Text

Annual Radioactive Effluent Release Report for 2006
	ML071080268
Person / Time
Site:	Harris
Issue date:	04/13/2007
From:	Corlett D; Progress Energy Co
To:	; Document Control Desk, NRC/NRR/ADRO
References
	HNP-07-046
	Download: ML071080268 (263)
	v • d • e

4Progress Energy APR 1 3 2007 SERIAL: HNP-07-046 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 2006.

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

Sincerely, D. H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/mgw Enclosure c: Mr. P. B. O'Bryan (NRC Senior Resident Inspector, HNP)

Ms. L. M. Regner (NRR Project Manager, HNP)

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

Progress Energy Carolinas, Inc.

Htaris Nuclear Plant PRO.Box 165 Now Hill, NC27562

~Progress Energy APR 1 3 2007 SERIAL: HNP-07-046 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 2006.

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

"* Sincerely, D. H. Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/mgw Enclosure c: Mr. P. B. O'Bryan (NRC Senior Resident Inspector, HNP)

Ms. L. M. Regner (NRR Project Manager, HNP)

Dr. W. D. Travers (NRC Regional Administrator, Region II) 9 Progress Energy Carolinas, Inc.

Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562

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, 2006 to December 31, 2006 Table of Contents Section Page No.

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

1. Lower Limits of Detection (LLDs) 11

2. Effluents Released 13

3. Solid Waste Disposal 22 Appendix 3. Changes to Offsite Dose Calculation Manual (ODCM) 30 Appendix 4. Changes to the Environmental Monitoring Program I. Environmental Monitoring Program 31

2. Land Use Census 31 Appendix 5. Additional Operational Requirements

1. Inoperability of Liquid Effluent Monitors 32

2. Inoperability of Gaseous Effluent Monitors 32

3. Unprotected Outdoor Tanks Exceeding Limits 32

4. Gas Storage Tanks Exceeding Limits 32 Appendix 6. Major Modifications to Radwaste System 33 Appendix 7. Meteorological Data 34 Appendix 8. Assessment of Radiation Doses 35 Revision 18 of the ODCM 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), Appendix F Section 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, 2006 to December 31, 2006. During this period, the plant operated in Cycle 13 & Cycle 14. Refueling Outage 13 was scheduled and completed in May 2006.

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 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months 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 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, 2006 through December 31, 2006. 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, 2006 through December 31, 2006, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents: Limit 5.95 E-03 mrem, Total Body 3.0 E+00 mrem 9.28 E-03 mrem, Max Organ (GI-LLI) 1.0 E+01 mrem Gaseous Effluents: Limit Noble Gases 7.40 E-05 mrad, Beta 2.0 E+01 mrad 7.18 E-05 mrad, Gamma 1.0 E+01 mrad Tritium, Radioiodime 131, 133, and Particulates with greater than an 8 Day Half Life:

3.66 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 10CFR20 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 mrem/yr 1 OCFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table 2, Column

1. This is based on 50 mrem/yr.

I OCFR50, 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.OOE-04 1tCi/ml total activity.

10CFR20 Limits The annual average concentrations to be less than the concentrations specified in 1 OCFR20, 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)

II. 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.

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 (2006)

A. Liquid Batch Releases Jan - June 2006 July - Dec 2006 Number of batch releases 2.6 E+01 1.40 E+01 Total time period for batch releases 1.78 E+04 minutes 9.20 E+03 minutes Maximum time of a batch release 1.11 E+03 minutes 7.62 E+02 minutes Average time for a batch release 6.85 E+02 minutes 6.57 E+02 minutes Minimum Time for a batch release 2.76 E+02 minutes 3.0 E+01 minutes Average stream flow during periods of release 1.92 E+03 cf/s 2.81 E+03 cf/s B. Gaseous Batch Releases Jan - June 2006 July - Dec 2006 Number of batch releases 2.6 E+01 2.00 E+00 Total time period for batch releases 3.37 E+04 minutes 8.18 E+02 minutes Maximum time of a batch release 3.01 E+03 minutes 4.76 E+02 minutes Average time for a batch release 1.30 E+03 minutes 4.09 E+02 minutes Minimum Time for a batch release 7.50 E+01 minutes 3.42 E+02 minutes C. Abnormal Releases

a. Liquid There were no abnormal liquid releases in 2006.

b. Gaseous Two unplanned gaseous releases occurred during 2006. Both of these releases were due to identified leakage in the Waste Gas System. For both of these releases, a sample was taken from the in-service Waste Gas Decay Tank to determine the activity in the tank at the time the leakage was discovered. There was a total from both releases of 1.0.25 E-01 curies released. The identified leakage was repaired on both occasions upon discovery.

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

LLDs for Gaseous Effluents Nuclide kCi/cc Gross Alpha 2.75 E-15 H-3 3.90 E-09 Ar-41 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 1-131 4.84 E-13 1-133 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 4.71 E-15 Sr-90 1.86 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 4Ci/ml Gross Alpha 7.96 E-08 H-3 2.45 E-06 Na-24 2.67 E-08 Cr-51 1.89 E-07 Mn-54 4.41 E-08 Fe-55 1.45 E-07 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 9.14 E-08 Zn-65 4.16 E-08 Sr-89 3.33 E-08 Sr-90 1.51 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 1-131 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 1A: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total

1 2 Error %

A. Fission and activation gases

1. Total release Ci 1.81 E-01 1.48 E-02 5.27 E+01

/ i

2. Average release rate for period pCi/sec 2.32 E-02 1.88 E-03

3. Percent of ODCM Operational Requirement limit % 5.34 E-04 9.38 E-05 B. Iodines

1. Total iodine-131 Ci <LLD 1.84 t-07 3.04 E+01I

2. Average release rate for period ýtCi/sec <LLD 2.34 E-08

3. Percent of ODCM Operational Requirement limit* 1.03 E+00 1.18 E+00 C. Particulates

1. Particulates with half-lives >8 days. Ci 6.66 E-05 7.43 E-05 3.38 E+01

2. Average release rate for period pCi/sec 8.56 E-06 9.45 E-06

3. Percent of ODCM Operational Requirement limit* % 1.03 E+00 1.18 E+00

4. Gross alpha radioactivity Ci <LLD <LLD D. Tritium

1. Total release Ci 5.68 E+01 6.54 E+01 5.22 E+01I

2. Average release rate for period ptCi/sec 7.31 E+00 8.32 E+00

3. Percent of ODCM Operational Requirement limit* % 1.03 E+00 1.18 E+00

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)

Enclosure 2: Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES A. Fission and activation gases FUnit Quarter Qu er Est Total

1. Total release Ci 6.27 E-06 5.54 E-02 5.27 E+01

2. Average release rate for period gCi/sec 7.89 E-07 6.97 E-03

3. Percent of ODCM Operational Requirement limit / 1.27 E-08 1.12 E-04 B. lodines

1. Total iodine-131 Ci <LLD <LLD 3.04 E+01

2. Average release rate for period [tCi/sec <LLD <LLD 4 +

3. Percent of ODCM Operational Requirement limit* 1.10 E+O0 1.58 E+00 Particulates

1. Particulates with half-lives >8 days Ci 6.25 E-05 <LLD 3.38 E+01

2. Average release rate for period gCi/sec 7.86 E-06 <LLD

3. Percent of ODCM Operational Requirement limit* % 1.10 E+00 1.58 E+00

4. Gross alpha radioactivity Ci <LLD <LLD D. Tritium

1. Total release Ci 6.07 E+01 8.78 E+01 5.22 E+701 1

2. Average release rate for period RCi/sec 7.64 E+00 1.10 E+01

3. Percent of ODCM Operational Requirement limit* % 1.10 E+00 1.58 E+00

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 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)

Enclosure 2: Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES iI Continuous Mode Batch Mode 11 Nuclides Released Unit Quarter 1 Quarter 2 [ Quarter I Quarter 2

1. Fission Gases Xenon- 131 m Ci <LLD <LLD <LLD <LLD Xenon-133 Ci 5.95 E-02 <LLD 6.42 E-02 4.53 E-06 Xenon-133m Ci <LLD <LLD 1.71 E-03 <LLD Xenon-135 Ci 1.81 E-02 <LLD 2.75 E-02 <LLD Xenon-135m Ci <LLD <LLD 9.11 E-05 <LLD Xenon- 138 Ci <LLD <LLD <LLD <LLD

.Argon-41 Ci <LLD <LLD 4.90 E-03 1.48 E-02 Krypton-85 Ci <LLD <LLD 3.68 E-04 <LLD Krypton-85m Ci <LLD <LLD 1.46 E-03 <LLD Krypton-87 Ci <LLD <LLD 5.29 E-04 <LLD Krypton-88 Ci <LLD <LLD 2.07 E-03 <LLD

[Total for period Ci 7.77 E-02 <LLD 1.03 E-01 1.48 E-02

2. Iodines Iodine- 131 Ci <LLD <LLD Note 1 1.84 E-07 Iodine-132 Ci <LLD <LLD Note 1 6.92 E-06 Iodine-133 Ci <LLD <LLD Note I Note 1 Iodine-135 Ci <LLD <LLD Note 1 Note 1 Total for period Ci <LLD <LLD Note 1 7.10 E-06

3. Particulates Chromium-51 Ci -<LLD <LLD Note 1 1.08 E-05 Manganese-54 Ci <LLD <LLD Note 1 8.66 E-07 Cobalt-58 Ci <LLD 6.17 E-06 Note 1 3.20 E-05 lron-59 Ci <LLD <LLD Note I Note I Cobalt-60 Ci 6.66-05 1.98 E-05 Note 1 1.31 E-06 Zinc-65 Ci <LLD <LLD Note I Note I Strontium-89 Ci <LLD <LLD Note I Note I Strontium-90 Ci <LLD <LLD Note 1 Note 1 Niobium-95 Ci <LLD <LLD Note 1 1.90 E-06 Zirconium-95 Ci <LLD <LLD Note 1 1.37 E-06 Molybdenum-99 Ci <LLD <LLD Note 1 Note 1 Cesium-134 Ci <LLD <LLD Note 1 Note I Cesium-137 Ci <LLD <LLD Note 1 Note I Barium-140 Ci <LLD <LLD Note 1 Note I Lanthanum-140 Ci <LLD <LLD Note 1 Note I Cerium-141 Ci <LLD <LLD Note 1 Note I Cerium-144 Ci <LLD <LLD Note 1 Note I Total for period Ci 6.66 E-05 2.60 E-05 Note 1 4.83 E-05

T L 1 fNote I - I ne pamcuiate ana ioaine activities released Irom waste Gas Decay I anK and Uontalnment rurge batcn releases are included in me detenminatons from the continuous releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES II Continuous Mode Batch Mode 11 Nuclides Rel d Unit Quarter 3 Quarter 4 uarter 3 Quarter 4

1. Fission Gases Xenon- 131 m Ci <LLD <LLD <LLD <LLD Xenon-133 Ci <LLD 5.54 E-02 6.27 E-06 <LLD Xenon-133m Ci <LLD <LLD <LLD <LLD Xenon-135 Ci <LLD <LLD <LLD <LLD Xenon- 135m Ci <LLD <LLD <LLD <LLD Xenon-138 Ci <LLD <LLD <LLD <LLD Argon-41 Ci <LLD <LLD <LLD <LLD Krypton-85 Ci <LLD <LLD <LLD <LLD Krypton-85m Ci <LLD <LLD <LLD <LLD Krypton-87 Ci <LLD <LLD <LLD <LLD Krypton-88 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD 5.54 E-02 6.27 E-06 <LLD

2. lodines Iodine-131 Ci <LLD <LLD Note 1 Note 1 Iodine-133 Ci <LLD <LLD Note 1 Note 1 Iodine-135 Ci <LLD <LLD Note 1 Note 1 Total for period Ci <LLD <LLD Note 1 Note 1

3. Particulates Chromium-51 Ci <LLD <LLD Note 1 Note 1 Manganese-54 Ci <LLD <LLD Note 1 Note 1 Cobalt-58 Ci <LLD <LLD Note 1 Note I Iron-59 Ci <LLD <LLD Note I Note I Cobalt-60 Ci 6.25 E-05 <LLD Note 1 Note I Zinc-65 Ci <LLD <LLD Note 1 Note I Strontium-89 Ci <LLD <LLD Note I Note 1 Strontium-90 Ci <LLD <LLD Note I Note I Niobium-95 Ci <LLD <LLD Note 1 Note 1 Zirconium-95 Ci <LLD <LLD Note 1 Note 1 Molybdenum-99 Ci <LLD <LLD Note 1 Note 1 Cesium-134 Ci <LLD <LLD Note 1 Note 1 Cesium-137 Ci <LLD <LLD Note 1 Note 1 Barium-140 Ci <LLD <LLD Note 1 Note 1 Lanthanum-140 Ci <LLD <LLD Note I Note I Cerium-141 Ci <LLD <LLD Note I Note 1 Cerium-144 Ci <LLD <LLD Note 1 Note I Total for period Ci 6.25 E-05 <LLD Note 1 Note I A,

V Note 1 -The from the particulate continuous and iodine activities released from Waste Gas Decay Tank and Containment Purge batch releases are included in the determinations releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter - Quarter Est. Total I1 1 1 2 Error %

A. Fission and Activation products 1 Total release (not including tritium, gases, Ci 2.30 E-03 2.00 E-02 3.28 E+01l alpha) __

2 Average diluted concentration during pCi/ml 3.47 E-10 3.62 E-09 perio 3 Percent of applicable limit % 2.08 E-02 2.46 E-01 B. Tritium

1. Total release Ci 9.39 E+01 7.77 E+01 5.43 E+01 2 Av~erae diluted concentration during iiCi/ml 1.42 E-05 1.41 E-05 perioa 3 Percent of applicable limit % 1.42 E+00 1.41 E+00 C. Dissolved and entrained gases 1 Total release Ci <LLD <LLD 3.28 E+0 I 2 Average diluted concentration during gtCi/ml

<LLD

< LLD <LLD

< LLD p erio a 3 Percent of applicable limit % 0.00 E+00 0.00 E+00 D. Gross alpha radioactivity 1 Total release Ci <LLD <LLD 3.2r8 E+I E. Volume of waste released 1 Continuous Releases 2 Batch Releases F. Volume of dilution water I 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 Quarter Quarter Est. Total 11 3 4 Error %

A. Fission and Activation products 1 Total release (not including tritium, gases, Ci 6.07 E-03 4.11 E-03 3.28 E+01 alpha) 2 Average diluted concentration during gCi/ml 1.07 E-09 7.47 E-10 period 3 Percent of applicable limit % 2.47 E-02 5.91 E-02 B. Tritium 1 Total release Ci 1.10 E+01 7.89 E+01 5.43 E+01 2 Average diluted concentration during gCi/ml 1.95 E-06 1.44 E-05 perona 3 Percent of applicable limit % 0.19 E+00 1.43 E+00 C. Dissolved and entrained gases 1 Total release Ci <LLD <LLD 3.28 E+01 2 Average diluted concentration during .tCi/ml <LLD <LLD period__

3 Percent of applicable limit % 0.00 E+00 0.00 E+00 D. Gross alpha radioactivity 1 Total release Ci <LLD <LLD 3.28 E+01 E. Volume of waste released I Continuous Releases 2 Batch Releases F. Volume of dilution water I Continuous Releases 2 Batch Releases Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci <LLD <LLD <LLD <LLD Chromium-51 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD <LLD 2.23 E-04 Iron-55 Ci <LLD <LLD 2.89 E-04 6.83 E-04 Cobalt-57 Ci <LLD <LLD <LLD <LLD Cobalt-58 Ci <LLD <LLD 2.67 E-04 8.15 E-03 Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD 6.44 E-04 6.16 E-03 Nickel-63 Ci <LLD <LLD 6.78 E-04 1.65 E-03 Strontium-89 Ci <LLD <LLD <LLD <LLD Strontium-90 Ci <LLD <LLD <LLD <LLD Zirconium-95 Ci <LLD <LLD <LLD 2.38 E-05 Zirconium-97 Ci <LLD <LLD <LLD <LLD Niobium-95 Ci <LLD <LLD <LLD 2.20 E-05 Niobium-97 Ci <LLD <LLD <LLD <LLD Technicium-99m Ci <LLD <LLD <LLD <LLD Ruthenium-106 Ci <LLD <LLD <LLD <LLD Antimony- 124 Ci <LLD <LLD <LLD <LLD Antimony-125 Ci <LLD <LLD 4.23 E-04 3.02 E-03 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 <LLD 2.31 E-05 Barium-140 Ci <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Cerium-141 Ci <LLD <LLD <LLD <LLD Cerium-144 Ci <LLD <LLD <LLD <LLD TOTAL Ci <LLD <LLD 2.30 E-03 2.00 E-02 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 Ci 9.22 E-02 1.10 E-01 9.39 E+01 7.77 E+01 Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 Ci <LLD <LLD <LLD <LLD Chromium-51 Ci <LLD <LLD <LLD <LLD Manganese-54 Ci <LLD <LLD 1.62 E-05 <LLD Iron-55 Ci <LLD <LLD 7.35 E-04 3.05 E-04 Cobalt-57 Ci <LLD <LLD 5.13 E-06 6.72 E-06 Cobalt-58 Ci <LLD <LLD 2.88 E-03 1.57 E-03 Iron-59 Ci <LLD <LLD <LLD <LLD Cobalt-60 Ci <LLD <LLD 8.28 E-04 1.01 E-03 Nickel-63 Ci <LLD <LLD 1.06 E-03 7.81 E-04 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 Ruthenium- 106 Ci <LLD <LLD <LLD <LLD Antimony-124 Ci <LLD <LLD <LLD 1.47 E-05 Antimony-125 Ci <LLD <LLD 5.17 E-04 4{20 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 3.21 E -05 <LLD Barium-140 Ci <LLD <LLD <LLD <LLD Lanthanum-140 Ci <LLD <LLD <LLD <LLD Cerium- 141 Ci <LLD <LLD <LLD <LLD Cerium- 144 Ci <LLD <LLD <LLD <LLD TOTAL Ci <LLD <LLD 6.07 E-03 4.11 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 Ci 1.83 E-01 2.00 E-01 1.10 E+01 7.89 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 1.A.a and LA.b. refer to radioactive solid waste materials processed and buried during 2006.

A. Type of Waste

a. Spent Resins.

Note: Waste processed and buried during 2006.

Number of Shipments Activity Shipped 2.OE-01 Curies Estimated Total Error 96% 3 Quantity Shipped 9.27E-01 m 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 2006.

Number of Shipments 41 Activity Shipped 1.22E+01 Curies Estimated Total Error 96%

Quantity Shipped 5.81E+01m 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)

a. Spent Resins..

Note: Waste processed and buried during 2006.

Percent Total Activity Nuclide Composition Curies C-14 2.71E-06 5.54E-07 Ce-144 2.76E-02 5.64E-03 Co-58 6.89E-03 1.41E-03 Co-60 1.89E-01 3.85E-02 Cs-137 6.68E-02 1.36E-02 Fe-55 2.25E-01 4.59E-02 H-3 5.99E-02 1.22E-02 Mn-54 4.13E-02 8.43E-03 Ni-63 3.84E-01 7.84E-02

[otal 1.00E+00 2.04E-01

- 23 -

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 2006.

Percent Total Activity Nuclide Composition Curies Am-241 3.40E-06 4.15E-05 C-14 9.55E-04 1.17E-02 Ce-144 1.15E-03 1.41E-02 Cm-242 4.52E-07 5.52E-06 Cm-243 1.72E-05 2.10E-04 Co-57 4.95E-04 6.04E-03 Co-58 5.83E-02 7.11E-01 Co-60 3.76E-01 4.59E+00 Cr-51 1.OOE-02 1.22E-01 Cs-137 1.91E-03 2.33E-02 Fe-55 3.98E-01 4.85E+00 Fe-59 7.19E-04 8.77E-03 H-3 1.83E-03 2.24E-02 In-54 1.69E-02 2.06E-01 Nb-95 3.74E-02 4.56E-01 Ni-63 6.90E-02 8.42E-01 Pu-238 2.96E-06 3.61E-05 Pu-239 1.02E-06 1.24E-05 Pu-241 1.08E-04 1.32E-03 Sb-125 7.84E-03 9.57E-02 Sn-113 1.30E-03 1.59E-02 Zr-95 1.80E-02 2.20E-01 lTotal 1.00E+00 1.22E+01 C. Solid Waste Disposal Number of Shipments

45 Mode of Transportation Rail Destination Envirocare Facility, Utah Nine shipments were made from the Studsvik processing facility in Erwin, Tennessee to Envirocare. Thirty Six shipments were made from the Energy Solutions 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 section 2.A.a refer to radioactive solid waste materials processed and buried during 2006.

A. Type of Waste

a. Spent Resins.

Note: Waste processed and buried during 2006.

Number of Shipments I Activity Shipped 5.48E+00 Curies Estimated Total Error 96.00 %

Quantity Shipped 9.39E-01 m3 Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

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

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

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 Report Period.

- 25 -

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.

Note: Waste processed and buried during 2006.

Percent Total Activity Nuclide Composition Curies Am-241 1.83E-05 1.OOE-04 Ce-144 4.44E-03 2.43E-02 Cm-243 8.60e-06 4.71E-05 Co-58 3.23E-03 1.77E-02 Co-60 1.95E-01 1.07E+00 Cs-137 1.32E-01 7.21E-01 Fe-55 4.40E-02 2.41E-01 H-3 1.11E-03 6.08E-03 Mn-54 7.81E-03 4.28E-02 Ni-63 6.08E-01 3.33E+00 Pu-238 5.35E-06 2.93E-05 Pu-239 4.18E-06 2.29E-05 Sb-125 4.02E-03 2.20E-02 Sr-90 3.78E-04 2.07E-03 Votal [ 1.00E+00 I 5.48E+00 C. Solid Waste Disposal Number of Shipments

1 Mode of Transportation Truck Destination Barnwell, SC One shipment were made from the Studsvik processing facility in Erwin, Tennessee to Barnwell.

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 2006.

A. Type of Waste

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

Note: Waste processed and buried during 2006.

Number of Shipments 4 Activity Shipped 7.22E+01 Curies Estimated Total Error 96.00%

Quantity Shipped 1.65E+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 2006.

Number of Shipments 1 Activity Shipped 3.70E-01 Curies Estimated Total Error 96.00%

Quantity Shipped 6.5 1E-03 m3 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.

- 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)

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

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

Note: Waste processed and buried during 2006.

Percent Total Activity Nuclide Composition Curies Am-241 1.51E-05 1.09E-03 Ce-144 3.38E-03 2.44E-01 Cm-242 1.73E-07 1.25E-05 Cm-243 7.01E-06 5.06E-04 Co-57 8.87E-04 6.40E-02 Co-58 1.99E-02 1.43E+00 Co-60 1.88E-01 1.35E+01 Cs-137 1.07E-01 7.76E+00 Fe-55 7.33E-02 5.29E+00 H-3 7.98E-05 5.76E-03 Mn-54 4.61E-02 3.33E+00 Nb-94 1.26E-05 9.07E-04 Ni-63 5.54E-01 4.OOE+01 Pu-238 4.08E-06 2.95E-04 Pu-239 3.09E-06 2.23E-04 Sb-125 6.68E-03 4.82E-01 Sr-90 2.84E-04 2.05E-02

[otal 1.00E+00 7.22E+01

- 28 -

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 2006.

Percent Total Activity Nuclide Composition Curies Am-241 8.63E-06 3.19E-06 C-14 1.87E-03 6.93E-04 Ce-144 1.34E-03 4.95E-04 Cm-242 6.25E-07 2.31E-07 Cm-243 1.63E-05 6.01E-06 Co-57 2.62E-04 9.67E-05 Co-58 1.30E-02 4.82E-03 Co-60 6.22E-0t 2.30E-01 Cr-51 5.14E-05 1.90E-05 Cs-137 4.38E-02 1.62E-02 Fe-55 2.66E-01 9.84E-02 H-3 3.33E-05 1.23E-05 Mn-54 4.63E-03 1.71E-03 Nb-95 1.48E-04 5.46E-05 Ni-63 4.30E-02 1.59E-02 Pu-238 7.17E-06 2.65E-06 Pu-239 2.52E-06 9.33E-07 Pu-241 2.57E-04 9.50E-05 Sb-125 2.67E-03 9.86E-04 Zr-95 5.36E-04 1.98E-04

[Total [ 1.00E+00 I 3.70E-01 C. Solid Waste Disposal Number of Shipments 5.

Mode of Transportation Rail, Truck Destination Barnwell Facility, South Carolina Five shipments were made from the Studsvik Processing Facility in Erwin, Tennessee to Barnwell.

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

Technical Specifications 6.14.c During 2006, the ODCM was revised. Revision 18 became effective on July 27, 2006. A complete copy of Revision 18 of the ODCM is included as Attachment 1 to this report.

Appendix 4: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Offsite Dose Calculation Manual Operational Requirement 3.12.1 .c Changes to the Environmental Monitoring Program in 2006 were: 1) the frequency changed in the milk collection at control locations when no indicator locations have milk animals. The frequency changed from bi-weekly to monthly; 2) eliminated GW-58 as a groundwater monitoring location. This well has been shown to have direct communication with lake/surface water as its concentration track; and 3) deleted food crop sample points since no crops are irrigated by water in which plant wastes have been discharged. These changes became effective on 8/15/2006 following the ODCM change.

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 2006 resulted in a couple of changes to the Environmental Monitoring Program. The changes observed in the 2006 Land Use Census from the previous year survey were as follows: a garden was found in the E sector @ 1.7 miles this year where no garden was found in 2005. No gardens were found again this year in the WNW, NE, S, & NW sectors. The garden location 62, (NE sector) has been removed from the sampling program as of 8/15/2006. The closest resident in the VWNW sector has changed from 2.3 miles to 2.5 miles. As in 2005, Harris Lake County Park was also included in the survey. Although there are not yet permanent residents on site, there are plans in the future for rangers &.a campground. The resident in the S sector has again been included in the data even though they are technically just outside the 5-mile radius, because of historical prevailing winds.

- 31 -

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 2006 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 3.3.3.11 .b Radioactivity Gaseous Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2006 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.

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- 114, Attachment 5, Operational Requirement 1.1 No gas storage tank exceeded the PLP- 114, Attachment 5 Operational Requirement limit of 1.05 E+05 Curies during this report period.

- 32 -

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.

- 33 -

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.

- 34 -

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 10CFR50, Appendix I is more restrictive than 40CFR190 for a single unit site, the assessment for 40CFR190 is performed when any of the I 0CFR50, 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 10CFR50, 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.

QaST nd 3 rd 4 th Annual 2

Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose 4.14 E-05 2.66 E-05 4.28 E-10 3.78 E-06 7.18 E-05 (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 5.34 E-05 9.38 E-06 1.27 E-09 1.12 E-05 7.40 E-05 (mrad) 10CFR50 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, 1-133, 7.72 E-02 8.84 E-02 8.24 E-02 1.18 E-01 3.66 E-01 Particulates, & H3 With T1/2

> 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+01

- 35 -

Appendix 8: Assessment of Radiation Doses ODCM Operational Requirement F.2 Licqui 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.

QaST 2 nd 3 rd 4 th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 1.00 E-03 3.69 E-03 3.70 E-04 8.86 E-04 5.95 E-03 10CFR50 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) 1.04 E-03 6.92 E-03 7.75 E-04 9.73 E-04 9.28 E-03 10CFR50 Appendix I Limit (mrem) 5.00 E+00 5.00 E+00 5.00 E+00 5.00 E+00 1.00 E+01 Atnr'VI'P 101) 1TT-hmi lP'n ,'1r.l Tl - r ltlrl P -o1ito

.L Maximum Total Body Dose = 3.65 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Total Body Dose Liquid Effluent Dose = 9.28 E-03 mrem Gas Effluent Dose = 3.65 E-01 mrem 40CFRI90 Limit = 25 mrem Maximum Organ Dose = 3.66 E-01 mrem Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 9.28 E-03 mrem Gas Effluent Dose = 3.66 E-01 mrem 40CFR190 Limit = 75 mrem Doses Due to Direct Radiation from the Harris Nuclear Plant:

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

- 36 -

Current Revision of ODCM Offsite Dose Calculation Manual, Revision 18

- 37 -

SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

Revision 18 Docket No. STN-50-400 PROGRESS ENERGY CAROLINAS Approval by PNM Approval by Gez Prcpared by Reviewed by ~k Effective Date 23-

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE OF CONTENTS Section Title ........................ ....................................... Page TABLE OF CONTENTS .......................... . . . . . . . . . . . . . i LIST OF TABLES ............................. ............ ii LIST OF FIGURES ............................ ............. V LIST OF EFFECTIVE PAGES ................................................. ............ vi ODCM REV. 18 CHANGE

SUMMARY

............................................. . ............ ix

1.0 INTRODUCTION

..................................................... . ........... 1-1 2.0 LIQUID EFFLUENTS ................................................. . ........... 2-1 2.1 Compliance With 10 CFR 20 ................................. . ........... 2-2 2.2 Compliance With 10 CFR 50 Appendix I ...................... . .......... 2-13 3.0 GASEOUS EFFLUENTS ................................................ . ........... 3-1 3.1 Monitor Alarm Setpoint Determination ...................... . ........... 3-1 3.2 Post-release Compliance With 10CFR20-Based ODCM Operational Requirement 3.11.2 ............................ . .......... 3-15 3.3 Compliance With 10 CFR 50 ................................. . .......... 3-22 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .................... . ........... 4-1 5.0 INTERLABORATORY COMPARISON STUDIES ............................... . ........... 5-1 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)for ODCM OR 3.11.4 ........ . ........... 6-1 6.1 Total Dose (COMPLIANCE WITH 40 CFR 190) for ODCM OR F.2 ............... 6-1 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM ...................................... 7-1 APPENDIX A - METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS ................ ......... A-I APPENDIX B - DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM ................................................ ......... B-I APPENDIX C - RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS ......................... ......... C-i APPENDIX D - PROGRAMMATIC CONTROLS ........................................ ......... D-I APPENDIX E - PROGRAMMATIC CONTROL BASES ................................... ......... E-1 APPENDIX F - ADMINISTRATIVE CONTROLS ...................................... ......... F-I APPENDIX G - DEFINITIONS .................................................. ......... G-1 1

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 LIST OF TABLES No. Title Page 2.1-1 Liquid Effluent Release Tanks and Pumps ............................ 2-19 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (Favail) ....................................................... 2-20 2.1-3 Signal Processor Time Constants (T) for GA Technologies RD-53 Liquid Effluent Monitors .................................................. 2-20 2.1-4 Nuclide Parameters ................................................. 2-21 2.2-1 Ai, Values for the Adult for the Shearon Harris Nuclear Power Plant ........................................................ 2-24 3.1-1 Gaseous Source Terms ............................................... 3-12 3.1-2 Dose Factors and Constants ......................................... 3-13 3.1-3 Gaseous Monitor Parameters ......................................... 3-14 3.2-1 Releases from Shearon Harris Nuclear Power Plant Normal Operation (Curies/year) ..................................... 3-18 3.2-3 Dose Factors for Noble Gases ....................................... 3-20 3.2-4 PiI Values (Inhalation) for a Child ................................. 3-21 3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant .................. 3-34 4.1 Radiological Environmental Monitoring Program ....................... 4-2 A-I through A-4 X/Q and D/Q Values for Long-Term Ground-Level Releases at Special Locations ................................................ A-4 ii

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 LIST OF TABLES (continued)

No. Title Page A-5 through A-6 Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At 3

Standard Distances (sec/mr ) .......................................... A-5 A-7 through A-8 Undepleted, 2.26 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (sec/M3 ) .............................. A-7 A-9 through A-10 Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (sec/M3 ) ....................................... A-9 A-11 through A-12 Deposition Values (D/Q) For Long Term Releases At Standard 2

Distances (m- ) ..................................................... A- 11 A-13 Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP ................................................... A-13 A-14 Shearon Harris Plant Site Input Information for Continuous Ground-level Release Calculations With the NRC XOQDOQ Program ................... A-16 B-1 Parameters for Cow and Goat Milk Pathways .......................... B-16 B-2 Parameters for the Meat Pathway .................................... B-17 B-3 Parameters for the Vegetable Pathway ............................... B-18 iii

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 LIST OF TABLES (continued)

No. Title Page NOTE: Tables in Appendix D are named after their respective Operational Requirement.

3.3-12 Radioactive Liquid Effluent Monitoring Instrumentation ................ D-3 4.3-8 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ................................... . ........ D-5 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation ..... . ........ D-8 4.3-9 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements ................................... ....... D-10 4.11-1 Radioactive Liquid Waste Sampling and Analysis Program ...... ....... D-13 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program ..... . ....... D-19 3.12-1 Radiological Environmental Monitoring Program ............... . ....... D-29 3.12-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples .................................... . ....... D-35 4.12-1 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ..................................... D-36 G-1 Frequency Notation .................................................. G-4 G-2 Operational Mode .................................................... G-5 iv

Shearon Harris Nuclear Power Plant (SHNPP) August, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 LIST OF FIGURES No. Title Page 2.1-1 Liquid Waste Processing Flow Diagram ....................... 2-27 2.1-2 Liquid Effluent Flow Stream Diagram ........................ 2-28 2.1-3 Normal Service Water Flow Diagram .......................... 2-29 2.1-4 Other Liquid Effluent Pathways ............................. 2-30 3.1 SHNPP Gaseous Waste Streams ................................ 3-53 3.2 Schematic of Airborne Effluent Release Points .............. 3-54 3.3 SHNPP Condenser Off-Gas System ............................. 3-55 4.1-1 SHNPP Exclusion Boundary Plan .............................. 4-16 4.1-2 through 4.1-6 Environmental Radiological Sampling Points and Legend ..... ........ 4-17 v

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 List of Effective Pages Page Revision Cover Page ................. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18

................................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. ... . ... .. .. ... .. ... . 18 ii.......................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . 17 iii ........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ... .. .. .. .. ... .. .. ... .. 5 iv ......................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. ... .. .. .. .. ... .. ... .. 6 v . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . ... .. .. ... .. .. ... 5 vi - x ..................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 I

1-1 ........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 2-1 ........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 2 2-5 .................. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2 ..................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 2 2-8 .................. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2-9 ........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2-10 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2-11........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 2-12 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 2-13 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 2-14 ....................... .. ... ... .. .. .. .. ... . ... ... .. ... .. ... ... . ... .. .. ... .. .. ... 4 2-15 ....................... .. ... ... .. .. .. .. .. .. ... ... .. ... .. ... ... . ... .. .. ... . ... ... 6 2 2-17 ................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 2-18 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 2-19 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 2-20 ....................... . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2 2-23 ................ .. ... ... .. .. .. .. .. .. .. ... ... .. ... ... .. .. .. ... .. .. . . . . . . . 15 2 2-27 ................ . . . . . . . . . . . . . . . . . . . . . . . . I. . . . . . . . . . . . . . . . . . . . . . . . . .. ... ... 4 2-28 ....................... . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. ... . 6 2-29 ....................... .. ... ... .. .. .. .. .. .. ... .. ... .. ... ... .. .. .. ... . ... .. .. ... . 4 2-30 ....................... .. ... ... .. .. .. .. .. .. .. ... ... .. ... ... .. .. .. .. .. ... .. .. ... . 6 3-1 ........................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3 3-5 .................. .. ... .. .. ... .. .. .. . . .. ... .. ... ... .. ... .. .. .. .. .. ... .. .. .. 5 3-6 ........................ .. ... .. .. .. ... .. .. . . .. ... .. ... .. ... .. . . . . . . . . . . . . . . . . . . . 15 3-7 ........................ .. .. ... .. .. .. .. ... . . . ... ... ... .. ... .. . . . . . . . . . . . . . . . . . . . 17 3 3-11 ................. .. ... ... . ... .. .. .. . . .. ... ... .. ... .. ... .. .. .. .. ... .. .. ... . 5 3-12 ....................... .. ... ... . ... .. .. .. . . .. ... .. ... ... .. ... . . . . . . . . . . . . . . . . . . 14 3 3-14 ................ .. ... .. .. .. .. .. ... . . . ... ... ... .. ... .. . .. .. .. .. .. ... .. ... . 5 3-15 ....................... . ... ... .. .. .. .. .. ... . ... ... ... .. ... .. ... . ... .. .. ... .. .. .. 6 3 3-19 ................ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3 3-21 ................ .. ... .. .. .. ... . ... .. .. .. ... ... .. ... .. ... .. .. .. .. ... .. ... . 5 3-22 ....................... .. ... .. .. .. .. .. ... .. . ... ... ... .. .. . .. ... . ... .. .. ... .. .. . 14 3 3-26 ................ .. .. ... .. .. .. .. .. ... . ... ... ... .. .. ... .. .. ... .. .. ... . ... . 17 3 3-28 ................ . ... ... .. .. .. .. .. .. .. ... ... .. ... .. ... .. .. .. ... .. .. .. ... . . 6 3 3-31 ................ .. ... .. .. .. ... . ... .. .. .. ... ... .. .. . .. ... . ... .. .. ... .. ... 17 3 3-33 ................ .. .. ... .. .. .. .. .. ... . ... ... ... .. .. . .. .. .. ... .. .. ... .. ... . 6 3-34 52 ................ .. .. ... .. .. .. .. .. .. .. ... ... ... .. .. ... .. .. .. ... .. ... .. .. . . 5 3-53 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 3-54 ....................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 3-55 ....................... .. ... .. .. .. .. .. .. ... . ... ... ... .. .. . . ... . ... .. .. ... .. ... . 5 vi

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 List of Effective Pages Page Revision 4-1 ............. ................ . . .. .. .. ... . 4 4-2 ............. . . . . . . . . . . ............ ................ ... .. ... .. .. 6 4 4-5 ....... . . . . . . . . . . ............ ................ ............. 16 4-6 ............. . . . . . . . . . . ............ 17 4-7 ............. . . . . . . . . . . ............ ........... ........... 18 I 4-8 ............. . . . . . . . . . . ............ ........... ........... 10 4 4-10 ...... . . . . . . . . . . ............ ........... ........... .4 4-11 ............ . . . . . . . . . . ............ ........... ........... 17 4-12 ............ ........... ........... .4 4-13 ............ ........... ........... 18 i 4 4-15 ..... ........... ........... 17 I 4-16 ............ ........... ........... 18 4-17 ............ .......... .4 4 4-21 ..... .......... 18 5-1 ............. .......... 17 6-1 ............. ........... .......... ............ 17 6-2 ............. ........... .......... .......... 15 7-1 .............. ........... .......... ............ 17 A-I ............. ........... .......... ............ 17 A-2 ............. ........... .......... . .. .. .. . .. . 6 A-3 ............. ........... .......... .......... 17 A A-21 ...... ........... .......... ... .. .. ... . 6 B-1 ............. ........... ........... 6 B-2 ............. ... .. ... .. . 5 B-3 ............. ........... ... .. .. ... . 6 B-4 ............. ........... . . ... .. . ... 5 B-5 - B-7 ....... ........... .. ... .. .. .. 4 B-8 ............. .......... 17 B-9 ............. . .. .. .. . ... 4 B-10 ............ .......... 17

.... 4 B-l1 - B-18 .....

C-i ............. ... 14

.... 6 D-I .............

D-2 ............. ... 13 D-3 ............. .. . 9

.. . 6 D-4 ............. ................. ............

D-5 ............. ................. ............ ... 17 D-6 ............. ................. ............ ... 10 D-7 ............. ......................................... 11 D-8 - D-9 ....... ......................................... ... 6 D-10 ............ ......................................... ... 17 D-1I ............ ......................................... .... 9 D-12 -D-13 ...... ........... ......................................... ... 17 D-14 - D-18 ..... ........... ......................................... .... 6 D-19 ............ ........... .........................................

... 17 D-20 ............ ........... ............ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 vii

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 List of Effective Pages Page Revision D D-22 ............... ................ 13 D D-30 ............... ................ .6 D -31 ...................... ................ 18 i

D D-33 ............... ................ .6 I D -34 ...................... ................ 18 D-35 ...................... ................ .6 D D-37 ............... ................ 12 D D-39 ............... ................ .6 D-40 ...................... 15 E E-9 ................. .6 E-10 ...................... 17 E E-12 ................ ........... .6 F F-2 ................. ........... .6 F --3 ....................... ........... 13 F -4 ....................... ........... 11 F -5 ....................... ........... ..... 17 G G-2 ................. ........... ...... 18 I

G G-5 ................. ........... .. ...... 6 viii

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 ODCM REV. IS CHANGE

SUMMARY

Revision 18 to the ODCM is as follows:

Section Page Description Title Page Revised to Rev. 18 Table of Contents i Changed to "ODCM REV. 18 CHANGE

SUMMARY

LEP vi, vii, Changed revision numbers as appropriate viii ODCM REV 18 CHANGE ix-x Changed to reflect Rev. 18 revisions.

SUMMARY

Table 4.1 4-7 Removed GW-58 as a groundwater monitoring location.

This well has been shown to have direct communication with lake/surface water as its concentration track lake/surface water concentrations.

Table 4.1 4-13 Deleted food crop sampling for sample points FC-5, FC-54, FC-55, FC-64. Food crop sampling is only required when the area where crops are grown is irrigated by water in which liquid plant wastes have been discharged (NUREG-1301). Also deleted Sample Point 62 as no food crops have been grown in the last two years at this location..

Figure 4.1-1 4-16 Years ago the Shearon Harris Road had two road numbers (SR-1135 & SR-1136). The road number has changed to one number (SR-1134). Figure 4.1-1 has been updated to reflect this change.

Figure 4.1-3 4-18 Updated the Shearon Harris Road to SR-1134. Figure 4.1-3 has been updated to reflect this change.

Figure 4.1-4 4-19 Deleted Food Crop Sample Points 62 as per page 4-13.

The Ground Water locations (GW-39, GW-57, GW-58, GW-59, and GW-60) were removed and Figure 4.1-5 was created for solely Ground Water Sampling locations.

Updated the Shearon Harris Road to SR-1134. Figure 4.1-4 has been updated to reflect this change.

Figure 4.1-5 4-20 This is a new Figure that has been added to identify ground water sampling locations(GW-39, GW-57, GW-59, and GW-60).

Figure 4.1-6 4-21 Figure 4.1-6 (Environmental Radiological Sampling Points Legend) was renumbered from Figure 4.1-5, page 4-20. Deleted Food Crop Sample Points from the legend as per page 4-13. Deleted GW-58 as per page 4-20.

Table 3.12-1 D-31 Added under Sampling and Collection Frequency for milk sampling "When no milk animals are available at indicator locations, milk sampling of the control location can be reduced to once per month to maintain historical data". This is consistent with note 9 in Table 4.1, page 4-15.

Table 3.12-1 D-34 Added the following to Table 3.12-1 Notation number (7); The five current ground water locations have not been used for drinking water since the construction days of Harris Nuclear Project nor have these wells ever been used for irrigation purposes. These wells were used for drinking purposes during the Preoperational Radiological Environmental Monitoring program, but this practice was abandoned prior to operational plant life. These wells have been used since that time to monitor hydraulic gradient or gradient properties for the Harris Site. GW-58 is no longer valuable for this purpose due to communication with the lake/surface water.

ix

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Section 'tion Appendix G Moved GASEOUS RADWASTE TREATMENT SYSTEM to G-1 for repagination. On G-2, added definitions for RELEASE, and ABNORMAL/ACCIDENTAL, NON-ROUTINE, PLANNED, MONITORED, and CONTROLLED RELEASES x

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to ensure compliance with Operational Requirements 3.3.3.10, 3.3.3.11, 3/4.11.1, 3/4.11.2, 3/4.11.4, 4.12.1, 4.12.2, and 4.12.3 and reporting requirements in Appendix F of the ODCM. These operational requirements are those related to normal liquid and gaseous radiological effluents, environmental monitoring, and reporting.

They are intended to show compliance with 10CFR20-based requirements, 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appropriate monitoring instrumentation, setpoints, dose rate, and cumulative dose limitations. Off-site dose estimates from non-routine releases will be included in the cumulative dose estimates for the plant to comply with Appendix I of 10CFR50.

The ODCM is based on "Westinghouse Standard Technical Specifications" (NUREG 0452), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant and Nuclear Generation Group (NGG) procedures implement the ODCM program requirements.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM are expected in the future. Any such changes will be properly reviewed and approved as indicated in Administrative Controls Section 6.14 of the SHNPP Technical Specifications.

The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant is estimated using the methodology in the ODCM for the report period. These off-site dose estimates for each calendar year are reported in the Annual Radioactive Effluent Release Report required by Appendix F of the ODCM.

1

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 2.0 LIQUID EFFLUENTS Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to demonstrate compliance with 10 CFR 50 Appendix I (ODCM Operational Requirement 3.11.1.2) and, on an annual average basis, be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases the concentration shall be limited to 2E-4 gCi/ml total activity. On an individual release basis, the release concentration for liquid effluents will be limited to ten times (10x) the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, Effluent Concentration (ODCM Operational Requirement 3.11.1.1). The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line into Harris Lake (see Figure 2.1-3 and T/S Figure 5.1-3).

Figure 2.1-1, Liquid Waste Processing Flow Diagram, and Figure 2.1-2 Liquid Effluent Flow Stream Diagram, show how effluents are processed and where they are released.

Effluent monitor identification numbers are provided in Appendix C. Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line. Concurrent batch releases shall not occur at SHNPP.

The Secondary Waste Sample Tank (SWST) and the Normal Service Water (NSW) system have a low potential for radioactive effluent releases. These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).

The Turbine Building floor drains and the outside tank area drains (Figure 2.1-

4) are monitored effluent lines with low probability of radioactive contamination.

The radioactive liquid waste sampling and analysis required for batch and continuous releases are found in Table 4.11-1 of the ODCM Operational Requirements.

The SHNPP ODCM uses the Canberra, Inc., Effluent Management System (EMS) software for automating the necessary calculations and record keeping. As such, the ODCM is written with the following parameters set in the EMS:

The SET-OPT option is set to NOWASTE The SETPEQN option is set to LOWACT 2-1

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1 Compliance with 10 CFR 20 10 CFR 20.1301 requires that the total effective dose equivalent to individual members of the public will not exceed 0.1 rem (100 mrem) in a year.

10 CFR 20.1302 states that a licensee can show compliance with the annual dose limit of 20.1301 by demonstrating that the annual average concentration of radioactive material released in liquid effluents at the boundary of the unrestricted area does not exceed the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

ODCM Operational Requirement 3.11.1.1 states that, on an individual release basis, the concentration of radioactive material released in liquid effluents to unrestricted area shall be limited to 10 times the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

ODCM Operational Requirement 3.3.10 requires that radioactive effluent instrumentation have alarm/trip setpoints that will ensure that an alarm/trip will occur prior to exceeding 10 times the limits of ODCM Operational Requirement 3.11.1.1. for principal gamma emitters.

Liquid effluent monitors have two setpoints, the high alarm and the alert alarm.

The high alarm setpoint, Smax, provides alarm and isolation if the radionuclide concentrations, when diluted, would approach the ODCM Operational Requirement limits for concentrations in unrestricted areas. Alert alarm setpoints, Salert, are set at a fraction of the Sx to provide an early warning of the approach to ODCM Operational Requirement limits.

2-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases Radioactive liquids are routinely released as batches from the Waste Evaporator Condensate Tank (WECT) and Treated Laundry and Hot Shower Tank (TL&HST). Batch releases may also originate from the Secondary Waste Sample Tank (SWST) and Waste Monitor Tank (WMT). These tanks are shown in Figures 2.1-1 and 2.1-2.

Based on analysis of the tank contents, the tank release rate is adjusted, based on the Cooling Tower Blowdown Line flow rate, to dilute the tank activities to 50 percent of the allowable concentrations at the release point to Harris Lake.

The ODCM software calculates a nuclide specific response setpoint which is based on the sum of responses for each nuclide. The nuclide specific response setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated.

If analysis of the batch sample indicates all gamma-emitting nuclides are < LLD, (as defined in ODCM Operational Requirement Table 4.11-1), the tank gamma activity, Ci, may be assumed to consist only of Cs-134. This nuclide has the lowest Effluent Concentration Limit (ECL) of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint.

2-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases (continued)

1. Minimum Tank Mixing Time Footnote 2 to ODCM Operational Requirement Table 4.11-1 requires that the method used to mix an isolated effluent tank prior to sampling and analysis be described.

Equation 2.1-1 below provides an acceptable method for ensuring a well mixed tank so that a representative sample can be taken for radioactivity or other appropriate analyses.

(V) (E) (N)

R = (2.1-1)

(RR) (6 0) where:

R = Minimum allowable mixing time, hr V = Tank capacity, gal E = Eductor factor RR = Pump design recirculation flow rate, gpm n = Number of tank volumes for turnover; this will be a minimum of two 60 60 min/hr Table 2.1-1 lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release tanks.

2-4

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases (continued)

2. Required Dilution Factor ODCM Operational Requirement 3.11.1.1 requires that the sum of concentrations divided by ECL values must not exceed 10 for an individual release. Therefore:

< 10 (2.1-2) 1 ECLi where:

Ci = the concentration of nuclide i to be released ECLi the Effluent Concentration Limit for nuclide i from 10CFR20, Appendix B, Table 2, Column 2.

If the summation is greater than 10, dilution is required. The total required dilution factor, Dreq, is the minimum acceptable dilution factor required to meet the limits of ODCM Operational Requirement 3.11.1.1, based on pre-release and composite analysis.

Dreq = Dreq,g + Dreq,ng (2.1-3) where:

Dreq,g = Required dilution factor for gamma-emitters C.

Zi=g 1 ECL.

1 (2.1-4) f 0 R_

2-5

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 2.1.1 Batch Releases (continued)

Dreq, ng Required dilution factor for non-gamma-emitters c.1-Xi= n g ECLi r

+ (2.1-5) f

Rmax f

Rmax and f = 0.5 A safety factor to assure that the nuclide concentrations are 50% of the ODCM Operational Requirement limit at the point of discharge.

r a value to take into account that tritium is potentially being released via the settling basin discharge to the cooling tower discharge line. This value is normally set to 1.OE-03, which is the H-3 ECL. NOTE: CRC-001 has a target limit of 2.OE-04

'ICi/ml.

Rmax The maximum ECL ratio for the release point (normally set to 10).

The sums include gamma-emitters (g) and non-gamma-emitters (ng),

respectively.

The measured concentration of each gamma-emitting nuclide, including noble gases, is reported in ýiCi/ml. If no gamma activity is detectable then an activity of 9E-07 J.Ci/ml of Cs-134 is assumed for setpoint calculations. The measured concentration of non-gamma emitters is determined by analysis of the liquid effluent or previous composite sample, and is reported in gCi/ml.

2-6

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases (continued)

3. Maximum Waste Flow For liquid releases,the maximum permissible waste flow rate for this release, Wmax is the minimum of Relax and R.max, where Favail 0 alloc (2.1-6)

Dreq Rwmax Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-1. This value is the same as Fwaste.

and Favail The available dilution flow is the minimum dilution stream flow (Cooling Tower Blowdown) that can be ensured for the period of the release. Since only one batch release occurs at a time out of a single discharge point, the flow is not corrected for other releases in progress, for any activity in the dilution stream, or reduced by a safety factor. The minimum dilution flow rate for each setting is shown in Table 2.1-2.

falloc Fraction of the available dilution volume which may be assigned to a particular release to ensure discharge point limits are not exceeded by simultaneous radioactive liquid releases. The value of failoc is based on assumed operational considerations for simultaneous releases but normally will be 0.8 for a batch release and 0.2 for a continuous release.

4. Minimum Dilution Flow Rate The Minimum Dilution Flow Rate (mindflow) is the minimum Cooling Tower discharge flow necessary to dilute the release to less than ODCM Operational Requirement Limits.

If Dreq

1, the minimum dilution flow rate is set to 0.0. If Dreq > 1, the minimum dilution flow rate is determined as follows:

Fwaste 0 Dreq mindf low (2.1-7) falloc where Fwaste waste flow anticipated for this release 2-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases (continued)

5. Setpoint Calculations The ODCM software calculates a nuclide specific response setpoint, which is based on the sum of responses for each nuclide. The setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated. The setpoint is listed in terms of Cs-equiv and the units are J.Ci/ml.

If analysis of the batch sample indicates all gamma-emitting nuclides are

< LLD, (as defined in ODCM Operational Requirement Table 4.11-1), the tank gamma activity, Ci, may be assumed to consist only of Cs-134. This nuclide has the lowest ECL of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint.

(1) Maximum setpoint value, based on Nuclide Specific Response Smax (Cs-equiv) = (Sadj

R...) + B (2.1-8) where Sadj = Setpoint adjustment factor.

ioc 0F - Dreqng Fwaste (2.1-9)

Dreqg Sadi should always be greater than 1 to ensure that adequate dilution flow is available for the release.

B = monitor background (gCi/ml) 2-8

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.1.1 Batch Releases (continued)

Rmon X Z slopei

Ci where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slopei = the Liquid Effluent Monitor Gamma Sensitivities (from Table 2.1-4) for nuclide i, relative to Cs-137. To make nuclide i relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

Sensitivity (nuclide i)

Cs-137 Sensitivity (2) Monitor alert alarm setpoint, Salert (Cs-equiv)

An Alert Alarm setpoint is calculated to provide an operator with adequate warning that the high alarm setpoint is being approached.

Salert is calculated from the nuclide specific response setpoint.

Salert [(Smax - B) 0 F.] + B (2.1-10) where:

Fx A value <1.0 designed to provide an operator with adequate warning that the high alarm setpoint is being approached.

2-9

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.1.1 Batch Releases (continued)

(3) Check for Excessive Monitor Background In order to differentiate between the Saiert and the statistical fluctuations associated with a high monitor background, a check for excessive monitor background is made. As a check, verify that the minimum detectable concentration (MDC) for the monitor is less than 0.1 of the net Salert; therefore, background is acceptable if:

MDC :5 0 . 1[(S.a - B) 0 F. I (2.1-11) where:

Bkg 2

F2'r MDC (2.1-12)

Em where:

Signal Processor Time constant, minutes.

(Table 2.1-3)

Bkg Background Count Rate, in cpm

= B / Em Em Monitor efficiency for the Cs-137 gamma energy, cpm/[tCi/ml determined by primary calibration.

If not, postpone the release and decontaminate or replace the sample chamber to reduce the background, then recalculate Smax and Salert using the new, lower background.

6. Post-Release Compliance After the release is made, actual concentrations are used to check 10 CFR 20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the start and end dates and times of the release. This is used with the actual release volume to calculate the release rate.

2-10

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 2.1.2 Continuous Releases The continuous releases from the SWST and the NSW return lines are monitored as shown in Figures 2.1-2 and 2.1-3. The function of these monitors, in contrast to the isolation function of batch release tank monitors, is to provide an indication of low levels of radioactivity in the effluent. The continuous effluent monitor setpoint is based on an assumed FSAR nuclide mix for the SWST (from Table 11.2.1-5 of the FSAR).

The EMS software does not calculate continuous release monitor setpoints.

1. Monitor High Alarm Setpoint, Smax (4Ci/ml).

0.1 (ECLeff

Senseff) + Bkg Smax = (2.1-13)

Em where:

ECLeff Weighted Effluent Concentration Limit for the SWST nuclides listed in Table 11.2.1-5 of the FSAR.

Senseff - Xg (Sensi x % abundance) for the SWST nuclide mix, cpm/ýLCi/ml.

2. Monitor Alert Alarm Setpoint, Salert (Cs-equiv)

Salert I[(Smax - B)

Fx] + B (2.1-14)

When the monitor is operable and not in alarm, analysis of weekly composite samples is not required by ODCM Operational Requirement Table 4.11-1.

If the monitor is in alarm or the presence of non-naturally occurring radioactivity > effluent LLD is confirmed, the releases may continue provided the sampling and analysis required by ODCM Operational Requirement Table 4.11-1 are performed. The results of the sample analysis will be evaluated for compliance with ODCM Operational Requirement 3.11.1.1.

The monitor alarm setpoints may be recalculated using the methodology in Section 2.1.1 with the results of the gamma analysis and analyses of the composite sample.

3. Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor is >0.01 ECLeff. Therefore, background is acceptable if:

0.01 (ECLef Sensef MDC < eff eff (2.1-15)

Em 2-11

Shearon Harris Nuclear Power Plant November 1995 Offsite Dose Calculation Manual (ODCM) Rev. 7 2.1.3 Other Liquid Releases

1. Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake. The line is monitored for radioactivity by the Tank Area Drain Transfer Pump Monitor. Because no radioactivity is normally expected in this line, the monitor high alarm and alert alarm setpoints are determined using the methodology is Section 2.1.2. If the setpoint is exceeded, the discharge pump is automatically secured. Effluent can then be diverted to the floor drain system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2. Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the yard oil separator for release to the environment via the waste neutralization system and then to the cooling tower discharge line.

Tritium is expected to be detected in this pathway from sources such as background from the lake. Because no other radioactivity is normally expected in this path, the setpoints for the turbine building drain monitor are determined using the methodology in Section 2.1.2. Should the setpoint be exceeded, the release is automatically terminated.

Effluent can then be diverted to the secondary waste treatment system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2-12

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 2.2 Compliance with 10 CFR 50 Appendix I 2.2.1 Cumulation of Doses The dose contribution from each release of liquid effluents will be calculated and a cumulative summation of the total body and each organ dose will be maintained for each 31 days (monthly), each calendar quarter, and the year.

The EMS software calculates and stores the dose for the critical receptor (site boundary), for each nuclide, and for each organ. The dose is the total over all pathways which apply to that receptor. A receptor is defined by receptor ID, age group (infant, child, teen, or adult), sector, and distance from the plant.

The dose contribution for batch releases and all defined periods of continuous release received by receptor "r" from a released nuclide "i" will be calculated using the following equation:

Dizr AiTr *

Ats Cis Frs (2.2-1) where:

Di=r the cumulative dose or dose commitment to the total body or an organ "T" by nuclide "i" for receptor "r" from the liquid effluents for the total time period of the release, in mrem.

Ai~r site-related ingestion dose or dose commitment factor for receptor "r" to the total body or organ "T" for nuclide i, in mrem/hr per IICi/ml.

At s length of time period 's', over which the concentration and F value are averaged, for all liquid releases, in hours.

Cis the average concentration of nuclide "i" in undiluted liquid effluent during time period Ats from any liquid release, in IICi/ml.

Frs the near field average dilution factor for receptor "r" during any liquid effluent release.

2-13

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2.1 Cumulation of Doses (continued)

Where:

Fwaste FrsFwaste + Favail mix (2.2-2) and Rmix mixing ratio fraction of the release that reaches the receptor.

At the SHNPP, this value is set to 1.

Also, the sum extends over all time periods 's'.

In the case of a continuous secondary waste sample tank radioactive release, Ci

the concentration of nuclide "i" in the SWST composite sample. For the NSW, Ci = concentration of nuclide "i" in the cooling tower basin and Fwaste

discharge from the cooling tower basin while Favaii = the flow from the makeup water cross-tie. For a release through the Turbine Building Floor Drain Line to the waste neutralization system, Ci = the Turbine Building floor drain sample activity, Fwaste = discharge from the Turbine Building floor drain line, and Favail

= the average flow during the period of the total Cooling Tower discharge. The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower Bypass Line flow.

When there is a primary-to-secondary leak, the change in concentration of tritium in the steam generators times the secondary loses (balance of plant),

will be used for effluent accountability. The secondary loss rate will also be used for volume accountability.

The dose factor A1 , (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:

-A t 730 i p A. = 1.14E + 05 (- + 21BF.) DF. e e (2.2-3)

D w

I ir where:

Ai, The ingestion dose commitment factor to the whole body or any organ "T" for an adult for each nuclide "i".

Corresponding to fish consumption from the Harris Lake (dilution = 1) and drinking water from Lillington (dilution

= 13.95).

Values for the adult total body and organs in mrem/hr per IICi/ml are given in Table 2.2-1.

2-14

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.2.1 Cumulation of Doses (continued) 1.14E+05 = Unit Conversion Factor 106 pci 1000 ml 1 yr 0 - (2.2-4) 1 IICi 1 liter 8760 hrs 21 Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kg/yr; 730 = Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), liters/yr.

D = Dilution factor for the drinking water pathway

= 13.95 BFi = Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1), pCi/kg per pCi/l DFi, = Dose conversion factor for nuclide "i' for adults for a particular organ r (from Table E-I1 of Regulatory Guide 1.109, Rev. 1),

mrem/pCi

= Radiological decay constant of nuclide "i," hr-1 ;

= 0.693 (t%) i (t2)i = Radiological half-life of nuclide "i," hr; t, Average transport time to reach point of exposure, hr;

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The more limiting decay time for the drinking water and fish exposure pathways (Reg. Guide 1.109, Appendix A, Rev. 1).

-xitp Table 2.2-1 presents the Ai, values for an adult receptor. Values of e are presented in Table 2.1-4 for each nuclide "i".

2.2.2 Comparison Against Limits The sum of the cumulative dose from all batch and any continuous releases for a quarter is compared to one-half the design objectives for total body and any organ. The sum of the cumulative doses from all releases for a calendar year is compared to the design objective doses. The following relationships should hold for the SHNPP to show compliance with ODCM Operational Requirement 3.11.1.2.

2-15

Shearon Harris Nuclear Power Plant (SHNPP) November 2001 Offsite Dose Calculation Manual (ODCM) Rev. 14 2.2.2 Comparison Against Limits (continued)

For the calendar quarter:

Dirr 4 1.5 mrem total body (2.2-5)

DiTr

5 mrem any organ (2.2-6)

For the calendar year:

DiTr

3 mrem total body (2.2-7)

Di~r

10 mrem any organ (2.2-8) where:

Ditr Cumulative total dose to any organ t or the total body from all releases, mrem:

The quarterly limits given above represent one-half the annual design objective of 10 CFR 50, Appendix I, Section II.A. If any of the limits in equations (2.2-

5) through (2.2-8) are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I, 10 CFR 50.

The calculations described in Section 2.2.1 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I for each release. Summation of doses for all releases for the quarter and year are compared to the limits in 10CFR50 Appendix I to ensure compliance.

The SHNPP ODCM uses a "modified" NUREG 0133 equation with conservative assumptions. It calculates the dose to a single maximum (ALARA) individual.

The ALARA individual is an individual that consumes fish caught in the Harris Lake (dilution of 1.0) and receives their drinking water from Lillington, North Carolina (dilution 13.95).

2-16

Shearon Harris Nuclear Power Plant (SHNPP) November 2001 Offsite Dose Calculation Manual (ODCM) Rev. 14 2.2.2 Post-release Compliance With 10 CFR 50 - Based ODCM Operational Requirement After the release is made, the doses are compared to the 10CFR50 limits. The actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the actual start and end dates and times of the release. This is used with the actual volume input to calculate the release rate. Each month the dilution volume is updated for times when no releases were being made in order to update the quarterly and yearly doses for comparison with the 10CFR50 Appendix I limits.

2.2.3 Projection of Doses Dose projections for this section are required at least once per 31 days (monthly) in ODCM Operational Requirement 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully utilized.

The doses will be calculated using Equation 2.2-1, and projected using the following expression:

D = (D, e p) + Da, (2.3-1) where:

D = the 31 Day Projected Dose by organ T D = sum of all open release points in mrem/day by organ T.

p = the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

DaT Additional Anticipated Dose for liquid releases by organ r and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard and Special Permit Reports. The 31 day dose projections on the Approval/Results screen include any additional dose.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

2-17

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 2.2.3 Projection of Doses (continued)

To show compliance with ODCM Operational Requirement 3.11.1.3, the projected 31 day dose should be compared to the following limits:

D : 0.06 mrem for total

body (2.3-2) and Dp : 0.2 mrem for any organ (2.3-3)

If the projections exceed either Expressions 2.3-2 or 2.3-3, then the appropriate portions of the liquid radwaste treatment system shall be used to reduce releases of radioactivity.

2-18

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 TABLE 2.1-1 LIQUID EFFLUENT RELEASE TANKS AND PUMPS Tank Radiation No. of PUMP DESIGN CAPACITY (gpm) Eductor Capacity Effluent Tank (2) Tanks Discharge Recirculation Factor (gal) Monitor ID SWST 1 100 100 0.2 25,000 REM-3542 WECT 2 35 35 1.0 10,000 REM-3541 3

WMT ) 2 100 100 0.25 25,000 REM-3542 TL&HS 2 100 100 0.25 25,000 REM-3540 The settling basin has two pumps. When one pump is running, the design flow rate is 500 gpm. When both pumps are running, the design flow rate is 800 gpm.

I Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 2 SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TL&HS: Treated Laundry and Hot Shower Tank Waste Monitor Tanks are used to batch release secondary waste effluent when activity is suspected in this pathway.

2-19

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (Favail)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate (gpm) 1 4,000 +/- 5% 3,800 2 7,000 +/- 5% 6,650 3 11,000 +/- 5% 10,450 4 15,000 +/- 5% 14,250 TABLE 2.1-3 Signal Processor Time Constants (T) for GA Technologies RD-53 Liquid Effluent Monitors Detector Background (cpm) T (min) 101 - 102 10 102 - 103 103/cpm bkg 103 - 104 10 3 /cpm bkg 104 - 105 10 3 /cpm bkg i05 - 106 0.01 106 - l0, 0.01 2-20

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 Page 1 of 3 TABLE 2.1-4 Nuclide Parameters Half-Life Sensitivity Sensitivity Nuclide (hr) (hr-l) e-*t (cpm/ItCi/ml) Slope TB Bldg.

Drain Only (cpm/Lci/ml)

H-3 1.08E+05 6.44E-06 1.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C-14 5.02E+07 1.38E-08 1.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 F-18 1.83E+00 3.78E-01 1.07E-02 0.OOE+00 0.OOE+00 7.78E+07 Na-24 1.50E+01 4.62E-02 5.74E-01 9.36E+07 9.OOE-01 9.11E+07 P-32 3.43E+02 2.02E-03 9.76E-01 0.00E+00 0.00E+00 0.OOE+00 Cr-51 6.65E+02 1.04E-03 9.88E-01 1.61E+07 1.55E-01 2.79E+06 Mn-54 7.50E+03 9.24E-05 9.99E-01 1.03E+08 9.90E-01 4.45E+07 Mn-56 2.58E+00 2.68E-01 4.OOE-02 1.01E+08 9.71E-01 6.41E+07 Fe-55 2.37E+04 2.93E-05 1.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 1.07E+03 6.47E-04 9.92E-01 1.26E+08 1.21E+00 4.58E+07 Co-57 6.50E+03 1.07E-04 9.99E-01 0.OOE+00 0.OOE+00 5.82E+06 Co-58 1.70E+03 4.08E-04 9.95E-01 1.46E+08 1.40E+00 5.68E+07 Co-60 4.62E+04 1.50E-05 I.OOE+00 1.89E+08 1.82E+00 9.07E+07 Ni-63 8.78E+05 7.89E-07 1.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Ni-65 2.52E+00 2.75E-01 3.67E-02 2.24E+07 2.15E-01 1.96E+07 Cu-64 1.27E+01 5.46E-02 5.19E-01 5.16E+07 4.96E-01 1.46E+07 Zn-65 5.87E+03 1.18E-04 9.99E-01 5.24E+07 5.04E-01 2.41E+07 Zn-69 9.27E-01 7.48E-01 1.26E-04 2.22E+03 2.13E-05 5.OOE+02 Zn-69m 1.38E+01 5.03E-02 5.47E-01 0.OOE+00 0.OOE+00 3.52E+07 Br-82 3.53E+01 1.96E-02 7.90E-01 0.OOE+00 0.OOE+00 1.43E+08 Br-83 2.38E+00 2.91E-01 3.05E-02 1.95E+06 1.88E-02 5.74E+05 Br-84 5.30E-01 1.31E+00 1.53E-07 6.50E+07 6.25E-01 5.06E+07 Br-85 4.78E-02 1.45E+01 3.02E-76 6.76E+06 6.50E-02 3.21E+06 Rb-86 4.48E+02 1.55E-03 9.82E-01 8.39E+06 8.07E-02 3.96E+06 Rb-88 2.97E-01 2.34E+00 6.66E-13 1.45E+07 1.39E-01 1.83E+07 Rb-89 2.57E-01 2.70E+00 8.43E-15 1.22E+08 1.17E+00 7.OOE+07 Sr-89 1.21E+03 5.71E-04 9.93E-01 1.46E+04 1.40E-04 6.72E+03 Sr-90 2.50E+05 2.77E-06 1.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-91 9.50E+00 7.30E-02 4.17E-01 8.16E+07 7.85E-01 3.48E+07 Sr-92 2.72E+00 2.55E-01 4.68E-02 1.01E+08 9.71E-01 4.61E+07 Y-90 6.42E+01 1.08E-02 8.78E-01 0.OOE+00 0.00E+00 0.OOE+00 Y-91 1.41E+03 4.93E-04 9.94E-01 2.83E+05 2.72E-03 1.36E+05 Y-91m 8.28E-01 8.37E-01 4.36E-05 1.28E+08 1.23E+00 3.96E+07 Y-92 3.53E+00 1.96E-01 9.50E-02 2.76E+07 2.65E-01 1.17E+07 Y-93 1.01E+01 6.86E-02 4.39E-01 1.37E+07 1.32E-01 3.96E+06 Zr-95 1.54E+03 4.51E-04 9.95E-01 1.07E+08 1.03E+00 4.35E+07 Zr-97 1.68E+01 4.12E-02 6.10E-1 2.68E+07 2.58E-01 9.16E+06 Nb-95 8.42E+02 8.24E-04 9.90E-01 1.06E+08 1.02E+00 4.41E+07 Nb-97 1.20E+00 5.771E-01 9.86E-04 0.OOE+00 0.OOE+00 4.33E+07 Mo-99 6.60E+01 1.05E-02 8.82E-01 3.47E+07 3.34E-01 9.38E+06 Tc-99m 6.02E+00 1.15E-01 2.51E-01 1.lE+08 1.07E+00 7.33E+06 2-21

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 Page 2 of 3 TABLE 2.1-4 Nuclide Parameters (continued)

Half-Life x Sensitivity Sensitivity Nuclide (hr) (hr-l) e-Xt (cpm/IICi/ml) Slope TB Bldg.

Drain Only (cpm/jiCi/ml)

Tc-101 2.37E-01 2.93E+00 5.45E-16 1.66E+08 1.60E+00 2.92E+07 Ru-103 9.45E+02 7.33E-04 9.91E-01 1.38E+08 1.33E+00 3.83E+07 Ru-105 4.43E+00 1.56E-01 1.53E-01 1.71E+08 1.64E+00 5.21E+07 Ru-106 8.83E+03 7.85E-05 9.99E-01 4.52E+07 4.35E-01 1.43E+07 Ag-ll0m 6.OOE+03 1.16E-04 9.99E-01 3.22E+08 3.10E+00 1.41E+08 Sn-113 2.76E+03 2.51E-04 9.97E-01 3.08E+06 2.96E-02 4.28E+05 Sb-124 1.45E+03 4.80E-04 9.94E-01 1.59E+08 1.53E+00 8.31E+07 Sb-125 2.43E+04 2.85E-05 1.OOE+00 1.21E+08 1.16E+00 3.20E+07 Te-125m 1.39E+03 4.98E-04 9.94E-01 3.OOE+05 2.88E-03 1.17E+04 Te-127m 2.62E+03 2.65E-04 9.97E-01 1.33E+04 1.28E-04 6.29E+03 Te-127 9.35E+00 7.41E-02 4.11E-01 1.97E+06 1.89E-02 4.14E+05 Te-129m 8.07E+02 8.59E-04 9.90E-01 5.17E+06 4.97E-02 1.95E+06 Te-129 1.16E+00 5.98E-01 7.69E-04 1.58E+07 1.52E-01 4.02E+06 Te-131m 3.OOE+01 2.31E-02 7.58E-01 2.17E+08 2.09E+00 7.37E+07 Te-131 4.17E-01 1.66E+00 2.14E-09 1.50E+08 1.44E+00 2.58E+07 Te-132 7.82E+01 8.87E-03 8.99E-01 1.39E+08 1.34E+00 1.69E+07 1-130 1.24E+01 5.60E-02 5.10E-01 4.13E+08 3.97E+00 1.41E+08 1-131 1.93E+02 3.59E-03 9.58E-01 1.55E+08 1.49E+00 3.21E+07 1-132 2.30E+00 3.01E-01 2.69E-02 3.31E+08 3.18E+00 1.30E+08 1-133 2.08E+01 3.33E-02 6.71E-01 1.39E+08 1.34E+00 4.28E+07 1-134 8.77E-01 7.91E-01 7.58E-05 3.08E+08 2.96E+00 1.31E+08 1-135 6.62E+00 1.05E-01 2.84E-01 1.03E+08 9.90E-01 5.82E+07 Cs-134 1.80E+04 3.85E-05 1.00E+00 2.60E+08 2.50E+00 9.68E+07 Cs-136 3.17E+02 2.19E-03 9.74E-01 3.37E+08 3.24E+00 1.1lE+08 Cs-137 2.65E+05 2.62E-06 1.00E+00 1.04E+08 1.00E+00 3.90E+07 Cs-138 5.37E-01 1.29E+00 1.86E-07 1.15E+08 1.lIE+00 8.43E+07 Ba-139 1.39E+00 5.OOE-01 2.46E-03 2.34E+07 2.25E-01 2.17E+06 Ba-140 3.07E+02 2.26E-03 9.73E-01 6.01E+07 5.78E-01 1.45E+07 Ba-141 3.05E-01 2.27E+00 1.43E-12 2.53E+08 2.43E+00 5.42E+07 Ba-142 1.78E-01 3.89E+00 5.54E-21 1.47E+08 1.41E+00 4.44E+07 La-140 4.02E+01 1.73E-02 8.13E-01 1.53E+08 1.47E+00 9.06E+07 La-142 1.59E+00 4.36E-01 5.35E-03 9.59E+07 9.22E-01 7.75E+07 Ce-141 7.80E+02 8.89E-04 9.89E-01 6.11E+07 5.88E-01 4.29E+06 Ce-143 3.30E+01 2.10E-02 7.77E-01 9.60E+07 9.23E-01 1.90E+07 Ce-144 6.82E+03 1.02E-04 9.99E-01 1.30E+07 1.25E-01 7.96E+05 Pr-143 3.25E+02 2.13E-03 9.75E-01 1.08E+02 1.04E-06 5.27E-01 Pr-144 2.88E-01 2.40E+00 2.96E-13 1.68E+06 1.62E-02 1.14E+06 Nd-147 2.63E+02 2.63E-03 9.69E-01 2.86E+07 2.75E-01 8.08E+06 Hf-181 1.02E+03 6.80E-04 9.92E-01 2.08E+08 2.OOE+00 4.14E+07 W-187 2.38E+01 2.91E-02 7.05E-01 1.04E+08 1.00E+00 3.09E+07 Np-239 5.65E+01 1.23E-02 8.63E-01 1.13E+08 1.09E+00 1.01E+07 2-22

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 Page 3 of 3 TABLE 2.1-4 Nuclide Parameters (continued)

Half-Life X Sensitivity Sensitivity Nuclide (hr) (hr-l) e-Xt (cpm/jICi/ml) Slope TB Bldg.

Drain Only (cpm/IiCi/ml)

Ar-41 1.83E+00 3.78E-01 1.07E-02 9.28E+07 8.92E-01 4.51E+07 Kr-83m 1.83E+00 3.78E-01 1.07E-02 0.00E+00 0.00E+00 0.00E+00 Kr-85 9.40E+04 7.37E-01 1.00E+00 6.20E+05 5.96E-03 1.75E+05 Kr-85m 4.48E+00 1.55E-01 1.56E-01 1.20E+08 1.15E+00 1.12E+07 Kr-87 1.27E+00 5.45E-01 1.44E-03 9.19E+07 8.84E-01 3.22E+07 Kr-88 2.83E+00 2.45E-01 5.31E-02 7.49E+07 7.20E-01 5.19E+07 Kr-89 5.27E-02 1.32E+01 2.58E-69 1.39E+08 1.34E+00 6.52E+07 Kr-90 8.95E-03 7.72E+01 0.00E+00 1.59E+08 1.53E+00 5.43E+07 Xe-131m 1.70E+04 2.45E-03 9.71E-01 2.62E+06 2.52E-02 2.21E+05 Xe-133 1.23E+02 5.51E-03 9.36E-01 9.90E+04 9.52E-04 9.33E+03 Xe-133m 5.25E+01 1.32E-02 8.53E-01 1.59E+07 1.53E-01 2.02E+06 Xe-135 9.12E+00 7.60E-02 4.02E-01 1.47E+08 1.41E+00 2.10E+07 Xe-135m 2.57E-01 2.70E+00 8.43E-15 1.14E+08 1.10E+00 3.30E+07 Xe-137 6.38E-02 1.09E+01 2.57E-57 4.85E+07 4.66E-01 1.32E+07 Xe-0138 2.35E-01 2.95E+00 4.25E-16 1.20E+08 1.15E+00 4.25E+07 Notes to Table 2.1-4 Sensitivity 80% of weighted response to 100 - 1400 keY gammas for offline and an adjacent to line monitor which are sodium iodide (NaI) detectors (reference GA Manual E-115-904, June 1980, and Figure 5, Expected Energy Response Normalized for one gamma per disintegration, Drawing 0360-8934 Rev A, page 14, respectively). Abundances for each gamma from "Radioactive Decay Tables" by David C.

Kocher (Report DOE/TIC-11026, Washington, D.C., 1981)

Slope The Liquid Effluent Monitor Gamma Sensitivities for nuclide "i", relative to Cs-137. To make nuclide "i" relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity. This column does not apply to TB Drains monitor.

2-23

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 3 TABLE 2.2-1 AiVALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT 730 -x t

=1.14E + 05 (730 + 21BF.) DF. *e i A.

iT, r,p D 1 lI w

(mrem/hr per VCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0. OOE+00 8. 54E-01 8. 54E-01 8. 54E-01 8. 54E-01 8. 54E-01 8. 54E-01 C-14 3 13E+04 6. 27E+03 6. 27E+03 6. 27E+03 6. 27E+03 6. 27E+03 6. 27E+03 NA-24 2. 40E+02 2. 40E+02 2. 40E+02 2. 40E+02 2. 40E+02 2 . 40E+02 2. 40E+02 P-32 4. 52E+07 2.81E+06 1.75E+06 0. OOE+00 0. OOE+00 0. OOE+00 5. 08E+06 CR-51 0. 00E+00 0. OOE+00 1.28E+00 7 .63E-01 2. 81E-01 1. 69E+00 3. 21E+02 MN-54 0 00E+00 4.41E+03 8.41E+02 0. OOE+00 1. 31E+03 0. OOE+00 1. 35E+04 MN-56 0 OOE+00 4.44E+00 7.87E-01 0. OOE+00 5. 63E+00 0. OOE+00 1. 42E+02 FE-55 6. 76E+02 4. 67E+02 1. 09E+02 0. OOE+00 0.OOE+00 2 .60E+02 2 .68E+02 FE-59 1. 06E+03 2.49E+03 9. 54E+02 0 OOE+00 0. OOE+00 6. 95E+02 8. 29E+03 CO-57 0. OOE+00 2. 20E+01 3 .66E+01 0. OOE+00 0. OOE+00 0. OOE+00 5. 58E+02 CO-58 0. OOE+00 9.33E+01 2. 09E+02 0 . OOE+00 0. OOE+00 0. OOE+00 1. 89E+03 CO-60 0. 00E+00 2.69E+02 5. 94E+02 0. OOE+00 0. OOE+00 0. OOE+00 5. 06E+03 NI-63 3 .20E+04 2.21E+03 1. 07E+03 0. OOE+00 0. OOE+00 0. OOE+00 4. 62E+02 NI-65 4. 76E+00 6.19E-01 2. 82E-01 0. OOE+00 0. OOE+00 0. OOE+00 1. 57E+01 CU-64 0. OOE+00 5. 45E+00 2 .56E+00 0. OOE+00 1.37E+01 0. OOE+00 4. 64E+02 ZN-65 2 32E+04 7.39E+04 3 .34E+04 0. OOE+00 4. 94E+04 0. OOE+00 4. 65E+04 ZN-69 6 .25E-03 1.20E-02 8.32E-04 0. OOE+00 7. 77E-03 0. OOE+00 1. 80E-03 ZN-69M 4. 46E+02 1. 07E+03 9.79E+01 0. OOE+00 6. 48E+02 0. OOE+00 6. 54E+04 BR-82 0. OOE+00 0. OOE+00 1.81E+03 0. OOE+00 0. OOE+00 0. OOE+00 2. 07E+03 BR-83 0. OOE+00 0.OOE+00 1.24E+00 0. OOE+00 0. OOE+00 0. OOE+00 1. 79E+00 BR-84 0. OOE+00 0. OOE+00 8. 07E-06 0. OOE+00 0. OOE+00 0. OOE+00 6. 33E-11 BR-85 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 RB-86 0. OOE+00 9. 95E+04 4. 63E+04 0. OOE+00 0. OOE+00 0. OOE+00 1. 96E+04 RB-88 0. OOE+00 1. 94E-10 1. 03E-10 0 . OOE+00 0. OOE+00 0. OOE+00 2. 67E-21 RB-89 0. OOE+00 1. 62E-12 1.14E-12 0. OOE+00 0. OOE+00 0. OOE+00 9. 43E-26 SR-89 2. 38E+04 0. OOE+00 6. 84E+02 0. OOE+00 0. OOE+00 0. OOE+00 3. 82E+03 SR-90 5. 91E+05 0. OOE+00 1.45E+05 0.OOE+00 0. OOE+00 0. OOE+00 1. 71E+04 SR-91 1. 84E+02 0. OOE+00 7.43E+00 0. OOE+00 0. OOE+00 0. OOE+00 8 .77E+02 SR-92 7 .84E+00 0. OOE+00 3.39E-01 0.OOE+00 0. OOE+00 0. OOE+00 1. 55E+02 2-24

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 2 of 3 TABLE 2.2-1 (Continued)

Aj, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per lCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-90 5. 57E-01 0. OOE+00 1.49E-02 0. OOE+00 0. OOE+00 0. OOE+00 5.91E+03 Y-91M 2.61E-07 0. OOE+00 1. OIE-08 0. OOE+00 0. OOE+00 0. OOE+00 7 . 67E-07 Y-91 9.24E+00 0. OOE+00 2.47E-01 0. OOE+00 0. OOE+00 0 OOE+00 5. 09E+03 Y-92 5.29E-03 0. OOE+00 1. 55E-04 0. OOE+00 0. OOE+00 0. OOE+00 9. 27E+01 Y-93 7. 75E-02 0. OOE+00 2. 14E-03 0. OOE+00 0. OOE+00 0. OOE+00 2.46E+03 ZR-95 4.20E-01 1.35E-01 9 .12E-02 0. OOE+00 2. 11E-01 0 OOE+00 4. 27E+02 ZR-97 1.42E-02 2 .87E-03 1.31E-03 0. OOE+00 4. 34E-03 0. OOE+00 8. 90E+02 NB-95 4. 43E+02 2.47E+02 1. 33E+02 0. OOE+00 2.44E+02 0. OOE+00 1. 50E+06 NB-97 3. 70E-03 9.36E-04 3.42E-04 0. OOE+00 1.09E-03 0. OOE+00 3.45E+00 MO-99 0 OOE+00 1. 14E+02 2.17E+01 0. OOE+00 2 .58E+02 0. OOE+00 2 .64E+02 TC-99M 2 . 60E-03 7.35E-03 9. 36E-02 0. OOE+00 1. 12E-01 3 .60E-03 4.35E+00 TC-101 5. 81E-18 8.37E-18 8.21E-17 0 . OOE+00 1. 51E-16 4. 28E-18 2. 52E-29 RU-103 5. 49E+00 0. OOE+00 2 .37E+00 0. OOE+00 2. 10E+01 0. OOE+00 6. 41E+02 RU-105 7. 07E-02 0. 00E+00 2 .79E-02 0. OOE+00 9.13E-01 0. OOE+00 4. 32E+01 RU-106 8. 23E+01 0. OOE+00 1.04E+01 0. OOE+00 1. 59E+02 0. OOE+00 5. 33E+03 AG-11OM 9. 55E-01 8. 83E-01 5.25E-01 0. OOE+00 1.74E+00 0. OOE+00 3 . 60E+02 SB-124 2 33E+01 4.40E-01 9.24E+00 5. 65E-02 0. OOE+00 1. 82E+01 6. 62E+02 SB-125 1. 50E+01 1. 67E-01 3 .57E+00 1. 52E-02 0. OOE+00 1. 16E+01 1. 65E+02 TE-125M 2 .57E+03 9. 32E+02 3.44E+02 7. 73E+02 1. 05E+04 0. OOE+00 1. 03E+04 TE-127M 6. 51E+03 2.33E+03 7. 94E+02 1. 66E+03 2. 65E+04 0. OOE+00 2.18E+04 TE-127 4. 36E+01 1. 57E+01 9.44E+00 3 .23E+01 1.78E+02 0. OOE+00 3. 44E+03 TE-129M 1. 10E+04 4. 10E+03 1.74E+03 3. 77E+03 4. 59E+04 0. OOE+00 5. 53E+04 TE-129 2. 33E-02 8. 76E-03 5. 68E-03 1.79E-02 9. 80E-02 0. OOE+00 1.76E-02 TE-131M 1. 27E+03 6. 19E+02 5. 16E+02 9. 80E+02 6.27E+03 0. OOE+00 6. 14E+04 TE-131 4. 07E-08 1.70E-08 1.28E-08 3.35E-08 1.78E-07 0. OOE+00 5.76E-09 TE-132 2 . 19E+03 1.41E+03 1. 33E+03 1. 56E+03 1. 36E+04 0 OOE+00 6. 69E+04 1-130 1. 62E+01 4.77E+01 1. 88E+01 4. 05E+03 7. 45E+01 0. OOE+00 4. 11E+01 1-131 1. 67E+02 2.39E+02 1. 37E+02 7. 84E+04 4. 10E+02 0. OOE+00 6. 31E+01 1-132 2. 29E-01 6. 12E-01 2.14E-01 2. 14E+01 9.75E-01 0 OOE+00 1. 15E-01 1-133 4. OOE+01 6. 95E+01 2. 12E+01 1. 02E+04 1.21E+02 0. OOE+00 6.25E+01 1-134 3 .37E-04 9. 15E-04 3.27E-04 1. 59E-02 1.46E-03 0. OOE+00 7 . 98E-07 1-135 5.29E+00 1.38E+01 5.11E+00 9.13E+02 2.22E+01 0.OOE+00 1.56E+01 2-25

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 3 of 3 TABLE 2.2-1 (Continued)

Ai, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per pCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI CS-134 2. 99E+05 7. 10E+05 5. 81E+05 0. OOE+00 2.30E+05 7. 63E+04 1. 24E+04 CS-136 3. 05E+04 1. 20E+05 8. 65E+04 0. OOE+00 6. 69E+04 9. 17E+03 1. 37E+04 CS-137 3 .83E+05 5.23E+05 3. 43E+05 0. OOE+00 1.78E+05 5. 91E+04 1. 01E+04 CS-138 4.92E-05 9.72E-05 4. 82E-05 0.00E+00 7. 14E-05 7 06E-06 4. 15E-10 BA-139 3.72E-03 2.65E-06 1. 09E-04 0. 00E+00 2. 48E-06 1. 50E-06 6. 60E-03 BA-140 3 . 08E+02 3. 86E-01 2 02E+01 0. OOE+00 1.31E-01 2. 21E-01 6. 33E+02 BA-141 1. 05E-12 7. 94E-16 3. 55E-14 0. OOE+00 7.38E-16 4. 51E-16 4. 95E-22 BA-142 1. 84E-21 1. 89E-24 1. 16E-22 0. OOE+00 1. 60E-24 1. 07E-24 0. OOE+00 LA-140 1.34E-01 6. 75E-02 1. 78E-02 0. OOE+00 0. OOE+00 0. OOE+00 4. 96E+03 LA-142 4.51E-05 2. 05E-05 5 11E-06 0. OOE+00 0. OOE+00 0. OOE+00 1. 50E-01 CE-141 7.76E-02 5.24E-02 5 .95E-03 0. OOE+00 2. 44E-02 0. OOE+00 2. 01E+02 CE-143 1. 07E-02 7.94E+00 8. 79E-04 0. OOE+00 3 . 50E-03 0 OOE+00 2. 97E+02 CE-144 4. 08E+00 1.71E+00 2. 19E-01 0. OOE+00 1. 01E+00 0. OOE+00 1. 38E+03 PR-143 5.91E-01 2.37E-01 2 . 93E-02 0. OOE+00 1. 37E-01 0 OOE+00 2 .59E+03 PR-144 5.88E-16 2.44E-16 2 . 99E-17 0. OOE+00 1. 38E-16 0. OOE+00 8. 46E-23 ND-147 4. 02E-01 4. 64E-01 2. 78E-02 0. OOE+00 2 .71E-01 0. OOE+00 2.23E+03 W-187 2. 10E+02 1.75E+02 6. 12E+01 0. OOE+00 0. OOE+00 .OOE+000 5. 74E+04 NP-239 3.08E-02 3.03E-03 1.67E-03 0. OOE+00 9. 44E-03 0. OOE+00 6. 21E+02 2-26

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 2.1-1 Liquid Waste Processing Flow Diagram 2-27

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 2.1-2 Liquid Effluent Flow Stream Diagram Legend Tank or Basin R Radiation Effluent Monitor 2-28

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 2.1-3 Normal Service Water Flow Diagram Normal Service Water REM - Radiation Effluent Monitor NSW - Normal Service Water NOTE: For detailed flow drawings of the Service Water System, refer to the FSAR 2-29

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 2.1-4 Other Liquid Effluent Pathways Turbine Building Floor Drains Outside Tank Area Drains Effluent Line Effluent Line

Turbine Building Floor Drains Effluent can be Diverted to the Secondary Waste Treatment System

- Outside Tank Area Drains Effluent can be Diverted to the Liquid Radwaste Treatment System 2-30

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.0 GASEOUS EFFLUENTS At SHNPP there are four gaseous effluent discharge points: Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A. During refueling outages the Equipment Hatch is removed and has potential airborne particulate releases. These are shown in Figures 3.1, 3.2, and 3.3 along with their tributaries. All gaseous effluent releases at the plant are considered ground releases.

3.1 Monitor Alarm Setpoint Determination (ODCM Operational Requirement 3.3.3.11)

This section provides the methodology for stack effluent monitor setpoints to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrem/year to the skin as specified in ODCM Operational Requirement 3.11.2.1. The 500 mrem/year to the whole body or 3000 mrem/year to the skin limits are more conservative than the 10 CFR 50.73 limits concerning airborne radioactivity release concentrations to unrestricted areas, and therefore the setpoint methodology set forth here is based on the limits of 500 mrem/year to the whole body or 3000 mrem/year to the skin.

The radioactivity effluent monitors for each stack and for specific effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.

Gamma spectroscopy analysis of the gas sample should provide the nuclide identification and activity. However, in the case where the noble gas activities are < LLD the relative nuclide composition can be assumed from the GALE code activities for projected normal operating releases (Table 3.1-1). The GALE code is used to establish a default setpoint for each vent stack. This setpoint will be used as a "fixed" setpoint until a more conservative setpoint is calculated, using either a different assumed mix or actual sample results.

3-1

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code)

The following methodology is the default setpoint for the continuous release vent stacks based on conservative assumptions of mix (GALE code) and maximum stack flow rate.

1. Determine the noble gas radionuclide activity (Qi) in PCi, and the activity release rate " in (ICi/sec for each nuclide "i" . is the release rate of nuclide "i" in gaseous effluent from discharge point "v",

in ICi/sec.

Qi = Xv Ci

Fv

duration

28316.85 (3.1-1a) and

- v Ci e Fv e 28316.85 / 60 (3.1-1b) where:

v = index over all vent stacks Ci= concentration of nuclide, in pCi/cc

= the GALE code activities from Table 3.1-1.

Fv= effluent release rate or vent flow rate in cfm

= the maximum effluent design flow rate at the point of discharge (acfm) from Table 3.1-3.

duration - duration of release, in minutes 28316.85 = conversion factor for cc/ft 3 60 = seconds per minute 3-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release.

Qm-wb = (X / Q) [Yi Ki *] (3.1-2a) and Qm-s = (X / Q) [Yi (Li + I.IMi) §l] (3.1-2b) where:

i = index over all nuclides Ki the total body dose factor due to gamma emissions for noble gas radionuclide i (in mrem/yr per .iCi/m3), from Table 3.1-2.

Li The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per JICi/m 3 )

Mi The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per JICi/m 3 ). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Li+l.lMi = Skin dose factor (mrem/yr per ýtCi/m3), from Table 3.1-2 X/Q = The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/M3 )

6.1E-06 sec/mi3 from Table A-i, Appendix A 3-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)

3. Determine the ratio of dose rate limit to dose rate.

Whole Body ratio 500 (3.1-3a)

Qm-wb and Skin ratio - 3000 (3.1-3b)

Qm-s where:

500 = site dose rate limit for whole body in mrem/year.

3000 site dose rate limit for skin in mrem/year.

4. Determine Sm-a, the maximum concentration setpoint in ýtCi/cc, and RRmax the maximum release rate setpoint in gCi/sec for the monitor.

Smax = (fs faloc,

nratio Y-Ci ) + Bkg (3.1-4a) and RR = Sx

Fv

28316.852 / 60 (3.1-4b) where f= safety factor for the discharge point

- 0.5 falloc = dose rate allocation factor for the discharge point

= fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases.

These values are based on the percentage of an individual stack flow to the total stack flow and are in Table 3.1-3.

nratio = lesser of the ratios Bkg = Monitor background, in pCi/cc

= 0 for calculation of default setpoint.

3-4

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)

Using the GALE code activities from Table 3.1-1 and the maximum effluent design flow rate, continuous release stack maximum setpoints in pCi/cc and pCi/sec are determined. These values will be used as default values for the stack monitors. Based on sampling and analysis, the setpoint will be recalculated. If the sample analysis setpoint is higher than the default setpoint, the setpoint will not be changed. If the sample analysis setpoint is lower than the default, the setpoint will be changed to reflect the more conservative setpoint. When the setpoint changes again, the more conservative setpoint, comparing the default (GALE code) and sample analysis, will be used.

5. Determine Saiert, the gas channel alert alarm setpoint in pCi/cc, and RRaiert the gas channel alert alarm release rate setpoint in ýtCi/sec.

Salert [ (Smax - Bkg) Af] + Bkg (3.1-5a) and RRalert [(RRmax - Bkgrr) AfI + Bkgrr (3.1-5b) where:

Af A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.

Bkgrr Bkg 9 F, o 28316.85 / 60 3-5

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 3.1.2 Monitor Setpoints Using Sample Results In Stacks 1 and 5, the potential exists for batch releases concurrent with the normal continuous ventilation flow of effluents. The sources of batch releases for the Plant Vent Stack 1 include containment normal and pre-entry purge and pressure relief. Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT). In these cases, the monitor setpoint must reflect the contribution of both the continuous and batch sources.

The following methodology will calculate a setpoint for the continuous release vent stacks based on actual sample results and for batch releases occurring concurrently with continuous releases.

1. Determine the noble gas radionuclide activity (Qi) in ýtCi, and the activity release rate - in ýtCi/sec for each nuclide "i". is the average release rate of nuclide "i" in gaseous effluent from discharge point "v", in ýICi/sec. Noble gases may be averaged over a period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Qi = Yv Ci

F,

duration

28316.85 (3.2-la) and S *v, Ci F,

28316.85 / 60 (3.2-1b) where:

v = index over all vent stacks Ci = concentration of nuclide, in IICi/cc

= the measured concentration from a stack effluent sample or pre-release sample. If there is no activity in the sample, then the GALE code activities from Table 3.1-1 will be used.

WGDTs

(ýiCi/cc from analysis of WGDT) (6.45 E-05) +

(pCi/cc from analysis/GALE Code of Vent Stack 5)(0.9999)

Containment Normal Purge (Batch)

(pCi/cc from analysis of Containment) (3.83 E-03) +

(pCi/cc from analysis/GALE Code of PV Stack 1) (0.9962)

Containment Preentry Purge (Batch)

(pCi/cc from analysis of Containment) (8.67 E-02) +

(pCi/cc from analysis/GALE Code of PV Stack 1) (0.9133) 6.45 E-05 = Dilution factor WGDT = (15 scfm)/(232,500 scfm + 15 scfm) 0.9999 = Dilution factor Vent Stack 5

= 232,500 scfm/(232,500 scfm + 15 scfm) 3.83 E-03 = Dilution factor Normal Purge

= 1500 scfm/(390,000 scfm + 1500 scfm) 0.9962 = Dilution factor PV-I = 390,000 scfm/(390,000 scfm + 1500scfm) 8.67 E-02 = Dilution factor Preentry Purge (Batch)

= 37,000 scfm/(390,000 scfm + 37,000 scfm) 0.9133 = Dilution factor PV-l

= 390,000 scfm/(390,000 scfm + 37,000 scfm) 3-6

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.1.2 Monitor Setpoints Using Sample Results (continued)

Fv = effluent release rate or vent flow rate in CFM for continuous releases, the measured effluent flow rate or the maximum effluent design flow rate at the point of release (acfm) from Table 3.1-3.

for batch releases, the release flow rate, in acfm 1,500 scfm for containment normal purge + 390,000 scfm from Plant Vent Stack 1 37,000 scfm for containment preentry purge + 390,000 scfm from Plan Vent Stack 1 15 scfm for Waste Gas Decay Tank pre release permits

+ 232,500 scfm from Vent Stack 5 for posting Waste Gas Decay Tank and Containment Pressure releases the following is used for effluent accountability.

2.26E + 06 ( APc ) (2730) 14.7 Tc t

for a containment pressure release APt 2730 600 (p) (- )

14.7 Tt t

for a Waste Gas Decay Tank release where:

3 2.26E+06 and 600 are the volumes in ft of the containment and decay tank, respectively, and T,, Tt, AP., and APt are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 psi = 1 atmosphere pressure t = Length of release, min APC,APpt change in pressure (psig) following the release of the containment or decay tank 0

273 K = 0°C 0 0 Tt,Tc= 273 K + C duration = duration of release, in minutes 3

28316.85 = conversion factor for cc/ft 3-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Setpoints Using Sample Results (continued)

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release by summing together the dose rates for this release with all concurrent releases for the time of the release.

Qm-wb (X / Q) Iv [Yi Ki *] (3.2-2a) and

= (X / Q) IV [1i (Li + I.IMi) *] (3.2-2b) where:

i = index over all radionuclides Ki = the total body dose factor due to gamma emissions for noble gas radionuclide i (mrem/yr per ýtCi/m3), from Table 3.1-2.

Li = The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per lICi/m 3 )

Mi = The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per pCi/mi3 ) . A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose 3

Li+l.iMi = Skin dose factor (mrem/yr per ýtCi/m ) from Table 3.1-2 X/Q The highest calculated annual average relative concentration 3

for any sector at or beyond the exclusion boundary (sec/m )

6.1E-06 sec/mi3 from Table A-l, Appendix A 3-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Setpoints Using Sample Results (continued)

3. Determine the ratio of dose rate limit to dose rate.

Whole Body ratio = 500 (3.2-3a)

Qm-wb and Skin ratio = 3000 (3.2-3b)

QM-s where:

500 = site dose rate limit for whole body in mrem/year.

3000 = site dose rate limit for skin in mrem/year.

4. Determine S.., the maximum concentration setpoint in pCi/cc, and RR.. the maximum release rate setpoint in pCi/sec for the monitor.

Smax = (fs a falloc 9 nratio Y-Ci ) + Bkg (3.2-4a) and RRmax Smax

Fv

28316.852 / 60 (3.2-4b) where:

fs = safety factor for the discharge point

= 0.5 falloc = dose rate allocation factor for the discharge point

- fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases.

These values are based on the percentage of an individual stack flow to the total stack flow and are in Table 3.1-3.

nratio = lesser of the ratios Bkg = Monitor background, in pCi/cc

= measured background at time of release or 0.

3-9

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Setpoints Using Sample Results (continued)

5. Determine Saiert, the gas channel alert alarm setpoint in pCi/cc, and RRaiert the gas channel alert alarm release rate setpoint in pCi/sec.

Salert = [(Sm.- Bkg) Af] + Bkg (3.2-5a) and RRalert [ (RR.ax - Bkgrr) Af ] + Bkgrr (3.2-5b) where:

Af A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.

Bkgrr = Bkg 9 F,

28316.85 / 60 3-10

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.3 Effluent Monitoring During Hogging Operations If the reactor has been shut down for greater than 30 days, the condenser vacuum pump discharge during initial hogging operations at plant start-up and prior to turbine operation may be routed as dual exhaust to (1) the Turbine Vent Stack 3A and (2) the atmosphere directly. In this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).

A conservative effluent channel setpoint has been established for Vent Stack 3A.

The monitor setpoint should be reduced proportionately to the estimated fraction of the main condenser effluent flowing directly to the atmosphere.

3-11

Shearon *ris Nuclear Power Plant (SHNPP) 9 Novembe 001 Offsite Dose Calculation Manual (ODCM) Rev. 14 Table 3.1-1 GASEOUS SOURCE TERMS(a'b)

Condenser Plant Vent Vacuum Pump WPB WPB Containment Ventilation Ventilation Ventilation Ventilation Purge or WGDT Flow Flow Flow Flow (C) Pressure Relief Release via via via via via via Stack 1 Stack 3A Stack 5 Stack 5A Stack 1 Stack 5 Ci % Rel. Ci % Rel. Ci % Rel. Ci % Rel. Ci % Rel. ci(d) % Rel.

Nuclide (gCi/cc) Mix (gCi/cc) Mix (pICi/cc)

Mix (pICi/cc) Mix Mix (4Ci/cc) Mi-x (jiCi/cc)

Kr-85m 5.17E-10 6.52 4.70E-9 9.52 0 0 1.94E-9 6.52 1.01E-7 3.79 0 0 Kr-85 0 0 0 0 1 . 60E-7 97.05 0 0 3.95E-8 1.49 2.22E-5 100.00 Kr-87 5.17E-10 6.52 4.70E-9 9.52 0 0 1.94E-9 6.52 3.59E-8 1.35 0 0 Kr-88 1.03E-09 13.04 7.04E-9 14.29 0 0 3.87E-9 13.04 1.29E-7 4.87 0 0 Xe-131m 3.45E-10 4.35 0 0 4. 86E-9 2.95 1.29E-9 4.35 2.16E-7 8.12 0 0 Xe-133m 0 0 0 0 0 0 0 0 5.57E-8 2.10 0 Xe-133 1. 90E-09 23.91 1.17E-8 23.81 0 0 7.10E-9 23.91 1.31E-6 49.39 0 0 Xe-135m 5.17E-10 6.52 2 .35E-9 4.76 0 0 1.94E-9 6.52 7.19E-9 0.27 0 0 Xe-135 2. 58E-9 32.61 1 . 64E-8 33.33 0 0 9.68E-9 32.61 7.55E-7 28.42 0 0 Xe-138 5.17E-10 6.52 2. 35E-9 4.76 0 0 1. 94E-9 6.52 5. 39E-9 0.20 0 (a) Source terms are from SHNPP FSAR Table 11.3.3-1 and not actual releases.

Values apply only to routine releases and not emergency situations.

(b) (uCi/cc) = (Ci/yr) (yr/5.256E5min) (lE6JICi/Ci) (ft3/28320cc)

(Flow Rate ft3/min) 7a (c) Source term for this effluent stream not presented with FSAR. RAB mix assumed.

(d) Maximum Effluent Design Flow Rates:

Plant Vent Ventilation via Stack 1 = 390,000 CFM

Condenser Vacuum Pump Ventilation via Stack 3A = 28,620 CFM

WPB Ventilation via Stack 5 = 232,500 CFM

WPB Ventilation via Stack 5A = 103,050 CFM

Containment Purge or Pressure Relief via Stack 1 = 37,000 CFM

WGDT Release via Stack 5 = 15 CFM 3-12

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.1-2 DOSE FACTORS AND CONSTANTS Whole Body Dose Skin Dose Factor Factor (Ki) (Li + 1.1 Mi)

Radionuclide (mrem/yr/I Ci/m3 (mrem/yr/ýtCi/m)3 Kr-83m 7.56E-02 2.12E+01 Kr-85m 1.17E+03 2.81E+03 Kr-85 1.61E+01 1.36E+03 Kr-87 5.92E+03 1.65E+04 Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 2.91E+04 Kr-90 1.56E+04 2.52E+04 Xe-131m 9.15E+01 6.48E+02 Xe-133m 2.51E+02 1.35E+03 Xe-133 2.94E+02 6.94E+02 Xe-135m 3.12E+03 4.41E+03 Xe-135 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.43E+04 Ar-41 8.84E+03 1.29E+04

Regulatory Guide 1.109, Rev. 1, Table B-1, multiplied by (1.0+E6 pCi/IICi).

3-13

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.1-3 GASEOUS MONITOR PARAMETERS I PVS-I TBVS-3A WPBVS-5 WPBVS-5A Maximum effluent design flow 390,000 28,620 232,500 103,050 rate, (acfm)

I Flow Allocation Factor 0.517 0.038 0.308 0.137

[fa IIoc]

3-14

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.2 Postrelease Compliance with 10CFR20-Based ODCM Operational Requirement 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors setpoints are utilized to show prerelease compliance with ODCM Operational Requirement 3.11.2.1. However, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the setpoints could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the event that if the high alarm setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded the dose rate limits of ODCM Operational Requirement 3.11.2.1.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin.

Based upon NUREG-0133, the following equations are used to show compliance:

Ki (X / Q)v, lv

500 mrem/yr (3.2-1)

(Li + L.lMi) (X / <_v3000 mrem/yr

(3.2-2 1

where:

(X/Q)V The highest calculated annual average relative concentration for long-term vent stack releases for areas at or beyond the exclusion boundary sec/m3.

6.1E-06 sec/mr3 from Table A-l, Appendix A, for ground-level releases in the S sector at the exclusion boundary.

Ki The total body dose factor due to gamma emissions for noble gas radionuclide "i," mrem/year per ýICi/m 3 . Table 3.2-3.

Li The skin dose factor due to beta emissions for noble gas radionuclide "i," mrem/year per p.Ci/m 3 . Table 3.2-3.

Mi The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad/year per 4Ci/m 3 . Table 3.2-3.

3-15

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.2.1 Noble Gases (continued) 1.1 The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest. Converts mrad to mrem (Reference NUREG-0133). The factors (Li + 1.1 Mi) are tabulated in Table 3.1-2.

=lThe release rate of radionuclide "i" in gaseous effluents Iv from all plant vent stacks (jICi/sec).

The determination of the controlling location for implementation of dose rate limits for noble gas exposure is a function of the historical annual average meteorology.

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is < LLD, then the GALE code, historical data for the mix, or a Xe-133 / Kr-85 LLD mix for that analysis will be used to demonstrate compliance.

The release rate is derived from either the actual flow rate or the default flow rate and the known or assumed mix.

Release Rate (jICi/sec) = Flow (cc/sec)

Concentration (jICi/cc)

The noble gas radionuclide mix was based upon source terms calculated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1. They are reproduced in Table 3.2-1 as a function of release point.

The X/Q value utilized in the equations is the highest long-term annual average relative concentration(X/Q), in the unrestricted area for the period 1976 -

1987. Long-term annual average (X/Q)v values at other special locations identified by the Land Use Census (see Operational Requirement 3.12.2) are presented in Appendix A. A description of their derivation is also provided in Appendix A.

To select the limiting location for ground-level releases, long-term annual average (X/Q)v values were calculated assuming no decay, undepleted transport to the exclusion boundary. These values are given in Table A-1, Appendix A . The maximum exclusion boundary (X/Q), for ground-level releases occurs in the S sector. Therefore, the limiting location for implementation of the dose rate limits for noble gases is considered to be the exclusion boundary (1.36 miles) in the S sector.

Values for Ki, Li, and Mi which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with ODCM Operational Requirement 3.11.2 are presented in Table 3.2-3. These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert mrad/pCi to mrad/JLCi for use in Equations 3.2-1 and 3.2-2.

3-16

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.2.2 Radioiodines and Particulates The basis for ODCM Operational Requirement 3/4.11.2.1 states that the dose rate to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and particulates with half-lives Ž 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG-0133, the following is used to show compliance:

[Pi / v flV]

1500 mrem / yr (3.2-3) where:

PiI The dose parameter for radionuclides other than noble gases for the inhalation pathway, mrem/yr per [tCi/m 3 , from Table 3.2-4.

I In the calculation to show compliance with ODCM Operational Requirement 3.11.2.1.b, only the inhalation pathway is considered.

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is < LLD, then no activity is assumed to have been released during the sampling period. The release rate is derived from the flow (actual or default) and the mix.

Release Rate (JICi/sec) = Flow (cc/sec)

Concentration (pCi/cc)

The determination of the controlling exclusion boundary location was based upon the highest exclusion boundary (X/Q)v value. Values for Pi in Eq. 3.2-3 were calculated for a child for various radionuclides for the inhalation pathway using the methodology of NUREG-0133. The Pi values are presented in Table 3.2-

4. A description of the methodology used in calculating the Pi values is presented in Appendix B. The values of Pi reflect, for each radionuclide, the maximum Pi value for any c rgan.

The (X/Q)v value utilized in Equation 3.2-3 is obtained from the tables presented in Appendix A. A description of the derivation of the X/Q values is provided in Appendix A.

3-17

Shearon *ris Nuclear Power Plant (SHNPP) 9 Novembe 004 Offsite Dose Calculation Manual (ODCM) Rev. 17 Table 3.2-1 Releases from the Shearon Harris Nuclear Power Plant (a)

Normal Operation (Curies/year)

Waste Processing Bldg Waste Processing Bldg Condenser Vacuum Pump Exhaust and/or Exhaust via VENT STACK 5A and Turbine Building Waste Gas Decay Tanks (b) RAB/FHB and Containment Exhaust via VENT STACK 5 Exhaust via VENT STACK 1 via VENT STACK 3A NOBLE NORMAL TOTAL GASES SHUTDOWN OPERATIONS CONTAINMENT RAB/FHB TURBINE STACK 3A Kr-85m 0 0 5.6E+01 3 .E+00 0 2.OE+00 6. 1E+01 Kr-85 5. OE+00 5 . 6E+02 2.2E+01 0 0 0 5. 9E+02 Kr-87 0 0 2. OE+01 3. OE+00 0 2.OE+00 2.5E+01 Kr-88 0 0 7.2E+01 6. OE+00 0 3. OE+00 8. 1E+01 Xe-131m 0 1.7E+01 1. 2E+02 2. OE+00 0 1.OE+00 1. 4E+02 Xe-133m 0 0 3. IE+01 0 0 0 3. 10E+01 Xe-133 0 0 7 .3E+02 1.lE+01 0 5.OE+00 7. 5E+02 Xe-135m 0 0 4. OE+00 3 . OE+00 0 1.OE+00 8. OE+00 Xe-135 0 0 4. 2E+02 1.5E+01 0 7.OE+00 4. 4E+02 Xe-138 0 0 3 OE+00 3 . OE+00 0 1.0E+00 7. OE+00 Ar-41 3. 4E+00 (a) Adapted from SHNPP FSAR Table 11.3.3-1 and do not reflect actual release data.

These values are only for routine releases and not for a complete inventory of gases in an emergency.

(b) Waste Gas Decay Tank releases assumed to be after a 90-day decay period.

3-18

Shearon Harris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM) November 2004 Rev. 17 Intentionally left blank.

I 3-19

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES

Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Radionuclide Ki Li Mi Ni (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per 3

tc i/mn ) pci/m3 ) pC i/rn 3 ) pci/m3 )

Kr-83m 7.56E-02 --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.1lE+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents.

3-20

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.2-4 PiI VALUES (INHALATION) FOR A CHILD ISOTOPE pi Value 3

mrem/yr per IICi/m H-3 1.12E+03 P-32 2.60E+06 Cr-51 1.70E+04 Mn-54 1.57E+06 Fe-59 1. 27E+06 Co-58 1.10E+06 Co-60 7.06E+06 Zn-65 9.94E+05 Rb-86 1.98E+05 Sr-89 2.15E+06 Sr-90 1.01E+08 Y-91 2.62E+06 Zr-95 2.23E+06 Nb-95 6.13E+05 Ru-103 6.61E+05 Ru-106 1.43E+07 Ag-110m 5.47E+06 Sn-113 3.40E+05 Sb-124 3.24E+06 Te-127m 1.48E+06 Te-129m 1.76E+06 1-131 1.62E+07 1-132 1.93E+05 1-133 3.84E+06 1-135 7.91E+05 Cs-134 1.01E+06 Cs-136 1.71E+05 Cs-137 9.05E+05 Ba-140 1.74E+06 Ce-141 5.43E+05 Ce-144 1.19E+07 Hf-181 7.95E+05 3-21

Shearon Harris Nuclear Power Plant (SHNPP) November 2001 Offsite Dose Calculation Manual (ODCM) Rev. 14 3.3 COMPLIANCE WITH 10CFR50 The calculations described in Section 3.2 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I for each release. Summation of doses for all releases for the quarter and year are compared to the limits in 10CFR50 Appendix I to ensure compliance.

The SHNPP ODCM calculates the dose to a single maximum (ALARA) individual. The ALARA individual is an individual that "lives" at the site boundary in the sector that has the most limiting long-term average X/Q value.

3-22

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.1 Noble Gases

1. Cumulation of Doses Based upon NUREG-0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following equations:

Dy = 3.17 E - 08 XMi [(X / Q)v Qiv + (X/ q)v iv] (3.3-1) 1vv Dp = 3.17 E- 08 XNi [(X / Q)v Qiv + (X/ q)v Eiv] (3.3-2) 1 where:

Dy = The air dose from gamma radiation, mrad.

Dp = The air dose from beta radiation, mrad.

3.17 E-08 The inverse of the number of seconds in a year (sec/year)-'

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/ýCi/m3). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Ni The air dose factor due to beta emissions for each identified noble gas radionuclide "i," mrad/year per pCi/mi3 . Table 3.2-3.

X/Qv The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack releases (Ž 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/M3 . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 6.1E-06 sec/m3 from Table A-l, Appendix A as the most limiting X/Qv.

X/qv The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack releases (* 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/mi3 . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 6.1E-06 sec/mi3 from Table A-l, Appendix A as the most limiting X/Qv.

Q The total release of noble gas radionuclide "i" in gaseous v

effluents for long term releases (>500 hrs/yr) from all vent stacks (pCi) q . The total release of radionuclide "i" in gaseous releases for v

short-term releases (*500 hours/year) from all vent stacks, (VCi).

3-23

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.1 Noble Gases (continued)

To show compliance with 10CFR50, Expressions 3.3-1 and 3.3-2 are evaluated at the controlling location where the air doses are at a maximum.

At SHNPP the limiting location is the exclusion boundary at 1.36 miles (-2.19 kilometers) in the S sector based upon the tables presented in Appendix A (see Section 3.2.1 earlier). For this document, long-term annual average X/Qv values can be used in lieu of short-term values. See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant.

The determination of the limiting location for implementation of 10CFR50 is a function of parameters such as radionuclide mix and meteorology. To select the limiting location, the highest annual average X/Qv value for ground-level releases is controlling. The only source of short-term releases from the plant vent are containment purges, containment pressure relief, and waste gas decay tank release. Determination of source terms is described in 3.3.1.2.

Values for Mi and Ni, which are utilized in the calculation of the gamma air and beta air doses in Equation 3.3-1 to show compliance with 10CFR50, are presented in Table 3.2-3. These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.OE+06 to convert from mrad/pCi to mrad/4Ci.

The following relationships should hold for SHNPP to show compliance with ODCM Operational Requirement 3.11.2.2.

For the calendar quarter:

Dy 5 mrad (3.3-3)

D* 10 mrad (3.3-4)

For the calendar year:

10 mrad (3.3-5)

D* 20 mrad (3.3-6)

The quarterly limits given above represent one-half of the annual design objectives of Section II.B.I of Appendix I of 10CFR50. If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

3-24

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.1 Noble Gases (continued)

2. Source Term Determination Containment Batch Purge A purge of containment may be started as a Batch purge and continued as a normal purge. The containment Batch Purge volume is considered to be two air containment volumes (RCB vol =

3 2.26E+06 ft ). The containment air is sampled and analyzed for noble gases and tritium prior to release. Stack 1 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The noble gases and tritium analysis are used for containment effluent accountability as follows; q = Ci

Vb (3.3-7)

Where; qj = Activity of nuclide "i" released (IICi).

Ci = Concentration of radionuclide "i" (pCi/cc) vb = Containment purge volume (cc).

Waste Gas Decay Tank Batch Releases Waste Gas Decay Tanks (WGDT) are sampled and analyzed for tritium and noble gases prior to each release. Stack 5 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The activity (IICi) for nuclide "i" for Waste Gas Decay Tank effluent accountability is calculated as follows; (C.1 0 APt

600

28316.85

298) qi = (3.3-7a)

(14.7

283)

Where; qj = Activity of nuclide "i" released (gCi).

Ci = Concentration of nuclide "i" (pCi/cc).

APt Change in pressure (psia) of the WGDT (psia = psig + 14.7) 3-25

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.1 Noble Gases (continued) 3

= WGDT volume, (ft )

600 28316.85 = Conversion factor for converting from ft3 to cc.

298 = Sample temperature at time of analysis, (°k).

14.7 = Sample pressure at time of measurement, (psia).

283 = WGDT Temperature, 'k (see Note below)

NOTE: The FSAR assumes WGDT temperature to be in the 50-140 OF range. Since there is no indicator for the actual WGDT temperature, 50'F (10°C) is conservatively assumed as an acceptable substitute. Also assumed is 0

a sample analysis temperature of 770F (25 C).

Containment Pressure Releases Containment Pressure Releases (ILRT) are calculated using the same methodology as Waste Gas Decay Tank Batch Releases. Containment Pressure Releases are released via Stack 1. The volume to use is 3

2.26E+06 ft .

Continuous Releases Each of the four effluent stacks at the HNP have noble gas monitors. Using the net concentration (gCi/cc) from these monitors times the volume released (determined from the flow monitors) the total activity (pCi) of noble gases released are calculated as follows:

Q. Cx 0 Vx (3.3-8)

Where; Q. = Total activity (pCi) released from Stack "x".

C. = Net concentration (pCi/cc) from Stack "x" noble gas monitor.

Vx = Volume (cc) released from Stack "x" using the flow monitor and, if out of service use the compensatory measurements for volume determination.

3-26

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.3.1 Noble Gases (continued)

The activity (gCi) released for radionuclide "i" equals the radionuclide "i" fraction of the radionuclide mix times the total activity released from Stack "x".

Qi = Qx si S (3.3-8a)

Where; C1 Si : (3.3-8b) i and; Si = The radionuclide "i" fraction of the radionuclide mix Ci = The concentration of nuclide "i" in the grab sample

(ýci/cc).

YCi = Total activity in grab sample (pCi/cc).

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.2.1. If the grab sample activity is < LLD, then a mix based on historical data or a mix based on the Xe-133 / Kr-85 LLD mix of that sample may be used.

When a monitor is out of service, the results of the compensatory sampling for each nuclide times the volume released for that time interval will be used for effluent accountability. During this situation if the sample shows no detectable activity then there is no activity released.

Corrections for Double Accounting For the two stacks that may have batch releases during the same time interval as continuous releases, the above calculations are corrected for double accounting as follows; Qic = Qi - qj (3.3-9)

Where; Qic = Total corrected activity of nuclide "i" (pCi) from Stack "x" when batch releases are being made during that time period.

For short term (batch) releases, the effluent stream is sampled and analyzed. The results of the sampling and analysis is used as the source term for the batch release. Release rate is derived from the source term and the release flow rate.

3-27

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.3.1 Noble Gases (continued)

3. Projection of Doses Doses resulting from the release of gaseous effluents will be projected once every 31 days (monthly). The doses will be projected utilizing Equations 3.3-1 and 3.3-2, and projected using the following expression:

DpT = (Dt 0 p) + Da* (3.3-10) where:

Dp = the 31 Day Projected Dose by organ T

, sum of all open release points in mrem/day by organ T.

p the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

DaT Additional Anticipated Dose for liquid releases by organ T and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard and Special Permit Reports. The 31 day dose projections on the Approval/Results screen include any additional dose.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned batch gas releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

To show compliance with ODCM Operational Requirement 3.11.2.4, the projected month's dose should be compared as in the following:

D* ! 0.2 mrad to air for gamma radiation (3.3-11) and D* < 0.4 mrad to air for beta radiation (3.3-12)

If the projections exceed either Equations 3.3-11 or 3.3-12, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

3-28

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.2 Radioiodine and Particulates

1. Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from a reactor such that the estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radioiodines and particulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

D, = 3.17E- 08 Y (R. ) [(X/Q)v Qiv+ (X/qv q.iv] +

(RiM + RIV + R.G + RiB) [(D/Qv Qiv+ (D/qv qiv] +

(RTM + RTI + RTV + RTB) [(X/QV QTv+ (X/q) qTV]

where:

DT Dose to any organ T from tritium, radioiodines, and particulates, mrem.

(D/Q )v The highest long-term (> 500 hr/yr) annual average relative deposition: 8.8 E-09 m- 2 for the food and ground plane pathways at the controlling location which is the exclusion boundary in the S sector (from Table A-4, Appendix A, for ground-level vent stack releases).

(D/q )v The relative deposition factor for short term, ground-level vent releases (5 500 hrs/yr), m 2 . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant if using "real" meteorology or use 8.8 E-09 m -2 from Table A-4, Appendix A, for the food and ground plane pathways at the controlling location.

Ri = Dose factor for an organ for radionuclide "i" for either the cow milk or goat milk pathway, mrem/yr per ptci/sec per m--2 3-29

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.2 Radioiodine and Particulates (continued)

R. Dose factor for an organ for radionuclide "i" for the ground plane exposure pathway, mrem/yr per pCi/sec per m-2.

R. Dose factor for an organ for radionuclide "i" for the 3

inhalation pathway, mrem/yr per pCi/m .

R.

iv Dose factor for an organ for radionuclide "i" for the vegetable pathway, mrem/yr per pci/sec per m-2.

R. Dose factor for an organ for radionuclide "i" for the 1B meat pathway, mrem/yr per VCi/sec per m-2.

R - Dose factor for an organ for tritium for the milk pathway mrem/yr per pCi/m 3 .

RTv Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per ýtCi/m 3 .

R Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per pCi/m3 .

RTB Dose factor for an organ for tritium for the meat 3

pathway, mrem/yr per pCi/m .

QT Tv Release of tritium in gaseous effluents for long-term vent stack releases (> 500 hrs/yr), pCi.

q T Tv Release of tritium in gaseous effluents for short-term vent stack releases (* 500 hrs/yr), pCi.

To show compliance with 10CFR50, Equation 3.3-13 is evaluated for a hypothetical individual at the limiting location. At SHNPP this location is the exclusion boundary in the S sector which has the highest annual average X/Qv and D/Qv values. This assures that the actual exposure of a member of the public will not be substantially underestimated. The critical receptor is a child.

Appropriate X/Qv and D/Qv values from tables in Appendix A are used. For this document, long-term annual average X/Qv and D/Qv values may be used in lieu of short-term values (see Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant).

3-30

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 3.3.2 Radioiodine and Particulates (continued)

The determination of a limiting location for implementation of 10CFR50 for radioiodines and particulates is a function of:

1. Isotopic mix

2. Meteorology

3. Exposure pathway

4. Receptor's age In the determination of the limiting location, the radionuclide mix of radioiodines and particulates is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is

< LLD, then no activity is assumed to have been released during the sampling period. The release rate is derived from the flow (actual or default) and the isotopic mix.

In the determination of the limiting sector, all age groups and all of the exposure pathways are evaluated using the highest XOQDOQ values in Appendix A at the site boundary. These include beef and vegetable ingestion, inhalation, and ground plane exposure. Goat and cow milk are not currently exposure pathways at SHNPP.

SHNPP ODCM Operational Requirement 3.12.2 requires that a land-use census survey be conducted on an annual basis. The age groupings at the various receptor locations are also determined during this survey. Thus, depending on the results of the survey, a new limiting location and receptor age group could result.

To avoid possible annual revisions to the ODCM software which evaluates effluent releases for compliance with 10CFR50, the limiting sector location has been fixed at the exclusion boundary in the S sector where the highest historical annual average X/Qv and D/Qv values occur (Appendix A) . With all of the exposure pathways identified in the Land Use Census (ODCM Operational Requirement 3.12.2) available to a hypothetical receptor, the critical organ is a child's bone. This approach avoids a substantial underestimate of the dose to a real member of the public.

Long-term X/Qv and D/Qv values for ground-level releases are provided in tables in Appendix A. They may be utilized if an additional special location arises different from those presented in the special locations of the Land Use Census (ODCM Operational Requirement 3.12.2). A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

3-31

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3-1 through 3.3-19 present Ri values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values were calculated using the methodology described in NUREG-0133 assuming a grazing period of eight months. A description of the methodology is presented in Appendix B.

The following relationship should hold for SHNPP to show compliance with SHNPP ODCM Operational Requirement 3.11.2.3.

For the calendar quarter:

D,

7.5 mrem (3.3-14)

For the calendar year:

D,

15 mrem (3.3-15)

The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50. If any of the limits of Equations 3.3-14 or 3.3-15 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC.

This report complies with Section IV.A of Appendix I of 10CFR50.

2. Projection of Doses Doses resulting from release of radioiodines and particulates will be projected once every 31 days (monthly). The doses will be projected utilizing Equation 3.3-13, and projected using the following expression:

Dp = (D, 9 p) + Da, (3.3-16) where:

Dp = the 31 Day Projected Dose by organ T D, sum of all open release points in mrem/day by organ T.

p the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

Da, Additional Anticipated Dose for gaseous releases by organ T and quarter of release.

3-32

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.3.2 Radioiodine and Particulates (continued)

NOTE: The 31 Day Projected Dose values appear on the Standard and Special Permit Reports. The 31 day dose projections on the Approval/Results screen include any additional dose.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned batch gas releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

To show compliance with ODCM Operational Requirement 3.11.2.4, the projected month's dose should be compared as in the following:

D

0.3 mrem to any organ (3.3-17)

If the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

3-33

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-1 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Ground AGE GROUP = ALL Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Cr-51 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4-66E+06 4.66E+06 5.51E+06 Mn-54 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1 . 34E+09 1. 34E+09 1.57E+09 Fe-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2. 75E+08 2. 75E+08 3.23E+08 Co-58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3. 79E+08 3. 79E+08 4.44E+09 Co-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2. 15E+10 2. 15E+10 2.52E+10 Zn-65 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7. 49E+08 7. 49E+08 8. 61E+08 Rb-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8. 99E+06 8. 99E+06 1.03E+07 Sr-89 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2 .23E+04 2. 23E+04 2. 58E+04 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1. 08E+06 1. 22E+06 Zr-95 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2 .49E+08 2. 49E+08 2.89E+08 Nb-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1. 36E+08 1. 36E+08 1.60E+08 Ru-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1. 09E+08 1. 09E+08 1.27E+08 Ru-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4. 19E+08 4 .19E+08 5.03E+08 Ag-IIOM 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3. 48E+09 3 48E+09 4. 06E+09 Sn-113 1.44E+07 6.28E+06 1.22E+07 6.21E+06 1.00E+07 1. 33E+07 8. 14E+06 4.09E+07 Sb-124 8.76E+08 7.53E+08 8.99E+08 7.76E+08 8.17E+08 1. 01E+09 8. 23E+08 1.24E+09 Te-127M 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9. 15E+04 9. 15E+04 1.08E+05 Te-129M 2.00E+07 2.00E+07 2.00E+07 2.O00E+07 2.00E+07 2 OOE+07 2. 00E+07 2.34E+07 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2. 09E+07 1-132 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1 .24E+06 1. 24E+06 1.46E+06 1-133 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2 .47E+06 2. 47E+06 3. 00E+06 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2. 56E+06 2. 56E+06 2.99E+06 Cs-134 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6. 82E+09 6. 82E+09 7.96E+09 Cs-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1. 49E+08 1.69E+08 Cs-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1. 03E+10 1. 03E+10 1.20E+10 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2. 05E+07 2. 05E+07 2.34E+07 Ce-141 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1 .36E+07 1. 36E+07 1.53E+07 Ce-144 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6. 95E+07 6. 95E+07 8.03E+07 Hf-181 1.97E+08 1.63E+08 2.30E+08 1.70E+08 1.77E+08 2. 33E+08 1. 82E+08 2.82E+08 3

R Values in units of mrem/yr per [Ci//M for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-34

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Veget AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.28E+03 2.28E+03 O.OOE+01 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 P-32 5.91E+07 1.72E+08 1.53E+09 9.51E+07 O.OOE+01 O .00E+01 0.00E+01 O.00E+01 Cr-51 4.60E+04 1.16E+07 O.OOE+01 O.OOE+01 1.01E+04 2 .75E+04 6. 10E+04 O.00E+01 Mn-54 5.83E+07 9.36E+08 O.OOE+01 3.05E+08 9.09E+07 0. 00E+01 0. 00E+01 O.00E+01 Fe-59 1.12E+08 9.75E+08 1.24E+08 2.93E+08 O.OOE+01 . 00E+01 8. 17E+07 0. 00E+01 Co-58 6.71E+07 6.07E+08 O.OOE+01 2.99E+07 O.OOE+01 0. OOE+01 O.00E+01 0. 00E+01 Co-60 3.67E+08 3.12E+09 0.OOE+01 1.66E+08 O.OOE+01 O .00E+01 O.00E+01 O.OOE+01 Zn-65 5.77E+08 8.04E+08 4.01E+08 1.28E+09 8.54E+08 O .OOE+01 0. OOE+01 0. 00E+01 Rb-86 1.03E+08 4.36E+07 O.OOE+01 2.21E+08 O.OOE+01 0 .00E+01 0. 00E+01 0. 00E+01 Sr-89 2.87E+08 1.60E+09 1.OOE+10 O.OOE+01 O.OOE+01 0. 00E+01 0. 00E+01 0. OOE+01 Sr-90 1.64E+11 1.93E+10 6.70E+11 O.OOE+01 O.OOE+01 0. 00E+01 O.OOE+01 0. 00E+01 Y-91 1.34E+05 2.76E+09 5.01E+06 O.OOE+01 O.OOE+01 0 .00E+01 O.00E+01 0.00E+01 Zr-95 2.51E+05 1.17E+09 1.16E+06 3.71E+05 5.82E+05 0. OOE+01 O.00E+01 O.00E+01 Nb-95 4.19E+04 4.73E+08 1.40E+05 7.79E+04 7.70E+04 0. OOE+01 O.00E+01 O.00E+01 Ru-103 2.04E+06 5.53E+08 4.74E+06 0.00E+01 1.81E+07 0. OOE+01 O.00E+01 0. OOE+01 Ru-106 2.46E+07 1.26E+10 1.94E+08 0.OOE+01 3.75E+08 0. OOE+01 O.OOE+01 0.00E+01 Ag-IIOM 6.23E+06 4.28E+09 1.13E+07 1.05E+07 2.06E+07 0. 00E+01 0.00E+01 0.00E+01 Sn-113 1.36E+07 2.52E+08 1.44E+07 5.66E+05 4.09E+05 1.96E+05 O.OOE+01 0. OOE+01 Sb-124 4.02E+07 2.88E+09 1.01E+08 1.92E+06 0.OOE+00 2.46E+05 7. 90E+07 O.00E+01 Te-127M 6.12E+07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 0. OOE+01 0. 00E+01 Te-129M 4.71E+07 1.50E+09 2.98E+08 1.11E+08 1.24E+09 1. 02E+08 0. OOE+01 O.OOE+01 1-131 6.61E+07 3.04E+07 8.07E+07 1.15E+08 1.98E+08 3. 78E+10 0. 00E+01 O.00E+01 1-132 5.21E+01 2.80E+01 5.57E+01 1.49E+02 2.37E+02 5. 21E+03 0. OOE+01 0. 00E+01 1-133 1.12E+06 3.30E+06 2.11E+06 3.67E+06 6.40E+06 5. 39E+08 O.OOE+01 O.00E+01 1-135 3.91E+04 1.20E+05 4.05E+04 1.06E+05 1.70E+05 7.OOE+06 0.00E+01 0.00E+01 Cs-134 8.83E+09 1.89E+08 4.54E+09 1.08E+10 3.49E+09 0. OOE+01 1.16E+09 O.OOE+01 Cs-136 1.19E+08 1.88E+07 4.19E+07 1.66E+08 9.21E+07 0.00E+01 1.26E+07 O.OOE+01 Cs-137 5.94E+09 1.76E+08 6.63E+09 9.07E+09 3.08E+09 0. 00E+01 1.02E+09 O.00E+01 Ba-140 8.40E+06 2.64E+08 1.28E+08 1.61E+05 5.47E+04 O.00E+01 9.22E+04 O.OOE+01 Ce-141 1.48E+04 4.99E+08 1.93E+05 1.31E+05 6.07E+04 O.00E+01 O.00E+01 0. 00E+01 Ce-144 1.69E+06 1.06E+10 3.15E+07 1.32E+07 7.80E+06 0.00E+01 O.OOE+01 0. OOE+01 HqfI-181 1i07E+06 7.06E+08 9.51E+06 5 36E+04 4.485+04 3. 41+04 n O_ o+01 o _OOp.+i 3

R Values in units of mrem/yr per ýtCi/m for inhalation and tritium and in units of 2

mrem/yr per j.Ci/sec per m- for all others.

3-35

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Veget AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2 . 61E+03 2 . 61E+03 0.00B+01 2. 61E+03 2. 61E+03 2.61E+03 2.61E+03 2. 61E+03 P-32 6. 80E+07 1.47E+08 1.75E+09 1. 09E+08 0. 00E+01 0.OOE+01 0.OOE+01 0.OOE+01 Cr-51 6. 11E+04 1.03E+07 0. 00E+01 0 OOE+01 1. 34E+04 3.39E+04 8. 72E+04 0.00E+01 Mn-54 8. 79E+07 9.09E+08 0. 00E+01 4. 43E+08 1. 32E+08 0.OOE+01 0.OOE+01 0.00E+01 Fe-59 1. 60E+08 9.78E+08 1.77E+08 4 .14E+08 0. 00E+01 0.00E+01 1.30E+08 0.00E+01 Co-58 9. 79E+07 5.85E+08 0. 00E+01 4. 25E+07 0 OOE+01 0.00E+01 0.00E+01 0. OOE+01 Co-60 5. 57E+08 3. 22E+09 0. OOE+01 2. 47E+08 0 .OOE+01 0. OOE+01 0.OOE+01 0. 00E+01 Zn-65 8. 68E+08 7. 88E+08 5.36E+08 1. 86E+09 1 .19E+09 0.00E+01 0. OOE+01 0.00E+01 Rb-86 1.30E+08 4.09E+07 0. OOE+01 2. 76E+08 0.00E+01 0.00E+01 0.00E+01 0. OOE+01 Sr-89 4.36E+08 1. 81E+09 1.52E+10 0 OOE+01 0.00E+01 0. 00E+01 0.OOE+01 0. OOE+01 Sr-90 2. 05E+11 2.33E+10 8. 32E+11 0 00E+01 0.OOE+01 0.00E+01 0.00E+01 0. 00E+01 Y-91 2. 06E+05 3. 15E+09 7. 68E+06 0. 00E+01 0.00E+01 0. 00E+01 0.00E+01 0. 00E+01 Zr-95 3. 68E+05 1.23E+09 1. 69E+06 5. 35E+05 7.86E+05 0. 00E+01 0.00E+01 0.00E+01 Nb-95 5. 77E+04 4. 48E+08 1.89E+05 1. 05E+05 1.02E+05 0.OOE+01 0.00E+01 0.00E+01 Ru-103 2. 90E+06 5. 66E+08 6.78E+06 0. 00E+01 2.39E+07 0.OOE+01 0.00E+01 0. 00E+01 Ru-106 3. 93E+07 1.50E+10 3.12E+08 0. 00E+01 6. 02E+08 0.00E+01 0.00E+01 0.00E+01 Ag-IIOM 9.39E+06 4.34E+09 1.63E+07 1. 54E+07 2.95E+07 0.00E+01 0.OOE+01 0.00E+01 Sn-113 2. 02E+07 2.29E+08 1.91E+07 8 .03E+05 5.65E+05 2. 63E+05 0. 00E+01 0. 00E+01 Sb-124 5. 89E+07 3. 04E+09 1.51E+08 2. 78E+06 0. OOE+01 3.43E+05 1.32E+08 0.00E+01 Te-127M 9. 44E+07 1.98E+09 7.93E+08 2. 81E+08 3. 22E+09 1. 89E+08 0.00E+01 0.00E+01 Te-129M 6. 79E+07 1.61E+09 4.29E+08 1 .59E+08 1.79E+08 1.38E+08 0. 00E+01 0. OOE+01 1-131 5.77E+07 2 . 13E+07 7. 68E+07 1. 07E+08 1.85E+08 3. 14E+10 0.00E+01 0. OOE+01 1-132 4. 72E+01 5.72E+01 5. 02E+01 1. 31E+02 2.07E+02 4.43E+03 0. OOE+01 0. OOE+01 1-133 1. 01E+06 2 . 51E+06 1.96E+06 3 .32E+06 5. 83E+06 4.64E+08 0.00E+01 0.OOE+01 1-135 3. 49E+04 1.04E+05 3. 66E+04 9. 42E+04 1.49E+05 6.06E+06 0.OOE+01 0.00E+01 Cs-134 7. 54E+09 2.02E+08 6. 90E+09 1. 62E+10 5. 16E+09 0.OOE+01 1.97E+09 0.00E+01 Cs-136 1.13E+08 1.35E+07 4.28E+07 1. 68E+08 9. 16E+07 0.OOE+01 1.44E+07 0. 00E+01 Cs-137 4. 90E+09 2.00E+08 1. 06E+10 1.41E+10 4.78E+09 0. OOE+01 1. 86E+09 0.00OE+01 Ba-140 8. 88E+06 2.12E+08 1.38E+08 1. 69E+05 5.72E+04 0. OOE+01 1.14E+05 0. 00E+01 Ce-141 2. 12E+04 5. 29E+08 2.77E+05 1.85E+05 8.70E+04 0. 00E+01 0. 00E+01 0. OOE+01 Ce-144 2. 71E+06 1.27E+10 5. 04E+07 2. 09E+07 1.25E+07 0. 00E+01 0.00E+01 0. OOE+01 Hf-181 1. 54E+06 6.90E+08 1.38E+07 7. 58E+04 6.32E+04 4.63E+04 0.00E+01 0.00E+01 3

R Values in units of mrem/yr per ý,Ci/m for inhalation and tritium and in units of 2

inrem/yr per ).Ci/sec per m- for all others.

3-36

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-4 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Veget AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 4. 04E+03 4. 04E+03 0. 00E+01 4 . 04E+03 4.04E+03 4. 04E+03 4. 04E+03 4.04E+03 P-32 1.42E+08 1.01E+08 3. 67E+09 1.72E+08 0. 00E+01 0.OOE+01 0.00E+01 0.00E+01 Cr-51 1.16E+05 6. 15E+06 0. 00E+01 0 OOE+01 1.76E+04 6.44E+04 1.18E+05 0.00E+01 Mn-54 1.73E+08 5.44E+08 0 OOE+01 6. 49E+08 1. 82E+08 0.00E+01 0. 00E+01 0.00E+01 Fe-59 3.17E+08 6. 62E+08 3 . 93E+08 6. 36E+08 0. 00E+01 0.OOE+01 1. 84E+08 0.00E+01 Co-58 1.92E+08 3.66E+08 0 OOE+01 6. 27E+07 0. 00E+01 0.OOE+01 0. 00E+01 0.00E+01 Co-60 1.11E+09 2. 08E+09 0.00E+01 3 . 76E+08 0. OOE+01 0.OOE+01 0. OOE+01 0.00E+01 Zn-65 1. 70E+09 4.81E+08 1. 03E+09 2. 74E+09 1. 73E+09 0.00E+01 0. OOE+01 0.00E+01 Rb-86 2.81E+08 2.94E+07 0 OOE+01 4. 56E+08 0. 00E+01 0.00E+01 0. 00E+01 0.00E+01 Sr-89 1.03E+09 1. 40E+09 3. 62E+10 0 OOE+01 0.OOE+01 0.OOE+01 0.00E+01 0.00E+01 Sr-90 3.49E+11 1.86E+10 1. 38E+12 0 OOE+01 0. OOE+01 0.OOE+01 0. OOE+01 0.00E+01 Y-91 4. 89E+05 2.44E+09 1.83E+07 0. 00E+01 0. 00E+01 0.OOE+01 0. 00E+01 0.00E+01 Zr-95 7.44E+05 8.71E+08 3. 80E+06 8. 35E+05 1. 20E+06 0.00E+01 0. 00E+01 0.00E+01 Nb-95 1. 12E+05 2.91E+08 4. 04E+05 1. 57E+05 1. 48E+05 0.OOE+01 0.00E+01 0.00E+01 Ru-103 5. 86E+06 3 . 94E+08 1. 52E+07 0 OOE+01 3 . 84E+07 0.OOE+01 0. OOE+01 0.00E+01 Ru-106 9.38E+07 1.17E+10 7. 52E+08 0. 00E+01 1. 02E+09 0. OOE+01 0. OOE+01 0.00E+01 Ag-IIOM 1. 87E+07 2.78E+09 3.46E+07 2 34E+07 4.35E+07 0. 00E+01 0.00E+01 0.00E+01 Sn-il3 3. 97E+07 1.45E+08 3 . 64E+07 1. 18E+06 8. 09E+05 4. 82E+05 0. OOE+01 0. 00E+01 Sb-124 1.21E+08 2.16E+09 3. 44E+08 4. 47E+06 0. OOE+01 7. 61E+05 1.91E+08 0. 00E+01 Te-127M 2. 26E+08 1. 54E+09 1. 90E+09 5. 12E+08 5.42E+09 4. 55E+08 0. OOE+01 0 00E+01 Te-129M 1. 55E+08 1.22E+09 9. 98E+08 2. 79E+08 2.93E+09 3. 22E+08 0.OOE+01 0. 00E+01 1-131 8. 16E+07 1.23E+07 1.43E+08 1. 44E+08 2.36E+08 4.75E+10 0.OOE+01 0. 00E+01 1-132 7. 53E+01 1.93E+02 8. 91E+01 1. 64E+02 2. 51E+02 7. 60E+03 0.00E+01 0. 00E+01 1-133 1. 67E+06 1.78E+06 3. 57E+06 4. 42E+06 7.36E+06 8. 21E+08 0.00E+01 0. 00E+01 1-135 5. 54E+04 8. 92E+04 6.50E+04 1. 17E+05 1.79E+05 1. 04E+07 0.00E+01 0. 00E+01 Cs-134 5. 40E+09 1.38E+08 1.56E+10 2. 56E+10 7 . 93E+09 0. 00E+01 2. 84E+09 0. 00E+01 Cs-136 1.43E+08 7.77E+06 8. 04E+07 2. 21E+08 1.18E+08 0.00E+01 1.76E+07 0.00E+01 Cs-137 3.52E+09 1. 50E+08 2.49E+10 2. 39E+10 7 . 78E+09 0. OOE+01 2.80E+09 0. 00E+01 Ba-140 1.61E+07 1.40E+08 2. 76E+08 2. 42E+05 7. 87E+04 0.00E+01 1.44E+05 0. 00E+01 Ce-141 4. 75E+04 3.99E+08 6.42E+05 3. 20E+05 1.40E+05 0. OOE+01 0.00E+01 0. 00E+01 Ce-144 6.49E+06 9. 94E+09 1. 22E+08 3. 81E+07 2 . 11E+07 0.OOE+01 0.00E+01 0. 00E+01 Hf-181 3. 15E+06 5. 17E+08 3 . 13E+07 1.22E+05 9. 78E+04 1 . 03E+05 0. 00E+01 0.00E+01 3

R Values in units of mrem/yr per IICi//M for inhalation and tritium and in units of

-2 mrem/yr per ptCi/sec per M for all others.

3-37

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 3.27E+02 3.27E+02 0. 00E+01 3.27E+02 3.27E+02 3 .27E+02 3. 27E+02 3.27E+02 P-32 1. 18E+08 3 .43E+08 3. 05E+09 1.89E+08 0.00E+01 0. 00E+01 0. OOE+01 0. 00E+01 Cr-51 4. 27E+03 1. 08E+06 0.00E+01 0.00E+01 9.42E+02 2. 56E+03 5.67E+03 0.OOE+01 Mn-54 1. 06E+06 1. 71E+07 0.OOE+01 5. 57E+06 1.66E+06 0 OOE+01 0. 00E+01 0.00E+01 Fe-59 1. 43E+08 1 .25E+09 1.59E+08 3.74E+08 0.00E+01 0. OOE+01 1.04E+08 0.00E+01 Co-58 2. 43E+07 2 .20E+08 0.OOE+01 1.08E+07 0.00E+01 0.00E+01 0 00E+01 0.00E+01 Co-60 1. 03E+08 8. 76E+08 0.OOE+01 4.66E+07 0. OOE+01 0. OOE+01 0. 00E+01 0. 00E+01 Zn-65 3. 58E+08 4. 98E+08 2.49E+08 7.91E+08 5. 29E+08 0 OOE+01 0. 00E+01 0. OOE+01 Rb-86 1. 42E+08 6. 00E+07 0.00E+01 3. 04E+08 0. OOE+01 0. 00E+01 0. OOE+01 0. OOE+01 Sr-89 5. 23E+06 2.92E+07 1.82E+08 0. 00E+01 0.OOE+01 0. 00E+01 0.00E+01 0.00E+01 Sr-90 2. 02E+09 2.38E+08 8.22E+09 0.00E+01 0. OOE+01 0 .00E+01 0. OOE+01 0.00E+01 Y-91 1. 80E+04 3.71E+08 6. 75E+05 0.00E+01 0.00E+01 0. OOE+01 0. 00E+01 0.00E+01 Zr-95 2. 43E+05 1.14E+09 1. 12E+06 3.59E+05 5. 64E+05 0. 00E+01 0. OOE+01 0.OOE+01 Nb-95 4. 12E+05 4.65E+09 1. 38E+06 7.66E+05 7. 58E+05 0.00E+01 0.00E+01 0.OOE+01 Ru-103 2 72E+07 7.38E+09 6.32E+07 0.OOE+01 2.41E+08 0 OOE+01 0.00E+01 0. 00E+01 Ru-106 2. 19E+08 1.12E+11 1.73E+09 0.OOE+01 3.35E+09 0 OOE+01 0 . 00E+01 0. 00E+01 Ag-IIOM 2. 34E+06 1.61E+09 4.27E+06 3.95E+06 7.76E+06 0. OOE+01 0.00E+01 0. 00E+01 Sn-113 2. 80E+07 5.19E+08 2.97E+07 1.15E+06 8. 40E+05 4. 03E+05 0.00E+01 0. OOE+01 Sb-124 4. 72E+06 3 .38E+08 1. 19E+07 2.25E+05 0 00E+01 2.88E+04 9.27E+06 0.00E+01 Te-127M 1. OOE+08 2.76E+09 8. 22E+08 2 .94E+08 3.34E+09 2 . 10E+08 0.00E+01 0.00E+01 Te-129M 1. 17E+08 3.73E+09 7. 40E+08 2. 76E+08 3. 09E+09 2.54E+08 0. 00E+01 0. OOE+01 1-131 5. 77E+06 2.66E+06 7.04E+06 1.01E+07 1.73E+07 3 .30E+09 0. 00E+01 0.00E+01 1-133 1. 51E-01 4.46E-01 2. 85E-01 4. 96E-01 8. 66E-01 7.29E+01 0. OOE+01 0.00E+01 1-135 6. 07E-17 1.86E-16 6. 28E-17 1. 64E-16 2. 64E-16 1. 08E-14 0. OOE+01 0.OOE+01 Cs-134 7.81E+08 1. 67E+07 4. 01E+08 9. 55E+08 3. 09E+08 0.OOE+01 1. 03E+08 0.OOE+01 Cs-136 2. 14E+07 3.33E+06 7. 53E+06 2. 97E+07 1. 65E+07 0. OOE+01 2.27E+06 0.00E+01 Cs-137 4.99E+08 1.47E+07 5. 57E+08 7. 61E+08 2. 58E+08 0.00E+01 8. 59E+07 0.OOE+01 Ba-140 1,20E+06 3.77E+07 1.83E+07 2. 30E+04 7. 82E+03 0.00E+01 1.32E+04 0. 00E+01 Ce-141 6,46E+02 2. 18E+07 8.42E+03 5-69E+03 2. 65E+03 0.00E+01 0. 00E+01 0.00E+01 Ce-144 4,70E+04 2. 96E+08 8.75E+05 3. 66E+05 2. 17E+05 0.00E+01 0. OOE+01 0.00E+01 Hf-181 1. 52E+06 9.97E+08 1.34E+07 7. 57E+04 6.33E+04 4. 81E+04 0. OOE+01 0.00E+01 3

R Values in units of mrem/yr per pCi//M for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-38

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1. 95E+02 1. 95E+02 0. OOE+01 1.95E+02 1. 95E+02 1. 95E+02 1. 95E+02 1. 95E+02 P-32 9. 98E+07 2.16E+08 2. 58E+09 1.60E+08 0. 00E+01 0.00E+01 0.OOE+01 0 OOE+01 Cr-51 3. 42E+03 5. 75E+05 0. OOE+01 0.00E+01 7.49E+02 1.90E+03 4.88E+03 0. 00E+01 Mn-54 8.43E+05 8.72E+06 0. OOE+01 4.25E+06 1.27E+06 0.OOE+01 0.00E+01 0. 00E+01 Fe-59 1. 15E+08 7.02E+08 1.27E+08 2. 97E+08 0. OOE+01 0.00E+01 9.3 6E+07 0. 00E+01 Co-58 1.93E+07 1.15E+08 0. 00E+01 8.36E+06 0.OOE+01 0.OOE+01 0. 00E+01 0. 00E+01 Co-60 8.15E+07 4.71E+08 0. 00E+01 3.62E+07 0.00E+01 0. 00E+01 0. OOE+01 0. 00E+01 Zn-65 2.83E+08 2.57E+08 1. 75E+08 6. 07E+08 3. 89E+08 0. OOE+01 0. OOE+01 0.00E+01 Rb-86 1.19E+08 3 76E+07 0.00E+01 2. 54E+08 0. 00E+01 0. OOE+01 0 OOE+01 0 OOE+01 Sr-89 4.40E+06 1.83E+07 1. 54E+08 0.00E+01 0. 00E+01 0.OOE+01 0. 00E+01 0.00E+01 Sr-90 1.31E+09 1.49E+08 5.32E+09 0 .00E+01 0. OOE+01 0. 00E+01 0. 00E+01 0 OOE+01 Y-91 1. 52E+04 2. 33E+08 5.68E+05 0.00E+01 0.00E+01 0 OOE+01 0 00E+01 0. OOE+01 Zr-95 1. 95E+05 6. 53E+08 8.97E+05 2.83E+05 4. 16E+05 0 00E+01 0 .00E+01 0. OOE+01 Nb-95 3. 29E+05 2. 55E+09 1.08E+06 5.97E+05 5.79E+05 0 OOE+01 0.00E+01 0.00E+01 Ru-103 2. 20E+07 4. 30E+09 5. 15E+07 0.00E+01 1.82E+08 0 00E+01 0 .00E+01 0.00E+01 Ru-106 1. 84E+08 7. 00E+10 1.46E+09 0. 00E+01 2. 81E+09 0. 00E+01 0.OOE+01 0.OOE+01 Ag-IIOM 1. 86E+06 8.59E+08 3. 23E+06 3.06E+06 5.83E+06 0 00E+01 0.00E+01 0. 00E+01 Sn-113 2. 22E+07 2. 51E+08 2.09E+07 8. 80E+05 6. 19E+05 2 88E+05 0. OOE+01 0.OOE+01 Sb-124 3. 80E+06 1.96E+08 9.73E+06 1. 79E+05 0. 00E+01 2 . 21E+04 8. 50E+06 0.00E+01 Te-127M 8. 25E+07 1. 73E+09 6.94E+08 2.46E+08 2. 81E+09 1. 65E+08 0. OOE+01 0.OOE+01 Te-129M 9. 81E+07 2.33E+09 6.20E+08 2. 30E+08 2. 59E+09 2 OOE+08 0. 00E+01 0.OOE+01 1-131 4. 40E+06 1. 62E+06 5. 85E+06 8.20E+06 1. 41E+07 2. 39E+09 0. OOE+01 0.OOE+01 1-133 1. 23E-01 3. 06E-01 2.39E-01 4. 05E-01 7. lE-01 5. 65E+01 0.OOE+01 0.00E+01 1-135 4. 88E-17 1.46E-16 5. 11E-17 1.32E-16 2. 08E-16 8.46E-15 0. 00E+01 0.00E+01 Cs-134 3. 48E+08 9. 34E+06 3.19E+08 7. 51E+08 2. 39E+08 0.OOE+01 9. 11E+07 0.OOE+01 Cs-136 1. 55E+07 1. 86E+06 5. 87E+06 2 .31E+07 1. 26E+07 0 .OOE+01 1.98E+06 0. 00E+01 Cs-137 2. 14E+08 8.75E+06 4. 62E+08 6. 15E+08 2. 09E+08 0.00E+01 8.13E+07 0.00E+01 Ba-140 9. 76E+05 2.34E+07 1. 51E+07 1.86E+04 6.29E+03 0.OOE+01 1.25E+04 0.00E+01 Ce-141 5. 42E+02 1.35E+07 7. 07E+03 4.72E+03 2. 22E+03 0. OOE+01 0.OOE+01 0.00E+01 Ce-144 3. 96E+04 1.85E+08 7. 37E+05 3.05E+05 1. 82E+05 0.00E+01 0. OOE+01 0.OOE+01 Hf-181 1. 22E+06 5. 50E+08 1.10E+07 6.05E+04 5. 04E+04 3 . 69E+04 0. 00E+01 0.00E+01

R Values in units of mrem/yr per pCi/mr3 for inhalation and tritium and in units of mrem/yr per pCi/sec per M-2 for all others.

3-39

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2 .36E+02 2.36E+02 0. OOE+01 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 P-32 1. 87E+08 1.34E+08 4. 86E+09 2.27E+08 0.00E+01 0.00E+01 0. 00E+01 0.00E+01 Cr-51 5.33E+03 2.83E+05 0. OOE+01 0.00E+01 8.09E+02 2. 96E+03 5 40E+03 0.00E+01 Mn-54 1 30E+06 4. 08E+06 0.00E+01 4.86E+06 1.36E+06 0.00E+01 0.00E+01 0.00E+01 Fe-59 1. 82E+08 3.80E+08 2. 25E+08 3.65E+08 0.00E+01 0.00E+01 1 .06E+08 0.00E+01 Co-58 2. 99E+07 5.70E+07 0.OOE+01 9.76E+06 0.00E+01 0.00E+01 0. 00E+01 0.00E+01 Co-60 1.27E+08 2.38E+08 0.00E+01 4.30E+07 0.00E+01 0.00E+01 0. 00E+01 0.OOE+01 Zn-65 4. 35E+08 1.23E+08 2. 62E+08 6. 99E+08 4.40E+08 0.00E+01 0. 00E+01 0.00E+01 Rb-86 2. 21E+08 2.32E+07 0. 00E+01 3.60E+08 0.00E+01 0.00E+01 0. 00E+01 0. 00E+01 Sr-89 8. 31E+06 1.13E+07 2.91E+08 0.00E+01 0. 00E+01 0.00E+01 0 00E+01 0.00E+01 Sr-90 1 74E+09 9. 26E+07 6.87E+09 0.00E+01 0 00E+01 0. 0E+01 0. 00E+01 0.00E+01 Y-91 2. 87E+04 1. 43E+08 1. 07E+06 0.00E+01 0 00E+01 0. 00E+01 0.00E+01 0. 00E+01 Zr-95 3 12E+05 3.65E+08 1.59E+06 3.50E+05 5.01E+05 0. 00E+01 0. 00E+01 0. 00E+01 Nb-95 5 17E+05 1.34E+09 1.86E+06 7.23E+05 6.80E+05 0 .00E+01 0 00E+01 0.00E+01 Ru-103 3 58E+07 2.41E+09 9.31E+07 0. 00E+01 2. 34E+08 0.00E+01 0 00E+01 0.00E+01 Ru-106 3 43E+08 4. 27E+10 2.75E+09 0. 00E+01 3 .71E+09 0.00E+01 0.00E+01 0.00E+01 Ag-IIOM 2 89E+06 4.3 0E+08 5.36E+06 3. 62E+06 6.74E+06 0.00E+01 0.00E+01 0.00E+01 Sn-113 3. 42E+07 1.25E+08 3.14E+07 1.01E+06 6. 97E+05 4.15E+05 0.00E+01 0.00E+01 Sb-124 6. 17E+06 1.10E+08 1.76E+07 2.28E+05 0 .00E+01 3. 88E+04 9.77E+06 0.00E+01 Te-127M 1. 55E+08 1. 06E+09 1.31E+09 3.52E+08 3.73E+09 3. 13E+08 0. 00E+01 0.00E+01 Te-129M 1. 81E+08 1.42E+09 1.17E+09 3.26E+08 3 .43E+09 3 .77E+08 0.00E+01 0.00E+01 1-131 6. 20E+06 9. 72E+05 1. 09E+07 1.09E+07 1. 79E+07 3 .61E+09 0. 00E+01 0.00E+01 1-133 2. 07E-01 2.21E-01 4.43E-01 5.48E-01 9. 13E-01 1.02E+02 0.00E+01 0.00E+01 1-135 7. 87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 0.00E+01 0.00E+01 Cs-134 1.95E+08 4.93E+06 5.63E+08 9.23E+08 2. 86E+08 0.00E+01 1.03E+08 0.00E+01 Cs-136 1. 80E+07 9. 78E+05 1.01E+07 2.78E+07 1.48E+07 0.00E+01 2.21E+06 0.00E+01 Cs-137 1.20E+08 5. 10E+06 8. 51E+08 8.15E+08 2. 65E+08 0. 00E+01 9.55E+07 0.00E+01 Ba-140 1. 63E+06 1.42E+07 2.80E+07 2.45E+04 7. 97E+03 0 00E+01 1.46E+04 0.00E+01 Ce-141 9. 86E+02 8.28E+06 1.33E+04 6.64E+03 2 .91E+03 0. 00E+01 0.00E+01 0. 00E+01 Ce-144 7. 42E+04 1.14E+08 1.39E+06 4.36E+05 2.41E+05 0.00E+01 0.00E+01 0.00E+01 Hf-181 2 . 02E+06 3.31E+08 2.00E+07 7.79E+04 6.26E+04 6.56E+04 0.00E+01 0.00E+01 3

R Values in units of mrem/yr per ýtCi/m for inhalation and tritium and in units of

-2 mrem/yr per pCi/sec per M for all others.

3-40

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 7. 69E+02 7.69E+02 0. 00E+01 7.69E+02 7. 69E+02 7. 69E+02 7.69E+02 7. 69E+02 P-32 4. 32E+08 1.26E+09 1.12E+10 6.95E+08 0. OOE+01 0 OOE+01 0. OOE+01 0.00E+01 Cr-51 1. 73E+04 4 .36E+06 0.OOE+01 0. 00E+01 3. 82E+03 1. 04E+04 2. 30E+04 0.00E+01 Mn-54 9.76E+05 1. 57E+07 0.00E+01 5.11E+06 1. 52E+06 0. 00E+01 0.00E-01 0.00E+01 Fe-59 1. 60E+07 1. 39E+08 1.77E+07 4. 17E+07 0. OOE+01 0. 00E+01 1. 17E+07 0.OOE+01 Co-58 6. 28E+06 5. 68E+07 0. OOE+01 2. 80E+06 0. 00E+01 0 OOE+01 0.00E+01 0. OOE+01 Co-60 2.24E+07 1.91E+08 0. 00E+01 1.02E+07 0. 00E+01 0. OOE+01 0.00E+01 0. 00E+01 Zn-65 1 .38E+09 1.92E+09 9. 59E+08 3. 05E+09 2. 04E+09 0. 00E+01 0. OOE+01 0. OOE+01 Rb-86 7. 54E+08 3.19E+08 0. OOE+01 1. 62E+09 0 OOE+01 0 OOE+01 0. 00E+01 0.00E+01 Sr-89 2. 50E+07 1.40E+08 8.70E+08 0. 00E+01 0. OOE+01 0. OOE+01 0. 00E+01 0. 00E+01 Sr-90 7. 59E+09 8. 94E+08 3.09E+10 0.00E+01 0. 00E+01 0. 00E+01 0. 00E+01 0. 00E+01 Y-91 1.37E+02 2. 81E+06 5. 11E+03 0 OOE+01 0. 00E+01 0. 00E+01 0.OOE+01 0.00E+01 Zr-95 1.22E+02 5.71E+05 5.62E+02 1. 80E+02 2. 83E+02 0.00E+01 0. OOE+01 0.OOE+01 Nb-95 1 .48E+04 1.67E+08 4. 95E+04 2. 75E+04 2. 72E+04 0 .00E+01 0. OOE+01 0. OOE+01 Ru-103 2 . 63E+02 7.14E+04 6. 11E+02 0 00E+01 2. 33E+03 0. 00E+01 0. OOE+01 0. OOE+01 Ru-106 1. 60E+03 8.17E+05 1.26E+04 0. 00E+01 2 44E+04 0. OOE+01 0. 00E+01 0.00E+01 Ag-IIOM 2. 04E+07 1.40E+10 3. 71E+07 3 44E+07 6. 76E+07 0 00E+01 0.OOE+01 0. 00E+01 Sn-113 1. 32E+06 2.44E+07 1.40E+06 5. 41E+04 3 . 95E+04 1 . 90E+04 0.OOE+01 0. OOE+01 Sb-124 6.14E+06 4.39E+08 1. 55E+07 2. 92E+05 0 OOE+01 3.75E+04 1.20E+07 0. 00E+01 Te-127M 4. 11E+06 1.13E+08 3. 37E+07 1. 21E+07 1. 37E+08 8.62E+06 0.00E+01 0. 00E+01 Te-129M 6. 19E+06 1.97E+08 3. 91E+07 1. 46E+07 1.63E+08 1.34E+07 0.00E+01 0. 00E+01 1-131 1. 59E+08 7.32E+07 1.94E+08 2 .77E+08 4. 76E+08 9. 09E+10 0. 00E+01 0. OOE+01 1-132 1. 03E+01 5. 51E-02 1.10E+01 2 . 93E+01 4.67E+01 1.03E+01 0.OOE+01 0. OOE+01 1-133 1. 40E+06 4.13E+06 2.64E+06 4. 59E+06 8. 01E+06 6.75E+08 0. OOE+01 0. OOE+01 1-135 9. 03E+03 2.76E+04 9.34E+03 2. 45E+04 3.92E+04 1.61E+06 0. 00E+01 0. OOE+01 Cs-134 6.71E+09 1.44E+08 3.45E+09 3.21E+09 2. 66E+09 0.OOE+01 8.82E+08 0.00E+01 Cs-136 4.73E+08 7.46E+07 1.66E+08 6.57E+08 3. 65E+08 0. 00E+01 5. 01E+07 0. 00E+01 Cs-137 4.22E+09 1.25E+08 4.71E+09 6.44E+09 2. 19E+09 0. OOE+01 7. 27E+08 0. 00E+01 Ba-140 1.12E+06 3 .53E+07 1.71E+07 2.15E+04 7.32E+03 0.00E+01 1. 23E+04 0. OOE+01 Ce-141 2.23E+02 7.52E+06 2.91E+03 1.97E+03 9.14E+02 0.OOE+01 0. OOE+01 0. 00E+01 Ce-144 1.15E+04 7.26E+07 2. 15E+05 8. 97E+04 5. 32E+04 0.OOE+01 0.00E+01 0.00E+01 Hf-181 ý- Rp+n2 4 .38E+05 5. 91E+03 3.33R+01 2 . 79E+01 2. 12F+01 0.OOE+01 0 00E+01 3

R Values in units of mrem/yr per I.Ci/m for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-41

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.OOE+03 1.OOE+03 0.OOE+01 1.00E+03 1. 00E+03 1. 00E+03 1. 00E+03 1.00E+03 P-32 8. OOE+08 1.73E+09 2. 06E+10 1.28E+09 0.OOE+01 0. OOE+01 0.00E+01 O.00E+01 Cr-51 3.02E+04 5.08E+06 0. OOE+01 0. OOE+01 6.63E+03 1.68E+04 4.32E+04 0.OOE+01 Mn-54 1. 69E+06 1.75E+07 0. OOE+01 8. 52E+06 2. 54E+06 0. OOE+01 0. 00E+01 0. OOE+01 Fe-59 2.79E+07 1. 71E+08 3. 10E+07 7.23E+07 0.00E+01 0. 00E+01 2.28E+07 0.OOE+01 Co-58 1. 09E+07 6.50E+07 0. OOE+01 4.72E+06 0.00E+01 0.00E+01 0. 00E+01 0. 00E+01 Co-60 3. 88E+07 2. 25E+08 0. OOE+01 1.72E+07 0. 00E+01 0. OOE+01 0. 00E+01 0. 00E+01 Zn-65 2.38E+09 2 .16E+09 1.47E+09 5.11E+09 3.27E+09 0. 00E+01 0.00E+01 0.00E+01 Rb-86 1. 39E+09 4. 37E+08 0.OOE+01 2.95E+09 0.00E+01 0. 00E+01 0. 00E+01 0.00E+01 Sr-89 4. 59E+07 1.91E+08 1.60E+09 0. OOE+01 0.OOE+01 0.00E+01 O.00KE+01 0.00E+01 Sr-90 1. 08E+10 1. 23E+09 4.37E+10 0.OOE+01 0.00E+01 0.00E+01 0.OOE+01 0.OOE+01 Y-91 2. 52E+02 3. 85E+06 9.40E+03 0. OOE+01 0. 00E+01 0.OOE+01 0.00E+01 0.00E+01 Zr-95 2.13E+02 7. 16E+05 9. 83E+02 3. 10E+02 4.56E+02 0. 00E+01 0. OOE+01 0.00E+01 Nb-95 2. 58E+04 2. OOE+08 8. 45E+04 4.68E+04 4. 54E+04 0. OOE+01 0. OOE+01 0. OOE+01 Ru-103 4.65E+02 9.08E+04 1. 09E+03 0.OOE+01 3.83E+03 0.00E+01 0. 00E+01 0. 00E+01 Ru-106 2.93E+03 1.11E+06 2.32E+04 0.00E+01 4.48E+04 0.00E+01 0.00E+01 0.00-E+01 Ag-1IOM 3 .53E+07 1.63E+10 6.14E+07 5.81E+07 1.11E+08 0. 00E+01 0.00E+01 0.OOE+01 Sn-113 2.28E+06 2. 58E+07 2.15E+06 9. 06E+04 6. 37E+04 2. 97E+04 0. OOE+01 0. 00E+01 Sb-124 1. 08E+07 5.56E+08 2.76E+07 5.08E+05 0.00E+01 6.26E+04 2.41E+07 0.00E+01 Te-127M 7. 39E+06 1.55E+08 6.22E+07 2.21E+07 2.52E+08 1.48E+07 0.00E+01 0. 00E+01 Te-129M 1. 13E+07 2. 69E+08 7. 15E+07 2.65E+07 2.99E+08 2.31E+07 O.00E+01 0.00E+01 1-131 2.65E+08 9. 75E+07 3. 52E+08 4.93E+08 8.48E+08 1.44E+11 0.00E+01 0.OOE+01 1-132 1. 83E+01 2.22E+01 1. 94E+01 5. 09E+01 8.02E+01 1.71E+01 0.00E+01 0.00E+01 1-133 2 . 49E+06 6.19E+06 4.82E+06 8. 18E+06 1. 43E+07 1.14E+09 0. 00E+01 0. 00E+01 1-135 1. 58E+04 4. 74E+04 1 . 66E+04 4. 27E+04 6. 75E+04 2.75E+06 0. 00E+01 0. 00E+01 Cs-134 6. 54E+09 1.75E+08 5. 99E+09 1.41E+10 4.48E+09 0. 00E+01 1.71E+09 0. OOE+01 Cs-136 7.48E+08 8.97E+07 2. 83E+08 1.l1E+09 6. 07E+08 0. 00E+01 9 56E+07 0.OOE+01 Cs-137 3. 96E+09 1.62E+08 8. 54E+09 1.14E+10 3.87E+09 0. 00E+01 1. 50E+09 0.OOE+01 Ba-140 1.99E+06 4. 77E+07 3. 09E+07 3. 79E+04 1.28E+04 0.00E+01 2. 55E+04 0.00E+01 Ce-141 4 . 09E+02 1. 02E+07 5. 33E+03 3. 56E+03 1. 68E+03 0. 00E+01 0 00E+01 0. 00E+01 Ce-144 2.12E+04 9. 93E+07 3. 95E+05 1.63E+05 9. 76E+04 0. 00E+01 0. OOE+01 0.00E+01 Hf-181 1. 18E+03 5.28E+05 1 _0E+04 5 - 8.R+01 4 - 84E+01 3. 55E+01 0 - 005+01 0.00E+01 3

R Values in units of mrem/yr per pCi//M for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-42

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.58E+03 1. 58E+03 0.00E+01 1.58E+03 1.58E+03 1. 58E+03 1.58E+03 1.58E+03 P-32 1.96E+09 1. 41E+09 5.09E+10 2.38E+09 0.00E+01 0. OOE+01 0.00E+01 0.00E+01 Cr-51 6. 17E+04 3 27E+06 0.OOE+01 0.OOE+01 9.36E+03 3.42E+04 6.25E+04 0.OOE+01 Mn-54 3 39E+06 1. 07E+07 0. OOE+01 1.27E+07 3.57E+06 0.OOE+01 0. OOE+01 0. OOE+01 Fe-59 5.79E+07 1. 21E+08 7.18E+07 1.16E+08 0. OOE+01 0 OOE+01 3.37E+07 0.OOE+01 Co-58 2 21E+07 4. 20E+07 0.00E+01 7.21E+06 0. 00E+01 0.00E+01 0.00E+01 0. 00E+01 Co-60 7. 90E+07 1.48E+08 0. 00E+01 2.68E+07 0.00E+01 0. 00E+01 0.00E+01 0.OOE+01 Zn-65 4 . 79E+09 1.35E+09 2. 89E+09 7.70E+09 4. 85E+09 0. 00E+01 0.00E+01 0.OOE+01 Rb-86 3 .36E+09 3. 52E+08 0.00E+01 5.47E+09 0. OOE+01 0. 00E+01 0.00E+01 0. 00E+01 Sr-89 1.13E+08 1. 54E+08 3 . 97E+09 o.OOE+01 0. OOE+01 0. 00E+01 0.00E+01 0. OOE+01 Sr-90 1. 87E+10 9. 95E+08 7.38E+10 0.OOE+01 0. OOE+01 0.00E+01 0.OOE+01 0. OOE+01 Y-91 6.21E+02 3. 09E+06 2.32E+04 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 4 .47E+02 5. 23E+05 2. 28E+03 5.02E+02 7. 18E+02 o. 00E+01 o.OOE+01 0.00E+01 Nb-95 5.31E+04 1.37E+08 1.91E+05 7.42E+04 6. 98E+04 o .OOE+01 o.OOE+01 0.00E+01 Ru-103 9. 88E+02 6. 65E+04 2. 57E+03 0.00E+01 6.47E+03 0. 00E+01 0.OOE+01 0.OOE+01 Ru-106 7.14E+03 8.90E+05 5.72E+04 0. 00E+01 7.72E+04 0. OOE+01 o.OOE+01 0.00E+01 Ag-IIOM 7. 19E+07 1. 07E+10 1.33E+08 9. 00E+07 1.68E+08 0. OOE+01 0.00E+01 0.00E+01 Sn-113 4. 61E+05 1 .69E+06 4. 22E+05 1.36E+04 9.37E+03 5. 58E+03 0.00E+01 0.OOE+01 Sb-124 2. 29E+07 4. 09E+08 6.53E+07 8. 47E+05 o.00E+01 1. 44E+05 3 .62E+07 0.OOE+01 Te-127M 1. 82E+07 1. 24E+08 1.53E+08 4.13E+07 4.37E+08 3 . 66E+07 0. 00E+01 0.OOE+01 Te-129M 2 . 74E+07 2. 15E+08 1.76E+08 4. 92E+07 5.18E+08 5. 68E+07 0. OOE+01 0. 00E+01 1-131 4. 88E+08 7. 64E+07 8. 54E+08 8.59E+08 1.41E+09 2. 84E+11 0. OOE+01 0. OOE+01 1-132 3. 89E+01 9. 95E+01 4. 60E+01 8.45E+01 1.29E+00 3. 92E+01 0. OOE+01 0.00E+01 1-133 5. 48E+06 5. 84E+06 1. 17E+07 1. 45E+07 2.41E+07 2. 69E+09 0. OOE+01 0.OOE+01 1-135 3 .35E+04 5.39E+04 3. 93E+04 7.07E+04 1.08E+05 6. 26E+06 0.00E+01 0.00E+01 Cs-134 4. 78E+09 1.22E+08 1.38E+10 2. 27E+10 7. 03E+09 0.00E+01 2. 52E+09 0.00E+01 Cs-136 1. 14E+09 6. 17E+07 6.39E+08 1 .76E+09 9.36E+08 0.00E+01 1.40E+08 0.00E+01 Cs-137 2. 91E+09 1.23E+08 2. 06E+10 1.97E+10 6.42E+09 0. 00E+01 2. 31E+09 0.OOE+01 Ba-140 4. 36E+06 3.78E+07 7.47E+07 6.54E+04 2. 13E+04 0. 00E+01 3.90E+04 0.OOE+01 Ce-141 9. 73E+02 8.17E+06 1.31E+04 6.55E+03 2.87E+03 0 OOE+01 0.00E+01 0.OOE+01 Ce-144 5. 20E+04 7.96E+07 9. 74E+05 3.05E+05 1 . 69E+05 0. OOE+01 0.00E+01 0.OOE+01 Hf-181 2 .53E+03 4.16E+05 2. 515+04 9. 79E+01 7. 86E+01 8. 24E+01 0. 00E+01 0. 00E+01 3

R Values in units of mrem/yr per ýtCi/m for inhalation and tritium and in units of mrem/yr per ýICi/sec per m-2 for all others.

3-43

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-11 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

, PATHWAY = Cow Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.40E+03 2 .40E+03 0.00E+01 2. 40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 P-32 4.06E+09 1 .42E+09 1. 05E+11 6. 17E+09 0 OOE+01 0. 00E+01 0. OOE+01 0.OOE+01 Cr-51 9. 77E+04 2.85E+06 0. OOE+01 0. 00E+01 1. 39E+04 6. 38E+04 1. 24E+05 0. 00E+01 Mn-54 5.37E+06 8.71E+06 0. 00E+01 2. 37E+07 5. 25E+06 0.00E+01 0.00E+01 0.00E+01 Fe-59 9. 23E+07 1.12E+08 1.34E+08 2 .34E+08 0. OOE+01 0.00E+01 6. 92E+07 0. OOE+01 Co-58 3. 60E+07 3.59E+07 0. 00E+01 1. 44E+07 0. 00E+01 0.OOE+01 0. OOE+01 0. 00E+01 Co-60 1.29E+08 1.30E+08 0. 00E+01 5. 47E+07 0.00E+01 0. OOE+01 0. OOE+01 0.OOE+01 Zn-65 6. 14E+09 1.12E+10 3.88E+09 1. 33E+10 6. 45E+09 0. 00E+01 0.OOE+01 0.00E+01 Rb-86 6. 86E+09 3. 55E+08 0. OOE+01 1.39E+10 0.00E+01 0. OOE+01 0. OOE+01 0.00E+01 Sr-89 2.17E+08 1. 55E+08 7. 55E+09 0 .OOE+01 0. 00E+01 0 . OOE+01 0.OOE+01 0. OOE+01 Sr-90 2.05E+10 1. 00E+09 8. 04E+10 0. 00E+01 0. 00E+01 0. OOE+01 0. 00E+01 0.00E+01 Y-91 1.16E+08 3. 12E+06 4.36E+04 0 OOE+01 0. 00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 7.01E+02 4. 92E+05 4. 05E+03 9 88E+02 1. 06E+03 0.00E+01 0.OOE+01 0. 00E+01 Nb-95 8.48E+04 1.24E+08 3. 56E+05 1. 47E+05 1. 05E+05 0. 00E+01 0. 00E+01 0.00E+01 Ru-103 1.74E+03 6.33E+04 5. 21E+03 0.00E+01 1. 08E+04 0.OOE+01 0.00E+01 0.OOE+01 Ru-106 1.47E+04 8.95E+05 1. 18E+05 0. 00E+01 1. 39E+05 0.00E+01 0. 00E+01 0.00E+01 Ag-IlOM 1.19E+08 9.32E+09 2. 46E+08 1. 80E+08 2. 57E+08 0.OOE+01 0. OOE+01 0.00E+01 Sn-113 6.65E+06 1.37E+07 6. 45E+06 2. 45E+05 1. 31E+05 9.34E+04 0.00E+01 0 00E+01 Sb-124 3.90E+07 3. 88E+08 1. 26E+08 1. 85E+06 0 OOE+01 3.34E+05 7. 88E+07 0 OOE+01 Te-127M 3.75E+07 1.25E+08 3. 10E+08 1. 03E+08 7. 64E+08 8. 96E+07 0.00E+01 0 00E+01 Te-129M 5. 57E+07 2. 16E+08 3 .62E+08 1. 24E+08 9. 05E+08 1.39E+08 0.00E+01 0. 00E+01 1-131 9. 23E+08 7.49E+07 1. 78E+09 2. 10E+09 2. 45E+09 6. 90E+11 0.OOE+01 0 OOE+01 1-132 6.90E+01 1.57E-00 9. 55E+01 1. 94E+00 2. 16E+00 9.09E+01 0. OOE+01 0 OOE+01 1-133 1.05E+07 6. 09E+06 2. 47E+07 3 60E+07 4. 23E+07 6.55E+09 0. 00E+01 0. OOE+01 1-135 5. 93E+04 5. 88E+04 8. 17E+04 1. 63E+05 1. 81E+05 1.46E+07 0. 00E+01 0. 00E+01 Cs-134 4. 19E+09 1. 13E+08 2 . 23E+10 4 15E+10 1. 07E+10 0.OOE+01 4.38E+09 0. 00E+01 Cs-136 1.37E+09 5. 58E+07 1. 25E+09 3 .67E+09 1. 46E+09 0. OOE+01 2.99E+08 0. OOE+01 Cs-137 2.72E+09 1.20E+08 3. 28E+10 3. 84E+10 1.03E+10 0.00E+01 4.18E+09 0. OOE+01 Ba-140 7. 91E+06 3. 77E+07 1.54E+08 1. 54E+05 3.65E+04 0.OOE+01 9.43E+04 0 OOE+01 Ce-141 1. 87E+03 8.21E+06 2.60E+04 1. 59E+04 4. 90E+03 0. OOE+01 0.00E+01 0. 00E+01 Ce-144 7. 82E+04 8. 01E+07 1.40E+06 5. 71E+05 2.31E+05 0. 00E+01 0. 00E+01 0 OOE+01 Hf-181 4.23E+03 3 93 +0 5 4. 78+/-+04 2. 26E+02 1. 3-2+02 1 . 91E+02 0. OOE+01 0 00.E+01 3

R Values in units of mrem/yr per ýLCi/m for inhalation and tritium and in units of mrem/yr per IICi/sec per m-2 for all others.

3-44

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-12 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1. 57E+03 1. 57E+03 0. OOE+01 1. 57E+03 1.57E+03 1. 57E+03 1. 57E+03 1. 57E+03 P-32 5. 19E+08 1.51E+09 1. 34E+10 8. 34E+08 0.00E+01 0.00E+01 0.00E+01 0. 00E+01 Cr-51 2.08E+03 5. 23E+05 0 OOE+01 0. 00E+01 4.58E+02 1.24E+03 2.76E+03 0. 00E+01 Mn-54 1.17E+05 1. 88E+06 0 OOE+01 6. 14E+05 1. 83E+05 0. 00E+01 0.OOE+01 0.OOE+01 Fe-59 2. 08E+05 1. 81E+06 2. 31E+05 5. 42E+05 0. 00E+01 0. OOE+01 1.51E+05 0.OOE+01 Co-58 7. 54E+05 6.82E+06 0. OOE+01 3. 36E+05 0. OOE+01 0.00E+01 0.00E+01 0. 00E+01 Co-60 2. 69E+06 2.29E+07 0 OOE+01 1. 22E+06 0. 00E+01 0.00E+01 0.00E+01 0.00E+01 Zn-65 1. 65E+08 2 .31E+08 1. 15E+08 3. 66E+08 2.45E+08 0. OOE+01 0.00E+01 0.OOE+01 Rb-86 9. 05E+07 3. 83E+07 0. OOE+01 1. 94E+08 0. 00E+01 0.00E+01 0.OOE+01 0.00E+01 Sr-89 5. 24E+07 2.93E+08 1. 83E+09 0. OOE+01 0.OOE+01 0.00E+01 0. OOE+01 0. 00E+01 Sr-90 1.59E+10 1.88E+09 6. 49E+10 0. 00E+01 0. 00E+01 0. OOE+01 0.00E+01 0. 00E+01 Y-91 1.64E+01 3.37E+05 6. 13E+02 0. 00E+01 0. 00E+01 0. OOE+01 0.OOE+01 0-00E+01 Zr-95 1.46E+01 6. 85E+04 6. 74E+01 2. 16E+01 3.39E+01 0.OOE+01 0.OOE+01 0 00E+01 Nb-95 1.78E+03 2. 01E+07 5. 94E+03 3 .31E+03 3.27E+03 0.OOE+01 0.OOE+01 0 OOE+01 Ru-103 3.16E+01 8.56E+03 7. 33E+01 0 .OOE+01 2.80E+02 0. 00E+01 0.00E+01 0. 00E+01 Ru-106 1. 92E+02 9.81E+04 1. 52E+03 0. 00E+01 2.93E+03 0. 00E+01 0.OOE+01 0. OOE+01 Ag-IIOM 2.45E+06 1. 68E+09 4. 46E+06 4. 12E+06 8.11E+06 0. 00E+01 0. OOE+01 0. OOE+01 Sn-113 1. 32E+05 2.44E+06 1. 40E+05 5. 41E+03 3.96E+03 1.90E+03 0.OOE+01 0 00E+01 Sb-124 7.36E+05 5.27E+07 1. 86E+06 3. 51E+04 0.00E+01 4.50E+03 1.44E+06 0 OOE+01 Te-127M 4. 93E+05 1. 36E+07 4. 05E+06 1.45E+06 1.64E+07 1.03E+06 0.00E+01 0 OOE+01 Te-129M 7.43E+05 2.36E+07 4. 69E+06 1. 75E+06 1. 96E+07 1.61E+06 0.00E+01 0. OOE+01 1-131 1. 91E+08 8. 78E+07 2 33E+08 3. 33E+08 5.71E+08 1.09E+11 0.00E+01 0. 00E+01 1-132 1.23E+01 6. 61E-02 1.32E+01 3. 52E+01 5.61E+01 1. 23E+01 0.OOE+01 0 00E+01 1-133 1. 68E+06 4. 95E+06 3. 17E+06 5.51E+06 9.61E+06 8.10E+08 0.OOE+01 0. 00E+01 1-135 1. 08E+04 3.32E+04 1. 12E+04 2.94E+04 4. 71E+04 1.94E+06 0. 00E+01 0 . 00E+01 Cs-134 2.01E+10 4. 31E+08 1. 03E+10 2.46E+10 7.97E+09 0.00E+01 2.65E+09 0 00E+01 Cs-136 1.42E+09 2.24E+08 4. 99E+08 1.97E+09 1.10E+09 0.00E+01 1.50E+08 0. OOE+01 Cs-137 1.27E+10 3.74E+08 1. 41E+10 1.93E+10 6. 56E+09 0. 00E+01 2.18E+09 0 OOE+01 Ba-140 1.35E+05 4.23E+06 2. 06E+06 2. 58E+03 8. 78E+02 0. 00E+01 1.48E+03 0 00E+01 Ce-141 2. 68E+01 9. 03E+05 3. 49E+02 2 .36E+02 1.10E+02 0. OOE+01 0.00E+01 0 OOE+01 Ce-144 1.38E+03 8. 71E+06 2. 58E+04 1.08E+04 6.39E+03 0. OOE+01 0.OOE+01 0. OOE+01 Hf-181 8. 02E+01 5.26E+04 7. 09E+02 3. 99E+00 3.34E+00 2. 54E+00 0.00E+01 0 00E+01 3

R Values in units of mrem/yr per JICi/m for inhalation and tritium and in units of mrem/yr per pCi/sec per m-2 for all others.

3-45

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2 . 04E+03 2 . 04E+03 0.OOE+01 2.04E+03 2. 04E+03 2. 04E+03 2. 04E+03 2. 04E+03 P-32 9.60E+08 2. 08E+09 2.48E+10 1. 53E+09 0. 00E+01 0. OOE+01 0. 00E+01 0. OOE+01 Cr-51 3 .63E+03 6. 10E+05 0.OOE+01 0.00E+01 7.95E+02 2.02E+03 5 18E+03 0.00E+01 Mn-54 2.03E+05 2. 10E+06 0.00E+01 1.02E+06 3.05E+05 0. 00E+01 0. 00E+01 0. OOE+01 Fe-59 3. 63E+05 2. 22E+06 4.03E+05 9. 40E+05 0. 00E+01 0. 00E+01 2. 96E+05 0. OOE+01 Co-58 1.30E+06 7. 80E+06 0. 00E+01 5. 66E+05 0.OOE+01 0.00KE+01 0. OOE+01 0. 00E+01 Co-60 4. 66E+06 2 . 69E+07 0.OOE+01 2 .07E+06 0. 00E+01 0. OOE+01 0. OOE+01 0.00E+01 Zn-65 2.86E+08 2. 60E+08 1.77E+08 6.13E+08 3. 93E+08 0. 00E+01 0 OOE+01 0. OOE+01 Rb-86 1. 66E+08 5 24E+07 0.00E+01 3. 54E+08 0.OOE+01 0 OOE+01 0 OOE+01 0. OOE+01 Sr-89 9.65E+07 4. 01E+08 3.37E+09 0. 00E+01 0. 00E+01 0 .OOE+01 0 00E+01 0.OOE+01 Sr-90 2.27E+I0 2. 58E+09 9.18E+10 0. 00E+01 0. 00E+01 0 OOE+01 0. OOE+01 0.00E+01 Y-91 3. 02E+01 4.62E+05 1. 13E+03 0.OOE+01 0.00E+01 0 OOE+01 0. 00E+01 0. OOE+01 Zr-95 2. 56E+01 8.59E+04 1.18E+02 3.72E+01 5.47E+01 0. OOE+01 0 OOE+01 0. 00E+01 Nb-95 3. 09E+03 2.40E+07 1.01E+04 5.62E+03 5.45E+03 0. 00E+01 0. OOE+01 0.00E+01 Ru-103 5.58E+01 1. 09E+04 1.30E+02 0. OOE+01 4. 60E+02 0. OOE+01 0 00E+01 0. OOE+01 Ru-106 3. 51E+02 1.34E+05 2.79E+03 0.00E+01 5 38E+03 0 00E+01 0.OOE+01 0. 00E+01 Ag-iIOM 4.24E+06 1. 96E+09 7.37E+06 6.97E+06 1. 33E+07 0 OOE+01 0. OOE+01 0.OOE+01 Sn-ll3 2. 28E+05 2. 58E+06 2 . 15E+05 9.06E+03 6. 37E+03 2. 97E+03 0. OOE+01 0. OOE+01 Sb-124 1.29E+06 6.67E+07 3 .31E+06 6.10E+04 0 OOE+01 7. 51E+03 2. 89E+06 0. OOE+01 Te-127M 8.87E+05 1.86E+07 7.46E+06 2. 65E+06 3. 02E+07 1. 77E+06 0.OOE+01 0. 00E+01 Te-129M 1.36E+06 3 . 22E+07 8. 58E+06 3.19E+06 3 .59E+07 2. 77E+06 0. OOE+01 0.OOE+01 1-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1. 02E+09 1. 73E+11 0. OOE+01 0. OOE+01 1-132 2 19E+01 2. 66E+01 2 .33E+01 6. 11E+01 9. 62E+01 2. 06E+01 0. OOE+01 0 OOE+01 1-133 2. 99E+06 7.43E+06 5.79E+06 9. 81E+06 1. 72E+07 1. 37E+09 0. OOE+01 0 OOE+01 1-135 1. 90E+04 5. 63E+04 1.99E+04 5. 13E+04 8. 10E+04 3.30E+06 0. OOE+01 0. OOE+01 Cs-134 1. 96E+10 5.26E+08 1.80E+10 4.23E+10 1.34E+10 0.00E+01 5.13E+09 0. 00E+01 Cs-136 2. 25E+09 2.69E+07 8. 50E+08 3 .34E+09 1. 82E+09 0. OOE+01 2. 87E+08 0. 00E+01 Cs-137 1. 19E+10 4. 85E+08 2. 56E+10 3.41E+10 1.16E+10 0.OOE+01 4. 51E+09 0. 00E+01 Ba-140 2. 39E+05 5.72E+06 3.71E+06 4.55E+03 1. 54E+03 0.OOE+01 3. 06E+03 0 OOE+01 Ce-141 4 .91E+01 1. 22E+06 6.40E+02 4.27E+02 2.01E+02 0. OOE+01 0. OOE+01 0 OOE+01 Ce-144 2. 55E+03 1. 19E+07 4. 74E+04 1.96E+04 1.17E+04 0.00E+01 0. 00E+01 0. 00E+01 Hf -1R8 1 41F+02 6. 34E+04 1 -27E+03 6. 97E+00 S. 80E+00 4.26E+00 0. 00E+01 0. OOE+01

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-46

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 3. 23E+03 3. 23E+03 0.00E+01 3.23E+03 3.23E+03 3 .23E+03 3. 23E+03 3.23E+03 P-32 2 35E+09 1.69E+09 6.11E+10 2.86E+09 0.00E+01 0. 00E+01 0. 00E+01 0. 00E+01 Cr-51 7. 40E+03 3 . 93E+05 0. 00E+01 0.00E+01 1. 12E+03 4. 11E+03 7. 50E+03 0. 00E+01 Mn-54 4. 07E+05 1.28E+06 0. 00E+01 1. 53E+06 4. 29E+05 0 .00E+01 0. 00E+01 0. 00E+01 Fe-59 7. 52E+05 1.57E+06 9.34E+05 1.51E+06 0. 00E+01 0 OOE+01 4. 38E+05 0.00E+01 Co-58 2. 65E+06 5.05E+06 0. OOE+01 8.65E+05 0.00E+01 0.00E+01 0. 00E+01 0.00E+01 Co-60 9. 48E+06 1.78E+07 0. 00E+01 3.21E+06 0. 00E+01 0.00E+01 0. 00E+01 0. 00E+01 Zn-65 5 74E+08 1.62E+08 3.47E+08 9.24E+08 5. 82E+08 0.00E+01 0.00E+01 0.00E+01 Rb-86 4. 04E+08 4.22E+07 0.00E+01 6.57E+08 0. OOE+01 0 OOE+01 0.OOE+01 0. 00E+01 Sr-89 2. 38E+08 3.23E+08 8. 34E+09 0. OOE+01 0.00E+01 0 OOE+01 0.OOE+01 0. OOE+01 Sr-90 3. 93E+10 2.09E+09 1.55E+11 0. 00E+01 0. 00E+01 0. OOE+01 0.00E+01 0.00E+01 Y-91 7. 45E+01 3.71E+05 2.79E+03 0 OOE+01 0. OOE+01 0. 00E+01 0. 00E+01 0. 00E+01 Zr-95 5 36E+01 6.28E+04 2.74E+02 6. 02E+01 8.62E+01 0. 00E+01 0.00E+01 0. 00E+01 Nb-95 6. 37E+03 1. 65E+07 2.29E+04 8. 91E+03 8.37E+03 0.00E+01 0.00E+01 0.00E+01 Ru-103 1. 19E+02 7.98E+03 3.09E+02 0. 00E+01 7.77E+02 0. OOE+01 0.00E+01 0. 00E+01 Ru-106 8. 56E+02 1. 07E+05 6.86E+03 0. 00E+01 9. 27E+03 0. 00E+01 0.OOE+01 0. 00E+01 Ag-lIOM 8. 63E+06 1.28E+09 1.60E+07 1 08E+07 2. 01E+07 0. 00E+01 0.OOE+01 0.OOE+01 Sn-113 4. 61E+05 1. 69E+06 4.22E+05 1.36E+04 9.38E+03 5. 59E+03 0. 00E+01 0. OOE+01 Sb-124 2. 75E+06 4.91E+07 7. 84E+06 1 . 02E+05 0. 00E+01 1. 73E+04 4. 35E+06 0.OOE+01 Te-127M 2. 18E+06 1. 49E+07 1.84E+07 4. 95E+06 5. 24E+07 4.40E+06 0.OOE+01 0.OOE+01 Te-129M 3. 28E+06 2. 58E+07 2. 12E+07 5 91E+06 6. 21E+07 6.82E+06 0.00E+01 0.OQE+01 1-131 5 85E+08 9.17E+07 1. 02E+09 1. 03E+09 1. 69E+09 3 .41E+11 0.00E+01 0. OOE+01 1-132 4 67E+01 1.19E+00 5.52E+01 1. 01E+00 1 55E+00 4. 71E+01 0.00E+01 0.00E+01 1-133 6. 58E+06 7.00E+06 1.41E+07 1. 74E+07 2.90E+07 3 .23E+09 0. 00E+01 0. 00E+01 1-135 4. 01E+04 6. 47E+04 4. 72E+04 8. 49E+04 1. 30E+05 7. 52E+06 0.00E+01 0.00E+01 Cs-134 1. 43E+10 3.67E+08 4.14E+10 6. 80E+10 2.11E+10 0. 00E+01 7. 56E+09 0.00E+01 Cs-136 3 .41E+09 1. 85E+08 1 .92E+09 5.27E+09 2. 81E+09 0. 00E+01 4.19E+08 0.00E+01 Cs-137 8. 72E+09 3 .70E+08 6.17E+10 5.91E+10 1.93E+10 0.00E+01 6.93E+09 0.00E+01 Ba-140 5. 23E+05 4 . 54E+05 8.96E+06 7.85E+03 2. 56E+03 0.00E+01 4. 68E+03 0o.OOE+01 Ce-141 1. 17E+02 9.81E+05 1. 53E+03 7.36E+02 3. 45E+02 0.00E+01 0.OOE+01 0.00E+01 Ce-144 6. 24E+03 9.55E+06 1.17E+05 3.66E+04 2. 03E+04 0.00E+01 0. 00E+01 0. OOE+01 Hf-181 3 - 04,+02 4.99P+04 3.02F+03 1. 175+01 9 431+00 9. 885+00 0. 00+01 0. 00F+01

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per M for all others.

3-47

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 4.90E+03 4. 90E+03 0.OOE+01 4. 90E+03 4.90E+03 4. 90E+03 4. 90E+03 4. 90E+03 P-32 4.88E+09 1. 70E+09 1.26E+11 7.40E+09 0.OOE+01 0.00E+01 0 00E+01 0 OOE+01 Cr-51 1. 17E+04 3 .42E+05 0.00E+01 0.00E+01 1.67E+03 7.65E+03 1.49E+04 0.00E+01 Mn-54 6. 45E+05 1. 04E+06 0. 00E+01 2.84E+06 6. 30E+05 0.00E+01 0 00E+01 0 OOE+01 Fe-59 1.20E+06 1. 45E+06 1. 74E+06 3. 04E+06 0.00E+01 0.00E+01 9. 00E+05 0.00E+01 Co-58 4.31E+06 4. 31E+06 0.00E+01 1.73E+06 0.00E+01 0 OOE+01 0 OOE+01 0. 00E+01 Co-60 1. 55E+07 1. 56E+07 0.00E+01 6.56E+06 0.00E+01 0. 00E+01 0 00E+01 0. 00E+01 Zn-65 7. 36E+08 1. 35E+09 4. 66E+08 1.60E+09 7.74E+08 0. 00E+01 0 00E+01 0 OOE+01 Rb-86 8. 23E+08 4. 26E+07 0. OOE+01 1.67E+09 0. OOE+01 0. 00E+01 0 .00E+01 0.00E+01 Sr-89 4. 55E+08 3. 26E+08 1. 59E+10 0.00E+01 0. 00E+01 0. 00E+01 0 OOE+01 0 OOE+01 Sr-90 4. 30E+10 2. 11E+09 1. 69E+11 0.00E+01 0. OOE+01 0. 00E+01 0 .OOE+01 0 OOE+01 Y-91 1. 39E+02 3 75E+05 5. 23E+03 0.00E+01 0.00E+01 0. 00E+01 0 OOE+01 0.00E+01 Zr-95 8 41E+01 5. 90E+04 4. 85E+02 1.19E+02 1.28E+02 0 OOE+01 0.00E+01 0.00E+01 Nb-95 1. 02E+04 1.48E+07 4.27E+04 1.76E+04 1.26E+04 0 OOE+01 0. 00E+01 0.00E+01 Ru-103 2. 09E+02 7. 60E+03 6. 25E+02 0. 00E+01 1.30E+03 0. OOE+01 0.00E+01 0. OOE+01 Ru-106 1. 77E+03 1. 07E+05 1.41E+04 0. 00E+01 1.67E+04 0. OOE+01 0. 00E+01 0. OOE+01 Ag-IIOM 1. 43E+07 1.12E+09 2. 95E+07 2.16E+07 3.08E+07 0.00E+01 0.00E+01 0. OOE+01 Sn-113 6. 66E+05 1.37E+06 6. 46E+05 2. 45E+04 1.32E+04 9. 34E+03 0.00E+01 0.OOE+01 Sb-124 4. 68E+06 4. 66E+07 1. 51E+07 2.22E+05 0 OOE+01 4. 01E+04 9.46E+06 0.00E+01 Te-127M 4. 51E+06 1. 50E+07 3.72E+07 1 23E+07 9 .16E+07 1. 08E+07 0.00E+01 0.00E+01 Te-129M 6. 69E+06 2. 59E+07 4. 34E+07 1. 49E+07 1. 09E+08 1. 67E+07 0.00E+01 0. 00E+01 1-131 1. 11E+09 8. 99E+07 2. 14E+09 2. 52E+09 2. 94E+09 8. 28E+11 0.00E+01 0.00E+01 1-132 8. 28E+01 1.88E+00 1. 15E+00 2.33E+00 2 59E+00 1.09E+02 0.00E+01 0.00E+01 1-133 1 . 27E+07 7.31E+06 2. 97E+07 4 .32E+07 5 08E+07 7. 86E+09 0.00E+01 0. OOE+01 1-135 7. 11E+04 7.06E+04 9.81E+04 1. 95E+05 2. 17E+05 1. 75E+07 0. OOE+01 0.00E+01 Cs-134 1. 26E+10 3.38E+08 6. 68E+10 1. 25E+11 3.21E+10 0. 00E+01 1.31E+10 0.00E+01 Cs-136 4. 11E+09 1. 67E+08 3.75E+09 1. 10E+10 4. 39E+09 0.00E+01 8.98E+08 0.00E+01 Cs-137 8. 17E+09 3.61E+08 9. 85E+10 1. 15E+11 3. 10E+10 0.00E+01 1.25E+10 0. 00E+01 Ba-140 9. 50E+05 4. 53E+06 1.84E+07 1 .84E+04 4. 38E+03 0. 00E+01 1.13E+04 0.00E+01 Ce-141 2. 24E+02 9. 85E+05 3.13E+03 1. 91E+03 5 88E+02 0. 00E+01 0.OOE+01 0.00E+01 Ce-144 9. 39E+03 9. 61E+06 1. 67E+05 6. 86E+04 2.77E+04 0. 00E+01 0.OOE+01 0.OOE+01 Hf-181 5 08E+02 4.72E+04 5.74E+03 2. 71E+01 1. 58E+01 2. 30E+01 0.00E+01 0.00E+01 3

R Values in units of mrem/yr per pCi/m for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m- for all others.

3-48

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.26E+03 1.26E+03 O.00E+01 1.26E+03 1.26E+03 1. 26E+03 1 .26E+03 1.26E+03 P-32 5. OOE+04 8. 63E+04 1.32E+06 7.70E+04 O.00E+01 O .OOE+01 0.OOE+01 O.OOE+01 Cr-51 9 .9E+01 3.32E+03 0. OOE+01 0. 00E+01 2.28E+01 5.94E+01 1.44E+04 0.00E+01 Mn-54 6. 29E+03 7. 72E+04 O.OOE+01 3. 95E+04 9.83E+03 O.OOE+01 1.40E+06 0. OOE+01 Fe-59 1. 05E+04 1. 88E+05 1. 17E+04 2. 77E+04 O .00E+01 0 .00E+01 1. 01E+06 0. 00E+01 Co-58 2 . 07E+03 1. 06E+05 0. OOE+01 1. 58E+03 O .00E+01 0. 00E+01 9. 27E+05 O.00E+01 Co-60 1. 48E+04 2. 84E+05 0. OOE+01 1. 15E+04 . 00E+01 0. 00E+01 5. 96E+06 O.00E+01 Zn-65 4. 65E+04 5. 34E+04 3.24E+04 1. 03E+05 6. 89E+04 0. 00E+01 8. 63E+05 O.00E+01 Rb-86 5. 89E+04 1. 66E+04 0. 00E+01 1.35E+05 . 00E+01 0. OOE+01 0. OOE+01 O.OOE+01 Sr-89 8.71E+03 3. 49E+05 3. 04E+05 O.00E+01 O .OOE+01 O .OOE+01 1.40E+06 O.OOE+01 Sr-90 6 09E+06 7.21E+05 9. 91E+07 O.00E+01 0. OOE+01 O .00E+01 9.59E+06 O.00E+01 Y-91 1. 24E+04 3. 84E+05 4. 62E+05 O.00E+01 0. OOE+01 O .OOE+01 1.70E+06 O.00E+01 Zr-95 2. 32E+04 1.50E+05 1. 07E+05 3.44E+04 5.41E+04 O .OOE+01 1.77E+06 0. OOE+01 Nb-95 4. 20E+03 1.04E+05 1.41E+04 7. 80E+03 7. 72E+03 O.00E+01 5. 04E+05 O.OOE+01 Ru-103 6. 57E+02 1.10E+05 1. 53E+03 0. 00E+01 5 82E+03 0. 00E+01 5.04E+05 O.00E+01 Ru-106 8. 71E+03 9. 11E+05 6. 90E+04 0. OOE+01 1. 33E+05 0. 00E+01 9.35E+06 O. 00E01 Ag-lIOM 5. 94E+03 3 . 02E+05 1. 08E+04 9. 99E+03 1. 97E+04 0. 00E+01 4.63E+06 0.00E+01 Sn-113 6. 48E+03 2. 48E+04 6.86E+03 2. 69E+02 1. 97E+02 9.33E+01 2.99E+05 0. 00E+01 Sb-124 1 . 24E+04 4.06E+05 3 . 12E+04 5. 88E+02 0 .00E+01 7.55E+01 2. 48E+06 O.OOE+01 Te-127M 1. 57E+03 1.49E+05 1.26E+04 5 76E+03 4. 57E+04 3.28E+03 9. 59E+05 O.OOE+01 Te-129M 1. 58E+03 3. 83E+05 9. 75E+03 4. 67E+03 3. 65E+04 3.44E+03 1.16E+06 O.OOE+01 1-131 2. 05E+04 6.27E+03 2.52E+04 3 .57E+04 6. 12E+04 1.19E+07 0. OOE+01 0.00E+01 1-132 1. 16E+03 4.06E+02 1. 16E+03 3. 25E+03 5. 18E+03 1.14E+05 0. OOE+01 O.OOE+01 1-133 4. 51E+03 8. 87E+03 8. 63E+03 1. 48E+04 2 . 58E+04 2.15E+06 0. OOE+01 O.00E+01 1-135 2. 56E+03 5.24E+03 2. 68E+03 6. 97E+03 1. 11E+04 4.47E+05 O.OOE+01 0. OOE+01 Cs-134 7. 27E+05 1. 04E+04 3.72E+05 8. 47E+05 2. 87E+05 O.00E+01 9.75E+04 0.00E+01 Cs-136 1.10E+05 1. 17E+04 3. 90E+04 1. 46E+05 8. 55E+04 0 .005+01 1.20E+04 0.00E+01 O .OOE+01 Cs-137 4 . 27E+05 8. 39E+03 4 .78E+05 6. 20E+05 2. 22E+05 0. 00E+01 7.51E+04 0. 00E+01 Ba-140 2.56E+03 2. 18E+05 3.90E+04 4. 90E+01 1. 67E+01 0. OOE+01 1.27E+06 O.OOE+01 Ce-141 1. 53E+03 1.20E+05 1. 99E+04 1. 35E+04 6. 25E+03 0. OOE+01 3. 61E+05 O.OOE+01 Ce-144 1. 84E+05 8. 15E+05 3.43E+06 1. 43E+06 8.47E+05 1 00E+01 7.76E+06 0.00E+01 Hf-181 5. 16E+03 1.29E+05 4. 56E+04 2. 57E+02 2.15E+02 5. 995+05 n . 00E+01 3

R Values in units of mrem/yr per pCi//M for inhalation and tritium and in units of mrem/yr per pCi/sec per M-2 for all others.

3-49

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-17 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.27E+03 1. 27E+03 0.OOE+01 1. 27E+03 1.27E+03 1 .27E+03 1.27E+03 1.27E+03 P-32 7. 15E+04 9. 27E+04 1. 89E+06 1. 09E+05 0. 00E+01 0.OOE+01 0. 00E+01 0. 00E+01 Cr-51 1. 35E+02 3. OOE+03 0.00E+01 0. 00E+01 3.07E+01 7.49E+01 2.09E+04 0. 00E+01 Mn-54 8. 39E+03 6.67E+04 0.00E+01 5. 10E+04 1.27E+04 0.00E+01 1. 98E+06 0. 00E+01 Fe-59 1.43E+04 1. 78E+05 1.59E+04 3 . 69E+04 0. 00E+01 0.00E+01 1. 53E+06 0 OOE+01 Co-58 2. 77E+03 9. 51E+04 0.00E+01 2. 07E+03 0. OOE+01 0 00E+01 1.34E+06 0. 00E+01 Co-60 1. 98E+04 2. 59E+05 0.00E+01 1. 51E+04 0. OOE+01 0 OOE+01 8.71E+06 0.00E+01 Zn-65 6. 23E+04 4.66E+04 3 . 85E+04 1.33E+05 8.63E+04 0. 00E+01 1. 24E+06 0.OOE+01 Rb-86 8. 39E+04 1. 77E+04 0. 00E+01 1.90E+05 0.00E+01 0. 00E+01 0. 00E+01 0. 00E+01 Sr-89 1. 25E+04 3.71E+05 4.34E+05 0. 00E+01 0.00E+01 0. 00E+01 2.41E+06 0. OOE+01 Sr-90 6.67E+06 7.64E+05 1.08E+08 0.00E+01 0.00E+01 0. OOE+01 1. 65E+07 0.00E+01 Y-91 1. 77E+04 4. 08E+05 6. 60E+05 0o.00E+01 0.00E+01 0. OOE+01 2. 93E+06 0. 00E+01 Zr-95 3 .15E+04 1. 49E+05 1. 45E+05 4. 58E+04 6.73E+04 0 OOE+01 2. 68E+06 0.00E+01 Nb-95 5.66E+03 9. 67E+04 1. 85E+04 1.03E+04 9. 99E+03 0 .OOE+01 7. 50E+05 0.00E+01 Ru-103 8.95E+02 1. 09E+05 2. 10E+03 0.OOE+01 7.42E+03 0.OOE+01 7.82E+05 0.00E+01 Ru-106 1. 24E+04 9. 59E+05 9.83E+04 0.00E+01 1.90E+05 0o.00E+01 1.61E+07 0.00E+01 Ag-IIOM 7.98E+03 2. 72E+05 1. 38E+04 1.31E+04 2. 50E+04 0.OOE+01 6.74E+06 0. 00E+01 Sn-113 8.68E+03 2. 03E+04 8. 19E+03 3 .44E+02 2.45E+02 1.13E+02 4.27E+05 0. OOE+01 Sb-124 1. 68E+04 3. 98E+05 4.30E+04 7. 94E+02 0. 00E+01 9.76E+01 3. 85E+06 0.00E+01 Te-127M 2.18E+03 1. 59E+05 1. 80E+04 8.15E+03 6. 53E+04 4.38E+03 1. 65E+06 0.00E+01 Te-129M 2.24E+03 4. 04E+05 1.39E+04 6. 57E+03 5.18E+04 4. 57E+03 1. 97E+06 0.OOE+01 1-131 2.64E+04 6.48E+03 3.54E+04 4. 90E+04 8.39E+04 1.46E+07 0. OOE+01 0.00E+01 1-132 1. 57E+03 1.27E+03 1.59E+03 4.37E+03 6. 91E+03 1.51E+05 0.OOE+01 0. OOE+01 1-133 6.21E+03 1. 03E+04 1.21E+04 2.05E+04 3. 59E+04 2 . 92E+06 0.OOE+01 0. OOE+01 1-135 3.48E+03 6. 94E+03 3. 69E+03 9.43E+03 1. 49E+04 6.20E+05 0.00E+01 0.00E+01 Cs-134 5.48E+05 9.75E+03 5. 02E+05 1. 13E+06 3. 75E+05 0.OOE+01 1.46E+05 0.00E+01 Cs-136 1.37E+05 1. 09E+04 5. 14E+04 1.93E+05 1. 10E+05 0.00E+01 1.77E+04 0.00E+01 Cs-137 3. 11E+05 8.48E+03 6. 69E+05 8.47E+05 3. 04E+05 0. OOE+01 1.21E+05 0.00E+01 Ba-140 3. 51E+03 2.28E+05 5. 46E+04 6.69E+01 2. 28E+01 0. OOE+01 2. 03E+06 0.00E+01 Ce-141 2. 16E+03 1.26E+05 2. 84E+04 1.89E+04 8. 87E+03 0. 00E+01 6. 13E+05 0.00E+01 Ce-144 2. 62E+05 8. 63E+05 4. 88E+06 2. 02E+06 1.21E+06 0o.00E+01 1. 33E+07 0.00E+01 Hf-181 7. 04E+03 1.20E+05 6.32E+04 3.48E+02 2.90E+02 2 . 12E+02 9.39E+05 0.00E+01 3

R Values in units of mrem/yr per ýLCi/m for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per m for all others.

3-50

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.12E+03 1.12E+03 0. 00E+01 1. 12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 9. 86E+04 4. 21E+04 2. 60E+06 1. 14E+05 0. 00E+01 0.00E+01 0.00E+01 0. 00E+01 Cr-51 1. 54E+02 1. 08E+03 0. OOE+01 0. 00E+01 2.43E+01 8.53E+01 1.70E+04 0.00E+01 Mn-54 9. 50E+03 2. 29E+04 0. OOE+01 4. 29E+04 1.00E+04 0.00E+01 1.57E+06 0.00E+01 Fe-59 1. 67E+04 7.06E+04 2 . 07E+04 3 34E+04 0.00E+01 0.00E+01 1.27E+06 0.00E+01 Co-58 3.16E+03 3.43E+04 0. 00E+01 1. 77E+03 0.00E+01 0. 00E+01 1.10E+06 0.OOE+01 Co-60 2. 26E+04 9. 61E+04 0. 00E+01 1. 31E+04 0.00E+01 0. 00E+01 7.06E+06 0.00E+01 Zn-65 7. 02E+04 1. 63E+04 4. 25E+04 1. 13E+05 7.13E+04 0. 00E+01 9.94E+05 0.00E+01 Rb-86 1. 14E+05 7. 98E+03 0. 00E+01 1. 98E+05 0.00E+01 0.OOE+01 0.00E+01 0. 00E+01 Sr-89 1. 72E+04 1. 67E+05 5. 99E+05 0. 00E+01 0.00E+01 0.00E+01 2.15E+06 0. OOE+01 Sr-90 6. 43E+06 3 . 43E+05 1. 01E+08 0. 00E+01 0.00E+01 0.00E+01 1.47E+07 0. 00E+01 Y-91 2. 43E+04 1.84E+05 9. 13E+05 0 00E+01 0.00E+01 0.00E+01 2.62E+06 0.00E+01 Zr-95 3 . 69E+04 6. 10E+04 1 90E+05 4. 17E+04 5. 95E+04 0.00E+01 2.23E+06 0. 00E+01 Nb-95 6.54E+03 3.69E+04 2. 35E+04 9. 16E+03 8. 61E+03 0. 00E+01 6.13E+05 0. 00E+01 Ru-103 1.07E+03 4.47E+04 2 .79E+03 0. 00E+01 7.02E+03 0.00E+01 6. 61E+05 0. 00E+01 Ru-106 1.69E+04 4.29E+05 1. 36E+05 0. 00E+01 1. 84E+05 0.00E+01 1.43E+07 0. 00E+01 Ag-lIOM 9. 13E+03 1. OOE+05 1. 68E+04 1. 14E+04 2.12E+04 0. OOE+01 5.47E+06 0. 00E+01 Sn-113 9. 83E+03 7.45E+03 9. 00E+03 2. 91E+02 2. 02E+02 1. 19E+02 3.40E+05 0.00E+01 Sb-124 2. OOE+04 1. 64E+05 5 .73E+04 7. 40E+02 0.00E+01 1.26E+02 3.24E+06 0. 00E+01 Te-127M 3. 01E+03 7. 13E+04 2. 48E+04 8. 53E+03 6.35E+04 6.06E+03 1.48E+06 0. 00E+01 Te-129M 3. 04E+03 1. 81E+05 1. 92E+04 6. 84E+03 5.02E+04 6.32E+03 1.76E+06 0.00E+01 1-131 2. 72E+04 2. 84E+03 4. 80E+04 4. 80E+04 7.87E+04 1.62E+07 0.00E+01 0 00E+01 1-132 1. 87E+03 3.20E+03 2. 11E+03 4. 06E+03 6.24E+03 1.93E+05 0.00E+01 0. 00E+01 1-133 7. 68E+03 5. 47E+03 1. 66E+04 2. 03E+04 3.37E+04 3.84E+06 0.00E+01 0. 00E+01 1-135 4. 14E+03 4.43E+03 4. 91E+03 8. 72E+03 1.34E+04 7. 91E+05 0.00E+01 0. 00E+01 Cs-134 2. 24E+05 3. 84E+03 6. 50E+05 1.01E+06 3.30E+05 0. 00E+01 1.21E+05 0.00E+01 Cs-136 1.16E+05 4.17E+03 6.50E+04 1.71E+05 9. 53E+04 0. 00E+01 1.45E+04 0. 00E+01 Cs-137 1.28E+05 3. 61E+03 9.05E+05 8.24E+05 2.82E+05 0.00E+01 1.04E+05 0.00E+01 Ba-140 4. 32E+03 1. 02E+05 7.39E+04 6. 47E+01 2.11E+01 0.00E+01 1.74E+06 0.00E+01 Ce-141 2. 89E+03 5. 65E+04 3. 92E+04 1. 95E+04 8. 53E+03 0. 00E+01 5.43E+05 0.00E+01 Ce-144 3. 61E+05 3. 88E+05 6. 76E+06 2. 11E+06 1.17E+06 0. 00E+01 1.19E+07 0.00E+01 Hf-181 8. 50E+03 5. 31E+04 8. 44E+04 3.28E+02 2.64E+02 2 . 76E+02 7.95E+05 0.00E+01 3

R Values in units of mrem/yr per gCi/m for inhalation and tritium and in units of 2

mrem/yr per pCi/sec per M- for all others.

3-51

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 6. 46E+02 6.46E+02 0. OOE+01 6. 46E+02 6.46E+02 6. 46E+02 6.46E+02 6.46E+02 P-32 7.73E+04 1. 61E+04 2. 03E+06 1. 12E+05 0. 00E+01 0.00E+01 0. 00E+01 0 00E+01 Cr-51 8. 93E+01 3. 56E+02 0 00E+01 0. 00E+01 1.32E+01 5. 75E+01 1.28E+04 0.00E+01 Mn-54 4. 98E+03 7.05E+03 0. 00E+01 2 . 53E+04 4.98E+03 0.00E+01 9.98E+05 0.00E+01 Fe-59 9.46E+03 2 .47E+04 1 .35E+04 2 35E+04 0. 00E+01 0. 00E+01 1.01E+06 0.00E+01 Co-58 1.82E+03 1.11E+04 0. OOE+01 1. 22E+03 0.00E+01 0.00E+01 7. 76E+05 0 00E+01 Co-60 1. 18E+04 3.19E+04 0. 00E+01 8. 01E+03 0.00E+01 0.00E+01 4. 50E+06 0 00E+01 Zn-65 3. 10E+04 5.13E+04 1. 93E+04 6. 25E+04 3.24E+04 0. 00E+01 6. 46E+05 0. 00E+01 Rb-86 8. 81E+04 3. 03E+03 0. 00E+01 1. 90E+05 0.00E+01 0. 00E+01 0. OOE+01 0. 00E+01 Sr-89 1.14E+04 6. 39E+04 3.97E+05 0. 00E+01 0. 00E+01 0.00E+01 2. 03E+06 0.00E+01 Sr-90 2. 59E+06 1.31E+05 4. 08E+07 0 OOE+01 0. OOE+01 0.00E+01 1.12E+07 0 00E+01 Y-91 1. 57E+04 7.02E+04 5. 87E+05 0. 00E+01 0. OOE+01 0.00E+01 2.45E+06 0.OOE+01 Zr-95 2. 03E+04 2.17E+04 1. 15E+05 2. 78E+04 3. 10E+04 0.00E+01 1. 75E+06 0.00E+01 Nb-95 3. 77E+03 1.27E+04 1.57E+04 6. 42E+03 4. 71E+03 0. OOE+01 4. 78E+05 0.OOE+01 Ru-103 6. 78E+02 1. 61E+04 2. 01E+03 0. 00E+01 4. 24E+03 0. 00E+01 5. 51E+05 0 .00E+01 Ru-106 1. 09E+04 1. 64E+05 8. 67E+04 0. 00E+01 1. 06E+05 0.00E+01 1. 15E+07 0.00E+01 Ag-IIOM 4 . 99E+03 3. 30E+04 9. 97E+03 7. 21E+03 1.09E+04 0.00E+01 3. 66E+06 0.00E+01 Sn-113 4. 89E+03 2. 29E+03 4. 67E+03 1. 74E+02 9. 94E+01 6.73E+01 2. 30E+05 0.00E+01 Sb-124 1.20E+04 5.91E+04 3 .79E+04 5. 56E+02 0. OOE+01 1.00E+02 2.64E+06 0. OOE+01 Te-127M 2.07E+03 2.73E+04 1. 66E+04 6. 89E+03 3 . 75E+04 4. 86E+03 1.31E+06 0.00E+01 Te-129M 2.22E+03 6. 89E+04 1. 41E+04 6. 08E+03 3.17E+04 5. 47E+03 1.68E+06 0.00E+01 1-131 1.96E+04 1. 06E+03 3 .79E+04 4. 43E+04 5.17E+04 1.48E+07 0.00E+01 0.OOE+01 1-132 1.26E+03 1.90E+03 1. 69E+03 3. 54E+03 3.94E+03 1. 69E+05 0.00E+01 0.00E+01 1-133 5. 59E+03 2. 15E+03 1. 32E+04 1. 92E+04 2.24E+04 3.55E+06 0.00E+01 0.00E+01 1-135 2. 77E+03 1. 83E+03 3. 86E+03 7. 59E+03 8.46E+03 6. 95E+05 0. 00E+01 0 OOE+01 Cs-134 7.44E+04 1 . 33E+03 3 .96E+05 7. 02E+05 1. 90E+05 0. 00E+01 7. 95E+04 0. 00E+01 Cs-136 5.28E+04 1. 43E+03 4. 82E+04 1.34E+05 5. 63E+04 0.00E+01 1. 17E+04 0. 00E+01 Cs-137 4. 54E+04 1. 33E+03 5.48E+05 6. 11E+05 1.72E+05 0.00E+01 7 . 12E+04 0. OOE+01 Ba-140 2. 89E+03 3. 83E+04 5. 59E+04 5. 59E+01 1. 34E+01 0.OOE+01 1. 59E+06 0. 00E+01 Ce-141 1. 99E+03 2. 15E+04 2.77E+04 1. 66E+04 5. 24E+03 0. OOE+01 5. 16E+05 0.00E+01 Ce-144 1.76E+05 1. 48E+05 3 .19E+06 1.21E+06 5.37E+05 0. OOE+01 9 .83E+06 0. OOE+01 Hf-181 5 - OSP+03 1 90E+04 5. 65E+04 9 r7.+n9 1 .959+02 2. 25E+02 6 . 73E+05 0.00E+01

R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per M-2 for all others.

3-52

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 Figure 3.1 SHNPP Gaseous Waste Streams rbine Bldg Vent Stack 3A REM - Radiation Effluent Monitor

-TV3536-l (WR) WPB - Waste Processing Bldg RAB - Reactor Auxiliary Bldg Condenser V- Pump REH1V-3534 I FHB - Fuel Handling Bldg WRGM - Wide Range Gas Monitor Condenser Polisher Area No RM - Radiation Monitor Gland Steam WPB Vent Stack 5 RM-lWV-3546-l (WHOM) OHEW S-WV34 WPB Hot k Cold Laundry 4 WPB Office Area Emhaust WPB Cold Laundry Dryers 1 WPB Control Room camke Exhaust WPB Office Areas 1 4 WPB General Areal Exhaust WPB Chiller Room Exhaust 10 Waste Gas Decay Tanks Waste Processing Area Filtered Exhaust WPB Vent Stack 5A ORf-LH-3547-1 (WOMs)

WPB Switchgear Room Exhaust WPB WVACEquip. Room Exhaust WPS Personnel Handling Facility Exhaust WPB Hot & Low Activity Labs Exhaust WPB Lab Areas Exhaust Plant Vent Stack 1 RM-21AV-3509-1SA (WRGM)

X-ILT-3502 -3 Containment Leak Detection Contai-nt Prs-Entry Purge FWO Normal Echaust Worth RFHBAV N-1 ExautNot RWB Norm-l Exhaust W HO N-oral Exhaust South REK-IAV- 3532A RE SAWEmergency Exhaust - RE-IAVW53 OHB Nor-al Exhaust (Oper. FI) South RAO Ventilation System I 35 FHB Normal Exhaust (Oper. FI) North Hydrogen Purge *EM REII-lFL-3508-SA RAB Purge 3-53

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 Figure 3.2 Schematic of Airborne Effluent Release Points 3-54

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 Figure 3.3 SHNPP Condenser Off-Gas System Turbine Building Vent Stack - 3A Blind Flange 3-55

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.1 contains the sample point description, sampling and collection frequency, analysis type, and frequency for various exposure pathways in the vicinity of the SHNPP for the radiological monitoring program.

Figure 4.1-1 shows the exclusion boundary surrounding SHNPP. Figures 4.1-2, 4.1-3, and 4.1-4 show the locations of the various sampling points and TLD locations. Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4.

4-1

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Airborne Particulates and Radioiodine Sampling and Collection Frequency: Continuous operating sampler with sample collection as required by dust loading but at least once per 7 days.

2 Analysis Frequency and Weekly Gross Beta Required Analysis: Weekly 1-131 (charcoal canisters) 4 5 Quarterly Gamma Isotopic '

(Composited by location)

Sample Point ID No. Sample Point, Description', Distance, and Direction 1 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2.6 mi. from site.

2 1.4 mi. S on SR 1134 from SR 1011 intersection.

NNE sector, 1.4 mi. from site.

4 0.7 mi. N on SR 1127 from intersection with US 1.

NNE sector, 3.1 mi. from site.

3 5 Pittsboro (Control Station)

WNW sector from site, > 12 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 47 1.3 mi. N on SR 1912 from intersection of NC 42 SSW sector, 3.4 miles from site 4-2

Shearon Harris Nuclear Power Plant (SHNPP) November 2002 Offsite Dose Calculation Manual (ODCM) Rev. 16 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 1 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2.6 mi. from site.

2 1.4 mi. S on SR 1134 from SR 1011 intersection.

NNE sector, 1.4 mi. from site.

3 HE&EC ENE sector, 1.9 mi. from site.

4 0.7 mi. N on SR 1127 from intersection with US 1 NNE sector, 3.1 mi. from site.

3 5 Pittsboro (Control Station)

WNW sector from site, > 12 mi. from site 6 Intersection of SR 1134 & SR 1135.

NE sector, 0.8 mi. from site.

7 Extension of SR 1134.

E sector 0.7 mi. from site.

8 Dead end of road. Extension of SR 1134.

ESE sector, 0.6 mi. from site.

9 1 mi. S on SR 1130 from intersection of SR 1127, 1115, and 1130.

SE sector, 2.2 mi. from site.

10 SR 1130 S of intersection of SR 1127, 1115, and 1130.

SSE sector, 2.2 mi. from site.

11 SHNPP site.

S sector, 0.6 mi. from site 12 SHNPP site.

SSW sector, 0.9 mi. from site.

13 SHNPP site.

WSW sector 0.7 mi. from site.

14 SHNPP site. Access road to aux. reservoir.

W sector, 1.5 mi. from site.

4-3

Shearon Harris Nuclear Power Plant (SHNPP) November 2002 Offsite Dose Calculation Manual (ODCM) Rev. 16 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 15 SR 1911.

W sector, 2.0 mi. from site.

16 1.2 mi. E of intersection of US 1 and SR 1011.

WNW sector 1.9 mi. from site.

17 Intersection of US 1 and Aux. Res.

NW sector, 1.5 mi. from site.

18 0.2 mi. N on US 1 from Station 17.

NNW sector, 1.4 mi. from site.

19 0.6 mi. E on SR 1142 from intersection of SR 1141.

NNE sector 5.0 mi. from site.

20 US 1 at intersection SR 1149.

NE sector 4.5 mi. from site.

21 1.2 mi. W on SR 1152 from intersection SR 1153.

ENE sector, 4.8 mi. from site.

22 Formerly Ragan's Dairy on SR 1115.

E sector, 4.3 mi. from site.

23 Intersection of SR 1127 and SR 1116.

ESE sector, 4.8 mi. from site.

24 Sweet Springs Church on SR 1116.

SE sector 4.0 mi. from site.

25 0.2 mi. W on SR 1402 from intersection of SR 1400 SSE sector, 4.7 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 27 NC 42 @ Buckhorn United Methodist Church SW sector, 4.8 mi. from site.

28 0.6 mi. on SR 1924 from intersection of SR 1916.

SSW sector, 4.8 mi. from site.

29 Parking lot of Dynea USA, Inc. on SR 1916.

WSW sector, 5.7 mi. from site.

4-4

Shearon Harris Nuclear Power Plant (SHNPP) November 2002 Offsite Dose Calculation Manual (ODCM) Rev. 16 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description', Distance, and Direction 30 Exit intersection of SR 1972 and US 1.

W sector, 5.6 mi. from site.

31 At intersection of SR 1908, 1909, 1910.

WNW sector, 4.7 mi. from site.

32 SR 1008.

NNW sector 6.4 mi. from site.

33 SR 1142. 1.7 mi.from intersection of SR 1141.

NNW sector, 4.5 mi. from site.

34 Apex (Population Center).

NE sector, 8.7 mi. from site.

35 Holly Springs (Population Center).

E sector, 6.9 mi. from site.

36 SR 1393 at intersection of SR 1421.

E sector, 10.9 mi. from site.

37 US 401 at old CP&L office, Fuquay-Varina (Pop. Center).

ESE sector, 9.2 mi. from site.

48 SR 1142. 1.5 mi. from intersection of SR 1141.

N sector, 4.5 mi. from site.

49 SR 1127. 0.3 mi. S from intersection with US 1.

NNE sector, 2.5 mi. from site.

50 SR 1127 W from intersection SR 1115 and 1130.

ESE sector, 2.6 mi. from site.

53 SR 1972 N from intersection of SR 1910 and SR 1972.

NW sector, 5.8 mi. from site.

56 SR 1912 at intersection of SR 1912 and SR 1924.

WSW sector, 3.0 mi. from site.

63 SHNPP Site.

SW sector, 0.6 mi. from site.

67 HE&EC, Sewage Treatment Facility ENE Sector, 1.2 mi. from site.

4-5

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Surface Water Sampling and Collection Frequency: Composite sample5 collected over a monthly period.

Analysis Frequency and Required Analysis: Monthly Gross Beta 4 and Quarterly Gamma Isotopic Sample Point ID No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)3 WSW sector, 6.2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C.

SSE sector, -17 mi. from site.

4-6

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Groundwater Sampling and Collection Frequency: Grab sample collected quarterly Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic 4 and Tritium Sample Point ID No. Sample Point, Descriptioni, Distance, and Direction 39 On-site deep well in the vicinity of the diabase dike SSW sector, 0.7 mi. from site 57 SHNPP Site N. bank of Emergency Service Water (ESW) intake channel, S. of Water Treatment Building.

SSW sector, 0.4 mi. from site 59 SHNPP Site N. side of Old Construction Road.

NNE sector, 0.5 mi. from site 60 SHNPP Site W. bank of Thomas Creek N of Cooling Tower.

ESE sector, 0.5 mi. from site 4-7

Shearon Harris Nuclear Power Plant (SHNPP) December 1997 Offsite Dose Calculation Manual (ODCM) Rev. 10 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Drinking Water Sampling and Collection Frequency: Composite sample5 collected over a two-week period if 1-131 analysis is performed; monthly composite otherwise.

Analysis Frequency and Required Analysis: 1-131 on each composite when the dose6 calculated for the consumption of the water is greater than 1 mrem per yr.

Monthly Gross Beta Monthly Gamma Isotopic4 Quarterly Tritium Sample Point ID No. Sample Point, DescriptionI, Distance, and Direction 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)3 WSW sector, 6.2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C.

SSE sector, -17 mi. from site.

51 SHNPP Water Treatment Building On Site NOTE: H-3 analysis is normally performed monthly.

4-8

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Sediment from Shoreline Sampling and Collection Frequency: Shoreline Sediment sample collected semiannually.

Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic 4 Sample Point ID No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.6 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site.

4-9

Shearon Harris Nuclear Power Plant (SHNPP) June, 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Bottom Sediment Sampling and Collection Frequency: Bottom Sediment sample collected semiannually.

Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic4 Sample Point ID No. Sample Point, Descriptioni, Distance, and Direction 52 Harris Lake in the vicinity of the mixing zone of the cooling tower S sector, 3.8 miles from site.

4-10

Shearon Harris Nuclear Power Plant (SHNPP) November, 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Milk 8 Sampling and Collection Frequency: Grab samples semi-monthly when animals are on9 pasture; monthly at other times.

Analysis Frequency and Required Analysis: Each Sample 1-131 Each Sample Gamma Isotopic4 Sample Point ID No. Sample Point, Description', Distance, and Direction 42 Maple Knoll Dairy on SR 1403 SSE sector, 7.0 mi. from site is no longer in business.

43 Goodwin's Dairy on SR 1134 N sector, 2.2 mi. from site is no longer in business 3

5 Manco's Dairy, Pittsboro (Control Station)

WNW sector from site, > 12 mi. from site 4-11

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Fish Sampling and Collection Frequency: One sample of each of the following semiannually:

1. Catfish (bottom feeders)

2. Sunfish & Largemouth Bass (free swimmers)

Analysis Frequency

!d Analysis: Each sample - Gamma Isotopic 4 on edible portion for each Sample Point ID No. Sample Point, Descriptioni, Distance, and Direction 44 Site varies within the Harris Lake.

45 Site varies above Buckhorn Dam on Cape Fear River (Control Station)3 4-12

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Intentionally Left Page Blank 4-13

Shearon Harris Nuclear Power Plant (SHNPP) November, 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Aquatic Vegetation Sampling and Collection Frequency: Annually Analysis Frequency 4 and Required Analysis: Each sample - Gamma Isotopic Sample Point ID No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site.

61 Harris Lake above Holleman's Crossroads (Control Location)

E sector, 2.5 mi. from site 8

Exposure Pathway and/or Sample: Broadleaf Vegetation (Trees)

Sampling and Collection Frequency: Monthly Analysis Frequency 4 and Required Analysis: Each sample - Gamma Isotopic Sample Point ID No. Sample Point, Description', Distance, and Direction 3

5 Pittsboro (Control Station)

NNW sector, > 12 mi. from site 65 Site Boundary S sector, 1.36 mi. from site 66 Site Boundary SSW sector, 1.33 miles from site 4-14

Shearon Harris Nuclear Power Plant (SHNPP) November, 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 NOTES TO TABLE 4.1 SHNPP Radiological Environmental Monitoring Program

1. Sample locations are shown on Figures 4.1-2, 4.1-3, and 4.1-4. Figure 4.1-5 provides a legend for Figures 4.1-2 through 4.1-4.

2. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.

3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations. All other sample stations that have the potential to be affected by radioactive emissions from plant operations are considered indicator stations.

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

5. Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) relative to the compositing period (e.g., monthly).

6. The dose will be calculated for the maximum organ and age group, using the methodology contained in ODCM Equation 2.2-1.

7. Based on historical meteorology (1976-1987), food product Locations 54 and 55 were added in the summer of 1988 as the off-site locations with the highest predicted D/Q values. Food product locations 43 and 46 were deleted after the 1988 growing season.

8. If no milk animals are available at indicator locations per page 4-11, sampling of Broadleaf Vegetation (trees) per page 4-14 can be substituted.

9. When no milk animals are available at indicator locations, milk sampling of the control location can be reduced to once per month to maintain historical data.

4-15

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Figure 4.1-1 Map of the Site Boundary s1134 SR N R 1127 100 SR 1010 0212 10 II S 11 Miles 1 - Main Reservoir 2- Auxiliary Reservoir 3 - Main Dam 4 - Auxiliary Dam Spillway 5 - Plant 6 - Cooling Tower Blowdown Line 7 - Cooling Tower 8 - Site Boundary for Radioactive Liquid Effluents 9 - Site Boundary for Radioactive Gaseous Effluents 10 - Unrestricted Area B - Boat Ramp W - Wake County - Harris Lake Park 4-16

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 Figure 4.1-2 Environmental Radiological Sampling Points 4-17

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Figure 4.1-3 Environmental Radiological Sampling Points Appro"imat.

Kilometer 4-18

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Figure 4.1-4 Environmental Radiological Sampling Points N

Miles 4-19

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Figure 4.1-5 Environmental Radiological Sampling Points 4-20

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 Figure 4.1-6 Environmental Radiological Sampling Points Legend STATION REFER TO STATION REFER TO NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE FIGURE 1 AP, AC, TL 4.1-4 34 TL 4.1-3 2 AP, AC, TL 4.1-4 35 TL 4.1-3 3 TL 4.1-4 36 TL 4.1-3 4 AP, AC, TL 4.1-4 37 TL 4.1-3 5 AP, AC, MK, TL, BL 4.1-2

38 SW, DW 4.1-2 6 TL 4.1-4 39 GW 4.1-4 7 TL 4.1-4 40 SW, DW 4.1-3

8 TL 4.1-4 41 SS, AV 4.1-4 9 TL 4.1-4 42 MK 4.1-3 10 TL 4.1-4 43 DELETED 4.1-4 11 TL 4.1-4 44 FH 4.1-4 12 TL 4.1-4 45 FH 4.1-2 13 TL 4.1-4 47 AP, AC 4.1-4 14 TL 4.1-4 48 TL 4.1-3 15 TL 4.1-4 49 TL 4.1-4 16 TL 4.1-4 50 TL 4.1-4 17 TL 4.1-4 51 DW 4.1-4 18 TL 4.1-4 52 SD 4.1-4 19 TL 4.1-3 53 TL 4.1-2 20 TL 4.1-3, 4.1-4 21 TL 4.1-3 22 TL 4.1-3 56 TL 4.1-4 23 TL 4.1-3 57 GW 4.1-4 24 TL 4.1-3 25 TL 4.1-3, 4.1-4 59 GW 4.1-4 26 AP, AC, AV, SS, SW, TL 4.1-3, 4.1-4 60 GW 4.1-4 27 TL 4.1-2, 4.1-4 61 AV 4.1-3 28 TL 4.1-2, 4.1-4 29 TL 4.1-2 63 TL 4.1-4 0 TL 4.1-2 31 TL 4.1-2 65 BL 4.1-4 32 TL 4.1-2 66 BL 4.1-4 33 TL 4.1-3 67 TL 4.1-4 AC Air Cartridge DW Drinking Water MK Milk TL TLD AP Air Particulate SD Bottom Sediment AV Aquatic Vegetation FH Fish SS Shoreline Sediment BL Broad Leaf Veg. GW Groundwater SW Surface Water

Approximate location 4-21

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 5.0 INTERLABORATORY COMPARISON STUDIES The objective of this program is to evaluate the total laboratory analysis process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.

Environmental samples from the SHNPP environs are to be analyzed by the Harris Energy & Environmental Center (HE&EC) or by a qualified contracting laboratory.

These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories' performances in the study will be included in the Annual Radiological Environmental Operating Report (see SHNPP ODCM Operational Requirement 4.12.3).

SHNPP E&RC will perform sample analyses for gamma-emitting radionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study.

Radiochemical analyses of composite samples required by ODCM Operational Requirements Tables 4.11-1 and 4.11-2 will be performed by the HE&EC.

The Progress Energy laboratory or vendor laboratory results shall be compared to the criteria established in the NRC Inspection Manual (Procedure 84750) for Radioactive Waste Treatment, Effluent, and Environmental Monitoring. The referenced criteria is as follows:

a) Divide each standard result by its associated uncertainty to obtain resolution (the uncertainty is defined as the relative standard deviation, one sigma, of the standard result as calculated from counting statistics).

b) Divide each laboratory result by the corresponding standard result to obtain the ratio (laboratory result/standard).

c) The laboratory measurement is in agreement if the value of the ratio falls within the limits shown below for the corresponding resolution:

Resolution Ratio

<4 4 - 7 0.5 - 2.0 8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 -200 0.80 - 1.25

>200 0.85 - 1.28 If the Progress Energy laboratory or vendor laboratory results lie outside the ratio criteria, an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation of the evaluation will be available to HNP and will be provided to the NRC upon request.

5-1

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)for ODCM OR 3.11.4 Compliance with 40 CFR 190 as prescribed in ODCM Operational Requirement 3.11.4 must be demonstrated only when one or more of ODCM Operational Requirements 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b is exceeded by a factor of two. Once this occurs, the company has 30 days to submit this report in accordance with Technical Specification 6.9.2.

ODCM Operational Requirement 3.11.4 requires that the annual dose or dose commitment to a member of the public from uranium fuel cycle sources be limited to 25 mrem for the whole body and any organ except the thyroid which is limited to 75 mrem. In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radiation, and any other nearby uranium fuel cycle sources are to be included.

The dose estimates from the gas and liquid effluent pathways to the likely most exposed member of the public can be obtained by using the Regulatory Guide 1.109 and WASH 1258-based NRC codes LADTAP II and GASPAR. This will allow the use of current annual average meteorology X/Q and D/Q values derived from the NRC XOQDOQ (NUREG/CR-2919) Code that is appropriate for the specific location of the receptor and the applicable exposure pathways.

Radiation exposures of members of the public from direct radiation sources (the reactor unit and other primary system components, radwaste, radioactivity in auxiliary systems such as storage tanks, transportation of radioactive material, etc.) will be determined from TLD measurements. Quarterly TLD measurements at locations within three miles of the plant center (inner ring) will be compared with the four-year, pre-operational TLD measurements using methods contained in NBS Handbook 91, "Experimental Statistics," to determine any significant contribution from direct radiation associated with plant operation.

If there is a significant direct radiation component at the TLD location in the sector containing the likely most exposed member of the public then this dose will be added to the doses from effluent pathways derived from LADTAP II and GASPAR.

6.1 Total Dose (COMPLIANCE WITH 40 CFR 190)for ODCM OR F.2 To demonstrate compliance with ODCM Operational Requirement F.2, the ODCM dose equations for noble gases, iodines, particulates, and tritium are used. They provide conservative dose estimates. The X/Q and D/Q valves are based on historical data for the exclusion boundary distances. The liquid dose estimates also use the ODCM equations for dose determination which are added together for demonstration of compliance with 40 CFR 190.

6-1

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 Intentionally left blank.

6-2

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Technical Specification 6.14. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PNSC and the approval of the Plant General Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the areas of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

7-1

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 Sheet 1 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) now conducting business as Progress Energy Carolinas has performed the assessment of the transport and dispersion of the effluent in the atmosphere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC, 1978).

The methodology for this assessment was based on guidelines presented in Regulatory Guide 1.111, Revision 1 (USNRC, 1977). The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.

Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line method described in XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CRC-2919 (USNRC, September 1982) would be used for generating the required analyses of Appendix I. To provide a more realistic accounting of the variability of wind around the plant site, standard terrain/recirculation correction factors (TCF) were used.

A-i

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Sheet 2 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS A twelve-year record of meteorological data was used from the on-site meteorological program at the Shearon Harris Plant. These data consisted of all collected parameters from the normal 10.0 meter tower level for the years 1976-1987. The description of the model used and the computations are presented in NUREG/CRC-2919. The following tables provide the meteorological dilution factors (i.e., the X/Q and D/Q values) utilized to show compliance with ODCM Operational Requirements 3/4.11.2 for noble gases and radioiodines and particulates.

Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for special locations for long-term releases.

Tables A-5 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for ground level releases for standard and segmented distance locations for long-term releases.

Table A-13 SHNPP on-site joint wind frequency distributions for 1976-1987.

The X/Q and D/Q values which are utilized in the appendices are all assumed to be ground level releases.

A-2

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 Sheet 3 of 3 APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS The NRC "XOQDOQ" Program was obtained and installed on the Progress Energy computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological information for the standard distances, and special locations of interest with a terrain/recirculation factor. The input to "XOQDOQ" for ground level releases are presented in Table A-14. The resulting computations will have the'TCFs applied to produce a final atmospheric diffusion estimate for the site.

A-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-1 THROUGH A-4 X/Q and D/Q Values for Long Term Ground Level Releases at Special Locations XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST Table A-I Table A-2 Table A-3 Table A-4 X/Q X/Q X/Q D/Q RELEASE DIRECTION DISTANCE (sec/m3) (sec/m3) (sec/m3) (per m2)

ID TYPE OF LOCATION FROM SITE (MILES) (METERS) NO DECAY 2.3 d DECAY 8.0 d DECAY NO DEPLETED DEPLETED DEPLETED A SITE BOUNDARY S 1.36 2189. 6.1E-06 5.9E-06 5.2E-06 8.8E-09 A SITE BOUNDARY SSW 1.33 2140. 6.OE-06 5.8E-06 5.1E-06 8.7E-09 A SITE BOUNDARY SW 1.33 2140. 5.5E-06 5.4E-06 4.7E-06 7.OE-09 A SITE BOUNDARY WSW 1.33 2140. 4.8E-06 4.7E-06 4.lE-06 5.4E-09 A SITE BOUNDARY W 1.33 2140. 3.6E-06 3.6E-06 3.1E-06 4.1E-09 A SITE BOUNDARY WNW 1.33 2140. 2.8E-06 2.7E-06 2.4E-06 3.3E-09 A SITE BOUNDARY NW 1.26 2028. 2.9E-06 2.8E-06 2.5E-06 3.9E-09 A SITE BOUNDARY NNW 1.26 2028. 3.3E-06 3.2E-06 2.8E-06 5.lE-09 A SITE BOUNDARY N 1.32 2124. 3.8E-06 3.8E-06 3.3E-06 6.6E-09 A SITE BOUNDARY NNE 1.33 2140. 4.1E-06 4.0E-06 3.5E-06 7.9E-09 A SITE BOUNDARY NE 1.33 2140. 3.2E-06 3.2E-06 2.7E-06 7.3E-09 A SITE BOUNDARY ENE 1.33 2140. 2.4E-06 2.4E-06 2.1E-06 6.3E-09 A SITE BOUNDARY E 1.33 2140. 2.0E-06 1.9E-06 1.7E-06 3.8E-09 A SITE BOUNDARY ESE 1.33 2140. 1.8E-06 1.7E-06 1.5E-06 4.SE-09 A SITE BOUNDARY SE 1.33 2140. 2.1E-06 2.1E-06 1.8E-06 5.1E-09 A SITE BOUNDARY SSE 1.33 2140. 3.5E-06 3.4E-06 2.9E-06 6.2E-09 A NEAREST RESIDENT SSW 3.90 6275. 7.8E-07 7.3E-07 5.9E-07 6.8E-10 A NEAREST RESIDENT SW 2.80 4506. 1.3E-06 1.2E-06 1.SE-06 1.2E-09 A NEAREST RESIDENT WSW 4.30 6920. 5.4E-07 5.OE-07 4.SE-07 3.4E-10 A NEAREST RESIDENT W 2.70 4345. 9.2E-07 8.8E-07 7.3E-07 7.3E-10 A NEAREST RESIDENT WNW 2.10 3380. 1.1E-06 1.IE-06 9.1E-07 l.IE-09 A NEAREST RESIDENT NW 1.80 2897. 1.4E-06 1.3E-06 I.IE-06 1.6E-09 A NEAREST RESIDENT NNW 1.50 2414. 2.2E-06 2.2E-06 1.9E-06 3.3E-09 A NEAREST RESIDENT N 2.20 3540. 1.4E-06 1.3E-06 1.IE-06 1.9E-09 A NEAREST RESIDENT NNE 1.70 2736. 2.4E-06 2.4E-06 2.OE-06 4.3E-09 A NEAREST RESIDENT NE 2.30 3701. l.OE-06 l.0E-06 8.5E-07 1.9E-09 A NEAREST RESIDENT ENE 2.00 3219. 1.0E-06 1.0E-06 8.5E-07 2.3E-09 A NEAREST RESIDENT E 1.90 3057. 9.3E-07 9.1E-07 7.7E-07 1.6E-09 A NEAREST RESIDENT ESE 2.70 4345. 4.3E-07 4.1E-07 3.4E-07 7.3E-10 A NEAREST RESIDENT SE 4.70 7562. 1.9E-07 1.8E-07 1.4E-07 2.6E-10 A NEAREST RESIDENT SSE 4.40 7081. 3.6E-07 3.4E-07 2.7E-07 3.7E-10 A GARDEN SSW 3.90 6276. 7.8E-07 7.3E-07 5.9E-07 6.8E-10 A GARDEN SW 2.80 4506. 1.3E-06 1.2E-06 1.0E-06 1.2E-09 A GARDEN WSW 4.30 6920. 5.4E-07 5.0E-07 4.0E-07 3.4E-10 A GARDEN W 3.00 4828. 7.6E-07 7.2E-07 6.0E-07 5.7E-I0 A GARDEN WNW 2.10 3380. lIIE-06 I.IE-06 9.1E-07 i.IE-09 A GARDEN NW 3.80 6116. 3.5E-07 3.3E-07 2.6E-07 2.8E-i0 A GARDEN NNW 1.90 3058. 1.4E-06 1.4E-06 I.IE-06 1.8E-09 A GARDEN N 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A GARDEN NNE 1.70 2736. 2.4E-06 2.4E-06 2.0E-06 4.3E-09 A GARDEN NE 2.30 3701. 1.OE-06 1.0E-06 8.5E-07 1.9E-09 A GARDEN E 4.70 7564. 1.8E-07 1.7E-07 1.3E-07 2.OE-10 A GARDEN ESE 2.80 4506. 4.OE-07 3.9E-07 3.2E-07 6.7E-10 A GARDEN SE 4.70 7562. 1.9E-07 1.8E-07 1.4E-07 2.6E-10 A COW MILK N 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A COW MILK NNE 2.92 4703. 8.5E-07 8.2E-07 6.7E-07 1.2E-09 A MEAT & POULTRY SSW 4.40 7081. 6.3E-07 5.9E-07 4.7E-07 5.2E-10 A MEAT & POULTRY SW 2.80 4506. 1.3E-06 1.2E-06 1.0E-06 1.2E-09 A MEAT & POULTRY WSW 4.30 6920. 5.4E-07 5.OE-07 4.SE-07 3.4E-10 A MEAT & POULTRY W 3.10 4989. 7.2E-07 6.8E-07 5.6E-07 5.3E-10 A MEAT & POULTRY WNW 2.50 4023. 8.1E-07 7.7E-07 6.4E-07 7.2E-10 A MEAT & POULTRY NW 3.80 6116. 3.5E-07 3.3E-07 2.6E-07 2.8E-I0 A MEAT & POULTRY NNW 1.90 3058. 1.4E-06 1.4E-06 1.1E-06 1.8E-09 A MEAT & POULTRY N 2.20 3540. 1.4E-06 1.3E-06 1.IE-06 1.9E-09 A MEAT & POULTRY NNE 1.80 2897. 2.2E-06 2.1E-06 1.8E-06 3.8E-09 A MEAT & POULTRY NE 2.30 3701. 1.0E-06 1.SE-06 8.5E-07 1.9E-09 A MEAT & POULTRY ENE 2.00 3219. 1.OE-06 i.OE-06 8.5E-07 2.3E-09 A MEAT & POULTRY E 4.60 7403. 1.8E-07 1.7E-07 1.4E-07 2.1E-10 A MEAT & POULTRY ESE 4.40 7081. 1.8E-07 1.7E-07 1.3E-07 2.4E-10 A-4

Shearon Oris Nuclear Power Plant (SHNPP) Augus 995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-5 3

Undepleted, No Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m )

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 NO DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUALAVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 1.720E-04 5. 121E-05 2.531E-05 1.246E-05 4.943E-06 2.814E-C06 1.851E-06 1.330E-06 1.015E-CC6 8.077E-C 7 6.637E-07 SSW 1. 571E-04 4.715E-05 2.346E-05 1.158E-05 4.596E-06 2.607E-C06 1.711E-06 1.227E-06 9.341E-C 7 7.424E-C 7 6.093E-07 SW 1.481E-04 4.412E-05 2.182E-05 1.074E-05 4.263E-06 2.428E-C06 1.597E-06 1.148E-06 8.757E-C 7 6.971E-C 7 5.728E-07 WSW 1.295E-04 3.842E-05 1.893E-05 9.308E-06 3.693E-06 2.108E-C06 1. 389E-06 9.995E-07 7.632E-C 7 6.080E-C 7 4.999E-07 W 9.839E-05 2.921E-05 1.440E-05 7.087E-06 2.814E-06 1.605E-C06 1.057E-06 7.608E-07 5. 808E-C 7 4.626E-7 07 3.803E-07 7.430E-05 2.216E-05 1.098E-05 5.420E-06 2.154E-06 1.225E-C06 8.053E-07 5.784E-07 4. 409E-C 7 3.0508E- 07 2.881E-07 NW WNW 6.636E-05 1.996E-05 9.994E-06 4.967E-06 1.982E-06 1.121E-C06 7.339E-07 5.254E-07 3.995E-C07 3.171E-707 2.599E-07 NNW 7.179E-05 2.185E-05 1.1IIE-05 5.570E-06 2.2 34E-06 1.254E-C06 8.166E-07 5.820E-07 4.4098-C 07 3.489E-707 2.853E-07 N 9.224E-05 2.824E-05 1.448E-05 7.277E-06 2.919E-06 1.633E8- 06 1. 060E-06 7.539E-07 5. 701E-C07 4.505E-707 3.678E-07 NNE 9 . 847E-05 3.034E-05 1.560E-05 7.846E-06 3.145E-06 1.754E-C06 1.137E-06 8.070E-07 6. 094E-C07 4.810E-707 3.923E-07 NE 7.892E-05 2.430E-05 1.240E-05 6.194E-06 2.467E-06 1.376E-C06 8.918E-07 6.2333E-07 4.784E-C07 3.777E-( 07 3.081E-07 ENE 5.998E-05 1.845E-05 9.388E-06 4.679E-06 1. 860E-06 1.036E-C06 6.711E-07 4.764E-07 3.597E-7 07 2.839E-7 07 2.316E-07 E 4.903E-05 1.498E-05 7.585E-06 3.779E-06 1.506E-06 8.439E-C07 5.488E-07 3.908E-07 2.959E-C07 2.341E-7 07 1.913E-07 ESE 4.458E-05 1. 361E-05 6.872E-06 3.417E-06 1. 359E-06 7.616E8- 07 4.952E-07 3.527E-07 2. 670E-C07 2.112E- 07 1.726E-07 SE 5.351E-05 1.632E-05 8.255E-06 4.102E-06 1. 629E-06 9.123E8- 07 5.929E-07 4.221E-07 3.195E-C07 2.526E-7 07 2.064E-07 SSE 9. IOIE-05 2 .734E-05 1.361E-05 6.718E-06 2.666E-06 1.509E-C06 9.885E-07 7.081E-07 5.387E-C07 4.278E-C07 3.509E-07 ANNUALAVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 5.589E-07 3.064E-07 2.075E-07 1.263E-07 8.904E-08 6.799E-08 5.459E-08 4.537E-08 3.867E-08 3.360E-08 2.964E-08 SSW 5.126E-07 2.798E-07 1.890E-07 1.147E-07 8.066E-08 6.149E-08 4.930E-08 4.093E-08 3.485E-08 3.026E-08 2.667E-08 SW 4.824E-07 2.645E-07 1.791E-07 1.090E-07 7.686E-08 5.869E-08 4.712E-08 3.916E-08 3.338E-08 2.900E-08 2.558E-08 WSW 4.213E-07 2.315E-07 1.5708-07 9.574E-08 6.758E-08 5.165E-08 4.150E-08 3.451E-08 2.943E-08 2.558E-08 2.257E-08 W 3.205E-07 1.760E-07 1.193E-07 7.275E-08 5.133E-08 3.922E-08 3.151E-08 2.620E-08 2.234E-08 1.941E-08 1.713E-08 WNWM 2.426E-07 1.328E-07 8.985E-08 5.463E-08 3.849E-08 2.937E-08 2.357E-08 1.958E-08 1.668E-08 1.449E-08 1.278E-08 NW 2.185E-07 1.188E-07 8.005E-08 4.839E-08 3.396E-08 2.584E-08 2.069E-08 1.716E-08 1.460E-08 1.266E-08 1.115E-08 NNW 2.392E-07 1.290E-07 8.639E-08 5.181E-08 3.617E-08 2.741E-08 2.187E-08 1.809E-08 1.535E-08 1.329E-08 1.168E-08 N 3.0818-07 1.654E-07 1.105E-07 6.603E-08 4.597E-08 3.478E-08 2.771E-08 2.289E-08 1.940E-08 1.678E-08 1.474E-08 NNE 3.283E-07 1.758E-07 1.171E-07 6.980E-08 4.852E-08 3.665E-08 2.918E-08 2.408E-08 2.040E-08 1.763E-08 1.548E-08 NE 2.579E-07 1.383E-07 9.230E-08 5.512E-08 3.839E-08 2.904E-08 2.315E-08 1.912E-08 1.622E-08 1.403E-08 1.232E-08 ENE 1.938E-07 1.039E-07 6.935E-08 4.142E-08 2.886E-08 2.184E-08 1.741E-08 1.439E-08 1.220E-08 1.056E-08 9.278E-09 E 1.604E-07 8.645E-08 5.789E-08 3.473E-08 2.426E-08 1.840E-08 1.469E-08 1.215E-08 1.032E-08 8.935E-09 7.858E-09 ESE 1.447E-07 7.804E-08 5.228E-08 3.139E-08 2.193E-08 1.664E-08 1.329E-08 1.100E-08 9.341E-09 8.091E-09 7.117E-09 SE 1.730E-07 9.328E-08 6.248E-08 3.750E-08 2.620E-08 1.988E-08 1.588E-08 1.314E-08 1.116E-08 9.665E-09 8.501E-09 SSE 2.950E-07 1.608E-07 1.085E-07 6.575E-08 4.622E-08 3.522E-08 2.823E-08 2.343E-08 1.995E-08 1.732E-08 1.526E-08 A-5

Shearon @ris Nuclear Power Plant (SHNPP) August*95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-6 3

No Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m )

Undepleted, EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 NO DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION FROM SITE .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 S 2.535E-05 5. 667E-06 1. 900E- 06 1. 026E-06 6. 676E- 07 3.185E-07 1.278E- 07 6. 824E-08 4. 545E-08 3 .363E-08 SSW 2.344E-05 5. 264E-06 1.756E- 06 9. 447E-07 6. 129E- 07 2.912E-07 1.161E- 07 6. 172E-08 4. 101E-08 3. 029E-08 SW 2.185E-05 4. 887E-06 1.639E- 06 8. 855E-07 5. 761E- 07 2. 749E-07 1.103E- 07 5. 891E-08 3 .923E-08 2. 903E-08 WSW 1.899E-05 4.236E-06 1.425E- 06 7. 715E-07 5. 028E- 07 2.405E-07 9.683E- 08 5. 184E-08 3 .457E-08 2. 560E-08 W 1.444E-05 3.226E-06 1. 085E- 06 5. 872E-07 3. 826E- 07 1.829E-07 7.358E- 08 3. 937E-08 2. 624E-08 1. 943E-08 WNW 1.099E-05 2.467E-06 8. 265E- 07 4. 459E-07 2. 898E- 07 1.381E-07 5. 528E- 08 2. 948E-08 1. 962E-08 1. 451E-08 NW 9. 975E-06 2.263E-06 7. 538E- 07 4. 041E-07 2. 615E- 07 1.237E-07 4.902E- 08 2.595E-08 1. 719E-08 1. 267E-08 NNW 1. 103E-05 2. 540E-06 8. 395E- 07 4. 462E-07 2. 871E- 07 1. 345E-07 5.254E- 08 2.753E-08 1. 813E-08 1 330E-08 N 1.434E-05 3. 316E-06 1. 090E- 06 5. 771E-07 3 . 702E- 07 1. 727E-07 6.700E- 08 3.494E-08 2. 294E-08 1.680E-08 NNE 1.543E-05 3.572E-06 1.169E- 06 6.169E-07 3 .949E- 07 1. 836E-07 7. 086E- 08 3. 682E-08 2 .413E-08 1.765E-08 NE 1.229E-05 2. 811E-06 9.176E- 07 4. 843E-07 3 .102E- 07 1. 445E-07 5. 595E- 08 2. 918E-08 1. 917E-08 1. 404E-08 ENE 9. 309E-06 2.120E-06 6. 906E- 07 3.642E-07 2 .331E- 07 1.085E-07 4.204E- 08 2.194E-08 1.442E-08 1. 057E-08 E 7. 536E-06 1.717E-06 5. 643E- 07 2. 995E-07 1. 925E- 07 9. 019E-08 3.523E- 08 1. 848E-08 1.218E-08 8.946E-09 ESE 6. 833E-06 1. 551E-06 5. 092E- 07 2. 702E-07 1. 737E- 07 8.141E-08 3. 183E- 08 1. 671E-08 1.102E-08 8. 101E-09 SE 8. 202E-06 1.860E-06 6. 097E- 07 3.233E-07 2. 078E- 07 9.732E-08 3. 803E- 08 1.996E-08 1.317E-08 9. 676E-09 SSE 1. 360E-05 3.052E-06 1. 015E- 06 5.449E-07 3. 530E- 07 1.674E-07 6.657E- 08 3. 536E-08 2.348E-08 1.733E-08 A-6

Shearon fris Nuclear Power Plant (SHNPP) Auguslt*95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-7 Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m 3 )

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 2.300 DAY DECAY, UNDEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROMTHE SITE SECTOR 0.250 0.500 0. 750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 1.712E-04 5. 078E-05 2.500E-05 1.226E-05 4. 824E--06 2. 723E-06 1.776E-06 1.266E-06 9. 571E-07 7.553E- 07 6.153E-07 SSW 1. 564E-04 4. 675E-05 2.318E-05 1.139E-05 4.489E -06 2. 525E-06 1.643E-06 1.168E-06 8. 820E-07 6.951E- 07 5.657E-07 SW 1.474E-04 4. 374E-05 2.154E-05 1.056E-05 4. 158E--06 2.347E-06 1.531E-06 1.091E-06 8.247E-07 6.508E- 07 5.301E-07 WSW 1.289E-04 3. 808E-05 1.869E-05 9.149E-06 3. 600E--06 2. 036E-06 1. 330E-06 9. 484E-07 7. 177E-07 5.667E- 07 4.619E-07 W 9.794E-05 2. 895E-05 1.422E-05 6.966E-06 2 .743E- -06 1.551E-06 1.013E-06 7. 221E-07 5. 464E-07 4.314E- 07 3.515E-07 WNW 7.398E-05 2. 197E-05 1.085E-05 5.331E-06 2. 102E--06 1.185E-06 7.723E-07 5. 499E-07 4. 156E-07 3.278E- 07 2.669E-07 NW 6. 609E-05 1.980E-05 9.879E-06 4.892E-06 1.938E--06 1.087E-06 7. 060E-07 5.014E-07 3.782E-07 2.978E- 07 2.421E-07 NNW 7. 152E-05 2.170E-05 1.099E-05 5. 495E-06 2. 189E -06 1.220E-06 7. 887E-07 5.581E-07 4. 197E-07 3.297E- 07 2.676E-07 N 9.191E-05 2. 805E-05 1.434E-05 7.184E-06 2. 864E -06 1.591E-06 1. 026E-06 7.247E-07 5. 442E-07 4.270E- 07 3.463E-07 NNE 9. 814E-05 3.014E-05 1.546E-05 7.751E-06 3 .088E -06 1.712E-06 1.102E-06 7.770E-07 5.829E-07 4.570E- 07 3.703E-07 NE 7. 865E-05 2.414E-05 1.228E-05 6.117E-06 2 . 422E--06 1.342E-06 8.635E-07 6.091E-07 4.569E-07 3.582E- 07 2.902E-07 ENE 5.978E-05 1. 833E-05 9. 300E-06 4.621E-06 1.825E -06 1.011E-06 6. 499E-07 4.582E-07 3.436E-07 2.693E- 07 2.182E-07 E 4.885E-05 1.487E-05 7. 507E-06 3.729E-06 1.476E -06 8.2 12E-07 5. 301E-07 3.748E-07 2.817E-07 2.212E- 07 1.794E-07 ESE 4.441E-05 1.351E-05 6. 801E-06 3.372E-06 1.332E -06 7. 411E-07 4. 783E-07 3.382E-07 2.541E-07 1.996E- 07 1.619E-07 SE 5.331E-05 1. 621E-05 8.172E-06 4. 047E-06 1.597E -06 8.879E-07 5. 728E-07 4.048E-07 3.042E-07 2.388E- 07 1.937E-07 SSE 9.063E-05 2.712E-05 1.345E-05 6.616E-06 2. 606E -06 1.463E-06 9. 505E-07 6. 753E-07 5.095E-07 4.014E- 07 3.265E-07 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000

-0 500 E0 00 0 s 5.138E-07 2.7008-07 1.755E-07 9.871E-08 6.459E-08 4.597E-08 3.454E-08 2.697E-08 2.167E-08 1.781E- 08 1.490E-08 SSW 4.719E-07 2.472E-07 1.603E-07 8.990E-08 5.871E-08 4.172E-08 3.131E-08 2.442E-08 1.960E-08 1.609E- 08 1.345E-08 SW 4.426E-07 2.324E-07 1.509E-07 8.472E-08 5.532E-08 3.929E-08 2.9468-08 2.296E-08 1.841E-08 1.510E- 08 1.261E-08 WSW 3.858E-07 2.029E-07 1.318E-07 7.405E-08 4.835E-08 3.433E-08 2.574E-08 2.005E-08 1.607E-08 1.317E- 08 1.100E-08 W

2.936E-07 1.544E-07 1.003E-07 5.633E-08 3.678E-08 2.612E-08 1.958E-08 1.525E-08 1.223E-08 1.003E- 08 8.370E-09 WNW 2.228E-07 1.169E-07 7.589E-08 4.259E-08 2.782E-08 1.976E-08 1.482E-08 1.155E-08 9.267E-09 7.602E- 09 6.350E-09 NW 2.019E-07 1.055E-07 6.837E-08 3.834E-08 2.505E-08 1.782E-08 1.339E-08 1.045E-08 8.394E-09 6.896E- 09 5.768E-09 NNW 2.228E-07 1.159E-07 7.490E-08 4.194E-08 2.742E-08 1.953E-08 1.470E-08 1.150E-08 9.252E-09 7.614E- 09 6.378E-09 N

2.880E-07 1.495E-07 9.650E-08 5.401E-08 3.534E-08 2.520E-08 1.898E-08 1.486E-08 1.198E-08 9.868E- 09 8.276E-09 NNE 3.078E-07 1.594E-07 1.028E-07 5.753E-08 3.766E-08 2.687E-08 2.026E-08 1.588E-08 1.281E-08 1.057E- 08 8.872E-09 NE 2.413E-07 1.250E-07 8.065E-08 4.512E-08 2.953E-08 2.106E-08 1.588E-08 1.244E-08 1.003E-08 8.276E- 09 6.949E-09 ENE 1.814E-07 9.395E-08 6.060E-08 3.391E-08 2.220E-08 1.585E-08 1.195E-08 9.369E-09 7.561E-09 6.239E- 09 5.241E-09 E

1.493E-07 7.761E-08 5.014E-08 2.807E-08 1.836E-08 1.308E-08 9.847E-09 7.705E-09 6.205E-09 5.110E- 09 4.284E-09 ESE 1.347E-07 7.005E-08 4.527E-08 2.535E-08 1.659E-08 1.183E-08 8.908E-09 6.974E-09 5.619E-09 4.630E- 09 3.8848-09 SE 1.612E-07 8.378E-08 5.414E-08 3.033E-08 1.985E-08 1.416E-08 1.067E-08 8.353E-09 6.732E-09 5.549E- 09 4.6578-09 2.723E-07 1.425E-07 9.243E-08 5.189E-08 Il *d48-S 2.4168-08 I.8168-08 1.41 9.-nR 1.1408-08 9. 775-09 7.8518-09 A-7

Shearon ris Nuclear Power Plant (SHNPP) Augus*995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-8 3

Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m )

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 2.300 DAY DECAY, UNDEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION FROM SITE .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 S 2.506E-05 5.542E-06 1.825E-06 9. 683E .07 6.192E-07 2. 822E-07 1. 006E-07 4. 636E 08 2.711E-08 1.787E-08 SSW 2.318E-05 5.151E-06 1. 688E-06 8. 926E .07 5.693E-07 2.585E-07 9. 168E-08 4.209E 08 2.455E-08 1. 615E-08 SW 2.159E-05 4.776E-06 1.572E-06 8. 345E 07 5. 334E-07 2.429E-07 8. 636E-08 3.964E 08 2.309E-08 1. 516E-08 WSW 1.876E-05 4.138E-06 1.366E-06 7.261E 07 4. 647E-07 2.119E-07 7. 547E-08 3.463E- 08 2.016E-08 1.323E-08 W 1.427E-05 3. 152E-06 1. 040E-06 5. 528E 07 3.537E-07 1 .613E-07 5. 741E-08 2 .635E- 08 1.534E-08 1. 006E-08 WNW 1.087E-05 2 .412E-06 7. 934E-07 4.205E 07 2.686E-07 1.222E-07 4. 343E-08 1.994E 08 1.162E-08 7. 632E-09 NW 9. 867E-06 2.216E-06 7.259E-07 3.827E 07 2.437E-07 1.104E-07 3.911E-08 1.798E 08 1. 051E-08 6.922E-09 NNW 1.093E-05 2.493E-06 8. 116E-07 4.250E -07 2.694E-07 1.214E-07 4. 281E-08 1. 970E- 08 1.156E-08 7. 641E-09 N 1.421E-05 3 .258E-06 1.056E-06 5. 511E .07 3.486E-07 1. 567E-07 5.515E-08 2. 541E- 08 1.494E-08 9.903E-09 NNE 1. 530E-05 3.513E-06 1.134E-06 5.904E -07 3 . 728E-07 1.672E-07 5.877E-08 2.710E 08 1. 596E-08 1.060E-08 NE 1.218E-05 2.763E-06 8. 893E-07 4. 628E -07 2. 923E-07 1.311E-07 4.608E-08 2. 125E- 08 1.251E-08 8.305E-09 ENE 9.227E-06 2. 084E-06 6.694E-07 3.480E 07 2. 197E-07 9.855E-08 3.464E-08 1.598E- 08 9. 418E-09 .6.261E-09 E 7.464E-06 1.685E-06 5.456E-07 2. 852E -07 1. 806E-07 8. 134E-08 2.866E-08 1.319E- 08 7. 746E-09 5.129E-09 ESE 6.768E-06 1. 523E-06 4. 923E-07 2.574E -07 1. 630E-07 7.341E-08 2.588E-08 1. 193E- 08 7.010E-09 4. 647E-09 SE 8. 124E-06 1. 826E-06 5. 897E-07 3. 080E -07 1.950E-07 8.781E-08 3.096E-08 1.428E- 08 8. 396E-09 5.569E-09 SSE 1.345E-05 2.989E-06 9.771E-07 5.157E-07 3.286E-07 1.491E-07 5.292E-08 2.437E-08 1.426E-08 9.413E-09 A-8

Shearon ris Nuclear Power Plant (SHNPP) Augus1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-9 3

Depleted, 8.0 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m )

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 8.000 DAY DECAY, DEPLETED CORRECTED USING STANDARD OPEN TERRAIN FACTORS ANNUALAVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROMTHE SITE SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 1.625E-04 4.665E-05 2.247E-05 1.085E-05 4.169E-06 2.308E-06 1.482E-06 1.042E-06 7.784E-07 6.080E-07 4.908E-07 SSW 1.485E-04 4.295E-05 2.083E-05 1.009E-05 3.877E-06 2.139E-06 1.369E-06 9.606E-07 7.168E-07 5.590E-07 4.507E-07 SW 1.400E-04 4.019E-05 1.937E-05 9.357E-06 3.594E-06 1.991E-06 1.278E-06 8.984E-07 6.715E-07 5.244E-07 4.233E-07 WSW 1.224E-04 3.499E-05 1.681E-05 8.107E-06 3.113E-06 1.728E-06 1.111E-06 7.818E-07 5.849E-07 4.572E-07 3.693E-07 W 9.300E-05 2.660E-05 1.279E-05 6.173E-06 2.372E-06 1.316E-06 8.458E-07 5.9520-07 4.4520-07 3.479E-07 2.810E-07 WNW 7.023E-05 2.018E-05 9.7530-06 4.721E-06 1.816E-06 1.005E-06 6.444E-07 4.5270-07 3.3820-07 2.640E-07 2.130E-07 NW 6.273E-05 1.819E-05 8.876E-06 4.329E-06 1.672E-06 9.202E-07 5.878E-07 4.1170-07 3.068E-07 2.390E-07 1.925E-07 NNW 6.787E-05 1.991E-05 9.871E-06 4.857E-06 1.886E-06 1.030E-06 6.548E-07 4.567E-07 3.391E-07 2.635E-07 2.117E-07 N 8.721E-05 2.574E-05 1.287E-05 6.346E-06 2.465E-06 1.342E-06 8.505E-07 5.920E-07 4.3890-07 3.404E-07 2.732E-07 NNE 9.311E-05 2.765E-05 1.387E-05 6.844E-06 2.657E-06 1.442E-06 9.123E-07 6.339E-07 4.694E-07 3.637E-07 2.916E-07 NE 7.462E-05 2.215E-05 1.102E-05 5.403E-06 2.084E-06 1.131E-06 7.156E-07 4.974E-07 3.683E-07 2.855E-07 2.289E-07 ENE 5.671E-05 1.6820-05 8.343E-06 4.081E-06 1.571E-06 8.519E-07 5.385E-07 3.741E-07 2.770E-07 2.146E-07 1.721E-07 0 4.635E-05 1.365E-05 6.739E-06 3.295E-06 1.271E-06 6.933E-07 4.401E-07 3.067E-07 2.276E-07 1.767E-07 1.419E-07 0SE 4.214E-05 1.240E-05 6.105E-06 2.980E-06 1. 147E-06 6.256E-07 3.971E-07 2.767E-07 2.054E-07 1.595E-07 1.281E-07 SE 5. 058E-05 1.487E-05 7.335E-06 3.576E-06 1.376E-06 7.495E-07 4.755E-07 3.312E-07 2.457E-07 1.908E-07 1.532E-07 SSE 8. 603E-05 2.491E-05 1.209E-05 5.855E-06 2.249E-06 1.238E-06 7.917E-07 5.547E-07 4.136E-07 3.2230-07 2.597E-07 ANNUALAVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROMTHE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 S 4.064E-07 2.000E-07 1.325E-07 7.280E- 08 4.700E-08 3.317E-08 2.477E-08 1.924E-08 1.538E-08 1.2570-08 1.045E-08 SSW 3.729E-07 1.901E-07 1.208E-07 6.616E- 08 4.2 63E-08 3.004E-08 2.240E-08 1.738E-08 1. 388E-08 1.134E-08 9.424E-09 SW 3.506E-07 1.794E-07 1.1430-07 6.274E- 08 4.049E-08 2.856E-08 2.131E-08 1.654E-08 1.322E-08 1.0790-08 8.973E-09 WSW 3.060E-07 1.569E-07 1.001E-07 5.502E- 08 3.554E-08 2.508E-08 1.872E-08 1.453E-08 1.1610-08 9.487E-09 7.887E-09 W 2.328E-07 1.193E-07 7.609E-08 4.182E- 08 2.701E-08 1.906E-08 1.422E-08 1.104E-08 8.0823E-09 7.2070-09 5.9910-09 WNW 1.764E-07 9.0140-08 5.738E-08 3 .147E- 08 2.030E-08 1. 431E-08 1.068E-08 8.289E-09 6.622E-09 5.409E-09 4.496E-09 NW 1. 591E-07 8.0086E-08 5.1290-08 2.801E- 08 1.8030-08 1. 269E-08 9.462E-09 7.339E-09 5.861E-09 4.7870-09 3.979E-09 NNW 1.746E-07 8.800E-08 5.560E-08 3.019E- 08 1. 936E-08 1.360E-08 1.013E-08 7.848E-09 6.264E-09 5.1150-09 4.2 51E-09 N 2.251E-07 1.132E-07 7.127E-08 3.859E- 08 2.471E-08 1.735E-08 1.291E-08 1.000E-08 7.981E-09 6.516E-09 5.417E-09 NNE 2.401E-07 1.204E-07 7.567E-08 4.089E- 08 2.616E-08 1.835E-08 1. 365E-08 1.057E-08 8. 437E-09 6.8880-09 5.726E-09 NE 1.885E-07 9.461E-08 5.954E-08 3.222E- 08 2.063E-08 1.449E-08 1. 078E-08 8.353E-09 6.668E-09 5.445E-09 4.527E-09 ONE 1.417E-07 7.109E-08 4.473E-08 2.421E- 08 1.551E-08 1.089E-08 8.109E-09 6.285E-09 5.0180-09 4.0990-09 3.409E-09 E 1. 171E-07 5.9020-08 3.724E-08 2.023E- 08 1.298E-08 9.120E-09 6.7910-09 5.2 64E-09 4.2030-09 3.432E-09 2.853E-09 0SE 1.056E-07 5.327E-08 3.363E-08 1.827E- 08 1.173E-08 8.246E-09 6.143E-09 4.7 63E-09 3.803E-09 3. 107E-09 2.583E-09 SE 1.263E-07 6. 369E-08 4.020E-08 2.184E- 08 1.402E-08 9.856E-09 7.343E-09 5.694E-09 4.547E-09 3.7140-09 3.089E-09 SSE 2.140E-07 1.094E-07 6.946E-08 3.801E- 08 2.449E-08 1. 726E-08 1. 288E-08 9.994E-09 7.985E-09 6.524E-09 5.425E-09 A-9

Shearon

is Nuclear Power Plant (SHNPP) August 95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-10 Depleted, 8.0 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/mr3 )

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 8.000 DAY DECAY, DEPLETED CHI/Q (SEC/METER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION FROM SITE .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 S 2.268E-05 4.827E-06 1.526E-06 7.887E-07 4.943E-07 2.186E-07 7.461E-08 3.350E-08 1.935E-08 1.262E-08 SSW 2.097E-05 4.485E-06 1.411E-06 7.263E-07 4.540E-07 1.999E-07 6.785E-08 3.034E-08 1.748E-08 1.138E-08 SW 1.955E-05 4.162E-06 1.316E-06 6.803E-07 4.264E-07 1.885E-07 6.430E-08 2.884E-08 1.664E-08 1.084E-08 WSW 1.698E-05 3.607E-06 1.144E-06 5.925E-07 3.719E-07 1.648E-07 5.637E-08 2.532E-08 1.462E-08 9.524E-09 W 1.292E-05 2.747E-06 8.710E-07 4.510E-07 2.830E-07 1.253E-07 4.285E-08 1.924E-08 1.111E-08 7.236E-09 WNW 9.835E-06 2.101E-06 6.638E-07 3.426E-07 2.145E-07 9.474E-08 3.226E-08 1.446E-08 8.338E-09 5.430E-09 NW 8.924E-06 1.928E-06 6.060E-07 3.109E-07 1.939E-07 8.510E-08 2.875E-08 1.282E-08 7.383E-09 4.806E-09 NNW 9.874E-06 2.166E-06 6.757E-07 3.439E-07 2.133E-07 9.287E-08 3.102E-08 1.375E-08 7.896E-09 5.136E-09 N 1.283E-05 2.828E-06 8.782E-07 4.451E-07 2.753E-07 1.194E-07 3.969E-08 1.754E-08 1.006E-08 6.543E-09 NNE 1.381E-05 3.048E-06 9.423E-07 4.761E-07 2.939E-07 1.271E-07 4.207E-08 1.855E-08 1.064E-08 6.917E-09 NE 1.100E-05 2.398E-06 7.392E-07 3.736E-07 2.307E-07 9.990E-08 3.314E-08 1.464E-08 8.404E-09 5.467E-09 ENE 8.332E-06 1.809E-06 5.563E-07 2.810E-07 1.734E-07 7.506E-08 2.491E-08 1.101E-08 6.323E-09 4.115E-09 E 6.744E-06 1.464E-06 4.542E-07 2.308E-07 1.430E-07 6.224E-08 2.079E-08 9.217E-09 5.296E-09 3.446E-09 ESE 6.115E-06 1.323E-06 4.099E-07 2.083E-07 1.291E-07 5.618E-08 1.878E-08 8.333E-09 4.791E-09 3.119E-09 SE 7.340E-06 1.586E-06 4.908E-07 2.492E-07 1.544E-07 6.717E-08 2.244E-08 9.960E-09 5.728E-09 3.730E-09 SSE 1.217E-05 2.601E-06 8.160E-07 4.191E-07 2.616E-07 1.151E-07 3.899E-08 1.743E-08 1.005E-08 6.550E-09 A-I 0

Shearon ris Nuclear Power Plant (SHNPP) August095 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-11 Deposition Values (D/Q) for Long Term Releases at Standard Distances (m-2)

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 CORRECTED USING STANDARD OPEN TERRAIN FACTORS

*

RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DOWNWIND SECTORS ** * * * * * * **

DISTANCES IN MILES DIRECTION FROM SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 S 2.324E-07 7.857E-08 4.034E-08 1.918E-08 6. 889E- 09 3.417E-09 2.012E-09 1. 317E-09 9.269E-10 6.869E-10 5.294E-10 SSW 2. 171E-07 7.343E-08 3.770E-08 1.792E-08 6.438E- 09 3.193E-09 1.880E-09 1.231E-09 8.662E-10 6.420E-10 4.947E-10 SW 1.740E-07 5.885E-08 3.022E-08 1.437E-08 5.160E- 09 2.559E-09 1.507E-09 9.866E-10 6.942E-10 5.145E-10 3.965E-10 WSW 1. 35SE-07 4. 582E-08 2.353E-08 1.119E-08 4.018E- 09 1.993E-09 1.173E-09 7.682E-10 5.406E-10 4.006E-10 3.087E-10 W 1. 013E-07 3.427E-08 1.759E-08 8.365E-09 3.005E- 09 1.490E-09 8 . 774E-10 5.745E-10 4.042E-10 2.996E-10 2.309E-10 WNW 8.296E-08 2.805E-08 1.440E-08 6.848E-09 2.460E- 09 1.220E-09 7.183E-10 4.703E-10 3.309E-10 2.453E-10 1.890E-10 NW 8.468E-08 2.864E-08 1. 470E-08 6.990E-09 2.511E- 09 1.245E-09 7.332E-10 4.801E-10 3.378E-10 2.503E-10 1.929E-10 NNW 1.105E-07 3.736E-08 1.918E-08 9.120E-09 3.276E- 09 1.625E-09 9.566E-10 6.264E-10 4.408E-10 3.266E-10 2.517E-10 N 1.626E-07 5.499E-08 2.823E-08 1.342E-08 4.821E- 09 2.391E-09 1.408E-09 9.218E-10 6.487E-10 4.807E-10 3.705E-10 NNE 1.985E-07 6.713E-08 3.447E-08 1.639E-08 5.886E- 09 2.919E-09 1,719E-09 1.125E-09 7.919E-10 5.869E-10 4.522E-10 NE 1. 815E-07 6.137E-08 3.151E-08 1.498E-08 5. 381E- 09 2.669E-09 1.571E-09 1.029E-09 7.240E-10 5.366E-10 4.135E-10 ENE 1. 568E-07 5.302E-08 2.723E-08 1.294E-08 4.649E- 09 2.306E-09 1.358E-09 8.890E-10 6.255E-10 4.636E-10 3.572E-10 E 9.595E-08 3.245E-08 1.666E-08 7.920E-09 2.845E- 09 1.411E-09 8.307E-10 5.439E-10 3.827E-10 2.837E-10 2.186E-10 ESE 1.003E-07 3.393E-08 1.742E-08 8.281E-09 2.975E- 09 1.475E-09 8.686E-10 5.688E-10 4.002E-10 2.966E-10 2.286E-10 SE 1.270E-07 4.294E-08 2.205E-08 1.048E-08 3.765E- 09 1.867E-09 1.099E-09 7.199E-10 5.066E-10 3.754E-10 2.893E-10 SSE 1.548E-07 5. 236E-08 2.688E-08 1.278E-08 4.591E- 09 2.277E-09 1.341E-09 8.778E-10 6.177E-10 4.578E-10 3.528E-10 DISTANCES IN MILES DIRECTION FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 S 4.205E-10 1.868E-10 1.132E- 10 5.720E-11 3.462E- 11 2.321E-11 1.663E-11 1.249E-11 9.711E-12 7.757E-12 6.332E-12 SSW 3.930E-10 1.746E-10 1.058E- 10 5.346E-11 3.235E- 11 2.169E-11 1.554E-11 1.167E-11 9.075E-12 7.249E-12 5.917E-12 SW 3.150E-10 1.399E-10 8.476E- 11 4.284E-11 2.593E- 11 1.739E-11 1.246E-11 9.354E-12 7.273E-12 5.810E-12 4.742E-12 WSW 2.453E-10 1.090E-10 6.600E- 11 3.336E-11 2.019E- 11 1.354E-11 .700E-12 97.284E-12 5.663E-12 4.524E-12 3.692E-12 W 1.834E-10 8.148E-11 4.935E- 11 2.495E-11 1. 510E- 11 1.012E-11 7.254E-12 5.447E-12 4.235E-12 3.383E-12 2.761E-12 WNW 1.501E-10 6.670E-11 4.040E- 11 2.042E-11 1.236E- 11 8.287E-12 5.938E-12 4.459E-12 3.467E-12 2.769E-12 2.261E-12 NW 1.533E-10 6.808E-11 4.124E- 11 2.085E-11 1.262E- 1i 8.459E-12 6.062E-12 4.552E-12 3.539E-12 2.827E-12 2.307E-12 NNW 2.000E-10 8.884E-11 5.381E- 11 2.720E-11 1.646E- 11 1.104E-11 7.909E-12 5.939E-12 4.618E-12 3.689E-12 3.011E-12 N 2.943E-10 1.307E-10 7.920E- 11 4.003E-11 2.423E- 11 1.624E-11 1.164E-11 8.740E-12 6.796E-12 5.428E-12 4.431E-12 NNE 3.593E-10 1.596E-10 9.668E- ii 4.887E-11 2.958E- 11 1.983E-11 1.421E-11 1.067E-11 8.296E-12 6.627E-12 5.409E-12 3.285E-10 1.459E-10 11 4.468E-11 2.704E 11 1.813E-11 1.299E-11 9.7 55E-12 7.585E-12 6.059E-12 4.946E-12 NE 8.839E-ENE 2.838E-10 1.261E-10 7.637E- 11 3.860E-11 2.336E- 11 1.566E-11 1.122E-11 8.428E-12 6.553E-12 5.235E-12 4.273E-12 E 1.737E-10 7.714E-11 4.673E- 11 2.362E-11 1.430E- 11 9.585E-12 6.868E-12 5.157E-12 4.010E-12 3.203E-12 2. 614E-12 ESE 1.816E-10 8. 066E-11 4.886E- 11 2.470E-11 1.495E- 11 1.002E-11 7.181E-12 5.393E-12 4.193E-12 3.349E-12 2.734E-12 SE 2.298E-10 1.021E-10 6. 185E- 11 3.126E-11 1.892E- 11 1.269E-11 9.090E-12 6.826E-12 5.307E-12 4.240E-12 3.460E-12 SSE 2.802E-10 1.245E-10 7.541E- ii 3.812E-11 2.307E- ii 1.547E-11 1.108E-11 8.323E-12 6.471E-12 5.169E-12 4.219E-12 A-11

9 Shearon *ris Nuclear Power Plant (SHNPP) Augus 95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-12 Deposition Values (D/Q) for Long Term Releases at Standard Distances (m-2)

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987

RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DOWNWIND SECTORS * ** * * * * * ** * * ** ** *

SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION FROM SITE .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 S 3 .943E-08 8. 077E-09 2 . 109E-09 9.470E- 10 5. 357E-10 2. 060E-10 5. 960E-11 2.362E-11 1.261E- -12 7. 808E-12 SSW 3. 685E-08 7.548E-09 1.971E-09 8.850E- 10 5. 007E-10 1. 925E-10 5.570E-11 2.208E-11 1. 179E- -11 7. 297E-12 SW 2. 953E-08 6. 050E-09 1. 579E-09 7.093E- 10 4. 013E-10 1. 543E-10 4.464E-11 1.769E-11 9.448E- -12 5. 848E-12 WSW 2. 300E-08 4. 710E-09 1.230E-09 5.523E- 10 3. 124E-10 1. 201E-10 3 .476E-11 1.378E-11 7.357E- -12 4. 554E-12 W 1. 720E-08 3. 523E-09 9.196E-10 4.130E- 10 2.337E-10 8. 985E-11 2.599E-11 1.030E-11 5.502E- -12 3. 405E-12 WNW 1. 408E-08 2. 884E-09 7.528E-10 3 .381E- 10 1. 913E-10 7. 356E-11 2.128E-11 8.434E-12 4. 504E- -12 2. 788E-12 NW 1. 437E-08 2. 944E-09 7.685E-10 3 .451E- 10 1.952E-10 7. 508E-11 2.172E-11 8. 609E-12 4. 597E- -12 2. 846E-12 NNW 1. 875E-08 3.841E-09 1.003E-09 4. 503E- 10 2. 548E-10 9. 797E-11 2.834E-11 1.123E-11 5.998E- -12 3. 713E-12 N 2. 760E-08 5.652E-09 1.476E-09 6.627E- 10 3.749E-10 1. 442E-10 4.171E-11 1.653E-11 8.828E- -12 5.464E-12 NNE 3. 369E-08 6. 901E-09 1. 801E-09 8.091E- 10 4. 577E-10 1. 760E-10 5.092E-11 2.018E-11 1.078E- -12 6. 671E-12 NE 3 . 080E-08 6. 309E-09 1.647E-09 7.397E- 10 4.185E-10 1. 609E-10 4. 655E-11 1.845E-11 9.853E- -12 6. 099E-12 ENE 2. 661E-08 5. 451E-09 1.423E-09 6.391E- 10 3. 615E-10 1. 390E-10 4. 022E-11 1.594E-11 8.513E- -12 5. 269E-12 E 1. 628E-08 3. 335E-09 8. 707E-10 3. 911E- 10 2.212E-10 8. 507E-11 2.461E-11 9. 754E-12 5.209E- -12 3 .224E-12 ESE 1. 703E-08 3.487E-09 9. 104E-10 4. 089E- 10 2.313E-10 8. 895E-11 2.573E-11 1.020E-11 5.447E- -12 3 371E-12 SE 2. 155E-08 4. 414E-09 1. 152E-09 5. 176E- 10 2. 928E-10 1. 126E-10 3. 257E-11 1.291E-11 6.894E-12 4. 267E-12 SSE 2. 628E-08 5. 383E-09 1.405E-09 6.311E- 10 3.570E-10 1. 373E-10 3.972E-11 1. 574E-11 8.406E-12 5. 203E-12 A-12

Shearon

is Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM) 0 August95 Rev. 6 TABLE A-13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS A UOAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 1.56 0.014 0.009 0.016 0.012 0.012 0.009 0.021 0.008 0.020 0.016 0.020 0.018 0.015 0.010 0.011 0.009 0.219 3.35 0.425 0.354 0.307 0.219 0.162 0.123 0.116 0.177 0.357 0.329 0.338 0.416 0.163 0.165 0.317 0.334 4.303 5.59 0.307 0.296 0.173 0.060 0.017 0.029 0.020 0.021 0.083 0.257 0.361 0.450 0.145 0.234 0.367 0.356 3.176 8.27 0.008 0.000 0.002 0.000 0.000 0.001 0.000 0.001 0.005 0.011 0.057 0.084 0.033 0.071 0.059 0.044 0.374 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.004 0.004 0.008 0.000 0.001 0.018 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.75 0.66 0.50 0.29 0.19 0.16 0.16 0.21 0.47 0.61 0.78 0.97 0.36 0.49 0.75 0.74 8.09 ATMOSPHERIC STABILITY CLASS B UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.56 0.014 0.015 0.023 0.022 0.017 0.021 0.017 0.018 0.022 0.020 0.032 0.021 0.025 0.013 0.018 0.017 0.314 3.35 0.308 0.269 0.204 0.181 0.151 0.121 0.087 0.133 0.234 0.282 0.323 0.314 0.111 0.142 0.221 0.217 3.298 5.59 0.109 0.087 0.061 0.022 0.021 0.008 0.020 0.022 0.047 0.099 0.160 0.196 0.102 0.151 0.216 0.158 1.478 8.27 0.006 0.000 0.001 0.000 0.000 0.000 0.000 0.001 0.004 0.005 0.031 0.026 0.032 0.053 0.028 0.019 0.205 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.002 0.001 0.003 0.001 0.001 0.010 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.001 TOTAL 0.44 0.37 0.29 0.23 0.19 0.15 0.12 0.17 0.31 0.41 0.55 0.56 0.27 0.36 0.48 0.41 5.31 ATMOSPHERIC STABILITY CLASS C UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.56 0.031 0.031 0.035 0.028 0.023 0.031 0.041 0.037 0.050 0.057 0.069 0.045 0.035 0.029 0.033 0.038 0.610 3.35 0.347 0.287 0.245 0.220 0.152 0.131 0.121 0.150 0.261 0.332 0.375 0.369 0.175 0.192 0.246 0.261 3.874 5.59 0.139 0.081 0.039 0.036 0.008 0.009 0.014 0.027 0.029 0.112 0.160 0.192 0.117 0.115 0.199 0.145 1.423 8.27 0.007 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.001 0.008 0.019 0.023 0.012 0.055 0.024 0.015 0.164 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.003 0.002 0.002 0.000 0.000 0.009 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.52 0.40 0.32 0.28 0.18 0.17 0.18 0.22 0.34 0.51 0.63 0.63 0.34 0.39 0.50 0.46 6.08 ATMOSPHERIC STABILITY CLASS D UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.002 0.002 0.002 0.002 0.001 0.001 0.001 0.001 0.002 0.002 0.002 0.001 0.001 0.001 0.001 0.001 0.025 1.56 0.434 0.506 0.444 0.370 0.329 0.266 0.278 0.300 0.362 0.481 0.465 0.346 0.287 0.258 0.269 0.346 5.739 3.35 1.759 2.054 1.350 0.964 0.624 0.523 0.556 0.742 1.058 1.346 1.316 1.177 0.647 0.583 0.746 1.025 16.471 5.59 0.556 0.491 0.330 0.114 0.066 0.076 0.100 0.190 0.220 0.376 0.550 0.462 0.260 0.402 0.523 0.558 5.271 8.27 0.055 0.023 0.004 0.011 0.004 0.006 0.005 0.023 0.032 0.047 0.069 0.075 0.042 0.092 0.062 0.063 0.610 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.001 0.001 0.008 0.017 0.000 0.004 0.000 0.000 0.032 11.62 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 TOTAL 2.81 3.08 2.13 1.46 1.02 0.87 0.94 1.26 1.68 2.25 2.41 2.08 1.24 1.34 1.60 1.99 28.15 A-13

Shearon

is Nuclear Power Plant (SHNPP) August95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION ATMOSPHERIC STABILITY CLASS E UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.005 0.007 0.006 0.005 0.004 0.003 0.004 0.006 0.009 0.009 0.005 0.004 0.003 0.002 0.003 0.003 0.079 1.56 0.747 0.962 0.824 0.692 0.518 0.480 0.536 0.818 1.244 1.183 0.723 0.492 0.415 0.312 0.405 0.466 10.816 3.35 1.028 0.855 0.549 0.329 0.309 0.266 0.356 0.577 1.058 1.547 1.029 0.744 0.488 0.459 0.660 0.667 10.920 5.59 0.124 0.032 0.046 0.029 0.019 0.028 0.032 0.080 0.138 0.148 0.216 0.145 0.067 0.101 0.085 0.131 1.421 8.27 0.007 0.003 0.000 0.002 0.002 0.004 0.006 0.006 0.016 0.010 0.015 0.026 0.010 0.003 0.003 0.008 0.120 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.003 0.004 0.000 0.001 0.000 0.000 0.008 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 1.91 1.86 1.42 1.06 0.85 0.78 0.93 1.49 2.47 2.90 1.99 1.41 0.98 0.88 1.16 1.28 23.36 ATMOSPHERIC STABILITY CLASS F UMAX (M/S) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.34 0.018 0.018 0.017 0.014 0.011 0.009 0.011 0.015 0.018 0.019 0.012 0.009 0.008 0.007 0.007 0.011 0.203 1.56 0.777 0.788 0.735 0.621 0.500 0.414 0.489 0.667 0.803 0.857 0.553 0.395 0.341 0.291 0.321 0.467 9.017 3.35 0.349 0.159 0.072 0.071 0.056 0.033 0.043 0.046 0.128 0.192 0.176 0.144 0.098 0.106 0.098 0.154 1.925 5.59 0.003 0.001 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.001 0.006 0.001 0.000 0.000 0.000 0.002 0.015 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.001 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.62 0.000 0.000 0.000 0.000 0.000 0. 000" 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 1.15 0.97 0.82 0.71 0.57 0.46 0.54 0.73 0.95 1.07 0.75 0.55 0.45 0.40 0.43 0.63 11.16 ATMOSPHERIC STABILITY CLASS G UMAX (M/S) N NNE NE ENE EESE SE SSE S SSW SW WOW W WNW NW NNW TOTAL 0.34 0.360 0.317 0.316 0.284 0.214 0.154 0.121 0.108 0.128 0.128 0.112 0.085 0.077 0.071 0.085 0.176 2.737 1.56 1.932 1.699 1.692 1.522 1.146 0.823 0.649 0.580 0.684 0.688 0.600 0.457 0.414 0.381 0.455 0.945 14.668 3.35 0.162 0.032 0.024 0.021 0.009 0.012 0.012 0.007 0.007 0.008 0.026 0.023 0.014 0.015 0.021 0.047 0.439 5.59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.001 0.001 0.003 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 2.45 2.05 2.03 1.83 1.37 0.99 0.78 0.70 0.82 0.82 0.74 0.57 0.51 0.47 0.56 1.17 17.85 OVERALL WIND DIRECTION FREQUENCY N NNE NE ENE E ESE SE SSE S SSW SW WOW W WNW NW NNW TOTAL FREQUENCY: 10.0 9.4 7.5 5.9 4.4 3.6 3.7 4.8 7.0 8.6 7.8 6.8 4.1 4.3 5.5 6.7 100.0 A-14

Shearon @rris Nuclear Power Plant (SHNPP)

Offsite Dose Calculation Manual (ODCM) 0 Augus*95 Rev. 6 TABLE A-13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP Period of Record : 01/01/76 - 12/31/87 TOTAL HOURS CONSIDERED ARE *****

OVERALL WIND SPEED FREQUENCY MAX WIND SPEED (M/S): 0.335 1.565 3.353 5.588 8.270 11.176 11.623 AVE WIND SPEED (M/S): 0.168 0.950 2.459 4.470 6.929 9.723 11.400 WIND SPEED FREQUENCY: 3.05 41.38 41.23 12.79 1.48 0.08 0.00 THE CONVERSION FACTOR APPLIED TO THE WIND SPEED CLASSES IS 0.447 DISTANCES AND TERRAIN HEIGHTS IN METERS AS FUNCTIONS OF DIRECTION FROM THE SITE:

DIRECTION = S SSW SW WSW W WNW NW NNW N NNE NE ENE E ESE SE SSE DISTANCE 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 2140. 2140. 2140. 2140. 2140.

ELEVATION 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 0.00 DIAMETER (METERS) 0.00 EXIT VELOCITY (METERS) 0.00 REP. WIND HEIGHT (METERS) 10.0 BUILDING HEIGHT (METERS) 55.0 BLDG.MIN.CRS.SEC.AREA (SQ.METERS) 2161.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

WIND MEASURED AT 12.0 METERS.

A-15

Shearon *ris Nuclear Power Plant (SHNPP) August095 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type Columns Variable Name Format Description Value used in XOQDOQ Card Type 1 is an array (KOPT) of options, such that 1 = DO, 0 = BYPASS.

These options remain in effect for all release points run. Thus, all release points must have the same assumptions.

1 1 KOPT(1) Il Option to distribute calms as the first wind-speed class 0 (if calms are already distributed by direction in Card Type 6, KOPT(l) = 0, and Card Type 5 is blank). If KOPT(1) = 1, the calm values of Card Type 5 are distributed by direction in the same proportion as the direction frequency of wind-speed class two.

1 2 KOPT(2) Ii Option to input joint frequency distribution data as 0 percent frequency.

1 3 KOPT(3) Ii Option to compute a sector spread for comparison with 1 centerline value in purge calculation (Normally = 1).

1 4 KOPT(4) Ii Option to plot short-term X/Q values versus probability 0 of occurrence (Normally = 0).

1 5 KOPT(5) Ii Option to use cubic spline in lieu of least square 0 function for fitting intermittent release distribution (Normally = 1).

1 6 KOPT(6) Ii Option to punch radial segment X/Q and D/Q values 1 (Normally = 1).

1 7 KOPT(7) Ii Option to punch output of X/Q and D/Q values of the 1 points of interest (Normally = 1).

1 8 KOPT(8) Ii Option to correct X/Q and D/Q values for open terrain 1 recirculation.

1 9 KOPT(9) Ii Option to correct X/Q and D/Q values using site specific 0 terrain recirculation data.

A-16

Shearon h*ris Nuclear Power Plant (SHNPP) Augus095 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type Columns Variable Name Format j Description I Value used in XOQDOQ 1 10 KOPT(10) Ii Option to use desert sigma curves (Normally = 0) 0 1 11 KOPT(II) Il Option to calculate annual X/Q with 30 degree sectors 0 for North, East, South and West and 20 degree sectors for all others. (Normally = 0, and the code will use 22-1/2 degree sectors) 2 1 - 80 TITLM 20A4 The main title printed at the beginning of the output. N/A 3 1 -5 NVEL I5 The number of velocity categories (maximum of 14). 7 3 6 - 10 NSTA I5 The number of stability categories (maximum of 7) (1 7 always equals Pasquill stability class A, 2 = B.

7 = G).

3 11 - 15 NDIS I5 The number of distances with terrain data for each 1 sector. The number of distances must be the same for each sector (Card Type 10) (maximum of 10).

3 16 - 20 INC 15 The increment in percent for which plotted results are 15 printed out (Normally = 15).

3 21 - 25 NPTYPE 15 The number of titles of receptor types (cow, garden, 5 etc.) (Card Type 13) (maximum of eight) 3 26 - 30 NEXIT 15 The number of release exit points (maximum of five). 1 3 31 - 35 NCOR 15 The number of distances of site specific correction 1 factors for recirculation (maximum of 10).

4 1 - 5 PLEV F5.0 The height (in meters, above ground level) of the 12.0 measured wind presented in the joint frequency data (Card Type 7). (For elevated/ground-level mixed release, use the 10-meter level winds).

A-17

Shearon # is Nuclear Power Plant (SHNPP) AugusQe 5 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type Columns Variable Name Format Description Value used in XOQDOQ 4 6 - 20 DECAYS(I) 3F5.0 For each I: The half-life (days) used in the X/Q 101.00 I = 1,3 calculations: if DECAYS > 100, no decay will occur; if 2.30 DECAYS < 0, depletion factor will be used in the X/Q -8.00 calculations; if DECAYS = 0, X/Q will not be calculated. (Normally, DECAYS(l) = 101, (2) = 2.26, (3) = -8.00.)

4 21 - 25 PLGRAD F5.0 Plant grade elevation (feet above sea level). If 0.00 PLGRAD = 0.0, DIST and HT data Card Type 10 and 11 must be in meters. If PLGRAD < 0.0, DIST in miles and HT data in feet above plant grade. If PLGRAD > 0.0 above DIST in miles and HT data in feet above sea level.

5 1 - 35 CALM(I) 7F5.0 The number of hours, or percent, of calm for each BLANK I = 1,NSTA stability category; if KOPT(1) = 0, insert blank card.

(Note: I = 1 is stability class A, 2 = B...... 7 = G).

6 1 - 80 FREQ(K,I,J) The joint frequency distribution in hours (or percent). (1)

K = 1,16 The values for 16 (K) sectors are read on each card for I = 1,NVEL (if each combination of wind-speed class (I) and stability KOPT(1)=0) class (J) . The loop to read these value cycles first I = 2,NVEL (if on direction continuing in a clockwise fashion), then KOPT(1)=l) on wind class and finally on stability class.

J = 1,NSTA 7 1 - 5 UCOR F5.0 A correction factor applied to wind-speed classes. If 200.

UCOR < 0: no corrections will be made. If UCOR > 100:

the wind-speed classes will be converted from miles/hour to meters/second.

A-18

Shearon ris Nuclear Power Plant (SHNPP) AugusQ95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type Columns [ Variable Name Format Description T Value used in XOQDOQ 7 6 - 75 UMAX(I) 14F5.0 The maximum wind speed in each wind-speed class, 0.75, 3.50, 7.50, 12.50, in either miles/hour or meters/second. (If given 18.50, 25.00, 26.00 in miles/hour, set UCOR > 100.)

Card Types 8 and 9 are read in for each correction factor and distance given, I = 1,NCOR 8 1 - 80 VRDIST(K,I) 16F5.0 The distance in meters at which correction factors All Distances = 1.0 K = 1,16 are given. These values are read in beginning with south and proceeding in a clockwise direction (maximum of 10).

9 1 - 80 VRCD(K,I) 16F5.0 Correction factor to be applied to X/Q and D/Q All Factors = 1.000 K = 1,16 values corresponds to distances specified in

_VRDIST.

Card Types 8 and 9 are repeated for the remaining distances and correction factors.

Card Types 10 and 11 are read in for each terrain distance and height given, I = I,NDIS 10 1 - 80 DIST(K,I) 16F5.0 The distance in meters at which terrain heights Distance = Site Boundary K = 1,16 are given. These values are read in beginning Distance with south and proceeding in a clockwise direction (maximum of ten distances).

11 1 - 80 HT(K,I) 16F5.0 The terrain heights (in meters, above plant grade All Heights = 0.0 K = 1,16 level) corresponding to the distances specified in the DIST array (Card Type 10). These values are read in the same order as the DIST array. For a given direction and distance, the terrain height should be the highest elevation between the source and that distance anywhere within the direction sector.

Card Types 10 and 11 are repeated for the remaining distances and heights.

A-19

Shearon

is Nuclear Power Plant (SHNPP) AugustO95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type I Columns Variable Name Format I Description Value used in XOQDOQ 12 1 - 25 NPOINT(I) 515 The number (maximum of 30) of receptor locations for a 16,15,13,2,0,11 I = 1,NPTYPE particular receptor type (such as the number of cows, gardens, or site boundaries).

Card Types 13 and 14 are read in for each receptor type, thus I = 1,NPTYPE 13 1 - 16 TITLPT(I,J) 4A4 The title (cows, gardens, etc.) of the receptor type Site Boundary = 16 for the receptor locations (Card Type 14) (a maximum of Nearest Resident = 15 16 spaces). Garden = 13 Cow Milk 2 Goat Milk = 0 Meat & Poultry = 11 14 1 - 80 KDIR(I,N) 8(I5,F5.0) The receptor direction and distance. KDIR is the See Table A-1 PTDIST(I,N) direction of interest, such that 1 = South, 2 =

SSW ....... 16 = SSE, PTDIST is the distance, in meters, N = I,NPOINT(I) to the receptor location.

Card Types 13 and 14 are repeated for the remaining receptor types.

Card Types 15, 16 and 17 are read in for each plant release point, thus I = I,NEXIT.

15 1 - 80 TITLE(I,J) 20A4 The title for the release point whose characteristics (1) are described on Card Types 16 and 17.

16 1 - 5 EXIT(I) F5.0 The vent average velocity (meters/second). (Note: if a 0 100% ground-level release is assumed, set EXIT = 0, DIAMTR = 0, and SLEV = 10 meters).

16 6 - 10 DIAMTR F5.0 The vent inside diameter (meters). 0 16 11 - 15 HSTACK(I) F5.0 The height of the vent release point (meters, plant 0.0 grade level). If release is 100% elevated, input negative of height.

16 16 - 20 HBLDG(I) F5.0 The height of the vent's building (meters, above plant 55.0 grade level).

A-20

Shearon Wis Nuclear Power Plant (SHNPP) August*95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type Columns Variable Name Format Description Value used in XOQDOQ 16 21 - 25 CRSEC(I) F5.0 The minimum cross-sectional area for the vent's 2161.0 building (square meters).

16 26 - 30 SLEV(I) F5.0 The wind height used for the vent elevated release 10.0 (meters, above plant grade level).

16 31 - 35 HEATR(I) F5.0 The vent heat emission rate (cal/sec) (Normally = 0). 0.0 17 1 RLSID(I) Al A one letter identification for the release point. A 17 2 - 5 IPURGE(I) 14 IPURGE = 1, 2 or 3 if the vent has intermittent 0 releases. The 1, 2, or 3 corresponds to DECAYS(l),

DECAYS(2), or DECAYS(3) (Card Type 4), respectively, whichever is used as the base for intermittent release calculations (normally no decay/no deplete X/Q, such that IPURGE(I) = 1; if a vent has no intermittent releases, IPURGE = 0.

17 6 - 10 NPURGE(I) 15 The number of intermittent releases per year for this 0 release point.

17 11 - 15 NPRGHR(I) 15 The average number of hours per intermittent release. 0 Card Types 15, 16, and 17 are repeated for the remaining release points.

Card Types 1 - 17 may be repeated for the next case.

A-21

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX B Sheet 1 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with ODCM Operational Requirement 3.11.2.1.b and Appendix I of 10CFR50 for gaseous effluents. These dose parameters, Pi and Ri, were calculated using the methodology outlined in NUREG 0133 along with Regulatory Guide 1.109, Revision 1. The following sections provide the specific methodology which was utilized in calculating the Pi and Ri values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively).

B.l Calculation of Pi The dose parameter, Pi, contained in the radioiodine and particulates portion of Section 3.2 includes only the inhalation pathway transport parameter of the "i" radionuclide, the receptor's usage of the pathway media, and the dosimetry of the exposure. Inhalation rates and the internal dosimetry are functions of the receptor's age; however, under the exposure conditions for ODCM Operational Requirement 3.11.2.1b, the child is considered to receive the highest dose. The values for P.

lI presents the highest dose to any organ including the whole body resulting from inhalation of radionuclide "i" by a child. The following sections provide in detail the methodology which was used in calculating the Pi values for inclusion into this ODCM.

The age group considered is the child because the bases for the ODCM Operational Requirement 3.11.2.1.b is to restrict the dose to the child's thyroid via inhalation to

1500 mrem/yr. The child's breathing rate is taken as 3700 m3 /yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFAi, are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi. The total body is considered as an organ in the selection of DFAi.

B-i

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 APPENDIX B Sheet 2 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.l Calculation of Pi (continued)

The evaluation of this pathway consists of estimating the maximum dose to the most critical organ received by a child through inhalation by:

P. : K'(BR) DFAi (B.1-1) 1I where:

P. = Dose parameter for radionuclide "i" for the inhalation pathway, mrem/yr 1I per tCi/m3 K' = A constant of unit conversion;

= 106 pci/ýtci; BR = The breathing rate of the children's age group, m3 /yr; DFAi = The maximum organ inhalation dose factor for the children's age group for radionuclide "i," mrem/pCi.

The incorporation of breathing rate of a child (3700 m3 /yr) and the unit conversion factor results in the following equation:

P 3.7 E+09 DFAi (B.1-2) 11 B-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX B Sheet 3 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2 Calculation of Ri The basis for ODCM Operational Requirement 3.11.2.3 states that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. Underestimation of the dose can be avoided by assigning a theoretical individual to the exclusion boundary in the sector with the highest X/Q and D/Q values and employing all of the likely exposure pathways, e.g., inhalation, cow milk, meat, vegetation, and ground plane. Ri values have been calculated for the adult, teen, child, and infant age groups for the inhalation, ground plane, cow milk, goat milk, vegetable, and beef ingestion pathways.

The methodology which was utilized to calculate these values is presented below.

B-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 APPENDIX B Sheet 4 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.1 Inhalation Pathway The dose factor from the inhalation pathway is calculated by:

R. = K' (BR)a (DFAi)a (B.2-1) where:

R = Dose factor for each identified radionuclide "i" of the organ of i1 3

interest, mrem/yr per jICi/m ;

K' = A constant of unit conversion;

= 106 pci/ýtci; (BR)a = Breathing rate of the receptor of age group "a," m3 /yr; (DFAi)a= Organ inhalation dose factor for radionuclide "i" for the receptor of age group "a", mrem/pCi.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision 1.

Age Group (a) Breathing Rate (m3 /yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.

B-4

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 5 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.2 Ground Plane Pathway The ground plane pathway dose factor is calculated by:

RiG Ii K'K"(SF)DFG.1 (1 - e i (B.2-2) where:

R = Dose factor for the ground plane pathway for each identified radionuclide IG 2

"i" for the organ of interest, mrem/yr per pci/sec per m ;

K' = A constant of unit conversion;

= 106 pci/ýci; K" A constant of unit conversion;

= 8760 hr/year; SF = The shielding factor (dimensionless);

(A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.)

DFGi = The ground plane dose conversion factor for radionuclide "i," mrem/hr per pCi/m2; (A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.)

xi = The radiological decay constant for radionuclide "i," sec-1; t = The exposure time, sec;

= 4.73 E+08 sec (15 years);

B-5

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 6 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.2 Ground Plane Pathway (continued)

Ii = Factor to account for fractional deposition of radionuclide "i."

For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133)

B-6

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 7 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathway The dose factor for the cow milk or goat milk pathway for each radionuclide for each organ is calculated by:

- E. te - Xtb R t (f r(l - e E ) B ( - e ib)

R IiK'Q U F (DFLi) e if(ff( + V ) +

M i F ap m 1ia pS Y p

XE. +

i 1

-x kt - Xitb r(l r~-e ~) B. (i -e -b) ith i

(1- f f) ( Y + lv )e i PSsE. 1 1

(B.2-3) where:

R. Dose factor for the cow milk or goat milk pathway, for each identified iM radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m-2 K' = A constant of unit conversion; 106 pCi/gCi; QF = The cow's or goat's feed consumption rate, kg/day (wet weight);

U The receptor's milk consumption rate for age group "a," liters/yr; ap Y, = The agricultural productivity by unit area of pasture feed grass, kg/ M2 Y = The agricultural productivity by unit area of stored feedg, kg/M2; B-7

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 APPENDIX B Sheet 8 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathway (continued)

Fm - The stable element transfer coefficients, pCi/liter per pCi/day; r = Fraction of deposited activity retained on cow's feed grass; (DFLi)a The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pCi;

= Xi +Xw; 1 = The radiological decay constant for radionuclide "i," sec- 1 ;

X = The decay constant for removal of activity on leaf and plant surfaces by w

weathering, sec-1; 5.73 E-07 sec- 1 (14 day half-life);

t Period of pasture grass and crop exposure during the growing season, sec; e

t f The transport time from feed, to cow or goat, to milk, to receptor, sec; th The transport time from pasture, to cow or goat, to milk to receptor, sec; t bbPeriod of time that sediment is exposed to gaseous effluents, sec; B. Concentration factor for uptake of radionuclide "i" from the soil by the e(v edible parts of crops, pCi/Kg (wet weight) per pCi/Kg (dry soil);

B-8

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 9 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathway (continued)

P = Effective surface density for soil, Kg (dry soil)/m f Fraction of the year that the cow or goat is on pasture; (dimensionless).

P f Fraction of the cow feed that is pasture grass while the cow is on S

pasture; (dimensionless).

t Period of pasture grass and crop exposure during the growing season, sec; e

I.i Factor to account for fractional deposition of radionuclide "i."

For radionuclides other than iodine, the factor I. is equal to one. For radioiodines, I

the value of I. may vary. However, a value of 1.0 was used in calculating the R 1

values in Tables 3.3-8 through 3.3-15. (Reference NUREG 0133)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f. was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8-month grazing period.

Table B-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

B-9

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 APPENDIX B Sheet 10 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathway (continued)

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

RT K'K' . 'FQFU (DFLi)a 0.75(0.5/H) (B.2-4)

TM ap where:

R TM = Dose factor for the cow or goat milk pathway for tritium for the organ of 3

interest, mrem/yr per IICi/m ;

K' ' = A constant of unit conversion;

= 103 gm/kg; H Absolute humidity of the atmosphere, gm/mi3 ; A value of H = 8 grams/

meter 3 , was used in lieu of site-specific information.

0.75 The fraction of total feed that is water; 0.5 The ratio of the specific activity of the feed grass water to the atmospheric water.

and other parameters and values as previously defined.

B-i 0

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 11 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway; therefore:

- E. te - Xtb

- X .ts (fr(l - e E )e Biv(i - e- tb Ri

'B

= IK'Q U F (DFL) e 1 (ff( + ) +

i F ap f i a P s Y XP.

p E.

1 r(l- e e) B. (1 - b)

(1 -f f ) ( Xiv it) s E.

1 (B.2.5) where:

R. Dose factor for the meat ingestion pathway for radionuclide "i" for any 1B organ of interest, mrem/yr per pCi/sec per m-2 Ff The stable element transfer coefficients, pCi/Kg per pCi/day; U The receptor's meat consumption rate for age group "a," kg/yr; ap t Transport time from slaughter to consumption, sec; s

B-11

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 12 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.4 Grass-Cow-Meat Pathway (continued) thh Transport time from harvest to animal consumption, sec; t = Period of pasture grass and crop exposure during the growing season, sec; e

I. Factor to account for fractional deposition of radionuclide "i."

I For radionuclides other than iodine, Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-5 through 3.3-7.

All other terms remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating Ri for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q.

R TB = K'K' ' FfQFU ap (DFLi)a 0.75(0.5/H) (B.2-6) where:

R = Dose factor for the meat ingestion pathway for tritium for any organ of TB interest, mrem/yr per VCi/m 3 .

All other terms are defined in Equations B.2-4 and B.2-5.

B-12

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 13 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

-Xt - X E.t e 1 e) B. ( -e ib) itL r(l -

Riv = I K'(DFL ) (ULf e PX.1 i ia aL v E.

1

-X E. t e - X B. ( -e e ib) u~fe - Xithih(____r(l -e iv p*

+V ag YE PX.

v E.1 I (B.2-7) where:

R Dose factor for vegetable pathway for radionuclide "i" for the organ of Iv 2

interest, mrem/yr per pCi/sec per m ;

K' = A constant of unit conversion; 6

10 pCi/JLCi; B-13

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 14 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Vegetation Pathway (continued)

U = The consumption rate of fresh leafy vegetation by the receptor in age a

group "a," kg/yr; U = The consumption rate of stored vegetation by the receptor in age group a

"a," kg/yr; fL The fraction of the annual intake of fresh leafy vegetation grown locally;

- 1.0 fg = The fraction of annual intake of stored vegetation grown locally;

- 0.76 tL = The average time between harvest of leafy vegetation and its consumption, sec; th = The average time between harvest of stored vegetation and its consumption, sec; Yv = The vegetation a real density, kg/M2; te = Period of leafy vegetable exposure during growing season, sec; Ii = Factor to account for fractional deposition of radionuclide "i."

All other factors as previously defined.

B-14

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 15 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Vegetation Pathway (continued)

For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in Tables 3.3-2 through 3.3-4.

Table B-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculations on Ri. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

RT TV KfK"tFULf L L

+ U Sf a+gj (DFLi)a F.

075 (0.5 / H) (B.2.8) where:

RT Dose factor for the vegetable pathway for tritium for any organ of Tv interest, mrem/yr per pCi/m 3 .

All other terms remain the same as those in Equations B.2-4 and B.2-7.

B-15

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE B-1 Parameters For Cow and Goat Milk Pathways Parameter Value Reference (Reg. Guide 1.109, Rev. 1)

QF (kg/day) 50 (cow) Table E-3 6 (goat Table E-3 Y (kg/M2 ) 0.7 Table E-15 p

t (seconds) 1.73 E+05 (2 days) Table E-15 f

r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL.) (mrem/pCi) Each radionuclide T able E-11 to E-14 i a F (pCi/liter per pCi/ day) Each stable element Table E-1 (cow) m Table E-2 (goat)

Tb (seconds) 4.75 E+08 (15 yr) Table E-15 Y (kr/M2 ) 2.0 Table E-15 s

th (seconds) 7.78 E+06 (90 days) Table E-15 U (liters/yr) 330 infant Table E-5 ap 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 t (seconds) 2.59 E+06 (pasture) Table E-15 e 5.18 E+06 (stored feed)

B. (pCi/kg [wet weightt] Each stable element Table E-1 iv per pCi/kg [dry soil])

2 P (kg dry soil/m ) 240 Table E-15 B-16

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE B-2 Parameters For The Meat Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. 1) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 Ff (pCi/ke per (pCi/Day) Each stable element Table E-1 u (kg/yr) 0 infant Table E-5 ap 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL.)

1 a (mrem/pCi) Each radionuclide Tables E-11 to E-14 Y 0.7 P (kg/M2) Table E-15 Y (kr/M2) 2.0 Table E-15 5

Tb (seconds) 4.73 E+08 (15 yr) Table E-15 T (seconds) 1.73 E+06 (20 days) Table E-15 s

th (seconds) 7.78 E+06 (90 days) Table E-15 t (seconds) 2.59 E+06 (pasture) Table E-15 e 5.18 E+06 (stored feed)

QF (kg/day) 50 Table E-3 B. (pCi/kg [wet weight] Each stable element Table E-1 lV per pCi/kg [dry soil])

2 P (kg dry soil/m 240 Table E-15 B-17

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE B-3 Parameters for The Vegetable Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL.) (mrem/pCi) Each radionuclide Tables E-11 to E-14 1 a QF (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 F

ULa (kg/yr) - Infant 0 Table E-5 26 Table E-5 Child 42 Table E-5 Teen 64 Table E-5 Adult Us (kr/hr) - Infant 0 Table E-5 a 520 Table E-5 Child 630 Table E-5 Teen 520 Table E-5 Adult TL (seconds) 8.6 E+04 (I day) Table E-15 th (seconds) 5.18 E+06 (60 day) Table E-15 2

Y (kg/M ) 2.0 Table E-15 V

t (seconds) 5.18 E+06 (60 day) Table E-15 e

tb (seconds) 4.73 E+08 (15 yr) Table E-15 2

P (kg dry soil/m ) 240 Table E-15 B. (pCi/kg [wet weight] Each stable element Table E-1 Iv per pCi/kg [dry soil])

B-18

Shearon Harris Nuclear Power Plant (SHNPP) November 2001 Offsite Dose Calculation Manual (ODCM) Rev. 14 Sheet 1 of 1 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Monitor Identification I. Liquid Effluent Monitoring Instruments A. Treated Laundry and Hot Shower Tank .................... .... REM-lWL-3540 B. Waste Monitor Tank ..................................... ... REM-21WL-3541 C. Waste Evaporator Condensate Tank ....................... ... REM-21WL-3541 D. Secondary Waste Sample Tank ............................ ... REM-21WS-3542 E. NSW Returns to Circulating Water System from Waste Processing Building ................... ... REM-lSW-3500A from Reactor Auxiliary Building .................. ... REM-lSW-3500B F. Outdoor Tank Area Drain Transfer Pump Monitor .......... .... REM-lMD-3530 G. Turbine Building Floor Drains Effluent ................. .... REM-lMD-3528 II. Gaseous Effluent Monitoring Instruments A. Plant Vent Stack 1 ..................................

RM-21AV-3509-lSA B. Turbine Building Vent Stack 3A .........................

RM-lTV-3536-1

.... REM-IWV-3546 C. Waste Processing Building Vent Stack 5 ................

" RM-lWV-3546-1 D. Waste Processing Building Vent Stack 5A ................

RM-lWV-3547-1 I

Wide-Range Gas Monitor (WRGM)

C-I

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX D PROGRAMMATIC CONTROLS The surveillance and operational requirements pertaining to the ODCM Operational Requirements are detailed in Sections:

D.1 - Instrumentation D.2 - Radioactive Effluents D.3 - Radiological Environmental Monitoring D-1

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 D.1 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.10 Radioactive Liquid Effluent Monitoring Instrumentation OPERATIONAL REQUIREMENT 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Operational Requirement 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Operational Requirement, immediately (1) suspend the release of radioactive liquid effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by b. below.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best effort to restore to the minimum number of radioactive liquid effluent channels within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-8.

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

D-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower 1 35 Tanks Discharge Monitor

2) Waste Monitor Tanks and Waste 1 35 Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tank 1 35, 36*

Discharge Monitor

b. Turbine Building Floor Drains Effluent 1 36 Line

2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump

a. Outdoor Tank Area Drain Transfer Pump 1 37 Monitor

3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System Return From 1 39 Waste Processing Building to the Circulating Water System

b. Normal Service Water System Return From 1 39 the Reactor Auxiliary Building to the Circulating Water System

4. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower 1 38 Tanks Discharge

2) Waste Monitor Tanks and Waste 1 38 Evaporator Condensate Tanks Discharge

3) Secondary Waste Sample Tank 1 38

b. Cooling Tower Blowdown 1 38 When the Secondary Waste System is in the continuous release mode and releases are occurring, Action 36 shall be taken when the monitor is inoperable. In the batch release mode, Action 35 is applicable.

D-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Operational Requirement 4.11.1.1.1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than IE-07 pCi/ml:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 zCi/gram DOSE EQUIVALENT I-131 or,

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 pCi/gram DOSE EQUIVALENT 1-131.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than IE-07 pCi/ml.

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the weekly Cooling Tower Blowdown weir surveillance is performed as required by Operational Requirement 4.11.1.1.1. Otherwise, follow the ACTION specified in ACTION 37 above.

D-4

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL INSTRUMENT CHANNEL SOURCE CHANNEL OPERATIONAL CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot D P R(3) Q(l)

Shower Tanks Discharge Monitor

2) Waste Monitor Tanks and D P R(3) Q(l)

Waste Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample D P, R(3) Q(1)

Tank Discharge Monitor M(5)

b. Turbine Building Floor Drains D M R(3) Q(l)

Effluent Line

2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump

a. Outdoor Tank Area Drain D M R(3) Q(l)

Transfer Pump Monitor

3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System D M R(3) Q(2)

Return From Waste Processing Building to the Circulating Water System

b. Normal Service Water System D M R(3) Q(2)

Return From the Reactor Auxiliary Building to the Circulating Water System

4. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot D(4) N.A. R N.A.

Shower Tanks Discharge

2) Waste Monitor Tanks and D(4) N.A. R N.A.

Waste Evaporator Condensate Tanks Discharge

3) Secondary Waste Sample D(4) N.A. R N.A.

Tank Pump Monitor b.Cooling Tower Blowdown D(4) N.A. K N.A.

See Table G-1 for explanation of frequency notation D-5

Shearon Harris Nuclear Power Plant (SHNPP) December, 1997 Offsite Dose Calculation Manual (ODCM) Rev. 10 TABLE 4.3-8 (Continued)

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate automatic isolation of this pathway (or, for the Outdoor Tank Area Drains Monitor, automatic stop signal to the discharge pump) and control room alarm annunciation* occur if any of the following conditions exists (liquid activity channel only):

a. Instrument indicates measured levels above the Alarm/Trip Setpoint,

b. Circuit failure (monitor loss of communications (alarm only), detector loss of counts (Alarm only) and monitor loss of power),

c. Detector check source test failure (alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only). (Not applicable for Turbine Building Drain Rad Monitor)

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exists (liquid activity channel only):

a. Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications , detector loss of counts, and monitor loss of power),

c. Detector check source test failure,

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(5) When the Secondary Waste System is being used in the batch release mode, the source check shall be prior to release. When the system is being used in the continuous release mode, the source check shall be monthly.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-II terminal (i.e., a change in color).

D-6

Shearon Harris Nuclear Power Plant (SHNPP) December 1998 Offsite Dose Calculation Manual (ODCM) Rev. 11 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation OPERATIONAL REQUIREMENT 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Operational Requirements 3.11.2.1 are not exceeded. The Alarm/Trip Setpoints of these channels meeting Operational Requirement 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Operational Requirement, immediately (1) suspend the release of radioactive gaseous effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by b. below.

b. With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to OPERABLE status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and a DIGITAL CHANNEL OPERATIONAL TEST or an ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

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

D-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MIN.

INSTRUMENT CHANNELS APPLICAI BILITY ACTION OPERABLE

1. GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALYZERS Specification is not used in ODCM

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

3. PLANT VENT STACK

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

4. WASTE PROCESSING BUILDING VENT STACK 5 a.l Noble Gas Activity Monitor (PIG) 1

45, 51 a.2 Noble Gas Activity Monitor (WRGM) 1 MODES 1 , 2, 3 52

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

5. WASTE PROCESSING BUILDING STACK 5A

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46 TABLE NOTATIONS

At all times.

D-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 45 - With the number channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the waste gas decay tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 - Not Used in the ODCM.

ACTION 49 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

ACTION 50 - Not used in the ODCM.

ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement for both the PIG and WRGM, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 52 - With the number of OPERABLE accident monitoring instrumentation channels for the radiation monitor(s) less than the Minimum Channels OPERABLE requirements of Technical Specification Table 3.3-10, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and either restore the inoperable channel(s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission, pursuant to Technical Specification 6.9.2, within the next 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channel(s) to OPERABLE status.

D-9

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL MODES FOR CHANNEL SOURCE CHANNEL CHANNEL WHICH INSTRUMENT CHECK CHECK CALIBRATION OPERATIONAL SURVEILLANCE TEST IS REQUIRED

1. GASEOUS WASTE PROCESSING SYSTEM. - HYDROGEN AND OXYGEN ANALYZERS Not Used in the ODCM.

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity D M R(3) Q(2)

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

c. Particulate Sampler N.A. N.A. N.A. N.A.

d. Flow Rate Monitor D N.A. R Q

e. Sampler Flow Rate D N.A. R Q Monitor

3. PLANT VENT STACK

a. Noble Gas Activity D M R(3) Q(2)

Monitor

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

C. Particulate Sampler N.A. N.A. N.A. N.A.

d. Flow Rate Monitor D N.A. R Q

e. Sampler Flow Rate D N.A. R Q Monitor

4. WASTE PROCESSING BUILDING VENT STACK 5 a.l Noble Gas Activity D M R(3) Q(1)

Monitor (PIG) a.2 Noble Gas Activity Monitor (WRGM)

D M R(3) Q(2)

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

c. Particulate Sampler N.A. N.A. N.A. N.A.

d. Flow Rate Monitor D N.A. R Q

e. Sampler Flow Rate D N.A. R Q Monitor

5. WASTE PROCESSING BUILDING VENT STACK 5A

a. Noble Gas Activity D M R(3) Q(2)

Monitor

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

c. Particulate Sampler N.A. N.A. N.A. N.A.

d. Flow Rate Monitor D N.A. R Q

e. Sampler Flow Rate D N.A. R Q Monitor

At all times.

- See Table G-1 for explanation of frequency notation D-1 0

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9 TABLE 4.3-9 (Continued)

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation* occur if any of the following conditions exists (gas activity and gas effluent channels only):

a. Instrument indicates measured levels above the Alarm/Trip Setpoint,

b. Circuit failure (monitor loss of communications - (alarm only), detector loss of counts (alarm only) and monitor loss of power),

c. Detector check source test failure (gas activity channel only), (alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exists (gas activity and gas effluent channels only):

a. Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications (alarm only), detector loss of counts, and monitor loss of power),

c. Detector check source test failure (gas activity channel only),

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) Not used in the ODCM.

(5) Not used in the ODCM.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-11 terminal (i.e., a change in color).

D-1 1

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 D.2 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration OPERATIONAL REQUIREMENT 3 .11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20.1001 -

20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 pCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Operational Requirement 3.11.1.1.

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

D-12

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION SAMPLING ANALYSIS TYPES OF ACTIVITY (LLD)"()

LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (gCi/ml)

1. Batch Waste Release Tanks(2)

a. Waste Monitor P P Principal Gamma 5E-07 Tanks Each Batch Each Batch Emitters(3) 1-131 1E-06

b. Waste P M Dissolved and IE-05 Evaporator One Batch/M Entrained Gases Condensate (Gamma Emitters)

Tanks

c. Secondary Waste P M H-3 1E-05 Sample Tank(8 ) Each Batch Composite(4)

Gross Alpha IE-07

d. Treated Laundry P Q 4 Sr-89, Sr-90 5E-08 and Hot Shower Each Batch Composite( )

Tanks Fe-55 IE-06 7

2. Continuous Releases(5)( )

a. Cooling Tower Continuous (6) W Principal Gamma 5E-07 Weir Composite (6) (7) Emitters(3)

b. Secondary Waste M(7) M(7 ) Dissolved and 1E-05 Sample Tank(8 Grab Sample Entrained Gases (Gamma Emitters) 1-131 1E-06 Continuous (6) M H-3 IE-05 Composite (6) (7)

Gross Alpha 1E-07 Continuous (6) Q Sr-89, Sr-90 5E-08 Composite (6) (7)

Fe-55 1E-06 See Table G-1 for explanation of frequency notation D-13

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD = 4.66

Sb E

V 0 (2.22E + 06)

Y

e-t Where:

LLD = the "a priori" lower limit of detection (pCi per unit mass or volume),

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

E the counting efficiency (counts per disintegration),

V the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per pCi, Y = the fractional radiochemical yield, when applicable, S = the radioactive decay constant for the particular radionuclide (sec-1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

D-14

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued)

(3) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured but with a LLD of 5E-

06. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

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

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(7) These points monitor potential release pathways only and not actual release pathways. The potential contamination points are in the Normal Service Water (NSW) and Secondary Waste (SW) Systems. Action under this Operational Requirement is as follows:

a) If the applicable (NSW or SW) monitors in Table 3.3-12 are OPERABLE and not in alarm, then no analysis under this Operational Requirement is required but weekly composites will be collected.

b) If the applicable monitor is out of service, then the weekly analysis for principal gamma emitters will be performed.

c) If the applicable monitor is in alarm or if the principal gamma emitter analysis indicates the presence of radioactivity as defined in the ODCM, then all other analyses of this Operational Requirement shall be performed at the indicated frequency as long as the initiating conditions exist.

(8) The Secondary Waste System releases can be either batch or continuous. The type of sample required is determined by the mode of operation being used.

D-15

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.2 Dose OPERATIONAL REQUIREMENT 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

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

D-16

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.3 Liquid Radwaste Treatment System OPERATIONAL REQUIREMENT 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

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

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

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

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Operational Requirements 3.11.1.1 and 3.11.1.2.

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

D-17

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate OPERATIONAL REQUIREMENT 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-1) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION:

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

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

4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

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

D-18

Shearon Qrris Nuclear Power Plant (SHNPP) NovemberQo 4 Offsite Dose Calculation Manual (ODCM) Rev. 17 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS DETECTION (LLD)()

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSI S (gCi/ml)

1. Waste Gas Storage P P Principal Gamma Emitters (2a) 1E-04 Tank Each Tank Each Tank Grab Sainpl e

2. Containment Purge P P Principal Gamma Emitters (2a) 1E-04 Each PURGE(3) or Vent(1°) Each PURGE (3)

Grab Sampl e M H-3 (oxide) 1E-06

3. a. Plant Vent Stack M (3),(4),(5) M Principal Gamma Emitters (2a) 1E-04 Grab Sampl e H-3 (oxide) 1E-06 (2a)

M M Principal Gamma Emitters 1E-04

b. Turbine Bldg Grab Sampl e Vent Stack, Waste Proc. H-3 (oxide) (Turbine Bldg. 1E-06 Bldg. Vent Vent Stack)

Stacks 5 & 5A All Release Types as Continuous(6) W(7) 1_131 (2bI 1E-12 4.

listed in 1.,2., and Charcoal

3. above (8), (9), (10) Sample 1-133 (2b) 1E-10 Continuous(6) W(?) Principal Gamma Emitters(2c) 1E-11 Particulate Sample Continuous (6) M Gross Alpha 1E-II Composite Particulate Sample Continuous(6) Q Sr-89, Sr-90 1E-11 Composite Particulate Sample

5. Equipment Hatch Continuous D 1-131,& 1E-11 during Refueling Charcoal 1E-09 1-133 Sample Continuous D(11) Principal Gamma Emitters 1E-10 Particulate Sample See Table G-1 for explanation of frequency notation D-19

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

4.66

Sb LLD =

E

V * (2.22E + 06) - Y - e-&Aý Where:

LLD = the "a priori" lower limit of detection (pCi per unit mass or volume),

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

E = the counting'efficiency (counts per disintegration),

V the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per pCi, Y = the fractional radiochemical yield, when applicable, x = the radioactive decay constant for the particular radionuclide (sec-3), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

D-20

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(2a) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases. This list does not mean that only these nuclides are to be considered. Other noble gas gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(2b) The principal gamma emitters for which the LLD Operational Requirement applies include 1-131 and 1-133 in Iodine (characoal cartridge) samples. This list does not mean that only these nuclides are to be considered. Other iodine gamma peaks that are identifiable, together with 1-131 and 1-133 nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(2c) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in particulate releases. This list does not mean that only these nuclides are to be considered. Other particulate gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Operational Requirements 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(8) Continuous sampling of Waste Gas Decay Tank (WGDT) releases can be met using the continuous samplers on Wide Range Gas Monitor RM-*lWV-3546-1 on Waste Processing Building Vent Stack 5.

(9) Continuous sampling of containment atmosphere for (1) Venting, (2) Normal Purge, and (3) Pre-entry purge operations, required by Operational Requirement 4.11.2.1.2, can be met using the continuous samplers on Wide Range Gas Monitor RM-01AV-3509-lSA on Plant Vent Stack 1.

D-21

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(10) The requirement to sample the containment atmosphere prior to release for normal and pre-entry containment purge operations (that is, to "permit" the release per the ODCM) is required on initial system startup, and prior to system restart following any system shutdown due to radiological changes in the containment (e.g. valid high alarms on leak detection or containment area monitors). System shutdown occurring on changes in containment pressure, equipment malfunctions, operational convenience, sampling, and so forth, do not require new samples or release permits.

(11) The composite of all filters collected when releases were being made through the equipment hatch are to be analyzed for gross alpha, strontium-89, and strontium 90 at the end of the outage.

D-22

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose - Noble Gases OPERATIONAL REQUIREMENT 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

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

D-23

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form OPERATIONAL REQUIREMENT 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

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

D-24

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.4 Gaseous Radwaste Treatment System OPERATIONAL REQUIREMENT 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

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

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

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

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

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the GASEOUS RADWASTE TREATMENT SYSTEM is not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GASEOUS RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Operational Requirements 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

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

D-25

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.4 TOTAL DOSE OPERATIONAL REQUIREMENT 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Operational Requirement 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a.,

or 3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Operational Requirement 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Operational Requirements 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Operational Requirement 3.11.4.

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

D-26

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 D.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT 3.12.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Section F.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Operational Requirements 3.11.1.2. 3.11.2.2, or 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration(l) concentration(2) reporting level(l) reporting level(2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Operational Requirement 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Ssection F.1.

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

D-27

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT ACTION (Continued):

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.

The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

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

D-28

Shearon @ris Nuclear Power Plant (SHNPP) August*95 5 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(l) COLLECTION FREQUENCY OF ANALYSIS 2

1. Direct Radiation(

Forty routine monitoring stations Quarterly. Gamma dose quarterly.

either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6 to 8 km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

D-29

Shearon *ris Nuclear Power Plant (SHNPP) August*95 5 Offsite Dose Calculation Manual (ODCM) Rev.6 TABLE 3.12-1 (Continued)

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

2. Airborne Samples from five locations: Continuous sampler Radioiodine Cannister:

Radioiodine and operation with sample 1-131 analysis weekly.

Particulates collection weekly, or Three samples from close to more frequently if the three SITE BOUNDARY required by dust locations, in different sectors, loading. Particulate Sampler:

of the highest Gross beta radioactivity calculated annual average analysis following ground-level D/Q; filter change;(3) and gamma isotopic analysis(d)

One sample from the vicinity of composite (by location) of a community having the quarterly.

highest calculated annual average ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

3. Waterborne

a. Surface(5) One sample upstream. Composite sample over Gamma isotopic analysis(4) 1-month period. (6) monthly. Composite for One sample downstream. tritium analysis quarterly.

b. Ground Samples from one or two sources Quarterly. Gamma isotopic(4 ) and only if likely tritium analysis quarterly.

7 to be affected~ ).

D-30

Shearon *ris Nuclear Power Plant (SHNPP) July 205 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY 1

AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS( ) COLLECTION FREQUENCY OF ANALYSIS

3. Waterbourne (Continued)

c. Drinking One sample in the vicinity Composite sample over 1-131 analysis on each of the nearest downstream 2-week period(6) when composite when the dose municipal water supply intake 1-131 analysis is calculated for the form the Cape Fear River. performed; monthly consumption of the water composite otherwise. is greater than One sample from a control 1 mrem per year.(8) location. Composite for gross beta and gamma isotopic analyses (4) monthly.

Composite for tritium analysis quarterly.

4

d. Sediment One sample in the vicinity of the Semiannually. Gamma isotopic analysis( )

from cooling tower blowdown discharge semiannually.

Shoreline in an area with existing or potential recreational value.

4. Ingestion

a. Milk Samples from milking animals in Semimonthly when Gamma isotopic(d) and three locations within 5 km distance animals are on pasture; 1-131 analysis having the highest dose monthly at other times. semimonthly when potential. If there are none, When no milk animals are animals are on pasture; then one sample from milking available at indicator monthly at other times.

animals in each of three areas locations, milk sampling between 5 to 8 km distant where of the control location doses are calculated to be greater can be reduced to once than 1 mrem per yr.(8) per month to maintain One sample from milking animals historical data.

at a control location 15 to 30 km distant and in the least prevalent wind direction.

D-31

Shearon *ris Nuclear Power Plant (SHNPP) Augus t@95 5 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-1 (Continued)

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

4. Ingestion (Continued)

b. Fish and One sample of Sunfish, Catfish, and Sample in season, or Gamma isotopic Invertebrates Large-Mouth Bass species in vicinity semiannually if they analysis(4) on of plant discharge area. are not seasonal. edible portions.

One sample of same species in areas not influenced by plant discharge.

c. Food Products Samples of three different kinds Monthly during Gamma isotopic(4) and of broad leaf vegetation grown growing season. 1-131 analysis.

nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

One sample of each of the similar Monthly during Gamma isotopic(4) and broad leaf vegetation grown 15 to growing season. 1-131 analysis.

30 km distant in the least prevalent wind direction if milk sampling is not performed.

D-32

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-1 (Continued)

TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional.description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM.

Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. (The 40 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

D-33

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

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

(5) The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

(6) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Five current ground water locations have not been used for drinking water since pre-operational days of Harris Nuclear Project nor have these wells ever been used for irrigation purposes. These wells were abandoned for drinking water purposes prior to plant operations. Since that time, these wells have been used to monitor the hydraulic gradient or gradient properties for the Harris Site and for the operational Radiological Environmental Monitoring program.

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

D-34

Shearon Pris Nuclear Power Plant (SHNPP) August 95 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/i) OR GASES (pCi/m3) (pCi/kg, wet) (pCi/i) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

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

D-35

Shearon *ris Nuclear Power Plant (SHNPP) December099 Offsite Dose Calculation Manual (ODCM) Rev. 12 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(')

LOWER LIMIT OF DETECTION (LLD)(21 WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT 3

ANALYSIS (pCi/l) OR GASES (pCi/m ) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 i** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/l may be used.

- If no drinking water pathway exists, a value of 15 pCi/l may be used.

D-36

Shearon Harris Nuclear Power Plant (SHNPP) December 1999 Offsite Dose Calculation Manual (ODCM) Rev. 12 TABLE 4.12-1 (Continued)

TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

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

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

4.66

Sb LLD =

E o V * (2.22E + 06) e Y e e-6t Where:

LLD = the "a priori" lower limit of detection (pCi per unit mass or volume),

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

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per pCi, Y = the fractional radiochemical yield, when applicable, S = the radioactive decay constant for the particular radionuclide (sec-1) , and At the elapsed time between the midpoint of sample collection and the time of counting (sec).

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

D-37

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.12-1 (Continued)

TABLE NOTATIONS (Continued)

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.I.

D-38

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.12.2 LAND USE CENSUS OPERATIONAL REQUIREMENT 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 M2 (500 ft 2 ) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Operational Requirement 4.11.2.3, pursuant to ODCM, Appendix F, Section F.2, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Operational Requirement 3.12.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.

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

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Operational Requirements for broad leaf vegetation sampling in Table 3.12-1, Part 4.c., shall be followed, including analysis of control samples.

D-39

Shearon Harris Nuclear Power Plant (SHNPP) July 2002 Offsite Dose Calculation Manual (ODCM) Rev. 15 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM OPERATIONAL REQUIREMENT 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1. The laboratory used for the Interlaboratory Comparison Program is to participate in the National Institute of Standard and Technology (NIST) program APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.

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

D-40

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX E PROGRAMMATIC CONTROL BASES The Bases for the ODCM Operational Requirements are detailed in Sections:

E.1 - Instrumentation E.2 - Radioactive Effluents E.3 - Radiological Environmental Monitoring E-1

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.1 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.10 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Operational Requirement 3.11.2.2 shall be such that concentrations as low as 1E-06 /uCi/ml are measurable.

E-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration This Operational Requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within:

(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 Dose This Operational Requirement is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

E-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.2 Dose (continued)

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

3/4.11.1.3 Liquid Radwaste Treatment System The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

E-4

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate This Operational Requirement is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column I. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b)]. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

E-5

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose - Noble Gases This Operational Requirement is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

E-6

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form This Operational Requirement is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirements are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate Operational Requirements for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition of the ground with subsequent exposure of man.

E-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.4 Gaseous Radwaste Treatment System The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

E-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.3 SOLID RADIOACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a, 10 CFR 61, and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

E-9

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.4 TOTAL DOSE This Operational Requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Operational Requirement requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Operational Requirements 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

E-1 0

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Operational Requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs) . The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.12.2 LAND USE CENSUS This Operational Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made, if required, by the results of this census. The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 2

10 CFR Part 50. Restricting the census to gardens of greater than 50 m provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2 .

E-11

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES (continued) 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

E-12

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX F ADMINISTRATIVE CONTROLS The Reporting Requirements pertaining to the ODCM Operational Requirements are detailed in Sections:

F.1 - Annual Radiological Environmental Operating Report F.2 - Annual Radioactive Effluent Release Report F.3 - Major changes to the Radwaste Treatment System (liquid and gaseous)

F-i

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 F.l Annual Radiological Environmental Operating Report (Formerly part of Specification 6.9.1.3)

Routine Annual Radiological Environmental Operating Reports, covering the operation of the unit during the previous calendar year, shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of the Land Use Census required by Operational Requirement 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps*

covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Operational Requirement 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Operational Requirement 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pursuant to ACTION b. of Operational Requirement 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

One map shall cover stations near the EXCLUSION AREA BOUNDARY; a second shall include the more distant station.

F-2

Shearon Harris Nuclear Power Plant (SHNPP) May 2001 Offsite Dose Calculation Manual (ODCM) Rev. 13 F.2 Annual Radioactive Effluent Release Report (Formerly part of Specification 6.9.1.4)

Routine Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted by May 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. For the assessment of radiation doses, approximate and conservative methods are acceptable. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

F-3

Shearon Harris Nuclear Power Plant (SHNPP) December 1998 Offsite Dose Calculation Manual (ODCM) Rev. 11 F.2 Annual Radioactive Effluent Release Report (continued)

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the ODCM, pursuant to Technical Specification 6.14, as well as any major change to Liquid and Gaseous Radwaste Treatment Systems pursuant to ODCM, Appendix F, Section F.3. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Operational Requirement 3.12.2.

The Annual Radioactive Effluent Release Report shall also include the following:

an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Operational Requirement 3.3.3.10 or 3.3.3.11, respectively; and a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or PLP-114, Attachment 5, respectively.

F-4

Shearon Harris Nuclear Power Plant (SHNPP) November 2004 Offsite Dose Calculation Manual (ODCM) Rev. 17 F.3 Major Changes to Liquid and Gaseous Radwaste Treatment Systems*

(Formerly part of Specification 6.15)

Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PNSC. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto.

5. An evaluation of the change, which shows the expected maximum exposures, to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population, that differ from those previously estimated in the License application and amendments thereto.

6. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the period prior to when the change is to be made.

7. An estimate of the exposure to plant operating personnel as a result of the change.

8. Documentation of the fact that the change was reviewed and found acceptable by the PNSC.

b. Shall become effective upon review and acceptance by the PNSC.

Licensees may choose to submit the information called for in the Operational Requirement as part of the annual FSAR update.

F-5

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 APPENDIX G DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout the ODCM Operational Requirements.

ACTION ACTION shall be that part of an ODCM Operational Requirement which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

DIGITAL CHANNEL OPERATIONAL TEST A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation to verify OPERABILITY of alarm and/or trip functions.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (DICi/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, "Limits for Intakes of Radionuclides by Workers."

EXCLUSION AREA BOUNDARY The EXCLUSION AREA BOUNDARY shall be that line beyond which the land is not controlled by the licensee to limit access.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Operational Requirements shall correspond to the intervals defined in Table G-1.

GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

G-1

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 DEFINITIONS (continued)

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

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

OPERATIONAL MODE - MODE An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table G-2.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.

PURGE - PURGING PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RELEASE A RELEASE shall be the discharge of radioactive effluent from the facility in gaseous, particulate or liquid media. Releases can be further categorized for evaluation purposes:

ABNORMAL RELEASE/ACCIDENTAL RELEASE - An unplanned, uncontrolled, or unmonitored RELEASE to the offsite environs exceeding 10% of the 10CFR Part 20 ODCM limits.

NON-ROUTINE RELEASE - An unplanned, uncontrolled, or unmonitored RELEASE to the environs less than 10% of the 10CFR Part 20 ODCM limits.

PLANNED RELEASE - A RELEASE for which a pre-release permit has been generated MONITORED RELEASE - A RELEASE which is monitored through installed or portable samplers.

CONTROLLED RELEASE - A RELEASE which can be controlled through component manipulation to ensure that ODCM limits are not exceeded.

G-2

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 DEFINITIONS (continued)

SITE BOUNDARY For these Operational Requirements, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

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

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

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

G-3

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE G-1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

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

G-4

Shearon Harris Nuclear Power Plant (SHNPP) July 2006 Offsite Dose Calculation Manual (ODCM) Rev. 18 TABLE G-2 OPERATIONAL MODES Mode Reactivity Keff % RATED AVERAGE COOLANT Condition THERMAL POWER* TEMPERATURE 1 Power Operations > 0.99 > 5% > 350OF 2 Startup Ž 0.99

5% Ž 350°F 3 Hot Standby < 0.99 0 > 350OF 4 Hot Shutdown < 0.99 0 350°F > Tavg > 200°F 5 Cold Shutdown < 0.99 0 < 200OF 6 Refueling ** < 0.95 0 < 140OF

Excluding decay heat.

- Fuel in the reactor vessel with the vessel head'closure bolts less than fully tensioned or with the head removed.

G-5

HNP-07-046, Annual Radioactive Effluent Release Report for 2006

Contents

Text

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

the concentration of nuclide "i" in the SWST composite sample. For the NSW, Ci = concentration of nuclide "i" in the cooling tower basin and Fwaste

Navigation menu

HNP-07-046, Annual Radioactive Effluent Release Report for 2006

Text

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

the concentration of nuclide "i" in the SWST composite sample. For the NSW, Ci = concentration of nuclide "i" in the cooling tower basin and Fwaste

Navigation menu

Search