Text

Annual Radioactive Effluent Release Rept Jan-Dec 1995. W/ 960430 Ltr
	ML18012A239
Person / Time
Site:	Harris
Issue date:	12/31/1995
From:	Robinson W; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HNP-96-073, HNP-96-73, NUDOCS 9605020305
	Download: ML18012A239 (284)
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ACCESSION NBR:9605020305 DOC.DATE: 95/12/31 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina DOCKET I 05000400 AUTH. NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.

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Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-96-073 APR 30 1996 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 ANNUALRADIOLOGICALEFFLUENT RELEASE REPORT Gentlemen:

In accordance with Technical Specification 6.9.1.4 for the Shearon Harris Nuclear Power Plant, Carolina Power &; Light Company hereby submits the enclosed Annual Radiological Effluent Release Report for 1995.

Questions regarding this matter may be referred to Mr. T. D. Walt at (919) 362-2711.

Sincerely, MGW Enclosure c: Mr. J. B. Brady Mr. S. D. Ebneter Mr. N. B. Le M5$ $ 1 9605020305 95f23i PDR ADOCK 05000400 R PDR State Road 1138 New Hill NC Tel 919 362-2502 Fax 919 362-2095

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CÃCM Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-96-073 At R 3 0 1996 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

,ANNUALRADIOLOGICALEFFLUENT RELEASE REPORT Gentlemen:

In accordance with Technical Specification 6.9.1.4 for the Shearon Harris Nuclear Power Plant, Carolina Power A, Light Company hereby submits the enclosed Annual Radiological Effluent Release Report for 1995.

Questions regarding this matter may be referred to Mr. T. D. Walt at (919) 362-2711.

Sincerely, MGW Enclosure c: Mr. J. B. Brady Mr. S. D. Ebneter Mr. N. B. Le State Road 1134 New Hill NC Tel 919 362-2502 Fax 919 362-2095

Carolina Power R Light Shearon Harris Nuclear Power Plant License No. NPF-063 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT January 1, 1995 to December 31, 1995 Prepared by Senior Analyst - Chemist+

Reviewed by:

nt -

4r uperinten Chem s ry Approved by:

General M ager - Harris Plant

Table of Contents Page No.

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

1. Lower Limits of Detection (LLDs) 2/1

2. Effluents Released 2/3

3. Solid Waste Disposal 2/12 Appendix 3. Changes to Process Control Program (PCP) 3/1 Appendix 4. Changes to Offsite Dose Calculation Manual (ODCM) 4/1 Appendix 5. Changes to the Environmental Monitoring Program

1. Environmental Monitoring Program 5/1

2. Land Use Census 5/1 Appendix 6. Additional Technical Specification Responsibilities

1. Inoperability of Liquid Effluent Monitors 6/1

2. Inoperability of Gaseous Effluent Monitors 6/1 (Radiation Gas Monitors)

Inoperability of Gaseous Effluent Monitors 6/1 (Explosive Gas Monitors)

4. Unprotected Outdoor Tanks Exceeding Limits 6/1

5. Gas Storage Tanks Exceeding Limits 6/1 Appendix 7. Major Modifications to Radwaste System 7/1 Appendix 8. Meteorological Data 8/1 Appendix 9. Assessment of Radiation Doses for Calendar Year 1995

1. Population Doses due to Effluent Releases 9/1

2. Doses to the General Public Due to Activities Inside the Site Boundary 9/2

3. Doses to Most Likely Exposed Member of the Public 9/4 4, Major Assumptions used to Calculate Radiation Doses 9/8

Introduction This Semiannual Radioactive Effluent Release Report is prepared in accordance with Shearon Harris Nuclear Power Plant's Operational Requirements - Offsite Dose Calculation Manual (ODCM), Section F.2, Technical Specification 6.9.1.4, Operating License No. NPF-063.

The Harris Nuclear Plant (HNP) achieved initial criticality on January 3, 1987.

This Report covers the period from January 1, 1995 to December 31, 1995.

During this period, the plant operated in Cycle 6 operation, refueled in September 1995, and operated in Cycle 7 for the balance of the year. The radiological dose assessment from radioactive releases during January 1, 1995 through December 31, 1995 is in Appendix 9 of this report.

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. As required by ODCM Operational Requirements, the solid waste table has been supplemented to include 10CFR61 class, type of container, and solidification agent or absorbent.

The doses were calculated by the programs LADTAP II (for liquid effluents) and GASPAR (for gaseous effluents) . LADTAP II and GASPAR are NRC approved programs using the methodology in Reg. Guide 1.109 (Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I) which is also the basis of the ODCM calculations. When appropriate, the doses are also broken down by age group (adult, teen, etc.) and organ (bone, thyroid, etc.). The radiological dose assessment results are reported in Appendix 9.

Discussion 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 HNP 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, HNP and Carolina Power and Light Company 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 reactor 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 given off as a gas when the coolant is depressurized. These gases 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, argon, and xenon. Noble gases are by nature inert and do not concentrate in humans or other organisms. Their contribution to human radiation exposure is as an external exposure. The major isotopes released are 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. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay.

Noble gases are readily dispersed in the atmosphere.

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

Tritium Tritium, a radioactive isotope of hydrogen, is the predominate 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.

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 provides monitors that are designed to ensure that all releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set lower than the regulatory limits, typically at less than 50 percent of the regulatory limit, to ensure that the limits are not exceeded. If a monitor alarms, a release from a tank is automatically suspended. Additionally, 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 pre-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 is used to calculate dose to the public using concurrent meteorology.

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

Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material. The major pathways of concern are those which 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, hydrological (water) and meteorological (weather) characteristics of the area. Information on water flow, wind speed and direction, dietary intake of residents, recreational use of the area and location of homes and farms in the area are some of the many factors used to calculate the potential exposure to offsite personnel.

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

Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure which 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 by the whole body or to a specific organ, with the organ receiving the largest fraction of the exposure called the critical organ.

The exposures to the general public in the area surrounding HNP aze calculated for gaseous and liquid releases. The exposure due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, weather conditions at the time of release, locations of exposure pathways, and usage factors. The exposures calculated due to radioactive materials released in liquid effluents are calculated using factors such as the total volume of liquid, the total volume of dilution water, and usage factors.

Results The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the HNP during the period from January 1, 1995 through December 31, 1995.

During the period of January 1, 1995 through December 31, 1995, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

0. 0505 millirem, total body Limit = 3.0000 millirem 0.0745 millirem, liver Limit = 10.0000 millirem Gaseous Effluents:

Beta Air Dose 0.0188 millirad Limit = 20.0000 millirad Gamma Air Dose 0.0125 millirad Limit = 10.0000 millirad Most Critical 0.0087 millirem Limit, 15. 0000 millirem Organ Dose (Lung)

These doses are much lower than anyone would receive from natural background in which we live in (300 millirem per year) .

Appendix 1: Supplemental Information I ~

A. Fission and Activation Gases:

Technical Specifications Maximum Instantaneous Release Rate Total Body Dose g500 mrem/yr Skin Dose z3000 mrem/yr 10CFR20, Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table IZ, 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 Z10 mrad (Used for calculating percent of applicable limit)

For Calendar Year Gamma Dose Z10 mrad Beta Dose <20 mrad B. Iodine - 131 and 133, Tritium, and Particulates )8 day half-lives:

Technical Specifications Maximum Instantaneous Release Rate Inhalation dose (only) to a child to any organ g1500 mrem/yr 10CFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table II, Column 1. This is based on 50 mrem/yr.

10CFR50, Appendix I (Organ Doses)

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

For Calendar Year ~15 mrem C. Liquids:

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

ODCM Operational Requirements For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 pCi/ml total activity. (Used for calculating percent of applicable limit for disolved and entrained gases) 10CFR20 The annual average concentrations to be less than the concentrations specified in 10CFR20, Appendix B, Table II, 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 Z1.5 mrem Any Organ Dose Z5 mrem For Calendar Year Total Body Dose Z3 mrem Any Organ Dose Z10 mrem

Appendix 1: Supplemental Information (Continued)

D. Average Energy (E):

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

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. If no activity is detected for the sampling period the mix is based on historical data.

2. Iodines 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).

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 (minimum weekly or more frequently if plant conditions requires it).

4. Tritium The activity released as tritium is based on grab sample analysis using liquid scintillation times total stack flow.

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 ~ Iodines The iodines from batch releases are included in the iodine determination from the continuous releases.

Appendix 1: Supplemental Information (Continued)

3. Particulates The particulate activity released from batch releases are 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) are comprised of the sum of the product individual radionuclide concentration in each batch using gamma spectroscopy times the volume of the batch.

2. Tritium and Alpha The measured tritium and alpha concentrations in a monthly composite sample times the volume released for the month are used to calculate the activity released.

3. Strontium-89, Strontium-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, non-steady release 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 (Continued): Supplemental Information III. Batch Releases A. Liquid Batch Releases Jan - June 1995 Jul - Dec 1995 Number of batch releases 4.20 E+01 6.80 E+01 Total time period for batch 2.26 E+04 minutes 4.89 E+04 minutes releases Maximum time of a batch release 8.63 E+02 minutes 1.03 E+03 minutes Avera e time for a batch release 5.38 E+02 minutes 7.19 E+02 minutes Minimum Time for a batch release 2.26 E+02 minutes 2.00 E+00 minutes Average stream flow during 4.450E+03 cfs 4.09 E+03 cfs eriods of release *

Measured from Cape Fear River at Lillington, N.C.

B. Gaseous Batch Releases Jan - June 1995 Jul - Dec 1995 Number of batch releases 5.00 E+00 7.00 E+00 Total time period for batch 2.80 E+03 minutes 5.21 E+03 minutes releases Maximum time of a batch release 6.24 E+02 minutes 3.01 E+03 minutes Avera e time for a batch release 5.60 E+02 minutes 7.44 E+02 minutes Minimum Time for a batch release 4.84 E+02 minutes 1.50 E+01 minutes C. Abnormal Releases

a. Liquid No abnormal liquid releases were made during 1995.

b. Gaseous No abnormal gaseous releases were made during 1995.

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

1. LLDs for Gaseous Effluents Gross Alpha 7.37 E-16 H-3 7.95 E-09 Ar-41 1.15 E-08 Kr-85 3.78 E-06 Kr-85m 9.59 E-09 Kr-87 2.76 E-08 Kr-88 3.73 E-08 Xe-131m 3.20 E-07 Xe-133 2.40 E"08 Xe-133m 6.80 E-08 Xe-135 6.53 E-09 Xe-135m 4.97 E-09 Xe-138 1.54 E"07 I-131 2.71 E-13 I"133 3. 10 E-13 I-135 7.71 E-12 Cr-51 9.77 E-13 Mn-54 2.21 E-13 Co-58 2.72 E-13 Fe-59 4.36 E-13 Co-60 1.36 E-13 Zn-65 2.21 E-13 Sr-89 4.39 E-15 Sr-90 2. 12 E-15 Nb-95 7.45 E-14 Zr-95 4.63 E-13 Mo-99 6.34 E-13 Cs-134 9.00 E-14 Cs-137 2.51 E-13 Ba-140 6.96 E-13 La-140 2.14 E-13 Ce-141 1.57 E-13 Ce-144 6 '3 E-13

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

LLDs for Liquid Effluents Hualida Gross Alpha 9.80 E-08 Cr-51 1. 96 E-07 Mn-54 5.98 E-08 Fe-55 5.49 E-08 Co-57 1. 97 E-08 Co-58 4.64 E-08 Fe-59 3.97 E-08 Co-60 7.10 E-08 Ni-63 1.75 E-07 Zn-65 4.47 E-08 Sr-89 3.27 E-08 Sr-90 1.59 E-08 Nb-95 4.38 E-08 Zr-95 9.86 E-08 Mo-99 1.23 E-07 Tc-99m 2. 87 E-08 Ru-106 1.34 E-07 Sb-124 2.31 E-07 Sb-125 1.21 E"07 Sb-126 4.42 E-08 I-131 4.80 E"08 I-133 4.64 E-08 Te-132 2.53 E-08 Xe-133 7.44 E-08 Xe-133m 1.85 E-07 Xe-135 2 '9 E-08 Cs-134 7.76 E-08 Cs-137 1 '4 E-08 Ba-140 4.57 E-08 La-140 3.34 E-08 Ce-139 2.42 E-08 Ce-141 4.09 E-08 Ce-144 1.83 E-07 2/2

Appendix 2 (Continued)t Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A : GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error 9o A. Fission and activation ases

1. Total release Ci 5.65 E+01 7.35 E+01 5.27 E+01

2. Avera e release rate for eriod Ci/sec 7.27 E+00 9.35 E+00

3. Percent of Tech S ec limit 2.90 E-01 4.02 E-01 B. lodines

1. Total iodine-131 Ci <LLD <LLD 3.18 E+01

2. Avera e release rate for eriod Ci/sec <LLD <LLD

3. Percent of Tech S ec limit " 8.63 E-03 4.74 E-04 C. Particulates

1. Particulates with half-lives ) 8 da s Ci <LLD <LLD 3.37 E+01

2. Avera e release rate for eriod Ci/sec <LLD <LLD

3. Percent of Tech S ec limit 8.63 E-03 4.74 E-04 Gross al ha radioactivit Ci < LLD < LLD D. Tritium

1. Total release Ci 4.36 E.01 2.52 E-04 3.37 E+01

2. Avera e release rate for eriod i/sec 5.60 E-02 3.21 E-05

3. Percent of Tech S ec limit" 8.63 E-03 4.74E-04 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly Technical Specification limit is 7.5 millirem. The most critical organ for both quarters was the lung.

Appendix 2 (Continued) t Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A : GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation ases

1. Total release Ci 5.66 E+01 3.56 E+01 5.27 E+01

2. Avera e release rate for eriod i/sec 7.12 E+00 4.48 E+00

3. Percent of Tech S ec limit 2.86 E-01 1.80 E-01 B. lodines

'i

1. Total iodine-131 Ci 4.30 E-05 <LLD 3.18 E+01

2. Avera e release rate for eriod i/sec 5.41 E-06 <LLD

3. Percent of Tech S ec limit 1.19 E-01 7.42 E-03 Particulates

1. Particulates with half-lives ) 8 da s Ci 8.34 E-05 3.02 E-05 3.37 E+01

2. Avera e release rate for eriod Ci/sec 1.05 E-05 3.80 E-06

3. Percent of Tech S ec limit 1.19 E-01 7.42 E.03 Gross af ha radioactivi Ci < LLD < LLD D. Tritium

'I. Total release 8.99 E-03 2.41 E-01 3.37 E+01

2. Avera e release rate for eriod i/sec 1.13 E-03 3.03 E-02

3. Percent of Tech S ec limit 1.'l9 E-01 7.42E-03 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly Technical Specification limit is 7.5 millirem. The most critical organ for both quarters was the lung.

2/4

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1B : GASEOUS EFFLUENTS - ELEVATED RELEASES All releases at Harris Nuclear Plant are made as ground releases.

2/S

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission sacs xenon-131m < LLD < LLD Note 1 3.59 E-03 xenon-133 Ci 2.14 E+01 2.11 E+01 Note 1 1.43 E-01 xenon-133m Ci < LLD < LLD Nots 1 1.08 E-04 xenon-135 Ci 3.52 E+01 5.02 6+01 Mote 1 4.97 E-04 xenon-135m < LLD < LLD Note 1 <LLD xenon-138 Ci < LLO < LLD Note 1 <LLO ar on.41 Ci < LLD < LLD Nota 1 <LLD kr ton-85 Ci < LLD < LLO Note 1 2.08 E+00 kr ton 85m Ci < LLD < LLD Note 1 <LLD k ton.87 Ci < LLD < LLD Note 1 <LLD kr ton-88 Ci < LLD < LLD Note 1 <LLD Total for eriod Ci 6.65 E+01 7.13 E+01 2.23 E+00

2. Iodines iodine.131 < LLD < LLD Note 1 Note 2 iodine.133 Ci 2.38 E.05 1.40 E-05 Note 1 Note 2 iodine.135 < LLD < LLD Nots 1 Note 2 Total for eriod 2.38 E.05 1.40 E-05

3. Particulates chromium-51 Ci < LLD < LLD Nots 1 Note 2 man anese.54 < LLO < LLD Note 1 Note 2 cobalt.58 < LLD < LLD Nots 1 Note 2 iron.59 Ci < LLD < LLO Note 1 Note 2 cobalt 60 < LLO <LLD Note 1 Note 2 zinc-65 Ci < LLD < LLO Note 1 Note 2 strontium-89 Ci < LLD < LLD Note 1 Note 2 strontium-90 < LLO < LLO Mots 1 Note 2 niobium-95 < LLD < LLO Nots 1 Note 2 zirconium-95 Ci < LLD < LLO Note 1 Note 2 mol bdenurn 99 < LLD < LLD Nots 1 Note 2 cesium-134 < LLO < LLD Note 1 Note 2 cesium-137 < LLD < LLD Note 1 Note 2 barium-140 Ci < LLD < LLD Note 1 Note 2 lanthanum-140 < LLD < LLD Note 1 Note 2 cerium-141 < LLD < LLD Note 1 Mote 2 cerium.144 Ci < LLD < LLD Nots 1 Note 2 Total for cried < LLD < LLD Note 1 - No Batch Releases wore made during first cuarter of 1995.

Note 2 -The particulate snd iodine activities released from batch releases are included In the particulate and iodine determinations from the continuous releases.

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission ases xenon-131m Ci < LLD < LLD Note 1 3.69 E-03 xenon.133 Ci 2.14 E+01 2.11 E+01 Note 1 1.43 E-01 xenon-133m Ci < LLD < LLD Note 1 1.08 E-04 xenon-135 Ci 3.52 E+01 6.02 E+01 Note 1 4.97 E-04 xenon-135m Ci < LLD < LLD Note 1 <LLD xenon-138 Ci < LLD < LLD Note 1 <LLD ar on.41 Ci < LLD < LLD Note 1 <LLD k ton 85 Ci < LLO < LLD Note 1 2.08 E+00 k ton 85m Ci < LLD < LLD Note 1 <LLD k ton-87 Ci < LLO < LLD Note 1 <LLD k ton.88 Ci < LLD < LLD Note 1 <LLO Total for eriosd 5.65 5+01 7.13 E+01 2.23 E+00

2. Iodines iodine-131 < LLD < LLD Note 1 Note 2 iodine-133 Ci 2.38 E-05 1.40 E-05 Note 1 Note 2 iodine-135 CI < LLD < LLD Note 1 Note 2 Total for eriod Ci 2.38 E.05 1.40 E-05

3. Particulates chromium-51 Ci < LLD < LLD Note 1 Note 2 man anese-54 < LLD < LLD Note 1 Note 2 cobalt.58 CI < LLD < LLD Note 1 Note 2 iron-59 Ci < LLD < LLD Note 1 Note 2 cobalt-60 CI < LLD <LLD Note 1 Note 2 zinc-65 Ci < LLD < LLO Note 1 Note 2 strontium-89 Ci < LLD < LLO Note 1 Note 2 strontium-90 Ci < LLD < LLO Note 1 Note 2 niobium.95 Ci < LLD < LLD Note 1 Note 2 zirconium-95 < LLD < LLD Note 1 Note 2 mol bdenum-99 Ci < LLD < LLD Note 1 Note 2 cesium.134 < LLO < LLD Note 1 Note 2 cesium-137 Ci < LLD < LLD Note 1 Note 2 barium-140 < LLD < LLD Note 1 Note 2 lanthanum-140 CI < LLD < LLD Note 1 Note 2 cerium-141 < LLD < LLD Note 1 Note 2 cerium-144 Ci < LLD < LLD Note 1 Note 2 Total for cried < LLD < LLD Note 1 - No Batch Releases were made. during first quarter of 1995.

Note 2-The particulate and Iodine activities released from batch releases are included In the particulate and Iodine determinations from the continuous releases.

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission gases xenon-131m Ci < LLD < LLD 2.11 E-03 < LLD xenon-133 Ci 2.05 E+01 1.38 E+01 8.62 E-03 9.48 E-02 xenon-133m Ci < LLD < LLD 1.20 E-04 <LLD xenon-135 Ci 3.48 E+ol 2.14 E+01 6.83 E-04 2,94 E-01 xenon-135m Ci < LLD < LLD < LLD < LLD xenon-138 Ci < LLO < LLD < LLO < LLO ar on.41 Ci < LLD < LLD < LLD 4.12 E.03 k ton.85 Ci < LLD < LLD 1.31 E+00 < LLD k ton-85m Ci < LLD < LLD < LLO 1.38 E-02 k ton-87 Ci < LLO < LLD < LLO < LLD k ton.88 Ci < LLO < LLD < LLD < LLO Total for cried Ci 6.63 E+01 3.52 E+01 1.32 5+00 4.06 E-01

2. lodines iodine.131 Ci 4.10 E-05 < LLD 2.04 E.06 < LLD iodine.133 Ci < LLD < LLD < LLD < LLD iodine-135 Ci < LLD < LLD < LLD < LLD Total for cried 4.10 E-05 < LLD 2.04 E-06 < LLD

3. Particulates chromium-51 < LLD < LLD 8.23 E.07 < LLD man anese 54 Ci < LLD < LLD 7.60 E-08 < LLO cobalt-58 < LLO < LLD 1.61 E.oa < LLO iron.69 Ci < LLD < LLD <LLD < LLD cobalt-60 8.04 E.OS 3.02 E-05 1.86 E.07 < LLD zinc.65 < LLD < LLD < LLD < LLD strontium-89 < LLD < LLD < LLO < LLD strontium-90 < LLD < LLD < LLD < LLD niobium.95 Ci <LLO <LLD 9.55 E-08 < LLD zirconium.95 Ci <LLD <LLD 1.50 E-07 < LLD mol bdenum-99 Ci < LLD < LLD < LLD < LLD cesium-134 Ci < LLD < LLD < LLO < LLD cesium-137 < LLD < LLD < LLD < LLD barium.140 Ci < LLD < LLO < LLD < LLO lanthanum-140 Ci < LLD < LLD < LLD < LLD cerium-141 Ci < LLO < LLD < LLD < LLO cerium-144 Ci < LLD < LLD < LLD < LLO Total for cried 8.04 E-05 3.02 E.05 2.94 E-06 < LLO Note - The Batch Particulate snd iodine releases are due to positive pressure in the Containment during refueling outage. Two releases were made via the Equipment Hatch.

2/7

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and Activation products

1. Total release Inot including tritium, Ci 1.86 E-02 1.79 E-02 3.28 E+01 ases, alpha)

2. Average diluted concentration during yCi/ml 2.28 E-09 2.52 E-09 eflod

3. Percent of a licable limit 2.00 E-02 3.00 E-02 B. Tritium

1. Total release Ci 7.98 E+01 1.15 E+02 3.28 E+01

2. Average diluted concentration during yCI/ml 9.79 E-09 1.62 E-08 eriod

3. Percent of a licable limit 3.26 E-04 5.39 E-04 C. Dissolved and entrained ases

1. Total release Ci 1.19 E-02 2.03 E-02 3.28 E+01

2. Average diluted concentration during pCI/ml 1.46 E-09 2.85 E-09 eriod

3. Percent of a licable limit 7.31 E-04 1.43 E-03 D. Gross al ha radioactivity

1. Total release Ci < LLD < LLD 3.28 E+01 E. Volume of waste released (prior to dilution) liters 8.58 E+05 1.36 E+06 2.00 E+01 F. Volume of dilution water used durin period liters 8.15 E+09 7.11 E+09 2.00 E+01

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and Activation roducts

1. Total release (not including tritium, Ci 2.12 E-02 6.16 E-02 3.28 E+01 ases, ai ha)

2. Average diluted concentration during pCI/ml 3.21 E-09 9.53 E-09 enod

3. Percent of applicable limit 3.00 E-02 5.00 E-02 B. Tritium

1. Total release Ci 8.54 E+01 3.81 E+01 3.28 E+01

2. Average diluted concentration during yCI/ml 1.24 E-08 5.89 E-09 period

3. Percent of a licable limit 4.14 E-04 1.96 E-04 C. Dissolved and entrained ases 1 ~ Total release Ci 5.73 E-03 7.21 E-04 3.28 E+01

2. Average diluted concentration during pCI/ml 8.67 E-10 1.11 E-10 eriod

3. Percent of a licable limit 4.33 E-04 5.57 E-04 D. Gross alpha radioactivit

1. Total release Ci ( LLD ( LLD 3.28 E+01 E. Volume of waste released ( rior to dilution) liters 2.88 E+06 1.62 E+06 2.00 E+01 F. Volume of dilution water used durin period liters 6.61 E+09 6.47 E+09 2.00 E+01

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode man anese-54 Ci Note 1 Note 1 9.36 E-05 4.04 E-05 iron-55 Ci Note 1 Note 1 3.46 E-03 3.23 E-03 cobalt-57 Ci No e1 Note 1 1.58 E-05 1.03 E-05 cobalt-58 Ci Note 1 Note 1 6.47 E-03 2.40 E-03 iron-69 Ci Note 1 Note 1 < LLD < LLD cobalt-60 Ci Note 1 Note 1 2.60 E-03 2.63 E-03 nickel.63 Ci Note 1 Note 1 1.53 E-03 1.95 E-03 zinc-65 Ci Note 1 Note 1 < LLD < LLD strontium-89 Ci No e1 Note 1 < LLD < LLD strontium-90 Ci Note 1 Note 1 < LLD < LLD zirconium-95 Ci Note 1 Note 1 <LLD <LLD niobium-95 Ci Note 1 Note 1 3.08 E-05 2.22 E-05 technicium-99m Ci Note 1 Note 1 2.40 E-05 3.83 E-05 mol bdenum-99 Ci Note 1 Note 1 < LLD < LLD ruthenium-106 Ci Note 1 Note 1 <LLD < LLD antimon -124 Ci Note 1 Note 1 <LLD < LLD antimon -125 Ci Note 1 Note 1 4.28 E-03 6.59 E-03 antirnon -126 Ci Note 1 Mots 1 <LLD < LLD tellurium-132 Ci Note 1 Note 1 <LLD < LLD iodine-131 Ci Nots 1 Note 1 6.94 E-05 3.41 E-04 iodine-133 Ci Note 1 Note 1 < LLD 6.76 E-05 cesium-134 Ci Note 1 Note 1 1.52 E-06 1.83 E-04 cesium-137 Ci Note 1 Note 1 1.68 E-05 2.88 E-04 barium-140 Ci Note 1 Note 1 <LLD < LLD lanthanum-140 Ci Note 1 No e1 < LLD < LLD corium-139 Ci Note 1 Nots 1 < LLD 4.25 E-06 cerium-141 Ci Note 1 No e1 < LLD < LLD corium-144 Ci Note 1 Note 1 < LLD < LLD TOTAL Ci Note 1 Note 1 1.86 E-02 1.79 E-02 xenon-133 Ci Note 1 Note 1 1.11 E-02 1.87 E-02 xenon-133m Ci Note 1 Note 1 2.75 E-04 2.95 E-04 xenon-135 Ci Note 1 Note 1 5.67 E-04 1.30 E-03 TOTAL Ci 1.19 E-02 2.03 E-02 Note 1 - No Continuous Releases were made during first or second quarters

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS n in B Mo Note 1 - No Continuous Releases were made during third or fourth quarters

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

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

Type of Waste

a. Spent Resin, filter sludge, etc.

No waste of this type shipped

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

Number of Shipments 15 Activity Shipped 4.31 E-01 Ci Estimated Total Error 180%'.32 Quantity Shipped E+00 m Solidification Agent N/A Container Type Strong Tight Package NRC-Approved Package Shipment Form Dewatered

c. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/12

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

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

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

a. Spent Resin, filter sludge, etc.

No waste of this type shipped

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

Percent Total Activity Nuclide Composition Ci C-14 3.01 E-04 1.30 E-06 Mn-54 4.10 E-02 1.77 E-04 Fe-55 7.10 E+01 3.07 E-01 Co-57 1.71 E-03 7.40 E-06 Co-58 1.48 E+00 6.37 E-03 Co-60 2.23 E+01 9.61 E-02 Ni-63 4 '8 E+00 2.15 E-02 Sr-89 1.51 E-03 6.50 E-06 Nb-95 2.32 E-02 1.00 E-04 Zr-95 1. 16 E" 02 5.00 E-05 Cs-134 2.32 E"03 1.00 E"05 Cs-137 9.96 E-02 4.30 E-04 Ce-144 9.96 E-04 4.30 E-06 Am-241 3.01 E-06 1.30 E-08 Pu-241 5.42 E-06 2 '4 E-08 Cm-242 6.88 E-09 2.97 E-11 TRU (*) 3.99 E-06 1.72 E-08

The TRU value is included as an isotopic contribution of 6 incore detectors which were disposed of during this period.

c. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/13

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )

C. Solid Waste Disposal Number of Shipments

15 Mode of Transportation Truck Destination Barnwell, S.C.

The fifteen type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.

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

A. Type of Waste Spent Resin, filter sludge, etc.

Number of Shipments 1 Activity Shipped 6.60 E+Ol Ci Estimated Total Error 128%'.85 Quantity Shipped E+00 m Solidification Agent, N/A Container Type NRC-Approved Package Shipment Form Dewatered Dry Compressible Waste, Contaminated Equipment, etc. ( DAW )

Number of Shipments 1 Activity Shipped 1.05 E+01 Ci Estimated Total Error 180%'.89 Quantity Shipped E-01 m Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered C. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped

Appendix 2 (Continued): Effluent and Waste Disposal Report 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 Resin, filter sludge, etc.

Percent Total Activity Nuclide Composition Ci H-3 6.53 E-03 4.31 E-03 C" 14 5.33 E-03 3.52 E-03 Fe-55 3.35 E+01 2.21 E+01 Co-60 4.86 E+01 3.21 E+01 Ni-63 1.10 E+00 7.31 E-01 Sr-90 1.16 E-01 7.66 E-02 Nb-94 3.48 E"03 2.30 E-03 Cs-134 6.92 E+00 4.57 E+00 Cs-137 9.58 E+00 6.33 E+00 Pu-238 1.01 E-03 6.68 E-04 PG-239/40 7.57 E-04 5.00 E-04 Pu-241 1.67 E-01 1.10 E-01 Cm-242 7.24 E-04 4.78 E-04 Cm-243/44 6.04 E-04 3.99 E-04

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

Percent Total Activity Nuclide Composition Ci H-3 2.90 E-05 3.00 E-06 C-14 5.49 E-06 5.70 E-07 Mn-54 6.59 E+00 6.81 E-01 Fe-55 1.41 E+01 1.48 E+00 Co-58 1.85 E+01 1.94 E+00 Ni-59 4.00 E-01 4.19 E-02 Co-60 1 ~ 75 E+01 1.83 E+00 Ni-63 1.91 E+01 2.00 E+00 Sr-90 1.83 E-04 2.00 E-05 Nb-94 3.90 E-06 4.10 E-07 Tc-99 2.58 E-06 2.70 E-07 Cd-109 3.60 E+00 3.77 E-01 Sb-125 2.30 E+00 2.41 E-01 Cs-134 9.30 E+00 9.74 E-01 Cs-137 8.70 E+00 9.11 E-01 Pu-241 6.40 E-05 6.70 E-06 Cm-242 1.19 E-06 1.25 E-07 Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/15

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

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

C. Solid Waste Disposal Number of Shipments

2 Mode of Transportation Truck Destination Barnwell, S.C.

The type 2.A.a shipment was made from HNP. The type 2.A.b shipment was made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.

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

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

Irradiated Fuel Shipments (Disposition)

No irradiated fuel was shipped during this Report Period.

Appendix 3 : Changes to Process Control Program (PCP)

Technical Specification 6.13

1. During this reporting period, HNP instituted administrative changes to the PCP per guidance from Generic Letter 89-01. These changes are as follows:

A. HNP Technical Specifications

a. 3/4.11.3, Solid Radioactive Wastes, and

b. 6.15, Major Changes to Solid Radwaste Treatment Systems were removed from HNP Technical Specifications and included in PLP-300, Process Control Program, as Attachment 1, "Solid Radwaste Programmatic Controls".

2. No major changes to solid radioactive waste treatment systems were made during this reporting period.

Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14.c During 1995, the ODCM was revised three times as revisions 6, 7, and 8. Descriptions of each revision are listed below.

REVZSZON 6g AUGUST 1995 Revision 6 of the ODCM incorporated two "global" changes and several smaller, individual changes. The two global changes were a result of Generic Letter 89-01 and its resulting Tech Spec change. These changes are described below and will be identified as Change 1 and Change 2.

Change 1 Generic Letter 89-01 relocated a number of Technical Specifications, called the Radiological Effluent Technical Specifications (RETS), from the Technical Specifications to the ODCM. In relocating these specifications, the description of the specification was changed from ~Qgjg~

All of the requirements of the specifications were transferred, and the number of the specification was not changed. (Example: Technical Specification 3. 11.1.1 is now Operational Requirement 3.11.1.1) .

Change 2 Changed the frequency of the Radioactive Effluent Release Report from Semi-annual to Annual.

The other changes in revision 6 are detailed below:

Section Pa e Descri tion Title Pa e Revised to Rev. 6.

TOC, LOT 6c See Change 1. Added Appendices D, E, F, and G LEP and other information as required. Revised LEP.

1.0 Editorial by removing last sentence of second ara ra h and see Chan e 1 2.0 2-1 thru Page 2-1, Change 1, and Added "Secondary Waste 2-8 Sample Tank".

Page 2 Editorial 3'aragraph - changed "says" to "state", removed unnecessary parenthesis and see Change 1.

Page 2 Editorial for defining "V" to be consistent with Table 2.1-1 6 Change 1.

Pa e 2-5 thru 2 See Chan e 1.

2.0 2-10 thru Page 2 Last paragraph & sentence was 2-12 revised as an editorial change by removing "input" and Change 1.

Page 2 See Change 1.

Page 2 Last paragraph, removed statement "Tritium activity will be administratively controlled to limit the activity at the release oint" and see Chan e 1.

2.0 2-15 See Chan e 1

Section Pa e Descri tion 2.0 2-17 thru See Change 1 2-18 2.0 2-19 The recirculation rate (pump design capacity) for the WECT was changed from 100 gpm to 35 gpm.

Radwaste procedures have always required recirculating the WECT at 35 gpm for 2 volumes rior to sam lin Fig. 2. 1-2 2-28 Converted figure to an electronic image and made correction showing Spectacle Flange from Waste Monitor Tank. This was a correction to the drawin and not a modification.

Fig. 2.1-3 2-29 Converted Figure to an electronic image. No technical chan e to Fi re.

Fig. 2.1-4 2-30 Converted Figure to an electronic image. The flanged pipe originally ran from the Waste Neutralization Basin to the Cooling Tower Blowdown (CTBD). The flanged pipe was relocated to downstream of the Yard Oil Separator to the CTBD. This was a correction to the drawing and not a modification.

3.0 3-1 See Chan e 1 3.0 3-15 thru See Change 1 3-17 3.0 3-24 See Chan e 1 3.0 3-27 thru See Change 1 3-28 3.0 3-31 thru See Change 1 3-33 3.0 3-53 Figure 3.1, Corrected the monitor numbers for the RAB Normal t RAB Emer enc Exhaust Table 4.1 4-2 Sample Point ¹5 (Control Station) was relocated from the NW Sector to WNW Sector due to CPaL's office chan in location.

Table 4.1 4-3 Sample Point ¹5 (Control Station) was relocated from the NW Sector to WNW Sector due to CPkL's office chan in location.

Table 4.1 4-11 Sample Point 43 (Goodwin's Dairy) "is no longer in business" was added and corrected typo for Road Number (from 1403 to 1134).

Table 4.1 4" 13 Sample Point 64 is a new monitoring location.

Addition to Radiological Environmental Monitorin Pro ram Fig. 4.1-4 4-19 Sample Point 64 is a new monitoring location.

Addition to Radiological Environmental Monitorin Pro ram Fig. 4.1-5 4-20 Sample Point 64 is a new monitoring location.

Addition to Radiological Environmental Monitorin Pro ram 4/2

Section Pa e Descri tion 5.0 5-1 See Chan e 1 6.0 6-1 thru See Change 1 6-2 See Chan e 2 7.0 7-1 Revised to reflect the requirements in Generic Letter 89-01. Com lete rewrite of section.

A . A A-2 See Chan e 1 Tables A-1 A-4 thru Retyped tables for clarity. Put into WP61 Table thru A-14 A-21 format. No change to any of the table data.

Deleted redundant information. Rearranged data to make fit in ODCM.

A . B B-1 See Chan e 1 A . B B-3 See Chan e 1 App. D D-1 thru This is a new Appendix incorporating the D-41 relocated Technical Specifications. The text is the same as what was in the Technical Specifications. The only change has been some minor formatting changes to get the pages to fit the ODCM format.

App. E E-1 thru This is a new Appendix incorporating the BASES E-11 of the relocated Technical Specifications. The text is the same as what was in the Technical Specifications. The only change has been some minor formatting changes to get the pages to fit the ODCM format.

App. F F-1 thru This is a new Appendix incorporating the F-5 ADMINISTRATIVE CONTROLS of the relocated Technical Specifications. The text is the same as what was in the Technical Specifications or as revised by the Generic Letter submittal. The only change has been some minor formatting chan es to et the a es to fit the ODCM format.

App. G G-1 thru This is a new Appendix incorporating G-5 Definitions, Frequency Notations, and the Operational Modes from the Technical Specifications. The text is the same as what was in the Technical Specifications. This information was added since the relocated Specifications have specific actions associated with articular definitions.

Incorporation of the 1994 Land Use Census data.

Technical Specification 3/4.12.2 requires that a land use census be performed annually. The land use census was performed in July and August, 1994. Table 3.2-2 has been revised to show the results of the 1994 Land Use census. This change has no impact on the ODCM since all it does is to incorporate current information. This is a routine change made annually.

2. REVISION 7 g NOVEMBER 1995 The ODCM classifies the Outdoor Tank Area Drain monitor (REM-01MD-3530) as one 4/3

providing automatic termination of release. This is based on a stop signal sent from the monitor to the Tank Area Drains (TAD) discharge pump on high radiation alarm, Zt was possible, however, to have some gravity flow through the system even after the discharge pump was turned off. To mitigate this effect, a spring loaded check valve was installed downstream of the discharge pump by PCR-4213.

Full credit cannot be taken for this check valve because it is susceptible to leak-by due to debris on the valve seat. Hence, the Outdoor Tank Area Drain Monitor does not currently provide "full automatic termination of the release".

Revision 7 changes the classification of this monitor from "providing automatic termination of the release" to "providing alarm and stop signal to the discharge pump" .

Section Pa e Descri tion Title Pa e Revised to Rev. 7.

LEP Chan ed revision numbers as a ro riate.

2.0 See above comment for chan es in 2.1.3.1 Table D-3 See above comment for changes.

3 03-12 Table D-5 See above comment for changes.

4.3-8 Table D-6 See above comment for changes for Notes 1 and 4.3-8 cont 2.b.

RBVZSXON 8I NOVEMBER 1995 Revision 8 to ODCM incorporated the new GALE code for source terms in the Updated FSAR due to changes in the operation of the Waste Gas Treatment System.

Section Pa e . Descri tion Title Pa e Revised to Rev. 8.

LEP vl. Chan ed revision numbers as a ro riate.

3.0 3-12 See above comment for chan e.

3.0 3-18 See above comment for change.

This is the latest revision of the ODCM and is attached to this Annual Effluent Report.

4/4

Appendix 5 : Changes to the Environmental Monitoring Program Offsite Dose Calculation Manual Operational Requirement 3. 12. 1.c As a result of the annual land-use census which was performed during July and August 1995, a change to the Environmental Sampling Program and to the ODCM was made as follows; Sample Point 43, Goodwin's Dairy on SR 1134 was dropped from the environmental program due to going out of business.

Offsite Dose Calculation Manual Operational Requirements 3.12.2.a and 3.12.2.b The land-use census that was completed in August 1994 resulted in an ODCM change, Revision 6, and is documented in Appendix 4 of the 1995 Annual Radioactive Effluent Release Report. This change required Sample Point 64, (Food Crop) in the ENE Sector (1. 8 miles from the site) to be added to the ODCM. Figure 4.1-4 on page 4-19 and Table 4.1 on page 4-13 are in the attached ODCM Revision 8.

The 1995 Land Use Census did require a change to the Environmental Monitoring Program and to the ODCM. Sample Point 43, Goodwin's Dairy on SR 1134 was dropped from the environmental program due to going out of business.

See the attached ODCM Revision 8, Table 4.1 page 4-11 for the revision.

Appendix 6 : Additional ODCM Operational Requirements ODCM Operational Requirement 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During this Report Period No liquid effluent monitoring instrumentation specified in ODCM Operational Requirements, Table 3.3-12 was inoperable for greater than 30 Days during this Report period.

ODCM Operational Requirement 3.3.3.11, Action a (Radiation Gas Monitors)

Monitors Out-of-Service > 30 Days During this Report Period The instruments listed in ODCM Operational Requirement 3.3.3.11 were reviewed for operability during 1995. None were inoperable for greater than 30 days during this report period.

Techncial Specification 3.3.3.11, Action a (Explosive Gas Monitors)

Monitors Out-of-Service > 30 Days During this Report Period The instruments listed in Technical Specification 3.3.3.11 were reviewed for operability during 1995. None were inoperable for greater than 30 days during this report period.

Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.

Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.

Appendix 7 : Major Modifications to Radwaste System ODCM Operational Requirement F.3 No major modifications were made to the Radwaste System during this Report period.

Appendix 8 : 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 at Corporate headquarters. This data will be provided to the NRC upon request.

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses

1. Integrated Population Dose Due to Liquid Effluents (man-rem)

A. 50 mile Ingestion Zone 1995 Bone Liver T. Body Thyroid Kidney GZ-LLZ Skin Sport Fish 4.94 E-02 4.59 E-02 3.02 E-02 7.31 E-03 1.92 E-02 1.17 E-02 1.68 E-02 0.00 E+00 Com Fish 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Sport Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Com Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 Eeoo 0.00 E+00 Drinking Water 2.52 E-02 6.36 E-01 6.36 E-01 6.33 E-01 6.33 E-01 6.34 E-01 6.59 E-01 0.00 E+00 Shoreline 2.70 E-02 2.70 E-02 2.70 E-02 2.70 E-02 2.70 E-02 2.70 E-02 2.70 E-02 3.14 E-02 Swimming 1.67 E-04 1.67 E-04 1.67 E-04 1.67 E-04 1.67 E-04 1.67 E-04 1.67 E-04 0.00 E+00 Boating 8.41 E-05 8.41 E-05 8.41 E-05 8.41 E-05 8.41 E-05 8.41 E-05 8.41 E-05 0.00 E+00 Zrri Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Zrri Leafy Veg 0 F 00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Zrri Milk 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Irri Meat 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 All Pathways 1.02 E-01 7.09 E-01 6.93 E-01 6.67 E-Ol 6.79 E-01 6.73 E-01 7.03 E-01 3.14 E-02 B. Tritium (Hydrosphere)

Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Total 0.00 E+00 4.21 E-03 4.21 E-03 4.21 E-03 4.21 E-03 4.21 E-03 4.21 E-03

2. Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone T. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin Plume 6.81 E-02 6.81 E-02 6.81 E-02 6.81 E-02 6.81 E-02 6.81 E-02 7.07 E-02 2.32 E-01 Ground Plane 1.59 E-03 1.59 E-03 1.59 E-03 1.59 E-03 1.59 E-03 1.59 E-03 1.59 E-03 1.87 E-03 Inhalation Vegetation 1.16 E-03 4.21 E-04 1.18 4.53 E-03 E-04 1.60 7.07 E-06 E-07

1. 16

4. 17 E-03 E-04 1.16 E-03 4.15 E-04

l. 79 6.95 E-03 E-04 1.71 4.13 E-03 E-04 1.16 4.13 E-03 E-04 Cow Milk 1.39 E-04 1.41 E-04 1.06 E-06 1.39 E-04 1.40 E-04 5.47 E-04 1.38 E-04 1.38 E-04 Meat a Poultry 1.89 E-04 2.23 E-04 8.09 E-08 1.86 E-04 1.83 E-04 2.17 E-04 1.83 E-04 1.83 E-04 TOTAL 7 '6 E-02 7. 17 E-02 6.97 E-02 7.16 E-02 7.16 E-02 7.30 E-02 7.48 E-02 2.36 E-ol

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses D D

1. Individual Dose Due to Liquid Effluents (mrem/yr.)

Bone Liver T. Body Thyroid Kidney Lung Gi-LLZ Skin ADULT Fish 7.69 E-02 7 F 80 E-02 5.91 E-02 1.34 E-02 3.35 E-02 2.05 E-02 3.28 E-02 Drinking 1.81 E-04 5.93 E-03 5.93 E-03 5.90 E-03 5.90 E-03 5. 91 E-03 6.19 E-03 Shoreline 2.74 E-02 2.74 E-02 2.74 E-02 2.74 E-02 2.74 E-02 2.74 E-02 2.74 E-02 3. 19 E-02 Swimming 1. 52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1. 52 E-04 1.52 E"04 Boating 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 TOTAL 1.05 E-01 1. 12 E-01 9.27 E-02 4.69 E-02 6.70 E-02 5.40 E-02 6.66 E-02 3.19 E-02 TEEN Fish 7.05 E-02 6.75 E-02 3.27 E-02 9.03 E-03 2.71 E-02 1.65 E-02 2.10 E-02 Drinking Shoreline 1.73 1.96 E-04 E-02 4.19 1.96 E-03 E-02 4.18 1.96 E-03 E-02 4.16 1.96 E-03 E-02 4.16 1.96 E-03 E-02 4.18 1.96 E-03 E-02 4 '5

1. 96 E-03 E-02 2.28 E-02 Swimming 1.52 E-04 1.52 E"04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 Boating 7.59 E-05 7.59 E"05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-OS 7.59 E-05 9.05 E-02 9.15 E-02 5.67 E-02 3.30 E-02 5.11 E-02 4.05 E-02 4.52 E-02 2.28 E-02 CHZLD Fish 1.57 E-01 1.03 E-01 3.23 E-02 1.30 E-02 3.97 E-02 2.33 E-02 2.03 E-02 Drinking 5.22 E-04 8.03 E-03 8.02 E-03 7.98 E-03 7.97 E-03 8.00 E-03 8.13 E-03 Shoreline 1.17 E-02 1. 17 E-02 1.17 E-02 1.17 E-02 1.17 E-02 1.17 E-02 1.17 E-02 1.37 E-02 Swimming 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 1.52 E-04 Boating 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-05 7.59 E-OS 1.69 E-01 1.23 E-01 5.23 E-02 3.30 E-02 5.97 E-02 4.33 E-02 4.04 E-02 1.37 E-02 INFANTS are assumed to have no exposure via this pathway.

9/2

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses

2. Individual Dose Due to Gaseous Effluents (mrem/yr.)

T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.19 E-03 1.62 E-02 Ground Plane 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 2.27 E-04 Inhalation 2.79 E-05 2.88 E-05 4.25 E-08 2.79 E-05 2.79 E-05 4.56 E-05 4.70 E-05 2.78 E-05 TOTAL 6 '8 E-03 6.28 E-03 6.25 E-03 6.28 E-03 6.28 E-03 6.30 E-03 6.43 E-03 1.65 E-02 TEENAGER Plume 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.06 E-03 6.19 E-03 1.62 E-02 Ground Plane 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 1.93 E-04 2.27 E-04 Inhalation 2.81 E-05 2.88 E"05 5.97 E-08 2.81 E-05 2.81 E-05 5.01 E-05 5.60 E-05 2.80 E-05 TOTAL 6.28 E-03 6.28 E-03 6.25 E-03 6.28 E-03 6.28 E-03 6.30 E-03 6.44 E-03 1.65 E-02 CHILD Plume Ground Plane 6 '6 E-03 1.93 E-04 6.06 E-03 1.93 E-04 6.06 E-03 1.93 E-04 6.06 1.93 E-03 E"04 6.06 1.93 E-03 E-04 6.06 E-03 1.93 E-04 6.19 1.93 E-03 E-04 1.62 2.27 E-02 E-04 Inhalation 2.49 E-05 2.51 E"05 8.11 E-08 2.49 E-05 2.49 E-05 5.00 E-05 4.74 E-05 2.48 E-05 TOTAL 6.28 E-03 6.28 E-03 6 '5 E-03 6.28 E-03 6.28 E-03 6.30 E-03 6.43 E-03 1.65 E-02 INFANTS are assumed to have no exposure via this pathway.

9/3

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses

1. Individual Dose Due to Liquid Effluents (mrem/yr.)

ADULT Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Fish 5.38 E-02 5.46 E"02 4.14 E-02 9.36 E-03 2.34 E-02 1.43 E-02 2.29 E-02 Drinking 1.81 E-04 5.93 E-03 5.93 E-03 5.90 E-03 5.90 E-03 5.91 E-03 6.18 E-03 Shoreline 2.82 E"03 2.82 E-03 2.82 E-03 2.82 E-03 2.82 E-03 2.82 E-03 2.82 E-03 3.28 E"03 Swimming 1.82 E-04 1.82 E-04 1.82 E-04 1.82 E-04 1.82 E-04 1.82 E-04 1.82 E-04 Boating 2.09 E-04 2.09 E-04 2.09 E-04 2.09 E-04 2.09 E"04 2.09 E-04 2.09 E-04 TOTAL 5.72 E-02 6.38 E-02 5.05 E-02 1.85 E-02 3.25 E-02 2.34 E-02 3.23 E-02 3.28 E-03 TEEN Fish 5.64 E-02 5.40 E-02 2. 61 E-02 7.22 E-03 2.17 E-02 1.32 E-02 1.68 E-02 Drinking 1.73 E-04 4. 19 E-03 4.18 E-03 4.16 E-03 4.16 E-03 4.18 E-03 4.35 E-03 Shoreline 1.57 E-02 1.57 E-02 1.57 E-02 1.57 E-02 1.57 E-02 1. 57 E-02 1.57 E-02 1.83 E-02 Swimming 2.73 E-04 2.73 E-04 2.73 E-04 2.73 E-04 2.73 E-04 2.73 E-04 2.73 E-04 Boating 3.03 E-04 3.03 E-04 3.03 E-04 3.03 E-04 3.03 E-04 3.03 E-04 3.03 E-04 TOTAL 7.29 E-02 7.45 E-02 4.67 E-02 2.77 E-02 4.22 E-02 3.37 E-02 3 '5 E-02 1.83 E-02 CHILD Fish 7.22 E-02 4.75 E-02 1.49 E-02 5.99 E-03 1.83 E-02 1.07 E-02 9.32 E-03 Drinking 5.22 E-04 8.03 E-03 8.02 E-03 7.98 E-03 7.97 E-03 8.00 E-03 8.13 E-03 Shoreline 3.29 E-03 3.29 E-03 3.29 E-03 3.29 E-03 3.29 E-03 3.29 E-03 3.29 E-03 3.82 E-03 Swimming 9.10 E-OS 9.10 E-05 9.10 E-05 9.10 E-05 9.10 E-05 9.10 E-05 9.10 E-05 Boating 1.14 E-04 1.14 E-04 1.14 E-04 l. 14 E-04 1.14 E-04 1.14 E-04 1.14 E-04 TOTAL 7.62 E-02 5. 91 E-02 2.64 E-02 1.75 E-02 2.98 E-02 2.022E-02 2.09 E-02 3.82 E-03 INFANT Drinking 4.21 E-04 7.89 E-03 7.87 E-03 7.84 E-03 7.83 E-03 7.86 E-03 7.92 E-03 TOTAL 4.21 E-04 7.89 E-03 7.87 E-03 7.84 E-03 7.83 E-03 7.86 E-03 7.92 E-03 9/4

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Most Likely Exposed Member of the Public

2. Individual Dose Due to Gaseous Effluents (mrem/yr.)

A. Maximum Hypothetical Individual - Exposure from Noble Gases, Particulates, Iodines, and Tritium T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.66 E-02 1.54 E-01 Ground Plane 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 1.12 E-03 Inhalation 2.84 E-04 2.92 E-04 4.75 E-07 2.85 E-04 2.85 E-04 4.78 E-04 4.61 E-04 2.83 E-04 Vegetation 4.96 E-04 6.04 E-04 4.19 E-07 4.89 E-04 4.83 E-04 6.76 E-04 4.82 E-04 4.82 E-04 Cow Milk Meat & Poultry 5.15 E-05 7.37 E-05 4.20 E-08 4.99 E-05 4.86 E-05 6.81 E-05 4.85 E-05 4.85 E-05 TOTAL 5.70 E-02 5.72 E-02 5.62 E-02 5.70 E-02 5.70 E-02 5.74 E-02 5.85 E-02 1.56 E-01 TEENAGER Plume 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.66 E-02 1.54 E-01 Ground Plane 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 1.12 E-03 Inhalation 2.86 E-04 2.93 E-04 6.67 E-07 2.87 E-04 2.87 E-04 5.26 E-04 5.44 E-04 2.85 E-04 Vegetation 5.89 E-04 6.95 E-04 4.06 E-07 5.76 E-04 5.67 E-04 7.31 E-04 5.66 E-04 5.66 E-04 Cow Milk Meat & Poultry 3.13 E-05 4.25 E-05 3.49 E-08 3.00 E-05 2.90 E-05 4.31 E-05 2.90 E-05 2.90 E-05 TOTAL 5.71 E-02 5.72 E-02 5.62 E-02 5.71 E-02 5.71 E-02 5.75 E-02 5.87 E-02 1.56 E-01 CHILD Plume 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.66 E-02 1.54 E-01 Ground Plane 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 1.12 E-03 Inhalation 2.53 E-04 2.55 E-04 9.04 E-07 2.54 E-04 2.54 E-04 5.26 E-04 4.62 E-04 2.52 E-04 Vegetation 9.29 E-04 9.68 E-04 7.66 E-07 9.00 E-04 8.85 E-04 1.14 E-03 8.84 E-04 8.84 E-04 Cow Milk Meat a Poultry 3.86 E-05 4.18 E-05 6.46 E-08 3.63 E-05 3.51 E-05 5.64 E-05 3.50 E-05 3.50 E-05 TOTAL 5.74 E-02 5.75 E-02 5.62 E-02 5.74 E-02 5.74 E-02 5.79 E-02 5.89 E-02 1.56 E-01 ENFANT Plume 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.53 E-02 5.66 E-02 1.54 E-01 Ground Plane 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 9.50 E-04 1.12 E-03 Inhalation 1.46 E-04 1.46 E-04 7.08 E-07 1.46 E-04 1.46 E-04 3.96 E-04 2.79 E-04 1.45 E-04 Cow Milk TOTAL 5.63 E-02 5.63 E-02 5.62 E-02 5.63 E-02 5.63 E-02 5.66 E-02 5.78 E"02 1.55 E-01 9/5

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Most Likely Exposed Member of the Public

2. Individual Dose Due to Gaseous Effluents (mrem/yr.)

B. Maximum Real Individual Exposure from Noble Gases, Particulates, Iodines, and Tritium T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.36 E-03 2.21 E-02 Ground Plane Inhalation 1.11 4.41 E-04 E-05 1.11 4.53 E-04 E-05 1.11 6.41 E-04 E-08

l. 11 4.41 E-04 E-05 1.11 4.42 E-04 E-05 1.11 7.08 E-04 E-05 1.11 7.08 E-04 E-05 1.30 4.40 E-04 E-05 Vegetation 7.65 E-05 8.89 E-05 4.44 E-08 7.56 E-05 7.49 E-OS 9.54 E-05 7.48 E-05 7.48 E-05 Meat & Poultry TOTAL 8.40 E-03 8.41 E-03 8.28 E-03 8.40 E-03 8.40 E-03 8.45 E-03 8.61 E-03 2.23 E-02 TEENAGER Plume 8.17 E"03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.36 E-03 2.21 E-02 Ground Plane 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.30 E-04 Inhalation 4.44 E-05 4.55 E-05 9.01 E-08 4.45 E-05 4.45 E-05 7.77 E-05 8.34 E-05 4.43 E-05 Vegetation 9.05 E-05 1.03 E-04 4.31 E-08 8.91 E-05 8.80 E-05 1.05 E-04 8.79 E-05 8.79 E-05 Meat & Poultry TOTAL 8.41 E-03 8.43 E-03 8.28 E-03 8.41 E-03 8.41 E-03 8.46 E-03 8.64 E-03 2.23 E-02 CHILD Plume 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.36 E-03 2.21 E" 02 Ground Plane 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.30 E-04 Inhalation 3.93 E-05 3.96 E-05 1.22 E-07 3.93 E-05 3.94 E"05 7.71 E-05 7.09 E-05 3.92 E"05 Vegetation 1.42 E-04 1.47 E-04 8.12 E-08 1.39 E-04 1.37 E-04 1.64 E-04 1.37 E-04 1.37 E-04 Meat & Puoltry TOTAL 8.46 E"03 8.47 E-03 8.28 E-03 8.46 E-03 8.46 E-03 8.52 E-03 8.68 E-03 2.24 E-02 INFANT Plume 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.17 E-03 8.36 E-03 2.21 E-02 Ground Plane 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.11 E-04 1.30 E-04 Inhalation 2.26 E-05 2.27 E-05 9.65 E-08 2.27 E-05 2.27 E-05 5.73 E-05 4.28 E-05 2.25 E-05 TOTAL 8.30 E-03 8.30 E-03 8.28 E-03 8.30 E-03 8.30 E-03 8.34 E-03 8.51 E-03 2.22 E-02 9/6

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Most Likely Exposed Member of the Public

3. Annual Air Dose (mrad)

A. Maximum Hypothetical Individual: Beta = 1.33 E-01 Gamma = 8.47 E-02 B. Maximum Real Individual: Beta = 1.88 E-02 Gamma = 1.25 E-02

4. Doses Due to Direct Radiation from the Harris Plant On-going environmental TLD dose measurements show that the offsite Direct Radiation Dose is negligible.

9/7

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses Enclosure 4 : Major Assumptions Used to Calculate Radiation Doses

1. Doses Due to Liquid Effluents A. Dilution Factors Lm~n Harris Lake 1.00 E+00 Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 6.05 E+01* Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 6.05 E+01* Boating

The dilution of 6.05 E+01 is calculated using the average flow of the Buckhorn Creek (measured at the gauging station at Corinth, N.C.) which is the blowdown of the Lake (70.55 cfs) and the average flow of the Cape Fear River (4267.25 cfs) as measured at the gauging station at Lillington, N.C. The above information was provided by the United States Geological Service for 1995.

B. Populations Affected Harris Lake 1. 10 E+05 person-hours Shoreline, Swimming, Boating Harnett County 4.53 E+04 persons Drinking Water Dunn Intake 1. 67 E+04 persons Drinking Water Fayetteville Area 1.40 E+05 persons Drinking Water Fuquay-Varina 2.68 E+03 persons Drinking Water Holly Springs 2.27 E+02 persons Drinking Water Harris Lake/

Cape Fear River 7.84 E+03 person-hours Fishing Cape Fear River/

Raven Rock Park 5.00 E+04 person-hours Boatinq Raven Rock Park 4.40 E+05 person-hours Shoreline C. The doses from liquid effluents for "Activities Inside the Site Boundary" were based on the use of the Cape Fear River as the Drinking Water supply year round and in Harris Lake on site using the following assum tions:

Pathwa Fish Shoreline Boatin Usa e hr hr r Adult 10 12 100 Teen 10 9/8

Annual Radioactive Effluent Release Report January 1, 1995 to December 31, 1995 Appendix 9 : Assessment of Radiation Doses Enclosure 4 (Continued): Major Assumptions Used to Calculate Radiation Doses

2. Doses Due to Gaseous Effluents A. The 50 mile Ingestion Zone population is 1.47 E+06 persons.

B. The Maximum Real Individual is located at 4666 meters ("2.9 miles) in the SW sector. This is based on the 1995 land use census with applicable pathways.

C. The Maximum Hypothetical 1ndividual is located on the site boundary at 2140 meters in the SSW sector. There are no cow milk pathways within 5 miles of the site boundary therefore no doses were calculated via this pathway.

D. The dose calculations for the Inside the Site Boundary is in the southeast sector at1219 meters. The number hours er ear used for this calculation is 876 hours0.0101 days 0.243 hours 0.00145 weeks 3.33318e-4 months based on the following assumptions:

Activity Boating Swimming Fishing* Other**

Hours/year 100 100 480 196 80 a.s xng traps year times 6 ours ay equa s 480 ours/year.

- 98 days/year times 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s/day for hiking, bird watching, a etc. equals 196 hours0.00227 days 0.0544 hours 3.240741e-4 weeks 7.4578e-5 months .

E. Concurrent meteorology for batch and continuous releases was used for all radiological dose calculations.

The doses from each mode were summed to obtain the annual dose.

9/9

SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCN}

Revision 8 Docket No. STN-50-400 CAROLINA POWER & LIGHT'OMPANY Approval by PNSC Chairman )d~

Approval by General Manager Harris Plan Effective Date

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE OF CONTENTS Section T~it e 'arcae TABLE OF CONTENTS LIST OF TABLES LIST OF FIGURES LIST OF EFFECTIVE PAGES vi 1.0 INTRODUCTIOI) 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 Postrelease 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 5.0 INTERLABORATORY COMPARISON STUDIES 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190) 6-1 6.1 Dose to the Likely Most Exposed Member of the Public 6-1 6.2 Dose to a Member of the Public Due to Activities Within the Site Boundary 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM APPENDIX A METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS A-1 AP PENDI fi B DOSE PARAMETERS FOR RADIOZODI NES I PARTICULATES /

AND TRITIUM B-1 APPENDIX C - RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS C-1 1 APPENDIX D - PROGRAMMATIC CONTROLS D-1 APPENDIX E - PROGRAMMATIC CONTROL BASES E-1 APPENDIX F ADMINISTRATIVE CONTROLS F-1 APPENDIX G DEFINITIONS

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 LIST OF TABLES No. Title . Pacae

2. 1-1 Liquid Effluent Release Tanks and Pumps 2-19

2. 1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (F,,<<) 2-20 2.1-3 Signal Processor Time Constants (x) for GA Technologies RD-53 Liquid Effluent Monitors 2-20 2.1-4 Nuclide Parameters 2-21 2.2-1 Q, 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 (1)

Normal Operation (Curies/year) 3-18 302-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (Miles) 3-19 302-3 Dose Factors for Noble Gases 3-20 3.2-4 P<< 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 Radiological Environmental Monitoring Program . . . . . . . . 4-2 A-1 through A-4 X/Q and D/Q values foz long-term ground-level releases at special locations A-4

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

No. Title Pacae A-5 through A-6 Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (Sec/M') 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/M') . 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/M') . . . . ~ . . . A-9 A-11 through A-12 Distances (m ~) ~...................

Deposition Values (D/Q) For Long Term Releases At Standard

...Distribution A-11 A-13 Joint Wind Frequency Classes At SHNPP ......................

By.

Shearon Harris Plant Site Input Information Pasquill Stability for Continuous A-13 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

Shearon Harzis Nuclear Powez plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 LIST OF TABLES (continued)

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

3.3-12 Radioactive Liquid Effluent Monitoring Instrumentation D-3

'.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 Instzumentation 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 Frequency Notation . . . . . . . . . . . . . . . . . . . . . G-4 Operational Mode . . . . . . . . . . . ~ ~ . . . . . . . . . G-5

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 LIST OF FIGURES No. Title Pacae 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 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 4.1-5 Environmental Radiological Sampling Points 4-17

Shearon Harris Nuclear Power Plant (SHNPP) November 1995 Offsite Dose Calculation Manual (ODC~ Rev. 8 List of E ective a es Pacae Revision Cover Page ~ ~ ~ ~

6 ii-1ii \ ~ ~ 5 iv V ~ 0 ~ ~ ~ ~ ~ ~ 5 Vi . s Vii ~ 0

~ ~ 0 0 ~ ~

2-1 8 ~ ~ ~ ~ ~ ~

2-9 2-10 2-11 ~ ~ 0 ~ ~ ~ ~ ~

2-12 0 ~ ~, ~ ~ ~ ~ ~

2-13 2-14 0 ~

2-15 2-16 ~ ~ ~ \ ~

2-17 2-19 2-20 2-27 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~

2-28 \ ~ ~ ~ \ ~ ~ ~ ~

2-29 ~ ~ 0 ~ ~ ~

2-30 ~ ~

3-1 0 ~ ~

3-2 5 3-12 8 I 3-13 3-14 ~ ~ 5 3-15 3-17 3-18 0 ~ ~

3-19 3-23 3-24 ~ ~ ~ ~ ~ ~ 0 0 ~ ~

3-25 3-26 3-27 3-28 ~ ~ ~ ~ 6 3-29 3-30 0 ~ ~ ~

3-31 3-33 ~ ~

3-34 3-52 3-53 0 ~

3-54 3-55

Shearon Harris Nuclear Power Plant (SHNPP) November 1995 Offsite Dose Calculation Manual (ODCM) Rev. 7 List of Effective Pa es Pacae Revision 4-1 ~ ~ ~ ~ ~ ~

4-2 4-3 6 4 4-10 4-11 6 4-12 4-13 4-14 4-18 ~ 4 4 4-20 ~ ~ ~ ~ 6 5-1 ~ ~ ~ ~

6-1 6-2 ~ ~ ~ ~ ~ ~ ~ 6 7 1 ~ ~ ~ ~ ~ ~

A-1 ~ ~

A 2 ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 A-3 ~ ~ ~ ~

A-4 - A-21 ~ ~ 6 6

B-2 5 B-3 ~ ~ ~ ~ ~ ~ ~ 6 5

B-5 - B-18 D-1 - D-2 ~ . 6 D 3 ~ ~ ~ ~ ~ ~ ~ ~ 7 D 4 ~ ~ ~ ~ 6 D-5 - D-6 ~ ~ ~ ~ ~ ~ 7 D-7 D-40 6 E-1 - E-12 ~ ~ ~ ~ 6 F-1 F-5 ~ ~ 6 G-1 - G-5 ~ ~ ~ ~ 6

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

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 procedures for implementation of this manual are presented in the SHNPP Plant Operating Manual.

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 NRC codes LADTAP II and GASPAR and concurrent meteorology 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.

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

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 pCi/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 (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 NO WASTE The SETP EQN option is set to LOW ACT 2-1

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

2. 1 Com liance 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 OperationaX 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. l Liquid effluent monitors have two setpoints, the high alarm and the alert alarm. The high alarm setpoint, S , 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, S are set at a fraction of the S 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 dhfined in ODCM Operational Requirement Table 4.11-1),

the tank gamma activity, Cz, 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 (ODChg Rev. 6 2.1.1 Batch Releases (continued)

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)

(RR) (,60)

(2. 1-1) 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.

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 divided by ECL values must not exceed 10 for an of'oncentrations individual release. Therefore:

(2. 1-2) where:

Cq = the concentration of nuclide i to be released ECLAT

= the Effluent Concentration Limit for nuclide 10CFR20, Appendix B, Table 2, Column 2.

i from If the summation is greater than 10, dilution is required. The total required dilution factor, Dq, is the minimum acceptable dilution factor required to meet the limits of ODCM Operational Requirement 3.11 '.1, based on .pre-release and composite analysis.

req, g

+ D isq, ag (2. 1-3) where:

D~ ~ = Required dilution factor for gamma-emitters ECL (2.1-4) 0-2-5

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

D,~,~ = Required dilution factor for non-gamma-emitters (2. 1-5) 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.

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 no'rmally set to 1E-03, which is the H-3 ECL.

R = The maximum ECL ratio for the release point (normally set to 10) ~

'he 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 pCi/ml. Zf no gamma activity is detectable then an activity of 9E-07 pCi/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 pCi/ml.

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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, W is the minimum of R and R where aval 1 a 1 1oc RcMaax (2. 1-6) req R = Liquid effluent tank maximum waste flow rate, specified in Table 2.1-1. This value is the as same as Fwast ~

and F.van 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 f3:ow 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,.

fallcc 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 F ll is based on assumed operational considerations foz simultaneous releases but normally will be 0.8 for a batch release and 0.2 foz a continuous release.

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

Ef Dq s 1, the minimum dilution flow rate is set to 0.0. Zf Dq

> 1, the minimum dilution flow rate is determined as follows:

Fwaste ~ D req min dflow (2. 1-7) alloc where F , = waste flow'anticipated for this release 2-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.F 1 Batch Releases (continued)

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 pCi/ml.

If analysis of the batch sample indicates all gamma-emitting nuclides are < LLD, (as defined in ODCM Opexational 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) Maxi@urn setpoint value, based on Nuclide Specific Response S~(Cs-equxv) = (S,> R ) + B (2. 1-8) where 4

Saa> Setpoint adjustment factor.

allo@ avail F~ate req, ny (2. 1-9)

S,~> should always be greatex'han 1 to ensure that adequate dilution flow is available for the release.

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

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2 '.1 Batch Releases (continued)

R = P slope< C<

where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slope~ = 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.

Sensitivit (nuclide i)

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

An Alert Alarm setpoint is calculated to provide an operator with adequate warning that the high alarm setpoint is being Sailors approached. S,~~ is'alculated from the nuclide specific response setpoint.

[(S -B)'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 (ODCMY Rev. 6 2.1.1 Batch Releases (continued)

(3) Check for Excessive Monitor Background In order to differentiate between the S,~~ 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 S. therefore, background is acceptable if:

MDC 0.1((S - B)'] (2.1-11) where:

MDC

+8k'2.1-12) where:

Signal Processor Time constant, minutes.

(Table 2.1-3)

Background Count Rate, in cpm B/ EQ Monitor efficiency for the Cs-137 gamma energy, cpm/pCi/ml determined by primary calibration.

If the not, postpone the release and decontaminate or replace sample chamber to reduce the background, then recalculate S and S, 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.

l 2-10

Shearon Harris Nuclear power plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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, S (pCi/ml) 0.1 (ECL,~~ Sens,~~ ) + Bkg S~x (2. 1-13) where:

ECLotc Weighted EC for the SWST nuclides listed in Table 11.2.1-5 of the FSAR.

Sens,<<

Saltire

= Z> (Sens.i x 4 abundance) for the SWST nuclide au.x, cpm/pci/ml."'onitor Alert Alarm Setpoint, S, (Cs-equiv)

[(S B)') + 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.

lf 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 aze performed. The results of the sample analysis will be evaluated foz 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 ECL,ff.

Therefore, background is acceptable if:

MDC 0.01 (ECL ii 'ENS ii) (2. 1-15) 2-11

Shearon Harris Nuclear Power Plant November 1995 Offsite Dose Calculation Manual (ODCM) Rev. 7 2.1.3 Other Li uid Releases 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 b< <li v

~

< I-< ~ <l I <> l.h< floor <I< tin:<y::i'cm for pro<< ~:::;in<> <<nd <.vcntua)

~

release (see Figures 2.1-1 and 2.1-2) .

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 nc other radioactivity is normally expected in this path, the setpoints for the turbine building drain monitor are determined using the methodology in Sectior< 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) June 1994 Of fsite Dose Calculation Manual (ODCM) Rev. 4 2.2 Com liance with 10 CFR 50 A endix 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 fo each 31 days (monthly), each calendar quarter, and the year.

The EMS software calculates and stores the dose for the critical i< ~

pl or (::i l I honncl.>> y), for onch nuclide, nnd for, encl> organ. The dose c c i" the Lol.al over. all pathway" which apply to that receptor. A receptor is defined by receptor ID, age group (infant, child, teen, cr 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:

A, Zht C>,F, (2.2-1) where:

the cumulative dose or dose commitment to the total body or an organ "x" by nuclide "i" for receptor "r" from the liquid effluents for the'total time period of the release, in m em.

Aavc site-related ingestion dose or dose commitment factor fo" receptor "r" to the total body or organ "x" for nuclide in mrem/hr per pCi/ml.

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

C,, the average concentration of nuclide "i" in undiluted li"u'd effluent during time period at. from any liquid release, pCi/ml .

F, 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:

was'te

(.2. 2-2)

+ F avail waste and R~ = mixing ratio fraction of the release that reaches the receptor. At the SHNPP, this value is set to l.

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

In the case of a continuous s'econdazy 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 F , = discharge from the cooling tower basin while F,zl = the flow from the makeup water cross-tie. For a release through

~

.the Turbine Building Floor Drain Line. to 'the waste neutralization system, C, = the Turbine Building floor drain sample activity, F , = discharge from the Turbine Building floor drain line, and Favil the average flow during the period of the total Cooling Tower discharge.

The total Cooling Towez 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 Ai, (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:

1.14E+05( w

+ 21BFi) DFi,.' "' (2. 2-3) where:

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

Corresponding to fi:sh consumption from the Harris'ake (dilution = 1) and drinking water from Lillington (dilution = 13.95).

Values for the adult total body and organs in mrem/hr per

)iCilml 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 = Units Conversion Factor 10~ pCi 1000 ml 1 yr (2. 2-4) 1 pCi 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/1 DFz, = Dose conversion factor for nuclide "i" for adults for a

.particular organ x (from Table E-11 of Regulatory Guide 1.109, Rev. 1), mrem/pCi Radiological decay constant of nuclide "i, " hr ';

0.693 (6<(i (tR) g 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).

Tag+ 2.2-1 presents the +, values for an adult receptor. Values of are presented in Table 2.1-4 for each nuclide i.

2.2.2 Com arison A ainst 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) June 1994 Offsite Dose Calculation Manual (ODCMJ Rev. 4 2.2.2 Com arison A ainst Limits (continued)

For the calendar quarter:

D, s 1.5 mrem total body (2. 2-5)

D, s 5 mrem any organ (2. 2-6)

For the calendar year:

D,s 3 mrem total body (2. 2-7)

D~c 10 mrem any organ (2. 2-8) where:

D, = 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 ZZ.A. Zf 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 Z, 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 on a "per-release" basis. The NRC approved program LADTAP ZI will be used to demonstrate compliance on an annual basis. While there aze substantial differences between the ODCM methodology and the methodology in LADTAP, conservative factors have been chosen foz'the ODCM methodology which will ensure compliance with the limits of 10 CFR 50 Appendix Z.

The SHNPP ODCM uses a "modified" NUREG 0133 equation with conservative assumptions. Xt calculates the dose to a single maximum (ALARA) individual. Zt does not calculate doses in a steady-state environment, nor does it calculate reconcentration factors. 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).

The SHNPP LADTAP II program uses the guidance of Reg Guide 1.109 and Reg Guide 1.113 to calculate the dose to a maximum individual in all age groups, downstream receptors, and integrated populations. Zt will calculate doses based on a steady-state environment using the completely-mixed model and reconcentration factors, as per Reg Guide 1. 113, and will use average, rathez than minimum values for the Cape Fear River flow.

2-16

Shearon Harris Nuclear Powez Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6

2. 2. 2 Com ari son A ainst Limits (continued)

LADTAP Parameters are maintained in the Laboratory and Facility Services Section instruction RC-ER-36, Operating instruction for XOQDOQ, GASPAR, and LADTAP Computer Programs. Parameters subject to change on a periodic basis (flows, source termsy etc.) are not listed, but will be defined and described in the Radioactive Effluent Release Report for the

~ - -

period of interest.

2.2.3 Post-release Com liance With 10 CFR 50 - Based ODCM 0 erational Re uirement After the release is made, actual concentrations are used to check 10CFR50 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 actual start and end dates and times of the release. This is used with the actual volume input to calculate the release rate.

2.2.4 Pro'ection 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 Djx where:

(Dx ')

fol'wing expression:

+ Dac (2. 3-1)

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

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.

D = Additional ~ticipated Dose for liquid zeleases 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 pzojections. 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.2.4 Pro'ection 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~, s 0.06 mrem for total body (2.3-2) and Dp c 0 . 2 mrem for any organ (2. 3-3)

Xf 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 ISBLE.~

LIQUID EFFLUENT RELEASE TANKS AND PUMPS o'o. of Tanks PUMP DESIGN CAPACITY (gpm)

Discharge Recirculation Eductor Factor

"'ank Tank Capacity

( al)

Radiation Effluent Monitor ID SWST 100 100 0.2 25.000 REM-3542 WECT 35 35 1.0 10,000 REM-3541 100 100 0.25 25,000 REM-3542 TLSHS 35 100 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.

Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TLSHS: Treated Laundry and Hot Shower Tank Waste Monitor Tank 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 LKBLFU 12 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (F,,,)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate

( pm) 4QQQ R 5% 3,800 7,000 ~ 5% 6,650 11,000 2 5% 10,450 15 000 ~ 5% 14,250 Signal Processor Time Constants (T) for GA Technologies RD-53 Liquid Effluent Monitors Detector Back round (cpm) (min) 104 10 10'0~

- 103 103/cpm bk 10 - 10 10~/cpm bk 1O4 - 10'/cpm bk 1O'O' 1O' 0.01 0.01 2-20

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE Page 1 of 3 Nuclide Pa rame te r s Hal f-Life Xt Sensitivity Nuclide (hours) (hr-1) e-Xt c m/ Ci/ml ~Slo e H-3 6. 46E+06 1.07E-07 1.00E+00 O.OOE+00 O.OOE+00 C-14 3.01E+09 2.30E-10 1.00E+00 O.OOE+00 O.OOE+00 F-18 1.10E+02 6.32E-03 9.27E-01 O.OOE+00 O.OOE+00 Na-24 9.00E+02 7.70E-04 9.91E-01 9.36E+07 9.00E-01 P-32 2.06E+04 3.36E-05 1.00E+00 O.OOE+00 O.OOE+00 Cr-51 3.99E+04 1.74E-05 1.00E+00 1.61E+07 1.55E-01 Mn-54 4.50E+05 1.54E-06 1.00E+00 1.03E+08 9.90E-01 Mn-56 1.55E+02 4.47E-03 9.48E-01 1.01E+08 9.71E-01 Fe-55 1.42E+06 '.88E-07 1.00E+00 O.OOE+00 O.OOE+00 Fe-59 6.43E+04 1 '8E-05 1.00E+00 1.26E+08 1.21E+00 Co-57 3.90E+05 1.78E-06 1.00E+00 O.OOE+00 O.OOE+00 Co-58 1.02E+05 6.80E-OG 1.00E+00 1.46E+08 1.40E+00 Co-60 2.77E+06 2.50E-07 1.00E+00 1.89E+08 1.82E+00 Ni-63 5.27E+07 1.32E-08'.59E-03 1.00E+00 O.OOE+00 O.OOE+00 Ni-65 1.51E+02 9.46E-01 2.24E+07 2.15E-01 Cu-64 7.62E+02 9 '0E-04 9.89E-01 5.16E+07 4.96E-01 Zn-65 3.52E+05 1.97E-OG 1.00E+00 5.24E+07 5.04E-01 Zn-69 5.56E+01 1.25E-02 8.61E-01 2.22E+03 2.13E-05 Zn-69m 8.26E+02 8.39E-04 9.90E-01 O.OOE+00 O.OOE+00 Br-82 2.12E+03 3.27E-04 9.96E-01 O.OOE+00 O.OOE+00 Br-83 1.43E+02 4.85E-03 9.43E-01 1.95E+06 1.88E-02 Br-84 3.18E+01 2.18E-02 7.70E-01 6 '0E+07 6.25E-01 Br-85 2.87E+00 2.42E-01 5.51E-02 6.76E+06 6.50E-02 Rb-86 2.69E+04 2.58E-05 1.00E+00 8.39E+06 8.07E-02 Rb-88 1.78E+01 3 '9E-02 6.27E-01 1.45E+07 1.39E-01 Rb-89 1.54E+01 4.50E-02 5.83E-01 1.22E+08 1.17E+00 Sr-89 7.28E+04 9.52E-06 1.00E+00 1.46E+04 1.40E-04 Sr-90 1.50E+07 4.62E-08 1.00E+00 O.OOE+00 O.OOE+00 Sr-91 5.70E+02 1.22E-03 9.86E-Ol 8.16E+07 7.85E-01 Sr-92 1.63E+02 4.25E-03 9.50E-01 1.01E+08 9.71E-01 Y-90 3.85E+03 1.80E-04 9.98E-01 O.OOE+00 O.OOE+00 Y-91 8.43E+04 8.22E-06 1.00E+00 2.83E+05 2.72E-03 Y-91m 4.97E+Ol 1.39E-'2 8.46E-01 1.28E+08 1.23E+00 Y-92 2.12E+02 3.27E-03 9.62E-01 2.76E+07 2.65E-01 Y-93 6.06E+02 1.14E-03 9.86E-01 1.37E+07 1.32E-01 Zr-95 9.22E+04 7.52E-OG 1 ~ OOE+00 1.07E+08 1.03E+00 Zr-97 1.01E+03 6.86E-04 9.92E-01 2.68E+07 2.58E-01 Nb-95 5.05E+04 1.37E-05 1.00E+00 1.06E+08 1.02E+00 Nb-97 7.21E+01 9.61E-03 8.91E-01 0.00E+00 O.OOE+00 Mo-99 3.96E+03 1.75E-04 9.98E-01 3.47E+07 3.34E-01 Tc-99m 3.61E+02 1.92E-03 9.77E-01 1.11E+08 1.07E+00 2-21

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 2 of 3 Nuclide Parameters (continued)

Half-Life )t Sensitivity Nuclide (hours) (hr-1) e-Xt ~cm/ Ci/ml ~Slo e Tc-101 1.42E+01 4.88E-02 5.57E-01 1.66E+08 1.60E+00 Ru-103 5.67E+04 1.22E-05 1.00E+00 1 '8E+08 1.33E+00 RU-105 2.66E+02 2.61E-03 9.69E-01 1.71E+08 1.64E+00 Ru-106 5.30E+05 1.31E-06 1.00E+00 4.52E+07 4.35E-01 Ag-110m 3.60E+05 1.93E-06 1.00E+00 3.22E+08 3.10E+00 Sn-113 2.76E+03 2.51E-04 9.97E-01 3.08E+06 2.96E-02 Sb-124 8.67E+04 7.99E-06 1.00E+00 1.59E+08 1.53E+00 Sb-125 1.46E+06 4.75E-07 1.00E+00 1.21E+08 1.16E+00 Te-125m 8.35E+04 8.30E-06 1.00E+00 3.00E+05 2.88E-03 Te-127m 1.57E+05 4.41E-06 1.00E+00 1.33E+04 1.28E-04 Te-127 5.61E+02 1.24E-03 9.85E-01 1.97E+06 1.89E-02 Te-129m 4.84E+04 1.43E-05 1.00E+00 5.17E+06 4.97E-02 Te-129 6.96E+01 9.96E-03 8.87E-01 1.58E+07 1.52E-01 Te-131m 1.80E+03 3.85E-04 9.95E-01 2.17E+08 2.09E+00 Te-131 2.50E+01 2.77E-02 7.17E-'01. 1.50E+08 1.44E+00 .

Te 132 4.69E+03 1.48E-04 9.98E-01 1.39E+08 1.34E+00 I-130 7.42E+02 9.34E-04 9.89E-01 4;13E+08 3.97E+00 I-131 1.16E+04 5.98E-05 9.99E-01 1.55E+08 1.49E+00 I-132 1.38E+02 5.02E-03 9.42E-01 3.31E+08 3.18E+00 I-133 1.25E+03 5.55E-04 9.93E-01 1.39E+08 1.34E+00 I-134 5.26E+01 1.32E-02 8 '4E-01 3.08E+08 2.96E+00 I-135 3.97E+02 1.75E-03 9..79E-01 1.03E+08 9.90E-01 Cs-134 1.08E+06 6.42E-07 1.00E+00 2.60E+08 2.50E+00 Cs-136 1.90E+04 3.65E-05 1.00E+00 3.37E+08 3.24E+00 Cs-137 1.59E+07 4.36E-08 1.00E+00 1.04E+08 1.00E+00 Cs-138 3. 22E+01 2.15E-02 7.72E-01 1.15E+08 1.11E+00 Ba-139 8.31E+01 8.34E-03 9.05E-01 2.34E+07 2.25E-01 Ba-140 1.84E+04 3.77E-05 1.00E+00 6.01E+07 5.78E-01 Ba-141 1.83E+01 3 '9E-02 6.35E-01 2.53E+08 2.43E+00 Ba-142 1.07E+01 6.48E-02 4.60E-01 1.47E+08 1.41E+00 La-140 2.41E+03 2.88E-04 9.97E-01 1.53E+08 1.47E+00 La-142 9.54E+01 7.27E-03 9.17E-01 9.59E+07 9.22E-01 Ce-141 4.68E+04 1.48E-05 1.00E+00 6.11E+07 5.88E-01 Ce-143 1.98E+03 3.50E-04 9.96E-01 9..60E+07 9.23E-01 Ce-144 4.09E+05 1.69E-06 1.00E+00 1.30E+07 1.25E-01 Pr-143 1 '5E+04 3.55E-05 1.00E+00 1.08E+02 1.04E-06 Pr-144 1.73E+01 4.01E-02 6.18E-01 1.68E+06 1.62E-02 Nd-147 1.58E+04 4.39E-05 9.99E-01 2.86E+07 2.75E-01 Hf-181 1.02E+03 6.81E-04 9.92E-01 2.08E+08 2.00E+00 W-187 1.43E+03 4.85E-04 9.94E-01 1.04E+08 1.00E+00 Np-239 3.39E+03 2.04E-04 9.98E-01 1.13E+08 1.09E+00 2-22

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 3 of 3 Nuclide Parameters (continued)

Half-Life )t e-Xt Sensitivity

~s1o Nuclide (hours) (hr-1) e Ar-41 1.10E+02 6.30E-03 9.27E-01 9.28E+07 8.92E-01 Kr-83m 1.10E+02 6.30E-03 9.27E-01 O.OOE+00 O.OOE+00 Kr-85 5.64E+06 1.23E-07 1.00E+00 6.20E+05 5.96E-03 Kr-85m 2.69E+02 2.58E-03 9.70E-01 1.20E+08 1.15E+00 Kr-87 7.63E+01 9.08E-03 8.97E-01 9.19E+07 8.84E-01 Kr-88 1.70E+02 4.08E-03 9.52E-01 7 '9E+07 7.20E-Ol Kr-89 3.16E+00 2.19E-01 7.19E-02 1.39E+08 1.34E+00 Kr-90 5.39E-01 1.29E+00 1.99E-07 1.59E+08 1.53E+00 Xe-131m 1.70E+04 4.08E-05 1.00E+00 2 '2E+06 2.52E-02 Xe-133 7.55E+03 9.18E-05 9.99E-01 9.90E+04 9.52E-04 Xe-133m 3.15E+03 2.20E-04 9.97E-01 1.59E+07 1.53E-01 Xe-135 5.47E+02 1.27E-03 9.85E-01 1.47E+08 1.41E+00 Xe-135m 1.54E+01 4.50E-02 5.83E-01 1.14E+08 1.10E+00 Xe-137 3.83E+00 1.81E-01 1.14E-01 4.85E+07 4.66E-01 Xe-138 1.41E+01 4.92E-02 5.54E-Ol 1.20E+08 1.15E+00 G-ALPHA 1.00E+05 6.93E-06 1.00E+00 O.OOE+00 0.00E+00 G-BETA 1.00E+09 6.93E-10 1.00E+00 O.OOE+00 O.OOE+00 OTHER 1.00E+09 6.93E-10 1.00E+00 O.OOE+00 O.OOE+00 Notes to Table 2.1-4 SENSITIVITY 80% of weighted response to 100 1400 keV .gammas for GA RD-53 offline sodium iodide (NaI) detector (reference GA Manual E-115-904, June 1980).

Abundances for each gamma from "Radioactive Decay Tables" by David C. Kocher (Report DOE/TIC-11026, Washington, D.C., 1981)

The Liquid Effluent Monitor Gamma Sensitivities for SLOPE nuclide i, relative to Cs-137. To make nuclide i relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

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 Ag, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT Afp114E+05(+ V 2 1BFf)DFfe (mrem/hr per pCi/ml)

Nuclide Bone Liver ~T. Bod ~Th roid ~Kidne ~Lun Gr-hhr H-3 O.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 '7E+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 O.OOE+00 O.OOE+00 O.OOE+00 5.08E+06 CR-51 O.OOE+00 O.OOE+00 1.28E+00 7.63E-01 2.81E-01 1.69E+00 3.21E+02 MN-54 O.OOE+00 4.41E+03 8.41E+02 O.OOE+00 1.31E+03 O.OOE+00 1.35E+04 MN-56 O.OOE+00 4.44E+00 7.87E-01 O.OOE+00 5.63E+00 O.OOE+00 1.42E+02 FE-55 6.76E+02 4.67E+02 1.09E+02 O.OOE+00 O.OOE+00 2.60E+02 2.68E+02 FE-59 1.06E+03 2.49E+03 9.54E+02 O.OOE+00 O.OOE+00 6.95E+02 8.29E+03 CO-57 O.OOE+00 2.20E+01 3.66E+01 O.OOE+00 O.OOE+00 0.00E+00 5.58E+02 CO-58 O.OOE+00 9.33E+01 2.09E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.89E+03 CO-60 O.OOE+00 2.69E+02 5.94E+02 O.OOE+00 O.OOE+00 O.OOE+00 5.06E+03 NI-63 3.20E+04 2.21E+03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.62E+02 NI-65 4 '6E+00 6.19E-01 2.82E-Ol O.OOE+00 O.OOE+00 O.OOE+00 1.57E+01 CU-64 O.OOE+00 5.45E+00 2.56E+00 0 ~ OOE+00 1.37E+01 O.OOE+00 4.64E+02 ZN-65 2.32E+04 7.39E+04 3.34E+04 O.OOE+00 4.94E+04 0.00E+00 4.65E+04 ZN-69 6.25E-03 1.20E-02 8.32E-04 O.OOE+00 7.77E-03 O.OOE+00 1.80E-03 ZN-69M 4.46E+02 1.07E+03 9.79E+Ol O.OOE+00 6.48E+02 O.OOE+00 6.54E+04 BR-82 O.OOE+00 O.OOE+00 1.81E+03 O.OOE+00 O.OOE+00 O.OOE+00 2.07E+03 BR-83 O.OOE+00 O.OOE+00 1.24E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.79E+00 BR-84 O.OOE+00 O.OOE+00 8.07E-06 O.OOE+00 O.OOE+00 O.OOE+00 6.33E-ll BR-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RB-86 O.OOE+00 9.95E+04 4.63E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.96E+04 RB-88 O.OOE+00 1.94E-10 1.03E-10 O.OOE+00 O.OOE+00 O.OOE+00 2.67E-21'.43E-26 RB-89 O.OOE+00 1 ~ 62E-12 1.14E-12 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 2.38E+04 O.OOE+00 6.84E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.82E+03 SR-90 5.91E+05 O.OOE+00 1.45E+05 O.OOE+00 O.OOE+00 O.OOE+'00 1.71E+04 SR-91 1.84E+02 O.OOE+00 7.43E+00 O.OOE+00 O.OOE+00 O.OOE+00 8.77E+02 SR-92 7.84E+00 O.OOE+00 3.39E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.55E+02 2-24

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

A'r VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per pci/ml)

Nuclide Bone Liver ~T. Bod ~Th roid ~Kidne ~Lan Gr-LLr Y-90 5.57E-01 O.OOE+00 1.49E-02 O.OOE+00 O.OOE+00 O.OOE+00 5.91E+03 Y-91M 2.61E-07 O.OOE+00 1.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 7.67E-07 Y-91 9.24E+00 O.OOE+00 2.47E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.09E+03 Y-92 5.29E-03 O,OOE+00 1.55E-04 O.OOE+00 O.OOE+00 O.OOE+00 9.27E+01 Y-93 7.75E-02 O.OOE+00 2.14E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.46E+03 ZR-95 4.20E-01 1.35E-01 O.OOE+00 2.11E-01 O.OOE+00 4.27E+02 9.12E-02'.31E-03 ZR-97 1.42E-02 2.87E-03 O.OOE+00 4.34E-03 O.OOE+00 8.90E+02 NB-95 4.43E+02 2.47E+02 1.33E+02 O.OOE+00 2.44E+02 O.OOE+00 1.50E+06 NB-97 3.70E-03 9.36E-04 3.42E-04 O.OOE+00 1.09E-03 O.OOE+00 3.45E+00 MO-99 O.OOE+00 1.14E+02 2.17E+01 O.OOE+00 2.58E+02 O.OOE+00 2.64E+02 TC-99M 2.60E-03 7.35E-03 9.36E-02 O.OOE+00 1.12E-01 3.60E-03 4.35E+00 TC-101 5 ~ 81E-18 8.37E-18 8 '1E-17 O.OOE+00 1.51E-16 4.28E-18 2.52E-29 RU-103 5.49E+00 O.OOE+00 2.37E+00 O.OOE+00 2.10E+01 O.OOE+00 ~ 6.41E+02 RU-105 7.07E-02 O.OOE+00 2.79E-02 O.OOE+00 9.13E-01 O.OOE+00 4 . 32E+'0'ls RU-106 8.23E+01 O.OOE+00 1.04E+01 O.OOE+00 1.59E+02 O.OOE+00 5.33E+03 AG-110M 9.55E-01 8.83E-01 5.25E-01 O.OOE+00 1.74E+00 O.OOE+00 3.60E+02 SB-124 2.33E+01 4.40E-01 9.24E+00 5.65E-02 O.OOE+00 1.82E+01 6.62E+02 SB-125 1.50E+01 1.67E-01 "

3.57E+00 1.52E-02 'O.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 O.OOE+00 1.03E+04 TE-127M 6.51E+03 2.33E+03 7.94E+02 1.66E+03 2.65E+04 O.OOE+00 2.18E+04 TE-127 4.36E+01 1.57E+01 9.44E+00 3.23E+01 1.78E+02 O.OOE+00 3.44E+03 TE-129M 1.10E+04 4.10E+03 1.74E+03 3.77E+03 4.59E+04 O.OOE+00 5.53E+04 TE-129 2.33E-02 8.76E-03 5.68E-03 1.79E-02 9.80E-02 O.OOE+00 1.76E-02 TE-131M 1.27E+03 6.19E+02 5 '6E+02 9.80E+02 6.27E+03 O.OOE+00 6.14E+04 TE-131 4.07E-08 1.70E-08 1.28E-08 3.35E-08 1.78E-07 O.OOE+00 5.76E-09 TE-132 2.19E+03 1.41E+03 1.33E+03 1.56E+03 1.36E+04 O.OOE+00 6.69E+04 I-130 1.62E+01 4.77E+01 1.88E+Ol 4.0SE+03 7.45E+Ol 0 'OE+00 4.11E+01 I-131 1.67E+02 2.39E+02 1.37E+02 7.84E+04 4.10E+02 O.OOE+00 6.31E+01 I-132 2.29E-01 6.12E-01 2.14E-01 2.14E+01 9.75E-01 O.OOE+00 1.15E-01 I-133 4.00E+01 6.95E+01 2.12E+01 1.02E+04 1.21E+02 O.OOE+00 6.25E+01 I-134 3.37E-04 9.15E-04 3.27E-04 1.59E-02 1.46E-03 O.OOE+00 7.98E-07 I-135 5.29E+00 1.38E+01 5.11E+00 9.13E+02 2.22E+01 O.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)

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

Nuclide Bone Liver ~T. Bod ~Th roid ~Kidne ~Lnn GI-LLZ CS-134 2.99E+05 7.10E+05 5.81E+05 O.OOE+00 2.30E+05 7.63E+04 1. 24E+04 CS-136 3.05E+04 1.20E+05 8.65E+04 O.OOE+00 6.69E+04 9.17E+03 1.37E+04 CS-137 3.83E+05 5.23E+05 3.43E+05 O.OOE+00 1.78E+05 5.91E+04 1.01E+04 CS-138 4.92E-05 9.72E-05 4.82E-05 O.OOE+00 7.14E-05 7.06E-06 4.15E-10 BA-139 3.72E-03 2.65E-06 1.09E-04 O.OOE+00 2.48E-06 1.50E-06 6.60E-03 BA-140 3.08E+02 3.86E-01 2.02E+01 O.OOE+00 1.31E-01 2.21E-01 6.33E+02 BA-141 1.05E-12 7.94E-16 3.55E-14 O.OOE+00 7.38E-16 4.51E-16 4.95E-22 BA-142 1.84E-21 1 ~ 89E-24 1.16E-22 O.OOE+00 1.60E-24 1.07E-24 O.OOE+00 LA-140 1.34E-01 6.75E-02 1.78E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.96E+03 LA-142 4.51E-05 2.05E-05 5.11E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.50E-01 CE-141 7.76E-02 5.24E-02 5.95E-03 O.OOE+00 2.44E-02 O.OOE+00 2.01E+02 CE-143 1.07E-02 7.94E+00 8.79E-04 O.OOE+00 3.50E-03 O.OOE+00 2.97E+02 CE-144 4.08E+00 1.71E+00 2.19E-01 O.OOE+00 1.01E+00 O.OOE+00 1.38E+03 PR-143 5.91E-01 2.37E-01 2.93E-02 O.OOE+00 1.37E-01 O.OOE+00 2.59E+03 PR-144 5.88E-16 2.44E-16 2.99E-17 O.OOE+00 1.38E-16 O.OOE+00 8.46E-23 ND"147 4.02E-01 4.64E-01 2.78E-02 O.OOE+00 2.71E-01 O.OOE+00 2.23E+03 W-187 2.10E+02 1.75E+02 6.12E+01 O.OOE+00 O.OOE+00 ,O.OOE+00 5.74E+04 NP-239 3.08E-02 3.03E-03 1.67E-03 O.OOE+00 9.44E-03 O.OOE+00 6.21E+02 2-26

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X N C V

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 2.1-2 Liquid Effluent Flow Stream Diagram

~Le cnd Treated Laundry & Treated Laundry & Tank or Basin C

Hot Shower Tank Hot Shower Tan'k 0 agu Radiation Ettlucnt Monitor 0

I Pump I

n g

REM-1WL4540.

Secondary Waste T Sample Tank 0 w

e AEM-ztws-3$ sz 8

"I 0 0 Spcdsdc Flsngc w d

Waste Monitor Waste Monitor Waste Neutralization 0 Tank Tank Basin I w

n Waste Evaporator Waste Evaporator Settling Condensate Tank Condensate Tank Basin I Liquids containing radioactive materials other than tritium are not permitted by procedure to be sent to the Waste Lake REM<1 WL4541 Neutralization Basin.

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 Norlnal Senrka Water Reaclor Auxiliary Building Hoat Loado Hoat Loado REM aaoo A

Waste Processing Hoat Loado Building REM a500 D

Stain Condenser Turbine Building Normal Senrke Water Circulating Water Pumps 0 Lesend 0 REM u Redlttten Kfnuenl Mentter NSW u None el aetstce Water Cooling Tower Basin OO OO NSW Pumps CTMU Puts ps CTMV Strainer Dypeos Uno Bacttwash Nants Lace NoTe por dtlacsd now drawings ot the setstee water systtec rsltr lo the PSAR 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 Outside Tank Area Drains Turbine Building Floor Drains ENuent Line Effluent Une Outside Tank Turbine Building Area Drains Floor Drains Sumps REM 3628 REM 3530 Yard OII Separator Storm Drain System Waste Neutralization Basin Settling Basin Harris Lake Cooling Tower Blowdown 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 Llquld Radwaste Treatment Sysyem 2-30

P Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 SA. These are shown in Figures 3.1, 3.2; and 3.3 along with their tributaries. All gaseous effluent releases ht the plant are considered ground releases.

3.1 Monitor Alarm Set oint Determination (ODCM Operational Requirement 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 mzem/year to the skin as specified in ODCM Operational Requirement 3.11.2.1.

The radioactivity effluent monitors for each stack and for specific effluent streams aze 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, either using 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 Set pints Usin 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.

Determine the noble gas. radionuclide activity (Q<) in pCi, .and the activity release rate (g) in pCi/sec for each nuclide i. g is the release rate of nuclide i in gaseous effluent from discharge point v, in pCi/sec.

Q Cz ~

F, ~ duration ~ 28316 85

~ (3. 1-la) and C~ ~

F ~ 28316.85 / 60 (3.1-1b) where:

index over all vent stacks c, concentration of nuclide, in pCi/cc the GALE code activities from Table 3.1-1.

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~

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 Set pints Usin a Conservative mix (GALE code) (continued)

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

~(X Q) [ Z, X, Q, ) (3 1-2a)

~

and

~XQ) [ Zq (Lq + 1.1){q) {}q ] (3.1-2b) where:

index over all nuclides the total body dose factor due to gamma emissions for Kg noble gas zadionuclide 3.1-2.

i (in mrem/yr per pCi/m3), from Table

'g The skin dose factor due to beta emissions for noble gas zadionuclide i (mrem/yr per pCi/m')

The air dose factor due to gamma emissions for noble Mz gas zadionuclide i (mrad/yr pez pCi/m'). A unit conversion constant of 1. 1 mrad/mrem converts aiz dose to skin dose Ll+1. 1M'kin dose factor (mrem/yr per pCi/m'), from Table 3.1-2 Wxg The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m')

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

Sheazon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor Set pints Usin a Conservative mix (GALE code) (continued) 3 ~ Determine the ratio of dose rate limit to dose rate.

nratio = lesser of the ratios Whole Body ratio = 500 (3. 1-3a)

Q w and Skin ratio = 3000 (3.1-3b) where:

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

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

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

S = (f, ~

f,u<< ~ nratio ~

/CD ) + Bkg (3.1-4a) and R~ ~ S~ 0 P3, 28316 852~ / 60 (3.1-4b) where f, = safety factor for the discharge point 0.5 f~~= 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 aze based on the percentage of an individual stack flow to the total stack flow and are in Table 3.1-3.

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 Set pints Usin 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'ased on sampling and analysis, the setpoint will be recalculated.

sample analysis setpoint is higher than the default setpoint, the If 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.

Determine S the gas channel alert alarm setpoint in pCi/cc, and RR~, the gas channel alert alarm release rate setpoint in pci/sec.

[(S~x - Bkg) Ar) + Bkg (3.1-5a) and RRaz erg [ (RR Bkg~~) Aq) + Bkg~~ (3.1-5b) where:

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

Bkg Bkg ~ F~ 28316 ~ 85 / 60 3-5

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le Results Zn 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 puzge and pressure relief. Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT). Zn 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.

Determine the noble gas. radionuclide activity (Qq) in pCi, .and the activity release rate (Q) in pCi/sec for each nuclide i. g is the average release rate of nuclide i in gaseous effluent from discharge point v, in pCi/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 .

PCq ~ Fduration ~ 28316. 85 (3.2-1a) and gv Cg Fy 28316 85 / 60 (3 2-1b)

~

where:

index over all vent stacks concentration of nuclide, in pci/cc the measured concentration from a stack effluent sample or pre-release sample. Zf there is no activity in the sample, then the GALE code activities from Table 3.1-1 will be used.

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.

3-6

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le Results (continued) for batch releases, the release flow rate, in acfm 1,500 acfm foz containment normal purge 37, 000 acfm for containment pzeentzy purge 2.26 8+06 ( hP 14.7 t

) 273' T

)

for a containment pressure release 600 ( ') ( 273'4.7 T~

)

foz a Waste Gas Decay Tank release where:

~ ~

2.26E+06 and'00 are the volumes in containment and decay tank, respectively, and ft'f the T g Tgg 6P I and hP, are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 = lb/in', i.e., 1 atmosphere pressure Length of release, min 273 K 0 C Tet Tc 273'K +

duration of release, in minutes C'uration 28316.85 = conversion factor for cc/ft, 3-7

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Of fsite Dose Calculation Manual (ODCM) Rev. 5 3.1.2 Monitor Set pints Usin Sam le 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.

Q~-e ~(X (() E [ Eq Ki ((q [ (3 '-2a) and

((,., = ~+Q Z[ Z~ ((~ + 1.>Mi) ((i [ (3.2-2b) where:

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

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

The air dose factor due to gamma emissions for noble Mg gas radionuclide i (mrad/yz pez pCi/m'). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Lg+1. 1M'kin dose factor (mrem/yr per pCi/m') from Table 3.1-2

~X Q = The highest calculated annual average relative concentration for any sector at oz beyond the exclusion boundary (sec/m')

6.1E-06 sec/m'rom 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 Set pints Usin Sam le Results (continued) 3 ~ Determine the ratio of dose rate limit to dose rate.

nratio = lesser of the ratios Whole Body ratio = 500 (3.2-3a) and Skin ratio = 3000 (3.2-3b) where:

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

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

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

S = (f, ~

f~, ~ nratio ~

PC< ) + Bkg (3.2-4a) and RR = S~ 'v '8316 852 / 60 (3. 2-4b) where safety factor foz 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 '-.3.

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 Set pints Usin Sam le Results (continued)

5. Determine S,<<, the gas channel alert alarm setpoint in pCi/cc, and RR~~ the gas channel alert alarm release rate setpoint in pci/sec.

( (S~x Bkg) Ar] + Bkg (3.2-5a) and RR~g<~g [ (R~ Bkg<~) Ag] + Bkg<< (3.2-5b) where:

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

Bkg 3-10

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.3 Effluent Monitorin Duzin Ho in O erations If the reactor has condenser vacuum been shut down for greater than 30 days, the discharge during initial hogging operations at pump 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 ').

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

Q tn Table 3.1-1 tb W tb ra GASEOUS SOURCE TERMS ra Q rr 0 la Condenser t) m Plant Vent Vacuum Pump WPB WPB Containment 0 ta Ventilation Ventilation Ventilation Ventilate on Purge or : WGDT rs Flow Flow Flow Flow Pressure Relief Release (d) O ta via via via via via via Stack 1 Stack 3A Stack 5 Stack 5R Stack 1 Stack 5 no0 i V rp rr CI

<c)

% Rel.

<e) .<d) r0 fu rs

~uid ~lc ~rci ~i ~i Ci

~lcc

% Rel.

h2lml 0

Z8 Kr-85m 6.89E-10 7.02 4.69E-9 7.69 2.61E-9 7.02 9.80E-B 2.93 I Kr-85 1.87E-7 97.16 6.17E-B 1.85 2.91E.3 97.16 c Kr.87 6.89E-10 7.02 4.69E.9 7.69 2.61E-9 7.02 3.45E-B 1.03 f r Kr.88 1.21E-09 12.28 7.04E.9 11.54 4.56E-9 12.28 1.23E-7 3.69 Q rr U

Xe.131m 5.17E-10 5.26 2.35E-9 3.85 5.49 E-9 O~tn 1.96E-9 5.26 3.27E-7 9.77 8.51E-5 g Xe-133m 7.26E-B 2.17 rtf X@-133 2.76E-09 28.07 1.64E-B 26.92 '1.04E-B 28.07 1.82E-6 54.29 3.36E-7 4.67E-3 Xe-135m 5.17E-10 5.26 4.69E-B 7.69 1.96E-9 5.26 7.26E-9 0.22 Xe-135 2.93E.9 29.82 1.88E-B 30.77 1.11E-B 29.82 7.99E-7 23.89 Xe-138 5.17E-10 5.26 2.35E-9 3.85 1.96E-9 5.26 5.45E-9 0.16

<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) Source term for this effluent stream not presented with FSAR. RAB mix assumed.

<c) Cl <uCi/cc) = Ci r I i f 8 0

<Flow Rate ft3/min)

<d) Based on an assumed flow rate of 15 CFM for WGDT. 0

<e) Based on an assumed f)ow rate of 37,000 CFM.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3 '-2 DOSE FACTORS AND CONSTANTS Whole Body Dose Skin Dose Factor Factor (K~) (Lg + 1.1 Mg)

Radionuclide (mrem/yr/pci/m') (mrem/yr/pCi/m')

Kr-83m 7.56E-02 2.12E+01 Kr-85m 1.17E+03 2.81E+03 Kr-85 1.61E+01 1.36E003 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-l, multiplied by (1.0+E6 pCi/pCi).

3-13

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.1-3 GASEOUS MONITOR PARAMETERS PVS-1 TBVS-3A WPBVS-5 WPBVS-SA Maximum effluent design 390, 000 28, 620 232,500 103, 050 flow rate, (acfm)

Flow Allocation Factor 0. 517 0. 038 0. 308 0. 137 (f...)

3-14

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.2 Postrelease Com liance with 10CFR20-Based ODCM 0 erational Re uirement 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors setpoints aze 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 high alarm setpoints are exceeded, a determination may be made as to if the whether the actual releases have exceeded the dose rate lhnits 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(~XQ) v Qi (3. 2-1) c 500 mrem/yr (Li + 1.1 Mi)(~X Q)v Qiv c 3000 mrem/yr (3.2-2) where:

(TXQ) The highest calculated annual average relative concentration foz long-term vent stack releases for areas at or beyond the exclusion boundary sec/m'.

6.1E-06 sec/m~ from Table A-1, Appendix A, for ground-level releases in the S sector at the exclusion boundary.

Kz The total body dose factor "due to gamma emissions for noble gas radionuclide "i, mzem/year per pCi/m'.

Table 3.2-3.

Lz The skin dose factor due to beta emissions for noble gas radionuclide "i," mrem/year per pCi/m'.

Table 3.2-3 '

Mz The air dose factor due to gamma emissions for noble gas radionuclide "i, " mrad/year per pCi/m'.

Table 3.2-3.

3-15

Shearon Harris Nuclear power Plant (SHNpp) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.2.1 Noble Gases (continued)

The ratio of the tissue to aiz absorption coefficients over the energy range of the photon of interest.

Converts mrad to mrem (Reference NUREG-0133) ~

Th' factors (Lz 1.1 Mq)

+ are tabulated in Table 3.1-2.

iv The release rate of radionuclide "i" in gaseous effluents from all plant vent stacks (pCi/sec).

The determination of the controlling location foz 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 (pCi/sec) = Flow (cc/sec) *..Concentration (pCi/cc)

The noble gas zadionuclide 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)v in the unrestricted area for the period 1976 1987. Long-term annual average (X~@) values at other locations shown in Table 3.2-2 are presented in Appendix A. A description of their derivation is also provided in this appendix.

To select the limiting location for ground-level releases, long-term annual average (~XQ) 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 (~XQ) v for ground-3.evel 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 Kz, Lz, and M~ which aze 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/pCi for use in Equations 3.2-1 and 3.2-2.

3-16

Shearon Harris Nuclear Power plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.2.2 Radioiodines and Particulates The bases for ODCM Operational Requirement 3/4 '1.2.1 states that the dose rate to the thyroid of a child in an unzestricted area resulting from the inhalation of radioiodines, tritium, and particulates

> 8 days is limited to 1500 mrem/yr to any organ. Based upon with'alf-lives NUREG-0133, the following is used to show compliance:

P P< ( (~X Q) Q<,] c 1500 mrem/yr (3. 2-3) 1 where:

Pi = The dose parameter foz zadionuclides other than noble gases for the inhalation pathway, mrem/yr per pCi/m'.

. 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 (pCi/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

'I for the inhalation pathway using the methodology of NUREG-0133 'he Pi values are presented in Table 3.2-4. A description of the methodology used in calculating the P~ values is presented in Appendix B. The values of Pz reflect, for each radionuclide, the maximum Pz value for any organ.

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

Table 3.2-1 Q M w0 Releases from the Shearon Harris Nuclear Power Plant (1) M Ql Normal Operation (Curies/year) N 0 0

Waste Processing Bldg Waste Processing Bldg Condenser Vacuum Pump am 0

Exhaust and/or Exhaust via VENT STACK SA and Turbine Building N Waste Gas Decay Tanks (2) or RAB/FHB and Containment Exhaust ts via VENT STACK 5 Exhaust via VENT STACK 1 via VENT STACK 3A r-NOBLE n~

She 51KX~W NORMAL QPEhhXIQ52 0 EBS/ iUR xeric rz 0 C c n Kr-85m 0 0 5.4E+01 4.B+00 2.0E+00 6.0E+01 P V Kr-85 8.0E+00 6.5B+02 8 3.4B+01 0 0 6.9E+02 rt Kr-87 0 0 1.9E+01 4.0E+00 2.0E+00 2.5E+01 r. P N

Kr-88 0 0 0 6.8E+01 7.0B+00 3.0E+00 7.8E+01 0

Xe-131m 1.9E+01 1.8E+02 3.0E+00 1.0E+00 2.0E+02 Z8 0

Xe-133m 0 4.0E+01 0 0 4.0E+01 Xe-133 0 1.0E+03 1.6E+01 7.0E+00 1.0E+03 c

Xe-135m 0 4.0B+00 3.0B+00 2.0E+00 9.0E+00 I Xe-135 Q 0 4.4E+02 1.7E+01 8.0E+00 4.7E+02 Xe-138 0 3.0E+00 3.0E+00 1.0E+00 7.0E+00 0 rt 3.4E+00 n-a g m

'z

~ Q

~ Q 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.

(2) Waste Gas Decay Tank releases assumed afler a 9(4hy decay period.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 Table 3.2-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (miles)"

(Comparison of 1993/1994 Data)

Residence Milk Animal Garden Meat Animal Exclusion Sector Boundar 1993 1994 1993 1994 1993 1994 1993 1994 N 1.32 2.2 2.2 2.2 2.2 2.8 2.2 2.2 2.2 1.33 1.9 1.9 1.7 1.9 2.2 2.2 NE 1.33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.33 1 ' 1.8 3.6 1.8 1.8 1.33 1.8 1.8 2.0 2.0 2.0 1.33 2.6 2.6 4.7 4.7 4.2 4.2 1.33 2.6 2.6 4.1 2.6 4.1 2.6 SSE 1.'33 4.2 4.2 4 '

1.36 5.3 5.3 5.3 5 ' 5.3 SSW 1.33 3.9 3.9 3.9 SW 1.33 2.9 2.9 2.9 2.9 WSW 1.33 4.5 4.5 4.5 4.5 4.6 1.33 3.0 3.0 3.1 3.1 3.1 3.1 1.33 2.3 2.3 2.3 2.3 2.6 1.26 2.4 2.4 2.7 F 7 3.7 3.7 1.26 1.6 2.0 2.0 2.0 2.0 As of August, 1994.

Distance estimates are + 0.1 miles except at the exclusion boundary.

Distances and sectors determined by Global Positioning System.

3-19

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

Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Radionuclide L M, N, (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per Ci/m3) Ci/m~) Ci/m ) Ci/m~)

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 1.11E+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 Of fsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.2-4 Pi~I VALUES (INHALATION) FOR A CHILD Pi I Value ISOTOPE mreml r er Cilm'-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 RQ-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 I-131 1.62E+07 I-132 1.93E+05 I-133 3.84E+06 I-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) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 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 on a "per-release" basis. The NRC approved program GASPAR will be used to demonstrate compliance on an annual basis. While there are differences between the ODCM methodology and the methodology in GASPAR, conservative factors have been chosen for the ODCM methodology which will ensure compliance with the limits of 10 CFR 50 Appendix I.

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.

The SHNPP GASPAR program calculates the dose to a maximum individual all age groups, down wind! receptors, and integrated populations. It in will calculate doses based on the actual average meteorology for the period of interest.

GASPAR Parameters are maintained in the Laboratory and Facility Services Section 1nstzuction RC-ER-36, Operating Instruction for XOQDOQ, GASPAR, and LADTAP Computer Programs. ,Parameters subject to change on a periodic basis (receptor locations, source terms, etc.) are not listed, but will be defined and described in the Radioactive Effluent Release Report for the period of interest.

3-22

Sheazon Harris Nuclear Power Plant (SHNpp) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases 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 Q Mi [ (WXQ)v Qi v + (WXq)v qj v ] (3. 3-1) 3.17 E-08 P Ni [ (~XQ) v Qiv + (~Xq) v qiv ) (3. 3-2) where:

D Y

The air dose from gamma radiation, mrad.

D~ The air dose from beta radiation, mrad.

The air dose factor due to'eta emissions for each identified noble gas radionuclide "i," mrad/year per pCi/m'.

Ng Table 3.2-3.

TXQv The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack releases (z 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/m'. See Section 3.0 earlier or use 6.1E-06 sec/m'rom Table A-l, Appendix A.

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

The total release of zadionuclide "i" in gaseous releases for short-term releases (s500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year) from all vent stacks, (pCi) .

3.17 E-08 The inverse of the number of seconds in a year (sec/year) aiz dose factor to gamma emissions for each

'he due identified noble gas radionuclide (mrad/yr/pCi/m~) . A unit conversion constant of 1.1 mrad/mrem convezts air dose to skin dose 3-23

Shearon Harris Nuclear Power Plant (SHNpp) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 ~XQv values can be used in lieu of short-term values (see Section 3.0 earlier) .

The determination of the limiting location for implementation of 10CFR50 is a function of parameters such as radionuclide mix, isotopic release, and meteorology. To select the limiting location, the highest annual average ~X Q 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 Mz and N<<which are utilized in the calculation of the gamma air and beta air doses in Equation 3.3-1'Co 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 1.0E+06 to convert from mrad/pCi to mrad/pCi .

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

For the calendar quarter:

Dy s 5 mrad (3. 3-3)

D() s 10 mrad (3. 3-4)

For the calendar year:

Dy s 10 mrad (3. 3-5)

D() s 20 mrad (3. 3-6)

The quarterly limits given above represent one-half of the annual design objectives of Section ZZ.B.1 of Appendix Z of 10CFR50. Zf 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 ZV.A of Appendix Z of 10CFR50.

3-24

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases (continued)

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 = 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 (mirfimum) 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; qg Cg

vb (3 3-7)

~

Where;

~ = Activity of nuclide "i" released (pCi).

Cf Concentration of radionucl ide "i" (pCi/cc) v~ = Containment 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 (pCi) for nuclide "i" for Waste Gas Decay Tank effluent accountability is calculated as follows; (Ci 'P '00 '8316.85 '98) (3.3-7a)

(14.7 '83) 3-25

Shearon Harris Nuclear Power plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.1 Noble Gases (continued)

Where; Activity of nuclide "i" released (pCi) .

Cg Concentration of nuclide "i" (pCi/cc) .

hP Change in pressure (psia) of the WGDT (psia = psig + 14.7) 600 WGDT volume, (ft~) .

28316.85 Conversion factor for converting from ft'o cc.

298 Sample temperature at time of analysis, (4k).

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 4F range..Since there is no indicator for the actual WGDT'emperature, 50'F (10 'C) is conservatively assumed as an acceptable substitute. Also assumed is a sample analysis temperature of 77' (25') .

NOTE 'ontainment Pressure calculated using the Releases (ILRT) are same methodology.

Containment Pressure Releases are released via stack 1. The volume to use is 2.26E+06 ft~.

Continuous Releases Each of the four effluent stacks at the HNP have noble gas monitors. Using the net concentration (pCi/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:

Cx'x (3.3-8)

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

CX 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 (pci) released for zadionuclide "i" equals the zadionuclide "i" fraction of the radionuclide mix times. the total activity released from Stack "x".

Q< Q>> 'z (3.3-8a)

Where; C~

Sg (3.3-8b) and; S~ The radionuclide "i" fraction of the radionuclide mix The concentration of nuclide "i" in the grab sample (pCi/cc).

/CD ~ 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 oz 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; Q~c=Q~- % (3. 3-9)

Where; Q<, = 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 Dp, = (Dt where:

')

the following expression:

+ D (3.3-10)

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

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.

D = 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 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:

Dy c 0.2 mrad to air for gamma radiation (3.3-11) and D() c 0.4 mrad to air for beta radiation (3 '-12)

Zf 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 (5HNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.2 Radioiodine and Particulates Cumulation of Doses Section TE.C of Appendix I of 10CFR50 limits the release of zadioiodines 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 P (R I [(WXq) Q + (WXq) q ] +

i iM iV iGG

+ R ) ((~DQ) Q ~ (~Dq q ~

) )+

(RT + RT + RT + RT ) [ (rrQV QT + (re)v qT v } (3 3->>)

M I V B v where:

D Dose to any organ x from tritium, radioiodines, and particulates, mrem.

(~R) v The highest long-term (> 500 hr/yr) annual average relative deposition: 8.8 E-09 m~ foz 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).

(~Dq) The relative deposition factor for short term, ground-level vent releases (s 500 hzs/yz), m '.

See Section 3.0 earlier if using "real" meteorology or use 8.8 E-09 m~ from. Table A-4, Appendix A, for the food and ground plane pathways at the controlling location.

R.

4 Dose factor for an organ for radionuclide "i" for either the cow milk oz goat milk pathway, mrem/yr pez pci/sec per m'.

3-29

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3.2 Radioiodine and Particulates (continued)

R i~

= Dose factor for an organ for radionuclide "i" for the ground plane exposure pathway, mrem/yz per pCi/sec per m '.

R

~!

= Dose factor for an organ for radionuclide "i" for the inhalation pathway, mzem/yr per pCi/m'.

R. gan for radionuclide "i" iy Dose factor for an oz for the vegetable pathway, mrem/yr per pCi/sec per m'.

Ri = Dose factor for an organ for radionuclide "i" for the meat pathway, mrem/yr per pCi/sec per m'.

RT Dose factor for an organ for tritium foz the milk pathway mrem/yr per pCi/m'.

Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per pCi/m'.

RT = Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per pCi/m'.

Dose factor foz an organ for tritium for the meat pathway, mrem/yz per pCi/m'.

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

pCi.

Release of tritium in gaseous effluents for short-tean vent stack releases (s 500 hrs/yr),

pCi.

To show compliance with 10CFR50, Equation 3.3-13 is evaluated foz 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 7X Q and 7D Q 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 Q and ~D Q values from tables in Appendix A are used. For this document, long-term annual average XTQv and DTQv values may be used in lieu of short-term values (see Section 3.0 earlier) .

3-30

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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, Radionuclide mix and isotopic release

2. Meteorology

3. Exposure pathway 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 mix.

In the determination of the limiting sector, all age groups and all of the exposure pathways are initially evaluated using the GASPAR code. These include cow milk, beef and vegetable ingestion, inhalation, and ground'lane exposure. Goat milk is not currently an exposure pathway 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 Q and ~D Qv values occur (Appendix A). With all of the exposure pathways identified in the land use census (Table 3.2-2) 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 XTQv and DTQv 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 Table 3.2-2. 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

'I 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3-1 through 3.3-19 present R~ values for the total body, GZ-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:

Dt s 7.5 mrem (3. 3-14)

For the calendar year:

Dt 5 15 mrem (3.3-15)

The quarterly limits given above represent one-half the annual design objectives of Section ZI.C of Appendix I of 10CFR50. Zf 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 Z 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 pt where:

= ( ~ ')

following expression:

+ at (3.3-16)

Dp, the 31 Day Projected Dose by organ t D, sum of all open release paints in mrem/day by organ x.

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.

Additional Anticipated Dose for gaseous releases by organ r 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 F 11.2.4, the projected month's dose should be compared as in the following:

D s 0.3 mrem to any organ (3.3-17)

Zf 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

e 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 bhuJida 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 '.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 '.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-110M 3.48E+09 3.48E+09 3.48E+09 3A8E+09 3.48E+09 3.48E+09 3.48E+09 4.06E+09 Sn-11 3 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 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.34E+07 I-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 I-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 I-133 2.47E+06 2.47E+ 06 2.47E+06 2.47E+06 2.47E+06 2.47E+ 06 2A7E+ 06 3.00E+ 06 I-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-138 1.49E+ 08 1.49E+08 1.49E+08 1.49E+ 08 1.49E+ 08 1 A9E+ 08 1 A9E+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 Kf-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

'R Values in units of mrem/yr per yCi/m'or inhalation and tritium and in units of mrem/yr per yCi/seo per m'or all others.

3-34

Shearon Harris Nuclear Power Plant (S~NPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Veget GROUP ~ Adult XJ3ody. Qitutct JQ dna@ ThymirL 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.OOE+Ol O.OOE+Ol O.OOE+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.OOE+01 Mn-54 5.83E+07 9.36E+08 O.OOE+01 3.05E+08 9.09E+ 07 O.OOE+ 01 O.OOE+01 O.OOE+01 Fe-59 1.12E+08 9.75E+08 1.24E+08 2.93E+08 O.OOE+ 01 O.OOE+ 01 8.17E+07 O.OOE+01 Co-58 6.71E+ 07 6.07E+08 O.OOE+01 2.99E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 3.67E+ 08 3.12E+09 O.OOE+01 1.66E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 5.77E+08 8,04E+08 4.01E+08 1.28E+09 8.54E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1.03E+ 08 4.36E+ 07 O.OOE+ 01 2.21E+ 08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-89 2.87E+08 1.60E+09 1.00E+ 10 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.64E+ 11 1.93E+ 10 6.70E+ 1 1 O.OOE+ 01 O.OOE+ Ol O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.34E+ 05 ~ 2.76E+ 09 5.01E+06 0;OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+Ol Zr-95 2.51E+05 1.17E+09 1.16E+06 3.71E+05 5.82E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 4.19E+ 04 4.73E+ 08 1.40E+ 05 7.79E+04 7.70E+04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ru-103 2.04E+ 06 5.53E+ 08 4.74E+ 06 O.OOE+ 01 1.81E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+01 RU-106 2.46E+ 07 1.26E+ 10 1.94E+08 O.OOE+Ol 3.75E+08 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 6.23E+06 4.28E+09 1.13E+07 1.05E+07 2.06E+07 O.OOE+Ol O.OOE+01 O.OOE+01 Sn-113 1.36E+07 2.52E+08 1.44E+ 07 5.66E+05 4.09E+05 1.96E+05 O.OOE+01 O.OOE+ 01 Sb-124 4.02E+07 2.88E+09 1.01E+08 1.92E+06 O.OOE+00 2.46E+05 7.90E+07 O.OOE+01 Te-1 27M 6.12E+07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 O.OOE+01 O.OOE+Ol Te-129M 4.71E+07 1.50E+09 2.98E+08 1.11E+08 1.24E+09 1.02E+08 O.OOE+01 O.OOE+Ol I-131 6.61E+ 07 3.04E+ 07 8.07E+ 07 1.15E+08 1.98E+ 08 3.78E+ 10 O.OOE+ 01 O.OOE+Ol I-132 5.21E+ 01 2.80E+01 5.57E+01 1.49E+02 2.37E+02 5.21E+03 O.OOE+01 O.OOE+Ol l-l 33 1.12E+06 3.30E+ 06 2.1 1 E+ 06 3.67E+06 6.40E+06 5.39E+08 O.OOE+01 O.OOE+01 I-135 3.91E+ 04 1.20E+05 4.05E+04 1.06E+05 1.70E+05 7.00E+06 O.OOE+ Ol O.OOE+ 01 Cs-134 8.83E+09 1.89E+08 4.54E+09 1.08E+10 3.49E+09 O.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 O.OOE+01 1.26E+07 O.OOE+01 Cs-137 5.94E+09 1.76E+08 6.63E+09 9.07E+09 3.08E+09 O.OOE+01 1.02E+09 O.OOE+01 Ba-140 8AOE+06 2.64E+08 1.28E+08 1.61E+05 5.47E+04 O.OOE+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.OOE+01 O.OOE+01 O.OOE+ 01 Ce-144 1.69E+06 1.06E+ 10 3.15E+ 07 1.32E+07 7.80E+06 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Hf-181 1.07E+06 7.06E+08 9.51E+06 5.36E+04 4.48E+04 3A1E+04 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per yCi/me for inhalation and tritium and in units of mrem/yr per yCI/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'ATHWAY

~ Veget AGE GROUP ~ Teen LJ3adg QLTract JQdnny. Ihyxnid H-3 2.61E+ 03 2.61E+03 O.OOE+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 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Cr-51 6.11E+04 1.03E+07 O.OOE+ 01 O.OOE+Ol 1.34E+04 3.39E+04 8.72E+ 04 O.OOE+ 01 Mn.54 8.79E+07 9.09E+08 O.OOE+01 4.43E+ 08 1.32E+08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Fe.59 1.60E+08 9.78E+08 1.77E+08 4.14E+ 08 O.OOE+Ol O.OOE+ 01 1.30E+08 O.OOE+ 01 Co-58 9.79E+07 5.85E+08 O.OOE+01 4.25E+ 07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Co-60 5.57E+ 08 3.22E+ 09 O.OOE+ 01 2.47E+08 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 8.68E+ 08 7.88E+08 5.36E+ 08 1.86E+09 1.19E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1.30E+08 4.09E+07 O.OOE+ Ol 2.76E+08 O.OOE+01 O.OOE+Ol O.OOE+Ol O.OOE+ 01 Sr-89 4.36E+08 1.81E+09 1.52E+10 O.OOE+O'I O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 2.05E+ 11 2.33E+ 10 8.32E+ 11 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Y-91 2.06E+ 05 ~ 3.15E+ 09 7.68E+06 O.OOE+Ol O.OOE+ 01 O.OOE+ 01 O.OOE+01 O.OOE+01 Zr-95 3.68E+05 1.23E+09 1.69E+06 5.35E+05 7.86E+ 05 O.OOE+Ol O.OOE+01 O.OOE+01 Nb-95 5.77E+04 4.48E+08 1.89E+05 1.05E+05 1.02E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.90E+06 5.66E+08 6.78E+06 O.OOE+01 2.39E+07 O.OOE+01 O.OOE+01 O.OOE+Ol Ru-106 3.93E+07 1.50E e10 3.12E+08 O.OOE+ 01 6.02E+08 O.OOE+01 O.OOE+01 O.OOE+Ol Ag-110M 9.39E+06 4.34E+09 1.63E+07 1.54E+07 2.95E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.02E+ 07 2.29E+08 1.91E+ 07 8.03E+ 05 5.65E+ 05 2.63E+05 O.OOE+ 01 O.OOE+ 01 Sb-124 5.89E+ 07 3.04E+09 1.51E+08 2.78E+06 O.OOE+01 3.43E+05 1.32E+08 O.OOE+01 Te-127M 9A4E+07 1.98E+09 7.93E+ 08 2.81E+ 08 3.22E+09 1.89E+08 O.OOE+ 01 O.OOE+01 Te-129M 6.79E+ 07 1.61E+09 4.29E+ 08 1.59E+08 1.79E+08 1.38E+08 O.OOE+ 01 O.OOE+01 I-131 5.77E+07 2.13E+ 07 7.68E+ 07 1.07E+ 08 1.85E+08 3.14E+ 10 O.OOE+ 01 O.OOE+01 I-132 4.72E+01 5.72E+01 5.02E+ 01 1.31E+02 2.07E+02 4.43E+03 O.OOE+ 01 O.OOE+01 I-133 1.01E+ 06 2.51E+06 1.96E+ 06 3.32E+ 06 5.83E+06 4.64E+08 O.OOE+01 O.OOE+01 1-135 3.49E+ 04 1.04E+05 3.66E+ 04 9.42E+ 04 1.49E+05 6.06E+06 O.OOE+ 01 O.OOE+ 01 Cs-134 7.54E+09 2.02E+08 6.90E+09 1.62E+ 10 5.16E+09 O.OOE+01 1.97E+ 09 O.OOE+ 01 Cs-136 1.13E+ 08 1.35E+ 07 4.28E+07 1.68E+08 9.16E+07 O.OI) E+ 01 1.44E+07 O.OOE+01 Cs-137 4.90E+09 2.00E+08 1.06E+10 1.41E+ 10 4.78E+09 O.OOE+O'I 1.86E+09 O.OOE+Ol Ba-140 8.88E+06 2.12E+08 1.38E+08 1.69E+05 5.72E+04 O.OOE+01 1.14E+05 O.OOE+01 Ce-141 2.12E+04 5.29E+08 2.77E+05 1.85E+05 8.70E+04 O.OOE+Ol O.OOE+01 O.OOE+01 Ce-144 2.71E+06 1.27E+10 5.04E+ 07 2.09E+ 07 1.25E+07 O.OOE+Ol O.OOE+01 O.OOE+01 Hf-18'I 1.54E+06 6.90E+08 1.38E+07 7.58E+04 6.32E+04 4.63E+04 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per yCI/ms for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or 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'ATHWAY

~ Veget AGE GROUP ~ Child

~odor. ZiLXraat. ~m ~g ~ida H-3 4.04E+03 4.04E+ 03 O.OOE+ 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 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 1.16E+05 6.15E+06 O.OOE+01 O.OOE+Ol 1.76E+04 6.44E+04 1.1 BE+05 O.OOE+01 Mn-54 1.73E+08 5.44E+08 O.OOE+01 6.49E+08 1.82E+08 O.OOE+01 O.QOE j01 O.OOE+01 Fe-59 3.17E+08 6.62E+08 3.93E+08 6.36E+08 O.OOE+01 O.OOE+01 1.84E+08 O.OOE+01 Co-58 1.92E+08 3.66E+ 08 O.OOE+ 01 6.27E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Co-60 1.11E+09 2.08E+09 O.OOE+ 01 3.76E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 1.70E+09 4.81E+08 1.03E+09 2.74E+ 09 1.73E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 2.81E+ 08 2.94E+ 07 O.OOE+ 01 4.56E+ 08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.03E+09 1.40E+09 3.62E+ 10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 3.49E+ 11 1.86E+ 10 1.38E+ 12 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol O.OOE+01 O.OOE+ 01 Y.91 4.89E+05 ~ 2.44E+ 09 1.83E+ 07 0;OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Zr-95 7.44E+05 8.71E+08 3.80E+ 06 8.35E+05 1.20E+06 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.12E+05 2.91E+ 08 4.04E+05 1.57E+05 1.48E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 5.86E+ 06 3.94E+ 08 1.52E+07 O.OOE+Ol 3.84E+07 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Ru-106 9.38E j07 1.17E+ 10 7.52E+08 O.OOE+Ol 1.02E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.87E+ 07 2.78E+ 09 3.46E+ 07 2.34E+07 4.35E+07 O.OOE+Ol O.OOE+01 O.OOE+01 Sn-113 3.97E+ 07 1.45E+ 08 3,64E+07 1.18E+06 8.09E+05 4.82E+05 O.OOE+01 O.OOE+01 Sb-124 1.21E+08 2.1 6E+ 09 3A4E 08j 4.47E+08 O.OOE+01 7.61E+05 1.91E+08 O.OOE+01 Te-127M 2.26E+ 08 1.54E+09 1.90E+09 5.12E+ 08 5.42E+09 4.55E+08 O.OOE+01 O.OOE+Ol Te-129M 1.55E+08 1.22E+09 9.98E+08 2.79E+08 2.93E+09 3.22E+08 O.OOE+01 O.OOE+01 I-l 31 8.16E+ 07 1.23E+07 1.43E+08 1.44E+08 2.36E+08 4.75E+10 O.OOE+01 O.OOE+01 I-132 7.53E+ 01 1.93E+02 8.91E+ Ol 1.64E+ 02 2.51E+ 02 7.60E+ 03 O.OOE+01 O.OOE+ 01 I-133 1.67E+ 06 1.78E+06 3.57E+06 4.42E+06 7.36E+ 06 8.21E+ 08 O.OOE+Ol O.OOE+ 01 1-135 5.54E+ 04 8.92E+04 6.50E+ 04 1.17E+05 1.79E+ 05 1.04E+ 07 O.OOE+Ol O.OOE+ 01 Cs-134 5.40E+09 1.38E+08 1.56E+10 2.56E+ 10 7.93E+09 O.OOE+ 01 2.84E+09 O.OOE+01 Cs-136 1.43E+08 7.77E+06 8.04E+07 2.21E+ 08 1 18E+08

~ O.OI)E j01 1.76E+07 O.OOE+01 Cs-137 3.52E+09 1.50E+08 2.49E+ 10 2.39E+ 10 7.78E+ 09 O.OOE+01 2.80E+09 O.OOE+01 Ba-140 1.61E+07 1.40E+08 2.76E+ 08 2.42E+ 05 7.87E+ 04 O.OOE+ Ol 1.44E+05 O.OOE+ 01 Ce-141 4.75E+ 04 3.99E+ 08 6.42E+ 05 3.20E+ 05 1.40E+ 05 O.OOE+ 01 O.OOE+01 O.OOE+01 Ce-144 6.49E+ 06 9.94E+ 09 1.22E+08 3.81E+ 07 2.1 1 E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Hf-181 3.15E+06 5.17E+08 3.13E+07 1.22E+05 9.78E+04 1.03E+05 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per /ICI/m~ for inhalation and tritium and in units of mrem/yr per pCi/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 QL'L'tact JQdnay. Ihyrnid H-3 3.27E+ 02 3.27E+02 O.OOE+ 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 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 4.27E+03 1.08E+06 O.OOE+01 O.OOE+01 9.42E+02 2.56E+03 5.67E+03 O.OOE+01 Mn.54 1.06E+06 1.71E+07 O.OOE+01 5.57E+06 1.66E+06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 1.43E+08 1.25E+09 1.59E+08 3.74E+08 O.OOE+Ol O.OOE+01 1.04E+08 O.OOE+01 Co-58 2.43E+ 07 2.20E+08 O.OOE+Ol 1.08E+07 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 Co.60 1.03E+08 8.76E+ 08 O.OOE+ 01 4.66E+ 07 O.OOE+ Ol O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 3.58E+08 4.98E+08 2.49E+08 7.91E+08 5.29E+ 08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1A2E+08 6.00E+07 O.OOE+01 3.04E+08 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 5.23E+ 08 2.92E+07 1.82E+08 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-90 2.02E+ 09 2.38E+08 8.22E+09 O.OOE+Ol O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Y-91 1.80E+04 . 3.71E+08 6.75E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2A3E+05 1.14E+09 1.12E+06 3.59E+05 5.64E+05 O.OOE+01 O.OOE+01 O.OOE+Ol Nb-95 4.12E+05 4.65E+09 1.38E+06 7.66E+05 7.58E+05 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-103 2.72E+07 7.38E+09 6.32E+07 O.OOE+Ol 2.41E+08 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-106 2.19E+08 1.12E+11 1.73E+09 O.OOE+01 3.35E+09 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.34E+ 06 1.61E+09 4.27E+06 3.95E+06 7.76E+06 O.OOE+Ol O.OOE+Ol O.OOE+01 Sn-113 2.80E+07 5.19E+08 2.97E+07 1.15E+06 8.40E+05 4.03E+05 O.OOE+Ol O.OOE+01 Sb.124 4.72E+06 3.38E+08 1.19E+07 2.25E+05 O.OOE+01 2.88E+04 9.27E+06 O.OOE+Ol Te-127M 1.00E+08 2.76E+09 8.22E+08 2.94E+08 3.34E+09 2.10E+08 O.OOE+ 01 O.OOE+Ol Te-129M 1.17E+08 3.73E+09 7.40E+08 2.76E+08 3.09E+09 2.54E+08 O.OOE+ 01 O.OOE+ 01 I-131 5.77E+06 2.66E+06 7.04E+06 1.01E+07 1.73E+07 3.30E+09 O.OOE+01 O.OOE+ Ol I-133 1.51E-01 4.46E-01 2.85E-01 4.96E-01 8.66E-01 7.29E+ 01 O.OOE+ 01 O.OOE+01 1-135 6.07E-17 1.86E-16 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+ 01 O.OOE+ Ol Cs-134 7.81E+ 08 1.67E+ 07 4.01E+ 08 9.55E+ 08 3.09E+ 08 O.OOE+ 01 1.03E+08 O.OOE+ 01 Cs-136 2.14E+07 3.33E+06 7.53E+06 2.97E+ 07 1.BSE+07 O.OOE+ 01 2.27E+06 O.OOE+ 01 Cs-137 4.99E+08 1.47E+ 07 5.57E+ 08 7.61E+ 08 2.58E+ 08 O.OOE+01 8.59E+07 O.OOE+ 01 Ba-140 1.20E+06 3.77E+07 1.83E+07 2.30E+04 7.82E+03 O.OOE+01 1.32E+04 O.OOE+01 Ce-141 6.46E+02 2.1 BE+07 8.42E+03 5.69E+ 03 2.65E+ 03 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 Ce-144 4.70E+04 2.96E+08 8.75E+05 3.66E+ 05 2.17E+05 O.OOE+01 O.OOE+01 O.OOE+ 01 Hf-181 1.52E+06 9.97E+ 08 1.34E+07 7.57E+ 04 6.33E+04 4.81E+04 O.OOE+01 O.OOE+ 01

'R VaIues in units of mrem/yr per yCi/ms for inhalation and tritium end in units of mrern/yr'per yCi/seo per m'or all others.

3-38

~

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Of fsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Meet GROUP ~ Teen LJ3ngt. JQdnng Thyroid H-3 1.95E+02 1.95E+02 O.OOE+01 1.95E+02 1.95E+02 'I.95E+02 1.95E+ 02 1.95E+ 02 P-32 9.98E+ 07 2.16E+08 2.58E+09 1.60E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 3.42E+ 03 5.75E+05 O.OOE+01 O.OOE+01 7.49E+02 1.90E+03 4.88E+03 O.OOE+01 Mn-54 8.43E+ 05 8.72E+ 06 O.OOE+ 01 4.25E+ 06 1.27E+ 06 O.OOE+01 O.OOE+01 O.OOE+01 Fe-59 1.1 5E+ 08 7.02E+ 08 1.27E+ 08 2.97E+ 08 O.OOE+ 01 O.OOE+01 9.36E+07 O.OOE+01 Co-58 1.93E+07 1.15E+08 O.OOE+01 8.36E+06 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+ 01 Co-60 8.15E+07 4.71E+08 O.OOE+Ol 3.62E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Zn-65 . 2.83E+ 08 2.57E+08 1.75E+08 6.07E+ 08 3.89E+08 O.OOE+ 01 O.OOE+Ol O.OOE+01 Rb-86 1.19E+08 3.76E+ 07 O.OOE+ 01 2.54E+08 O.OOE+01 O.OOE+ Ol O.OOE+01 O.OOE+01 Sr-89 4.40E+06 1.83E+07 1.54E+08 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Sr-90 1.31E+09 1.49E+08 5.32E+09 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 O.OOE+Ol

~ ~ Y-91 1.52E+ 04 ~ 2.33E+08 5.68E+05 O.OOE+Ol, O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 1.95E+05 6.53E+08 8.97E+05 2.83E+05 4.16E+05 O.OOE+01 O.OOE+01 Nb-95 3.29E+05 2.55E+09 1.08E+06 5.97E+05 5.79E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.20E+07 4.30E+09 5.15E+07 O.OOE+01 1.82E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01'.22E+07 Ru-106 1.84E+ 08 7.00E+ 10 1.46E+ 09 O.OOE+01 2.81E+ 09 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Ag-110M 1.86E+06 8.59E+08 3.23E+06 3.06E+06 5.83E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.51E+08 2.09E+07 8.80E+05 6.19E+05 2.88E+ 05 O.OOE+01 O.OOE+ 01 Sb-124 3.80E+06 1.96E+08 9.73E+06 1.79E+05 O.OOE+01 2.21E+ 04 8.50E+06 O.OOE+ 01 Te-127M 8.25E+ 07 1.73E+09 6.94E+08 2.46E+08 2.81E+09 1.65E+08 O.OOE+01 O.OOE+01 Te-129M 9.81E+07 2.33E+09 6.20E+08 2.30E+08 2.59E+09 2.00E+08 O.OOE+01 O.OOE+01 I-131 4.40E+ 06 1.62E+06 5.85E+06 8.20E+06 1.41E+ 07 2.39E+ 09 O.OOE+01 O.OOE+01 I-133 1.23E-01 3.06E-01 2.39E-01 4.05E-01 7.10E-01 5.65E+ 01 O.OOE+Ol O.OOE+ Ol I-135 4.88E.17 1.46E-16 5.11E-17 1.32E-16 2.08E-16 8.46E-15 O.OOE+01 O.OOE+ 01 Cs-134 3.48E+ 08 9.34E+06 3.19E+ 08 7.51E+ 08 2.39E+08 O.OOE+ 01 9.11E+07 O.OOE+ 01 Cs-136 1.55E+07 1.86E+06 5.87E+06 2.31E+07 1.26E+07 O.OOE+01 1.98E+06 O.OOE+01 Cs-137 2.14E+08 8.75E+06 4.62E+08 6.15E+08 2.09E+08 O.OOE+01 8.13E+07 O.OOE+01 Ba-140 9.76E+05 2.34E+ 07 1.51E+ 07 1.86E+ 04 6.29E+ 03 O.OOE+01 1.25E+04 O.OOE+ Ol Ce-141 5.42E+ 02 1.35E+07 7.07E+03 4.72E+03 2.22E+03 O.OOE+ 01 O.OOE+01 O.OOE+01 Ce-144 3.96E+ 04 1.85E+08 7.37E+05 3.05E+05 1.82E+05 O.OOE+ 01 O.OOE+01 O.OOE+01 Hf-181 1.22E+06 5.50E+ 08 1.10E+ 07 6.05E+ 04 5.04E+ 04 3.69E+ 04 O.OOE+01 O.OOE+01

'R Values in units of mrem/yr per /rCI/m'or inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-39

4 '!

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'GE PATHWAY ~ Meat GROUP ~ Child H-3 2.36E+02 2.36E+02 O.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 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Cr-51 5.33E+03 2.83E+05 O.OOE+01 O.OOE+Ol 8.09E+02 2.96E+03 5AOE+03 O.OOE+ 01 Mn-54 1.30E+06 4.08E+06 O.OOE+01 4.86E+06 1.36E+06 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Fe-59 1.82E+08 3.80E+08 2.25E+08 3.65E+08 O.OOE+01 O.OOE+01 1.06E+08 O.OOE+01 Co-58 2.99E+07 5.70E+07 O.OOE+01 9.76E+06 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Co-60 1.27E+08 2.38E+08 O.OOE+Ol 4.30E+07 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 2n-65 4.35E+ 08 1.23E+ 08 2.62E+ 08 6.99E+ 08 4AOE+08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Rb-86 2.21E+08 2.32E+07 O.OOE+01 3.60E+08 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-89,, 8.31E+06 ~ 1.13E+07 2.91E+08 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.74E+09 9.26E+07 6.87E+09 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Y-91 2.87E+04 1.43E+08 1.07E+06 O.OOE+Ol O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Zr-95 3.12E+05 3.65E+08 1.59E+06 3.50E+05 5.01E+05 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 5.17E+05 1.34E+09 1.86E+06 7.23E+05 6.80E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 3.58E+ 07 2.41E+ 09 9.31E+ 07 O.OOE+ 01 2.34E+ 08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ru-106 3.43E+08 4.27E+10 2.75E+09 O.OOE+01 3.71E+09 O.OOE+Ol O.OOE+01 O.OOE+01 Ag-110M 2.89E+06 4.30E+08 5.36E+06 3.62E+06 6.74E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 3.42E+07 1.25E+08 3.14E+07 1.01E+06 6.97E+05 4.15E+05 O.OOE+01 O.OOE+01 Sb-124 6.17E+06 1.10E+08 1.76E+07 2.28E+05 O.OOE col 3.88E+04 9.77E+06 O.OOE+01 Te-127M 1.55E+08 1.06E+09 1.31E+09 3.52E+08 3.73E+09 3.13E+08 O.OOE+Ol O.OOE+01 Te-129M 1.81E+ 08. 1.42E+ 09 1.17E+ 09 3.26E+ 08 3.43E+ 09 3.77E+ 08 O.OOE+ 01 O.OOE+ 01 I-131 6.20E+06 9.72E+05 1.09E+07 1.09E+07 1.79E+07 3.61E+09 O.OOE+01 O.OOE+01 l-133 2.07E-01 2.21E-01 4.43E-01 5.48E-01 9.13E-01 1.02E+02 O.OOE+01 O.OOE+01 I-135 7.87E-17 1.27E-16 9.25E-17 1.66E-16 2.55E-16 1.47E-14 O.OOE+01 O.OOE+01 Cs-134 1.95E+ 08 4.93E+ 06 5.63E+ 08 9.23E+ 08 2.86E+ 08 O.OOE + 01 1.03E'+ 08 O.OOE+ 01 Cs-136 1.80E+07 9.78E+05 1.01E+07 2.78E+07 1.48E+07 O.OOE+Ol 2.21E+06 O.OOE+01 Cs-137 1.20E+08 5.10E+06 8.51E+08 8.15E+08 2.65E+08 O.OOE+Ol 9.55E+07 O.OOE+Ol B3-140 1.63E+06 1.42E+07 2.80E+07 2.45E+04 7.97E+03 O.OOE+Ol 1.46E+04 O.OOE+Ol Ce-141 9.86E+02 8.28E+06 1.33E+04 6.64E+03 2.91E+03 O.OOE+01 O.OOE+Ol O.OOE+01 Ce-144 7.42E+04 1.14E+08 1.39E+06 4.36E+05 2.41E+05 O.OOE+01 O.OOE+Ol O.OOE+Ol Hf-181 2.02E+ 06 3.31E+ 08 2.00E+ 07 7.79E+ 04 6.26E+ 04 8.56E+ 04 O.OOE+01 O.OOE+ 01

'R Values in units of mrem/yr per pCi/m'or inhalation and tritium end in units of mrem/yr per /ICI/seo per m s 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'ATHWAY

~ Cow Milk AGE GROUP ~ Adult LBndg Q Lect H-3 7.69E+02 7.69E+02 O.OOE+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 O.OOE+01 O.OOE+ 01 O.OOE+01 O.OOE+ 01 Cr-51 1.73E+04 4.36E+06 -

O.OOE+01 O.OOE+01 3.82E+03 1.04E+04 2.30E+04 O.OOE+Ol Mn-54 9.76E+05 1.57E+07 O.OOE+01 5.11E+06 1.52E+ 06 O.OOE t 01 O.OOE-Ol O.OOE+01 Fe.59 1.60E+07 1.39E+08 1.77E+07 4.17E+07 O.OOE+01 O.OOE+01 1.17E+07 O.OOE+01 Co-58 6.28E+06 5.68E+07 O.OOE+01 2.80E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 2.24E+07 1.91E+08 O.OOE+01 1.02E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Zn-65 1.38E+09 1.92E+09 9.59E+08 3.05E+09 2.04E+09 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 7.54E+08 3.19E+08 O.OOE+01 1.62E+09 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-89 2.50E+07, . 1.40E+08 8.70E+08 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-90 7.59E+09 8.94E+08 3.09E+10 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+Ol Y-91 1.37E+02 2.81E+06 5.11E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Zr-95 1.22E+02 5.71E+05 5.62E+02 1.80E+02 2.83E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.48E+04 1.67E+08 4.95E+04 2.75E+04 2.72E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.63E+02 7.14E+04 6.11E+02 O.OOE+01 2.33E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 1.60E+03 8.17E+05 1.26E+04 O.OOE+01 2.44E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 2.04E+ 07 1.40E+ 10 3.71E+ 07 3.44E+07 6.76E+ 07 O.OOE+ 01 O.OOE+01 O.OOE+ 01 Sn-113 1.32E+06 2.44E+07 1.40E+06 5.41E+04 3.95E+04 1.90E+04 O.OOE+01 O.OOE+01 Sb-124 6.14E+06 4.39E+08 1.55E+07 2.92E+05 O.OOE+Ol 3.75E+04 1.20E+07 O.OOE+01 Te-127M 4.11E+06 1.13E+08 3.37E+07 1.21E+07 1.37E+08 8.62E+06 O.OOE+01 O.OOE+01 Te-129M 6.19E+06 1.97E+ 08 3.91E+07 1.46E+07 1.63E+ 08 1.34E+ 07 O.OOE+01 O.OOE+ 01 I-131 1.59E+08 7.32E+ 07 1.94E+08 2.77E+08 4.76E+08 9.09E+ 10 O.OOE+01 O.OOE+ 01 I-132 1.03E+01 5.51E-02 1.10E+01 2.93E+01 4.67E+Ol 1.03E+01 O.OOE+01 O.OOE+Ol I-133 1.40E+06 4.13E+06 2.64E+06 4.59E+06 8.01E+06 6.75E+08 O.OOE+01 O.OOE+01 I-135 9.03E+03 2,76E+04 9.34E+03 2.45E+04 3.92E+04 1.61E+06 O.OOE+01 O.OOE+01 Cs-134 6.71E+09 1.44E+ 08 3.45E+09 3,21E+ 09 2.66E+ 09 O.OOE+ 01 8.82E+08 O.OOE+ 01 Cs-136 4.73E+ 08 7.46E+ 07 1.66E+ 08 6.57E+ 08 3.65E+ 08 O.OOE+ 01 5.01E+ 07 O.OOE+ 01 Cs-137 4.22E+ 09 1.25E+ 08 4.71E+ 09 6.44E+ 09 2.1 9E+ 09 O.OOE+ 01 7.27E+ 08 O.OOE+ 01 Ba-140 1.12E+06 3.53E+07 1.71E+07 2.15E+04 7.32E+03 O.OOE+01 1.23E+04 O.OOE+01 Ce-141 2.23E+02 7.52E+06 2.91E+03 '1.97E+03 9.14E+02 O.OOE+01 O.OOE+01 O.OOE+Ol Ce-144 1.1 5E+ 04 7.26E+ 07 2.1 5E+ 05 8.97E+ 04 5.32E+ 04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Hf-181 6.68E+02 4.38E+05 5.91E+03 3.33E+01 2.79E+01 2.12E+01 O.OOE+01 O.OOE+Ol

'R Values in units of mrem/yr per /rCI/me for inhalation and tritium and in units of mrem/yr per pCi/sec per ms 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'GE PATHWAY ~ Cow Milk GROUP ~ Teen XJhufg QLItact JQdnatr IhyxoirL H-3 1.00E+03 1.00E+03 O.OOE+ 01 1.00E+03 1.00E+03 1.0OE+03 1.00E+03 1.0OE+03 P-32 8.00E+ 08 1.73E+ 09 2.06E+ 10 1.28E+09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Cr-51 3.02E+ 04 5.08E+ 06 O.OOE+ 01 O.OOE+ 01 6.63E+ 03 1.68E+ 04 4.32E+ 04 O.OOE+ Ol Mn-54 1.69E+06 1.75E+07 O.OOE+01 8.52E+06 2.54E+06 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Fe-59 2.79E+ 07 1.71E+08 3.10E+07 7.23E+07 O.OOE+ 01 O.OOE+ 01 2.28E+ 07 O.OOE+ Ol Co-58 1.09E+07 6.50E+07 O.OOE+01 4.72E+06 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Co-60 3.88E+07 2.25E+08 O.OOE+01 1.72E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 2.38E+09 2.16E+09 1.47E+09 5.11E+09 3.27E+09 O.OOE+01 O.OOE+01 O.OOE+Ol Rb-86 1.39E+09 4.37E+08 O.OOE+01 2.95E+09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Sr-89 4.59E+07 1.91E+08 1.60E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.08E+ 10 1.23E+09 4.37E+ 10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+01 Y-91 2.52E+02 3.85E+06 9.40E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Zr-95 2.13E+02 7.16E+05 9.83E+02 3.10E+02 4.56E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 2.58E+04 2.00E+08 8.45E+04 4.68E+04 4.54E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 4.65E+02 9.08E+04 1.09E+03 O.OOE+01 3.83E+03 O.OOE+01 O.OOE+01 O.OOE+0'I Ru-106 2.93E+ 03 1.1 1E+ 06 2.32E+04 O.OOE+01 4.48E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 3.53E+ 07 1.63E+ 10 6.14E+07 5.81E+07 1 11E+08

~ O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 2.28E+ 06 2.58E+ 07 2.15E+ 06 9.06E+04 6.37E+04 2.97E+04 O.OOE+01 O.OOE+01 Sb-1 24 1.08E+07 5.56E+ 08 2.76E+07 5.08E+05 O.OOE+01 6.26E+04 2.41E+07 O.OOE+01 Te-127M 7.39E+ 06 1.55E+ 08 6.22E+ 07 2.21E+ 07 2.52E+08 1.48E+07 O.OOE+01 O.OOE+01 Te-129M 1.13E+ 07 2.69E+08 7.15E+07 2.65E+ 07 2.99E+08 2.31E+07 O.OOE+01 O.OOE+01 I-131 2.65E+08 9.75E+07 3.52E+08 4.93E+08 8.48E+08 1 44E+11 O.OOE+01 O.OOE+01 1-132 1.83E+01 2.22E+ 01 1.94E+ 01 5.09E+ 01 8.02E+01 1.71E+01 O.OOE+01 O.OOE+Ol I-l 33 2.49E+06 6.19E+06 4.82E+06 8.18E+06 1.43E+07 1.14E+09 O.OOE+01 O.OOE+Ol I-135 1.58E+04 4.74E+04 1.66E+04 4.27E+04 6.75E+04 2.75E+06 O.OOE+01 O.OOE+01 Cs-134 6.54E+09 1.75E+08 5.99E+09 1.41E+ 10 4.48E+09 O.OOE+ 01 1.71E+09 O.OOE+01 Cs-1 36 7ABE+ 08 8.97E+ 07 2.83E+ 08 1.11E+09 6.07E+ 08 O.OOE+01 9.56E+07 O.OOE+01 Cs-137 3.96E+ 09 1.62E+08 8.54E+ 09 1.14E+ 10 3.87E+ 09 O.OOE+ Ol 1.50E+09 O.OOE+01 Ba-140 1.99E+06 4.77E+07 3.09E+ 07 3.79E+ 04 1.28E+ 04 O.OOE+ 01 2.55E+04 O.OOE+01 Ce-141 4.09E+02 1.02E+07 5.33E+ 03 3.56E+ 03 1.68E+03 O.OOE+ 01 O.OOE+ Ol O.OOE+Ol Ce-144 2.12E+04 9.93E+07 3.95E+ 05 1.63E+05 9.76E+ 04 O.OOE+01 O.OOE+01 O.OOE+Ol Hf-181 1.18E+03 5.28E+05 1.06E+04 5.82E+01 4.84E+01 3.55E+01 O.OOE+ 01 O.OOE+01 "R Values in units of mrem/yr per yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/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'GE PATHWAY ~ Cow Milk GROUP ~ Child

%diner. Kidney IhyroirL H-3 1.58E+03 1.58E+ 03 O.OOE+ 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 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+ 01 Cr-51 6.17E+ 04 3.27E+ 06 O.OOE+01 O.OOE+01 9.36E+03 3.42E+04 6.25E+04 O.OOE+01 Mn-54 3.39E+ 06 1.07E+ 07 O.OOE+01 1.27E+07 3.57E+06 O.OOE+ 01 O.OQE+ Ol O.OOE+ 01 Fe-59 5.79E+ 07 1.21E+ 08 7.18E+07 1.16E+ 08 O.OOE+ 01 O.OOE+ 01 3.37E+07 O.OOE+ 01 Co-58 2.21E+ 07 4.20E+07 O.OOE+01 7.21E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Co-60 7.90E+07 1.48E+08 O.OOE+01 2.68E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Zn-65 4.79E+ 09 1.35E+09 2.89E+09 7.70E+09 4.85E+09 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Rb-86 3.36E+09 3.52E+08 O.OOE+01 5.47E+09 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+ 01 Sr-89 1.13E+08 1.54E+08 3.97E+ 09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 1.87E+10 9.95E+ 08 7.38E+ 10 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91, 6.21E+02 ~ 3.09E+06 2.32E+04 O.OOE+01. O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 4.47E+02 5.23E+05 2.28E+03 5.02E+02 7.18E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 5.31E+ 04 1.37E+08 1.91E+05 7.42E+04 6.98E+ 04 O.OOE+Ol O.OOE+Ol O.OOE+01 Ru-103 9.88E+ 02 6.65E+04 2.57E+ 03 O.OOE+01 6.47E+ 03 O.OOE+01 O.OOE+Ol O.OOE+01 Ru-106 7.14E+03 8.90E+ 05 5.72E+ 04 O.OOE+01 7.72E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 7.19E+07 1.07E+10 1.33E+08 9.00E+ 07 1.68E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 4.61E+05 1.69E+ 06 4.22E+ 05 1.36E+04 9.37E+ 03 5.58E+ 03 O.OOE+01 O.OOE+ 01 Sb-124 2.29E+ 07 4.09E+08 6.53E+07 8.47E+05 O.OOE+ 01 1.44E+05 3.62E+07 O.OOE+ 01 Te-127M 1.82E+07 1.24E+08 1.53E+08 4.13E+07 4.37E+ 08 3.66E+07 O.OOE+01 O.OOE+ 01 Te-129M 2.74E+ 07 2.15E+08 1.76E+08 4.92E+07 5.18E+ 08 5.68E+07 O.OOE+ 01 O.OOE+01 I~ 131 4.88E+ 08 7.64E+07 8.54E+08 8.59E+08 1.41E+09 2.84E+11 O.OOE+01 O.OOE+01 1-132 3.89E+ 01 9.95E+01 4.60E+01 8.45E+ 01 1.29E+00 3.92E+01 O.OOE+01 O.OOE+01 I~ 133 5.48E+ 06 5.84E+ 06 1.17E+ 07 1.45E+ 07 2.41E+ 07 2.69E+ 09 O.OOE+01 O.OOE+ 01 l-l 35 3.35E+04 5.39E+04 3.93E+04 7.07E+04 1.08E+05 6.26E+06 O.OOE+01 O.OOE+ 01 Cs-134 4.78E+09 1.22E+08 1.38E+ 10 2.27E+ 10 7.03E+ 09 O.OOE+01 2.52E+09 O.OOE+01 Cs-136 1.14E+09 6.17E+ 07 6.39E+ 08 1.76E+ 09 9.36E+ 08 O.OOE+01 1.40E+08 O.OOE+01 Cs-137 2.91E+ 09 1.23E+ 08 2.06E+ 10 1.97E+ 10 6.42E+09 O.OOE+01 2.31E+ 09 O.OOE+ 01 Ba-140 4.36E+ 06 3.78E+ 07 7.47E+ 07 6.54E+ 04 2.13E+ 04 O.OOE+ 01 3.90E+ 04 O.OOE+ 01 Ce-141 9.73E+ 02 8.17E+06 1.31E+04 6.55E+03 2.87E+03 O.OOE+ 01 O.OOE+01 O.OOE+ Ol Ce-144 5.20E+ 04 7.96E+07 9.74E+05 3.05E+05 1.69E+05 O.OOE+ 01 O.OOE+01 O.OOE+ 01 Hf-181 2.53E+03 4.16E+05 2.51E+04 9.79E+01 7.86E+Ol 8.24E+01 O.OOE+01 O.OOE+01

'R Values in units of mrern/yr per yCi/m'or inhalation and tritium and in units of mrem/yr per yCi/seo per m'~ 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'GE PATHWAY ~ Cow Milk GROUP ~ Infant ZJhdy. QLZmr JQdmty ZhycnixL H-3 2.40E+03 2.40E+03 O.OOE+ 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 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Cr-51 9.77E+04 2.85E+06 O.OOE+01 O.OOE+01 1.39E+04 6.38E+ 04 1.24E+05 O.OOE+01 Mn.54 5.37E+ 06 8.71E+ 06 O.OOE+ 01 2.37E+07 5.25E+ 06 O.OOE+ Ol O.OOE+ 01 O.OOE+ Ol Fe-59 9.23E+ 07 1.12E+08 1.34E+08 2.34E+ 08 O.OOE+Ol O.OOE+01 6.92E+07 O.OOE+Ol Co.58 3.60E+G7 3.59E+07 O.OOE+01 1.44E+07 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Co-60 1.29E+ 08 1.30E+ 08 O.OOE+ 01 5.47E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Zn.65 6.14E+09 1.12E+10 3.88E+ 09 1.33E+ 10 6.45E+ 09 O.OOE+ 01 O.OOE+01 O.OOE+01 Rb-86 6.86E+ 09 3.55E+ 08 O.OOE+ 01 1.39E+ 10 O.OOE+01 O.OOE+01 O.OOE+ Ol O.OOE+ 01 Sr-89 2.17E+08 1.55E+08 7.55E+ 09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-90 2.05E+ 10 1.00E+ 09 8.04E+ 10 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Y-91 1.16E+08 . 3.12E+06 4.36E+04 O.OOE+Ol. O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Zr-95 7.01E+02 4.92E+05 4.05E+03 9.88E+02 1.06E+03 O.OOE+01 O.OOE+Ol O.OOE+Ol Nb-95 8.48E+04 1.24E+08 3.56E+05 1.47E+05 1.05E+05 O.OOE+01 O.OOE+01 O.OOE+Ol Ru-103 1.74E+ 03 6.33E+04 5.21E+03 O.OOE+01 1.08E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ru-106 1.47E+04 8.95E+05 1.18E+05 O.OOE+01 1.39E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.19E+08 9.32E+09 2.46E+08 1.80E+08 2.57E+08 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 6.65E+06 1.37E+07 6.45E+06 2.45E+05 1.31E+05 9.34E+ 04 O.OOE+01 O.OOE+01 Sb-1 24 3.90E+07 3,88E+08 1.26E+08 1.85E+06 O.OOE+01 3.34E+ 05 7.88E+ 07 O.OOE+ 01 Te-127M 3.75E+ 07 1.25E+08 3.10E+08 1.03E+08 7.64E+08 8.96E+ 07 O.OOE+01 O.OOE+01 Te-129M 5.57E+07 2.16E+08 3.62E+ 08 1.24E+08 9.05E+08 1.39E+08 O.OOE+Ol O.OOE+01 I-131 9.23E+08 7.49E+ 07 1.78E+09 2.10E+09 2.45E+09 6.90E+11 O.OOE+01 O.OOE+Ol 1-132 6.90E+01 1.57E-OO 9.55E+01 1.94E+00 2.16E+00 9.09E+01 O.OOE+01 O.OOE+Ol I-133 1.05E+ 07 6.09E+06 2.47E+ 07 3.60E+07 4.23E+07 6.55E+09 O.OOE+ 01 O.OOE+01 I-135 5.93E+04 5.88E+04 8.17E+ 04 1.63E+05 1.81E+05 1.46E+07 O.OOE+01 O.OOE+ 01 Cs-134 4.19E+ 09 1.13E+08 2.23E+ 10 4.15E+10 1.07E+10 O.OOE+ Ol 4.38E+ 09 O.OOE+ 01 Cs-136 1.37E+09 5.58E+ 07 1.25E+ 09 3.67E+09 1.46E+09 O.OOE+Ol 2.99E+08 O.OOE+01 Cs-137 2.72E+ 09 1.20E+08 3.28E+ 10 3.84E+ 1 0 1.03E+ 1 0 O.OOE+ 01 4.1 BE+ 09 O.OOE+ 01 Be-140 7.91E+ 06 3.77E+07 1.54E+08 1.54E+05 3.65E+04 O.OOE+01 9.43E+04 O.OOE+ 01 Ce-141 1.87E+03 8.21E+ 06 2.60E+ 04 1.59E+04 4.90E+03 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Ce-144 7.82E+04 8.01E+ 07 1.40E+06 5.71E+05 2.31E+05 O.OOE+01 0 OOE+01 0 OOE+Ol Hf-181 4.23E+03 3.93E+05 4.78E+04 2.26E+02 1.32E+02 1.91E+02 O.OOE+Ol O.OOE+01

'R Values in units of mrem/yr per yCi/me for inhalation end tritium and in units of mrem/yr per yCi/sec per m'or ell others.

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'GE PATHWAY ~ Goat Milk GROUP = AdUIt GLIBaot Xidtuty Zhyrnid H-3 1.57E+03 1.57E+ 03 O.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 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+Ol Cr-51 2.08E+ 03 5.23E+05 O.OOE+01 O.OOE+01 4.58E+02 1.24E+03 2.76E+03 O.OOE+01 Mn-54 1.17E+05 1.88E+06 O.OOE+ 01 6.14E+05 1.83E+ 05 O.OOE+ Ol O.OOE+ 01 O.OOE+ 01 Fe-59 2.08E+ 05 1.81E+06 2.31E+ 05 5.42E+05 O.OOE+ 01 O.OOE+ 01 1.51E+05 O.OOE+01 Co-58 7.54E+05 6.82E+06 O.OOE+01 3.36E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 2.69E+06 2.29E+07 O.OOE+01 1.22E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn 1.65E+08 2.31E+08 1.15E+08 3.66E+08 2.45E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb.86 9.05E+ 07 3.83E+07 O.OOE+ 01 1.94E+ 08 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+ 01 Sr-89 5.24E+07 2.93E+08 1.83E+ 09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Sr-90 1.59E+ 10 1.88E+09 6.49E+ 10 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Y-91 1.64E+01 . 3.37E+05 8.13E+02 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+01 O.OOE+01 Zr-95 1.46E+01 6.85E+04 6.74E+01 2.16E+01 3.39E+01 O.OOE+ 01 O.OOE+ 01 O.OOE+

01'b-95 1.78E+ 03 2.01E+ 07 5.94E+ 03 3.31E+ 03 3.27E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 3.16E+01 8.56E+03 7.33E+01 O.OOE+ 01 2.80E+ 02 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol RU-106 1.92E+ 02 9.81E+ 04 1.52E+03 O.OOE+01 2.93E+03 O.OOE+01 O.OOE+Ol O.OOE+01 Ag-110M 2.45E+ 06 1.68E+ 09 4.46E+06 4.12E+06 8.11E+06 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 1.32E+05 2.44E+06 1.40E+05 5A1E+03 3.96E+ 03 1.90E+ 03 O.OOE+ 01 O.OOE+ 01 Sb.124 7.36E+ 05 5.27E+ 07 1.8BE+06 3.51E+ 04 O.OOE+ 01 4.50E+03 1.44E+06 O.OOE+01 Te-127M 4.93E+05 1.36E+07 4.05E+06 1.45E+06 1.64E+07 1.03E+06 O.OOE+01 O.OOE+01 Te-129M 7.43E+05 2.3BE+07 4.69E+06 1.75E+08 1.96E+07 1.61E+06 O.OOE+01 O.OOE+01 I-131 1.91E+08 8.78E+07 2.33E+ 08 3.33E+ 08 5.71E+08 1.09E+ 1 1 O.OOE+ 01 O.OOE+01 I-132 1.23E+01 6.61E-.02 1.32E+ 01 3.52E+01 5.61E+01 1.23E+01 O.OOE+01 O.OOE+01 I-133 1.68E+06 4.95E+06 3.17E+06 5.51E+06 9.61E+06 8.10E+08 O.OOE+01 O.OOE+01 I-135 1.08E+04 3.32E+04 1.12E+04 2.94E+04 4.71E+04 1.94E+06 O.OOE+01 O.OOE+Ol Cs-134 2.01E+ 10 4.31E+ 08 1.03E+10 2.46E+10 7.97E+09 O.OOE+01 2.65E+09 O.OOE+01 Cs-136 1A2E+09 2.24E+08 4.99E+ 08 1.97E+09 1.10E+09 O.OOE+01 1.50E+08 O.OOE+01 Cs-137 1.27E+10 3.74E+08 1.41E+10 1.93E+10 6.56E+09 O.OOE+01 2.18E+09 O.OOE+01 Ba-140 1.35E+05 4.23E+06 2.06E+06 2.58E+03 8.78E+ 02 O.OOE+ 01 1.48E+03 O.OOE+ 01 Ce-141 2.68E+01 9.03E+05 3.49E+ 02 2.36E+02 1.10E+ 02 O.OOE+ 01 O.OOE+01 O.OOE+01 Ce-144 1.38E+03 8.71E+ 06 2.58E+ 04 1.08E+04 6.39E+ 03 O.OOE+ 01 O.OOE+01 O.OOE+01 Hf-181 8.02E+01 5.26E+04 7.09E+ 02 3,99E+ 00 3.34E+ 00 2.54E+ 00 O.OOE+ Ol O.OOE+ 01

'R Values inunits of mrem/yr per pCi/me for inhalation and tritium and inunits of mrem/yr per pCi/seo per m'~ for all others.

3-45

Shearon Harris Nuclear Power P1ant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3 3 13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY = Goat Milk GROUP ~ Teen JQdmqr Xhtrraid H-3 2.04E+ 03 2.04E+03 O.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 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+Ol Cr-51 3.63E+03 6.10E+05 O.OOE+01 O.OOE+ 01 7.95E+02 2.02E+03 5.18E+03 O.OOE+Ol Mn-54 2.03E+05 2.10E+06 O.OOE+01 1.02E+06 3.05E+05 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Fe-59 3.63E+05 2.22E+06 4.03E+05 9.40E+05 O.OOE+01 O.OOE+Ol 2.96E+ 05 O.OOE+ 01 Co-58 1.30E+ 06 7.80E+ 08 O.OOE+ 01 5.66E+ 05 O.OOE+ Ol O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Co.60 4.66E+06 2.69E+07 O.OOE+Ol 2.07E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 2n-65 . 2.86E+08 2.60E+08 1.77E+08 6.13E+08 3.93E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 1.66E+08 5.24E+07 O,OOE+01 3.54E+08 O.OOE+Ol O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 9.65E+07 4.01E+08 3.37E+09 O.OOE+01 O.OOE+Ol O.OOE+ 01 O.OOE+01 O.OOE+01 Sr-90 2.27E+ 10 2.58E+09 9.18E+ 10 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+01 O.OOE+01 Y-91 3.02E+01, 4.62E+05 1.13E+03 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 2.56E+01 8.59E+04 1.18E+02 3.72E+01 5.47E+01 O.OOE+01 O.OOE+01 O.OOE+01 Nb.95 3.09E+ 03 2.40E+ 07 1.01E+ 04 5.62E+03 5.45E+03 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 5.58E+01 1.09E+04 1.30E+02 O.OOE+Ol 4.60E+02 O.OOE+01 O.OOE+01 O.OOE+01 RU-106 3.51E+ 02 1.34E+ 05 2.79E+ 03 O.OOE+ Ol 5.38E+ 03 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ag-110M 4.24E+06 1.96E+09 7.37E+06 6.97E+06 1.33E+07 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Sn-113 2.28E+05 2.58E+06 2.15E+05 9.06E+03 6.37E+03 2.97E+ 03 O.OOE+ 01 O.OOE+ 01 Sb-124 1.29E+06 6.67E+07 3.31E+06 6.10E+04 O.OOE+01 7.51E+ 03 2.89E+06 O.OOE+Ol Te-127M 8.87E+05 1.86E+07 7.46E+06 2.65E+ 06 3.02E+07 1.77E+06 O.OOE+01 O.OOE+01 Te-129M 1.36E+06 3.22E+07 8.58E+06 3.19E+06 3.59E+07 2.77E+ 06 O.OOE+01 O.OOE+01 I-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1.02E+09 1.73E+ 11 O.OOE+Ol O.OOE+01 I-132 2.19E+01 2.66E+01 2.33E+01 6.11E+Ol 9.62E+01 2.06E+ 01 O.OOE+01 O.OOE+01 I-133 2.99E+ 06 7.43E+ 08 5.79E+06 9.81E+06 1.72E+07 1.37E+09 O.OOE+ 0'I O.OOE+ 01 l-135 1.90E+ 04 5.83E+ 04 1.99E+ 04 5.13E+04 8.10E+04 3.30E+ 06 O.OOE+ 01 O.OOE+ 01 Cs-134 1.96E+10 5.26E+08 1.80E+10 4.23E+10 1.34E+10 O.OOE+ 01 5.13E+09 O.OOE+01 Cs-136 2.25E+09 2.69E+07 8.50E+08 3.34E+09 1.82E+09 O.OOE+ 01 2.87E+08 O.OOE+01 Cs-137 1.19E+ 10 4.85E+ 08 2.56E+ 1 0 3A1E+ 10 1.'I 6E+ 10 O.OOE+01 4.51E+ 09 O.OOE+01 Ba-140 2.39E+05 5.72E+06 3.71E+06 4.55E+03 1.54E+03 O.OOE+ 01 3.06E+ 03 O.OOE+01 Ce-141 4.91E+ 01 1.22E+06 6.40E+02 4.27E+02 2.01E+ 02 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Ce-144 2.55E+ 03 1.19E+ 07 4.74E+04 1.96E+04 1.17E+ 04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Hf-181 1.41E+ 02 6.34E+04 1.27E+03 6.97E+00 5.80E+00 4.26E+00 O.OOE+01 O.OOE+01

'R Values in units of mrern/yr per pCi/ms for inhalation and tritium and in units of mrem/yr per /rCI/sec per m s for all others.

3-46

Shearon Harris Nuclear Power Plant QSHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Goat Milk GROUP m Child XJhufg QLIract JQdantr. Ihtrtaid H-3 3.23E+ 03 3.23E+ 03 O.OOE+ 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 O.OOE+01 O.OOE+ Ol O.OOE+ Ol O.OOE+ Ol Cr-51 7.40E+ 03 3.93E+05 O.OOE+ Ol O.OOE+ 01 1.12E+03 4.11E+ 03 7.50E+ 03 O.OOE+ 01 Mn-54 4.07E+05 1.28E+06 O.OOE+01 1.53E+06 4.29E+ 05 O.OOE+ 01 0.90E+ 01 O.OOE+ 01 Fe-59 7.52E+05 1.57E+ 06 9.34E+05 1.51E+06 O.OOE+ 01 O.OOE+01 4.38E+05 O.OOE+Ol Co-58 2.65E+ 06 5.05E+06 O.OOE+01 8.65E+05 O.OOE+01 O.OOE+01 O.OOE+ Ol O.OOE+ 01 Co-60 9.48E+ 06 1.78E+07 O.OOE+01 3.21E+06 O.OOE+01 O.OOE+ 01 O.OOE+01 O.OOE+01 Zn-65 5.74E+08 1.62E+08 3.47E+08 9.24E+ 08 5.82E+08 O.OOE+01 O.OOE+01 O.OOE+01 Rb-86 4.04E+08 4.22E+07 O.OOE+01 6.57E+ 08 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Sr-89 2.38E+08 3.23E+08 8.34E+09 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+01 Sr-90 3.93E+10 2.09E+ 09 1.55E+ 11 O.OOE+01 O.OOE+ Ol O.OOE+01 O.OOE+ 01 O.OOE+ 01 Y-91 . 7A5E+Ol . 3.71E+ 05 2.79E+ 03 O.OOE+01 0;OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 5.36E+ 01 6.28E+04 2.74E+ 02 6.02E+ 01 8.62E+ 01 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 6.37E+03 1.65E+07 2.29E+04 8.91E+03 8.37E+03 O.OOE+ 01 O.OOE+01 O.OOE+01 Ru-103 1.19E+02 7.98E+03 3.09E+02 O.OOE+ Ol 7.77E+ 02 O.OOE+ 01 O.OOE+ Ol O.OOE+ Ol Ru-106 8.56E+ 02 1.07E+ 05 6.86E+03 O.OOE+01 9.27E+03 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Ag-110M 8.63E+ 06 1.28E+ 09 1.60E+07 1.08E+07 2.01E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 4.61E+ 05 1.69E+06 4.22E+05 1.36E+04 9.38E+03 5.59E+03 O.OOE+01 O.OOE+ 01 Sb-'I 24 2.75E+06 4.91E+07 7.84E+06 1.02E+ 05 O.OOE+ 01 1.73E+04 4.35E+06 O.OOE+01 Te-127M 2.1 BE+ 06 1.49E+ 07 1.84E+07 4.95E+06 5.24E+ 07 4.40E+ 06 O.OOE+ Ol O.OOE+Ol Te-129M 3.28E+06 2.58E+07 2.12E+07 5.91E+ 06 6.21E+07 6.82E+ 08 O.OOE+01 O.OOE+01 I-131 5.85E+ 08 9.17E+ 07 1.02E+ 09 1.03E+ 09 1.69E+09 3.41E+ 11 O.OOE+ 01 O.OOE+ 01 1-132 4.67E+01 1.19E+00 5.52E+01 1.01E+00 1.55E+00 4.71E+01 O.OOE+01 O.OOE+01 l-133 6.58E+06 7.00E+08 1.41E+ 07 1.74E+07 2.90E+ 07 3.23E+ 09 O.OOE+01 O.OOE+01 I-135 4.01E+04 6.47E+04 4.72E+04 8.49E+04 1.30E+05 7.52E+ 06 O.OOE+ 01 O.OOE+ 01 Cs-134 1.43E+10 3.67E+08 4.14E+10 6.80E+10 2.11E+10 O.OOE+01 7.56E+ 09 O.OOE+ 01 Cs-136 3.41E+ 09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 0.06E+01 4.19E+08 O.OOE+Ol Cs-137 8.72E+ 09 3.70E+ 08 6.17E+10 5.91E+10 1.93E+ 10 O.OOE+ 01 6.93E+09 O.OOE+01 Ba-140 5.23E+05 4.54E+05 8.96E+06 7.85E+03 2.56E+ 03 O.OOE+ 01 4.68E+03 O.OOE+ 01 Ce-141 1 17E+02

~ 9.81E+05 1.53E+03 7.36E+ 02 3.45E+ 02 O.OOE+01 O.OOE+01 O.OOE+Ol C0-144 6.24E+ 03 9.55E+ 06 1.17E+05 3.66E+04 2.03E+ 04 O.OOE+01 O.OOE+ 01 O.OOE+Ol Hf-181 3.04E+02 4.99E+04 3.02E+03 1.17E+01 9.43E+00 9.88E+00 O.OOE+01 O.OOE+01 "R Values in units of mrem/yr per yCi/m'or inhalation and tritium and in units of mrem/yr per yCi/sec per m'~ for all others.

3-47

Shearon Harris Nuclear Power plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.1 5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Goat Milk AGE GROUP ~ Infant XJiadg QGt'tot JQdtuty Ihyraid H-3 4.90E+ 03 4.90E+03 O.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 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+ 01 Cr-51 1 17E+04

~ 3.42E+05 O.OOE+ 01 O.OOE+ 01 1.67E+ 03 7.65E+ 03 1.49E+ 04 O.OOE+ 01 Mn.54 6ASE+05 1.04E+06 O.OOE+01 2.84E+06 6.30E+05 O.OOE+01 O.OOE+ Ol O.OOE+ 01 Fe-59 1.20E+06 1.45E+06 1.74E+06 3.04E+06 O.OOE+01 O.OOE+01 9.00E+05 O.OOE+01 Co-58 4.31E+06 4.31E+06 O.OOE+01 1.73E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Co-60 1.55E+07 1.56E+07 O.OOE+01 6.56E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zn-65 ~ 7.36E+08 1.35E+09 4.66E+ 08 1.60E+09 7.74E+08 O.OOE+01 O.OOE+01 O.OOE+ 01 Rb-86 8.23E+08 4.26E+07 O.OOE+ 01 1.67E+09 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Sr-89 4.55E+ 08 3.26E+08 1.59E+ 10 O.OOE+ 01 O.OOE+01 O.OOE+ Ol O.OOE+01 O.OOE+ 01 Sr-90 4.30E+10 2.11E+09 1.69E+11 O.OOE+Ol O.OOE+01 O.OOE+Ol O.OOE+ 01 O.OOE+Ol Y-91 1.39E+02, 3.75E+05 5.23E+03 O.OOE+01 0;OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 8.41E+01 5.9OE+04 4.85E+02 1.19E+02 1.28E+02 O.OOE+01 O.OOE+01 O.OOE+01 Nb-95 1.02E+04 1.48E+07 4.27E+ 04 1.76E+ 04 1.26E+04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ru-103 2.09E+ 02 7.60E+ 03 6.25E+ 02 O.OOE+ 01 1.30E+ 03 O.OOE+ 01 O.OOE+ 01 O.OOE+01 Ru-106 1.77E+03 1.07E+05 1.41E+04 O.OOE+01 1.67E+04 O.OOE+01 O.OOE+01 O.OOE+01 Ag-110M 1.43E+07 1.12E+09 2.95E+07 2.16E+07 3.08E+07 O.OOE+01 O.OOE+01 O.OOE+01 Sn-113 6.66E+ 05 1.37E+06 6.46E+05 2.45E+04 1.32E+04 9.34E+03 O.OOE+01 O.OOE+01 Sb-124 4.68E+ 06 4.66E+07 1.51E+07 2.22E+05 O.OOE+01 4.01E+04 9.46E+06 O.OOE+01 Te-127M 4.51E+ 06 1.50E+07 3.72E+ 07 1.23E+07 9.16E+07 1.08E+07 O.OOE+01 O.OOE+01 Te-129M 6.69E+ 06 2.59E+07 4.34E+ 07 1.49E+07 1.09E+08 1.67E+07 O.OOE+01 O.OOE+01 1-131 1.11E+09 8.99E+07 2.14E+09 2.52E+09 2.94E+09 8.28E+11 O.OOE+01 O.OOE+01 1-132 8.28E+ 01 1.88E+00 1.15E+00 2.33E+00 2.59E+00 1.09E+02 O.OOE+01 O.OOE+01 I-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 5.08E+07 7.86E+09 O.OOE+ 01 O.OOE+ 01 I-135 7.11E+04 7.06E+04 9.81E+04 1.95E+05 2.17E+ 05 1.75E+07 O.OOE+ 01 O.OOE+ 01 Cs-134 1.26E+ 10 3.38E+ 08 6.68E+ 10 1.25E+ 11 3.21E+ 10 O.OOE+01 1.31E+ 10 O.OOE+ 01 Cs-136 4.11E+ 09 1.67E+08 3.75E+09 1.10E+10 4.39E+09 O.OOE+ 01 8.98E+08 O.OOE+01 Cs-137 8.17E+09 3.61E+08 9.85E+10 1.15E+11 3.10E+10 O.OOE+01 1.25E+ 10 O.OOE+01 Ba-140 9.50E+05 4.53E+06 1.84E+07 1.84E+04 4.38E+03 O.OOE+Ol 1.13E+04 O.OOE+ 01 Ce-141 2.24E+ 02 9.85E+ 05 3.13E+03 1.91E+03 5.88E+02 O.OOE+01 O.OOE+01 O.OOE+Ol Ce-144 9.39E+03 9.61E+06 1.67E+05 6.86E+04 2.77E+04 O.OOE+01 O.OOE+01 O.OOE+01 Hf-181 5.08E+ 02 4.72E+ 04 5.74E+ 03 2.71E+ 01 1.58E+ 01 2.30E+ 01 O.OOE+ 01 O.OOE+ Ol

'R Values in units of mrem/yr per yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/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 JRInay Xhyraid H-3 1.26E+03 1.26E+ 03 O.OOE+ 01 1.26f + 03 1.26E+ 03 1.26E+ 03 1.26E+03 1.26E+03 P-32 5.00E+04 8.63E+04 1.32E+06 7.70E+04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Cr-51 9.99E+ 01 3.32E+ 03 O.OOE+ 01 O.OOE+01 2.28E+01 5.94E+ 01 1.44E+04 O.OOE+01 Mn-54 6.29E+03 7.72E+04 O.OOE+01 3.95E+04 9.83E+03 O.OOE+ 01 1.40E+06 O.OOE+01 Fe.59 1.05E+04 1.88E+05 1.17E+04 2.77E+04 O.OOE+ 01 O.OOE+ 01 1.01E+06 O.OOE+Ol Co.58 2.07E+ 03 1.06E+05 O.OOE+01 1.58E+03 O.OOE+01 O.OOE+ 01 9.27E+05 O.OOE+01 Co-60 1.48E+04 2.84E+05 O.OOE+01 1.15E+04 O.OOE+01 O.OOE+01 5.96E+06 O.OOE+01 Zn-65 4.65E+04 5.34E+04 3.24E+04 1.03f+05 6.89E+04 O.OOE+Ol 8.63f + 05 O.OOE+01 Rb-86 5.89E+04 1.66E+04 O.OOE+01 1.35E+05 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+01 Sr-89 8.71E+03 3.49E+05 3.04E+05 O.OOE+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.OOE+Ol O.OOE+01 O.OOE+Ol 9.59E+06 0.00f +01 Y-91 1.24E+04 . 3.84E+05 4.62E+05 O.OOE+01. O.OOE+01 O.OOE+Ol 1.70E+06 O.OOE+01 Zr-95 2,32E+04 1.50E+05 1,07E+05 3 44E+04 5,41E+04 O.OOE+01 1.77E+06 O.OOE+01'.04E+05 Nb-95 4.20E+03 1.04E+05 1.41E+04 7.80E+03 7.72E+03 O.OOE+ 01 O.OOE+01 RLI~ 103 8.57E+02 1.10E+05 1.53E+03 O.OOE+01 5.82E+03 O.OOE+ 01 5.04E+ 05 O.OOE+ 01 Ru-106 8.71E+03 9.11E+05 6.90E+04 O.OOE+Ol 1.33E+05 O.OOE+01 9.35E+06 O.OOE+ 01 Ag-110M 5.94E+ 03 3.02E+05 1.08E+04 9.99E+03 1.97E+04 O.OOE+ 01 4.63E+ 06 O.OOE+ 01 Sn-113 6.48E+03 2.48E+04 6.86E+03 2.69E+02 1.97E+02 9.33E+01 2.99E+ 05 O.OOE+ 01 Sb-124 1.24E+04 4.06E+05 3.12E+04 5.88E+ 02 O.OOE+ 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 I-131 2.05E+04 6.27E+03 2.52E+ 04 3.57E+ 04 6.1 2E+ 04 1.19E+ 07 O.OOE+01 O.OOE+ 01 I-132 1.16E+03 4.06E+02 1.16E+03 3.25E+ 03 5.18E+ 03 1.14E+05 O.OOE+01 O.OOE+ 01 I-133 4.51E+03 8.87E+03 8.63E+03 1.48E+04 2.58E+ 04 2.15E+06 O.OOE+01 O.OOE+ 01 I-135 2.56E+03 5.24E+03 2.68E+03 6.97E+03 1.11E+04 4.47E+ 05 O.OOE+01 O.OOE+ 01 Cs-134 7.27E+ 05 1.04E+04 3.72E+05 8.47E+05 2.87E+ 05 O.OOE+ 01 9.75E+04 O.OOE+ 01 Cs-136 1.10E+ 05 1.17E+04 3.90E+04 1.46E+05 8.55E+04 O.OOE+01 1.20E+04 O.OOE+ 01 Cs-137 4.27E+05 8.39E+03 4.78E+05 6.20E+05 2.22E+05 O.OOE+Ol 7.51E+04 O.OOE+01 Ba-140 2.56E+03 2.18E+05 3.90E+04 4.90E+ 01 1.67E+Ol O.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 O.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 O.OOE+ 01 7.76E+ 06 O.OOE+ 01 Hf-181 5.1 6E+ 03 1.29E+05 4.56E+04 2.57E+ 02 2.15E+02 1.63E+02 5.99E+ 05 O.OOE+ 01

'R Values in units of mrem/yr per pCi/me for inhalation and tritium and in units of mrem/yr per pCi/sec per ms 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'GE PATHWAY ~ Inhal GROUP ~ Teen XJhuiy. JQrhtey IhyraitL H-3 1.27E+ 03 1.27E+03 O.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 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Cr-51 1.35E+02 3.00E+03 O.OOE+01 O.OOE+01 3.07E+01 7.49E+01 2.09E+04 O.OOE+01 Mn-54 8.39E+ 03 6.67E+ 04 O.OOE+ 01 5.10E+ 04 1.27E+04 O.OOE+ 01 1.98E+06 O.OOE+Ol Fe-59 1.43E+ 04 1.78E+05 1.59E+ 04 3.69E+ 04 O.OOE+01 O.OOE+ 01 1.53E+06 O.OOE+ Ol Co-58 2.77E+ 03 9.51E+04 O.OOE+01 2.07E+03 O.OOE+Ol O.OOE+01 1.34E+06 O.OOE+ Ol Co-60 1.98E+ 04 2.59E+05 O.OOE+01 1.51E+04 O.OOE+01 O.OOE+01 8.71E+ 06 O.OOE+ 01 Zn 6.23E+ 04 4.66E+ 04 3.85E+04 1.33E+05 8.63E+04 O.OOE+01 1.24E+06 O.OOE+01 Rb-86 8.39E+04 1.77E+04 O.OOE+01 1.90E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.25E+ 04 3.71E+ 05 4.34E+ 05 O.OOE+ 01 O.OOE+01 O.OOE+01 2Al E+06 O.OOE+ 01 Sr-90 6.67E+06 7.64E+05 1.08E+08 O.OOE+Ol O.OOE+01 O.OOE+ 01 1.65E+ 07 O.OOE+ 01 Y-91 1.77E+04, 4.08E+05 6.60E+05 O.OOE+01, O.OOE+01 O.OOE+01 2.93E+06 O.OOE+01 Zr-95 3.15E+04 1.49E+05 1.45E+05 4.58E+04 6.73E+04 O.OOE+01 2.68E+06 O.OOE+01 Nb-95 5.66E+03 9.67E+04 1.85E+04 1.03E+04 9.99E+03 O.OOE+01 7.50E+05 O.OOE+01 Ru-103 8.95E+ 02 1.09E+ 05 2.10E+ 03 O.OOE+ Ol 7.42E+ 03 O.OOE+ 01 7.82E+ 05 O.OOE+ 01 Ru-106 1.24E+04 9.59E+05 9.83E+04 O.OOE+Ol 1.90E+05 O.OOE+01 1.61E+07 O.OOE+Ol Ag-110M 7.98E+03 2.72E+05 1.38E+04 1.31E+04 2.50E+04 O.OOE+01 6.74E+06 O.OOE+01 Sn-113 8.68E+03 2.03E+04 8.19E+03 3.44E+02 2.45E+02 1.13E+02 4.27E+05 O.OOE+01 Sb-124 1.68E+04 3.98E+05 4.30E+04 7.94E+02 O.OOE+01 9.76E+01 3.85E+06 O.OOE+01 Te-127M 2.18E+03 1.59E+05 1.80E+04 8.15E+03 6.53E+04 4.38E+03 1.65E+06 O.OOE+01 Te-129M 2.24E+03 4.04E+05 1.39E+04 6.57E+03 5.18E+04 4.57E+ 03 1.97E+06 O.OOE+01 I-131 2.64E+04 6.48E+03 3.54E+04 4.90E+04 8.39E+04 1 A6E+ 07 O.OOE+ 01 O.OOE+ 01 I-132 1.57E+03 1.27E+03 1.59E+03 4.37E+03 6.91E+03 1.51E+05 O.OOE+ 01 O.OOE+ 01 I-133 6.21E+ 03 1.03E+ 04 1.21E+ 04 2.05E+ 04 3.59E+ 04 2.92E+06 O.OOE+ 01 O.OOE+ 01 I-135 3.48E+ 03 6.94E+ 03 3.69E+03 9.43E+03 1.49E+ 04 6.20E+05 O.OOE+01 O.OOE+Ol Cs-134 5.48E+ 05 9.75E+03 5.02E+ 05 1.1 3E+ 06 3.75E+ 05 O.OOE+ Ol 1.46E+ 05 O.OOE+ Ol Cs-136 1.37E+05 1.09E+ 04 5.14E+04 1.93E+05 1.10E+05 O.OOE+01 1.77E+04 O.OOE+01 Cs-137 3.11E+ 05 8.48E+ 03 6.69E+05 8.47E+05 3.04E+05 O.OOE+Ol 1.21E+05 O.OOE+01 Ba-140 3.51 E+ 03 2.28E+ 05 5.46E+04 6.69E+01 2.28E+Ol O.OOE+01 2.03E+06 O.OOE+01 C0-141 2.16E+03 1.26E+05 2.84E+04 1.89E+04 8.87E+03 O.OOE+ 01 6.13E+05 O.OOE+01 Ce-144 2.62E+ 05 8.63E+ 05 4.88E+ 06 2.02E+ 06 1.21E+ 06 O.OOE+ 01 1.33E+ 07 O.OOE+ 01 Hf-181 7.04E+03 1.20E+05 6.32E+04 3.48E+02 2.90E+02 2.12E+02 9.39E+05 O.OOE+01

'R Values in units of mrem/yr per /rCI/m'or inhalation end tritium end in units of rnrem/yr per pCi/sec per m'or ell 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'GE PATHWAY ~ Inhal GROUP ~ Child Xidnay IhyrouL H-3 1.12E+03 1.12E+ 03 O.OOE+ 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 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Cr-51 1.54E+02 1.08E+03 O.OOE+ 01 O.OOE+Ol 2.43E+01 8.53E+01 1.70E+04 O.OOE+01 Mn-54 9.50E+03 2.29E+04 O.OOE+Ol 4.29E+04 1.00E+04 O.OOE+01 1.57E+06 O.OOE+ 01 Fe-59 1.67E+04 7.06E+04 2.07E+04 3.34E+04 O.OOE+01 O.OOE+01 1.27E+ 06 O.OOE+01 Co-58 3.16E+03 3.43E+04 O.OOE+Ol 1.77E+03 O.OOE+01 O.OOE+01 1.10E+06 O.OOE+01 Co.60 2.26E+ 04 9.61E+ 04 O.OOE+ 01 1.31E+04 O.OOE+01 O.OOE+Ol 7.06E+06 O.OOE+01 Zn-65 7.02E+04 1.63E+ 04 4.25E+ 04 1.13E+05 7.13E+04 O.OOE+01 9.94E+05 O.OOE+01 Rb-86 1.14E+05 7.98E+ 03 O.OOE+01 1.98E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Sr-89 1.72E+04 1.67E+05 5.99E+05 O.OOE+Ol O.OOE+01 O.OOE+01 2.15E+06 O.OOE+01 Sr-90 6.43E+06 3.43E+05 1.01E+08 O.OOE+01 O.OOE+01 O.OOE+01 1.47E+07 O.OOE+Ol Y-91 2.43E+04 . 1.84E+05 9.13E+05 O.OOE+01 O.OOE+01 O.OOE+01 2.62E+06 O.OOE+01 Zr-95 3.69E+04 6.10E+04 1.90E+05 4.17E+04 5.95E+04 O.OOE+01 2.23E+06 O.OOE+01 Nb-95 6.54E+03 3.69E+04 2.35E+ 04 9.16E+03 8.61E+03 O.OOE+01 6.13E+05 O.OOE+01 Ru-103 1.07E+03 4A7E+04 2.79E+ 03 O.OOE+01 7.02E+03 O.OOE+01 6.61E+05 O.OOE+01 Ru-106 1.69E+04 4.29E+05 1.36E+05 O.OOE+01 1.84E+05 O.OOE+01 1.43E+07 O.OOE+01 Ag-110M 9.13E+03 1.00E+05 1.68E+04 1.14E+04 2.12E+04 O.OOE+Ol 5.47E+06 O.OOE+01 Sn-113 9.83E+03 7.45E+03 9.00E+ 03 2.91E+02 2.02E+02 1.19E+02 3.40E+05 O.OOE+01 Sb-124 2.00E+04 1.64E+05 5.73E+04 7.40E+02 O.OOE+01 1.26E+02 3.24E+06 O.OOE+01 Te-127M 3.01E+03 7.13E+04 2.48E+ 04 8.53E+03 6.35E+04 6.06E+03 1.48E+06 O.OOE+01 Te-129M 3.04E+ 03 1.81E+ 05 1.92E+04 6.84E+03 5.02E+04 6.32E+03 1.76E+06 O.OOE+01 I-131 2.72E+04 2.84E+03 4.80E+04 4.80E+04 7.87E+04 1.62E+07 O.OOE+ 01 O.OOE+ 01 1-132 1.87E+03 3.20E+03 2.11E+03 4.06E+03 6.24E+03 1.93E+05 O.OOE+ 01 O.OOE+ 01 1-133 7.68E+03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 3.84E+06 O.OOE+01 O.OOE+01 I-l 35 4.14E+03 4.43E+03 4.91E+03 8.72E+03 1.34E+04 7.91E+05 O.OOE+01 O.OOE+01 Cs-1 34 2.24E+ 05 3.84E+03 6.50E+ 05 1.01E+ 06 3.30E+05 O.OOE+01 1.21E+05 O.OOE+01 Cs-136 1.16E+ 05 4.17E+ 03 6.50E+ 04 1.71E+05 9.53E+ 04 0.0dE+01 1.45E+ 04 O.OOE+ 01 Cs-137 1.28E+05 3.61E+03 9.05E+05 8.24E+ 05 2.82E+ 05 O.OOE+ Ol 1.04E+ 05 O.OOE+ 01 Ba-140 4.32E+03 1.02E+05 7.39E+04 6.47E+01 2.11E+01 O.OOE+01 1.74E+ 06 O.OOE+ 01 Ce-141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+03 O.OOE+01 I'.43E+05 O.OOE+ 01 Ce-144 3.61E+05 3.88E+05 6.76E+06 2.11E+06 1.17E+06 O.OOE+01 1 ~ 19E+07 O.OOE+01 Hf-181 8.50E+ 03 5.31E+04 8.44E+ 04 3.28E+02 2.64E+ 02 2.76E+02 7.95E+ 05 O.OOE+ 01

'R Values inunits of mrern/yr per/rCI/m~ for inhalation and tritium and in units of 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 TA8LE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Inhal GROUP ~ Infant JQdnay 'hyroirL H-3 6.46E+ 02 6.46E+02 O.OOE+01 6.46E+02 6.46E+02 6.46E+02 6A6E+02 6.46E+ 02 P-32 7.73E+ 04 1.61E+04 2.03E+06 1.12E+05 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Cr-51 8.93E+01 3.56E+02 O.OOE+01 O.OOE+01 1.32E+01 5.75E+01 1.28E+04 O.OOE+01 Mn-54 4.98E+03 7.05E+03 O.OOE+01 2.53E+04 4.98E+03 O.OOE+01 9.98E+ 05 O.OOE+01 Fe-59 9.46E+03 2.47E+04 1.35E+04 2.35E+04 O.OOE+Ol O.OOE+01 1.01E+ 06 O.OOE+ 01 Co.58 1.82E+03 1.11E+04 O.OOE+01 1.22E+03 O.OOE+01 O.OOE+01 7.76E+05 O.OOE+01 Co-60 1.18E+04 3.19E+04 O.OOE+01 8.01E+03 O.OOE+ Ol O.OOE+01 4.50E+06 O.OOE+ 01 Zn-65 ~ 3.10E+04 5.13E+04 1.93E+04 6.25E+04 3.24E+04 O.OOE+01 6.46E+05 O.OOE+01 Rb-86 8.81E+ 04 3.03E+03 O.OOE+01 1.90E+05 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-89 1.14E+04 6.39E+04 3.97E+05 O.OOE+Ol O.OOE+01 O.OOE+01 2.03E+06 O.OOE+01 Sr.90 2.59E+06 1.31E+05 4.08E+07 O.OOE+01 O.OOE+01 O.OOE+01 1.12E+07 O.OOE+01 Y-91 1.57E+04 . 7.02E+04 5.87E+05 O.OOE+01 O.OOE+01 O.OOE+01 2A5E+06 O.OOE+01 Zr-95 2.03E+04 2.17E+04 1.15E+05 2.78E+04 3.10E+04 O.OOE+01 1.75E+06 O.OOE+ 01 Nb-95 3.77E+03 1.27E+04 1.57E+04 6.42E+03 4.71E+03 O.OOE+01 4.78E+05 O.OOE+Ol Ru-103 6.78E+02 1.61E+04 2.01E+03 O.OOE+Ol 4.24E+03 O.OOE+01 '.51E+05 O.OOE+01 Ru-106 1.09E+04 1.64E+05 8.67E+04 O.OOE+ 01 1.06E+05 O.OOE+ 01 1.15E+ 07 O.OOE+01 Ag-110M 4.99E+03 3.30E+04 9.97E+03 7.21E+03 1.09E+04 O.OOE+ 01 3.66E+06 O.OOE+Ol Sn-113 4.89E+03 2.29E+03 4.67E+03 1.74E+02 9.94E+01 6.73E+01 2.30E+ 05 O.OOE+01 Sb-124 'l.20E+ 04 5.91E+04 3.79E+04 5.56E+02 O.OOE+01 1.00E+02 2.64E+ 06 O.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 O.OOE+ 01 Te-129M 2.22E+ 03 6.89E+04 1.41E+04 6.08E+ 03 3.17E+04 5.47E+03 1.68E+06 O.OOE+01 I-131 1.96E+04 1.06E+03 3.79E+04 4.43E+04 5.17E+04 1.48E+07 O.OOE+01 O.OOE+01 I-132 1.26E+ 03 1.90E+03 1.69E+03 3.54E+03 3.94E+03 1.69E+05 O.OOE+01 O.OOE+01 I-133 5.59E+03 2.15E+03 1.32E+04 1.92E+04 2.24E+04 3.55E+06 O.OOE+01 O.OOE+01 I-135 2.77E+03 1.83E+03 3.86E+03 7.59E+03 8.46E+03 6.95E+05 O.OOE+01 O.OOE+01 Cs-134 7.44E+04 1.33E+03 3.96E+05 7.02E+05 1.90E+05 O.OOE+01 7.95E+04 O.OOE+01 Cs-136 5.28E+04 1 A3E+ 03 4.82E+ 04 1.34E+ 05 5.63E+ 04 O.OOE+ 01 1.17E+ 04 O.OOE+01 Cs-137 4.54E+ 04 1.33E+03 5.48E+05 6.11E+ 05 1.72E+05 O.OOE+01 7.12E+ 04 O.OOE+Ol ea.140 2.89E+03 3.83E+04 5.59E+04 5.59E+ 01 1.34E+Ol O.OOE+01 1.59E+06 O.OOE+01 C0-141 1.99E+03 2.15E+04 2.77E+04 1.66E+04 5.24E+03 O.OOE+01 5.16E+05 O.OOE+01 Ce-144 1.76E+05 1.48E+05 3.19E+06 1.21E+ 06 5.37E+05 O.OOE+Ol 9.83E+06 O.OOE+ 01 Hf-181 5.05E+ 03 1.90E+ 04 5.65E+ 04 2.66E+ 02 1.59E+02 2.25E+02 6.73E+05 O.OOE+01

'R Values in units of mrem/yr per yCI/m~ for inhalation and tritium and in units of mrem/yr per yCi/sec per m'or all others.

3-52

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 3.1 SHNPP Gaseous Waste Streams Turbine Bldg Vent Stack 3A Rnt Rs4iauoa rmooai Sfoaxor NS VVe4yoocooiaINS RAR. RooiooxoaiUoor RQS atfa rais ~RQI WRCM4'llonaofo Oaovoaxor RXSSIIV4QI Condenser Vaclxn Pump .

Condenser Polisher Area WPB Vent Stack 5 WPS Hot S Cold Laundry WPB Dtrice Area Exhaust WPS Cold Laundry Dryer!

WPB Control Roon Smoke Exhaust WPB Nlice Areas WPB General Area Exhaust WPB Chiller Room Exhaust Waste Gas Decay Tanks Waste Pfocessing Afea Fillefed Exhaust WPB Vent Stack 5A WPB Swttchgev Room ExhauN WPB HVAC Equip. Room Exhaust WPB Personnel Handeting Facility Exhaust WPB Hot C txnv ActivityLabs Exhaust WPB Lsb Areas Exhaust Plant Vent Stack 1 RAAIIAYanslxlrrrsorI

~lsvasns RM REM RrssIAYJQIIA Containment PreEntry Purge RtQAAY4QI Rlg Normal Exhaust North RAB Normal Exhaust RS Normal Exhaust South RXSSIAY4QIA Rxxslrsasu RAB Emergency Exhaust RXSSIAY4QIR FHB Normal Exhaust(Oper. Fl) South RXISIIWQI RAB Ventilation System FHB Normal Exhaust (Oper. R) North Hydrogen Purge RAB Smoke Purge RS Emergency Exhaust RAB Purge 3-53

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PARKING AREA 33 CD 0 WARE XO O~ CD GI HOUSE ~ CI Ol CD U

O SWITCHYARO tV'O OARICINO AREA

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 Ventstack - 3A.

Wide Range Caa Monsor (WRCM)

RM RM 1TV4ddd.t Gland Steam Condenser CVPETS

Main Condenser REM REM.1TV4$ S4 Hogging Valve Atmosphere 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-S provides a legend for Figures 4 1-2 through 4.1-4.

~

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 da s ~

Analysis Frequency and Weekly Gross Beta~

Required Analysis: Weekly I-131 (charcoal canisters)

Quarterly Gamma Isotopic'~ (Composited b location)

'Sample Point ID No. Sam le Point, Descri tion', Distance, and Direction 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2. 6 mi. from site.

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

NNE sector, 1.4 mi. from site.

0.7 mi. N on SR 1127 from intersection with US l.

NNE sector, 3.1 mi. from site.

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

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: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once er uarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description', Distance, and Direction 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2.6 mi. from site.

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

NNE sector, 1.4 mi. from site.

HE&EC ENE sector, 2.6 mi. from site.

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

Pittsboro (Contxol Station)'NW sector from site, > 12 mi. from site Intersection of SR 1134 6 SR 1135.

NE sector, 0.8 mi. from site.

Extension of SR 1134.

E sector 0.7 mi, from site.

Dead end of road. Extension of SR 1134.

ESE sector, 0.6 mi. from site.

1 mi. S on SR 1130 from intersection of SR 1127, 1115, and 1130 sector, 2.2 mi. fxom site.

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

SSE sector, 2.2 mi. from site.

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.

SHNPP site. Access road to aux. reservoir.

W sector 1.5 mi. from site.

Shearon Harris Nuclear Power Plant (SHNpP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once er uarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Descri tion', 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 sector 1.9 mi. from site. 'NW 17 Intersection of US 1 and Aux. Res.

NW sector, 1.5 mi. from site.

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.

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 Harris Lake Spillway S sector, 4.7 mi. from site 27 NC 42 8 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 Neste Resins Corporation on SR 1916.

WSW sector 5.7 mi. from site.

Shearon Harris Nuclear power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure -Pathwa and/or Sam le: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once er uarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ZD No. Sam le Point, Descri tion', 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.'R 32 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.

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.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathwa and/or Sam le: Waterborne, Surface Water Sampling and Collection Fzequency: Composite sample collected over a period of less than or equal to 31 da s ~

Analysis Frequency and Required Analysis: Monthly Gross Beta'nd Quarterly Gamma Isotopic Sample Point ID No. Sam le Point, Descri tion', Distance, and Direction 26 Harris Lake spillway S sector, 4.7 mi., from site 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)~

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.

Shearon Harris Nuclear power plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4 '

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathwa and/or Sam le: Waterborne, Groundwater Samplin and Collection Fre uenc : Grab sample collected uarterly Analysis Frequency and Required Analysis: Each Sample Gamma Zsotopic'nd Tritium Sample Point ZD No. Sam le Point, Description', Distance, and Direction 39 On-site deep well in the vicinity of the diabase dike SSW sector, 0.7 m'. from site 57 SHNPP Site N. bank of Emergency'ervice Water (ESW) intake channel, S. of Water Treatment Building.

SSW sector, 0.4 mi. from site 58 SHNPP Site N. bank of Emergency Service Water (ESW) intake channel, S. of Water Treatment Building.

WSW sector, 0.5 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

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, Drinkin Water Sampling and Collection Frequency: Composite sample collected over a two-week period if I-131 analysis is performed; monthly composite otherwise.

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

Monthly Gross Beta Monthly Gamma Tritium Isotopic'uarterly Sample Point ID No. Sam le Point, Descri tion', Distance, and Direction 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)~

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.

SHNPP Water Treatment Building On Site NOTE: I-131 analysis is normally performed weekly on these samples.

H-3 analysis is normally performed monthly.

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathwa and/or Sam le: Waterborne, Sediment from Shoreline Sampling and Collection Frequency: shoreline Sediment sample collected semiannuall Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic'ample Point ZD No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.6 mi. from site Shoreline of Mixing Zone of Cooling Tower Blowdown Line S'ector, 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 semiannuall Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic'ample Point ID No. Sam le Point, Descri tion', 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathwa and/or Sample: Zn estion Milk Sampling and Collection Frequency: Grab samples semi-monthly when animals are on pasture; monthly at other times.

Analysis Frequency and Required Analysis: Each Sample Z-131 Each Sample Gamma Zsotopic'ample Point ZD No. Sample Point, D'escription', Distance, and Direction Maple Knoll Dairy on SR 1403 SSE sector, 7.0 mi. from site:.

43 Goodwin's Dairy on SR 1134 N sector, 2.2 mi. from site is no ion er in business Stroud's Dairy, Pittsboro (Control Station)'W 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 Ex osure Pathwa and/or Sample: Ingestion Fish Sampling and Collection Frequency: One sample of each of the following semiannually:

Catfish (bottom feeders)

2. Sunfish & Largemouth Bass (free swimmers)

Analysis Frequency and Required Analysis: Each sample Gamma Isotopic'n edible portion for each Sample Point ID No. Sample Point, Descri tion', Distance, and Direction Site varies within the Harris Lake.

Site varies above Buckhorn Dam on Cape Fear River (Control Station)~

4-12

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathwa and/or Sam le: In estion Food Products~

Sampling and Collection Frequency: Samples of 3 different kinds of broadleaf vegetation monthly during the rowin season Analysis Frequency and Required Analysis: Each sample Gamma Isotopic'n edible portion for each Sample Point ID No. Sam le Point, Description', Distance, and Direction Pittsbozo (Control Station)'NW sector, > 12 mi. from.site SR 1189. Gunter-Morris Rd.

NNE sector, 1.7 mi. from site.

55 SR 1167, Bonsai NNN sector, 2.0 mi. from site 62 SR 1127, 0. 4 m. W of SR 1134 NE sector, 2.3 mi. from site SR1127, 3/4 miles S of HEEC ENE Sector, 1.8 miles from site 4-13

Shearon Harris Nucleaz Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathwa and/or Sam le: A uatic Ve etation Samplin and Collection Fre uenc : Annuall Analysis Frequency and Required Analysis: Each sample Gamma Isotopic'ample Point ID No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 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

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 NOTES TO TABLE 4.1 SHNPP Radiolo ical Environmental Monitorin Pro ram 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.

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. Zf 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) aze 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 indicat'or stations.

Gamma isotopic analysis means the identification and quantitation of gamma-emitting zadionuclides 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.

4-15

Shearon Harris Nuclear Power Plant. (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-1 SHNPP Exclusion Boundary Plan 0

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

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~r'igure 4.1-2 Environmental Radiological Sampling Points

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Shearon Harris Nuclear Power Plant (sHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-3 Environmental Radiological Sampling Points

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~ o Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Rev. 6 Offsite Dose Calculation Manual (ODCM)

Figure 4.1-4 Environmental Radiological Sampling Points

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4-19

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 4.1-5 Environmental Radiological Sampling Points STATION REFER TO STATION REFER. TO NUMBER SAMPLE TYPE FIGURE NUMBER SAMPLE TYPE FIGURE AP,AC, TL 4.1-4 TL 4.1-3 AP, AC, TL 4.1-4 35 TL 4.1-3 TL 4.1-4 36 TL 4.1-3 AP,AC, TL 4'.1-4 37 TL 4.1-3 AP, AC, MK, FC, TL 4.1-2 38 SW, DW 4.1-2 TL '.1-4 39 GW 4.1-4 TL 4.1-4 40 SW, DW 4.1-3 TL 4.1-4 41 SS, AV '.1-4 TL 4.1-4 42 MK 4.1-3 10 TL 4.1-4 43 DELETED 4.1-4 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 TL 4.1-3 53 TL 4.1-2 20 TL 4.1-3, 4.1-4 54 FC 4.1-4 21 TL 4.1-3 55 FC 4.1-4 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. 58 GW 4.1-4 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 62 FC 4.1-4 29 TL 4.1-2 63 TL 4.1-4 30 TL 4.1-2 64 FC 4.1-4 31 TL 4.1-2 32 TL 4.1-2 33 TL 4.1-3 AC Air Cartridge FC Food Crop SD Bottom Sediment AP Air Particulate FH Fish SS Shoreline Sediment AV Aquatic Vegetation GW Groundwater SW Surface Water DW Drinkin Water MK Milk TL TLD

'pproximate location 4-20

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 5.0 INTERLABORATORY COMPARISON STUDIES The objective of this program is to evaluate the total laboratory analysxs process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.

Environmental samples from the SHNPP environs aze to be analyzed by the Harris Energy & Environmental Center (HE&EC) or by a qualified contracting laboratory. These laboratories will paztzcipate at least annually in a nationally recognized interlaboratory comparison study.

The results of the laboratories'erformances 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 foz gamma-emitting zadionuclides in effluent releases. The E&RC radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study. Radhochemical analyses of composite samples required by ODCM Operational Requirements Tables 4.11-1 and 4.11-2 will be performed by the HE&EC.

If the CP&L laboratory or vendor laboratory results lie at greater than three standard deviations from the "recognized value," an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation on the evaluation will be available to SHNPP and will be provided to the NRC upon request.

Shearon Harris Nuclear Power plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)

ODCM Operational Requizement 3.11.4 requires that the annual dose oz 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. Zn addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radxation, and any other nearby uranium fuel cycle sources are required by ODCM Operational Requirement, Appendix F, Section F,2 to show conformance with 40 CFR 190 limits ~ The results of the dose assessments are submitted with the Radioactive Effluent Release Report.

If a dose assessment is made as a requirement of ODCM Operational Requirement 3.11.4, the calculation will include a complete statement of the assumptions and parameters used in calculating the dose for the report.

6.1 Dose to the Likel Most Ex osed Member of the Public 6.1.1 Effluent Pathwa s The ODCM dose equations for noble gases, iodines, particulates, and tritium provide conservative estimates because the X/Q and D/Q are historical values for the exclusion boundary distances. Because these distances are fixed and represents the closest points in the unrestricted areas to the plant, it assures that 10 CFR 50 Appendix I doses to a member of the public are unlikely to be substantially underestimated.

More realistic estimates of the actual doses 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 ZZ and GASPAR. These permit use of current annual average meteorology X/Q and D/Q values'derived from the NRC XOQDOQ (NUREG/CR-2919) Code appropriate for the specific location of the receptor and the applicable exposure pathways.

6.1.2 Direct Radiation 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 maternal, 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, pze-operational TLD measurements using methods contained in NBS Handbook 91, "Experimental Statistics," to determine any significant contribution from direct radiation associated with plant operation.

Zf 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 .ZZ and GASPAR.

6-1

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 6.2 Dose to a Member of the Public Due to Activities Within the Site

~aun ar 'I The Annual Radioactive Effluent Release Report shall include assess-ments of the radiation doses to members of the public due to activities within the site boundary. The Harris Lake is generally available for public recreational purposes year-round, and certain areas are within the site boundary (Figure 4.1-4).

LADTAP XZ and GASPAR allow the calculation of doses for special cases.

The assumptions used in the calculations, e.g., exposure time, location, and activity, will be included in the Radioactive Effluent Release Report.

6-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 6.10.3.p. 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.

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

Ce 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) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 3 APPENDIX A Carolina Power & Light Company (CP&L) has performed the assessment of the transport and dzspersion of the effluent in the atmosphere as outlined in Pze aration of Radiolo ical Effluent Technical 1978) .

S ecifications or uc ear ower an s, e me o o ogy or xs assessmen was based on guidelines presented 1 (USNRC, 1977).

in Regulatory Guide 1 111, Revision relative The results of depositions flux and

~

the assessment were to provide the 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 deposztion flux and concentrations. These aze (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable and trajectory model based on the statistical approach to diffusion),

(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 Com uter Pro ram for the Meteorolo ical Evaluation of Routine EZX:quent e eases a uc ear ower a mons, I ep e er wou e use or 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.

Shearon Harris Nuclear power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Sheet 2 of 3 APPENDIX A A twelve-year record of meteorological data was used from the on-s'ite meteorological program at the Shearon Harris Plant. These meter data consisted of all collected parameters from the normal 10.0 tower description of the model used and level for the years 1976-1987. TheNUREG/CRC-2919.

the computations aze presented in 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 zadioiodines and particulates.

Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for round 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 foz 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) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 3 of 3 APPENDIX A The NRC "XOQDOQ" Program (Version 2.0) was obtained and installed. on the CP&L computer system. For routine meteorological dispersion evaluations, the "XOQDOQ" Program will be run with the appropriate physical plant data, appropriate meteorological informatxon 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 GROUHD-LEVEL HISTORICAL DATA, 1976-1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-'1987 CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF IHTEREST Z&dLL X/Q MLI~'/Q Zdzh X/Q M D!Kh-4 D/Q (sec/m3) (sec/m3) (sec/m3) (per m2)

RELEASE TYPE OF DIRECTION DISTANCE NO DECAY 2.3 d DECAY 8.0 d DECAY A SITE BOUNDARY S 1.36 2189. 6.1E 06 .9E 06 .2E-06 8.86-09 A SITE BOUNDARY SS'M 1.33 2140. 6.0E-06 5.8E-06 5.1E-06 8.?E.09 A SITE BOUHDARY SW 1.33 2140. 5.5E-06 5.4E-06 4 'E-06 7.0E-09 A SITE BOUHDARY WSW 1.33 2140. 4.8E-06 4.7E-06 4, 1E-06 5.4E-09 A SITE BOUHDARY 'W 1.33 2140. 3.6E-06 3.6E-06 3.1E-06 4.1E-09 A SITE BOUNDARY WHM 1.33 2140. 2.8E-06 2.7E.06 2.4E 06 3.3E-09 A SITE BOUNDARY NM 1.26 2028. 2.9E-06 2.8E.06 2.5E 06 3.9E-09 A SITE BOUHDARY HHW 1.26 2028. 3.3E-06 3 'E.06 2.8E.06 5 'E-09 A SiTE BOUNDARY H 1.32 2124. 3.8E.06 3.8E-06 3.3E.06 6.6E-09 A SITE BOUNDARY HHE 1.33 2140 ~ 4 'E.06 4.0E-06 3.5E-06 7.9E-09 A SITE BOUNDARY HE ~ 1.33 2140. 3.2E.06 3.2E-06 2.7E-06 7.3E.09 A SITE BOUHDARY EHE 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 BOUHDARY ESE 1.33 2140. 1.8E-06 1.7E.06 1.5E-06 4.0E 09 A SITE BOUNDARY SE 1.33 2140. 2.16.06 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 S'M 2.80 4506. 1.3E-06 1.2E-06 1.0E-06 1.2E.09 A HEAREST RESIDENT WSW 4.30 6920. 5.4E-07, S.OE-07 4.0E-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 2.10 3380. 1.1E-06 1 ~ 1E.06 9.1E-07 1.'IE 09 A NEAREST RESIDENT NW 1.80 2897. 1.4E-06 1.3E-06 1.1E-06 1.6E-09 A NEAREST RESIDENT HHW 1.50 2414. 2.2E-06 2.2E-06 1.9E-06 3.3E-09 A NEAREST RESIDENT N 2.20 3540. 1 'E-06 1.3E-06 1.1E-06 1.9E.09 A NEAREST RESIDENT HHE 1.70 2736. 2.4E-06 2.4E-06 2.0E-06 4.3E-09 A

A HEAREST RESIDENT NEAREST RESIDENT NE EHE 2 '0 2.00 3701.

3219.

F 06-06 1.0E-06 1.0E-06 1.0E-06 8.5E-07 8.5E-07 1.9E-09 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 'E-07 7.3E-10 A HEAREST 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 SSM 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 S.OE.07 4.0E-07 3.4E-10 A GARDEN W 3.00 4828. 7.6E-07 7.2E-07 6.0E-07 5.7E-10 A GARDEN 'MNW 2.10 3380. 1.1E-06 1.1E-06 9.1E-07 1.1E-09 A GARDEN N'W 3.80 6116. 3.5E-07 3.3E.07 2.6E-07 2.8E-10 A GARDEN NNW 1.90 3058. 1.4E-06 1.4E.06 1.1E-06 1.8E-09 A GARDEN H 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A GARDEN HHE 1.70 2736. 2.4E-06 2.4E.06 2.0E-06 4.3E-09 A GARDEN HE 2.30 3701. 1.0E-06 1.0E 06 8 'E-07 1.9E-09 A GARDEN E 4.70 7564. 1.8E-07 1.7E-07 1.3E 07 2.0E-10 A GARDEN ESE 2.80 4506. 4.0E-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 HILK N 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A COW HILK HHE 2.92 4703. 8.5E-07 8.2E-07 6.7E-07 1.2E-09 A HEAT & POULTRY SSW 4.40 7081. 6.3E-07 5.9E-07 4.7E-07 5.2E-10 A HEAT & POULTRY SW 2.80 4506. 1.3E.06 1.2E-06 1.0E-06 1 '6-09 A HEAT & POULTRY 'WSW 4.30 6920. 5 'E-07 5.0E-07 4.0E-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 '116.

3.5E-07 3 'E-07 2.6E-07 2.8E-10 A HEAT & POULTRY NNW 1.90 3058. 1.4E-06 1.4E-06 1.1E-06 'I.BE 09 A HEAT & POULTRY N 2.20 3540. 1.4E-06 1.3E.06 1.1E-06 1.9E-09 A HEAT & 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 1.0E-06 8.5E-07 1.9E-09 A HEAT & POULTRY ENE 2.00 3219. 1.0E-06 1.0E-06 8.5E.07 2.3E-09 A HEAT & POULTRY E 4.60 7403. 1.8E-07 1.7E-07 1.4E 07 2.1E-10 A HEAT & POULTRY ESE 4.40 7081. 1.8E 07 1.7E-07 1.3E 07 2.4E-10

TABLE A-5 0 lh th K th e Undepleted, No Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') rt 0 O

ax 0

EXIT OHE -- GROUND-LEVEL HISTORICAL DATA, 'l976-'l987 N III NO DECAY, UHDEPLETED I CORRECTED USING STANDARD OPEN TERRAIN FACTORS n rn I

S ANNUAL AVERAGE 1.720E-04 CHI/O (SEC/HETER CUBED) 5.121E 05 2.531E-05 1.246E-OS DISTANCE IN IIILES FRDH THE SITE 0

4.943E-06 2.814E-06 1.851E-06 1.330E-06 1.015E-06 8.077E-07 6.637E-07 rr n r.

c n 8

SSM 1.571E-04 4.715E-05 2.346E-05 1.158E-05 4.596E-06 2.607E-06 1.711E-06 1.227E-06 9.341E-07 7.424E-07 6.093E-OT r 0

g SM 1.481E-04 4.412E-05 2.182E-05 1.074E-05 4.263E-06 2.428E-06 'I'97E-06 1. 148E-06 8.757E-07 6.971E-OT 5.728E-07

'MSM 1.295E-04 3.842E-05 1.893E-OS 9.308E-06 3.693E-06 2.108E-06 'I.389E-06 9.995E-07 7.632E-07 6.080E-07 4.999E-OT 0 M 9-839E-05 2.921E-05 1.440E-05 7.087E-06 2.814E-06 1.605E-06 1.057E-06 7.608E-07 5.808E-07 4.626E-07 3.803E-07 Z8 S

'MNM 7.430E-05 2.216E-05 1.098E-05 5.420E-06 2.154E-06 1.225E-06 8.053E-OT 5.784E-07 4.409E-07 3.508E-07 2.881E-07 C

HM 6.636E-05 1.996E-05 9.994E-06 4.967E-06 1.982E-06 1.121E-06 7.339E-OT 5.254E-07 3.995E-07 3.171E-07 2 '99E-07 NHII 7.179E-05 2.185E-05 '1.111E-05 5.570E-06 2.234E-06 1.254E-06 8.166E-07 5.820E-07 4.409E-07 3.489E-07 2.853E-07 H 9.224E-05 2.824E-05 1.448E-05 7.277E-06 2.919E-06 1.633E-06 1.060E-06 7.539E-07 5.701E-07 4.505E-07 3.678E-07 HHE 9.847E-05 3.034E-05 1 '60E-05 7.846E-06 3.145E-06 1.754E-06 1 '37E-06 8.070E-07 6.094E-07 4.810E-07 3.923E-07 0 rt HE 7.892E-05 2.430E-05 1.240E-05 6.194E-06 2.467E-06 1.376E-06 8.918E-OT 6.333E-07 4.784E-07 3.777E-07 3.081E-07 a~

Q EHE 5.998E-05 1.845E-05 9.388E-06 4.679E-06 1.860E-06 1.036E-06 6.71'IE-07 4.764E 07 3.597E-07 2.839E-07 2.316E-OT 3,'M E 4.903E-05 1.498E-05 7.585E-06 3.779E-06 1.506E-06 8.439E-07 5.488E-07 3.908E-07 2.959E-07 2.341E-OT 1.913E-07 '2a ESE 4.458E-05 1.361E-05 6.872E-06 3.417E-06 1.359E-06 7.616E-07 4.952E-07 3.527E-07 2.670E-07 2.112E-07 1.726E-07 tg I Ig SE 5.351E-05 1.632E-05 8.255E-06 4 '02E-06 1.629E-06 9.123E-07 5.929E-OT 4.221E-07 3.195E-07 2.526E-07 2.064E-07 SSE 9.101E-05 2.734E-05 1.361E-05 6.718E-06 2.666E-06 1.509E-06 9.885E-07 7.081E-07 5.387E-07 4.278E-07 3 '09E-07 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH MILES FROH THE SITE 0 0 S 5.589E-07 3.064E-OT 2.075E-07 1.263E-07 8.904E-OB 6.T99E-OB 5.459E-OB 4.537E-OS 3.867E-OB 3.360E-OB 2.964E-OB SS'M 5.126E-OT 2.798E-07 1.890E-07 1.147E-07 8.066E-OB 6. 149E-08 4.930E-OB 4.093E-OB 3.485E-OS 3.026E-OS 2.667E-OS SII 4.824E-07 2.645E-OT 1.791E-OT 1.090E-07 7.686E-OS 5.869E-OB 4.712E-OB 3.916E-OB 3.338E-OB 2.900E-OS 2.558E-OB MSM 4.213E-07 2.315E-07 1.570E-07 9.574E-OB 6.758E-OS 5.165E-OB 4.150E-OS 3.451E-OS 2.943E-OB 2.558E-OB 2.257E-OB M 3.205E-OT 1.760E-07 1.193E-07 7.275E-OS 5 '33E-08 3.922E-OS 3.151E-OS 2.620E-OS 2.234E-OB 1.941E-OB 1. 713E-08 RIM 2.426E-07 1.328E-07 8.985E-OS . 5.463E-OB 3.849E-DB 2.937E-OB 2.357E-OS 1.958E-OS 1.668E-OB 1.449E-OB 1 '78E-08 NII 2.185E-07 1.188E-07 8.005E-OB 4.839E-OB 3.396E-OS 2.584E-OS 2.069E-OS 1.716E-OS 1.460E-OS 1.266E-OB 1 '15E-08 HNM 2.392E-07 1.290E-07 8.639E-OS 5 '81E-08 3.6'ITE-08 2.741E-OS 2.187E-OS 1.809E-OS 1.535E-OB 1.329E-OB 1.168E-OS H 3.081E-07 1.654E-07 1.105E-07 6.603E-OB 4.597E-OB 3.478E-OS 2.771E-OB 2.289E-OB 1.940E-OB 1.678E-OB 1.474E-OS HHE 3.283E-OT 1.75SE-07 1 ~ 171E-07 6.980E-OS 4.852E-OB 3.665E-OB 2.918E-OB 2.40SE-OB 2.040E-OS 1.763E-DB 1 '48E-08 HE 2.579E-07 1.383E-OT 9.230E-08 5.512E-OS 3.839E-OB 2.904E-OS 2.315E-OS 1.912E-OB 1.622E-OB 1..403E-OS 1.232E-DB EHE 1.938E-07 1.039E-OT 6.935E-OB 4.142E-OS 2.886E-OB 2.184E-OB 1.741E-OS 1.439E-OB 1.220E-OS 1.056E-OB 9.278E-09 E 1.604E-07 8.645E-OS 5".789E-08 3.473E-OB 2.426E-OB 1.840E-OB 1.469E-OS 1.215E-OB 1.032E-OB 8.935E-09 7.858E-09 ESE 1.447E-OT 7.804E-OS 5.228E-OB 3. 139E-08 2. 193E-08 1.664E-OS 1.329E-OB 1 ~ 100E-08 9.341E-09 8.091E-09 7. 117E-09 SE 1.730E-07 9.328E-OB 6.248E-OS 3.750E-OS 2.620E-OB 1.988E-OB 1.588E-OS 1.314E-OB 1.116E-OB 9.665E-09 8.501E-09 SSE 2.950E-07 1.608E-07 1.085E-07 6.575E-OS 4.622E-OB 3.522E-OS 2.823E-OB 2.343E-OB 1.995E-OS 1.732E-OS 1.526E;08 PQ N

0 4 r Ch Ul

TABLE A-6 o ol

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

lh Qt

r. ~

N 0 (P

EXIT OHE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 tI 0 fU X

NO DECAY, UNDEPLETED N lD CHI/O (SEC/HETER CUBED) FOR EACH SEGHENT n tn rg n c DIRECTION S 2.535E-05 5.667E.06 1.900E-06 SEGHENT BOUNDARIES 1.026E-06 6.676E-O?

IN HILES FROH THE 3.185E-07 SITE 1.278E.07 6.824E-OB 4.545E-OS 3.363E-OB rr C 0 lb SSM SM 2.344E-OS 2.185E-05 5.264E-06 4.887E-06 1.756E-06 1.639E-06 9.447E-07 8.855E-07 6.129E-07 5.761E-OT 2.912E-07 2.749E-OT 1.161E-O?

1.103E-O?

6.172E-OB 5.891E-OB 4.101E-OB 3.923E-OB 3 '29E-08 r0 g 2.903E-OB IISM 1.899E-05 4.236E-06 1.425E-06 7.715E-OT 5.028E-07 2.405E-07 9.683E-OB 5.184E-OB 3;457E-OB 2.560E-OS 0 M 1.444E-05 3.226E-06 1.085E-06 5.872E-07 3.826E-07 1.829E-07 7.358E-OB 3.937E-DB 2.624E-OS 1.943E-OS Z 89 MNM 1.099E-05 2.46?E-06 8.265E-07 4.459E-07 2.898E-07 1.381E-07 5.528E-OS 2.948E-OB 1.962E-OB 1.451E-OS NM 9.975E-06 2.263E-06 7.538E-07 4.041E-07 2.615E-07 1.237E-07 4.902E-OS 2.595E.OB 1.719E-OB 1 ~ 267E-08 NHII N

1.103E-05 1.434E-05 2.540E-06 3.316E-06 8.395E-07 1.090E-06 4.462E-07 5.771E-07 2.871E"07 3.702E-07 1.345E-07 1.727E-07 5.254E-OS 6.700E-OB 2.753E-OB 3.494E-OS 1.813E-OB 2.294E-OB 1.330E-OB 1.680E-OB r l Ql NNE 1.543E-05 3.572E-06 1.169E-06 6.169E-07 3.949E-07 1.836E-07 7.086E-OB 3.682E-OB 2.413E-OB 1.765E-OS 0 ft NE 1.229E-05 2.811E-06 9.176E-07 4.843E-OT 3.102E-07 1.445E-07 5.595E-OB 2.918E-OB 1.917E-OB 1.404E-OS tI n~

ENE 9.309E-06 2.120E-06 6-906E-07 3.642E-07 2.331E-07 1.085E-07 4.204E-OB 2.194E-OS 1.442E-OB 1.057E-OS Q N 7.536E-06 1.?17E-06 5.643E-07 2.995E-07 1.925E-O? 9.019E-OS 3.523E-OB ESE E

6.833E-06 1.551E-06 5:092E-07 2.702E-07 1.737E-07 8.141E-OS 3.183E-OB ~

1.848E-OB 1.671E-OB 1.218E-OB 1.102E-OB 8.946E-09 8.101E-09 z

SE 8.202E-06 1.860E-06 6.097E-07 3.233E-O? 2.078E-07 9.?32E-OS 3.803E-OB 1.996E-OS 1.31?E-OB 9.676E-09 SSE 1.360E-05 3.052E-06 1.015E-06 5.449E-O? 3.530E-07 1.674E-OT 6.65?E-DB 3.536E-OB 2.348E-OS 1 '33E-08

TABLE A-7 0 M

&O Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') N 0 O

EXIT OHE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 UX 2.300 DAY DECAY, UHDEPLETED 0 lh CORRECTED USING STANDARD OPEN TERRAIN FACTORS O I

n Q AHNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IN HILES FRNI THE SITE I 0 c S

SSM 1.712E-04 1.564E-04 5.078E-OS 4.675E-OS 2.500E-OS 2.318E-05 1.226E-05 1 ~ 139E-05 4.824E-06 4.489E-06 2.723E-06 2.525E-06 1.776E-06 1.643E-06 ~

1.266E-06 1.168E-06 9.571E-OT 8.820E-07 7.553E-OT 6.951E-07 00 6.153E-07 5.657E-07 rr 0 0

SM 1.474E-04 4.374E-OS 2. 154E-05 1.056E-OS 4.158E-06 2.347E-06 1.531E-06 1.091E-06 8.247E-07 6.508E-07 5.301E-07 I

'MSW 1.289E-04 3.808E-OS 1.869E-OS 9. 149E-06 3.600E-06 2.036E-06 1.330E-06 9.484E-07 7.177E-07 5.667E-07 4.619E-07 0 W 9.794E-OS 2.895E-05 1.422E-OS 6.966E-06 2.743E-06 1 ~ 551E-06 1.013E-06 7.221E-07 5;464E-07 4.314E-OT 3 '15E-07 0 WNM 7.398E-OS 2.197E-OS 1.085E-OS 5.331E-06 2.102E-06 1.185E-06 7.723E-07 5.499E-07 4. 156E-07 3.278E-07 2.669E-07 Z8 HM 6.609E-OS 1.980E-OS 9.879E-06 4.892E-06 1.938E-06 1.087E-06 7.060E-07 Q 8 5.014E-07 3.782E-07 2.978E-07 2.421E-07 HNM HHE N

7.152E-OS 9.191E-OS 9.814E-OS 2.170E-DS 2.805E-05 3.014E-OS 1.099E-OS 1 '34E-05

'1.546E-OS 5.495E-06 7.184E-06 7.751E-06 2.189E-06 2.864E-06 3.088E-06 1.220E-06 1.591E-06 1.712E-06 7.887E-07 1.026E-06 1 '02E-06 5.581E-07 7.247E-07 7.770E-07

4. 197E-07 5.442E-OT 5.829E-OT 3.297E-07 4.270E-07 4.570E-07 2.676E-OT 3.463E-07 3.703E-07 rr C

Ql HE 7.865E-05 2.414E-OS 1.228E-05 6. 117E-06 2.422E-06 1.342E-06 8.635E-07 6.091E-07 4.569E-OT 3.582E-07 2.902E-07 0 rt EHE 5.978E-OS 1.833E-OS 9.300E-06 4.621E-06 1.825E-06 1.011E-06 6.499E-OT 4.582E-07 3.436E-07 2.693E-OT 2.182E-07 tI n-E 4.885E-05 1.487E-OS 7.507E-06 3.729E-06 1 '76E-06 8.212E-07 5.301E-07 3.748E-07 2.817E-OT 2.212E-O'7 1.794E-07 P vl ESE 4.441E-05 1.351E-OS 6.801E-06 3.372E-06 1.332E-06 7.411E-07 4.783E-OT 3.382E-OT 2.541E-07 1.996E-07 1.619E-07 SE 5.331E-05 1.621E-05 8.172E-06 4 '47E-06 1 '97E-06 8.879E-07 5.728E-07 "4.048E-07 3.042E-07 2.388E-07 1.937E-07 tQ SSE 9.063E-05 2.712E-05 1.345E-OS 6.616E-06 2.606E-06 1.463E-06 9.505E-07 6.753E-OT 5.095E-07 4.014E-07 3.265E-07 AHHUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IN IIILES FRNI THE SITE S 5.138E-07 2.700E-07 1.755E-07 9.871E-OB 6.459E-OB 4.597E-OB 3.454E-OB ' 2.697E-OB 2.167E-OB 1.781E-OB 1.490E-OB SSM 4.719E-07 2-472E-07 1.603E-OT 8.990E-OB 5.871E-OB 4.172E-OB ~ 131E-08 2.442E-OB 1.960E-OB 1.609E-OB 1.345E-OB SW 4.426E-OT 2.324E-OT 1.509E-07 8.472E-OB 5 '32E-08 3.929E-OB 2.946E-OB 2.296E-OB 1.841E-OB 1.510E-OB 1.261E-OB MSM 3.858E-OT 2.029E-OT 1.318E-07 7.405E-OB 4.835E-OB 3.433E-OB 2.574E-OB 2.005E-OB 1.607E-OB 1.317E-OB 1.100E-OB M 2.936E-07 1.544E-07 1 '03E-07 5.633E-OB 3.678E-OB 2.612E-OB 1.958E-OB 1.525E-OB 1.223E-OB 1.003E-OB 8.370E-09 MHM 2 '28E-07 1.169E-07 7.589E-OB 4 '59E-08 2.782E-OB 1.976E-OB 1.482E-OB 1.155E-OB 9-267E-09 7.602E-09 6.350E-09 NM 2.019E-07 1.055E-07 6.837E-OB 3.834E-OB 2.505E-OB 1.782E-OB 1.339E-OB 1.045E-OB 8.394E-09 6.896E-09 5.768E-09 NHM 2.228E-OT 1.159E-OT 7.490E-OB 4. 194E-08 2.742E-OB 1.953E-OB 1.470E-OB 1. 150E-08 9.252E-09 7.614E-09 6.378E-09 N 2.880E-OT 1.495E-07 9.650E-OB 5.401E-OB 3.534E-OB 2.520E-OB 1.898E-OB 1.486E-OB 1 '98E-08 9.868E-09 8.276E-09 HHE 3.078E-07 1.594E-OT 1.028E-07 5.753E-OB 3.766E-OB 2.687E-OB 2 '26E-08 1.588E-OB 1.281E-OB 1.057E-OB 8.872E-09 HE 2.413E-07 1.250E-07 8.065E-OB 4.512E-OB 2.953E-OB 2.106E-OB 1.588E-OB 1.244E-OB 1.003E-OB 8.276E-09 6.949E-09 EHE 1.814E-07 9.395E-OB 6.060E.OB 3.391E-OB 2.220E-OB 1.585E-OB 1.195E-OB 9.369E-09 7.561E-09 6,239E-09 5.241E-09 E 1.493E-07 7.761E-OB 5.014E-OB 2.807E-OB 1.836E-OB 1.308E-OB 9.847E-09 7.705E-09 6.205E-09 5 '10E-09 4.284E-09 ESE 1.347E-07 T.DOSE-OB 4.527E-OB 2.535E-OB 1.659E-OB 1.183E-OB 8.908E-09 6.974E-09 5.619E-09 4.630E-09 3.884E-09 SE 1.612E-OT 8.378E-OB 5.414E-OB 3.033E-OB 1.985E-OB 1.416E-OB 1.067E-OB 8.353E-09 6.732E-09 5.549E-09 4.657E-09 SSE 2.723E-OT 1.425E-07 9.243E.OB 5.189E-OB 3.394E-OB 2.416E-OB 1.816E-OB 1.419E-OB 1.140E-OB 9.378E-09 7.851E-09 Pl Ol &

TABLE A-8 o ch th S 4

Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m ) ft 0 0

EXIT OHE -- GROUND-LEVEL HISTORICAL DATA( 1976-1987 U X 0

2.300 DAY DECAY, UHDEPLETED Gl tl CHI/O (SEC/METER CUBED) FOR EACH SEGHENT 8 O N DIRECTION SEGHENT BOUHDARIES IN IIILES FRON THE Sl'IE V4 n c 2.506E-OS 5.542E-06 1.825E-06 9.683E-07 6.192E-07 c n S 2.822E-07 1.006E-07 4.636E-OS 2.711E-08 1.787E-08 VV SSM 2.318E-05 5.151E-06 1.68SE-06 8.926E-07 5.693E-07 2.585E-07 9.168E-OS ~ 4.209E-OS 2.455E-08 1.615E-08 0 ct Q SM 2.159E-OS 4.776E-06 1 '72E-06 8.345E-07 5.334E-07 2.429E-07 8.636E-08 3.964E-08 2.309E-OS 1.516E-08 MSM 1.876E-05 4 '38E-06 1.366E-06 7.261E-07 4.647E-07 2. 119E-07 7.547E-OS 3.463E-OS 2.016E-OS 1.323E-DB 0 M 1.427E-OS 3. 152E-06 1.040E-06 5 '28E-07 3 '37E-07 1.613E-07 5.741E-OS 2.635E-OS 1;534E-08 1.006E-OB 0 MHM 1.087E-OS 2.412E-06 7.934E-07 4.205E-07 2.686E-07 'I.222E-07 4.343E-OS 1.994E-OS 1.162E-08 7.632E-09 X8 9.867E.06 2.216E-06 8

HM 7.259E-07 3.827E-07 2.437E-07 1.104E-07 3.911E-OS 1.798E-08 1.051E-OS 6.922E-09 NHM 1 '93E-05 2.493E-06 8.116E-07 4.250E-07 2.694E-07 1.214E-07 4.281E-08 1.970E-OS 1. 156E-08 7.641E-09 C Ql H 1.421E-OS 3.258E-06 1.056E-06 5.511E-07 3.486E-07 1 '67E-07 5.515E-08 2.541E-OS 1.494E-08 9.903E.09 VI HNE 1.530E-OS 3.513E-06 1.134E-06 5.904E-07 3.728E-07 1.672E-07 5.877E-08 2.710E-OS 1.596E-08 1.060E-OS rt a0O~

NE 1.218E-OS 2.763E-06 8.893E-07 4.628E-07 2.923E-07 1.311E-07 4.608E-08 2.125E-08 1.251E-OS 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-OS 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-OS 7.746E-09 5.129E-09 3,'M ESE 6.768E-06 1.523E-06 4.923E-07 2.574E-07 1.630E-07 7.341E-08 2.588E-OS 1.193E-OS 7.010E-09 4.647E-09 SE 8.124E-06 1.826E-06 5;897E-07 3.080E-07 1.950E-07 8.781E-OS 3.096E-08 '.428E-08 8.396E-09 5.569E-09 tg PQ SSE 1.345E-OS 2.989E-06 9.771E-07 5. 157E-07 3.286E-07 1.491E-07 5.292E-08 2.437E-OS 1.426E-08 9.413E-09

TABLE A-9 o M AO N

Depleted, 8.0 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') rt 0 Ql N

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA( 1976-1987 U X 0

8.000 DAY DECAY, DEPLETED N tf CORRECTED USING STANDARD OPEN TERRAIN FACTORS 5 nI ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES FROH THE SITE VZ n c S 1.625E-04 4.665E-05 2.247E-05 1 '85E-05 4 '69E-06 2.308E-06 1.482E.06 1.042E-06 7.784E-OT 6.080E-07 4.908E-OT c n SSW 1.485E-04 4.295E-OS 2.083E-05 1.009E-05 3.877E-06 2.139E-06 1.369E-06 9.606E-07 7.168E-07 5 '90E-OT 4.507E-07 8 SW WSW 1.400E-04 1.224E-04 4.019E-05 3.499E-05 1.937E-05 1.681E 05 9.357E-06 8.10TE-06 3.594E-06 3.113E-06 1.991E-06 1.728E-06 1.2?SE-06 1.111E-06 8.984E-07 7.818E-OT 6.715E-07 5.244E-OT 4.233E-07 r0 g 5.849E-OT 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 5.952E-OT 4.452E-07 3 '79E-07 2.810E-OT 0 WNW 7.023E-05 2.018E-05 9.753E-06 4.721E-06 1.816E-06 1.005E-06 6.444E-07 4.527E-OT 3.382E-07 2.640E-OT 2.130E-07 Z 80 HM 6.273E-05 1.819E-05 8.876E-06 4.329E-06 1.672E-06 9.202E-07 5.878E-07 4.117E-07 3.068E-07 2.390E-OT 1.925E-07 NNW 6.787E-05 1.991E-OS 9.871E-06 4.85?E-06 1.886E-06 1.030E-06 6.548E-07 4.56?E-07 3.391E-07 2.635E-OT 2 '1?E-07 c N 8.721E-05 2.574E-05 1.287E-OS 6.346E-06 2.465E-06 1 '42E-06 8.505E-07 5.920E-07 4.389E-OT 3.404E-07 2.732E-07 VI 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 3.63?E-07 2.916E-07 HE 7.462E-05 2.215E-05 1.102E-05 5.403E-06 2.084E-06 1.131E-06 7.156E-07 3.683E-07 2.855E-OT 2.289E-07 0 rt EHE 5.671E-05 1.682E-05 8.343E-06 4 '81E-06 1 '71E-06 8.519E-07 5.385E-07 4.974E-07'.741E-OT 2.770E-OT 2 '46E-07 1.721E-07 a O~

E 4.635E-05 1.365E-05 6.739E-06 3.295E-06 1 '71E-06 6,933E-OT 4.401E-07 3.067E-07 2.276E-OT 1.767E-07 1.419E-OT g m ESE 4.214E-05 1.240E-05 6.105E-06 2.980E-06 147E-06 6.256E-07 3.971E-07 2.767E-OT 2.054E-OT 1.595E-07 1 ~ 281E-07 5.058E-05 '87E-05 7:335E-06 3.576E-06 1 ~

1.376E-06 7.495E-07 4

SE 1 4.755E-O? .3.312E-07 2.457E-07 1 '08E-07 1 '32E-07 tQ SSE 8.603E-05 2.491E-05 1.209E-05 5.855E-06 2.249E-06 1.238E-06 7.917E-07 5.547E-OT 4.136E-07 3.223E-07 2.597E-07 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES FROH THE SITE 0

S 4.064E-07 2.080E-07 1.325E-07 7.280E-08 4.?OOE-OS 3.317E-OS 2.47?E-08 ~ .1.924E-08 1.538E-OS 1.25?E-OS 1.045E-OS SSW 3.729E-07 1.901E-07 1.208E-07 6.616E-08 4.263E-08 3.004E-OS 2.240E-08 1.738E-08 1.388E-OS 1 '34E-08 9.424E-09 SW 3.506E-OT 1.794E-07 1.143E-OT 6.274E-OS 4 '49E-08 2.856E-OS 2.131E-OS 1.654E-OS 1.322E-08 1.079E-OS 8.973E-09 WSW 3.060E-07 1.569E-07 1.001E-07 5 '02E-08 3.554E-OS 2.508E-08 1.872E-08 1.453E-08 1.161E-OS 9.48?E-09 7.8S7E-09 M 2.328E-07 1.193E-OT 7.609E-08 4.182E-08 2.701E-08 1.906E-08 1.422E-08 1.104E-OS 8.823E-09 7.207E-09 5.991E-09 MHM 1.764E-07 9.014E-08 5.738E-08 3.147E-08 2.030E-08 1.431E-OS 1.068E-08 8.289E-09 6.622E-09 5 '09E-09 4.496E-09 NW 1. 591E-07 8.086E-08 5 '29E-08 2.801E-08 1.803E-08 1.269E-OS 9.462E-09 7.339E-09 5.861E-09 4.787E-09 3.979E-09 HNM 1.746E-07 8.808E-08 5.560E-08 '.019E-08 1.936E-OS 1.360E-OS 1.013E-08 7.848E-09 6.264E-09 5 '15E-09 4.251E-09 H 2.251E-07 1.132E-07 7.127E-OS 3.859E-08 2.471E-08 1.735E-08 1.291E-08 1.000E-08 7.981E-09 6.516E-09 5.417E-09 HHE 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 6.8ME-09 5.726E-09 HE 1.885E-OT 9.461E-OS 5.954E-OS 3.222E-08 2.063E-08 1.449E-08 1.078E-08 8.353E-09 6.668E-09 5.445E-09 4 '27E-09 EHE 1.41?E-07 7.109E-08 4.473E-OS 2.421E-08 1.551E-08 1.089E-OS 8. 109E-09 6.285E-09 5.018E-09 4.099E-09 3.409E-09 E 1.171E-OT 5.902E-08 3.724E-08 2.023E-08 1.298E-OS 9.120E-09 6.791E-09 5.264E-09 4.203E-09 3!432E-09 2.853E-09 ESE 1.056E-07 5.327E-OS 3.363E-08 1.827E-OS 1.173E-08 8.246E-09 6. 143E-09 4.763E-09 3.803E-09 3.107E-09 2.583E-09 SE 1.263E-07 6.369E-08 4.020E-08 2.184E-OS 1 '02E-08 9.856E-09 7.343E-09 5.694E-09 4.547E-09 3.714E-09 3.089E-09 SSE 2.148E-07 1.094E-DT 6.946E-08 3.801E-OS 2.449E-08 1.726E-OS 1.288E-08 9.994E-09 7.985E-09 6.524E-09 5.425E-09 PQ 8

TABLE A-10 o ol

&O Depleted, 8.0 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') A0 0

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA( 1976-1987 tl 0

X 8.000 DAY DECAY, DEPLETED lh CHI/O (SEC/HETER CUBED) FOR EACH SEGNENT 8 nv D I RECT ION SEGNENT BOUNDARIES IN IIILES FRDN THE SITE

- 0 ri n r S

SSM 2.268E-OS 2.097E-OS 4.827E-06 4.485E-06 1.526E-06 1.411E-06 7.887E-07 7.263E-07 4.943E-07 4.540E-07 2.186E-07 1.999E-07 7.461E-08 6.785E-OS 3.350E-08 3.034E-08 1.935E-OS

'I.748E-OS 1.262E-08 1 '38E-08 rr an 8

SM 1.955E-05 4 '62E-06 1.316E-06 6.803E-07 4.264E-07 1.885E-07 6.430E-08 2.884E-08 1.664E-OS 1.084E-OS r. g MSM '1.698E-OS 3.607E-06 1.144E-06 5.925E-07 3.719E-07 1.648E-07 5.637E-OS 2.532E-OS 1.462E-DS 9.524E-09 0 M 1.292E-OS 2.747E-06 8.710E-07 4.510E-07 2.830E-07 1.253E-07 4.285E-08 1.924E-OS 1 111E-08 7.236E-09 0 MNM 9.835E-06 2.101E-06 6.638E-07 3.426E-07 2.145E-07 9.474E-08 3 '26E-08 1.446E-08 8.338E-09 5.430E-09 Z 88 NM 8.924E-06 1.928E-06 6.060E-07 3.109E-07 1.939E-07 8.510E-08 2.875E-DB 1 '82E-08 7.383E-09 4.806E-09 NNM N

NNE 9.874E-06 1.283E-05 1.381E-OS 2.166E-06 2.828E-06 3.048E-06 6.757E-07 8.782E-07 9.423E-07 3.439E-07 4.451E-07 4.761E-07 2.133E-07 2.753E-07 2.939E-07 9.287E-08 1.194E-07 1.271E-07 3.102E-08 3.969E-08 4.207E-08 1.375E-OB 1.754E-OB 1.855E-DS 7.896E-09 1.006E-08 1.064E-08 5.136E-09 6.543E-09 6.917E-09 rr C

fO NE 1.100E-OS 2.39SE-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 0 rt ENE E

8.332E-06 6.744E-06 1.809E-06 1.464E-06 5.563E-07 4 '42E-07 2.810E-07 2.308E-07 1.734E-07 1 '30E-07 7-506E-08 6.224E-OS 2.491E-08 2.079E-OS 1.101E-08

,9.217E-09 6.323E-09 5.296E-09 4.115E-09 3.446E-09 U

n-g Ql ESE 6.115E-06 1.323E-06 4.099E-07 2.083E-07 1.291E-07 5.618E-OS 8.333E-09 3.1'I9E-09 SE 7.340E-06 1.586E-06 4.908E-07 2.492E-07 1.544E-07 6.717E-OS 1.878E-OS 2.244E-08 ,9.960E-09 4.791E-09 5.728E-09 3.730E-09 z

PQ SSE 'I.217E-DS 2.601E.06 8.160E-07 4.191E-07 2.616E-07 1.151E-07 3.899E-08 1.743E-08 1.005E-OS 6.550E-09 o

TABLE A-ll Q Ol th S Deposition Values (D/Q) for Long Term Releases at Standard Distances (m ') r. o N 0 N

EXIT -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 UX OHE 0 CORRECTED USING STANDARD OPEN TERRAIN FACTORS N 8

- - - - *** * ******** RELATIVE DEPOSITION PER UNIT AREA (M~~-2) AT FIXED POINTS BY DOWNWIND SECTORS ****l*********************** n tn DIRECTION 0 C DISTAHCES IH MILES en I I S 2.324E-07 7.857E-OB 4.034E-OS 1.918E-OB 6.889E-09 3.417E-09 2.012E-09 1.317E-09 9.269E-10 6. 869E-10 5.294E-10 O SS'M 2.171E-07 7.343E-OB 3.770E-OS 1.792E.OS 6.438E-09 3.193E-09 1.880E-09 1.231E-09 8.662E-10 6.420E-10 4.947E-10 r0 I1 SM 1.T40E-07 5.885E-OB 3.022E-OS 1.437E-OB 5.160E-09 2.559E-09 1 '07E-09 9.866E-10 6.942E-10 5 ~ 145E-10 3.965E-10 MSM 1.355E-07 4.582E-OS 2.353E-OB 1.119E-OB 4.018E-09 1.993E-09 1. 173E-09 7.682E-10 5.406E-10 4.006E-10 3.087E-10 0 M 1.013E-07 3.427E-OB 1.759E-OB 8.365E-09 3.005E-09 1.490E-09 8.774E-10 5.745E-IO 4.042E-10 2.996E-10 2.309E-10 Z 8 QI S MHM 8.296E-OS 2.805E-OB 1.440E-OB 6.848E-09 2.460E-09 1.220E-09 7.183E-10 4.703E-10 3.309E-10 2.453E-10 1.890E-10 N'M 8.468E-OB 2.864E-OB 1.470E-OB 6.990E-09 2.511E-09 1.245E-09 7.332E-10 4.801E-10 3.378E-10 2.503E-10 1.929E-10 HHM 1.105E-07 3.736E-OB 1.918E-OB 9 '20E-09 3.276E-09 1.625E-09 9.566E-10 6.264E-10 4.408E-10 3.266E-10 2.517E-10 H 1.626E-07 5.499E-OS 2.823E-OB 1.342E-OS 4.821E-09 2.391E-09 1.408E-09 9.218E-10 6.487E-10 4.80TE-10 3.705E-10 HHE 1.985E-07 6.713E-OS 3.447E-OB 1.639E.OB 5.886E-09 2.919E-09 1.719E-09 1 ~ 125E-09 7.919E-10 5.869E-10 4 '22E-10 Q ~

HE 1.815E-07 6.137E-OB 3.151E-OB 1.498E-OB 5.381E-09 2.669E-09 1.571E-09 1.029E-09 7.240E-10 5.366E-10 4.135E-10 U O

EHE 1.568E-07 5.302E-OB 2.723E-OB 1.294E-OS 4.649E-09 2.306E-09 1.358E-09 8.890E-10 6.255E-10 4.636E-10 3. 572E-10 g lh E 9.595E-OB 3.245E-OB 1.666E-OS 7.920E-09 2.845E-09 1.411E-09 8.307E-10 5.439E-10 3.827E-10 2.837E-10 2.186E-10 z tg ESE 1.003E-07 3.393E-OB 1;742E-08 8.281E-09 2.975E-09 1.475E-09 8.686E-10 ,5.68SE-10 4.002E-10 2.966E-10 2.286E-10 SE 1.270E-OT 4.294E-OB 2.205E-OS 1.048E-OB 3.765E-09 1.867E-09 1.099E-09 7.199E-10 5.066E-10 3.754E-10 2.893E-10 %I SSE 1 '48E-07 5.236E-OB 2.688E-OB 1.278E-OB 4 '91E-09 2.277E-09 1.341E-09 8.778E-10 6.'177E-10 4.578E-10 3.528E-10 DIRECTION DISTANCES IH MILES S 4 '05E-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 SS'M 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 SM 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 9.700E-12 7.284E-12 5.663E-12 4.524E-12 3.692E-12

'M 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 MHM 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 HM 1.533E-10 6.808E-11 4.124E-11 2.085E-11 1 '62E-11 8.459E-12 6.062E-12 4.552E-12 3.539E-12 2.827E-12 2.307E-12 HHW 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-1'I 8.740E-12 6.796E-12 5.428E-12 4.431E-12 NNE 3.593E-10 1.596E-10 9.668E-11 4.887E-11 2.958E-11 1.983E-11 1.421E-11 1.067E-11 8.296E-12 6.627E-12 5.409E-12 HE 3.285E-10 1.459E-10 8.839E-11 4.468E-11 2.704E-11 1.813E-11 1.299E-11 9.755E-12 7.585E.12 6.059E-12 4.946E-12 EHE 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 1.73TE-10 7.7'l4E-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 '69E-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-11 3.812E-11 2.307E-11 1 '47E-11 1 ~ 108E-11 8.323E-12 6.471E-12 5.169E-12 4. 219E-12 C

< v

'Ol lB

TABLE A-12 0 ol

& ID l/l Ql Deposition Values (D/Q) for Long Term Releases at Standard Distances (m ') &0 0

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 U X 0

Gl l0

- - - - t******it*t*t*fkitiiH* RELATIVE DEPOSITION PER UNIT AREA y** 2) BT DOWNWIND SECTORS ****************0******* n~

DIRECT ION SEGHENT BOUNDARIES IN HILES FROH THE SITE n c S 3.943E-OB 8.07?E-09 2.109E-09 9.470E-10 5.35?E-10 2.060E-10 5.960E-11 2.362E-11 1.261E-11 7.808E-12 z n Mk SS'W 3.685E-OB 7.548E-09 1.971E-09 8.850E-10 5.00?E-10 1.925E-10 5.570E-11 , 2.20&E-11 1.179E-11 7.297E-12 0 S'W 2.953E-DB 6.050E-09 1.579E-09 7.093E-10 4.013E-10 1.543E-10 4.464E-11 1.769E-11 9.448E-12 5.84&E-12 WSW 2.300E-OS 4.710E-09 1.230E-09 '.523E-10 3.124E-10 1 201E-10

~ 3.476E-11 1.37&E-11 7.357E-12 4.554E-12 0 W 1.?20E-OS 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 0 WNW 1.40&E-OB 2.884E-09 7.52&E-10 3.381E-10 1.913E-10 7.356E-11 2.12&E-11 8.434E-12 4.504E-12 2.78&E-12 Z 88 HW 1.437E-OB 2.944E-09 7.685E-10 3.451E-10 1.952E-10 7.508E-11 2.172E-11 8.609E-12 4.59?E-12 2.846E-12 NNW 1.875E-OB 3.841E-09 1.003E-09 4 ~ 503E-10 2.54&E-10 9.797E-11 2.834E-11 1 '23E-11 5.99&E-12 3. 713E-12 lQ H 2.760E-OS 5.652E-09 1.476E-09 6.62?E-10 3.749E-10 1 '42E-10 4 'T1E-11 1.653E-11 8.82&E-12 5.464E-12 HHE 3.369E-OB 6.901E-09 1.801E-09 8.091E-10 4.5??E-10 1.760E-10 5.092E-11 2.01&E-11 1.07&E-11 6.671E-12 HE 3.080E-OS 6.309E-09 1.647E-09 7.39?E-10 4.185E-10 1.609E-10 4.655E-11 1.845E-11 9.853E-12 6.099E-12 0 rt EHE 2.661E-OB 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 1.62&E-OB 3.335E-09 8.70?E-10 3.9'11E-10 2.212E-10 8.507E-11 2.461E-11 9.754E-12 5 '09E-12 3 '24E-12 g Ol ESE 1.?03E-O& 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-OB 4.414E-09 1;152E-09 5.176E-10 2.928E-10 1.126E-10 3.25?E-11 . 1.291E-11 6.894E-12 4.267E-12 lg 2.62&E-OS 5.383E-09 1.405E-09 6.311E-10 3.570E-10 tg SSE 1.373E-10 3.972E-11 1.574E-11 8.406E-12 5.203E-12

TABLE A-13 o ol

&O 4

Joint Wind Frequency Distribution by Pascluill Stability Classes at SHNPP N 0 0

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA( 1976-1987 tl 0

X JOINT FREQUENCY DISTRIBUTION OF HIND SPEED AHD DIRECTION lh ATNOSPHERIC STABILITY CLASS A O

nQt rrn 0.34 0.000 0.000 0.000 0.000 0.000 n c vcnrI 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 8 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 r. g 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 0 l1.18 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 0 1'l.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 Z4 O

TOTAL 0.75 0.66 0.50 0.29 0.19 0.16 0.16 0.21 0.47 0.61 0.7e 0.97 0.36 0.49 0.75 0.74 8.09 c

I I Ql ATHOSPHERIC STABILITY CLASS 8 0 rt 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 F 000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 aO~

1.56 0.014 0.015 0.023 0.022 0.017 0.021 0.017 0.018 0.022 0 '20 0.032 0.021 0.025 0.013 0.018 0.017 0.314 g Ol 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 4 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 PQ 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 ATHOSPHERIC STABILITY CLASS C 0.34 0.000 0.000 0.000 0 F 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 0.6'IO 3.35 0.347 0.287 0.245 0.220 0.152 0.131 0.121 0.158 0.261 0.332 0.375 0.369 0.175 0.192 0.246 0.261 3.874 5 '9 0.'l39 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 F 000 0.000 0.000 0.000 0 F 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 ATNOSPHERIC STABILITY CLASS D 0.34 0.002 0.002 0.002 0.002 0.001 0.001 0.001 0.00'I 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 '9 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 5.27'I c 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 Ol 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 0 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 C M TOTAL 2.el 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 lD Ol lP

TABLE A-13 Q Ol

&0 N

Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP r' rt 0 0

XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 UX 0

JOINT FREQUENCY DISTRIBUTIOH OF IIIHD SPEED AHD DIRECTION N l1 O 4 r.

ATMOSPHERIC STABILITY CLASS E O 0 0.34 0.005 H

0.007 0.006 0.005 0.004 0.003 0.004 0.006 0.009 0.009 0.005 0 F 004 0.003 0.002 0.003 0.003 0.079 rno4 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 c n 3.35 1.028 0.855 0.549 0.329 0.309 0.266 0.356 0.577 '58 1.547 1.029 0.744 0.488 0.459 0.660 0.667 10.920 ill 0 5.59 0.124 0.032 0.046 0.029 0.019 0.028 0.032 0.080 1

0.138 0.148 0.216 0.145 0.067 0.101 0.085 0.131 1.421

~ Dl 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 0 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 0 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 Z Q 8 8

TOTAL 1.91 1.86 1.42 F 06 0.85 0.78 0.93 1.49 2.47 2.90 1.99 1 '1 0.98 0.88 1.16 1.28 23.36 ATMOSPHERIC STABILITY CLASS F rr C

Q 0 rt 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 tI 1.56 0.777 0.788 0.735 0.621 0.500 0.414 0 '89 0.667 0.803 0.857 0.553 0.395 0.341 0.291 0.321 0.467 9.017 g M 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 '54 1.925 4 5 '9 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 Ig tQ 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 F 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 0.34 0.360 0.3'I7 0.316 0.284 0.214 0.'l54 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 0.6S4 0.688 0.600 0.457 0.414 0.381 0.455 0.945 14.66S 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 8.2T 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 I'1.18 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 HIND DIRECTION FREQUENCY N H FREQUENCY: 100 94 75 59 44 36 3T 48 70 86 78 68 41 43 55 67 1000

TABLE A-13 0 Vl

&S Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP V rt 0 8

Period of Record : 01/01/76 - 12/31/87 U X 0 Ql M

TOTAL HOURS CONSIDERED ARE ***~~ f0 V.

0 tn 0

OVERALL WIND SPEED FREQUENCY C 0 MAX WIND SPEED (M/S): 0.335 1.565 3.353 5.588 8.270 11 '76 11.623 rt lD Ql AVE WIND SPEED (M/S): 0.168 0.950 2.459 4.470 6.929 9.723 11.400 V g

'WIND SPEED FREQUENCY: 3.05 41.38 41.23 12.79 1.48 0.08 0.00 0 THE CONVERSION FACTOR APPLIED TO THE WIND SPEED CLASSES IS 0.447 0 Z

0 C

lO C

DISTANCES AND TERRAIN HEIGHTS IH METERS AS FUNCTIONS OF DIRECTION FROM THE SITE:

DIRECTION = S SSW SW WSW W WNW NW HHW N NHE NE ENE E ESE SE SSE V r DISTANCE 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124 ~ 2140 ~ 2140. 2140 ~ 2140. 2140. 2140. 2140. 0 N ELEVATION 0. 0. 0. 0~ 0. 0. 0. 0. 0~ 0. 0. 0. 0. 0~ 0~ 0. U Z Io z

IQ VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 0.00 DIAMETER (METERS) 0.00 EXIT VELOCITY (METERS) 0.00 REP. WIND HEIGHI'UILDING (METERS) 10.0 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.

Q V)

TABLE A-14

&0

'h Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rt 0 Calculations with the NRC XOQDOQ Program 0 UX 0

Card Type Columns Variable Name Format Description Value used in I r.

lh XOQDOQ Card Type 1 is an array (KOPT) of options, such that 1 = DO, 0 = BYPASS.

rz n c These o tions remain in effect for all release points run. Thus, all release oints must have the same assum tions. r 0r0 C

KOPT(1) Option to distribute calms as the first wind-speed class 0

{if calms are already distributed by direction in Card 0 Type 6, KOPT(l) = 0, and Card Type 5 is blank). If 0 g 8 Ql 0 KOPT(1) = 1, the calm values of Card Type 5 are distributed by direction in the same proportion as the direction fre uenc of wind-s eed class two. rr C

KOPT(2) Option to input joint frequency distribution data as 0 rt ercent fre uenc . U O~

Q 0)

KOPT(3) Option to compute a sector spread for comparison with centerline value in ur e calculation {Normall = 1).

z tQ tQ KOPT(4) Option to plot short-term X/0 values versus probability 0 of occurrence (Normal{ = 0).

KOPT(51 Option to use cubic spline in lieu of least square function for fitting intermittent release. distribution (Normally =

1).

KOPT(61 Option to punch radial segment X/0 and D/0 values

{Normally ~ 1).

KOPT{7) Option to punch output of X/0 and D/0 values of the oints of interest (Normall = 1).

KOPT(8) Option to correct X/0 and D/0 values for open terrain recirculation.

KOPT(9) Option to correct X/0 and D/0 values using site specific 0 terrain recirculation data.

Q VI TABLE A-14 tb K th OI Ql Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rt 0 O

Calculations with the NRC XOQDOQ Program tl 0

X l0 OI Card Type Columns Variable Name Format Description Value used in r.

XOQDOQ 0 IO

= 0) rZ 0 c 10 KOPT(10) 0 tion to use desert si ma curves (Normall r. n WI KOPT(1 1) Option to calculate annual X/Q with 30 degree sectors for P O rt Q North, East, South and West and 20 degree sectors for all I 0

others. (Normally = 0, and the code will use 22-1/2 de ree sectors) 0 Z 8 Ql O 1 -80 TITLM 20A4 The main title rinted at the be innin of the out ut. N/A 1-5 NVEL l5 The number of velocit cate ories (maximum of 14). I r 6-10 NSTA l5 The number of stability categories (maximum of 7) (1 Q U

rt always equals Pasquill stability class A, 2 = B, ..., 7 =

G). g M z

to 11 -15 NDIS l5 The number of distances with terrain data for each to (

sector. The number of distances must be the same for each sector (Card T e 10) (maximum of 10).

16- 20 INC l5 The increment in percent for which plotted results are 15 printed out {Normall = 15)..

21 -25 NPTYPE l5 The number of titles of receptor types (cow, garden, etc.)

(Card T e 13) (maximum of ei ht) 26-30 NEXIT IS The number of release exit oints (maximum of five).

31 -35 NCOR IS The number of distances of site specific correction factors for recirculation (maximum of 10).

1-5 PLEV F5.0 The height (in meters, above ground level) of the 1 2.0 measured wind presented in the joint frequency data (Card Type 7). {For elevated/ground-level mixed release, use the 10-meter level winds).

0 Ol TABLE A-14 &8 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rt 0 (D

Calculations with the NRC XOQDOQ Program ax 0

N Card Type Columns Variable Name Format Description Value used in 5 V

XOQDOQ O 0 6-20 DECAYS(I) 3F5.0 For each I: The halt-life (days) used in the X/Q 101.00 nrn 0-1=1,3 calculations: if DECAYS > 100, no decay will occur; if 2.30 Ql k

S DECAYS < 0, depletion factor will be used in the X/Q -8.00 ct Q calculations; if DECAYS = 0, X/Q will not be calculated.

r0 e tg (Normally, DECAYS(1) ~ 101, (2) = 2.26, (3) = -8.00.) 0 8

J 21-25 PLGRAD F5.0 Plant grade elevation (feet above sea level). If PLGRAD 0.00

= 0.0, DIST and HT data Card Type 10 and 11 must be er in meters. If PLGRAD < 0.0, DIST in miles and HT data in feet above plant grade. If PLGRAD > 0.0 above DIST 0 rt in miles and HT data in feet above sea level. n-U g Ch 1-35 CALIVI(I) 7F5.0 The number of hours, or percent, of calm for each BLANK 'z

~Q I = 1,NSTA stability category; if KOPT(1) ~ 0, insert blank card. PQ

{Note: I = 1 is stability class A, 2 = B, ..., 7 = G).

1 -80 FREQ(K,I,J) The joint frequency distribution in hours (or percent). The K =1,16 values for 16 {K) sectors are read on each card for each I = 1,NVEL (if KOPT(l)=0) combination of wind-speed class (I) and stability class (J).

I ~ 2,NVEL {if KOPT(1) =1) The loop to read these value cy'cles first on direction J = 1,NSTA continuing in a clockwise fashion), then on wind class and finall on stabilit class.

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.

Q M TABLE A-14 th K th 8 M

Shearon Harris Plant Site Input Information for Continuous Ground Level Releases N 0 Calculations with the NRC XOQDOQ Program . 8 U X 0

'0l Card Type Columns Variable Name Format Description Value used in tD I

XOQDOQ O 8 6-75 rg Qt n c UMAX(I) 14F5.0 The maximum wind speed in each wind-speed class, in either miles/hour or meters/second. (If given in miles/hour. set UCOR ) 100.)

0.75, 3.50,'7.50, 12.50, 18.50, 25.00, 26.00 rr L 0 Q O rt Ql ardT es 8 and 9 are read in for each cor rection factor and distance ~ 1,NCOR 0 iven, I 0

1-80 VRDIST(K,I) 6F5.0 The distance in meters at which correction factors are All Distances = 1.0 Zc 1 0 K=1,16 given. These values are read in beginning with south and proceeding in a clockwise direction (maximum of 10). rr C

Ql 1-80 16F5.0 Correction factor to be applied to X/0 and D/0 values All Factors = 1.000 0 rr VRCD(K,I) aO~

K=1,16 corres onds to distances s ecifiedin VRDIST. g V)

Card Types 8 and 9 are re eated for the remainin distances and correction factors. fg tQ Card T es 10 and 11 are readin for each terrain distance and hei ht iven, I 1,NDIS 10 1-80 DIST(K,I) 16F5.0 The distance in meters at which terrain heights are given. Distance Site K=1,16 These values are read in beginning with south and Boundary Distance proceeding in a clockwise direction (maximum of ten distances).

1 -80 HT(K,I) 1 6F5.0 The terrain heights (in meters, above plant grade level) All Heights ~ 0.0 K =1,16 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 T pes 10 and 11 are repeated for the remainin distances and hei hts.

P M TABLE A-14 th K W III Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rt 0 Calculations with the NRC XOQDOQ Program 8 ax 0

lO Card Type Columns Variable Name Format Description Value used in 8 I

XOQDOQ O tn 12 1-25 NPOINT(l) 5I5 The number (maximum of 30) of receptor locations for a 1 6,1 5,13,2,0,1 1 0

cn I = 1,NPTYPE particular receptor type (such as the number of cows, V I III ardens, or site boundaries). rt

r. Ql g

= 1,NPTYPE 0 Card Types 1 3 and 14 are read in for each receptor ty e, t hus I 0

13 -16 TITLPT(I,J) 4A4 The title (cows, gardens, etc.) of the receptor type for the Site Boundary = 16 Z8 1 8 receptor locations (Card Type 14) (a maximum of 16 Nearest Resident =

'spaces).

Garden = 13 15 rr C

Ql Cow Milk = 2 0 rt Goat Milk = 0 U O~

3', OI Meat 5 Poultr = 11 14 -80 KDIR(I,N) 8(IS,F5.0) The receptor direction and distance. KDIR is the direction zIg 1 See Table A-1 t(j PTDIST(I,N) of interest, such that 1 = South, 2 = SSW......, 16 =

N =. 1,NPOINT(l) SSE, PTDIST is the distance, in meters, to the receptor location.

Card T es 13 and 14 are re eated for the remainin rece tor t es.

Card T es 15, 16 and 17 are readin for each plant release oint, thus I = 1,NEXIT.

15 1-80 TITLE(I,J) 20A4 The title for the release point whose characteristics are described on Card T es 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 FS.O The vent inside diameter (meters).

16 11 -15 H STACK(I) F5.0 The height of the vent release point (meters, plant grade 0.0 If release is 100% elevated, input negative of 'evel).

hei ht.

16 16-20 HBLDG(I) F5.0 The height of the vent's building (meters, above plant 55.0 rade level). ul XI rt 8

V

& CB

Q 0)

TABLE A-14 W S Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rrt v0 lh Ql Calculations with the NRC XOQDOQ Program 0 ax 0 Ql lh I1 Card Type Columns Variable Name Format Description Value used in O I

XOQDOQ O 0 M4

-25 0 16 21 CRSEC(I) F5.0 The minimum cross-sectional area for the vent's building 2161.0 cn Mr (s uare meters). O 16 26-30 SLEV(I) FS.O The wind height used for the vent elevated release 10.0 0 (meters, above lant rade level).

0 16 31 -35 HEATR(I) F5.0 The vent heat emission rate (cal/sec) (Normall = 0). 0.0 Z Ql 8 4

P5 17 17 2-5 RLSID(I)

IPURGE(I)

A1

!4 A one letter identification for the release IPURGE = 1, 2 or 3 if the oint.

vent has intermittent releases.

A 0

rr Ql The 1, 2, or 3 corresponds to DECAYS(1), DECAYS(2), 0 ct or DECAYS(3) (Card Type 4), respectively, whichever is n-U g Ol used as the base for intermitterit release calculations (normally no decay/no deplete X/Q, sucli that IPURGE(l) z It@

= 1; if a vent has no intermittent releases, IPURGE = 0. tg 17 6- 10 NPURGE(l) l5 The number of intermittent releases per year for this 0 release point.

17 11-15 NPRGHR(l) IS The avera e number of hours er intermittent release.

Card Types 15, 16, and 17 are re eated for the remainin release oints.

Card T es 1 - 17 may be re eated for the next case.

Shearon Harris Nuclear Power plant (SHNpp) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX B Sheet 1 of 15 DOSE PARAMETERS FOR RADIOZODINES/ 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 foz gaseous effluents.

These dose parameters, Pz and R~, 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 Pz and Rz values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively).

B.l Calculation of P The'dose parameter, Pz, 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 iz 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 P~ 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 c 1500 mrem/yr. The child's breathing rate is taken as 3700 m'/yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFQ, 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 DF+.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rey. 5 APPENDIX B Sheet 2 of 15 DOSE PARAMETERS FOR RADZOZODZNES ~ PARTI CULATES / AND TRITIUM B.l Calculation of P (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.

ig K'(BR) DH4 (B.1-1) where:

P ~

Dose parameter for radionuclide "i" for the inhalation pathway, mrem/yr per pCi/m~;

K' constant of unit conversion; 10~ pCi/pCi; BR The breathing rate of the children's age group, m'/yr; DFQ The maximum organ inhalation dose factor for the children' age group for zadionuclide "i, " mrem/pCi .

The incorporation of breathing rate of a child (3700 m'/yr) and the unit conversion factor results in the following equation:

Pi 3.7 E+09 DFAl (B.1-2)

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 g PARTI CULATES g AND TRITIUM B.2 Calculation of R The bases for ODCM Operational Requirement 3.11.2.3 state that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that the actual exposuze 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.

Rz 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 Pathwa The dose factor from the inhalation pathway is calculated by:

R.

ig K'BR) a (DFAt) a (B. 2-1) where:

K'ose R.

ig factor for each identified radionuclide "i" of the organ of interest, mzem/yr per pCi/m';

A constant of unit conversion; 10'Ci/pCi; (BR) Breathing rate of the receptor of age group "a, "

m'/yr; (DFQ) ~ Organ inhalation dose factor for zadionuclide "i" for the receptor of age group "a", mrem/pCi.

The breathing rates (BR), for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision 1.

Breathin Rate m~/ r Infant 1400 Child 3700 Teen 8000 Adult . 8000 Inhalation dose factors (DF+), for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.

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'ND TRITIUM B.2.2 Ground'Plane Pathwa The ground plane pathway dose factor is calculated by:

R ~

iG I. K'K"(SF)DFG.

i (1-e )/Aq (B.2-2) where:

R. identified ig Dose factor for the ground plane pathway for each radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m ~;

K' constant of unit conversion; 10'Ci/pCi; KII A constant of unit conversion; 8760 hr/year; The radiological decay constant for radionuclide "i, " sec ';

The exposure time, sec; 4.73 E+08 sec (15 years);

DFGi The ground plane dose conversion factor for radionuclide "i, "

mrem/hr per pci/m';

A tabulation of DFGz values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.

SF The shielding factor (dimensionless);

(A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.)

B-5

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 6 o f 15, DOSE PARAMETERS FOR RADZOZODZNES g PART Z CULATES g AND TRITIUM B.2.2 Ground'Plane Pathwa (continued)

Factor to account for fractional deposition of radionuclide II j II For radionuclides other than iodine, the factor Iq is equal to one. For radioiodines, the value of Z~ 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) Dune 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 7 of 15, DOSE PARAMETERS FOR RADZOIODINESI PARTICULATES, AND TRITIUM BE 2 ' Grass Cow or Goat Milk Pathwa The dose factor for the cow milk or goat milk pathway for each radionuclide for each organ is calculated by:

f (f f ( r (1-e Ei e) Biv (1-e itb)

= ZiKQF Uap (DFLi) e + +

Ri Fm Pki

)

p Ei itb )

Ei t e) B iv( 1 -ee -) ith (B. 2-3)

(1-fpfs) ( r(1-e +

Phi

) e )

Ys ~E ~

where R.

Dose factor for the cow milk or goat milk pathway, for each identified radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m';

K' constant of unit conversion; 10'ci/pci; The cow's or goat's feed consumption rate, kg/day (wet weight);

U The receptor's milk consumption rate for age group "a,"

ap liters/yr; The agricultural productivity by unit area of pasture feed grass, kg/m~;

The agricultural productivity by unit area of stored feed, kg/m';

B-7

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDZX B DOSE PARAMETERS FOR RADZOZODZNES, PARTZCULATES, AND TRZTZUM B.2.3 Grass Cow or Goat Milk Pathwa (continued)

The stable element transfer coefficients, pCi/liter per pCi/day; Fraction of deposited activity retained on cow's feed grass; (DFLg) i The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pci; XE Z

= Xi+A i The radiological decay constant for radionuclide "i,"

sec ';

The decay constant for removal of activity on leaf and plant surfaces by weathering, sec ';

5.73 E-07 sec '14 day half-life);

The transport time from feed to cow, or goat to milk, to receptor, sec; The transport time from pasture, to cow or goat, to milk to receptor, sec; Period of time that sediment is exposed to gaseous effluents, sec; B.

iv Concentration factor for uptake of radionuclide "i" from the soil by the 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 FOR RADIOlODZNES, PARTZCULATES AND TRITIUM B.2.3 Grass 'Cow or Goat Milk Pathwa (continued)

Effective surface density for soil, Kg (dry soil)/m';

fP Fraction og the year that the cow or goat is on pasture; fs Fraction of the cow feed that is pasture grass while the cow is on pasture; (dimensionless).

te Period of pasture grass and crop exposure during the growing. season, sec; i

Z. Factor to account for fractional deposition of radionuclide "i."

For zadionuclides other than iodine, the factor I is equal to one. For radioiodines, the value of I may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-8 through 3.3-15. (Reference NUREG 0133)

Milk cat tie and goats are considered to be fed fzom 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 f 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) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 10 of 15.

DOSE PARAMETERS FOR RADIOIODINESg PARTICULATES'ND TRITIUM B.2.3 Grass'ow or Goat Milk Pathwa (continued)

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Rq is based on X/Q:

R K'K' 'F~QrUap(DFLa) a 0.75 (0.5/H) (B. 2-4) where:

R TH Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per pCi/m';

Kl I I A constant of unit conversion; 10'm/kg; H Absolute humidity of the atmosphere, gm/m';

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 are given above. A value of H = 8 grams/ meter',

was used in lieu of site-specific information.

B-10

P Shearon Harris Nuclear power plant (SHNPP) June 1994 Offsite*Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 11 of 15.

DOSE PARAMETERS FOR RADIOZODZNES, PARTICULATES, AND TRITZUM B.2.4 Grass-Cow-Meat Pathwa The integrated concentration in meat follows in a similar manner to the development for the milk pathway; therefore:

t f fs r(l-e i e)

+

iv ( e i b)

F Uaap Ff (DFLi a e

= ZiKQF Ri p s p

-Xitb r(l e -XE it )

Biv(1-e

) e ) (B.2-5) p s Ys XE Phi where:

Ri Dose factor for the meat ingestion pathway for radionuclide for any organ of interest, mrem/yr per pCi/sec per m';

Fg The stable element transfer coefficients, pCi/Kg per pCi/day; U The receptor's meat consumption rate for age group "a,"

ap kg/yr; ts Transport time from slaughter to consumption, sec;

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 12 of 15, DOSE PARAMETERS FOR RADIOIODZNES/ PARTICULATES'ND TRITIUM B.2.4 Grass'-Cow-Meat Pathwa (continued) h Transport time from harvest to animal consumption, sec; te Period of pasture grass and crop exposure during the growing season, sec; Zi Factor to account foz fractional deposition of zadionuclide Ili II For radionuclides other than iodine, I~ is equal to one. For zadioiodines, the value of I~ may vary. However, a value of1.0- 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 Rz for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the Rz is based on X/Q.

R K 'cQrUap (DFLx) a 0. 75 (0. 5/H) (B. 2-6) where:

R Dose factor for the meat ingestion pathway for tritium for any organ of interest, mrem/yr per pCi/m'.

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) Rey. 4 APPENDZX B Sheet 13 of 15 .

DOSE PARAMETERS FOR RADZOZODZNES, PARTZCULATES, AND TRZTZUM B.2.5 Ve etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed in'he 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:

t e) -X tb) i L ~itL r(1-e Ei Biv (1-e v E ~

i r(1-e XE te ) B iv (1-e

-Xitb)

US a fgee ~ith (

Yv XE. P)i (B. 2-7)

E where:

Ri Dose factor for vegetable pathway for radionuclide "i" for the organ of interest, mrem/yr per pCi/sec per m ';

K' constant of unit conversion; 10'P Ci/pCi; 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 RADZOZODZNES, PARTICULATES, AND TRITIUM B.2.5 Ve etation Pathwa (continued)

U" a

The consumption rate of fresh leafy vegetation by the receptor in age group "a," kg/yr; Us a

The consumption rate of stored vegetation by the receptor in age group "a, " kg/yr; The fraction of the annual intake of fresh leafy vegetation grown locally; 1.0 The fraction of annual intake of stored vegetation grown locally; 0.76 The average time between harvest of leafy vegetation and its consumption, sec; The average time between harvest of stored vegetation and its consumption, sec; Yy The vegetation a zeal density, kg/m~;

Period of leafy vegetable exposure during growing season, sec; Zg Factor to account for fractional deposition of radionuclide lli 1I All other factors as defined before.

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 RADIOIODINESi PARTICULATES g AND TRITIUM B.2.5 Ve etation Pathwa (continued)

For radionuclides other than iodine, the factor Zz is equal to one. For radioiodines, the value of Z~ 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 foz f and f~, 1.0 and 0.76, respectively, were used in the calculations on Rz. 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/9:

R V

= K'K' '

fL + U f ~ (DFLi) a 0 ~ 75 (0.5/H) (B.2.8) where:

R Tg Dose factor for the vegetable pathway foz tritium for any organ of interest, mrem/yr per pci/m .

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 Reference Parameter Value (Re . Guide 1.109, Rev. 1)

Q (kg/day) 50 (cow) Table E-3 6 (goat Table E-3 Y (kg/M') 0.7 Table E-15 P

t (seconds) 1.73 E+05 (2 days) Table E-15 r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 radionuclide Table E-11 to E-14 (DFL.

ia

) (mrem/pCi) Each Table E-l (cow)

F m

(pCi/liter per pCi/day) Each stable element Table E-2 (goat)

T (seconds) 4.75 E+08 (15 yr) Table E-15 Y (kr/m') 2.0 Table E-15 s

(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 te (seconds) 2.59 E+06 (pasture) Table E-15 5.18 E+06 (stored feed)

B (pCi/kg [wet weight] Each stable element Table E-1 iv per pCi/kg [dry soil] )

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 (Re . Guide 1.109, Rev. 1) 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 F (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-S 110 adult Table E-5 Each radionuclide Tables E-11 to E-14 (DFL ia

) (mrem/pCi) 0.7 Table E-15 Y (kg/m')

P, Table E-15 Y (kr/m') 2.0 s

(seconds) 4.73 E+08 (15 yr) Table E-15 T

T t

s soil/m'alue (seconds)

(seconds) 1.73 7.78 E+06 (20 days)

E+06 (90 days)

Table Table E-15 E-15 te (seconds) 2.59 E+06 (pasture) Table E-15 5.18 E+06 (stored feed)

Q (kg/day) 50 Table E-3 stable element Table E-1 B.

iv (pCi/kg [wet weight]

per pCi/kg [dry soil] )

Each P (kg dry 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 (Re . Guide 1.109, Rev. 1) r (dimensionless) 1. 0 (radioiodines) Table E-1

0. 2 (particulates) Table E-1 Each radionuclide Tables E-11 to E-14 i

(DFL.) a (mrem/pCi) 50 (cow) Table E-3 Q (kg/day) 6 (goat) Table E-3 U"

a (kg/yr) - Infant 0 Table E-5

- Child 26 Table E-5 Teen 42 Table E-5 Adult 64 Table E-5 U'kr/hr) - Infant ' Table E-5

- Child 520 Table E-5 Teen 630 Table E-5 Adult 520 Table E-5 T (seconds) 8.6 E+04 (1 day) Table E-15 t (seconds) 5.18 E+06 (60 day) Table E-15 2.0 Table E-15 v (kg/m )

Y te (seconds) 5.18 E+06 (60 day) Table E-15 t (seconds) 4.73 E+08 (15 yr) Table E-15 P (kg dry soil/m' 240 Table E-15 iv (pCi/kg (wet weight] Each stable element Table E-1 per pci/kg [dry soil])

B-18

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 1 of 1 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING ZNSTRUMENTATZON NUMBERS Monitor Li uid Effluent Monitorin Instruments Identification Treated Laundry and Hot Shower Tank REM-1WL-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-1SW-3500A from Reactor Auxiliary Building REM-1SW-3500B F ~ Outdoor Tank Area Drain Transfer Pump Moni'toz ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ REM-1MD-3530 Turbine Building Floor Drains Effluent REM-1MD-3528 IZ. Gaseous Effluent Monitorin Instruments A. Plant Vent Stack 1 REM-1AV-3509-SA

RM-21AV-3509-1SA B~ Turbine Building Vent Stack 3A . . . . . . . . . . ~

RM-1TV-3536-1 C. Waste Processing Building Vent Stack 5 . . . . . . . . . REM-1WV-3546

RM-1WV-3546-1 D. Waste Processing Building Vent Stack 5A . . . . . . . . REM-1WV-3547

RM-1WV-3547-1 Wide-Range Gas Monitor (WRGM)

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.I - Instrumentation D.2 - Radioactive Effluents D.3 Radiological Environmental Monitoring

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 D.l INSTRUMENTATZON 3/4 '.3 MONITORING INSTRUMENTATION 3/4.3.3.10 Radioactive Li uid Effluent Monitorin 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 aze not exceeded. The Alarm/Trip Setpoirits of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSZTE 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 return the instrument to OPERABLE status 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 REQUZREMENTS 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

Sheazon Harris Nuclear Power Plant (SHNPP) November 1995 Offsite .Dose Calculation Manual (ODCM) Rev. 7 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 35 Shower Tanks Discharge Monitor

2) Waste Monitor Tanks and Waste 35 Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tank 35, 36*

Discharge Monitor

b. Turbine Building Floor Drains 36 Effluent Line

2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump a Outdoor Tank Area Drain Transfer Pump 37 Monitor 3 ~ Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a ~ Normal Service Water System Return 39 From Waste Processing Building to the Circulating Water System

b. Normal Service Water System Return 39 From the Reactor Auxiliary Building to the Circulating Water System Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Lines Treated Laundry and Hot 38 Shower Tanks Discharge

2) Waste Monitor Tanks and Waste 38 Evaporator Condensate Tanks Discharge

3) Secondary Waste Sample Tank 38

b. Cooling Tower Blowdown 38 When the Secondary Waste System is being used in the continuous release mode, 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 aze analyzed for radioactivity at a lower limit of detection of no more than 10 '. microCurie/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 microCurie/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 microCuzie/gram DOSE EQUIVALENT I-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 pez 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 10 ~ microCurielml.

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.

Shearon Harris Nuclear Power Plant (SHNPP) November 1995 Offsite .Dose Calculation Manual (ODCM) Rev. 7 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 R(3)

Shower Tanks Discharge Monitor

2) Waste Monitor Tanks and R(3)

Waste Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tank D P, M(5) R(3)

Discharge Monitor

b. Turbine Building Floor Drains R(3) Q(1)

Effluent Line 2 ~ Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump

a. Outdoor Tank Area Drain R(3)

Transfer Pump Monitor

3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System R (3) Q(2)

Return From Waste Processing Building to the Circulating

,Water System

b. Noxmal Service Water System 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. N.A.

Shower Tanks Discharge

2) Waste Monitor Tanks and D (4) N.A. N.A.

Waste Evaporator Condensate Tanks Discharge

3) Secondary Waste Sample Tank D(4) N.A. N.A.

Pump Monitor

b. Cooling Tower Blowdown D(4) N.A. N.A.

D-5

Shearon Harris Nuclear Power Plant (SHNPP) November 1995 Offsite Dose Calculation Manual (ODCM) Rev. 7 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 zoom alarm annunciation occur if any of the following conditions exists:

a Instrument indicates measured levels above the Alarm/Trip Setpoint, or

b. Circuit failure (monitor loss of communications (alarm only),

detector loss of counts (Alarm only) or monitor loss of power), or

c. Detector check source test failure (alarm only), oz

d. Detector channel out of service (alarm only), or

e. Monitor loss of sample flow (alarm only).

(2) The DIGITAL CHANNEL OPERATZONAL TEST shall also demonstrate that control room alarm annunciation occurs if any og the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications , detector loss of counts, oz monitor loss of power), or

c. Detector check source test failuze, or

d. Detector channel out of service, or

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) oz using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standazds 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.

D-6

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Rev. 6 Offsite Dose Calculation Manual (ODCM) 3/4.3.3 MONITORING ZNSTRUMENTATZON 3/4.3.3.11 Radioactive Gaseous Effluent Monitorin Instrumentation OPERATIONAL REQUIREMENT 3.3.F 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 and 3.11.2.5 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. Zf 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 ZNSTRUMENTATZON MIN. CHANNELS INSTRUMENT OPERABLE APPLICABILITY. ACTION GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALYZERS Specification is not used in ODCM

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity Monitor

b. Iodine Sampler Ce Particulate Sampler 49

d. Flow Rate Monitor e Sampler Flow Rate Monitor 46

3. PLANT VENT STACK

a. Noble Gas Activity Monitor 47

b. Zodine Sampler 49 c Particulate Sampler

d. Flow Rate Monitor.

e. Sampler Flow Rate Monitor

4. WASTE PROCESSING BUILDZNG VENT STACK 5 a.1 Noble Gas Activity Monitor (PZG) 45, 51 a.2 Noble Gas Activity Monitor (WRGM) MODES I, 2, 3 52

b. Zodine Sampler Ce Particulate Sampler

d. Flow Rate Monitor Sampler Flow Rate Monitor

5. WASTE PROCESSING BUILDING STACK 5A a Noble Gas Activity Monitor

b. Zodine Sampler 49 C ~ Particulate Sampler

d. Flow Rate Monitor

e. Sampler Flow Rate Monitor 46 TABLE NOTATIONS

At all times.

D-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 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 aze 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 Minimu'm Chanels OPERABLE requirements of Technical Specification Table 3.3.10, initiate the preplanned alternate method of monitoring the appropriate parqameter(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 '.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) August 1995 Offsite Dose Calculation Manual (ODCM) RevE 6 TABLE 4 ~ 3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES FOR WHICH DIGITAL CHANNEL SURVEILLANCE CHANNEL SOURCE CHANNEL OPEIIIITZOIIEZ ~ZE IIE DZIIED INSTRUMENT CHECK CHECK CALIBRATION TEST

1. GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALYZERS Not Used ia the ODOM.

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity R(3) ()(2)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulato Sampler N.A. N.A.

d. Flow Rate Monitor D N.A.

sampler Flow Rate Monitor D N.A.

3~ PLANT VENT STACK

a. Noble Gas Activity Moaitor D R(3) ()(2)

b. Iodine Sampler N.A. N.A.

c. Particulate Sampler N.A. N.A.

d. Flow Rate Monitor N.A.

e. Sampler Flow Rate Monitor D N.A.

4 ~ WASTE PROCESSING BUILDING VENT STACK 5 a.1 Noble Gas Activity Monitor D R(3)

(PIG) a.2 Noble Gas Activity Monitor D R(3) 0(2)

(WRGM)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. N.A.

d. Flow Rate Monitor

e. Sampler Flow Rate Monitor D N.A.

WASTE PROCESSING BVILDING VENT STACK SA

a. Noble Gas ActivityMoaitor R(3) Q(2)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. N.AE

d. Flow Rate Moaitor N.A.

e. Sampler Flow Rate Monitor N.A.

At all times.

D-10

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.3-9 (Continued)

TABLE NOTATIONS The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic (1) isolation of this pathway and control room following conditions exists:

annunciation occur if any of the a Instrument indicates measured levels above the Alarm/Trip Setpoint, or Circuit failure (monitor loss of communications - (alazm only),

detector loss of counts (alarm only) or monitor loss of power), or

c. Detector check source test failure (alarm only), or

d. Detector channel out of service (alarm only), or

e. Monitor loss of sample flow (alarm only) .

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm, annunciation occurs if. any of the following conditions exists:

a. Znstrument indicates measured levels above the Alarm Setpoint, or Circuit failure (monitor loss of communications (alarm only),

detector loss of counts, or monitor loss of power), or c ~ Detector check source test failure, or

d. Detector channel out of service, or

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.

Sheazon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 2 x 10 'icroCurie/ml total activity.

APPLICABILITY: At all times.

ACTION:

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 zesults 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-1 RADZOACTZVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF LIQUZD RELEASE TYPE SAMPLZNG ANALYSIS TYPES OF ACTIVITY DETECTION FREQUENCY FREQUENCY ANALYSIS (LLD)<>>

(pCi/ml)

Batch Waste Rel ease Tanks<'>

P P Principal Gamma -Sx10 a Waste Monitor Each Batch Each Batch Emitters <~>

Tanks I-131

'x10

b. Waste Evaporator P Dissolved and ~

'x10 Condensate One Batch/M Entrained Gases Tanks (Gamma Emitters)

C. Secondary P M H-3 lx10 Waste Sample Each Batch Composite"'

'x10 Tank"'reated Gross Alpha 4

Laundry and Sr-89, Sr-90

'x10 P

Hot Shower Each Batch Composite<"

Tanks Fe-55

'x10

~

2. Rele ases +ontinuous Cooling Tower Continuous'" W Principal Gamma Sx10 Weir Com osite "><'> Emitters <'> '.

Tank"'(7) M<>> Dissolved and lx10 ~

Secondary Waste Sample Grab Sample Entrained Gases (Gamma Emitters)

I-131 lx10 ~

M H-3 Composite'" "'

Continuous"'ontinuous" Gross Al ha lxlo'xl0-'x10 Sr-89, Sr-90 Composite "> <n Fe-55 'xl0

'-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:

4.66 s~

LLD E V '.22 >< 10 Y exp (-XDt)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

s~ = 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),

2.22 x 10' the number of disintegrations per minute per microCurie, the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec '), and Dt = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and ht should be used in the calculation.

Zt should be reoognized that the LLD is defined as an ~a riori (before the fact) limit representing the capability of a measurement system 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) r (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 5 x 10 '. 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:

If theOPERABLE are applicable (NSW or SW) monitors and not in alarm, then no in Table 3.3-12 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 the if 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.

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 '.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.

ACTXON:

'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 Li uid Radwaste Treatment S stem 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:

Explanation of why liquid zadwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason foz the inoperability, Action(s) taken to zestoze the inoperable equipment to OPERABLE status, and r

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 F 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.

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 0 Foz noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mzems/yr to the skin, and

b. For Zodine-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/yz to any organ.

APPLICABILITY: At all times.

ACTION:

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 Zodine-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 suzveillance interval.

D-18

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM M

MINIMUM LIMIT OF SAMPLING ANALYSIS LOWER DETECTION (LLD)(1) ~

M I

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pCi/ml} k'tt rt O Q

1. Waste Gas Storage P P Principal Gamma Emitters( )

Tank Each Tank Each Tank lxlo ~

0 lo tf Grab Sample 0 Qo

2. Containment Purge P P Principal Gamma Emitters( ) lxl0 4 N or Vent Each PURGE Each PURGE( ) I O g g 0 Grab Sample H-3 (oxide) lxlo s + tm rt 0>

M(3). <<).(5)

I ~ 6

3. a. Plant'Vent Principal Gamma Emitters lxlo ~ 0 Stack 0 Grab Sample H-3 (oxide) lxlO Ql lD

b. Turbine Bldg M Principal Gamma Emitters ~

'xl0 Vent Stack, Grab Sample Waste Proc. 0 rt Bldg. Vent H-3 (oxide) (Turbine Bldg. lxlO-'

Stacks 5 & 5A Vent Stack) ~ tA

4. All Release Types Continuous W(7) I-131 lx10 '~

as listed in 1.,2.,

and 3. above Charcoal I-133 lxlo (8), (9), (10) Sample Continuous W(7) Principal Gamma Emitters( ) lxlo 11 Particulate Sample Continuous M Gross Alpha lxlO->>

Composite Particulate Sample Continuous Q Sr-89, Sr-90 ~

lxlO->>

Composite Particulate Sample 00 e rt

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:

LLD -"

4 '6 sb E V 2.22 x 10 ' 'xp (-ggt)

Where:

LLD = the "a priori" lower limit of detection (microCurie 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 oz volume),

2.22 x 10' the number of disintegrations per minute pez microCurie, Y = the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec '), and ht = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and ht should be used in the calculation.

Zt should be recognised that the ihn is defined as an ~ariori (before the fact) limit representing the capability of a measurement system and not as an a posteriori drafter the fact) limit for a particular measurement.

D-20

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 TABLE 4.11-2 (Continued)

TABLE NOTATZONS (Continued)

(2) 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 and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Z-131, Cs-134, Cs-137, Ce-141, and Ce-144 in Zodine and particulate releases.

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.

(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 p6riod.

(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.

(~) 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 EQUZVALENT Z-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-*1WV-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-3509-1SA on Plant Vent Stack l.

D-21

Shearon Harris Nuclear Power plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 T~gE ~.11-2 (Continued)

TJQ3L< 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.

D-22

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 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:

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 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 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 da/s ~

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) Rey. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Zodine-131, Zodine-133, Tritium, and Radioactive Material in Particulate Form OPERATIONAL REQUIREMENT 3,11 '.3 The dose to and a MEMBER OF THE PUBLIC all from Iodine-131, zadionuclides in particulate form with half-lives Iodine-133'ritium, 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 0 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 mzems to any organ.

APPLICABILITY: At all times.

ACTION:

a ~ With the calculated dose, from the release of Zodine-131, Iodine-133, tritium, and zadionuclides 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 zadionuclides 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 S stem 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:

0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to. air from beta radiation, or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

,ACTION:.

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:

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 oz any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION 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 ', 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 achiev'ing 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. Zt shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

the estimated dose(s) exceeds the above limits, and if the release If 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 RADZOLOGZCAL 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 e 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 s'pecified 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 ', 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 (1) + concentration (2) + 51+0 reporting level (1) reporting level (2) o ~ ~

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted the potential annual dose* to a MEMBER OF THE PUBLIC from all if 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 radio'activity 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) Rey. 6 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT ACTZON (Continued):

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 REQU1REMENTS 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

TABLE 3. 12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM* 0 M th 0 EXPOSURE PATHWAY OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY N0 AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 0 Radiation"'UMBER

1. Direct Forty routine monitoring stations Quarterly. Gamma dose quarterly. U X 0

either with two or more dosimeters N or with one instrument for lD I '~

measuring and recording dose rate continuously, placed as follows: Vg 0 C C 0 An inner ring of stations, one in V 8

each meteorological sector in the general area of the SITE BOUNDARY; r0 g 0

An outer ring of stations, one in ZC8 each meteorological sector in the C5 6- to 8-km range from the site; and VIQl The balance of the stations 0 rt to be placed in special interest U n-areas such as population centers, Q V) nearby residences, schools, and 'z in one or two areas to serve as tg tg control stations.

TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM O m

& 0Ql N

EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY r. tt rt 0 AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS lb five locations: Continuous sampler Radioiodine Cannister: UX

2. Airborne Samples from 0 Radioiodine and operation with sample I-131 analysis weekly. Ql 8

Particulate's collection weekly, or Three samples from close to the three SITE more frequently required by dust if no Dl V4 BOUNDARY n c locations, in. different loading. Particulate Sam ler: 6 0 VV sectors, of the highest Gross beta radioactivity I rr p calculated annual average analysis following r. v ground-level D/Q; filter change; "'nd 0 gamma isotopic analysis<'> 'X 0

c One sample from the vicinity of composite (by location) 8 of a community having the quarterly. C highest calculated annual VV average ground-level D/Q; and a0 rr One sample from a control Q location, as for example 15 to U) 30 km distant and in the least prevalent wind tg direction.

3. Waterborne

a. Surface<" One sample upstream. Composite sample over Gamma isotopic period.'" monthly. Composite analysis"'-month for One sample downstream. tritium analysis quarterly.

b. Ground Samples from one or two Quarterly. Gamma isotopic"'nd sources only to be if affected"'.

likely tritium analysis quarterly.

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 LOCATIONS0~ COLLECTION FREQUENCY . OF ANALYSIS

3. Waterbourne (Continued)

c. Drinking One sample in the vicinity Composite sample over I-131 analysis on. each of the nearest downstream 2-week period'" when composite when the dose municipal water supply intake I-131 analysis is calculated for the form the Cape Fear River. performed; monthly consumption of the composite otherwise. water is greater than One sample from a control 1 mrem per location. for gross year.'4'omposite beta and gamma isotopic analyses"'onthly.

Composite for tritium analysis quarterly.

d. Sediment One sample in the vicinity of the Semiannually. Gamma isotopic from cooling tower blowdown discharge analysis'>> semiannually.

Shoreline in an area with existing or potential recreational value.

4. Ingestion

a. Milk Samples from milking animals in Semimonthly when Gamma isotopic"'nd three locations within 5 km animals are on I-131 analysis distance having the highest dose pasture; monthly semimonthly when potential. If there are none, at other times. animals are on pasture; then one sample from milking monthly at other times.

animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr.'"

One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 0 N W O EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY ct 0 AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSu~ COLLECTION FREQUENCY OF ANALYSIS (D

4. Ingestion t7 0

X (Continued) S V

b. Fish and One sample of Sunfish, Catfish, and Sample in season, or Gamma isotopic n N Invertebrates Large-Mouth Bass species in vicinity semiannually if they analysist" on 0 C of plant discharge area. are not 'seasonal. edible portions. rr co rt Ib 0

One sample of same species in areas not influenced by plant discharge. 0 0

c. Food Products Samples of three different kinds Monthly during Gamma isotopic"'nd Z Z S

of broad leaf vegetation grown growing season. I-131 analysis. Ql nearest each of two different offsite locations of highest r Ql tQ predicted annual average ground level D/Q not if performed.

milk sampling is 0 n-a rt g m~(

z One sample of each of the similar MOnthly during Gamma isotopic<" and Pg broad leaf vegetation grown 15 to growing, season. I-131 analysis.

30 km distant in the least prevalent wind direction not performed.

if milk sampling is

Shearon Harxis Nucleax Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-1 (Continued)

TABLE NOTATIONS Specific parameters of distance and direction sector from the centerline of one xeactor, 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 hazazdous 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 '.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 altexnative 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

)ustifying the selection of the new location(s) foz obtaining samples.

One or more instruments, such as a pressurized ion chamber, for measux'ing and recording dose rate continuously may be used in place of, or in addition to, integrating dosimetezs. For the purposes of this table, a thermoluminescent

'osimetex (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 numbex. 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 ox'eadout for TLD systems will depend upon the chazactexistics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 progxam 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'his source is tapped for drinking oz irrigation purposes in areas whexe the hydraulic gradient or recharge properties aze suitable for contamination.

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES O V)

W 8 Ql WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS A0 ANALYSIS (pci/1) OR GASES ( Ci/m') (pCi/kg, wet) (pci/1) (pCi/k , wet) 8 H-3 20, 000* 0 8

Mn-54 1, 000 30, 000 n~

Ql Fe-59 400 10, 000 M

0 C 4

r n Co-58 lr 000 30, 000 8 rt Q r

0

~

Co-60 300 10, 000 0

3l Z Zn-65 300 2Q, OOQ S Zr-Nb"95 400 er Q tQ I-131 0.9 100 0 rt n-U g M Cs-134 30 10 1 I 000 60 1, 000 Cs-137 50 20 2s 000 70 2, 000 Ba-La-140 200 300

For drinking water samples:

of 3Q,OOO pCi/1 may be used.

This is 40 CFR Part 141 value. If no drinking water pathway exists, a value

"Ifno drinking water pathway exists, a value of 20 pCi/l may be used.

TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS~>>>> o>>

0 th W M

tb 8 LOWER LIMIT OF DETECTION LID V' N 0 WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT t>> X ANALYSIS ( Ci/1) OR GASES (pCi/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry) 0 M

8 Gross Beta 0.01 n~

H-3 2000* >>

n r.

4 0

Mn-54 15 130 >>>>>> 0 K>>>>>>

V 0

Fe-59 30 260 Co-58, 60 15 130 8 Zn-65 30 260 Ql

>> r lg Zr-Nb-95 0 rt n-t>>

g Vl I-131 0.07 60 tQ Cs-134 15 0.05 130 15 60 150 ~ Q Cs-137 18 0.06 150 80 180 Ba-La-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/1 may be used.

- Ifno drinking water pathway exists, a value of 15 pCi/1 may be used.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 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) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) 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 wi.th 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 2.22 . Y exp (-Xbt)

Where:

LLD = the "a priori" lower limit of detection (picocurie per unit mass or volume),

Sg 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),

the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picoCurie, the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide (sec-'), and the elapsed time between environmental collectio'n, or end of the sample collection period and the time of counting (sec) .

Typical values of E, V, Y, and ht should be used in the calculation.

D-37

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 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'ccasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. 1n such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.

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 m~ (500 ft~)

producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

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 ', 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 oz 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 supp'orting the change in sampling locations.

SURVEILLANCE REQUIREMENTS 4.12 ' The Land Use Census shall be conducted during the growing season at least once pez 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.12.3 ZNTERLABORATORY COMPARISON PROGRAM OPERATIONAL REQUIREMENT 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that, correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a 0 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.l.

SURVEILLANCE REQUIREMENTS 4.12.3 The Znterlaboratozy 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

,0 APPENDIX E PROGRAMMATIC CONTROL BASES The Bases for the ODCM Operational Requirements are detailed in Sections:

E.l Instrumentation E.2 - Radioactive Effluents E.3 - Radiological. Environmental Monitoring

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 Li uid Effluent Monitorin 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 Pazt 50.

3/4.3.3.11 Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual oz 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 1 x 10

'Ci/ml are measurable.

E-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTXVE EFFLUENTS BASES 3/4. 11. 1 LIQUXD EFFLUENTS 3/4.11.1.1 Concentration This Operational Requizement 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 matezials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section IZ.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),

Currieg L A Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, " Anal. Chem. 40, 586-93

~ g (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, IIZ.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section ZZ.A of Appendix I. The ACTXON statements provide the zequired 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 UNRESTRXCTED AREAS will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the ODCM implement the requirements in Section IIZ.A of Appendix I that conformance with the guides of Appendix X be shown by calculational pzocedures 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 ED 2 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.2 Dose (continued) k 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.

314. 11. 1. 3 Li uid Radwaste Treatment, S stem 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 zadioactive 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.

Shearon Hazris 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 IZ, 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 ZZ of 10 CFR Part 20 [10 CFR.Part 20.106(b)J. 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 zestr3:ct, 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 LLDi 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 Hanfozd Company Report ARH-SA-215 (one 1975).

E-5

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/a.11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose Noble Gases This Operational Requirement is provided to implement the requizements of Section ZI.B, ZZZ.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section Z.B of Appendix Z. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section ZV.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'

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 I'/4.11.2.3 GASEOUS EFFLUENTS Dose Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form This Operational Requirement is provided to implement the requirements of Sections IX.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirements are the guides set forth in Section IZ.C of Appendix Z. The ACTION statements provide the required operating flexibility and at the same time implement the guides- set forth in Section ZV.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 ZXI.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 aze 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 S stem The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTXLATION 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 XZ.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 IZ.B and XI.C of Appendix X, 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 RAD1'OACTIVE 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.4 TOTAL DOSE This Operational Requirement is provided to meet the dose limitations of 10 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 mzems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Foz 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 20.405c, 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-10

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 zesulting 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 ~ariori (before the fact) lind.t representing the capability of a particular measurement.

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).

3/4.12.2 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 aze 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 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/m2.

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.

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.l - Annual Radiological Environmental Operating Report F.2 - Annual Radioactive Effluent Release Report F.3 - Major changes to the Radwaste Treatment System (liquid and gaseous)

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 F.l Annual Radiolo ical Environmental 0 eratin Re ort (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 OFFSZTE 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. Zn 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 all sampling locations keyed to a table giving distances and maps'overing directions fzom the centerline of the reactor; the results of licensee participation in the Znterlaboratory 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Annual Radioactive Effluent Release Re ort (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 g June 1974, with data summarized on a quarterly basis fol lowing the format of Appendix B thereof.

The Annual Radioacpive Effluent Release Report shall include an annual summary of hourly meteorological data collected over'he 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 frqguency distributions of wind speed, wind direction, and atmospheric stability. This report shall include an

'assessment of the radiation doses 'due to th'0 radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

This report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Technical Specification Figure 5.1-3) during the report period.

All assumptions used in making these assessments; i.e., specific activity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. 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." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.

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.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 F.2 Annual Radioactive Effluent Release Re ort (continued)

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to UNRESTRICTED AREAS, of radioactive matezials 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 foz 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 expganation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not cozrected 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 3.11.2.6, respectively.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 F.3 Ma or Chan es to Li uid and Gaseous Radwaste Treatment S stems (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 in accordance with Specification 6.5. The discussion of each change shall contain:

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.

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 in accordance with Technical Specification

6. 5.

Shall become effective upon review and acceptance in accordance with Technical Specification 6.5 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 entize 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 I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, Z-133, I-134, and I-135 actually present. The thyzoid dose conversion factors used for this calculation shall be those listed in Table ZZZ of TZD-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

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.

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

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 Crom the primary system and providing for delay or holdup foz the purpose of reducing the total radioactivity prior to release to the environment.

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.

OFFSZTE DOSE CALCULATION MANUAL The OFFSZTE 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 all necessary it is capable of performing its specified function(s),and when attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that aze required foz 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 PURGZNG shall be any controlled process of discharging aiz 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.

G-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 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 .VENTZLATION 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) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 TABLE G-1 FREQUENCY NOTATION NOTATION FREQUENCY' At least once per 12 hours.

At least once per 24 hours.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

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.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rey. 6 TABLE G-2 OPERATIONAL MODES Mode Reactivity Keff RATED AVERAGE COOIANT Condition THERMAL POWER* TEMPERATURE Power 0 erations w 0.99 > 5% 350'F Startu w 0.99 s 5% 350'F Hot Standb 0.99 > 350 F Hot Shutdown 0.99 350'F > Tavg > 200'F Cold Shutdown 0.99 c 200'F Refuelin "' 0.95 s 140'F Excluding decay heat.

.Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

ML18012A239

Text

SUBJECT:

1.0 INTRODUCTION

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