon-135 Ci <LLD <LLD <LLD <LLD TOTAL Ci <LLD <LLD <LLD <LLD Tritium l Ci 1.20 E-01 2.10 E-01 7.47 E+01 1.51 E+02

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS A1.

1 Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 Ci <LLD <LLD <LLD <LLD Chromiur -51 Ci <LID <LLD <LLD <LLD Manganes -54 Ci <LLD <LLD <LLD 2.43. E-05 Iron-55 Ci <LLD <LLD 7.19 E-04 1.6'4 E-03 Cobalt-57 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD <LLD 4.92 E-04 2.29 E-04 Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD 2.41 E-03 2.8'; E-03 Nickel-63 Ci <LLD <LLD 2.46 E-03 2.0'; E-03 Strontium-89 Ci <LLD <LLD <LLD <LLD Strontium-90 Ci <LLD <LLD <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD <LLD Zirconium.-97 Ci <LLD <LLD <LLD <LLD Niobium-95 Ci <LLD <LLD <LLD <LLD Niobium-97 Ci <LLD <LLD <LLD <LLD Technicium-99m Ci <LLD <LLD <LLD <LLD Rutheniumn-106 Ci <LLD <LLD <LLD <LLD Antimony-124 Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD <LLD 4.24 E-04 5.85 E-04 Antimony-126 Ci <LLD <LLD <LLD <LLD Tellurium*132 Ci <LLD <LLD <LLD <LLD Iodine-131 Ci <LLD <LLD <LLD <LLD Iodine-132 Ci <LLD <LLD <LLD <:LLD Iodine-133 Ci <LLD <LLD <LLD <.LLD Cesium-134 Ci <LLD <LLD <LLD <LLD Cesium-137 Ci <LLD <LLD 1.72 E -05 1.50 E-05 Barium-140 Ci <LID <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Cerium-141I Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD TOTAL Ci <LLD j <LLD 6.52 E-03 7.39 E-03 Xenon-133 Ci <LLD <LLD <LLD <LLD Xenon-133m Ci <LLD <LLD <LLD <LLD Xenon-135 Ci <LLD <LLD <LLD <LLD lTOTAL Ci l <LLD [ <LLD <LLD l <LLD Tritium [ Ci 2.32 E-01 [ 1.92 E-01 l 5.25 E+01 [ 4.61 E+01

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3 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.

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

NOTE: Values reported in Table 3 section I .A.b. refer to radioactive solid waste materials processed and buried during 2005.

A. Type of Waste

a. Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

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

b. Dry compressible Waste (DAW), Mechanical Filters, Contaminated Equipment, etc.

Number of Shipments 45 Activity Shipped 2.92E+01 Curies Estimated Total Error 96%

Quantity Shipped I .72E+Olm 3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

c. Irradiated Components, Control rods, etc.

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

d. Other Describe)

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

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)

B. Estimate of Major Nuclide Composition (by type of waste)

b. Dry Compressible Waste (DAW), Mechanical Filters, Contaminated Equipment, etc.

Note: Waste processed and buried during 2005.

Percent Total Activity Nuclide Composition Curies Am-241 5.93E-06 1.73E-04

-- 14 3.55E-03 1.04E-01 Ce-144 5.48E-04 1.60E-02 Cm-242 1.78E-06 5.20E-05 Cm-243 2.48E-05 7.25E-04 o-57 1.06E-04 3.09E-03 Co-58 2.90E-02 8.46E-01 Co-60 2.62E-01 7.64E+00 Cr-51 1.14E-02 3.34E-01 Cs-134 3.02E-03 8.83E-02 Cs-137 7.57E-03 2.21E-01 Fe-55 5.43E-01 1.59E+01 Fe-59 3.62E-03 1.06E-01 H-3 6.55E-03 1.91E-01 Mn-54 1.35E-02 3.93E-01 Nb-95 8.78E-03 2.56E-01 Ni-63 9.51 E-02 2.78E+00 Pu-238 1.25E-05 3.64E-04 u-239 3.27E-06 9.54E-05 Pu-241 4.56E-03 1.33E-01 Sb-125 8.14E-04 2.38E-02 Sn-113 1.05E-04 3.08E-03 Sr-90 1.99E-06 5.81 E-05 r-95 6.60E-03 1.93E-01 Iotal J 1.00E+00 2.92E+01 C. Solid Waste Disposal Number of Shipments

  • 45 Mode of Transportation Rail, Truck Destination Barnwell, SC; Envirocare Facility, Utah
  • Three shipments were made from the Studsvik processing facility in Erwin, Tennessee to Barnwell. Two shipments were made from the Studvsik processing facility in Erwin.

Tennessee to Envirocare. Three shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell. Thirty Seven shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Envirocare.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

NOTE: Values reported in Table 3 sections 2.A.a. & 2.A.b refer to radioactive solid waste materials processed and buried during 2005.

A. Type of Waste

a. Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

Note: Waste processed and buried during 2005.

Number of Shipments 3 Activity Shipped 5.10E+01 Curies Estimated Total Error 96.00 %

Quantity Shipped 1.03E+00 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

b. Dry Compressible Waste(DAW), Mechanical Filters, Contaminated Equipment, etc.

Note: Waste processed and buried during 2005.

Number of Shipments 2 Activity Shipped 2.29E+01 Curies Estimated Total Error 96.00 %

Quantity Shipped 3.75E-01 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

c. Irradiated Components, Control rods No waste of this type was shipped during this Report Period.
d. Other (Describe)

No waste of this type was shipped during this period

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

B. Estimate of Major Nuclide Composition (by type of Waste)

a. Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

Note: Waste processed and buried during 2005.

Percent Total Activi Nuclide Composition Curies Am-241 1.60E-05 8.17E-04 C-14 3.97E-04 2.03E-02l Ce-144 1.38E-03 7.05E-02 Cm-243 8.24e-06 4.20E-04 Co-57 2.02E-03 1.03E-01 Co-58 7.87E-02 4.01E+00 Co-60 2.19E-01 1.12E+01 Cs-134 7.73E-04 3.94E-02 Cs-137 6.76E-02 3.45E+00 Fe-55 1.30E-01 6.64E+00 H-3 6.05E-04 3.09E-02 Mn-54 3.98E-02 2.03E+00 Ni-63 4.49E-01 2.29E+01 Pu-238 3.55E-06 1.81E-04 Pu-239 2.48E-06 1.26E-04 Pu-241 1.12E-04 5.73E-03 Sb-125 1.02E-02 5.19E-01 Sr-89 2.92E-06 1.49E-04 Sr-90 2.17E-04 1.1OE-02 Total 1.00E+00 l 5.10E+01

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

B. Estimate of Major Nuclide Composition (by type of waste)

b. Dry Compressible Waste (DAW), Mechanical Filters, Contaminated Equipment, etc.

Note: Waste processed and buried during 2005.

Percent Total Activity Nuclide Composition Curies Am-241 1.39E-06 3.18E-05 C-14 1.84E-02 4.21E-01 e-144 2.29E-03 5.23E-02 m-242 7.56E-06 1.73E-04 Cm-243 1.65E-05 3.78E-04 Co-57 7.09E-04 1.62E-02 Co-58 1.78E-01 4.07E+00 Co-60 2.19E-01 5.01E+00 Cr-51 8.83E-02 2.02E+00 Cs-134 1.23E-04 2.82E-03 Cs-137 3.60E-03 8.22E-02 Fe-55 3.38E-01 7.72E+00

-3 5.26E-03 1.20E-01 1-129 4.10E-02 9.38E-01 Mn-54 3.34E-04 7.63E-03 Nb-95 2.36E-02 5.39E-01 Ni-63 3.27E-02 7.48E-01 Pu-238 4.80E-02 1.10E+00

?u-239 5.35E-06 1.22E-04 Pu-241 3.31 E-04 7.56E-03 Sb-125 4.29E-04 9.81E-03 Sn-113 1.92E-04 4.40E-03 Sr-89 3.83E-09 8.77E-08 Sr-90 1.84E-07 4.22E-06 Zr-95 5.66E-05 1.29E-03 Votal 1.OOE+00 2.29E+01 C. Solid Waste Disposal Number of Shipments

  • 5 Mode of Transportation Rail, Truck Destination Barnwell, SC; Envirocare Facility, Utah
  • Four shipments were made from the Studsvik processing facility in Erwin, Tennessee to Barnwell. One shipment was made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell.

- 27 -

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

NOTE: Values reported in Table 3 section 3.A.a. & 3.A.b refer to radioactive solid waste materials processed and buried during 2005.

A. Type of Waste

a. Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

Note: Waste processed and buried during 2005.

Number of Shipments 2 Activity Shipped 1.35E+02 Curies Estimated Total Error 96.00%

Quantity Shipped 1.14E+00 in3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

b. Dry Compressible Waste(DAW), Mechanical Filters, Contaminated Equipment, etc.

Note: Waste processed and Buried during 2005.

Number of Shipments 3 Activity Shipped 3.15E+01 Curies Estimated Total Error 96.00%

Quantity Shipped 1.08E+00 in3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

c. Irradiated Components, Control Rods, etc.

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

d. Other (Describe)

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

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

B. Estimate of Major Nuclide Composition (by type of Waste)

a. Spent Resins, Filter Sludges, Evaporator Bottoms, etc.

Note: Waste processed and buried during 2005.

Percent Total Activit uclide Composition Curies m-241 1.39E-05 1.87E-03

-14 3.32E-04 4.49E-02 Ce-144 1.24E-03 1.67E-01 Cm-243 7.1 OE-06 9.60E-04 Co-57 2.66E-03 3.59E-01 Co-58 1.33E-01 1.79E+01 Co-60 2.02E-01 2.73E+01 Cs-134 4.91E-04 6.63E-02 Cs-137 5.88E-02 7.94E+00 Fe-55 1.27E-01 1.71E+01 H-3 1.47E-04 1.98E-02 Mn-54 4.89E-02 6.60E+00 Ni-63 4.16E-01 5.62E+01 Pu-238 3.24E-06 4.37E-04 Pu-239 2.32E-06 3.14E-04 Pu-241 1.O1E-04 1.37E-02 Sb-125 9.81E-03 1.32E+00 Sr-89 5.58E-06 7.53E-04 Sr-90 1.91E-04 2.58E-02 Total r I.OOE+00 1.35E+02

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

C. Estimate of Major Nuclide Composition (by type of Waste)

b. Dry Compressible Waste(DAW), Mechanical filters, Contaminated Equipment, etc.

Note: Waste processed and buried during 2005.

Percent Total Activity Nuclide Composition Curies Am-241 2.37E-06 7.47E-05 C-14 5.90E-04 1.86E-02 Ce-144 8.90E-04 2.80E-02 Cm-242 3.60E-06 1.13E-04 Cm-243 9.1 IE-06 2.87E-04 Co-57 1.15E-04 3.62E-03 Co-58 1.90E-02 5.99E-01 Co-60 1.96E-01 6.17E+00 Cr-51 2.80E-03 8.83E-02 Cs-134 7.08E-03 2.23E-01 Cs-137 1.27E-02 3.99E-01l Fe-55 6.39E-01 2.01E+01 H-3 4.01E-04 1.26E-02 Mn-54 2.1 lE-02 6.64E-01 Nb-95 1.62E-02 5.1 1E-01 Ni-63 6.29E-02 1.98E+00 Pu-238 4.65E-06 1.47E-04 Pu-239 1.27E-06 4.02E-05 Pu-241 8.70E-03 2.74E-01 Sb-125 2.74E-03 8.62E-02 Sn-I 13 7.57E-04 2.38E-02 Sr-90 8.16E-07 2.57E-05 Zr-95 8.73E-03 2.75E-01 otal [ 1.00E+00 3.15E+01

3. Solid Waste Disposal Number of Shipments 5 Mode of Transportation Rail, Truck Destination Barnwell Facility, South Carolina; Envirocare Facility, Utah
  • Two shipments were made from the Studsvik Processing Facility in Erwin, Tennessee to Barnwell. Three shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee to Barnwell.

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

Technical Specifications 6.14.c During 2005, the ODCM was not revised. Revision 17 became effective on November 30, 2C04.

Appendix 4: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Offsite Dose Calculation Manual Operational Requirement 3.12.1.c There were no changes to the HNP Environmental Monitoring Program in 2005.

Enclosure 2: 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 2005 resulted in no changes to the Environmental Monitoring Program. The 2005 Land Use Census found that there continues to be no garden in the NE sector where there was a garden at 2.3 miles in 2003. No gardens were found again this year in the E, WNW, NE, S, &

NW sectors. The changes observed in the 2005 Land Use Census from the previous year are as follows: chickens were found in the WSW sector @ 4.5 miles instead of 4.6 miles & the garden in the ESE sector was found @ 4.6 miles in 2005 instead of 2.6 miles as in 2004.

Appendix 5: Additional Operational Requirements Enclosure 1: Inoperability of Liquid Effluent Monitors ODCM Operational Requirement 3.3.3.1 O.b Radioactivity Liquid Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2005 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.

Enclosure 2 : Inoperability of Gaseous Effluent Monitors ODCM Operational Requirement 3.3.3.1 L.b Radioactivity Gaseous Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2005 by the Condition Reporting Process pursuant to ODCM Operational Requirement 3.3.3.1 Lb. None were inoperable for greater than 30 continuous days during the reporting period.

Enclosure 3 : 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.

Enclosure 4: Gas Storage Tanks Exceeding Limits PLP-1 14, Attachment 5, Operational Requirement 1.1 No gas storage tank exceeded the PLP-1 14, Attachment 5 Operational Requirement limit of 1.05 E+05 Curies during this report period.

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.

- 34 -

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.

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 I0CFR50, Appendix I limits are exceeded by a factor of 2 using LADTAP, XOQDOQ, and GASPAR II (N'C computer codes). The ODCM software is more conservative and is used for annual effluent dose assessment for demonstration of compliance with IOCFR50, Appendix I and 40CFR190.

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.

iST 3 rd 2nd 4 th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose 4.46 E-07 3.15 E-05 1.96 E-05 7.64 E-05 1.28 E-04 (mrad) 10CFR'0 Appendix I Limit (irad) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+01 Noble Gas Beta Dcse 1.33 E-06 3.19 E-05 4.38 E-05 7.55 E-05 1.53 E-04 (mrad) 10CFR5;0 Appendix I Limit (nrad) 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-133, 5.46 E-02 3.82 E-02 4.09 E-02 5.94 E-02 1.93 E-01 Particulates, & H3 With TI /2

> 8 days (mrem) 10CFRS'O Appendix I Limit (mrad) 7.5 E+00 7.5 E+00 7.5 E+00 7.5 E+00 1.50 E+01

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 bouidary) plus drinking water from Lillihgton.

1 ST 2nd 3 rd Annual 4 th Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 1.79 E-03 2.38 E-03 6.29 E-04 9.32 E-04 5.73 E-03 IOCFR'O 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) 2.02 E-03 2.48 E-03 6.58 E-04 1.07 E-03 6.23 E-03 IOCFRfiO Appendix I Limit (mrem) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+0i.

40CFR190 Uranium Fuel Cycle Dose Calculation Results Maximum Total Body Dose = 1.93 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Total Body Dose Liquid Effluent Dose = 5.73 E-03 mrem Gas Effluent Dose = 1.93 E-01 mrem 40CFR190 Limit = 25 mrem Maximum Organ Dose = 1.93 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 6.23 E-03 mrem Gas Effluent Dose = 1.93 E-01 mrem 40CFRI90 Limit= 75 mrem Doses Due to Direct Radiation from the Harris Nuclear Plant:

Ongoing Environmental TLD Dose measurements show that the offsite Direct Radialion Dose is negligible. Components considered include Radwaste storage onsite and the Old Steam Generator Storage Facility.

  • . t A Appendix 9: Correction to 2004 Annual Radioactive Release Report 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.

iST 3rd 2 nd 4 th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 4.90 E-04 1.09 E-02 4.01 E-03 3.23 E-03 1.86 E-02 IOCFR 0 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) 6.18 E-04 1.32 E-02 5.87 E-03 6.60 E-03 2.63 E-02 I OCFR5 0 Appendix I Limit (mrem) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+01 40CFRI 90 Uranium Fuel Cycle Dose Calculation Results Maximum Total Body Dose = 2.38E-01 mrem Liquid and Gas Effluent Contribution to Maximum Total Body Dose Liquid Effluent Dose = 1.86 E-02 mrem Gas Effluent Dose = 2.38 E-01 mrem 40CFR1 90 Limit = 25 mrem Maximum Orrzan Dose = 2.38 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 2.63 E-02 mrem Gas Effluent Dose= 2.38 E-01 mrem 40CFRI90 Limit= 75 mrem Doses Due to Direct Radiation from the Harris Nuclear Plant:

Ongoing Environmental TLD Dose measurements show that the offsite Direct Radialion Dose is negligible. Components considered include Radwaste storage onsite and the Old Steam Generator Storage Facility. This statement applies for years 2001 through 20C3 also.

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