Text

Annual Radioactive Effluent Release Rept 960101-1231. W/970414 Ltr
	ML18022B014
Person / Time
Site:	Harris
Issue date:	12/31/1996
From:	Robinson W; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HNP-97-084, HNP-97-84, NUDOCS 9704220349
	Download: ML18022B014 (311)
	v • d • e

l CATEGORY j.

REGULAT ~i INFORMATION DISTRIBUTION ~ STEM (RIDS)

'..w:>>>>

FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina DOCKET 05000400 AUTH. NAME AU'ZHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION ~z~~)

SUBJECT:

adioactive Effluent Release Rept 960101-1231."

/970414 1 DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES:Application for permit renewal filed. 05000400 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR, ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 0-LE,N 1 1 INTERNAL: ACRS 1 1 ILE CE TE -M. 1 1 NRR/DRPM/PERH/A 1 1 RGN2 DRS/RSB 1 1 RGN2 FILE 1 1 EXTERNAL: NRC PDR 1 1 D

0 C,

U E

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

'1 J

U n

Carolina Power 8 Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris NUclear Plant APR 1 4 1997 United States Nuclear Regulatory Commission Serial: HNP-97-084 ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 ANNUAL'ADIOLOGICALEFFLUENT RELEASE REPORT

Dear Sir or Madam:

In accordance with Technical Specification 6.9.1.4 for the Shearon Harris Nuclear Plant, Carolina Power & Light Company provides the enclosed Annual Radiological Effluent Release Report for 1996.

Ifyou have questions or need additional information regarding this report, please contact Ms. D. B. Alexander at (919) 362-3190.

Sincerely, MV Enclosures AQP$ $ Q c: Mr. J. B. Brady (HNP Senior NRC Resident)

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

Mr. N. B. Le (NRC - NRR Project Manager) 97042V0Se9 SeXasX PDR ADQCK 05000400 g 10lI1111llMIlllllllLlll c PDRQ State Road 1134 NewHill NC Tel 919362-2502 Fax 919362-2095

E Carolina Power 4 Light Shearon Harris Nuclear Power Plant License No. NPF-063 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT January 1, 1996 to December 31, 1996 Prepared by:

Senior Analyst - Chemistry Reviewed by:

Su erintenden - Chemistry Approved by:

General Manager - Harris Plant

Table of Contents Page No.

Introduction 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)

Appendix 5. Changes to the Environmental Monitoring Program

1. Environmental Monitoring Program

2. Land Use Census Appendix 6. Additional Technical Specification Responsibilities

1. Inoperability of Liquid Effluent Monitors 6/1

2. Inoperability of Gaseous Effluent Monitors 6/2

3. Unprotected Outdoor Tanks Exceeding Limits 6/2

4. Gas Storage Tanks Exceeding Limits 6/3 Appendix 7. Major Modifications to Radwaste System 7/1 Appendix 8. Meteorological Data 8/1 Appendix 9. Assessment of Radiation Doses

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 the Most Likely Exposed Member of the Public 9/4

4. Major Assumptions used to Calculate Radiation Doses 9/8

Introduction This Annual Radioactive Effluent Release Report is prepared in accordance with Shearon Harris Nuclear Power Plant's Operational Requirements - Offsite Dose Calculation Manual (ODCM), Section F.2, Technical Specification 6.9.1.4, Operating License No. NPF-63.

The Shearon Harris Nuclear Power Plant (SHNPP) achieved initial criticality on January 3, 1987. This Report covers the period from January 1, 1996 to December 31, 1996. During this period, the plant continued in Cycle 7 operation. The radiological dose assessment from radioactive releases during January 1, 1996 through December 31, 1996 is in Appendix 9 of this report.

Discussion

1. Protection Standards The main objective in the control of radiation is to ensure that any exposure is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA) . The ALARA concept applies to reducing radiation exposure both to workers at Harris Nuclear Plant and to the general public. "Reasonably achievable" means that radiation exposure reduction is based on sound environmental practices, economic decisions, and operating practices. By practicing ALARA, Harris Nuclear Plant and 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 primary coolant water. The types of radioactive material released are noble gases, iodines and particulates, and tritium.

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

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

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. Xenon-133 and Xenon-135 with half-lives of approximately 5 days and 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months respectively, are the major isotopes released. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay. Noble gases are readily dispersed in the atmosphere.

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

S. 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.

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

The plant radiation monitoring system has monitors that are designed to ensure that all releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set lower than the regulatory limits, typically at 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 effluent composition than in-plant monitoring instruments.

The plant has a meteorological tower which is linked to computers which record the meteorological data. The meteorological data and the release data is used to calculate the dose to the public.

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

Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure 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 to 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 Harris are calculated for gaseous and liquid releases. The exposure due to radioactive material released in gaseous effluents is calculated using f'actors such as the amount of radioactive material released, the concentration beyond the site boundary,'eather 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.

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. For the period January 1, 1996 through December 31, 1996 no solid waste was,shipped offsite for burial. All radioactive solid waste generated at Harris Nuclear Plant is stored onsite.

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.

The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the Harris Nuclear Plant during the period from January 1, 1996 through December 31, 1996.

During the period of January 1, 1996 through December 31, 1996, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

3. 05 8-02 millirem, Total Body 3.76 E-02 millirem, Max Organ (Gi-LLi)

Gaseous Effluents:

5.30 E-02 mrad, Total Body 6.02 E-02 mrad, skin These doses are much lower than anyone would received from natural background in the area surrounding the Harris Nuclear Plant (300 millirem per year).

0 Appendix 1: Supplemental Information A. Fission and Activation Gases:

Technical Specifications Maximum Instantaneous Release Rate Total Body Dose ~500 mrem/yr Skin Dose ~3000 mrem/yr 10CFR20, Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table II, Column 1. This is based on 100 mrem/yr.

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

Beta Dose ~10 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 s1500 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 g7.5 mrem (Used for calculating percent of applicable limit.)

For Calendar Year <15 mrem C. Liquids:

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

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

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 <1.5 mrem Any Organ Dose ~5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 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, 90, Iron-55, and Nickel-63 Analyses are performed on quarterly composite samples times the volume released during the quarter to calculate the activity released.

D. Estimated Total Errors

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

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

Appendix 1 (Continued): Supplemental Information III. Batch Releases (First Six Months 1996)

A. Liquid Batch Releases Jan - June 1996 July - Dec 1996 Number of batch releases 3.40 E+01 3.80 E+01 Total time period for batch 2.32 E+04 minutes 2.96 E+04 minutes releases Maximum time of a batch release 9.49 E+02 minutes 2.17 E+03 minutes Average time for a batch release E+02 minutes 7.78 E+02 minutes for batch release 2.41 E+02 minutes 2.48 E+02 minutes Minimum Time release'.83 a

Average stream flow during periods of 4.33 E+03 cfs 4.49 E+03 cfs

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

B. Gaseous Batch Releases Jan - June 1996 July - Dec 1996 Number of batch releases 3.00 E+00 1.00 E+00 Total time period for batch 2.23 E+03 minutes 9.90 E+02 minutes releases Maximum time of a batch release 9.67 E+02 minutes 9.90 E+02 minutes Average time for a batch release 7.43 E+02 minutes 9.90 E+02 minutes Minimum Time for a batch release 4.79 E+02 minutes 9.90 E+02 minutes C. Abnormal Releases

a. Liquid No abnormal liquid releases were made during 1996.

b. Gaseous No abnormal gaseous releases were made during 1996.

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

1. LLDs for Gaseous Effluents Gross Alpha 4.63 E-16 H-3 4.25 E-09 Ar-41 2.13 E-08 Kr-85 2.23 E-06 Kr-85m 5. 14 E-09 Kr-87 2.37 E-08 Kr-88 2.41 E-08 Xe-131m 2.40 E-07 Xe-133 1.49 E-08 Xe-133m 5.08 E-08 Xe-135 7.12 E-09 Xe-135m 7.76 E-09 Xe-138 1.26 E-07 I-131 1.52 E-14 I-133 3.04 E"14 I-135 3.41 E-13 Cr-51 8.85 E-14 Mn-54 9.24 E-15 Co-58 2.45 E-14 Fe-59 6.06 E-14 Co-60 1.55 E-14 Zn-65 2.52 E-14 Sr-89 4.13 E-15 Sr-90 1.56 E-15 Nb-95 8.40 E-15 Zr 95 1.50 E-14 Mo-99 1.72 E-13 Cs-134 2.79 E-14 Cs-137 2.65 E-14 Ba-140 7.73 E-14 La-140 1.97 E-14 Ce-141 1.67 E-14 Ce-144 4.14 E-14

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

2. LLDs for Liquid Effluents al ul Gross Alpha 7.68 E-08 Sb-124 6.11 E-08 Cr-Sl 1.76 E-07 Sb-125 1.28 E-07 Mn-54 1.61 E-08 Sb-126 1.99 E-08 Fe-55 2.52 E-08 I-131 3.32 E-08 Co-57 8.13 E-09 I-133 4.19 E-08 Co-58 4.28 E-08 Te-132 2.23 E-08 Fe-59 3.64 E-08 Xe-133 5.33 E-08 Co-60 2. 43 E-08 . Xe-133m 1.93 E-07 Ni-63 3.27 E-08 Xe-135 2.76 E-08 Zn-65 9.77 E-08 Cs-134 5.65 E-08 Sr-89 3.30 E-08 ~ Cs-137 5.22 E-08 Sr-90 1.31 E-08 Ba-140 4.24 E-08 Nb-95 4.05 E-08 La-140 8.14 E-08 Zr-95 2.66 E-08 Ce-141 2.98 E-08 Mo-99 3.06 E-07 Ce-144 1.78 E-07 Tc-99m 1.83 E-08 Ru-106 1.25 E-07 2/2

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released

'i Table lA : GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error 9o A. Fission and activation ases

1. Total release Ci 1.11 E+01 1.25 E+01 5.27 E+01

2. Avera e release rate for eriod Ci/sec 1.41 5+00 1.58 E+00 f

3. Percent of Tech Spec limit 4.98 E-02 7.80 E-02 B. Iodines

1. Total iodine-131 0.00 E+00 9.53 E-07 3.18 E+01

2. Avera e release rate for eriod /rCI/sec 0.00 E+00 1.21 E-07

3. Percent of Tech S ec limit 1.83 E-01 1.76 E.01 C. Particulates

1. Particulates with half. lives ) 8 da s Ci 9.83 E-06 1.32 E-05 3.37 5+01

2. Avera e releaso rate for eriod yCI/sec 1.25 E-06 1.68 E.06

3. Percent of Tech S ec limit " 1.83 E-01 1.76 E-01

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

'CI/sec

1. Total release Ci 1.01 E+01 9.62 E+00 3.37 E+01

2. Avera e refeaso rate for eriod 1.29 E+00 1.22 E+00

3. Percent of Tech S ec limit 1.83 E-01 1.76 E.01 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM mothodoiogy and paramoters. The quarterly Tochnical Specification limit is 7.5 millirem. The most critical organ for both quarters was tho [u9g

Appendix 2 (Continuedjt 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 5.73 5+00 1.36 E+01 5.27 E+01

2. Avera e release rate for period yCi/sec 7.21 E-01 1.71 E+00

3. Percent of Tech S ec limit 3.99 E-02 9.76 E-02

8. lodinos

'i/sec

'i

1. Total iodine-131 Ci 0.00 5+00 0.00 E+00 3.18 5+01

2. Avera e release rate for eriod 0.00 E+00 0.00 5+00

3. Percent of Tech S ec limit 5.59 E-02 4.04 E-02 C. Particulates

1. Particulates with half*fives >8 days Ci 9.15 E.06 8.22 E-06 3.37 E+01

2. Avera o release rato for eriod yCi/sec 1.15 E.06 1.03 E-06

3. Percent of Tech Spec limit 5.59 E-02 4.04 E.02 Gross al ha radioactivit Ci < LLD < LLD D. Tritium

1. Total release 3.06 E+00 2.20 E+00 3.37 E+01

2. Avera e release rate for eriod yCi/sec 3.85 E-01 2.77 E-01

3. Percent of Tech Spec limit 5.59 E-02 4.045-02 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM mothodology and parameters. The quarterly Technical Spocification limit is 7.5 millirem. The most critical organ for both quarters was the lu'ng f

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

0

ndix 2 {Continued): Effluent and Waste Dis Report Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode aatch Modo Nuclides Released Unit Quarter 1 . Quarter 2 Quarter 1 Quarter 2

1. Fission ases xenon.131m Ci < LLO < LLO 9.82 E.04 Note 1 xenon.133 Ci 4.73 E+00 2.38 5+00 9.14 E.02 Note 1 xenon.133m Ci < LLD < LLO S.G4 E.04 Note 1 xenon.135 Ci 5.82 E+00 1.01 5+01 6.97 E.04 Note 1 xenon-135m Ci < LLD < LLD < LLO Note 1 xenon-138 Ci < LLD < LLO < LLD Note 1 ar on-41 Ci < LLO < LLD < LLD Noto 1 kr ton.85 Ci < LLO < LLO 4.38 E-01 Note 1 kr ton 85m Ci < LLD < LLD < LLO Note 1 kr ton 87 Ci < LLO < LLO < LLO Note 1 kr ton 88 Ci < LLD < LLO < LLO Note 1 Total for eriosd Ci 1.0G 5+01 1.25 E+01 5.32 E-01

2. lodines iodine-131 Ci < LLO 9.53 E-07 Note 2 Note 2 iodine-133 Cl < LLO < LLO Note 2 Note 2 iodine.135 Ci < LLD < LLD Note 2 Note 2 Total for eriod Ci < LLO 9.53 E.07

3. Particulates chromium.51 Ci < LLD < LLD Note 2 Note 2 manganese.54 Ci < LLO < LLD Note 2 Nota 2 cobalt.58 Ci < LLD < LLD Note 2 Note 2 iron 59 Ci < LLD < LLO Note 2 Note 2 cobalt-60 Ci 9.83 E-06 1.32 E-05 Note 2 Note 2 zinc.65 Ci < LLD < LLD Note 2 Note 2 strontium.89 Ci < LLO < LLO Note 2 Note 2 strontium.90 Ci < LLO < LLO Note 2 Note 2 niobium.95 Ci < LLO < LLO Note 2 Note 2 zirconium.95 Ci < LLD < LLD Noto 2 Note 2 mol bdenum.99 Ci < LLD < LLD Note 2 Note 2 cesium-134 Ci < LLO < LLD Note 2 Note 2 cesium-137 Ci < LLO < LLD Note 2 Note 2 barium-140 Ci < LLD < LLO Note 2 Nota 2 lanthanum.140 Ci < LLO < LLO Note 2 Note 2 cerium-141 Ci < LLD < LLO Note 2 Noto 2 cerium.144 Ci < LLO < LLD Note 2 Noto 2 Total for criod Ci 9.83 E 06 1.32 E 05 ote 1 --24o aatch rfctcases were made.durinn second uarter of 199G.

z't ote z the partrcurate anc ioamc actrvitrcs rcleasec trom batch releases are included in the determinations from tho continuous releases.

Appendix 2 fContinued): Effluent and Waste Disposal Report Enclosure 2: E(fluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Modo Batch Mode Nuclides Aafeased Unit Quaner 3 Quarter 4 Quarter 3 Quarter 4

1. Fission gasos xenon.t 31m Ci < LLD < LLD Nots 1 3.23 E.04 xenon.133 Ci 4.34 E.ol 3.54 E 01 Note 1 2.89 E 03 xenon 133m Ci < LLD < LLD Nots 1 < LLO xenon.135 Ci 5.29 E+00 1.31 E+01 Note 1 3.75 E.05 xenon-135m Ci < LLD < LLO Note 1 < LLO xenon-138 Ci < LLD < LLO Nots 1 < LLO ar on 41 Ci < LLO < LLO Nots 1 < LLD kr ton.85 Ci < LLO < LLD Noto 1 1.25 E-01 kc ton-85m Ci < LLD < LLO Nota 1 < LLO kr ton 87 Ci < LLD < LLO Note 1 < LLO kr ton 88 Ci < LLO < LLD Nota 1 < LLD Total for ariod Ci 5.73 5+01 1.34 E+01 1.29 E.o 1

2. lodinas iodine 131 Ci < LLO < LLO Note 2 Nots 2 iodine.1 33 Ci < LLO < LLO Nota 2 Nots 2 iodine.135 Ci < LLD < LLO Note 2 Note 2 Total for criod Ci < LLD < LLD

3. Particulates chromium.51 Ci < LLO < LLO Nota 2 Nota 2 man anese.54 Ci < LLD < LLD Note 2 Note 2 cobalt-58 Ci < LLO < LLD Nota 2 Nota 2 iron 59 Ci < LLD < LLO Note 2 Note 2 cobalt 60 Ci 9.15 E-OG 8.22 E.OG Nots 2 Nots 2 zinc 65 Ci < LLD < LLD Note 2 Nots 2 strontium 89 Ci < LLO < LLD Nots 2 Nato 2 strontium 90 Ci < LLD < LLO Noto 2 Nota 2 niobium 95 Ci <LLD <LLD Nots 2 Note 2 zirconium 95 Ci <LLD < LLO Nots 2 Note 2 mol bdenum 99 Ci < LLD < LLO Note 2 Nots 2 cesium-134 Ci < LLD < LLD Nots 2 Nato 2 cesium-137 Ci < LLD < LLO Nots 2 Nots 2 barium 140 Ci < LLD < LLO Nots 2 Nots 2 lanthanum 140 Ci < LLO < LLO Nots 2 Note 2 cerium.141 CE < LLD < LLD Noto 2 Noto 2 cscium 144 Ci < LLD < LLD Note 2 Noto 2 Total for period Ci 9.15 E-06 8.22 E.06 1 - Ihcre wars no Batch Relsasos in,tho third auartec of 1996 oto 2 Ph Pne c'arucutate and foams actnnties celeaserr crom batclt releases are included in tho determinations from tire continuous releases.

C'te 2/7

Appe dix 2 (Continued): Effluent and Waste Disp sal Report Enclosure 2: tffluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (FIRST SIX MONTHS)

Unit Quarter Quarter Est. Total 1 2 Error jo A. Fission and Activation products

1. Total release (not including tritium, Ci 1.64 E-02 1.76 E-02 3.28 E+01 ases, alpha)

2. Average diluted concentration during pCi/ml 2.57 E-09 2.63 E-09 period

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

1. Total release Ci 9.12 E+01 1.54 E+02 3.28 E+01

2. Average diluted concentration during pCI/ml 1.42 E-05 2.30 E-05 penod

3. Percent of applicable limit 1.42 E+00 2.30 E+00 C. Dissolved and entrained ases

1. Total release Ci 3.42 E-04 1.54 E-03 3.28 E+01

2. Avqraqe diluted concentration during yCI/ml 5.34 E-11 2.30 E-10 penod=

3. Percent of applicable limit 2.67 E-05 1.15 E-04 D. Gross alpha radioactivity

1. Total release Ci ( LLD < LLD 3.28 E+01 E. Volume of waste released (prior to dilution) liters 9.88 E+05 1.19 E+06 1.00 E+01 F. Volume of dilution water used durin period liters 6.41 E+09 6.67 E+09 1.00 E+01

Table 2A:

~... Enclosure 2: tffluents Released

~

Appendix 2 (Continued): Effl>ent and Waste Disposal Report LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (SECOND SIX MONTHS)

Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and Activation products

1. Total release (not including tritium, Ci 1.37 E-02 1.23 E-02 3.28 E+01 ases, alpha)

2. Average diluted concentration during yCI/ml 2.00 E-09 2.00 E-09 penod

3. Percent of applicable limit 2.00 E-02 2.00 E-02 B. Tritium

1. Total release Ci 1.26 E+02 8.98 E+01 3.28 E+01

2. Average diluted concentration during yCI/ml 1.84 E-05 1.46 E-05 pe clod

3. Percent of applicable limit 1.84 E+00 1.46 E+00 C. Dissolved and entrained ases

1. Total release Ci 3.75 E-04 4.47 E-04 3.28 E+01

2. Average diluted concentration during pCI/ml 5.49 E-11 7.26 E-11 period

3. Percent of applicable limit 2.74 E-05 3.63 E-05 D. Gross alpha radioactivity

1. Total release Ci < LLD < LLD 3.28 E+01 E. Volume of waste released (prior to dilution) liters 1.82 E+06 6.95 E+05 1.00 E+01 F. Volume of dilution water used durin period liters 6.84 E+09 6.15 E+09 1.00 E+01

0 App dix 2 IContinued): Effluent and Waste Disp sal Report Enclosure 2:, Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 man anese.54 Ci Note 1 Note 1 3.71 E-04 1.74 E-04 iron.55 Ci Note 1 Note 1 7.33 E-04 8.22 E-04 cobalt-57 Ci Note 1 Note 1 < LLD < LLD cobalt.58 Ci Note 1 Note 1 2.94 E-03 3.15 E-03 iron-59 Ci Note 1 Note 1 < LLD 1.19 E-04 cobalt-60 Ci Note 1 Note 1 3.55 E-03 2.62 E.03 nickel 63 Ci Note 1 Note 1 4.10 E-04 4.87 E-04 zinc 65 Ci Note 1 Note 1 < LLO < LLD strontium-89 Ci Note 1 Note 1 < LLO < LLD strontium-90 Ci Note 1 Note 1 < LLD < LLO zirconium-95 Ci Note 1 Note 1 1.31 E-04 5.06 E-05 niobium-95 Ci Note 1 Note 1 2.36 E-04 1.42 E-04 technicium-99m Ci Note 1 Note 1 2.00 E-05 < LLO 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 <LLO 1.32 E-04 1'ote antimon -125 Ci Note 1 1 7.77 E-03 8.75 E-03 antimon -126 Ci Moto 1 Note 1 <LLD < LLO tellurium-132 Ci Note 1 Note 1 <LLD < LLD iodine-1 31 Ci Note 1 Note 1 2.13 E.04 < LLD iodine-1 33 Ci Note 1 Note 1 6.87 E-05 < LLO cesium-1 34 Ci Note 1 Note 1 9.95 E-06 < LLD cesium-137 Ci Note 1 Note 1 5.09 E-05 3.17 E-05 barium.139 Ci Note 1 Noto 1 < LLO < LLD barium-140 Ci Note 1 Note 1 <LLD < LLO lanthanum-140 Ci Note 1 Noto 1 < LLD < LLD cerium-141 Ci Note 1 Note 1 < LLO < LLO cerium-144 Ci Note 1 Noto 1 < LLD < LLD TOTAL Ci Note 1 Note 1 1.65 E-02 1.76 E-02 xenon-133 Ci Noto 1 Note 1 3.42 E-04 1.47 E-04 xenon-133m Ci Note 1 Note 1 < LLD 1.79 E-05 xenon-135 Ci Note 1 Note 1 < LLD 5.41 E-05 TOTAL Ci 3.42 E-04 1 r54 E.03 Note 1 - No Continuous Releases were made during first or second quarters 2/iO

App ndix 2 (Continued): Effluent and Waste Disp sal Report Enclosure 2: Effluents Released Table 28: LIQUID Ei=i=LUENTS nin>> M d Ba h Mori Nfli Rla ni r4 Iaf r4 hr miIm 1 Ci N 1 (L 0 447 - 4 Note 1 - No Continuous Releases were made during third or fourth quarters

Appendix (Continued): Effluent and Waste sposal 'Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS HNP was prohibited from burying or disposing of radioact'ive solid waste materials at a licensed facility during 1996. Consequently, all values reported in Table 3 refer to radioactive solid waste materials processed and returned to HNP, during 1996, for interim storage awaiting future burial.

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

A. Type of Waste "Number of Shipments" discussed in 1.A.a and 1.A.b are the same 2 shipments.

a. Cartridge/Mechanical Filters Number of Shipments 2 Activity Shipped 3.94 E+01 Ci Estimated Total Error 142~o Quantity Shipped 1.54 E+00 m~

Solidification Agent N/A Container Type NRC-Approved Package /

Shipment Form Dewatered, Compacted

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

Number of Shipments 2 Activity Shipped 2.26 E+01 Ci Estimated Total Error 175%'.62 Quantity Shipped E+00 m~

Solidification Agent N/A Container Type NRC-Approved Package Shipment Form Dewatered, Compacted

c. Irradiated Components, Control Rods, etc.

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

d. Other (Describe)

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

2/12

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

Estimate of Major Nuclide Composition (by type of Waste)

a. Cartridge/Mechanical Filters Percent Total Activity Nuclide Composition Ci H"3 3.70 E-02 1.46 E-02 C"14 4.20 E-02 1.64 E-02 Mn-54 5.00 E-01 1.97 E-01 Fe-55 7.40 E+01 2.90 E+01 Co-60 1.80 E+01 7.18 E+00 Ni-63 7.40 E+00 2.90 E+00 Sr-90 2.60 E-04 1.02 E-04 Cs-137 8.20 E-02 3.24 E-02 PU-238 5.20 E-04 2.05 E-04 Pu-239 3.00 E-04 1.20 E-04 Pu-241 1.70 E-01 6.76 E-02 Am-241 2.60 E-04 1.08 E-04 Cm-242 3.70 E-04 1.46 E-04 Cm-243 6.60 E-04 2.60 E-04

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

Percent Total Activity Nuclide Composition Ci H-3 1.30 E-01 2.91 E-02 C-14 5.30 E-03 1.19 E-03 Mn-54 1.70 E+00 3.91 E-01 Fe-55 6.20 E+01 1. 41 E+01 Co-58 4.50 E-01 1.02 E-01 Co-60 2.90 E+01 6.63 E+00 Ni-63 5.80 E+00 1.31 E+00 Sr-90 8.90 E-04 2.02 E-04 Nb-95 1.90 E-03 4.31 E-04 Zr-95 1.00 E-03 2.32 E-04 Cs-134 8.30 E-04 1.87 E-04 Cs-137 5.80 E-02 1.31 E-02 Pu-241 3.40 E-02 7.68 E-03 Cm-242 2.10 E-03 4.80 E-05 Cm-243 2.70 E-04 6.10 E-05

c. Irradiated Components, Control Rods, etc.

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

d. Other (Describe)

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

2/13

t S

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

Solid Waste Disposal Number of Shipments

2 Mode of Transportation Truck Destination HNP, New Hill NC (For Storage)

The two type 1.A.a and 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 I

( WASTE CLASS B )

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

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.

0 Appen x 3 : Changes to Process Control rogram (PCP)

Technical Specification 6.13 During this reporting period, HNP has had no major changes to the solid radioactive waste treatment systems.

0

Appendix 4 : anges to the Offsite Dose Calcul ion Manual (ODCM)

Technical Specification 6.14.c During 1996, the ODCM was revised one time as revision 9. 'A description of this revision is listed below.

ODCM Rcv. 9 List of Ch:lngcs Revision 9 to the ODCM provides additional clarification of Secondary Waste Sample Tank sampling when the monitor is inoperable. For Effluent Monitoring Instrumentation the changes define the channels that meet the requirements of the digital channel operational test, clarifies the term annunciator and alarm, defines what is used to acconlplish satisfactory results, and removes the "or" statements.

Section Pa<<c DCSCI'I )tloll Title Page Revised to Rev. 9 Vi Changed revision numbers as appropriate.

LEP VII Changed revision numbers as appropriate Table D-3 Clarification of Secondary Waste Sample Tank sampling when the 3.3-12 monitor is inoperable.'efine Table 4.3-8 D-6 the channels that meet the requirements of the digital channel Notatlolls operational test, clarifies the term annunciator and alarm, defines what i used to accomplish satisfactory results, and removes the "or" statements.

Table 4.3-9 D-l 1 Define the channels that meet the requirements of the digital channel Notations operational test, clarifies the term annunciator and alarm, defines wllat i used to accomplish satisfactory results, and removes the "or" statements.

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 September 1996, no changes were required to the Environmental Sampling Program or to the ODCM.

Offsite Dose Calculation Manual Operati'onal Requirements 3.12.2.a and 3.12.2.b The land-use census that was completed in July and September 1996 resulted in no changes to the ODCM or to the Environmental Monitoring Program.

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 REM-01MD-3528 On 4/4/96 REM-01MD-3528, Turbine Building Drains Radiation Monitor, was declared inoperable due to a loss of sample flow (LOSF). Operations was not able to start the sample pump to clear the LOSF alarm.

This radiation monitor used a swing vane type flow switch. There have been numerous problems with this flow switch, usually caused by debris getting stuck in the flow switch mechanism, causing the flow switch to stick. Maintenance worked on the existing flow switch but could not get it to operate. Maintenance decided to install a new flow switch per ESR 95-00583.

ESR 95-00583 specified installation of a thermal dispersion type flow switch manufactured by Magnetrol, Inc. After installation of the replacement flow switch, Maintenance had difficulty calibrating it.

They requested help from Engineering. With help from Engineering, the thermal dispersion flow switch was calibrated and the radiation monitor was started. It ran for several hours and then tripped on a LOSF.

Maintenance and Engineering trouble shot the flow switch to try and determine the cause of the LOSF. An ultrasonic strap on the flow meter was installed on the radiation monitor and attached to a recorder. By recording the flow it was determined that the LOSF alarms were not real. The alarms were occurring when flow was well above the low flow setpoint. Based on this it was determined that the thermal dispersion flow switch was not working correctly. Engineering decided that the thermal dispersion flow switch would not work in this application.

ESR 95-00583 was revised to replace the existing flow switch with an electromagnetic flow transmitter and a rate meter switch. The electromagnetic flow meter had no obstructions in the flow. Its only requirement was that the liquid be conductive greater than 3 umhos/cm.

The ESR was revj.sed and the new flow instrumentation was installed.

After calibration of the new flow instrumentation, the radiation monitor ran successfully and was declared operable.

The long unavailability was caused by the amount of time required to correct the sample flow measuring problem. An extensive amount of troubleshooting and engineering was performed during this time. The monitor was never declared operable during this time even when it was functioning. The sample flow instrumentation problem appears to be corrected by this modification. During the time period the monitor was inoperable, compensatory sampling was completed in accordance with ODCM Operational Requirement per Table 3.3-12 Action 36.

REM-015W-3500B On 1/29/96 radiation monitor REM-015W-3500B, Normal Service Water System Return from the Reactor Auxiliary Building to the Circulating Water System, was declared inoperable when the detector failed to calibrate when performing a scheduled calibration. Engineering evaluated the situation and recommended changes to the procedure to allow a greater adjustment of the high voltage. The technician attempted to adjust the detector using this procedure change, but the detector still failed to calibrate. A corrective maintenance procedure was revised to include adjustment to the transfer calibration values from the primary calibration.

When the detector failed to calibrate after adjustment of the high voltage, the technician went to the corrective maintenance procedure and proceeded to make adjustment to the transfer calibration values from the primary calibration. These values were obtained but when the multichannel analyzer (MCA) was attached to confirm these values, they did not agree (transfer calibration values compared to MCA values). A second technician and the back-up system engineer attempted the alignment and the same problem occurred.

After exhausting all possibilities, the team decided to perform a new primary calibration and new transfer calibration values were obtained.

These values passed both the corrective maintenance and surveillance calibrations and the monitor was returned to service.

An extensive amount of troubleshooting was exhausted on returning this monitor to service. Two procedure changes and verification testing to ensure the changes worked plus the additional primary calibration were performed. During this time compensatory sampling was performed in accordance with ODCM Operational Requirement Table 3.3-12 3b Action 39.

ODCM Operational Requirement 3.3.3.11 (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 1996 per the Condition Reporting Process. None were inoperable for greater than 30 continuous 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.

6/2

m 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.

lg 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, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses Integrated Population Dose Due to Liquid Effluents (man-rem)

A. 50 mile Ingestion Zone Bone Liver T. Body Thyroid Kidney Lung GZ-LLI Skin Sport Fish 1.59 E-02 1.77 E-02 1.42 E-02 9.01 E-03 1.15 E-02 9.93 E-03 1.94 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 Ey00 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 Ew00 0.00 E+00 Drinking Water 1.09 E-02 8.51 E-01 8.52 E-01 8.50 E-01 8.50 E-01 8.51 E-01 8.65 E-01 0.00 E+00 Shoreline 1.87 E-02 1.87 E-02 1.87 E-02 1.87 E-02 1.87 E-02 1. 8'7 E-02 1.87 E-02 2.18 E-02 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 0.00 E+00 Swimming E-05 5.31 E-05 5.31 E-05 5.31 E-05 5.3) E-05 5.31 E-05 5.31 E-05 0.00 E+00 Boating 5.31 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Zrri Veg 0.00 E+00. 0.00 E+00 0.00 E+00 0.00 E+00 0.00 Zrri Leafy 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 E+00 Irri 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 Zrri 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 4.56 E-02 8.88 E-01 8. 85 E-01 8. 78 E-01 8.80 E-01 8.79 E-01 9.03 E-01 2.18 E-02 Tritium (Hydrosphere)

Bone Liver W. Body Thyroid Kidney Lung GZ-LLZ Total 0.00 E+00 6.16 E-03 6. 16 E-03 6.16 E-03 6.16 E-03 6.16 E-03 6.)6 E-03

2. Integrated Population Dose Due to Gaseous Ef fluents (man-rem) 50 mile Ingestion Zone T. Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin Plume 1.75 E-02 1.75 E-02 1.75 E-02 1.75 E-02 1.75 E-02 1.75 E-02 1.81 E-02 5.91 E-02 Ground Plane 6.30 E-04 6.30 E-04 6.30 E-04 6.30 E-04 6.30 E-04 6.30 E-04 6.30 E-04 7.41 E-04 Inhalation 4.39 E-02 4.40 E-04 3.07 E-08 4.39 E-02 4.39 E-02 4.40 E-02 4.42 E-02 4.39 E-02 1.47 E-02 1.47 E-02 1.56 E-08 1.47 E-02 1.47 E-02 1.47 E-02 1.47 E-02 1.47 E-02 Vegetation 5.20 E-03 2.42 E-08 5.20 E-03 5.20 E-03 5.21 E-03 5.20 E-03 5.20 E-03 Cow Milk 5.20 E-03 5.93 E-03 5.93 E-03 5.93 E-03 Meat a Poultry 5.93 E-03 5.94 E-03 1.71 E-09 5.93 E-03 5.93 E-03 8.79 E-02 8.79 E-02 1.81 E-02 8.79 E-02 8.79 E-02 8.79 E-02 8.87 E-02 1.29 E-01 TOTAL

i(~

Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses

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

Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin ADULT Fish 8.20 E-03 1.03 E-02 8.82 E-03 5.47 E-03 6. 87 E-03 5.96 E-03 1.28 E-02 Drinking 1. 15 E-06 1.16 E-04 ).16 E-04 1.16 E-04 1. 16 E" 04 1.16 E-04 1. 18 E-04 Shoreline 3.23 E-03 3.23 E-03 3.23 E-03 3.23 E-03 3.23 E-03 3.23 E-03 3.23 E-03 3.77 E-03 Boating 4.78 E-05 4.78 E-OS 4.78 E-05 4.78 E-05 4.78 E-05 4.78 E-05 4.78 E-05 TOTAL 1. 15 E-02 1.37 E-02 1.22 E-02 8.86 E-03 1.03 E-02 9.35 E-03 1.61 E-02 3.77 E-03 TEEN Fish 9.02 E-03 9.67 E-03 6.66 E-03 4.42 E-03 5.95 E-03 5.05 E-03 9.79 E-03 Drinking 1.57 E-06 1.17 E-04 1.17 E-04 1.17 E-04 1. 17 E-04 1.17 E-04 1. 19 E-04 Shoreline 2.69 E-03 2.69 E-03 2.69 E-03 2.69 E-03 2.69 E-03 2.69 E-03 2.69 E-03 3.14 E-03 Boating 4.78 E-OS 4.78 E-OS 4.78 E-OS 4.78 E-05 4.78 E-05 4.78 E-05 4.78 E-05 TOTAL 1.18 E-02 1.25 E-02 9.51 E-03 7.27 E-03 8. 81 E-03 7.90 E-03 1.26 E-02 3.14 E-03 CHILD Fish 1.35 E-02 9.72 E-03 5.77 E-03 4.24 E-03 5.76 E-03 4.82 E-03 6.42 E-03 Drinking 4.75 E-06 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 2.26 E-04 Shoreline 1.34 E-03 1.34 E-03 1.34 E-03 1.34 E-03 1.34 E-03 1.34 E-03 1.34 E-03 1.57 E-03 Boating 4.78 E-05 4.78 E-OS 4.78 E-05 4.78 E-05 4.78 E-05 4.78 E-05 4.78 E-05 TOTAL 1.49 E-02 1. 13 E-02 7.39 E-03 5.85 E-03 7.38 E-03 6.43 E-03 8.03 E-03 1.57 E-03 9/2

> tg Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses Du

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

T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT ).13 E-03 Plume 1.11 E-03 1.11 E-03 1.11 E-03 ).1) E-03 1.11 E-03 3.22 E-05 1.)1 E-03 3.22 E-05 3.22 E-05 2.94 E-03 3.79 E-05 Ground Plane 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 8.38 E-08 Inhalation 8.38 E-04 8.38 E-04 5.90 E-10 8.38 E-04 8.38 E-04 8.38 E-04 8.44 E-04 TOTAL 1.98 E-03 1.98 E-03 1. 14 E-03 1.98 E-03 1.98 E-03 1.98 E-03 2.01 E-03 3.82 E-03 TEENAGER E-03 1.13 E-03 2.94 E-03 Plume ).11 E-03 1. 11 E-03 ).11 E-03 1. 1) E-03 1. 11 E-03 1.11 E-05 Ground Plane 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.79 8.30 E-10 8.43 E-04 8.43 E-04 8.44 E-04 8.51 E-04 8.43 E-04 Inhalation 8.43 E-04 8.44 E-04 TOTAL 1.99 E-03 1.99 E-03 1.14 E-03 1.99 E-03 1.99 E-03 1.99 E-03 2.02 E-03 3.82 E-03 CHILD E-03 1. 11 E-03 1. 13 E-03 2.94 E-03 Plume 1. 11 E-03 1.11 E-03 1.11 E-03 1. 11 E-03 1.11 E-05 Ground Plane 3.22 E-OS 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.22 E-05 3.79 Inhalation 7.46 E-04 7.46 E-04 1.13 E-09 7.46 E-04 7.46 E-04 7.46 E-04 7.52 E-04 7.46 E-04 1.89 E-03 ).89 E-03 1.14 E-03 1.89 E-03 1.89 E-03 1.89 E-03 1.92 E-03 3.73 E-03 TOTAL 9/3

0 Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses

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

Bone Liver T. Body Thyroid Kidney Lung Gi-LLI Skin ADULT 1.25 E-02 E-02 Fish 1.72 E-02 -2.16 E-02 1.85 E-02 1.15 E-02 1.44 E-02 2 68 8.46 E-03 8.47 E-03 8.45 E-03 8.45 E-03 8.46 E-03 8.62 E-03 Drinking 8.40 E-05 E-03 1.94 E-03 1.94 E-03 1.94 E-03 1.94 E-03 1.94 E-03 2.26 E-03 Shoreline 1.94 E-03 1.94 1.15 E-04 1.15 E-04 Swimming ).15 E-04 1. 15 E-04 1.15 E-04 1.15 E-04 1.15 E-04 E-04 Boating 1.32 E-04 1.32 E-04 1.32 E-04 1.32 E-04 1.32 E-04 1.32 E-04 1.32 TOTAL 1. 95 E-02 1.32 E-02 2.92 E-02 2.21 E-02 2.51 E-02 2.31 E-02 3.V6 E-02 2. 26 E-03 TEEN E-02 1.01 E-02 1.96 E-02 Fish 1.80 E-02 1.93 E-02 1.33 E-02 8.84 E-03 1.19 E-03 Drinking 8.01 E-05 5.97 E-03 5.97 E-03 5.96 E-03 5.96 E-03 5.97 E-03 6.07 Shoreline 1.08 E-02 1.08 E-02 1.08 E-02 1.08 E-02 1.08 E-02 ).08 E-02 1.08 E-02 1.26 E-02 1.72 E-04 1.72 E-04 Swimming Boating 1.72 E-04

1. 91 E-04 1.72 1.91 E-04 E-04 1.72 1.91 E-04 E-04 1.72 1.91 E-04 E-04 l. 91 E-04 1.72 E-04 1.91 E-04 ).91 E-04 TOTAL 2.93 E-02 3.65 E-02 3.05 E-02 2.60 E-02 2.90 E-02 2.72 E-02 3.68 E-02 1.26 E-02 CHILD E-03 7.31 E-03 9.94 E-03 8.31 E-03 1.11 E-02 Pish 2. 33 E-02 1.68 E-02 9.95 E-02 1.14 E-02 1.15 E-02 Drinking 2.42 E-04 1. 14 E-02 1.14 E-02 1.14 E-02 1.14 Shoreline 2.26 E-03 2.26 E-03 2.26 E-03 2.26 E-03 2.26 E-03 2.26 E-03 2.26 E-03 2.64 E-03 Swimming 5.74 E-05 5.74 E-05 5.74 E-05 5.74 E-05 5.74 E-05 5.74 E-05 5.74 E-05 Boating 7.18 E-OS 7.18 E-05 7.18 E-OS 7.18 E-05 7.18 E-OS 7.18 E-05 7.18 E-05 TOTAL 2.59 E-02 3.06 E-02 2.38 E-02 2.11 E-02 2.37 E-02 2.21 E-02 2.50 E-02 2.64 E-03 INFANT 0.00 0.00 E+00 0.00 E+00 Fish 0.00 E~OO 0.00 E+00 0.00 E+00 0.00 E+00 E+00 E-02 Drinking 1.94 E-04 1.12 E-02 1.12 E-02 1.12 E-02 1.12 E-02 1.12 E-02 1.13 Shoreline 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 TOTAL 1.94 E-04 1.)2 E-02 1.12 E-02 1.12 E-02 1.12 E-02 1. 12 E-02 1.13 E-02 0.00 E+00 9/4

Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment. of Radiation Doses

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

A. Maximum Hypothetical Individual - Exposure from Noble Gases, Particulates, Zodines, and Tritium T. Body GZ-LLZ Bone Liver Kidney Thyroid Lung skin ADULT E-02 1.13 E-02 2.94 E-02 Plume 1.11 E-02 1.11 E-02 1.11 E-02 ).11 E-02 1.11 E-02 1.11 E-04 3.22 E-04 3.79 E-04 Ground Plane 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 Inhalation 8.38 E-03 8.38 E-03 5.90 E-09 8.38 E-03 8.38 E-03 8.38 E-03 8.44 E-03 8.38 E-03 1.43 E-02 1.43 E-02 7.85 E-09 1.42 E-02 1.42 E-02 1.43 E-02 1.42 E-02 1.42 E-02 Vegetation E-03 2.20 E-08 3.37 E-03 3.37 E-03 3.38 E-03 3.37 E-03 3.37 E-03 Cow Milk 3.37 E-03 3.37 1.44 E-03 1.44 E-03 Meat & Poultry 1.44 E-06 1.44 E-03 7.98 E-10 1.44 E-03 ).44 E-03 1.44 E-03 3.89 E-02 3.89 E-02 1.14 E-02 3.88 E-02 3.88 E-02 3.89 E-02 3.91 E-02 5.72 E-02 TOTAL TEENAGER 1.13 E-02 2.94 E-02 Plume 1. 11 E-02 1.11 E-02 ).11 E-02 1.11 E-02 1. 11 E-02 1. 11 E-02 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.79 E-04 Ground Plane E-09 8.43 E-03 8.43 E-03 8.44 E-03 8.51 E-03 8.44 E-03 Inhalation 8.43 E-03 8.44 E-03 8.30 E-02 1.67 E-02 ).67 E-02 Vegetation 1.67 E-02 1.68 E-02 7.62 E-09 1.67 E-02 1.67 E-02 1.67 4.39 E-03 3.98 E-08 4.39 E-03 4.39 E-03 4.41 E-03 4.39 E-03 4.39 E-03 Cow Milk 4.39 E-03 E-04 8.56 E-04 8.56 E-04 Heat & Poultry 8.57 E-04 8. 61 E-04 6.63 E-10 8.56 E-04 8.56 E-04 8.56 4.18 E-02 4.19 E-02 1. 14 E-02 4.)8 E-02 4.18 E-02 4. 19 E-02 4. 21 E-02 6.02 E-02 CHILD E-02 1.11 E-02 1.13 E-02 2.94 E-02 Plume 1;11. E-02 1.)1 E-02 ).11 E-02 1. 11 E-02 1.11 E-04 3.22 E-04 3.22 E-04 3.79 E-04 Ground Plane 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-03 Inhalation 7.46 E-03 7.46 E-03 1.13 E-08 7.46 E-03 7.46 E-03 7.46 E-03 7.52 E-03 7.46 2.62 E-02 2.62 E-02 1.44 E-08 2.61 E-02 2.61 E-02 2.61 E-02 2.61 E-02 2.61 E-02 Vegetation E-03 9.67 E-08 6.94 E-03 6.94 E-03 6.97 E-03 6.94 E-03 6.94 E-03 Cow Milk 6.94 E-03 6.94 E-05 E-05 3.50 E-05 3.50 E-05 Heat & Poultry 3.86 E-05 4.18 E-05 6.46 E-08 3.63 E-OS 3.51 5.64 5.30 E-02 5.30 E-02 1. 14 E-02 5.30 E-02 5.30 E-02 5.30 E-02 5.32 E-02 7.14 E-02 TOTAL INFANT 1.11 E-02 1.13 E-02 2.94 E-02 Plume ).11 E-02 ).11 E-02 1.11 E-02 ).11 E-02 1.11 E-02 3.22 E-04 3.79 E-04 Ground Plane 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 3.22 E-04 Znhalation 4.29 E-03 4.29 E-03 8.88 E-09 4.29 E-03 4.29 E-03 4.29 E-03 4.33-E-03 4.29 E-03 Cow Milk TOTAL 2.62 E-02 2.62 E-02 1.14 E-02 2.62 E-02 2.62 E-02 2.63 E-02 2.65 E-02 4.46 E-02 9/5

l Og 4

Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9: Assessment of Radiation Doses

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

B. Maximum Real Individual - Exposure from Noble Gases, Particulates, Iodines, and Tritium T, Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT 1.93 E 03 1.97 E-03 5.23 E-03 Plume 1.93 E-03 1.93 E-03 1. 93 E-03 1.93 E-03 1.93 E-03 E-04 Ground Plane 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.24 E-03 1.01 E-09 1.46 E-03 1.46 E-03 1.46 E-03 1.47 E-03 1.46 E-03 Inhalation 1.46 E-03 1.46 2.49 E-03 2.58 E-09 2.48 E-03 2.48 E-03 2.48 2.48 E-03 2.48 E-03 Vegetation 2.48 E-03 E-04 2.50 E-04 E-04 2.50 E-04 2.50 E-04 2.62 E"10 2.50 E-03'.50 Meat & Poultry 2.50 E-04 2.52 E-04 6.22 E-03 6.23 E-03 2.04 E-03 6.22 E-03 6.22 E-03 6.22 E-03 6.27 E-03 9.53 E-03 TOTAL TEENAGER E-03 1.93 E-03 1.97 E-03 5.23 E-03 Plume 1.93 E-03 ).93 E-03 1.93 E-03 1.93 E-03 1.93 E-04 Ground Plane 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.24 1.47 E-03 1.42 E-09 1.47 E-03 1.47 E-03 1.47 E-03 1.48 E-03 1.47 E-03 Znhalation 1.47 E-03 E-03 2.50 E-09 2. 91 E-03 2.91 E-03 2.91 E-03 2.91 E-03 2.91 E-03 Vegetation 2.91 E-03 2.92 E-04 1.49 E-04 1.49 E-04 1.49 E-04 Meat & Poultry 1.49 E-04 1.50 E-04 2.18 E-)0 1.49 E-04 1.49 TOTAL 6.56 E-03 6.57 E-03 2.04 E-03 6.56 E-03 6.56 E-03 6.56 E-03 6.6) E-03 9.87 E-03 CHILD E-03 E-03 1.93 E-03 1.93 E-03 1.97 E-03 5.22 E-03 Plume 1.93 E-03 1.93 E-03 1.92 1.93 E-04 1.06 E-04 1.24 E-04 Ground Plane 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 Inhalation 1.30 E-03 1.30 E-03 1.93 E-09 1.30 E-03 1.30 E-03 1.30 E-03 1.31 E-03 1.30 E-03 4.55 E-03 4.55 E-03 4.72 E-09 4.54 E-03 4.54 E-03 4.54 E-03 4.54 E-03 4.54 E-03 Vegetation Meat a Puoltry TOTAL '8.06 E-03 8.06 E-03 2.04 E-03 8.05 E-03 8.05 E-03 8.05 E-03 8.10 E-03 1.14 E-02 INFANT E-03 E-03 1.93 E-03 1.93 E-03 1.97 E-03 5.23 E-03 Plume 1.93 E-03 1.93 E-03 1.93 1.93 E-04 1.06 E-04 1.24 E-04 Ground Plane 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 Inhalation 7.45 E-04 7.45 E-04 1.52 E-09 7.45 E-04 7.45 E-04 7.46 E-04 7.52 E-04 7.45 TOTAL 2.78 E-03 2.78 E-03 2.04 E-03 2.78 E-03 2.78 E-03 2.78 E-03 2.83 E-03 6.10 E-03 9/6

f~

Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses

3. Annual Air Dose (mrad)

A. Maximum Hypothetical Individual: Beta ~ 2.29 E-02 Gamma ~ 1.69 E-02 B. Maximum Real Individual: Beta = 4.15 E-03 Gamma 2.94 E-03

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.

I~

Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses Enclosure 4: Major Assumptions Used to Calculate Radiation Doses

1. Doses Due to Liquid Effluents A. Dilution Factors

~~a V~

1.00 E+00 Shoreline, Swimming, Boating, Fish Consumption Harris Lake Shoreline, Drinking water Cape Fear River 5.23 E+01*

(for Harnett County, Lillington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 5.23 E+01* Boating

The dilution of 5.23 E+01 is calculated usina the average flow of the Buckhorn Creek (measured at the gauging station at Corinth, N.C.) which is the blowdown and the average flow of the Cape Fear River (4406.5 CFS) asService of Harris Lake (84.24 CFSfxnformation measured at the gauging station at Lillington, N.C. The above was by provided by the United States Geological for 1996.

Populations Affected 1um~n ~V w

Harris Lake 1.10 E+05 person-hours Shoreline, Swimming, Boating Harnett County 4.52 E+04 persons Drinking Water Dunn Intake 1.67 E+04 persons Drinking Water Fayetteville Area 1.40 E+05 persons Drinking Water Fuauay-Varina 2.68 E+03 persons Drinking Water HoZly SprinCs 2.27 E+02 persons Drinking Water.

Harris Lake7 E+03 person-hours Fishing Cape Fear River 7.84 Cane Fear River/

Raven Rock Park 5.00 E+04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shorelrne C, The doses from liquid effluents for "Activities Inside the Site Boundary" use the Cape Fear River as the Drinking Water supply year round and Harris Lake on site using the following assumptions:

Pathwav Fish Shoreline Boating Usaae kc/ r hr vr hr r Adult 10 12 100 Teen 10 9/8

0 t g Annual Radioactive Effluent Release Report January 1, 1996 to December 31, 1996 Appendix 9 : Assessment of Radiation Doses Enclosure 4 (Continued): Hajor. Assumptions Used to Calculate Radiation Doses

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

B. The Maximum Real Individual is located at 2885 meters (-2.8 miles) in the ENE sector. This is based on the 1996 land use census with applicable pathways.

The (4aximum Hypothetical Individual is located on the site boundary at 2132 meters in the SSM sector.

The dose calculations for the inside the Site Boundary is in the southeast sector at 1219 meters. The number hours per year 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 fishing trips/year= times 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s/day equals 480hours/year.

98 days/year times 2 hours/day for hiking, bird watching, a etc. equals 196 hours0.00227 days 0.0544 hours 3.240741e-4 weeks 7.4578e-5 months .

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

~" C 9704220349 N. \V SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCH)

Revision 9 Docket No. STN-50-400 CAROLINA POWER & LIGHT COMPANY Approval by PNSC Chairman Approval by General Manager Harris Plant 8yzr~m A Pdw Effective Date 3a RECEIVED SEP Oi f996 HNP DOCi V<<NT CONTR()l

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE OF CONTENTS Section Ti~ e Pacae TABLE OF CONTENTS LIST OF TABLES LIST OF FIGURES LIST OF EFFECTIVE PAGES vi

1.0 INTRODUCTION

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 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 ZNTERLABORATORY COMPARXSON STUDIES 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 6-2 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM APPENDIX A - METEOROLOGICAL DISPERSION r ACTOR COMPUTATIONS APPENDI:C B DOSE PARAMETERS FOR RADIOIODZNES, 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 APPENDIX F - ADMINISTRATIVE CONTROLS APPENDIX G DEFINITIONS G-1

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 (Fgygn) o ~ ~ ~ ~ ~ ~ ~ ~ 2-20

2. 1-3 Signal Processor Time Constants (t) for GA Technologies RD-53 Liquid Effluent Monitors ~ . 2-20 2.1-4 Nuclide Parameters 2-21 2.2-1 +, 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 3.2-2 Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (Miles) . . . ~ 3-19 3.2-3 Dose Factors for Noble Gases 3-20

3. 2-4 Pz, Values (Inhalation) for a Child ~ ~ 3-21 3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant 3-34 4.1 Radiological Environmental Monitoring Program 4-2 A-1 through A-4 X/Q and D/Q values for long-tenn ground-level releases at special locations . . . . . . . . . . . . . . . . . . . . A-4

Shearon Harris Nuclear Po~er 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 A-13 Distances Joint (m ........ ~..............

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

')

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

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 I,IST 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 4.3-8 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . D-5 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation D-8

4. 3-9. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements D-10 4.11-1 Radioactive Liquid Waste Sampling and Analysis Program D-13 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program . D-19 3.12-1 Radiological Environmental Monitoring Program . D-29 3.12-2 Reporting Levels for Radioactivity Concentrations in Environmental samples D-35 4.12-1 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) . ~ ~ ~ ~ . ~ . ~ D-36 Frequency Notation . . . . . . . . . . . . . . . . . . . . . G-4 G-2 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 3.1 SHNPP Gaseous Waste Streams 3-53 3.2 Schematic of Airborne Effluent Release Points........ 3-54 3.3 SHNPP Condenser Off-Gas System 3-55 4.1-1 SHNPP Exclusion Boundary Plan ~ ~ ~ ~ ~ ~ ~ 4 16 4.1-2 through 4.1-5 Environmental Radiological Sampling Points ~ ~ ~ . . . . . 4-17

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9

'st o ect've a es

~ae P~ev'~o Cover Page ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

ii-iii ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

iv ~ ~ 0 ~ ~ ~

v ~ ~ ~ ~ ~ ~ ~ ~ ~

vi 4 ~ ~ ~ ~ ~ ~ ~ ~

vil o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2 2-8 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \

2-9 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2-10 2-11 ~ ~ ~ ~ ~

2-12 ~ ~ ~ ~ ~ ~ ~ ~ ~

2-13 2-14 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2-15 ~ ~ ~ ~ ~ ~

2-16 ~ ~ ~ ~ ~ ~ ~ ~ ~

2-17 2-19 ~ ~ ~ ~ ~

2-20 2-27 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

2-28 ~ ~ ~ ~ ~ ~ ~

2-29 ~ ~ ~ ~ ~

2-30 3 1 ~ ~ ~ ~

3 3-11 ~ ~ ~ ~

3-12 3-13 -, 3-14 ~ ~ ~ ~ ~ ~

3 3-17 ~ ~

3-18 ~ ~ ~ ~ ~ ~ ~ ~

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

3-24 ~ ~ ~ ~ ~

3-25 3-26 ~ ~ ~

3-27 3-28 3-29 3-30 ~ ~ ~ ~ ~ ~ ~ ~ ~

3-31 3-33 ~ ~ ~

3-34 3-52 ~ ~ 0 3-53 ~ ~ ~ ~ ~ 0 ~

3-54 3-55 ~ ~ ~ e ~ ~

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9

'st o f ective a e

~ae P~ev s~o 4-1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4 4-3 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 4-4 4-10 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4-11 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 4-12 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4-13 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 6 4-14 4-18 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4-19 4-20 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 6 5-1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6 6-2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 7-1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 A 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

A-4 A-21 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 B 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 B-2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 B-3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 B-4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 5 B B-18 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

C-1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

D D-2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 D-3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 D-4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 D-5 \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 7 D-6 \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 D D-10 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 D-11 ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 D 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 Of fsite 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.

1-1

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 E (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 3.995 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 Operational Requirement 3.3.10 requires that radioactive effluent instrumentation have alarm/trip setpoints that will ensure that an alarm/trip will occur prior to exceeding 10 times the limits of ODCM Operational Requirement 3.11.1.1. for principal gamma emitters. 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.

Zf 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, C~, may be assumed to consist only of Cs-134.

This nuclide has the lowest Effluent Concentration Limit (ECL) of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint.

2-3

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

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 of

~

concentrations divided by ECL values must not exceed 10 for an individual release. Therefore:

(2.1-2) where:

C~ = the concentration of nuclide i to be released ECL~ = the Effluent Concentration Limit for nuclide 10CFR20I Appendix B Table 2 Column 2 i from Zf the summation is greater than 10, dilution is required. The total required dilution factor, D,~, is the minimum acceptable dilution factor required to meet the limits of ODCM Operational Requirement 3.11.1.1, based on pre-release and composite analysis.

(2.1-3) where:

Required dilution factor for gamma-emitters ECL (2.1-4) 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 Efegy ECL)

(2.1-5) and 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 normally set to 1E-03, which is the H-3 ECL.

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

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

respectively.

The measured concentration of each gamma-emitting nuclide, including noble gases, is reported in 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.

2-6

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

2. 1.1 Batch Releases (continued)

3. Maximum Waste Flow For liquid releases, the maximum permissible waste flow rate for this release, W is the minimum of R and R where avail a 1loc (2. 1-6)

R~a req R = Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-1. This value is the same as and Fad all The available dilution flow is the minimum dilution stream flow (Cooling Tower Blowdown) that can be ensured for the period of the release. Since only one batch release occurs at a time out of a single discharge point, the flow is not corrected for other releases in progress, for any activity in the dilution stream, or reduced by a safety factor. The minimum dilution flow rate for each setting is shown in Table 2.1-2.

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

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.

If D,~ s 1, the minimum dilution flow rate is set to 0.0. If D,~

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

~ D min df low MME r~ (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 2.1.1 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.

Zf analysis of the batch sample indicates all gamma-emitting nuclides are < LLD, (as defined in ODCM Operational Requirement Table 4.11-1), the tank gamma activity, C~, 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'mum setpoint value, based on Nuclide Specific Response S~ (Cs-equiv) = (S,~> R ) + B (2.1-8) where Setpoint adjustment factor.

alloc avail FN5$ 'Co roq, ng (2. 1-9) re@,g S,~> should always be greater than 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.

2.1.1 Batch Releases (continued)

R, = g slope, C, where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slopeq = 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 approached. S~, is calculated from the nuclide specific response setpoint.

[(S -B)'F] +B (2.1-10) where:

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

2-9

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

(3) Check for Excessive Monitor Background In order to differentiate between the S and the statistical fluctuations associated withg,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:

E (2. 1-12) where:

t = Signal Processor Time constant, minutes.

(Table 2.1-3)

Bkg Background Count Rate, in cpm B / E~

Monitor efficiency for the Cs-137 gamma energy, cpm/pCi/ml determined by primary calibration.

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

Post-Release Compliance After the release is made, actual concentrations aze used to check 10 CFR 20 limits, and the actual dilution flow and waste flow aze 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.F 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~ff Sens,ff ) + Bkg (2.1-13) where:

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

Sensors Z< (Sens i x 0 abundance) nu.x, cpm/pci/ml.

for the SWST nuclide

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

[(S -B)'F] +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.

Zf the monitor is in alarm or the presence of non-naturally occurring radioactivity > effluent LLD is confirmed, the releases may continue provided the sampling and analysis required by ODCM Operational Requirement Table 4. 11-1 are performed. The results of the sample analysis will be evaluated for compliance with ODCM Operational Requirement 3.11.1.1.

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

3. Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor is >0.01 ECL,ff.

Therefore, background is acceptable if:

01 ECL tr SENS n MDC C (2. 1-15) 2-11

Shearon Harris Nuclear Power Plant November 1995 Offsite Dose Calculation Manual (ODCM) Rev. 7 2.1.3 Ot er Li uid Releases

1. Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake. The line is monitored for radioactivity by the Tank Area Drain Transfer Pump Monitor.

Because no radioactivity is normally expected in this line, the monitor high alarm and alert alarm setpoints are determined using the methodology is Section 2.1.2. If the setpoint is exceeded, the discharge pump is automatically secured. Effluent can then be diverted to the floor drain system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

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 towe discharge line. Tritium is expected to be detected in this pathway from sources such as background from the lake. Because no other radioactivity is normally expected in this path, the setpoints for the turbine building drain monitor are determined using the methodology in Section 2.1.2. Should the setpoint be exceeded, the release is automatically terminated. Effluent can then be diverted to the secondary waste treatment system for processing and eventual release (see Figures 2. 1-1 and 2. 1-2) .

2-12

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 2.2 Compliance with 10 CFR 50 An 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 receptor (site boundary), for each nuclide, and for each organ. The dose is the total over all pathways which apply to that receptor. A receptor is defined by receptor ID, age group (infant, child, teen, 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:

Dier Ai,. Zht Ci F (2. 2-1) where:

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

Aisr 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 releases, an hours.

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

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:

F waste F avail lx (2.2-2) waste and mixing ratio fraction of the release that reaches the receptor. At the SHNPP, this value is set to 1.

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

In the case of a continuous secondary'aste sample tank radioactive release, Cl = the concentration of nuclide "i" in the SWST composite sample. For the NSW, Cl = 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 czoss-tie. For a release through the Turbine Building Floor Drain Line to the waste neutralization system, Cl = the Turbine Building floor drain sample activity, F ~ = discharge from the Turbine Building floor drain line, and F,,l, =

the average flow during the period of the total Cooling Tower discharge.

The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower Bypass Line flow.

When there is a primary-to-secondary leak, the change in concentration of tritium in the steam generators times the secondary loses (balance of plant), will be used for effluent accountability. The secondary loss rate will also be used for volume accountability.

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

1'14E+05( + 21BFl) DF (2. 2-3) where:

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

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

Values for the adult total body and organs in mrem/hz per pCi/ml aze 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 1iter 8760 trs 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 BFz = Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1), pCi/kg per pci/1 DFi, = 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 (tB) g Radiological half-life of nuclide "i, " hr; 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 e 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 objectives for total body and any organ. The sum of the cumulativedesign doses from all releases for a calendar year is compared to the design ob)ective 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 (ODCM) Rev.

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:

Dq s 3 mrem total body (2. 2-7)

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

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

The quarterly limits given above represent one-half the annual design objective of 10 CFR 50, Appendix I, Section II.A. If any of the limits in equations (2.2-5) through (2.2-8) aze exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I, 10 CFR 50.

The calculations described in Section 2.2.1 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I on a "per-release" basis. The NRC approved pxogram LADTAP II will be used to demonstrate compliance on an annual basis. While there are substantial differences between the ODCM methodology and the methodology in LADTAP, 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 uses a "modified" NUREG 0133 equation with conservative assumptions. It calculates the dose to a single maximum (ALARA) individual. It 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. It 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, rather than minimum values for the Cape Fear River flow.

2-16

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 2.2.2 Com arison A ainst Limits (continued)

LADTAP Parameters are maintained in the Laboratory and Facility Services Section Instruction RC-ER-36, Operating Znstruction for XOQDOQ, GASPAR, and LADTAP Computer Programs. Parameters subject to change on a periodic basis (flows, source terms, 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 ti.mes 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 Operati.onal Requirement 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully utilized.

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

Dpv = (Dl p)'+ D, (2. 3-1) where:

Dp, = the 31 Day Projected Dose by organ z 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 liquid releases, etc.) should be accounted foz in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and addi.ng 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 D~, c 0.2 mrem for any organ (2. 3-3)

If the pro)ections 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 LIQUID EFFLUENT RELEASE TANKS AND PUMPS

"'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 WMTo) 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 XN3LFZM Setpoints for Cooling Tower Blowdown Dilution Flow Rates (F,,,)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate

( pm) 40PO a 6% 3.800 7000 a 6% 6,650 11 000 ~ 6% 10,450 15 000 ~ 5% 14,250 IABLE~R Signal Processor Time Constants (T) for GA Technologies RD-53 Liquid Effluent Monitors Detector Back round (cpm) (min) 10~ 10~ 10 10~ - 103 10'/cpm bk 10 - 10 10~/cpm bk 10'- 10 103/cpm bk 0.01 10'-10'0'-10' 0.01 2-20

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 1 of 3 Nuclide Parameters Half-Life Sensitivity Nuclide (hours) (hr-1) e-Xt ~cm/ Cl/ml ~Sic 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 4.88E-07 1.00E+00 O.OOE+00 O.OOE+00 Fe-59 6.43E+04 1.08E-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-06 1.00E+00 1.46E+08 1.40E+00 Co-60 2 '7E+06 2.50E-07 1.00E+00 1.89E+08 1.82E+00 Ni-63 5.27E+07 1.32E-08 1.00E+00 O.OOE+00 O.OOE+00 Ni-65 1.51E+02 4.59E-03 9.46E-01 2.24E+07 2.15E-01 Cu-64 7.62E+02 9.10E-04 9.89E-01 5.16E+07 4.96E-01 Zn-65 3 '2E+05 1.97E-06 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 6.50E+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 3.89E-02 6.27E-Ol 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-01 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+01 1.39E-02 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-06 1.00E+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 O.OOE+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 Po~er Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 2.1-4 Page 2 of 3 Nuclide Parameters (continued)

Half-Life A.t Sensitivity Nuclide (hours) (hr-1) e-Xt ~cm/ ci/ml ~Sic 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 1.38E+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-12'Sm 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 '3E+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 1-133 1.25E+03 5.55E-04 9.93E-01 1.39E+08 1.34E+00 I-134 5.26E+Ol 1.32E-02 8.54E-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 3.79E-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 '1E+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 1.95E+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 A,t Sensitivity Nuclide (hours) (hr-1) e-) t ~cm/ cl/ml ~elc 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 7.49E+07 7.20E-01 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 2.62E+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+Ol 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-01 1.20E+08 1.15E+00 G-ALPHA 1.00E+05 6.93E-06 1.00E+00 O.OOE+00 O.OOE+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)

SLOPE The Liquid Effluent Moni.tor Gamma Sensitivities for nuclide i, relative to Cs-137. To make nuclide i.

relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

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 Ai~ VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT Af,, = 1e14E+05( + 21BFf) DF~, e per pCi/ml) 4'mrem/hr Nuclide Bone Liver ~T. Bod ~rh roid ~Kidne Luncu Gr-LLZ H-3 O.OOE+00 8.54E-01 8.54E-01 8 '4E-01 8.54E-01 8.54E-01 8.54E-01 C-14 3.13E+04 6e27E+03 6.27E+03 6.27E+03 6.27E+03 6 '7E+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 '0E+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-Ol O.OQE+00 5.63E+OQ 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.OQE+00 6.95E+02 8.29E+03 CO-57 O.OOE+00 2.20E+01 3.66E+Ol O.OOE+00 O.OOE+00 O.OOE+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 NE-63 3.20E+04 2.21E+03 1.07E+03 O.OOE+00 O.OOE+00 O.OOE+00 4.62E+02 NI-65 4.76E+00 6.19E-01 2.82E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.57E+Ol CU-64 O.OOE+00 5.45E+00 2.56E+00 O.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 O.OOE+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.OQE+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.OQE+00 O.OOE+00 1.24E+00 O.OOE+00 Q.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-11 BR-85 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 'OE+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-lo O.OOE+00 O.OOE+00 O.OOE+00 2.67E-21 RB-89 O.OOE+00 1.62E-12 1.14E-12 O.OOE+00 O.OOE+00 Q.OOE+00 9.43E-26 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

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 ~

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

Nuclide Bone Liver Bod ~Th roid ~Kidne Luncn GZ-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 '7E-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 9.12E-02 O.OOE+00 2.11E-01 O.OOE+00 4.27E+02 ZR-97 1.42E-02 2.87E-03 1.31E-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 8.21E-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+01 RU-106 8.23E+Ol O.OOE+00 1.04E+Ol 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 5.16E+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+01 4.05E+03 7.45E+01 O.OOE+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+Ol 6.95E+Ol 2.12E+01 1.02E+04 1.21E+02 O.OOE+00 6.25E+Ol 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 0 'OE+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)

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

Nuclide Bone Liver Trod ~Th roid ~Kidne Luncu GI-LLI 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 '7E-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

O Ul y>>>> A lh 7 '7 77>>

Tt 0 ld Q X 0 777 tt l7>>

O 7>>7 I

V 'Z Figure 2. 1-1 nt:n Liquid Reste Processing Flow Diegrem VV 7=

I 8 4a 9- V Chemo>>arly Narsre 0 So>>oars>>y >>77

'Teats We>>re 0 Cahrohsa!o polehsr SMpl>> Teat Z8 Oeahereyrer (7 WST) 777 75 Roy>>a 7-Care>>yyry S>>orate S Qs V V' dypsso 77CJ Teats Wears Heaters>>y I- rt Teats U tws>>77 0 O~

Cteattylet Orch>> S lsherry S Hel Ster or A g 777 Dere>>Tsar Orat>> ~ Sea p Teats 8 S z

~ 77

>>77 Tree>>>>a b3 tosarry S I pl>>or Ores>> freer Ore>>>> Hal Storer Shape Teats Thats rrtsH$ 77 I I

E lad>>hoot Or>>ho 0

Soap Where froperorar Doat>>

Wears Eropereror C eh rob>> e(e That DyfC77 CVCS Roe>>ale Coat>> He>>rap 4>>reah dorM Teats Re>>yare Ere pere>>or 4

X j

7 ld 77>>

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 end Treated Laundry & Treated Laundry & Tank or Basin Mot Shower Tank Mot Shower Tank C ttBu Radiation ENuent Monitor 0 0

I Pump I

REM n REM-1 WL4540 Secondary Waste T Sample Tank 0 w

REM-21WS-35 42 r REM B I

0 0 Speasde Flange w Waste Monitor Waste Monitor d Waste Neutralization Tank Tank Basin ~

w n

Waste Evaporator Waste Evaporator Settling Condensate Tank Condensate Tank Basin

~ Liquids containing radioactive materials other than tritium are not permitted REM by procedure to be sent Maffis to the Waste Lake REM-21 WL4541 Neutralization Basin.

2-28

0

~ ~ ~ ~

lg

~ l r ~ o P'

t)

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 2.1-4 Other Liquid Effluent Pathways Turbine Building Floor Drains Outside Tank Area Drains Effluent Line Effluent Line Turbine Building Outside Tank Floor Drains Area Drains Sumps REM 3028 REM 3530 Yard Oil Separator Storm Drain Waste System Neutralization Basin Settling Basin Harris Lake Cooling Tower Blowdown Line Turbfne Building Floor Drafns Effluent can be diverted to the Secondary Waste Treatment System

" Outsfde Tank Area Drafns Effluent can be diverted to the Liquid Radwaste Treatment Sysyem 2-30

Sheazon 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 5A. These are shown in Figures 3.1, 3.2, and 3.3 along with their tributaries. All gaseous effluent releases at the plant are considered ground releases.

3.1 Monitor Alarm Set oint Determination (ODCM Operational Requirement 3.3.F 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 mremlyear to the whole body or 3000 mrem/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 are shown in Figures 3.1 and 3.3 and are listed in Appendix C.

Gamma spectroscopy analysis of the gas sample should provide the nuclide identification and activity. However, in the case where the noble gas activities are < LLD the relative nuclide composition can be assumed from the GALE code activities for projected normal operating releases (Table 3.1-1). The GALE code is used to establish a default setpoint foz 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. Q is the release rate of nuclide v, in pci/sec.

i in gaseous effluent from discharge point g Cz ~

F duration ~ 28316.85 (3.1-1a) and Q Cg ~

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

index over all vent stacks 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 m'nutes 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)

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

~(< Q) t >, K, Q, ) (3.1-2a) and TXXQ) [ Zq (Lq + 1.1M~) Qq ] (3.1-2b) where:

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

i (in mrem/yr per pci/m3), from Lg 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 M<

gas radionuclide i (mrad/yr per pci/m') . A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Ll+1. 1M'kin dose Table 3.1-.2 factor (mrem/yr per pCi/m'), from

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

6.1E-06 sec/m'rom Table A-l, Appendix A 3-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.1.1 Default Continuous Release Monitor 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) 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 for the monitor.

t (f, ~

f~,<< ~ nratio ~

QC, ) + Bkg (3.1-4a) and RR = S ~

F ~ 28316.852 / 60 (3.1-4b) where 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 are 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. Based on sampling and analysis, the setpoint will be recalculated. Zf the sample analysis setpoint is higher than the default setpoint, the setpoint will not be changed. Zf the sample analysis setpoint is lower than the default, the setpoint will be changed to reflect the more conservative setpoint. When the setpoint changes again, the more conservative setpoint, comparing the default (GALE code) and sample analysis, will be used.

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

[ (S~- Bkg) Ag) + Bkg (3.1-5a) and RRaierc = [ (RR a

- Bkgrr) At) + Bkgr: (3.1-5b) where:

'r 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 Vsin 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 contai t and pre-entry an ur e and pressure relief. Batch release sources for Vent re-entr purge Stack 5 include releases from the waste gas decay tanks (WGDT). ln th ese t monitor setpoint must reflect the contribution of both the casess, the continuous and batch sources.

The release vent stacks based on actual sample results and for batch releases occurring concurrently with continuous releases.

activity release r

following methodology will calculate a setpoint for the continuous Determine the noble gas. radionuclide activity (g ) in p i, .an the 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 .

g Cq ~

F ~ duration ~ 28316.85 (3.2-1a) and Q Cg ~

Fy ~ 28316.85 / 60 (3.2-1b) where:

index over all vent stacks Cg 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 Ha ris Nuclear Power plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM} Rev. 5

3. 1.2 Monitor Set oi.nts Usin Sam le Results (continued) for batch releases, the release flow rate, in acfm 1,500 acfm for containment normal purge 37, 000 acfm for containment preentry purge

2. 26 8+06 ( 5P 14.7 t

) ( 273 T

)

for a containment pressure release 600 ( ')

DP~

14.7 (

273 T

)

for a Waste Gas Decay Tank release where:

2.26E+06 and 600 are the volumes in containment and decay tank, respectively, and ft'f the T T hP and hP, are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 ib/in~, i.e., 1 atmosphere pressure Length of release, min 273'K 0 C 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 Offsite Dose Calculation Manual (ODCM) Rev. S 3.1.2 Monitor Set pints Usin Sam le Results (continued)

2. Dete rnu.ne 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.

Qa-~ = ~(X Ql Z( Zi Kq Qq 1 (3.2-28) and

~(X Q) Z>> [ Z~ (L~ + 1.1M~) Q~ ] (3.2-2b) where:

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

i (mrem/yr per pci/m3), from The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per pCi/m')

The air dose factor due to emissions for noble gas radionuclide i (mrad/yr per pCi/m')

Mg gamma

. A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose Ls+1.1Mi Skin dose factor (mrem/yr per pCi/m') from Table 3.1-2 Q The h'ighest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m')

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

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

Qa-~

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 for the monitor.

S~x (f, ~

f,n'ratio ~

ZCq ) + Bkg (3.2-4a) and Saax Fv ~ 28316 852 / 60 (3.2-4b) where safety factor for the discharge point 0.5 dose rate allocation factor for the discharge point fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases. These values are based on the percentage of an individual stack flow to the total stack flow and are in Table 3.1-3.

Bkg Monitor background, in pCi/cc measured background at time of release or Q.

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. rmine S 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~- Bkg) A~] + Bkg (3. 2-5a) and RRaloz~ Bkgcr ) c> + Bkgtr (3.2-5b) where:

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

Bkg = Bkg ~

F ~ 2&316.85 / 60 3-10

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

A conservative effluent channel setpoint has been established for Vent Stack 3A. The monitor setpoint should be reduced proportionately to the estimated fraction of the main condenser effluent flowing g directl iree y to the atmosphere.

3-11

0 Table 3.1-1 GASEOUS SOURCE TERMS Condenser Plant Vent Vacuum Pump WPB WPB Containment Ventilation Ventilation Ventilation Ventilate on Purge or WGDT Flow Flow Flow Flow Pressure Relief Release via via via via via via Stack 1 Stack 3A Stack 5 Stack 5A Stack 1 Stack 5 (c) fe) fd)

Ci Ci Ci u lid ~ic ~rCi ~i ~ic ~ic Kr.85m 6.89E-10 7.02 4.69E-9 7.69 2.61E-9 7.02 9.80E-S 2.93 Kr-85 1.87E-7 97.16 6.17E 8 1.85 2.91E-3 97.16 Kr-87 6.89E-10 7.02 4.69E-9 7.69 2.61E-9 7.02 3.45E-S 1.03 Kr-88 1.21E-09 12.28 7.04E-9 11.54 4.56E-9 12.28 1.23E-7 3.69 Xe.131m 5.17E-10 5.26 2.35E.9 3.85 5.49E-9 2.84 1.96E.S 5.26 3.27E-7 9.77 8.51E.5 2.84 Xe-133m 7.26E-S 2.17 Xe-133 2.76E.09 28.07 1.64E-S 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-9 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 ta) Source terms are from SHNPP FSAR Table 11.3.3-1 and not actual releases.

Values apply only to routine re'leases and not emergency situations.

lb) Source term for this elfiuent stream not presented with FSAR. RAB m)x assumed.

lc) Ci fuCilcc) u G r r Smin i Ci f 0 (Flow Rate ft3/min)

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

fe) Based on an assumed flow rate of 37,000 CFM.

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.1-2 DOSE FACTORS AND CONSTANTS'hole Body Dose Skin Dose Factor Factor (Kq) (Lg + 1.1 Mg)

Radionuclide (mrem/ r/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 1.36E+03 Kr-87 5.92E+03 1.65E+04 Kr-88 1.47E+04 1.91E+04 Kr-89 1.66E+04 2.91E+04 Kr-90 1.56E+04 2.52E+04 Xe-131m 9.15E+01 6.48E+02 Xe-133m 2.51E+02 1.35E+03 Xe-133 2.94E+02 6.94E+02 Xe-135m 3.12E+03 4.41E+03 Xe-135 1.81E+03 3.97E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.43E+04 Ar-41 8.84E+03 1.29E+04 "Regulatory Guide 1.109, Rev. 1, Table B-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-5A 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 Offsi.te 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 are utilized to show prerelease compliance with ODCM Operational Requirement 3. 11. 2. 1. However, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the setpoints could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the event that high alarm setpoints are exceeded, a determination may be made as to if the whether the actual releases have exceeded the dose rate limits of ODCM Operational Requirement 3.11.2.1.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin. Based upcn NUREG-0133, the following equations are used to show compliance:

Ki (mKQ) Q (3. 2-1) i v s 500 mrem/yz i.

( i ')(~Q)v Qiv

+ s 3000 mrem/yr (3.2-2) where:

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

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

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

Table 3.2-3 ~

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

Mg 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) 1 1 = T he ratio of the tissue to air absorption coefficients over the energy range of the photon of interest.

Converts mrad to mrem (Reference NUREG-0133). The factors (L~ + 1.1 M,) are tabulated in Table 3.1-2.

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

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

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

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

Release Rate (pCi/sec) = Plow (cc/sec) " Concentration (pCi/cc)

The noble gas radionuclide mix was based upon source terms calculated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1.

They are reproduced in Table 3.2-1 as a function of release point.

The X/Q value utilized in the equations is the highest long-term annual average relative concentration (X~9) v in the unrestricted area for the period 1976 1987. Long-term annual average (~X Q) v 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 (X~@) values were calculated assuming no decay, undepleted transport to the exclusion boundary. These values are given in Table A-l, Appendix A . The maximum exclusion boundary (~X g) v for ground-level releases occurs in the S sector. Therefore, the limiting location for implementation of the dose rate limits for noble gases is considered to be the exclusion boundary (1.36 miles) in the S sector.

Values for K<, L~, and Mz which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with ODCM Operational Requirement 3.11.2 are presented in Table 3.2-3. 'These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert mrad/pCi to mrad/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 3/4.11.2.1 states that the dose rate to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and particulates with half-lives > 8 days is limited to 1500 mremlyr to any organ. Based upon NUREG-0133, the following is used to,show compliance:

P P, [ (~X Q), Q) s 1500 mrem/yr (3. 2-3) where:

Pi = The dose paramete" for radionuclides other than noble gases foz 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 I in Eq. 3.2-3 were calculated foz a child for various radionuclides for the inhalation pathway using the methodology of NUREG-0133. The Pi values are presented in Table 3.2-4. A description of the me(hodology 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'.

3-17

Table 3.2-1 Q III Releases from the Shearon Harris Nuclear Power Plant (1) m Ol I

Normal Operation (Curies/year) rt 0 Waste Processing Bldg Waste Processing Bldg I

Condenser Vacuum Pump U m Exhaust and/or Exhaust via VENT STACK 5A and Turbine Building 0 Waste Gas Decay Tanks (2) or RAB/FHB and Containment Exhaust M

OI via VENT STACK 5 Exhaust via VENT STACK 1 via VENT STACK 3A NOBLE

~G S~U>OWN ~ NORMAL J~~OS CO ~Ul~ S~~l~g O

P Z 0 C C 0 III Kr-85m 0 0 5.4E+01 4.E+00 2.0E+00 VP 6.0E+01 8 Kr-85 8.0E+00 6.5E+02 3.4E+01 0 0 6.9E+02 & Ql Kr-87 0 0 1.9E+01 4.0E+00 2.0E+00 2.5E+01 Kr-88 0 0 6.8E+01 7.0E+00 3.0E+00 0 7.8E+01 'u 0

Xe-131m 1.9E+01 1.8E+02 3.0E+00 1.0E+00 2.0E+02 Z 8 Cu III Xe-133m 0 4.0E+01 0 0 4.0E+01 Xe-133 0 1.0E+03 1.6E+01 7.0E+00 C 1.0E+03 Xe-135m 0 4.0E+00 3.0E+00 2.0E+00 9.0E+00 I I Xe-135 0 4.4E+02 1.7E+01 8.0E+00 4.7E+01 Xe-138 0 3.0E+00 3.0E+00 1.0E+00 7.0E+00 Q It tI ~

Ar-41 A 3.4E+00 P IjI z

'o 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 aAer a 90My 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 Boundary 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 NNE 1.33 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 1.8 3.6 1.8 1.8 1.33 1.8 1.8 2.0 2.0 2.0 ESE l. 33 2.6 2.6 4.7 4.7 4.2 1.33 2.6 2.6 2.6 , 4.1 2.6 SSE 1.33 4.2 4.2 1.36 5.3 5.3 5.3 5.3 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 4.6 1.33 3.0 3.0 3.1 3.1 3.1 3.1 1.33 2.3 2.3 2.3 2.6 1.26 2.7 2.7 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 l994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES

Tata( 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/m ) 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 6.1 7E+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. &3E+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 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3. 2-4 Pi 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 Sr-95 2.23E+06 Nb-95 6.13E+05 Ru-103 6.61E+05 Ru-106 1.43E+07 Ag-110m 5.47E+06 Sn-113 3.40E+05 Sb-124 3.24E+06 Te-127m 1.48E+06 Te-129m 1.76E+06 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

Sheazon 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 (ALA)M) 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 in all age groups, down wind receptors, and integrated populations. It 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 Instruction 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

Shearon 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:

3,17 E-08 P M [ (~X Q) Qi v + (WX q) q. ] (3. 3-1) i v D 3 17 E 08

~

Q Ni [ (WXQ) v Qi v + (XR) qi v ) (3. 3-2) where D

Y The air dose from gamma radiation, mrad.

The air dose from beta radiation, mrad.

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

Table 3.2-3.

~XQ The relative concentration for areas at or beyond the exclusion boundary for short-tenn ground-level vent stack releases (s 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~ from Table A-l, Appendix A.

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

q.i The total release of radionuclide "i" in gaseous releases for short-term releases (s'500 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) '.

The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/pCi/m~) . A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose 3-23

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3.3.3. 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 a t 1.36 . mi'1 es

(--2.19

. i kilometers) in the S sector based upon the tables Appendix A (see Section 3.2.1 earlier). Foz this document, long-term pzesented in annual average ~X Qv values can be used in lieu of short-term values (see Section 3.0 earlier).

The determination of the limiting location foz 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~Qv value for ground-level releases is controlling. The only source of shozt-term releases from the plant vent are containm e nt p u rges, 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 to show compliance with 10CFR50, are presented in Table 3.2-3. These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+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:

4 Dy s 5 mrad (3 3-3)

D() c 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 II.B.1 of Appendix I of 10CFR50. If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be, filed with the NRC.

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

3-24

Shearon Harris Nuclear Power Plant (SHNPP) 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 (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The noble gases and tritium analysis are used for containment effluent accountability as follows; qg = Cg

vb (3.3-7)

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

Cz = Concentration of radionuclide "i" (pCi/cc) vh = 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; (C~ 'P~ 600 '8316.85 298)

(3.3-7a)

(14.7 283) 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)

C, Concentration of nuclide "i" (pci/cc) .

BP 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, ('k) .

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

283 WGDT Temperature, 4k (see Note below)

NOTE'he FSAR assumes 50-140 4F WGDT temperature to be in the range. Since there is no indicator for the actual WGDT temperature, 50'F (10 'C) is conservatively assumed as an acceptable substitute. Also assumed is a sample analysis temperature of 77 F (25').

NOTE: Containment Pressure Releases (XLRT) are calculated using the 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:

Qx = Cx Vx (3.3-8)

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

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

V= Volume (cc) rele;sed 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 radionuclide "i" equals the radionuclide "i" fraction of the radionuclide mix times the total activity released from Stack "x".

Qi = Qx '~ (3.3-8a)

Where; Sg (3.3-8b) and; S> = The radionuclide "i" fraction of the radionuclide mix C< = 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 zequired by oDCM operational Requirement 4.11.2.2.1. If the grab sample activity is < LLD, then a mix based on historical data or a mix based on the Xe-133 / Kr-85 LLD mix of that sample may be used.

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

Corrections for Double Accounting For the two stacks that may have batch releases during the same time interval as continuous releases, the above calculations aze corrected for double accounting as follows; Q<<=Qi-% (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 D>, = (Dt where:

')

the following expression:

+ D (3.3-10)

D~, = the 31 Day Projected Dose by organ x 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-tenn data fzom 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 s'.2 mrad to air for gamma radiation (3.3-11) and Dl) s 0.4 mrad to air for beta radiation (3.3-12)

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

3-28

Shearon Harris Nuclear Power Plant (SHNPP) August Offsite Dose Calculation Manual (oDCM) 199'ev.

5 3.3.2 Radioiodine and Particulates Cumulation of Doses Section ZZ.C of Appendix Z of 10CFRSO limits the release of radioiodines and radioactive material in particulate form from a reactor such that the estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radioiodines and particulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

D = 3.17E-08 Q (R [(WX q) Q + (XTq) q. ) +

V M 1V iG+ R ) [(DjQ) Q + (Djq q ])+

M Z V

'T B

) [ (~XQV QT v

'~R) v where:

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

(WDQ) v The highest long-term (> 500 hr/yr) annual average relative deposition: 8.8 E-09 m the food and ground plane pathways at the

'or 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 hrs/yr), 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 or goat milk pathway, mrem/yr per pci/sec per m ~.

3-29

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 3.3t2 Radioiodine and Particulates (continued)

R.

3.g Dose factor for an organ for radionuclide "i" for the ground plane exposure pathway, mrem/yr per pci/sec per m '.

R.

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

R.

factor for or gan for radionuclide "i"

iy Dose an for the vegetable pathway, mrem/yr per pci/sec per m'.

R 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 for the milk pathway mrem/yr per pCi/m'.

RT = 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'.

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

Tv t

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

pCi.

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

pCi.

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

't Appropriate ~X Q and ~D Q values from tables in Appendix A are used. Eor this document, long-term annual average ~X Q v and ~D Qv 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

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

the analysis is ( LLD, then no activity is assumed to have been If 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 plane 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 VQ and ~D Q values for ground-level releases are provided in tables in Appendix A. They may be utilized additional special, location arises different from those presented if an 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 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3-1 through 3.3-19 present, R~ values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetab', and meat ing'estion 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:

Dx s 7.5 mrem (3.3-14)

For the calendar year:

Dx s 15 mrem (3.3-15)

The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50.

any of the limits of Equations 3.3-14 or 3.3-15 are exceeded, a If Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

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

')

following expression:

+ D, (3. 3-16)

Dp, the 31 Day Projected Dose by organ x Dr 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.

Da, 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 3.11.2.4, 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

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'GE PATHWAY ~ Ground GROUP ~ ALL 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 7A9E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 '.49E+08 7.49E+08 8.61E+08 Rb-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 1.03E+ 07 Sr.89 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.58E+04 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 Zr-95 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.89E+08 Nb.95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.60E+08 Ru-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.27E+08 Ru-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 '.19E+08 4.19E+08 5,03E+08 Ag-110M 3.48E+ 09 3.48E+ 09 3.48E+ 09 3.48E+ 09 3.48E+ 09 3.48E+ 09 3.48E+ 09 4.06E+ 09 Sn-113 1.44E+07 6.28E+06 1.22E+07 6.21E+06 1.00E+07 1.33E+07 8.14E+06 4.09E+07 Sb-124 8.76E+08 7'.53E+08 8.99E+08 7.76E+08 8.17E+08 1.01E+09 8.23E+08 1.24E+09 Te-127M 9.15E+04 9.15E+04 9.15E+04 9.15E+04 .9.15E+04 9.15E+04 9.15E+04 1.08E+05 Te-129M 2.00E+07 2.00E+07 2.00E+07 2.00E+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 1-132 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.46E+06 I-133 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 3.00E+06 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2,56E+06 2.99E+06 Cs-1 34 6.82E+ 09 6.82E+ 09 6.82E+ 09 6.82E+ 09 6.82E+ 09 6.82E+ 09 6.82E+ 09 7.96E+ 09 Cs-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 Cs-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 Ba.140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.34E+07 Ce-141 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.53E+07 Ce-144 6.95E+ 07 6.95E+ 07 6.95E+ 07 6.95'5+ 07 6.95E+ 07 ~ 6.95E+07 6.95E+ 07 8.03E+ 07 Hf-1 81 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 /ICI/m~ tor inhalation and tritium and in units of mrem/yr per pCi/sec per m't for all others.

3-34

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

PATHWAY ~ Veget AGE GROUP ~ Adult bhuJida LBnr4t Ihyraid 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+ 01 O.OOE+ 01 O.OOE+ Ol 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+Ol 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+Ol 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+ Ol 2.99E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Co-60 3.67E+08 3.12E+09 O.OOE+01 1.66E+08 O.OOE+Ol 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+Ol 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+ Ol 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+ 11 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Y-91 1.34E+05 2.76E+09 5.01E+ 06 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+Ol O.OOE+ 01 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+ Ol 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+Ol 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+ 01 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 2A6E+05 7.90E+ 07 O.OOE+ 01 Te-127M 6.12E+ 07 1.68E+09 5.02E+08 1.80E+08 2.04E+09 1.28E+08 O.OOE+01 O.OOE+01 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+01 I-1 31 6.61E+07 3.04E+07 8.075+07 1.15E+08 1.98E+08 3.78E+ 10 O.OOE+ 01 O.OOE+ 01 I-132 5.21E+ 01 2.80E+ Ol 5.57E+ 01 1.49E+ 02 2.37E+02 5.21E+03 O.OOE+01 O.OOE+01 I-l 33 1.1 2E+ 06 3.30E+ 06 2.11E+ 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+ 01 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 8.40E+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 1.935+05 1.31E+05 6.07E+04 O.OOE+01 O.OOE+Ol 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+Ol Hf-1 81 1.07E+06 7.06E+08 9.51E+06 5.36E+04 4.48E+04 3.41E+04 O.OOE+01 O.OOE+Ol

'R Values in units of mrem/yr per yCi/m'or inhalation and tritium and in units of mrem/yr per yci/sec per ma for ali 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 LBndg QlZrau Xhrrrruid H-3 2.61E+03 2.61E+03 O.OOE+ 01 2.61 E+ 03 2.61E+ 03 2.61E+03 2.61E+ 03 2.61E+ 03 P-32 6.8OE+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+ 01 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+ Ol O.OOE+ 01 Fe-59 1'.60E+ 08 9.78E+ 08 1.77E+08 4.14E+08 O.OOE+01 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+ 01 Co.60 5.57E+08 3.22E+09 O.OOE+ 01 2.47E+08 O.OOE+ 01 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+ Ol Rb-86 1.30E+ 08 4.09E+ 07 O.OOE+ Ol 2.76E+ 08 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 O.OOE+ Ol Sr-89 4.36E+ 08 1.81E+ 09 1.52E+ 10 O.OOE+Ol O.OOE+01 O.OOE+Ol 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+01 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+Ol Zr-95 3.68E+05 1.23E+09 1.69E+06 5.35E+05 7.86E+ 05 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Nb-95 5.77E+ 04 4ASE+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+ 01 Ru-106 3.93E+ 07 1.50E+ 10 3.12E+ 08 O.OOE+Ol 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+ Ol 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 9.44E+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 1.6'I E+ 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-1 33 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+Ol 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.OOE+01 1.44E+07 O.OOE+Ol Cs-137 4.90E+ 09 2.00E+ 08 1.06E+10 1.41E+10 4.78E+ 09 O.OOE+ 01 1.86E+09 O.OOE+ 01 Ba-140 8.88E+ 06 2.1 2E+ 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+ 01 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+ 01 O.OOE+ 01 O.005+ 01 Hf-181 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 Vaiues in units of mrem/yr per /rCI/m'or inhalation and tritium and in units of mrem/yr per pCi/seo 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'GE PATHWAY ~ Veget GROUP ~ Chiid ZJody ~act 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+01 1.76E+04 6.44E+04 1.18E+ 05 O.OQE+ 01 Mn-54 1.73E+ 08 5.44E+ 08 O.OOE+ 01 6.49E+08 1.82E+08 O.OOE+01 O.OOE+01 O.OQE+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 6.2?E+ 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+ 0? Q.OOE+ Ol 4.56E+ 08 O.OOE+ 01 O.OOE+ Ol 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+ Ol O.OOE+ 01 O.OOE+ 01 O.005+ 01 Y-91 4.89E+05 2.44E+09 1.83E+ 07 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 ?A4E+ 05 8.71E+ 08 3.80E+ 06 8.35E+05 1.20E+ 06 O.OOE+ 01 O.OOE+ Ol O.OOE+ Ol Nb-95 1.12E+05 2.91E+08 4.04E+ 05 1.5?E+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+01 3.84E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+Ol Ru.106 9.38E+07 1.17E+10 7.52E+ 08 O.OOE+ Ol 1.02E+09 O.OOE+Ol Q.QOE+ 0 1 O.QQE+ 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.OQE+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+Ol Sb-124 1.21E+08 2.16E+09 3.44E+ 08 4.4?E+ 06 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+01 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-131 8.16E+ 07 1.23E+ 07 1.43E+08 1.44E+08 2.36E+ 08 4.75E+ 10 O.OOE+Ol O.OOE+ 01 I-132 7.53E+ 01 1.93E+02 8.91E+ 01 1.64E+02 2.51E+ 02 7.60E+ 03 O.OOE+ 01 O.OOE+ 01 I-l 33 1.67E+06 1.78E+06 3.57E+ 06 4.42E+ 06 7.36E+ 06 8.21E+ 08 O.OOE+ 01 O.OOE+01 I-135 5.54E+ 04 8.92E+ 04 6.50E+ 04 1.17E+ 05 1.79E+ 05 1.04E+ 07 O.OOE+01 O.OOE+ Ol 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.OQE+Ol 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 7.8?E+ 04 O.OOE+ 01 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+ Ol O.OOE+ 01 Ce-l44 6.49E+ 06 9.94E+ 09 1.22E+ 08 3.81E+ 07 2.11E+ 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 Vaiues in units of mremlyr per yCI/m for inhalation and tritium and in units of mremlyr per yCilsec per m'or ail others.

3-37

Shearon Harris Nuclear Power Plant (SHNPP) August l994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Meat GROUP ~ Adult XJhulg Ihyraid 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 1.1 8E+ 08 3.43E+ 08 3.05E+ 09 1.89E+ 08 O.OOE+ 01 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+ 01 O.OOE+ 01 1.04E+08 O.OOE+ 01 Co.58 2.43E+07 2.20E+08 O.OOE+01 1.08E+07 O.OOE+ 01 O.OOE+ 01 O.OOE+ O'I O.OOE+ Ol Co.60 1.03E+08 8.76E+08 O.OOE+01 4.66E+07 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol 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+06 2.92E+ 07 1.82E+08 O.OOE+Ol O.OOE+ 01 O.OOE+01 O.OOE+ 01 O.OOE+01 Sr-90 2.02E+09 2.38E+08 8.22E+ 09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.005+ 01 Y-91 1.8OE+ 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+01 Nb-95 4.12E+05 4.65E+09 1.38E+06 7.66E+05 7.58E+05 O.OOE+01 O.OOE+01 O.OOE+01 Ru-103 2.72E+07 7.38E+09 6.32E+07 O.OOE+01 2.41E+08 O.OOE+01 O.OOE+01 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+01 O.OOE+01 O.OOE+01 Sn-113 2.80E+ 07 5.1 9E+ 08 2.97E+ 07 1.15E+06 8.40E+05 4.03E+05 O.OOE+01 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+01 Te-127M 1.00E+08 2.76E+ 09 8.22E+ 08 2.94E+ 08 3.34E+ 09 2.10E+ 08 O.OOE+ Ol O.OOE+ 01 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 1-131 5.77E+ 06 2.66E+ 06 7.04E+06 1.01E+07 1.73E+07 3.30E+09 O.OOE+ 01 O.OOE+ 01 I-133 1.51E.01 4A6E-01 2.85 E-01 4.96E-01 8.66E-01 7.29E+ 01 O.OOE+01 O.OOE+ 01 I-135 6.07E-1 7 1.86E-1 6 6.28E-17 1.64E-16 2.64E-16 1.08E-14 O.OOE+01 O.OOE+Ol Cs-1 34 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 1.65E+07 O.OOE+ 01 2.27E+ 06 O.OOE+01 Cs-1 37 4.99E+ 08 1.47E+ 07 5.57E+08 7.61E+ 08 2.58E+ 08 O.OOE+ Ol 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 C0-141 6.46E+ 02 2.1 8E+ 07 8.42E+ 03 5.69E+ 03 2.65E+ 03 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ce-144 4.70E+ 04 2.96E+ 08 8.75E+ 05 3.66E+ 05 2.1 7E+ 05 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Hf-1 81 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 Values in units of mrem/yr per yCi/ms for inhalation and tritium and in units of mrem/yr'per yCi/sec per me for ail others.

3-38

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3 6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT PATHWAY ~ Meat AGE GROUP ~ Teen btuciide Zjhady Ihyraid H-3 1.95E+02 1.95E+02 O.OOE+ 01 1.95E+ 02 1.95E+02 1.95E+02 1.95E+ 02 1.95E+02 P-32 9.98E+07 2.16E+08 2.58E+ 09 1.60E+08 O.OOE+ Ol O.OOE+ Ol 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 1.15E+ 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 1.1 5E+ 08 O.OOE+ 01 8.36E+ 06 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Co-60 8.15E+07 4.71E+08 O.OOE+01 3.62E+07 O.OOE+01 O.OOE+Ol O.OOE+01 O.OOE+Ol Zn.65 2.83E+08 2.57E+08 1.75E+08 6.07E+ 08 3.89E+ 08 O.OOE+ Ol O.OOE+ 01 O.OOE+Ol Rb-86 1.19E+08 3.76E+07 O.OOE+ 01 2.54E+08 O.OOE+Ol O.OOE+01 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+Ol O.OOE+01 O.OOE+ 01 Sr-90 1.31E+09 1A9E+08 5.32E+ 09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Y-91 1.52E+04 2.33E+08 5.68E+ 05 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol O.OOE+01 O.OOE+01 Zr-95 1.95E+05 6.53E+ 08 8.97E+ 05 2.83E+05 4.1 6E+ 05 O.OOE+ 01 O.OOE+Ol 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 0 OOE+ 01 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 2.22E+ 07 2.51E+08 2.09E+07 8.80E+05 6.19E+05 2.88E+05 O.OOE+01 O.OOE+ Ol 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+Ol 1-131 4AOE+06 1.62E+06 5.85E+06 8.20E+ 06 1 AlE+ 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+ 01 I-135 4.88E-1 7 1.46E-1 6 5.1 1E-1 7 1.32E-1 6 2.08E-1 6 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+Ol 9.11E+07 O.OOE+01 Cs-1 36 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 BQ-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 5A2E+02 1.35E+07 7.07E+03 4.72E+03 2.22E+03 O.OOE+01 O.OOE+01 O.OOE+Ol 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 yCi/m'or inhalation and tritium and in units of mrem/yr per yCi/sec per m'or ail others.

3-39

Shearon Harri s Nuclear Power Plant (SHNPP) August l994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'ATHWAY

~ Meat AGE 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+ 01 8.09E+ 02 2.96E+ 03 5.40E+ 03 O.OOE+ 01 Mn-54 1.30E+06 4.08E+06 O.OOE+Ol 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+ Ol Co-58 2.99E+ 07 5.70E+ 07 O.OOE+ 01 9.76E+ 06 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Co-60 1.27E+ 08 2.38E+ 08 O.OOE+ 01 4.30E+ 07 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 Zn-65 4.35E+ 08 1.23E+ 08 2.62E+ 08 6.99E+ 08 4.40E+08 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Rb-86 2,21E+08 2.32E+07 O.OOE+01 3,60E+08 O.OOE+Ol O.OOE+01 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+ 01 O.OOE+ 01 O.OOE+ 0 1 Y-91 2.87E+04 1.43E+08 1.07E+06 O.OOE+01 O.OOE+Ol O.OOE+01 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 t Nb.95 Ru-103 Ru-106 Ag-110M Sn-113 5.17E+05 3.58E+07 3.43E+ 08 2.89E+06 3.42E+07 1.34E+09 2.41E+09 4.27E+ 10 4.305+08 1.25E+08 1.86E+06 9.31E+07 2.75E+ 09 5.36E+ 06 3.14E+07 7.23E+05 O.OOE+01 O.OOE+ 01 3.62E+ 06 1.01E+06 6.80E+05 2.34E+08 3.71E+ 09 6.74E+ 06 6.97E+05 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 4.15E+05 O.OOE+01 O.OOE+Ol O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+Ol O.OOE+01 Sb-124 6.17E+ 06 1.10E+ 08 1.76E+ 07 2.28E+05 O.OOE+01 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.OQE+01 O.OOE+Ol 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 I-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-1 7 1.27E-1 6 9.255-1 7 1.66E-1 6 2.55E-1 6 1 A7E-14 O.OOE+ 01 O.OOE+ 01 Cs-1 34 1.95E+08 4.93E+06 5.63E+08 9.23E+08 2.86E+08 O.OOE+01 1.03E+08 O,005+ Ol Cs-136 1.80E+ 07 9.78E+ 05 1.01E+ 07 2.78E+ 07 1.48E+ 07 0 OOE+ 01 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+ 01 9.55E+ 07 O.OOE+ Ol Ba-140 1.63E+06 1.42E+07 2.80E+07 2.45E+04 7.97E+03 O.OOE+01 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+01 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+01 O.OOE+ 01 Hf-181 2.02E+06 3.31E+08 2.0OE+07 7.79E+04 6.26E+04 6.56E+04 O.OOE+01 O.OOE+ 01

'R Values in units of mrem/yr per pCi/ms for inhaIation and tritium and in units of mrem/yr per /ICI/sec per me for all others.

3-40

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3.8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT" PATHWAY ~ Cow Milk AGE GROUP ~ Adult 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+Ol O.OQE+01 O.OOE+Ol 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+ 01 Mn-54 9.76E+ 05 1.57E+ 07 O.OOE+ 0 1 5.1 1E+ 06 1.52E+ 06 O.OOE+ Ol O.OOE-01 O.OOE+ 01 Fe-59 1.60E+ 07 1.39E+ 08 1.77E+ 07 '.17E+ 07 O.OOE+ 01 O.OQE+ 01 1.1?E+ 07 O.QQE+ Ol Co-58 6.28E+06 5.68E+07 O.OQE+01 2.80E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OQE+Ol Co.60 2.24E+07 1.91E+08 O.OQE+01 1.02E+07 O.QOE+01 O.OOE+01 O.OOE+Ol O.OOE+01 Zn-65 1.38E+09 1.92E+09 9.59E+08 3.05E+09 2.04E+09 O.OQE+Ol O.OOE+Ol O.QOE+01 Rb-86 7.54E+08 3.19E+08 O.OOE+01 1.62E+09 O.OOE+01 O.OQE+01 O.OOE+01 O.OOE+01 Sr-89 2.50E+07 1.40E+08 8.?OE+08 O.OOE+Ol O.OOE+01 O.OOE+01 O.OQE+01 O.OOE+01 Sr-90 7.59E+ 09 8.94E+ 08 3.09E+ 10 O.OOE+ 01 O.OOE+ 01 O.OQE+ 01 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+Ol O.OOE+01 O.OOE+01 Zr-95 1.22E+ 02 5.71E+ 05 5.62E+ 02 1.80E+ 02 2.83E+ 02 O.QOE+ Ol 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.OQE+Ql O.OOE+01 O.OOE+01 Ru-106 1.60E+03 8.17E+05 1.26E+ 04 O.OOE+01 2.44E+ 04,0.00E+ 01 O.OOE+ 01 O.OOE+ 01 Ag-110M 2.04E+ 07 1 AOE+ 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 1.9OE+04 O.OOE+01 O.OOE+01 Sb-124 6.14E+06 4.39E+08 1.55E+07 2.92E+05 O.OOE+01 3.75E+04 1.20E+07 O.OOE+01 Te-127M 4.1 1 E+ OS 1.1 3E+ 08 3.37E+ 07 1.21 E+ 0? 1.37E+ 08 8.62E+ 06 O.QQE+01 O.OOE+ 01 Te-129M 6.19E+ 06 1.97E+08 3.91E+ 07 1 A6E+ 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+01 1.03E+Ol O.OOE+01 O.OOE+Ol I-1 33 1.4QE+06 4.13E+OS 2.64E+06 4.59E+06 8.01E+OS 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+Ol Cs-1 34 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.?3E+08 7.46E+07 1.66E+08 6.57E+08 3.65E+08 O.QQE+01 5.01E+07 O.OOE+01 Cs-1 37 4.22E+ 09 1.25E+ 08 4.71E+ 09 6.44E+ 09 2.19E+ 09 O.QOE+ 01 7.27E+ 08 O.QQE+ Ql Ba-140 1.12E+06 3.53E+ 07 1.71E+ 07 2.15E+ 04 7.32E+ 03 O.OOE+ Ol 1.23E+ 04 O.OOE+ 01 Ce-141 2.23E+ 02 7.52E+ 06 2.91E+03 1.9?E+03 9.14E+Q2 O.QOE+01 O.OOE+Ol O.OQE+Ol Ce-144 1.15E+ 04 7.26E+ 07 2.15E+ 05 8.97E+ 04 5.32E+ 04 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Hf-181 6.68E+ 02 4.38E+ 05 5.91E+ 03 3.33E+01 2.79E+01 2.12E+01 O.OQE+01 O.OOE+01

'R Values in units of mrem/yr per pCi/m'or inhalation and tritium and in units of mrem/yr per pCi/sec per m'or 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'ATHWAY

~ Cow Milk AGE GROUP ~ Teen IhyraiL H-3 1.00E+03 1.00E+03 O.OOE+ 01 1.00E+03 1.0OE+ 03 1.00E+03 1.00E+03 1.00E+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+ 01 Mn-54 1.69E+06 1.75E+ 07 O.OOE+ 01 8.52E+ 06 2.54E+ 06 O.OOE+ Ol 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+ 01 Co-58 1.09E+07 6.50E+ 07 O.OOE+ 01 4.72E+ 06 O.OOE+01 O.OOE+Ol O.OOE+ Ol O.OOE+ Ol 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 5.1 1E+ 09 3.27E+ 09 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 1.39E+ 09 4.37E+ 08

'b-86 O.OOE+ 01 2.95E+ 09 O.OOE+ Ol O.OOE+Ol O.OOE+ Ol O.OOE+ 01 Sr-89 4,59E+ 07 1.91E+ 08 1,60E+ 09 O.OOE+ Ol 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+ Ol 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+Ol 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+ Ol Nb-95 2.58E+04 2.0OE+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+01 Ru-106 2.93E+03 1.11E+06 2.32E+04 O.OOE+01 4.48E+04 O.OOE+01 O.OOE+01 O.OOE+ 01 Ag-1 10M 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-124 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 I~ 132 1.83E+01 2.22E+01 1.94E+Ol 5.09E+01 8.02E+01 1.71E+01 O.OOE+ 01 O.OOE+ 01 I-133 2A9E+06 6.19E+06 4.82E+ 06 8.18E+06 1.43E+ 07 1.14E+09 O.OOE+ 01 O.OOE+ 01 I-1 35 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 7A8E+08 8.97E+07 2.83E+08 1.11E+09 6.07E+ 08 O.OOE+ 01 9.5 6E+ 07 O.OOE+ 01 Cs-137 3.96E+09 1.62E+08 8.54E+09 1.14E+ 10 3.87E+09 O.OOE+01 1.50E+09 O.OOE+01 BQ-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+Ol O.OOE+01 O.OOE+01 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-1 81 1.18E+ 03 5.28E+ 05 1.06E+04 5.82L+Ol 4.84E+01 3.55E+01 O.OOE+01 O.OOE+01

'R Values in units of mrern/yr per yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/sec per mr 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 XJhndg JQdney 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+ 01 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+Ol 1.27E+07 3.57E+ 06 O.OOE+01 O.OOE+01 O.OOE+01 Fe.59 5.79E+ 07 1.21E+ 08 7.18E+07 1.16E+08 O.OOE+ 01 O.OOE+Ol 3.37E+07 O.OOE+01 Co-58 2.21E+ 07 4.20E+07 O.OOE+ Ol 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+Ol 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 SA7E+09 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-89 1.13E+08 1.54E+08 3.97E+ 09 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 O.OOE+Ol O.OOE+01 Sr-90 1.87E+ 10 9.95E+ 08 7.38E+ 10 O.OOE+ 01 O.OOE+ Ol 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 7.1 8E+ 02 O.OOE+ Ol 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+01 O.OOE+01 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+01 O.OOE+01 Ru-106 7.14E+03 8.90E+05 5.72E+ 04 O.OOE+Ol 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+Ol 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-1 27M 1.82E+ 07 1.24E+08 1.53E+08 4.1 3E+ 07 4.37E+ 08 3.66E+ 07 O.OOE+ 01 O.OOE+ Ol 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 1ASE+07 2.41E+ 07 2.69E+ 09 O.OOE+ 01 O.OOE+ 01 I-1 35 3.35E+ 04 5.39E+ 04 3.93E+ 04 7.07E+04 1.08E+05 6.26E+06 O.OOE+ 01 O.OOE+ Ol 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 6.1 7E+ 07 6.39E+ 08 1.76E+09 9.36E+ 08 O.OOE+ 01 1.40E+08 O.OOE+ 01 Cs-1 37 2.91E+ 09 1.23E+08 2.06E+ 10 1.97E+ 10 6.42E+ 09 O.OOE+ 01 2.31E+ 09 O.OOE+ Ol 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+01 Ce-144 5.20E+04 7.96E+07 9.74E+05 3.05E+ 05 1.69E+05 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 Hf-181 2.53E+03 4.16E+05 2.51E+04 9.79E+01 7.86E+01 8.24E+01 O.OOE+01 O.OOE+01 I

'R Vaiues 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.

3-43

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'ATHWAY

= Cow Milk AGE GROUP ~ Infant bhuJ/da Xidttatr Ihyrnid H-3 2.40E+ 03 2.40E+ 03 O.OOE+ 01 2.40E+03 2.40E+ 03 2.40E+03 2AOE+03 2.40E+03 P-32 4.06E+ 09 1.42E+09 1.05E+ 1 1 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+ 0 1 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+ Ol 2.37E+ 07 5.25E+ 06 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Fe-59 9.23E+07 1.12E+08 1.34E+08 2.34E+08 O.OOE+ 01 O.OOE+ Ol 6.92E+ 07 O.OOE+ 01 Co.58 3.60E+07 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+ Ol O.OOE+ 01 Zn.65 '.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+ 01 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 1.1 6E+ 08 3.1 2E+ 06 4.36E+ 04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 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+01 O.OOE+01 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

'u-106 1.47E+04 8.95E+ 05 1.18E+05 O.OOE+ 01 1.39E+05 O.OOE+ 01 O.OOE+ Ol 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+ Ol 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+ 01 O.OOE+ Ol 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+ 01 I-1 32 6.90E+01 1.57E-OO 9.55E+ 01 1.94E+ 00 2.16E+ 00 9.09E+01 O.OOE+ 01 O.OOE+ 01 1-133 1.05E+07 6.09E+ 06 2.47E+ 07 3.60E+ 07 4.23E+ 07 6.55E+ 09 O.OOE+ Ol 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-1 34 4.19E+09 1.13E+08 2.23E+ 10 4.15E+ 10 1.07E+ 10 O.OOE+ 01 4.38E + 09 O.OOE + Ol Cs-136 1.37E+09 5.58E+ 07 1.25E+ 09 3.67E+ 09 1.46E+09 O.OOE+ 01 2.99E+08 O.OOE+01 Cs-137 2.72E+09 1.20E+08 3.28E+10 3.84E+10 1.03E+10 O.OOE+01 4.18E+09 O.OOE+ 01 Ba-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+ Ol O.OOE+ 01 Ce.144 7.82E+ 04 8.01E+07 1AOE+06 5.71E+05 2.31E+05 O.OOE+01 O.OOE+ 01 O.OOE+01 Hf-181 4.23E+ 03 3.93E+ 05 4.78E+ 04 2.26E+ 02 1.32E+ 02 1.91E+ 02 O.OOE+01 O.OOE+ 01

'R Values in units of mrem/yr per yCi/m'or inhalation and tritium and in units ot mrem/yr per yCi/sec m'~

per for ail 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'G PATHWAY ~ Goat Milk E GROUP = Adult JQrhmy IhyuiuL 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+01 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 1.81 E+ 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+Ol O.OOE+01 O.OOE+Ol Zn-65 1.65E+08 2.31E+08 1.15E+08 3.66E+08 2.45E+08 O.OOE+Ol O.OOE+Ol O.OOE+01 Rb.86 9.05E+ 07 3.83E+07 O.OOE+ 01 1.94E+08 O.OOE+ 01 O.OOE+ 01 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+ Ol 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 6.13E+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 2.1 6E+01 3.39E+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ Ol Nb-95 1.78E+03 2.01E+ 07 5.94E+ 03 3.31E+ 03 3.27E+ 03 O.OOE+ Ol O.OOE+ 01 O.OOE+Ol RU-103 3.16E+01 8.56E+ 03 7.33E+01 O.OOE+01 2.80E+02 O.OOE+01 O.OOE+Ol 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+ 01 O.OOE+ 01 Ag.110M 2.45E+ 06 1.68E+09 4.46E+06 4.12E+06 8.1 1E+ 06 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sn-113 '.32E+05 2.44E+06 1.40E+05 5.41E+ 03 3.96E+ 03 1.90E+ 03 O.OOE + 01 O.OOE+01 Sb-124 7.36E+ 05 5.27E+ 07 1.86E+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 2.36E+07 4.69E+06 1.75E+06 1.96E+07 1.61E+06 O.OOE+Ol O.OOE+01 I-131 1.91E+ 08 8.78E+ 07 2.33E+08 3.33E+ 08 5.71E+ 08 1.09E+11 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 3.1 7E+ 06 5.51E+ 06 9.61E+06 8.10E+ 08 O.OOE+01 O.OOE+01 I-1 35 1.08E+04 3.32E+04 1.12E+04 2.94E+ 04 4.71E+ 04 1.94E+06 O.OOE+ 01 O.OOE+ 01 Cs-134 2.01E+ 10 4.31E+08 1.03E+ 10 2.46E+ 10 7.97E+09 O.OOE+Ol 2.65E+ 09 O.OOE+ 01 Cs-136 1.42E+09 2.24E+ 08 4.99E+ 08 1.97E+09 1.10E+09 O.OOE+01 1.50E+ 08 O.OOE+01 Cs-1 37 1.27E+ 10 3.74E+ 08 1.41E+ 10 1.93E+10 6.56E+ 09 O.OOE+ 01 2.1 BE+ 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+ Ol 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+ Ol 5.26E+ 04 7.09E+ 02 3.99E+ 00 3.34E+ 00 2.54E+ 00 O.OOE+ 01 O.OOE+ Ol

'R Values in units of mrem/yr per yci/me for inhalation and tritium and in units of mrem/yr per yci/seo per m'or ail others.

3-45

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manua3. (ODCM) Rev. 5 TABLE 3.3-13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Goat Milk GROUP ~ Teen Lundy. JGdn alt. ZhyLouL 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+ 01 Cr-51 3.63E+03 6.10E+05 O.OOE+ 01 O.OOE+ Ol 7.95E+ 02 2.02E+ 03 5.18E+03 O.OOE+ 01 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+ 01 2.96E+ 05 O.OOE+Ol Co.58 1.30E+ 06 7.80E+ 06 O.OOE+ 0 1 5.66E+ 05 O.OOE + 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Co-60 4.66E+06 2.69E+07 O.OOE+01 2.07E+06 O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+ 01 Zn-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+01 O.OOE+ 01 O.OOE+ Ol O.OOE+ Ol Sr-89 9.65E+ 07 4.01E+08 3.37E+09 O.OOE+ 01 O.OOE+ 01 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+ Ol 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+01 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+ 01 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+ Ol 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+ 01 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 3.1 9E+ 06 3.59E+ 07 2.77E+ 06 O.OOE+ Ol 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+ 01 O.OOE+ 01 I-132 2.19E+01 2.66E+ 01 2.33E+01 6.11E+01 9.62E+ 01 2.06E+ 01 O.OOE+01 O.OOE+ 01 I-133 2.99E+ 06 7.43E+ 06 5.79E+ 06 9.81E+ 06 1.72E+ 07 1.37E+ 09 O.OOE+ 01 O.OOE+ 01 l.135 1.9OE+04 5.63E+04 1.99E+ 04 5.1 3E+ 04 8.10E+ 04 3.30E+ 06 O.OOE+ Ol O.OOE+ 01 Cs-1 34 1.96E+ 10 5.26E+ 08 1.80E+ 10 4.23E+ 10 1.34E+10 O.OOE+ 01 5.1 3E+ 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-1 37 1.19E+10 4.85E+ 08 2.56E+10 3.41E+ 10 1.16E+ 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+ Ol 3.06E+ 03 O.OOE+ Ol 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 C@-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 mrem/yr per /ICI/ms for inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-46

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~ Goat Milk GROUP ~ Chiid JQdnev thyroid H-3 Id'.23E+03 3.23E+03 3.23E+ 03 3.23E+ 03 3.23E+03 3.23E+ 03 3.23E+03 O.OOE+Ol P-32 2.35E+09 1.69E+09 6.11E+10 2.86E+09 O.OOE+ 01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 Cr.51 7.40E+ 03 3.93E+ 05 O.OOE+ 01 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 O.OOE+ 01 O.OOE+ 01 Fe-59 7.52E+ 05 1.57E+ 06 9.34E+ 05 1.51E+06 O.OOE+ 01 O.OOE+ Ol 4.38E+05 O.OOE+01 Co-58 2.65E+06 5.05E+06 O.OOE+01 8.65E+05 O.OOE+Ol O.OOE+01 O.OOE+01 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+ Ol Rb-86 4.04E+08 4.22E+07 O.OOE+ 01 6.57E+ 08 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-89 2.38E+08 3.23E+08 8.34E+09 O.OOE+01 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-90 3.93E+ 10 2.09E+ 09 1.55E+ 1 1 O.OOE+ Ol O.OOE+01 O.OOE+ 01 O.OOE+ Ol O.OOE+ 01 Y-91 7.45E+01 3.71E+05 2.79E+03 O.OOE+01 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+ 01 Zr-95 5.36E+01 6.28E+04 2.74E+ 02 6.02E+ Ol 8.62E+ 01 O.OOE+Ol O.OOE+ 01 O.OOE+ Ol 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+ 01 7.77E+ 02 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Ru-106 '.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 1.3'6E+ 04 9.38E+03 5.59E+03 O.OOE+ 01 O.OOE+ 01 Sb-124 2.75E+06 4.91E+07 7.84E+ 06 1.02E+05 O.OOE+ Ol 1.73E+04 4.35E+06 O.OOE+Ol Te-127M 2.18E+ 06 1.49E+ 07 1.84E+07 4.95E+06 5.24E+07 4.40E+ 06 O.OOE+ 01 O.OOE+ 01 Te-129M 3.28E+ 06 2.58E+ 07 2.12E+07 5.91E+06 6.21E+07 6.82E+06 O.OOE+01 O.OOE+ 01 I-131 5.85E+08 9.17E+07 1.02E+ 09 1.03E+ 09 1.69E+09 3A1E+11 O.OOE+Ol O.OOE+ 01 I-1 32 4.67E+01 1.19E+00 5.52E+ Ol 1.01E+ 00 1.555+ 00 4.71E+ 01 O.OOE+ Ol O.OOE+ 01 I-133 6.58E+06 7.00E+06 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 8A9E+04 1.30E+05 7.52E+ 06 O.OOE+ 01 O.OOE+ 01 Cs-134 . 1 A3E+ 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 O.OOE+ 01 4.19E+08 O.OOE+01 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+ Ol 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+ 01 Ce-144 6.24E+03 9.55E+ 06 1.17E+ 05 3.66E+ 04 2.03E+ 04 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Hf-181 3.04E+ 02 4.99E+ 04 3.02E+ 03 1.17E+ 01 9.43E+ 00 9.88E+ 00 O.OOE+ Ol 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 rn'or all others.

3-47

Shearon Harris Nuclear Power Plant (SHNPP) August l994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PI.ANT'GE PATHWAY ~ Goat Milk GROUP ~ Infant LJhulV. QLIrau edna@ Ihyra'uL 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+ 01 O.OOE+ 01 Cr-51 1.17E+ 04 3.42E+ 05 O.OOE+ Ol O.OOE+ 01 1.67E+03 7.65E+ 03 1A9E+04 O.OOE+ 01 Mn-54 .6.45E+ 05 1.04E+ 06 O.005+ Ol 2.84E+06 6.30E+05 O.OOE+ 01 O.OOE+01 O.OOE+ 01 Fe-59 1.205+ 06 1.45E+ 06 1.74E+ 06 3.04E+ 06 O.OOE+ 01 O.OOE+ 01 9.00E+05 O.OOE+ 0 1 Co-58 4.31E+06 4.31E+06 O.OOE+Ol 1.73E+06 O.OOE+ Ol O.OOE+ Ol O.OOE+ Ol O.OOE+ Ol 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+OS 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+ Ol O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Sr-90 4.30E+ 10 2.11E+09 1.69E+11 O.OOE+01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 O.OOE+ 01 Y-91 1.39E+ 02 3.75E+ 05 5.23E+ 03 O.OOE+ 01 O.OOE+ 01 O.OOE+01 O.OOE+01 O.OOE+01 Zr-95 8.41E+01 5.SOE+04 4.85E+02 1.19E+02 1.28E+ 02 O.OOE+ 01 O.OOE+ Ol O.OOE+ Ol Nb-95 1.02E+04 1.48E+ 07 4.27E+ 04 1.76E+04 1.26E+04 O.OOE+Ol 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+ Ol O.OOE+01 O.OOE+Ol 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+ Ol Sn-113 6.66E+ 05 1.37E+06 6.46E.+ 05 2.45E+ 04 1.325+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+Ol Te-127M 4.51E+ 06 1.50E+ 07 3.72E+07 1.23E+ 07 9.1 6E+ 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 1.67Ef 07 O.OOE+01 O.005+ 01 I-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 I-1 32 8.28E+ 01 1.885+ 00 1.15E+00 2.33E+00 2.59E+ 00 1.09E+02 O.OOE+ 01 O.005+ 01 1-133 1.27E+07 7.31E+ 06 2.97E+07 4.32E+07 5.08E+ 07 7.86E+ 09 O.OOE+ 01 O.OOE+ 01 1-135 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. 1 34 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+Ol Ba-140 9.50E+ 05 4.53E+ 06 1.84E+07 1.84E+04 4.38E+03 O.OOE+01 1.13E+04 O.OOE+01 GIB-141 2.24E+ 02 S.85E+05 3.13E+ 03 1.91E+03 5.88E+02 O.OOE+Ol 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 5.745+ 03 2.71E+ 01 1.58E+ Ol 2.30'E+ 01 O.OOE + 01 O.OOE+Ol

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

3-48

Shearon Harris Nuclear Power Plant (SHNPP) August l994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT'GE PATHWAY ~'lnhal GROUP ~ Adult LBndy. JCidnay H-3 1.26E+ 03 1.26E+ 03 O.OOE j01 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+ 03 P-32 5.00E+04 8.63E+04 1.32E j06 7.?OE+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 j 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+Ol Fe.59 1.05E+04 1.88E+05 1.17E+04 2.7?E+04 O.OOE+ 01 O.OOE+ 01 1.01 E+ 06 O.OOE+ 01 Co-58 2.0?E+ 03 1.06E+ 05 O.OOE+ 0'I 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 1.1 5E+ 04 O.OOE+ 01 O.OOE+ 01 5.96E+ 06 O.OOE j 01 2n-65 ~

4.65E+ 04 5.34E+04 3.24E+04 1.03E+05 6.89E+04 O.OOE+01 8.63E+05 O.OOE+01 Rb-86 5.89E+ 04 1.66E+ 04 O.OOE+ 01 1.35E+05 O.OOE+ 01 O.OOE+Ol O.OOE+ 01 O.OOE+ 01 Sr-89 8.71E+ 03 3.49E+ 05 3.04E+05 O.OOE+ Ol O.OOE+ 01 O.OOE+01 1 40E+06 O.OOE jol Sr-90 6.09E+ 06 '.21E+05 9.91E+ 07 O.OOE+01 O.OOE+01 O.OOE+01 9.59E+ 06 O.OOE+ 01 Y-91 1.24E+04 3.84E+05 4.62E+ 05 O.OOE+ Ol O.OOE+ 01 O.OOE+ 01 1.70E+06 O.OOE+ 01 2r-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 Nb-95 4.20E+03 1.04E+ 05 1.41E+04 7.80E+03 7.72E+03 O.OOE+ 01 5.04E j05 O.OOE+ 01 RU-103 6.57E+ 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+01 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+Ol 4.63E+06 O.OOE+Ol 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+Ol 7.55E+ 01 2.48E+ 06 O.OOE+ 01

'I Te-127M 1.57E+03 1.49E+ 05 1.26E+ 04 5.76E+ 03 4.57E+ 04 3.28E+ 03 9.59E j05 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+ O'I I-1 31 2.05E+ 04 6.27E+ 03 2.52E+04 3.57E+ 04 6.12E+ 04 1.1 9E+ 07 O.OOE+ 01 O.OOE+ Ol 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-1 33 4.51 E+ 03 8.8?E+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 j05 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+ 01 7.51E+ 04 O,OOE+01 Ba-140 2.56E+ 03 2.18E+05 3.90E+ 04 4.90E+01 1.67E+ 01 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+ Ol Hf-1 81 5.16E+03 1.29E+ 05 4.56E+ 04 2.57E+02 2.15E+02 1.63E+02 5.99E j05 O.OOE+01 I

'R Values in units of mrem/yr per yCi/ms for inhalation and tritium and in units of mrem/yr per yCi/sec per ma 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. JQdnav H-3 1.27E+03 1.27E+ 03 O.OOE+01 1.27E+ 03 1.27E+ 03 1.27E+03 1.27E+ 03 1.276+03 P-32 7.15E+04 9.27E+04 1.89E+06 1.09E+05 O.OOE+ 01 0.006+01 O.OOE+01 O.OOE+01 Cr-51 1.35E+02 3.006+03 O.OOE+ 01 O.OOE+01 3.07E+01 7.496+01 2.09E+04 O.OOE+01 Mn.54 8.3SE+03 6.67E+04 0.006+ 0'I 5.10E+ 04 1.27E+04 O.OOE+ 01 1.98E+06 O.OOE+01 Fe-59 1 A3E+04 1.78E+ 05 1.59E+04 3.69E+ 04 O.OOE+ 01 O.OOE+ 01 1.53E+06 O.OOE+01 Co-58 2.77E+03 9.51E+ 04 O.OOE+ 01 2.07E+03 O.OOE+ 01 0.006+ 01 1.34E+06 O.OOE+01 Co.60 1.98E+04 2.59E+05 O.OOE+ 01 1.51E+04 O.OOE+ 01 0 OOE+01 8.71E+06 O.OOE+01 Zn-65 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 1.776+04 O.OOE+01 1.90E+05 O.OOE+ 01 O.OOE+ 01 O.OOE+01 O.OOE+01 Sr-89 1.25E+ 04 3.716+05 4.34E+ 05 O.OOE+01 O.OOE+01 O.OOE+ 01 2A1E+06 O.OOE+ 01 Sr-90 6.67E+ 06 7.64E+ 05 1.08E+08 O.OOE+01 O.OOE+ Ol 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 1.496+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+Ol 7.50E+ 05 O.OOE+ Ol Ru.103 8.95E+ 02 1.09E+ 05 2.10E+ 03 O.OOE+ 01 7A2E+03 0.006+ 01 7 82E+05 0.006+01 Ru. 1 06 ~

1.246+ 04 9.59E+05 9.83E+ 04 O.OOE+ 01 1.90E+05 O.OOE+ Ol 1 61E+07 O.OOE+ 01 Ag.110M 7.98E+03 2.72E+ 05 1.38E+04 1.31E+04 2.5OE+ 04 Q.OOE+ 01 6.74E+ 06 O.OOE+01 Sn-113 8.68E+ 03 2.03E+ 04 8.196+ 03 SA46+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.S4E+ 02 O.OOE+Ol 9 76E+01 3.85E+06 O.OOE+01 Te-12/M 2.18E+ 03 1.59E+05 1.80E+04 8.15E+03 6.53E+04 4.386+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 1.46E+ 07 O.OOE+ Ol O.OOE+Ol I-132 1.57E+03 1.27E+03 1.59E+03 4.37E+ 03 6.91E+03 1.51E+ 05 O.OOE+ Ol 0.006+01 I-133 6.21E+ 03 1.03E+04 1.21E+ 04 2.05E+ 04 3.59E+ 04 2.92E+06 O.OOE+Ol O.OOE+01 I-135 3.48E+ 03 6.946+ 03 3.69E+ 03 9.43E+ 03 1.49E+ 04 6.20E+ 05 O.OOE+ Ol O.OOE+ 01 Cs-134 5.48E+ 05 9.75E+03 5.02E+05 1.13E+06 3.75E+ 05 O.OOE+ 0 1 1.46E+ 05 O.OOE+ 01 Cs-1 36 1.37E+ 05 1.09E+ 04 5.14E+ 04 1.93E+ 05 1.10E+05 O.OOE+ 01 1.776+04 O.OOE+01 Cs-137 3.11E+ 05 8.48E+ 03 6.69E+ 05 8.47E+ 05 3.04E+ 05 O.OOE+ 01 1.21E+05 O.OOE+01 BQ-140 3.51E+03 2.28E+ 05 5.46E+ 04 6.69E+ Ol 2.28E+ 01 O.OOE+ 01 2.03E+ 06 O.OOE+01 Ce-141 2.16E+03 1.26E+05 2.84E+04 1.89E+04 8.87E+03 O.OOE+ 01 6.136+05 O.OOE+01 Ce-144 2.62E+ 05 8.63E+05 4.88E+06 2.02E+06 1.21E+06 O.OOE+ 01 1.336+07 O.OOE+ 01 Hf-181 7.04E+03 1.20E+05 6.32E+04 3A8E 02 2.90E+02 2.12E+02 9.396+ 05 O.OOE+ 01 I

4

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

I 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 IJhdg GLIBJ 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+ Ol O.OOE+ 01 2.43E+ 01 8.53E+01 1.70E+ 04 O.OOE+ 01 Mn.54 9.50E+03 2.29E+04 O.OOE+01 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+ Ol Co.58 3.16E+03 3.43E+04 O.OOE+01 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+Ol 1.31E+04 O.OOE+01 O.OOE+01 7.06E+06 O.OOE+01 Zn-65 7.02E+ 04 1.63E+04 4.25E+04 1.1 3E+ 05 7.1 3E+ 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+ 01 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+01 Y-91 2.43E+ 04 1.84E+ 05 9.13E+ 05 O.OOE+01 O.OOE+Ol 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 4.47E+04 2.79E+03 O.OOE+01 7.02E+03 O.OOE+ 01 6.61E+05 O.OOE+Ol 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+01 5.47E+06 O.OOE+ 01 Sn-113 9.83E+ 03 7.45E+ 03 9.0OE+ 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+ Ol Te-127M 3.01E+ 03 7.13E+04 2ABE+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 I-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 I-1 33 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-134 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 O.OOE+01 1.45E+04 O.OOE+Ol Cs-137 1.28E+05 3.61E+ 03 9.05E+05 8.24E+05 2.82E+05 O.OOE+ 01 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+ Ol 5.43E+ 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 in units of mrem/yr per pCi/ms for inhalation and tritium and in units of mrem/yr per /rCI/sec per m'or all others.

3-51

Shearon Harris Nuclear Power Plant (SHNPP) August 1994 Offsite Dose Calculation Manual (ODCM) Rev. 5 TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANTS PATHWAY ~ Inhal AGE GROUP ~ Infant XJ3ady. GLIcaa 6.46E+ 02 6.46E+02 O.OOE+ 01 6.46E+ 02 6.46E+ 02 6A6E+02 6.46E+ 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+ Ol Cr-5\ 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+Ol 2.53E+04 4.SSE+ 03 O.OOE+Ol 9.98E+ 05 O.OOE+ Ol Fe-59 9.46E+ 03 2.47E+ 04 1.35E+ 04 2.35E+04 O.OOE+ 01 O.OOE+Ol 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+01 O.OOE+ Ol 4.50E+06,0.00E+01 Zn-65 3.10E+ 04 5.13E+04 1.93E+04 6.25E+04 3.24E+04 O.OOE+ 01 6A6E+ 05 O.OOE+ Ol 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+01 O.OOE+01 O.OOE+Ol 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-S 1 1.57E+04 7.02E+04 5.87E+05 O.OOE +01 O.OOE+Ol O.OOE+01 2.45E+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+ Ol Nb-95 3.77E+ 03 1.27E+ 04 1.57E+04 6.42E+ 03 4.71E+03 O.OOE+Ol 4.78E+05 O.OOE+ 01 Ru-103 6.78E+ 02 1.61E+ 04 2.01E+03 O.OOE+01 4.24E+03 O.OOE+01 '.51E+05 O.OOE+01 RQ-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+ 01 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+ Ol Sb.124 1.20E+04 5.91E+ 04 3.79E+04 5 56E+02 O.OOE+ 01 1.00E+02 2.64E+ 06 O.OOE+ 01 Te-1 27M 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+ Ol 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.005+ 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-1 36 5.28E+ 04 1.43E+ 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 5ABE+05 6.11E+05 1.72E+05 O.OOE+01 7.1 2E+ 04 O.OOE+ 01 Ba.140 .2.89E+ 03 3.83E+ 04 5.59E+04 5.59E+01 1.34E+01 -

O.OOE+ 01 1.59E+06 O.OOE+ 01 Ce-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+ 01 9.83E+ 06 0 OOE+01 Hf-181 5.05E+ 03 1.SOE+ 04 5.65E+04 2.66E+02 1.5SE+02 2.25E+02 6.73E+ 05 O.OOE+ 01

'R Vaiues in units of mrem/yr per/rCI/m~ for inhalation and tritium and in units of mrem/yr per yCI/sec per m'~ for 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 RDt. Rootoeor Lrnooor air otor tl?s tv~Pro ~tmrt RAR.Roooror Aooarorr Rut RIIIIYJQslt4%asr RM Bra Fool tlootuot trit SiÃbt trvro Rooto Ooo Ãooxoo RtltltVJQI RM Roosoeoo )looaor Condenser Vacutn Puinp .

Condcnscr Polisher Arcs WPB Vent Stack 5 WPB Hot 8 Cold Laundry WPB ericc Arts Exhaust WPS Cold Laundry Orycrs WPB Control Room Smoke Exhaust WPBOlricc Areas WPB General Area Exhaust WPS Chiller Room Exhaust Waste Gas Decay Tanks Waste Processing Area Filtercd Exhaust WPB Vent Stack 5A RlotoOVJSOI OOXCIIt REM 1tQ4IIYJsrr WPB Switchgear Room Exhaust WPB HVAC Equip. Room Ethanol WPB PersonnelHandeling Facility Exhaust WPB Hol 8 LorrAcBvity Labs Exhaust WPB Lah Areas Exhaust Plant Vent Stack 1 lll4IAVJIISILIrwxcso RAIIILI4xrra RM RIISIAYJlrrsx Containrnenl Piekntry Purge RISSIAVJQI FHB Normal Exhaust North RAB Normal Exhaust FHB Normal Exhaust South RIISIAVJQIA Rtstl ILJQO RAB Emergency Exhaust Rtss)AYJQI4 FHB Normal Exhaust(Oper. Ft) Sou4h RIISI ILJ sir RAB Vcntiiatlcn System FHB Normlt Exhaust(Oper. Ftj North RIISIILJQIAJA Hydrogen Purge RAB Smoke Purge XIXSIKJ4OOSI4 FHB Emergency Exhaust RAB Purge 3-53

0 Ol W 0 Gl Pl Ct 0 0

U X PLANT 0 Cll NORTH (P r.

MAONETIC n In

~ NORTH I 25 0 C 0

0 CO (D

0 O Ct Dl Cl

r. g 0 0 Z VENT STACK 0

0 z g iD Z O Z 0 Pze 0 C Ql PQ 0 I LI UNIT ILl Z U 0 Ct 0 U IO O~

3,'D)

CC

'ENTSTACK D CQ A

CD 'z

'6 COOLINO m ~Q TOWER Cd C

CD WATER SERVICE ECURIT EATME BI OO, OOO PARKING AREA XI CD WARE HOUSE QER CD 0)

Ch CD 0

tj SWITCHYARD 0

PARKING V)

QQ AEA Cl

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 Monitor (WRCM)

RM.1 TV4330.1 Gland Steam Condenser CVPETS "

Main Condenser REM REM.1TV 3334 Hogglrig Valve Atmosphere Blind Flange 3-55

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

Figure 4.1-1 shows the exclusion boundary surrounding SHNPP.

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

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 Required Analysis: l-131 (charcoal canisters)

Beta'eekly Quarterly Gamma Isotopic'~ (Composited b location)

Sample Point ZD 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.

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

NNE sector, 3.1 mi. from site.

Pittsboro (Control Station)'NW sector from site, > 12 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 1.3 mi. N on SR 1912 from intersection of NC 42 SSW sector, 3.4 miles from site

~ I

~ ~ s o ~ o ~

~ ~ ~ ~

~ ~ 0

~ 0 ~ 0 I~

~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ 0 0

~ ~

~ I I-.o ~ ~ ~ 0 I ~

I o ~ ~

o I

~ ~

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 per uarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point ID No. Sample Point, Description', Distance, and Direction 15 SR 1911.

W sector, 2.0 mi. from site.

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

WNW sector 1.9 mi. from site.

Intersection of US 1 and Aux. Res.

NW sector, 1.5 mi. from site.

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

NNW sector, 1.4 mi. from site.

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

NNE sector 5.0 .mi. from site.

20 US 1 at intersection SR 1149.

NE sector 4.5 mi. from site.

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

ENE sector, 4.8 mi. from site.

22 Formerly Ragan's Dairy on SR 1115.

E sector, 4.3 mi. from site.

23 Intersection of SR 1127 and SR 1116.

ESE sector, 4.8 mi. from site.

Sweet Springs Church on SR 1116.

SE sector 4.0 mi. from site.

25 0.2 mi. W on SR 1402 from intersection of SR 1400 SSE sector, 4.7 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 27 NC 42 8 Buckhorn United Methodist Church SW sector, 4.8 mi. from site.

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

SSW sector, 4.8 mi. from site.

Parking lot of Neste Resins Corporation on SR 1916 sector 5.7 mi. from site. 'SW

~ ~ ~ ~

~ ~ 0 0 ~ 0

~ ~

~ 0 ~ ~

~ ~ ~ 0 ~ - - ~ ~

~ ~

~ 0 ~ ~

~ ~

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, Surface Water Sampling and Collection Frequency: Composite sample'ollected over a period of less than or equal to 31 days.

Analysis Frequency and Required Analysis: Monthly Gross Beta'nd Quarterly Gamma Isotopic Sample Point ZD No. Sample Point, Description', Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)'SW sector, 6.2 miles from site 40 NE Harnett Metro'ater 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. 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sam le: 'aterborne, Groundwater Sam ling and Collection Fre uency: Grab sample collected quarterl Analysis Frequency and Require'd Analysis: Each Sample Gamma Isotopic'nd Tritium Sample Point ID No. Sam le Point, Description', Distance, and Direction 39 On-site deep well in the vicinity of the diabase dike SSW sector, 0.7 mi. from site 57 SHNPP Site N. bank of Emergency Service Water (ESW) intake channel, S. of Water Treatment Building.

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

WSW sector, 0.5 mi. from site 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 Sam le: Waterborne, Drinking Water Sampling and Collection Frequency: Composite sample~ collected over a two-week period if I-131 analysis is performed; monthly composite otherwi se.

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. Sample Point, Description', Distance, and Direction 38 Cape Fear Steam Electric Plant Intake Structure (Control Station) sector, 6.2 miles from site

'SW 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C.

SSE sector, -17 mi. from site.

51 SHNPP Water Treatment Building On Site NOTE: 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.

TABLE 4.1 RADXOLOGlCAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway 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 ID 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 sector, 3.8 miles 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, Bottom Sediment Sampling and Collection Frequency: Bottom Sediment sample collected semiannually.

Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic'ample Point ZD No. Sam le Point, Description', 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 Exposure Pathway and/or Sample: Ingestion 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 I-131 Each Sample Gamma Xsotopic'ample Point ZD No. Sample Point, Description', 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 longer in business Stroud's Dairy, Pittsboro (Control Station)'W sector from site, > 12 mi. from site

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 TABLE 4. 1 RADlOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ex osure Pathway and/or Sam le: 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)'-12

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4. 1 RADIOLOGICAL ENVIRONNENTA'L'MONITORTNG PRDGMN Exposure Pathway and/or Sample: ingestion Food Products'ampling and Collection Frequency: Samples of 3 different kinds of broadleaf vegetation monthly during the growing season Analysis Frequency and Required Analysis: Each sample - Gamma Isotopic'n edible portion for each Sample Point ZD No. Sam le Point, Description', Distance, and Direction Pittsboro (Control Station)'NW sector, > 12 mi. from site SR 1189. Gunter-Morris Rd.

NNE sector, 1.7 mi. from site.

55 SR 1167, Bonsai NNW sector, 2.0 mi. from site 62 SR 1127, 0.4 m. W of SR 1134 NE sector, 2.3 mi. from site

'64 SR1127', 3/4 miles S of HEEC ENE S ector, 1. 8 miles from site 4-13

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: Aquatic Vegetation Sampling and Collection Frequency: Annually 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.

2. Particulate samples will be analyzed for gross beta radioactivity 24 hours or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.

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

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

Composite samples will be collected with equipment which is capable of collecting a'n aliquot at time intervals which are very short (e.g.,

every 2 hours) relative to the compositing period (e.g., monthly).

P

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 N

I I

I I.

O

'( I l /

I /

I I

/ //

2 Aatlccy Rcscnrctr 3 MinDam I

I

//

4-AootccyDom Bpitwsy I 5- Pfsnt 6 Ccotnff Tower Bfawcfown Uno O 2 Cocsnff yawcr 0- sto cuncfccy for Rcktoccsvw Ucfttd Eftucnts 9- 0 to Bancky fcr RaSaebe Pppccstmcto socfe Caucus Effvcnts 0 1 2 0 Siscufofof Arcs 8 - Boat Rcmp Ktoa el crc W- Wcko Canly Perk Hot 1 Mlcc

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-2 Environmental Radiological Sampling Points B>avm Us e4 Not to scale P.~".,'>>'. ~" '~'>>';8 <;w.....~,,:.' >> ~,.>q,'.3 " ~

>>g, < ' ',:'>> ".';~ ~ ~k..~ @...,,~., /<<',,d<

4-17

Shearon Har is Nuclear Power Plant (SHNPP) vune 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Figure 4.1-3 Environmental Radiological Sampling Points NORTH CAROLINA V

4-18

Shea "on Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Figure 4.1-4 Environmental Radiological Sampling Points NORTH CAROLINA 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 34 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 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 4.1-4 12 TL 4.1-4 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 DW 4.1-4 18 TL 4.1-4 SD 4.1-4 19 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 4.1-4 TL 4.1-2 32 TL 4.1-2 33 TL 4.1-3 'I

'C 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 STUDEES 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 are to be analyzed by the Harris Energy & Environmental Center (HE&EC) or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study.

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

Zf 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.

5-1

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 Requirement 3. 11.4 requires that the annual dose or dose commitment, to a member of the public from uranium fuel cycle sources be limited to 25 mrem for the whole body and any organ except the thyroid which is limited to 75 mrem. In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct 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 tritium provideequations The ODCM dose for noble gases, iodines, particulates, and conservative estimates because the X/Q and D/Q are historical values for the exclusion boundary distances. these distances are fixed and represents the closest points in Becausethe unrestricted areas to the doses to a member plant, it assures that 10 CFR 50 Appendix of the public are unlikely to be substantial.1y I 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.

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

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

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 oun ar 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 withxn the site boundary (Figure 4.1-4).

LADTAP ZZ 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.

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

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 indi. cating 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 & Liqht Company (CP&L) has performed the assessment of the transport and dxspersion of the effluent in the atmosphere as outlined in Pre aration of Radiolo ical Effluent Technical S ecifications or uc ear ower an s, 1978) .

e me o o ogy or xs assessment was based on guidelines presented in Regulatory Guide 1.111, Revision 1 (USNRCg 1977) The results of the assessment were to provide the relative depositions flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.

Regulatory Guide 1. 111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are (1) particle-in-cell model (a variable trajectory model based on the gradient-transport theory), (2) puff-advection model (a variable trajectory model based on the statistical approach to diffusion), and (3) the constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line method described in XOQDOQ Com uter Pro ram for the Meteorolo ical Evaluation of Routine Fluent e eases a uc ear ower a sons, 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-site meteorological program at the Shearon Harris Plant. These data consisted of all collected parameters from the normal 10.0 meter tower level for the years 1976-1987. The description of the model used and the computations are presented in NUREG/CRC-2919. The following tables provide the meteorological dilution factors (i.e., the X/Q and D/Q values) utilized to show compliance with ODCM Operational Requirements 3/4. 11.2 for noble gases and radioiodines and particulates.

Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for 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 for 1976-1987.

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

Shearon Harris Nuclear Power Plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 Sheet 3 of 3 APPENDjX 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 information for the standard distances, and special locations of interest with a terrain/recirculation factor. The input to "XOQDOQ" for ground level releases are presented in Table A-14. The resulting computations will have the TCFs applied to produce a final atmospheric diffusion estimate for the site.

Shearon Harr's Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Hanual (ODCM) Rev. 6 TABLE A-1 THROUGH A-4 X/Q and D/Q Ualues for Long Term Ground Level Releases at Special Locations XOQDOQ -- SHNPP GROUND-LEVEL HISTORICAL DATA( 1976.1987 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976.1987 CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POIN'IS OF INTEREST

~>~be~

X/Q x/a M~L x/a 0/a (sec/m3) (sec/m3) (sec/m3) (per m2)

RELEASE TYPE OF DIRECTION DISI'AHCE HO DECAY 2.3 d DECAY 8.0 d DECAY A SITE BOUNDARY S 1.36 2189. 6.1E-06 5.9E-06 .2E-06 8.8E-09 A Sll'E BOUNDARY SS'4 1.33 2140. 6.0E-06 5.8E-06 5. 1E.06 8.?E-09 A SITE BOUNDARY SW 1.33 2140. 5.5E 06 5.4E.06 4.7E.06 7.0E.09 A SITE BOUNDARY 'WSW 1.33 2140. 4.8E 06 4.7E-06 4.1E-06 5.4E-09 A SITE BOUNDARY 'W 1.33 2140. 3.6E 06 3.6E-06 3.1E-06 4.1E-09 A SITE BOUNDARY WNW 1.33 2140. 2.8E 06 2.7E-06 2.4E-06 3.3E-09 A SITE BOUNDARY HW 1.26 2028. 2.9E 06 2.8E-06 2.5E-06 3.9E-09 A SITE BOUNDARY HNW 1.26 2028. 3.3E.06 3.2E F 06 2.8E.06 5.1E-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. 4.1E 06 4.0E-06 3.5E-06 7.9E-09 A SITE BOUNDARY NE 1.33 2140. 3.2E.06 3.2E-06 2.7E-06 7.3E.09 A SITE BOUNDARY 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 'E-06 1.?E-06 3.8E-09 A SITE BOUNDARY ESE 1.33 2140. 1.8E 06 1.?E-06 1.5E-06 4.0E-09 A SITE BOUNDARY SE 1.33 2140. 2.1E 06 2.1E-06 1.8E-06 5.1E-09 A SITE BOUNDARY SSE 1.33 2140. 3.5E-06 3.4E-06 2.9E-06 6.2E-09 A NEAREST RESIDEHT SSW 3.90 6275. 7.8E-07 7.3E-07 5.9E-07 6.8E-10 A HEAREST RESIDENT SM 2.80 4506. 1.3E-06 1 'E-06 1.0E-06 1.28-09 A NEAREST RESIDENT WSW 4.30 6920. 5.4E-07 5.0E-07 4.0E-OT 3.4E-10 A NEAREST RESIDENT M 2.70 4345. 9.2E-07 8.8E-OT 7.3E-07 7.38-10 A NEAREST RESIDENT WNW 2.10 3380. 1.1E-06 1.1E-06 9.1E-OT 1.18-09 A NEAREST RFSIDEHT NM 1.80 2897. 1.4E-06 1.3E.06 1.1E-06 1.6E-09 A NEAREST RESIDENT NNW 1.50 2414. 2.2E-06 2.2E-06 1 'E-06 3.3E-09 A NEAREST RESIDENT N 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A NEAREST RESIDENT HHE 1.70 2736. 2.4E-06 2.4E-06 Z.DE-06 4.3E-09 A NEAREST RESIDENT HE 2.30 3701. 1.0E-06 1.0E-06 8.5E-O? 1.98-09 A NEAREST RESIDENT ENE 2.00 3219. 1.0E-06 1.0E 06 8.5E-OT 2.3E 09 A HEAREST RESIDENT E 1.90 3057. 9.3E-07 9.1E.07 7.7E-07 1.6E-09 A HEAREST RESIDENT ESE 2.70 4345 4.3E-07 4.1E.07 3.4E-07 7.3E-10 A HEAREST RESIDENT SE 4.70 '562.

1.9E-OT 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.?E-10 A GARDEN SSM 3.90 6276. 7.8E-07 7.3E-07 5.9E-07 "6.8E-10 A GARDEN SM 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 4 3.0Q 4828. 7.6E-O? 7.2E-07 6.0E-OT 5.7E-10 A GARDEN MNM 2.10 3380. 1.1E.06 1.1E-06 9.1E-07 1.1E-09 A GARDEN -HW 3.80 6116. 3.5E-07 3.3E-07 2.6E-07 2.8E-10 A GARDEH NN4 1.90 3058. 1.4E-06 1.4E-06 1.1E-06 1.8E-09 A GARDEN N 2.20 3540. 1.4E-06 1.3E-06 1.1E-06 1.9E-09 A GARDEH HHE 1.70 2736. 2.4E-06 2.4E-06 2.0E.06 4.3E-09 A GARDEN NE 2.30 3701. 1.0E-06 1.0E-06 8.5E-07 1.9E-09 A GARDEN E 4.70 7564. 1.8E-07 1.?E-07 1.3E-07 2.0E-10 A GARDEH ESE Z.'80 45Q6. 4 ~ OE-0? 3 9E-07 3.2E-OT 6.TE-10 A GARDEH SE 4.70 7562. 1.9E-07 1.8E-07 1.4E-07 2.6E-10 A COM HILK N 2.20 3540. 1 'E-06 1.3E-06 1.1E-06 1.9E-09 A CO4 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 8 POULTRY SW 2.80 4506. 1.3E-06 1.2E-06 1.0E-06 1.2E-09 A HEAT & POULTRY WSW 4.30 6920. 5.4E-07 5.0E-07 4.0E-07 3.4E.10 A HEAT & POULTRY W 3.10 4989. 7.2E-07 6.8E-07 5.6E-07 5.3E-10 A HEAT 8 POULTRY MNW 2.50 4023. 8.1E-07 7.7E-07 6.4E-07 7.2E-10 A HEAT 8, POULTRY NM 3.80 6116. 3.5E-07 3.3E-07 2.6E-07 2.8E-10 A HEAT & POULTRY HNW 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. ?.2E-06 2.1E-06 1.8E-06 3.8E.09 A MEAT 8 POULTRY HE 2.30 3701. 1.0E-06 1.0E-06 i8.5E-07 1.9E 09 A MEAT & POULTRY ENE 2.00 3219. 1.0E-06 1.0E-06 8.5E-07 ?.3E-09 A HEAT & POULTRY E 4.60 7403. 1.8E-07 1.7E.07 1.4E-07 2.1E 10 A MEAT & POULTRY ESE 4.40 7081 ~ 1.8E-OT 1.7E-07 ~

1.3E-07 2.4E-10 I

TABLE A-5 0 M W 8 lh lv Undepleted, No Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') N 0 (D

ax 0

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 N 8

HO DECAY, UNDEPLETED CORRECTED USIHG STANDARD OPEN TERRAIN FACTORS O ln I 'Z n c S

S AHHUAL AVERAGE 1.720E-04 CHI/O (SEC/HETER CUBED) 0 5.121E-05 2.531E-05 1.246E-OS DISTAHCE IH HILES FROH THE SITE 4.943E-06 2.814E-06 1.851E-06 1.330E-06 1.015E-06 8.077E-OT 6.637E-DT rr c n rt O

SS'M 1.571E-04 4.715E-05 2.346E-05 1. 15&E-05 4 .596E-06 2.60TE-06 1.711E-06 1.22TE-06 9.341E-07 7.424E.07 6.093E-07 r0 Q g

SM 1. 481E-04 4.412E-05 2.182E-05 1.074E-05 4.263E-06 2.428E-06 1.597E-06 1.14&E-06 8.757E-07 6.9T1E-07 5.72&E.07 MSM 1.295E-04 3.842E-05 1.893E-05 9.30&E-06 '3.693E-06 2.10&E-06 1.389E-06 9.995E-OT 7.632E-OT 6.080E-07 4.999E-07 0 9.839E-05 2.921E-05 1.440E-05 7.087E-06 2.814E-06 1.605E-06 1.057E-06 7.608E-07 5.80&E-07 4.626E-OT 3 '03E-07 Z 8 M 8 MNM 7.430E.05- 2. 216E-05 1.09&E-05 5.420E.06 2.154E 06 1.225E-06 8.053E-OT 5.784E-OT 4.409E-OT 3.508E-OT 2.881E-OT C

N'M HHM H

6.636E-05 7.179E-05 9.224E.05 1.996E-05 2.185E-05 2.824E-05 9.994E-06

1. 111E-05 1.448E-05 4.967E-06 5.570E-06 7.277E-06 1.982E-06 2.234E-06 2.919E-06 1.121E-06 1.254E.06 1.633E-06 7.339E-OT 8.166E-OT 1.060E-06 5.254E-07 5.820E-07 7.539E-07 3.995E-07 4.409E-07 5.701E-07 3.171E-07 3.489E.OT 4.505E-07 2.599E-07 2.853E-OT 3.67&E-07 rr HHE 9.847E-OS 3.034E.05 1.560E-05 7.846E-06 3. 145E-06 1.754E.06 1.137E-06 S.QTQE-OT 6.094E-07 4.810E-OT 3.923E-OT 0 ct NE 7.892E-OS 2.430E-05 1.240E-05 6.194E-06 2.467E-06 1.376E-06 8.91&E-07 6.333E-OT 4.7&4E-07 3.777E-OT 3.081E-07 a~

O ENE 5.998E-OS 1.S45E-05 9.3&BE-06 4.679E-06 1.860E-06 1.036E-06 6.711E-07 4.764E-07 3.597E-OT 2.839E-QT 2.316E-OT g, 0)

E 4.903E.05 1.498E-05 7.585E-06 3.779E.06 1.506E-06 8.439E-07 5.4&BE-07 3.90&E-07 2.959E-07 2.341E.07 1.913E.07 'z ESE 4.45&E-05 1.361E-05 6.872E-06 3.417E-06 1.359E-06 7.616E-07 4.952E-OT 3.527E-07 2.670E-07 2.112E-07 1.726E-OT

'U SE 5.351E-05 1.632E-05 8.255E-06 4.102E-06 1.629E-06 9.123E-07 5.929E-07 4.221E.07 3.195E-07 2.526E.07 2.064E.07 SSE 9.101E-05 2.734E-05 1.361E-05 .6.71&E-06 2.666E-06 1.509E-06 9.885E-OT 7.081E-07 5.387E-07 4.278E.07 3.509E-OT AHHUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES FROH THE SITE 0 0 0 S 5.589E 07 3.064E-OT 2.075E-07 1.263E-07 8.904E-OB 6.799E-OS 5.459E-OS 4.537E-OB 3.867E-OB 3.360E-OB 2.964E-OS SSM 5.126E-07 2.79&E-07 1.890E-07 1.147E-07 8.066E-OS 6.149E-OB 4.930E-OS 4.093E-OB 3.485E-OB 3.026E.OB 2.667E-OS SM 4.824E-07 2.6ISE-07 1.791E-07 1.090E-07 7.686E-OS 5.869E-OB 4.712E-OB 3.916E-OB 3.338E-OS 2.900E.OS 2.558E-OB MS'M 4.213E-07 2.315E-OT 1.570E-07 9.574E-OB 6.75&E-OB 5.165E-OS 4.150E-OS 3.451E-OB 2.943E-OB 2.558E-OS 2.257E-OS M 3.205E-07 1.760E-07 1.193E-07 7.275E-OS 5.133E-OS 3.922E-OB 3.151E-OB 2.620E-OB 2.234E-OB 1.941E-OS 1.713E-OS MNM 2.426E-07 1.328E-OT 8.985E-OB 5.463E-OB 3.849E 08 2.937E-OB 2.357E.OS 1.958E-OB 1.66&E-OS 1.449E-OB 1.27&E.OB N'M 2.185E-07 1.188E-07 8.005E-OB 4.839E-OS 3.396E-OB 2.584E-OS 2.069E-OB 1.716E-OB 1.460E-OB 1.266E-OS 1.115E-OS HN'M 2.392E-07 1.290E-OT 8.639E-OB 5.181E-OS 3.617E.OS 2.741E-OS 2.187E-OB 1.809E-OB 1.535E-OS 1.329E-OB 1.16&E-OS N 3.081E-07 1.654E-07 1.105E-OT 6.603E-OB 4.597E-OB 3.478E-OB 2.771E-OS 2.289E-OB 1.940E-OB 1.67&E-OB 1.474E-OB HNE 3.283E-07 1.T5&E-OT 1. 171E-07 6.980E-OB 4.852E-OB 3.665E-OB 2.91&E.OS 2.40&E-OS 2.040E-OB 1.763E-OS 1.548E-OB HE 2.5T9E-07 1.383E-OT 9.230E-08 5.512E-OS 3.839E-OB 2.904E-OB 2.315E-OB 1.912E-DB 1.622E-OB 1.403E-OS 1 '32E-08 EHE 1.93&E-07 1.039E-07 6.935E-OB 4.142E-OS 2.886E 08 2.184E-OB 1.741E-OS 1.439E-OB 1.220E-OB 1.056E-OB 9.27&E.09 E '1.604E-07 8.645E-OB 5.789E.OS 3.473E-OS 2.426E-OS 1.840E-OB 1.469E-OB 1.215E-OB 1.032E-OS 8.935E-09 7.85BE.09 ESE 1.447E-07 7.804E-OB 5.22&E-OB 3.139E-OB 2 '93E.OS 1.664E-OS 1 '29E-08 1.100E-OB 9.341E-09 8.091E-09 7.117E.09 SE 1.730E-OT 9.328E-OB 6.?4&E-OS 3.750E-OS 2.620E.OB 1.98&E-OS 1.58&E-OS 1.314E-OB 1.116E-OS 9.665E-09 8.501E-09 SSE 2.950E-OT 1.60&E-OT 1.0&SE-07 6.575E-OB 4.622E-OB 3.522E-OB 2.823E-OS 2.343E-OB 1.995E-OB 1.732E-OB 1.526E.OB c

Cl C

A 8

C

TABLE A-6 O Ill th O Undepleted, No Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') rrt e0 tn fu O

EXIT ONE -- GROUND-LEVEL HISTORICAL DATA) 1976-1987 am 0

NO DECAY, UNDEPLETED Ol ib CHI/O (SEC/HETER CUBED) O B SEGNENI'.8246-08 FOR EACH V 'g DIRECTION SEGMENT BOUNDARIES IN NILES FROM THE SITE 0

- 0 0 VV 2.535E-05 5.667E-06 1.900E-06 1.026E-06 6.676E-07 3.185E-07 1.278E-07 4.545E-OS 3.363E-OS 8 S rt P SSM 2.344E-OS 5.264E-06 1.756E-06 9.447E-07 6.129E-07 2.912E-07 1. 161E-07 6.172E-OS 4. 101E-08 3.029E-OB SM 2.185E-05 4.887E-06 1.639E-O& 8.855E-07 5. 761E-07 2.749E-07 1. 103E-07 5.891E-OB 3.923E-OS 2.903E-OB 0

'MS'M 1.899E-OS 4.236E-06 1.425E-06 7.715E-07 5.0286-07 2.405E-07 9.683E-OB 5.1846-08 3.457E-OB 2.560E-OB 0 M 1.444E-05 3.226E-06 1.085E.06 5.872E.07 3.826E-07 1.829E-OT 7.358E-OS 3.9376-08 2.624E-OB 1.943E-OB Z8 MNM 1.099E-OS 2.46TE-O& 8.265E-OT 4.459E-OT 2.8986-07 1-381E-OT 5.528E-OB 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-OB 2.595E-OB 1.719E-OB 1.267E-OB Ql NHM 1.103E-OS 2.540E-O& 8.395E-07 4.462E-07 2.8716-07 1.345E-07 5 '54E-08 2.753E-OB 1.813E-OS 1.330E-OS 3 '94E-08 Dp N 1.434E.OS 3.316E-06 1.090E-06 5.771E-07 3.7026-07 1.727E-07 6.700E-OB 2.294E-OS 1.680E-OS NHE 1.543E-OS 3.572E-06 1.169E-06 6.169E.OT 3.949E-07 1.836E-07 7.086E-OS 3.682E-OB 2.413E-OS 1.765E-OS 0 rt U

NE 1.229E-OS 2.811E-06 9.176E-OT 4.843E-OT 3.1026-0T 1 4456-07 5.595E-OB 2.918E-OB 1.917E-OB 1.404E-OB O~Ul ENE 9.309E.06 2.120E-06 6.906E-07 3.642E-07 2.331E-OT 1.085E-07 4.204E-OB 2.194E-OB 1.442E-OB 1.057E-OB g E 7.536E-06 1.717E-O& 5.6436-07 2.995E-07 1.925E-07 9.019E-DS 3.523E-OS 1.848E-OB 1.218E-OS 8.946E-09 'z ESE 6.833E-06 1.551E-06 5:092E-07 2.702E-OT 1.737E-07 8.141E-OS 3.183E-OB 1.671E-OS 1-102E-08 8.101E-09 SE 8.202E-06 1.860E-06 6.097E.07 3.233E-OT 2.078E-07 9.732E-OS 3.803E-OB 1.996E-OB 1.317E-OB 9.676E-09 SSE 1.360E-OS 3.052E.06 1.015E.06 5.449E-07 3-5306-07 1.6T4E-OT &.657E-08 3.5366.08 2.3486-08 1.733E-OB

0 TABLE A-7 Q Vl th S Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') V rt 0 S

EXIT QHE -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 tI 0

X 2.300 DAY DECAY> UNDEPLETED th O

CORRECTED USING STANDARD OPEN TERRAIH FACTORS rI t/I ANNUAL AVERAGE CHI/O (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE 00 rZ n c c n S 1.712E-OC 5.0/BE 05 2.500E-05 1.226E-05 4.824E-06 2.723E-06 1.776E-06 1.266E-06 9.571E.07 7.553E-Q? 6.153E-07

1. 564E-04 4.675E-05 2.318E-05 1. 139E-05 4.489E-Q6 2.525E-06 1.643E-06 1. 168E-06 8.820E-07 6.951E-O? 5.657E-07 0 SSM rt 0 SW 1 ~ 474E-04 4.374E.05 2.154E-05 1.056E-OS 4.158E-06 2.34?E-06 1. 531E-06 1 ~ 091E-06 &.24'?E OT 6.508E-OT 5.301E-07 MSM 1.289E-04 3.808E-05 1.869E-05 9.149E-06 3.600E-06 2 '36E-06 1.330E-06 9.484E-07 7.1?TE-07 5.66?E-07 4.619E-OT 0

'M 9.79!E-05 2.895E-05 1.422E-05 6.966E-06 2.743E-06 1.551E-06 1.013E-06 7.221E-07 5'.464E-07 4.314E-07 3.515E-07 0 MN'M 7.398E-05 2.19?E.05 1.085E-05 5.331E-06 2.102E-06 1. 185E-06 7.723E-07 5.499E-07 4.156E-07 3.2?SE-07 2.669E-07 Z 0Z DP HM 6.609E-OS 1.980E.05 9.879E-06 4.892E-06 1.938E-06 1.08TE-06 7.060E-07 5.014E-OT 3.782E-07 2.978E-07 2.421E-07 HHW NNE H

7.152E-05

9. 191E.05 9.814E-05 2.170E.05 2.805E-05 3.014E-05 1.099E-05 1.434E-OS 1.546E-05 5.495E-06 7.184E-06 7.751E-06 2 '89E-06 2.864E-06 3.08SE-06 1 '20E-06 1.591E-06 1.712E-06

?.SBTE-O?

1.026E-06 1.102E.06 5.581E-QT 7.247E-07 7.7?OE-D?

4.19?E-OT 5.442E-07 5.829E-07 3.29TE-07 4.270E-O?

4.5?OE-07 2.676E-OT 3.463E-OT 3.703E-07 rr NE ?.865E.05 2.414E-05 1.228E-05 6.117E-06 2.422E-06 1.342E-06 8.635E-07 6.091E-07 4.569E-07 3.582E-O? 2.902E-OT Q ~

EHE 5.9?BE.05 1.833E 05 9.300E-06 4.621E-06 1.825E-06 1.011E-06 6.499E-07 4.582E-07 3.436E-OT 2.693E-07 2.182E-07 tI n-E 4.8&SE-05 1.487E-05 7.507E-06 3.729E-06 1.476E-06 8.212E-OT 5.301E-O? 3.748E-OT 2.81TE-07 2.212E-07 1.794E-07 'X M ESE 4.441E-05 1.351E 05 6. 801E-06 3.372E-06 1.332E-06 7.411E-OT 4.783E-07 3.382E-OT 2.541E-OT 1.996E-OT 1.619E-07 ztg SE 5.331E.05 1.621E-05 8.172E-06 4.04?E-06 1.597E-06 8.879E-07 5.728E-07 4.0CBE-O? 3.042E-07 2.388E-07 1.937E-07 '0 SSE 9.063E-05 2.712E-05 1.3CSE-05 6.616E-06 2.606E-06 1.463E-06 9.505E-07 6.753E-O? 5.095E-07 4.014E-07 3.265E-O?

ANNUAL AVERAGE CHI/O (SEC/METER CUBED) DISTANCE IH MILES FROM THE SITE 0 0 S 5.138E.07 2.700E.07 1.755E-07 9.871E-OS 6.459E-OB 4.597E-OB 3.454E-OB 2.697E-OS 2.167E-OB 1.781E-OS 1.490E-OB SSM 4.719E-O? 2.4?2E.O? 1.603E-07 8.990E-OB 5.871E-OB 4.172E-QS 3.131E-OB 2.442E-OB 1.960E-OB 1.609E-OB 1.345E-OS SW 4.426E-07 2.324E-OT 1.509E-O? 8 4?2E-08 5.532E-OB 3.929E-OS 2.946E-OB 2.296E-OS 1.841E-OS 1.510E-OS 1.261E-OB MS'W 3.858E-07 2.029E.07 1.318E-07 7.405E-OS 4.835E-OS 3.433E-QS 2.5?4E-QB 2.005E-OB 1.607E-QB 1.31?E-QB 1.100E-OB W 2.936E.07 1.544E-O? 1.003E-07 5.633E-OB 3.678E-OS 2.612E-OB 1.958E-OS 1.525E-OS 1.223E-OB 1.003E-QB 8.3TOE-09 MNM 2.228E-07 1.169E-07 7.589E-OB 4.259E-OS 2.782E-QB 1.976E-OB 1.482E-OB 1. 155E-08 9.26?E-09 7.602E-09 6.350E-09 HM 2.019E-07 1.055E-OT 6.83?E-OS 3.834E-OS 2.505E-OS 1.782E-OS 1.339E-OB 1.045E-OB 8.394E-09 6.896E-09 5.768E-09 NHM 2.22&E-Q? 1.159E-07 7.490E-OB 4.194E-OS 2.742E-OB 1.953E-OS 1.4?QE-OB 1.150E-OB 9.252E-09 7.614E-09 6.37BE.09 H 2.880E-07 1.495E.07 9.650E-OS 5.401E-OS 3.534E-OB 2.520E-O& 1.898E-OS 1.486E-OS 1. 198E-08 9.868E-09 8.276E-09 NNE 3.078E.07 1.594E 07 1.028E-07 5.753E-QS 3.766E-QB 2.687E-OS 2.026E-OB 1.588E-OB 1.281E-QB 1.05?E-OB 8.872E-09 NE 2.413E-07 1.250E-OT 8.065E-OB 4.512E-OB 2.953E-OS 2.106E-OB 1.588E-DB 1.244E-OS 1.003E-OS 8.276E-09 6.949E-09 ENE 1.81IE-07 9.395E 08 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-OT 7.?61E 08 5.014E-OS 2.807E-QB 1.836E-OB 1.30BE-OS 9.847E-09 7.705E-09 6.205E.09 5 '10E-09 4.284E-09 ESE 1.347E-07 7.005E 08 4.527E-OB 2.535E-QB 1.659E-OS 1.183E-OS 8.908E-09 6.9?CE-09 5.619E 09 4.630E-09 3.884E-09 SE 1.612E.07" 8.378E-OS 5.414E-OB 3.033E-OS 1.985E-OB 1.416E-OS 1.067E-OB 8.353E-09 6.732E.09 5.549E-09 4.65?E-09 SSE 2.723E-07 1.425E.07 9.243E-OB 5.189E-OB 3.394E-OB 2.416E-OS 1.816E-OB 1.419E-OB 1.140E-QB 9.3?SE-09 ?.851E-Q9 C

Cl C

O Ch (P

TABLE A-8 O N th K W 8 Ql Undepleted, 2.26 Day Decay, X/Q Values for Long Term Ground Level Releases at Standard Distances (sec/m') n 0 0

EXIT -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 UK ONE 0 2.300 DAY DECAY, UNDEPLETED S

CHI/O (SEC/HETER CUBED) FOR EACH SEGMENT r.

0 4 DIRECT ION SEGHENT BOUNDARIES IN HILES FROH THE SITE M 4 c

n c n S 2.5066.05 5.542E-06 1 '25E-06 9.683E-D? 6.192E-07 2.822E-07 1.0066-07 4.636E-OB 2.711E-OB 1.78?E-OB r I O

SS'N 2.318E-05 5.151E-06 1.688E-06 8.926E-07 5.693E-07 2.585E-07 9.1686-08 4.209E-OB 2.455E-OB 1.615E-OS SII 2.159E-05 4.776E-06 1.572E-06 8.345E-O? 5.334E-07 2.429E-07 8.636E-OS 3.964E-OB 2.309E-OB 1.516E-OB r' Q IISII 1.876E-05 4.138E-06 1.366E-06 7.261E-O? 4.647E-O? 2. 119E-07 ?.54?E-08 3.463E-OB 2.016E-OB 3236-08 0 1 '0 1 '27E 05 3.152E-06 1.040E-06 5.528E-07 3.537E-07 1.613E-07 5.7416-08 2.635E-OB 1.534E-OB 1.006E-OB 0 IDI'N 1.087E-05 2.412E-06 7.934E-07 4.205E-07 2.686E-07 1.222E-07 4.343E-OS 1.994E.OB 1.162E-OB 7.632E-09 XZ 0

NM 9.867E-06 2.216E-06 7.259E-07 3.827E-07 2.437E-07 1.104E-07 3.9116-08 1.798E-OB 1.051E-OB 6.922E-09 NHM 1.093E-05 2.493E-06 8.116E-07 4.250E-07 2.694E-07 1. 214E-07 4.281E-OB 1.970E-OB 1. 156E-08 7.641E-09 H 1.421E.05- 3.258E-06 1.056E-06 5. 511E-07 3.486E-07 1.5676-07 5.515E-OB 2.541E-OS 1.49CE-OB 9.903E-09 r I HNE 1.530E-05 3.513E-06 1. 134 E-06 5.904E-07 3.728E-07 1.672E-07 5.87?E-OB 2.710E-OB 1.596E-OB 1.060E.OB QP HE 1.218E-05 2.763E-06 8.893E-07 4.628E-07 2.923E-07 1.311E-O? 4.608E-OB 2.125E-OS 1.251E-OB 8.305E-09 on U

EHE 9.22?E-06 2.084E-06 6.694E-07 3.480E-O? 2.19?E-07 9.855E-OB 3.464E-OB 1.598E-OB 9.418E-09 6.261E-09 O E 7.464E-06 1.6856-06 5.456E-O? 2.852E-O? 1.806E-07 8.134E-OB 2.866E-OB 1.319E-OB 7.746E-09 5.129E-09 3,'N ESE 6.768E-06 1.523E.06 4.923E-O? 2.574E-D? 1.630E-07 7.3C1E-OB 2.588E-OB 1. 193 E-08 7.010E-09 4.647E-09 z, SE 8.124E-06 1.8266-06 5;897E-07 3.080E-07 1.950E-07 8.781E-OB 3.096E-OB 1.428E-OB 8.396E-09 5.569E-09 SSE 1.345E-OS 2.989E-06 9.771E-07 5.157E-07 3.286E-07 1.491E-07 5.292E-OB 2.437E-OB 1.426E-OS 9.413E-09

TABLE A-9 Depleted, 8.0 Day Decay, X/9 Values for Long Term Ground Level Releases at Standard Distances (sec/m')

EXIT ONE -. GROUND-LEVEL HISTORICAL DATA, 1976-1987 ax 0

8.000 DAY DECAY, DEPLETED N CORRECTED USING STANDARD QPEH TERRAIN FACTORS (D

I.

O 4 ANNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IH HILES FRQH THE SITE rz 0 C 1.625E-04 4.665E-QS 2.24TE-OS 1.085E-05 4 '69E-06 2.30&E-06 1.482E.06 '42E-06 c n S 1 7.784E-O? 6.OBOE-07 4.90&E-07 1.485E-04 4.295E-OS 2.083E-05 1.009E-05 3.877E-06 ,2.139E-06 1.369E-06 9.606E-07 7.16&E-07 5.590E-O? 4.50?E-07 0 SSM tt Q S'M 1.4QQE-04 4.019E-OS 1.937E-OS 9.357E-06 3.594E-O& 1.991E-06 1.27&E-06 8.984E-O? 6.715E-07 5.244E-07 4.233E-07

'MSM 1.224E-04 3.499E-OS 1.681E-OS 8.107E.06 3.113E-06 1.72&E-06 1.111E-06 7.81&E-OT 5.849E-07 4.572E-OT 3.693E-07 0 M 9.300E-OS 2.660E-OS 1.279E-OS 6. 173E. 06 2.372E-06 1. 316E-06 8.45&E.07 5.952E-07 4.452E-O? 3.479E-O? 2.810E-O? 0 MNM 7.023E-OS 2.01&E-OS 9.753E-06 4 '21E-06 1.816E-06 1.005E-06 6.444E-Q? 4.52?E-OT 3.382E-OT 2.640E-07 2.130E-OT O HM 6.273E-DS 1.819E-OS 8.876E-06 4.329E-06 1.672E-06 9.202E-07 5.878E-07 4.117E-O? 3.068E-07 2.390E.OT 1.925E-07 6.787E-OS 1.991E-OS 9.8TIE-06 4.85?E-06 1.&S6E-O& 1.030E-Q& 6.548E-OT 4.56TE-OT 3.391E-07 2.635E-07 2.117E-O? G NNM N 8.721E-OS 2.574E-OS 1.287E-OS 6.346E-06 2.465E-06 1.342E.06 8.505E-O? 5.920E-07 4.3&9E-OT 3.404E-07 2.732E-07 HHE 9.311E.OS 2.765E-OS 1.38?E-OS 6.844E-06 2.657E-06 1.442E-06 9.123E-07 6.339E-07 4.694E-07 3.637E-07 2.916E-07 NE 7.462E-OS 2.215E-OS 1.102E-OS 5.403E-06 2.0S4E-06 1 ~ 131E-06 7.156E-07 4.974E-O? 3.683E-07 2.855E.O? 2.289E-07 0 rt EHE 5.671E.05 '1.682E-05 8.343E.06 4.081E-O& 1.571E.06 '.519E-07 5.3&SE.07 3.741E-07 2.770E-07 2. 146E-07 1.721E-07 U E 4.635E-OS 1.365E-OS 6.739E-06 3.295E-06 1.271E-06 6.933E-07 4.401E-07 3.067E-OT 2.276E-O? 1.767E-07 1.419E-Q7 g M ESE 4.214E-OS 1.240E-05 6.105E-06 2.980E-06 1. 14?E-06 6.256E-O? '3.971E-07 2.76?E-O? 2.054E-D? 1.595E-O? 1.281E-07 z SE 5.058E-OS 1.487E-OS 7;335E-06 3.576E-06 1.376E-06 7.495E-OT 4.755E-07 3.312E-OT 2.45?E-O/ 1.90&E-07 1.532E-OT SSE 8.603E-OS 2.491E-OS 1.209E-OS 5.855E-06 2.249E-06 1.23&E-06 7.917E-07 5.547E-07 4.136E-07 3.223E-07 2 '9?E-07 AHNUAL AVERAGE CHI/O (SEC/HETER CUBED) DISTANCE IN HILES FRDH THE SITE 00 S 4.064E-07 2.0&DE-07 1.325E-O? 7.2&DE-QB 4.700E-O& 3.317E-OS 2.477E 08 1.924E-OS 1.538E-OB 1.257E-OS 1.045E-OB SSM 3.729E-07 1.901E-07 1.208E-OT 6.616E-O& 4.263E-OB 3.004E-OB 2.240E.O& 1.738E-OB 1.388E-OS 1 '34E.OS 9.424E-09 SM 3.506E-O? 1.794E-07 1.143E-OT 6.274E-QB 4.049E-OS 2.&56E-OB 2.131E-OB 1.654E-OB 1.322E-O& 1.079E-OS 8.973E-09 MSM 3.060E-07 1.569E-07 1.001E-07 5.502E-OB 3.554E-OB 2.508E.OB 1.872E.OB 1.453E-O& 1.1&1E-O& 9.487E-09 T.BBTE-09 M 2.328E-07 1.193E-07 7.609E-OB 4.182E-OB 2.701E-OS 1.906E-OS 1.422E-OB 1.104E-OS 8.823E-09 7.207E-09 5.991E-09 MNM 1.'764E-OT 9.014E-OS 5.738E-OS 3.14?E-0& 2.030E-QB 1.431E.O& 1.068E.QB 8.289E-09 6.622E-09 5.409E-09 4.496E-09 NM 1.591E-07 8.086E-OS 5.129E-OS 2.801E-OS 1.803E-OB 1 '69E-08 9.462E.09 7.339E-09 5.861E-09 4.787E-09 3.979E-09 NNM 1.746E.OT 8.&OBE-QB 5.560E-QB 3.019E-QB 1.936E-OB 1.36QE-OB 1.013E-OS 7.84&E-D9 6.264E.09 5 ~ 115E-09 4.251E-09 N 2.251E.O? 1.132E-O? 7.12?E-OS 3.859E-OB 2 '71E-08 1.735E-OS 1.291E-OB 1.000E-OS 7.981E-09 6.516E-09 5.417E-09 HNE 2.401E-07 1.204E-07 7.567E-OB 4.089E-OB 2.616E-OB 1.835E-OB 1.365E-QB 1.057E-OB 8.437E-09 6.&ME 09 5.726E-09 NE 1.&BSE-07 9.461E-OB 5.954E-OS 3.222E-OB 2.063E-OS 1 '49E-08 1-078E 08 8.353E-09 6.66&E-09 5.445E-09 4.52?E-09 ENE 1.417E-07 7.109E-O& 4.473E-OB 2.421E-OB 1.551E-OB 1.089E-OB 8.109E-09 6.2&SE-09 5.01&E-09 4.099E-09 3 409E-09 E 1. 171E-07 5.902E-OB 3.724E-OB 2.023E-OB 1.298E-OS 9.120E-09 6.791E 09 5.264E-09 4.203E-09 3.432E-09 2.853E-09 ESE 1.056E-O? 5.327E-OS 3.363E.OB 1.827E-OS 1 ~ 173E-08 8.246E-09 6.143E.09 4.763E-09 3.803E-09 3 '07E-09 2.583E-09 SE 1.263E-Q? 6.369E-OB 4.02QE-QS 2.1&4E-O& 1.402E-QB 9.856E-09 T.343E.09 5.694E-09 4.547E-09 3.714E-09 3.089E-09 SSE 2.14&E-O? 1.094E-07 6.946E-OB 3.801E-QS 2.449E-OS 1.726E-OB 1.288E 08 9.994E-09 7.9&SE.09 6.524E 09 5.425E.09 G

AA O

LO

4 TABLE A-10 o tn

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

EXIT -- GROUND-LEVEL HISTORICAL DATA, 1976-1987 tI X OHE 0 8.000 DAY DECAY, DEPLETED ill N

CHI/O (SEC/HETER CUBED) FOR EACH SEGNENT I O 4 DIRECTION SEGHENT BOUNDARIES IH HILES FRON THE SITE V 'Z 0 C S 2.26BE-05 4.827E-06 1.526E-06 7.887E-07 4.943E-OT 2.186E-O7 7.461E-OB 3.350E.OB 1.935E-OB 1.262E-OS c 0 VI SSM 2.097E-05 4.485E-06 1.411E-06 7.263E-OT 4.540E-OT 1.999E-07 6.785E-OS 3.034E-QB 1.'748E-08 1.138E-OS Gl SM 1.955E-05 4.162E-06 1.316E-06 6.803E-07 4.264E.07 1.885E-07 6.430E-OS 2.884E.OS 1.664E-OS 1.084E-OS V'

'MSM 1.69SE-05 3-607E-06 1.144E-06 5.925E-OT 3.719E 07 1.648E-OT 5.637E-OS 2.532E.OS 1.462E-OB 9.524E-09 0 M 1.292E-05 2.747E.06 8.710E-07 4.510E-07 2.830E-07 1.253E-07 4.285E-OS 1.924E 08 1 111E-08 T.236E-09 0 MHM 9.835E-06 2. 101E. 06 6.638E-OT 3.426E-OT 2 '45E-07 9.474E-OS 3.226E-OB 1.446E-OB 8.338E-09 5.430E-09 Z Z NM 8.924E-06 1.928E-O& 6.0&DE-OT 3.109E-OT 1.939E-OT 8.510E-OS 2.875E-OB 1.282E-OB 7.383E-09 4.806E-09 NNII 9.874E-06 2.166E 06 6.757E-07 3.439E-07 2.133E-07 9.287E-OB 3.102E-OB 1-375E-08 7.896E-09 5.136E-09 P N 1.283E-05 2.828E-O& 8.782E.07 4.451E-07 2.753E-07 1. 194E-07 3.969E-OS 1.754E-OB 1.006E-OB 6.543E-09 HHE 1.381E-05 3.048E-06 9.423E-07 4.761E-07 2.939E-OT 1-2T1E-07 4.207E-OB 1.855E.OB 1.064E-OB 6.917E-09 NE 1.100E-05 2.398E-06 7.392E.OT 3.736E-07 2.307E.OT 9.990E-OB 3.314E-OB 1.464E-OS 8.404E-09 5.467E-09 0 rt U

ENE 8.332E-06 1.809E-06 5.563E-07 2.810E-07 1.734E.07 7.506E-OB 2.491E-OS 1.101E-OB 6.323E-09 4.115E-09 O~

'g CA E 6.744E-06 1.464E-06 4:542E.07 2.308E-OT 1.430E-OT 6.224E-OB 2.079E-OB 9.217E 09 5.296E-09 3.446E-09 ESE 6.115E-06 1.323E-06 4.099E-07 2.083E-07 1.291E-07 5.618E-OS 1.878E-OS 8.333E.09 4. 791E-09 3.119E-09 R SE 7.340E-06 1.586E-06 4.908E-07 2.492E-07 1.544E-07 6.717E-OB 2.244E-OS 9.960E-09 5.728E-09 3.730E.09 SSE 1.217E-05 2.601E-06 8.160E-07 4.191E.07 2.616E.07 1.151E-OT 3.899E-OB 1.743E.QB 1.005E-OB 6.550E-09 o

TABLE A-11 O M th D W 0 N

Deposition Values (D/Q) for Long Term Releases at Standard Distances (m ') r. e N 0 0

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

CORRECTED USING STANDARD OPEN TERRAIN FACTORS Q 8

'***"********'**'***'**'*'*** RELATIVE DEPOSITION PER UNIT AREA (H**-2) At FIXED POINtS BY DDMNMIND SECTORS *%*4****%*1***114k**%**i%*** 0 N rn c D I RECT IDH DISTAHCES IH HILES e n 0

2.3246-07 7.85?E-OB 4.034E-OB 6.889E-09 3.417E-09 2.012E-09 1.317E-09 lD S 1.918E-OB 9.269E-10 6. 869E. 10 5.294E-10 SSM 2.17'IE.07 7.343E-OS 3.770E-OB 1.792E-OS 6.438E-09 3.193E.09 1.880E-09 1.231E-09 8.662E-10 6.420E-10 4.947E-10 SM 1.740E.O? 5.885E-OS 3.022E-OB 1.43?E-OB 5.1606-09 2.559E-09 1.5D?E-09 9.866E-10 6.942E-10 5.145E-10 3.965E-10 0 MSM 1.355E-07 4.582E-OB 2.353E-OB 1. 119E-08 4. 018E-09 1.993E-09 1. 173E-09 7.682E-10 5 406E-10 4.006E-10 3.087E-10 0 M 1-OTSE 07 3.427E-OB 1.?59E-08 8.365E-09 3.005E-09 ~ 1.490E-09 8.7746-10 5.745E-10 4.042E-10 2.9966.10 2.309E-10 Z 0Z MNM 8.296E-OS 2.805E-DB 1.440E-OS 6.848E-09 2.460E-09 1.220E-09 7.183E-10 4.703E-10 3.309E-10 2.453E-10 1.890E-10 HM 8.468E F 08 2.864E.OB 1.470E-OS 6.990E-09 2.511E-09 1.245E-09 7.332E-10 4.801E-10 3.3?SE-10 2.503E.10 1.929E-10 C P

NHM 1.105E.07 3.736E-OB 1.918E-OB 9. 120E-09 3.276E-09 1.625E-09 9.566E-10 6.264E-10 4.408E-10 3.266E.10 2.517E-10 I I H 1.626E-07 5.499E-OB 2-823E-08 1.342E-DB 4.821E-09 2.391E-09 1.408E-09 9.218E-10 6.487E-10 4.807E-10 3.705E-10 NNE 1.985E-07 6.713E-OB 3.447E-OS 1.639E-DB 5.886E.09 2.919E-09 1.719E-09 1.125E-09 7.919E-10 5.869E-10 4.522E-10 o rt HE 1.815E-O? 6.137E-OS 3.151E-OS 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

ENE 1.568E 07 5.302E-OB 2.723E-OS 1.294E-OB 4.649E-09 2.306E-09 1.358E-09 8.890E-10 6.255E-10 4.636E-10 3. 572E-10 g 0)

E 9.595E-OB 3.245E-OB 1.666E-OB 7.920E-09 2.8456-09 1.411E-09 8.30?E-10 5.439E-10 3.82?E-10 2.837E.10 2.186E-10 'z ESE 1.003E-O? 3.393E-OB 1:?42E-08 8.281E-09 2.9?5E-09 1.475E-09 8.686E-10 5.688E-10 4.002E-10 2.966E-10 2.286E-10 '0 SE 1.270E-07 4.294E-OS 2.205E-OS 1.048E-O& 3.765E 09 1.867E-09 1.099E-09 7.199E-10 5.066E-10 3.754E-10 2.893E-10 SSE 1.548E.07 5.236E-OB 2.688E-OB 1.2?BE-08 4.5916-09 Z.Z??6-09 1.341E-09 8.7?SE.10 6.177E.10 4.5?BE-10 3.528E-10 0 I RECT'DH DISTAHCES IN HILES S 4.205E-10 1.868E-10 1.132E-10 5.720E-11 3.462E-11 2.321E-11 1.663E-11 1.249E-11 9.711E-12 7.757E.12 6.332E-12 SS'M 3.930E-10 1-746E-10 1.058E-10 5.346E-11 3.235E-11 2. 169E-11 1.554E-11 1 ~ 16?E-11 9.075E-12 7.249E-12 5.917E-12 SM 3. 150E-10 1.399E-10 8.476E-11 4.284E-1'1 2.593E-11 1.739E-11 1.246E-11 9.354E-12 7.273E-12 5.810E.12 4.742E-12 MS'M 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 5.44?E-12 4.235E-12 3.383E.12 2.761E-12 MNM 1.501E-10 6.6?OE-11 4.040E-11 2.042E-11 1.2366-11 8.287E-12 5.938E-12 4.459E-12 3.467E-12 2.769E-12 2.261E-12 HM 1.533E-10 6.BOSE-11 4.124E-11 2.085E-11 1.262E-11 8.459E-12 6.062E-1Z 4.552E-12 3.539E-12 2.82?E.12 2.30?E-12 HH'M 2.000E-10 8.884E-11 5.381E-11 2.720E-11 1.646E-11 1.104E-11 7.909E-12 5.939E-12 4.618E-12 3.689E-12 3.011E-12 N 2.943E-10 1.307E-10 7.920E-11 4.003E-11 2.423E-11 1.624E-11 1 ~ 164E-11 8.740E-12 6.796E-12 5.428E.12 4.431E-12 HHE 3.593E-10 1 '96E-10 9.668E-11 4.887E-11 2.9586-11 1.983E-11 1.421E-11 1.067E-11 8.296E-12 6.627E.12 5.409E-12 NE 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 '35E-12 4.273E-12 E 1. 737E-10 7.714E-11 4.673E-11 2.362E-11 1.430E-11 9.585E-12 6.868E-12 5. 15?E-12 4.010E-12 3.203E 12 2.614E-12 ESE 1. 816E-10 8.066E-11 4.886E-11 2.4?06-11 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 1.8926-11 1.269E-11 9.090E-12 6.826E-12 5.30?E-12 4.240E.12 3.460E-12 SSE 2.802E-10 1.245E-10 7.541E. 11 3.812E-11 2.3076-1'I 1.54?E-11 1.108E-11 8.323E-12 6.471E-12 5.169E-12 4.219E-12 C

0

& Ch

TABLE A-12 o Ul

& QI0 B

Deposition Values (D/Q) for Long Term Releases at Standard Distances (m ') V rt 0 0

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

8 r.

44*4%****4***kkf**i1*01tltkkAAAA*k RELATIVE DEPOSITIOH PER UHIT AREA OI**-2) BY **~ **********~***~

0 th DIRECT IOH SEGHEHT BOUNDARIES IH HILES DOMNMIND SECTORS PRON THE SITE rz S

SS'M 3.943E-OS 3.685E-08 8.077E-09 7.548E-09 2.109E-09 1.Q71E-09 9.470E-10 8.850E 10 5.357E-10 5.007E-10 2.060E-10 1.Q25E-10 5.960E-11 5.570E-11 2.362E-11 2.208E-1'I 1.261E-11 1.179E-11 0-7.808E-12 7.2976-12 rr n c c n Ql 0 lV SM 2.953E.OS 6.050E-09 1.579E-09 7.093E-10 4.013E-10 1.543E-10 4.464E-11 1.769E-11 9.448E-12 5.8486-12 MS'M 2.300E-08 4.7106-09 1.230E-09 '.5236 10 3.124E-10 'I.201E-10 3.476E-11 '1.378E-11 7.357E-12 4.554E-12 0 M 1.72OE-08 3.523E-09 9. 196E-10 4 ~ 130E-10 2.337E-'IO 8.985E-11 2.599E-11 1.030E-11 5.502E-12 3 '056-12 0 MH'M 1.408E 08 2.884E-09 7.528E-10 3.381E-10 1.913E-10 7.356E-11 2 '28E-11 8.434E-12 4.504E-12 2.7886-12 Z 08 HM 1.437E.08 2.944E-09 7.685E-'IO 3.451E-10 1.952E-10 7.508E-11 2.172E-11 8.609E-12 4.5Q7E-12 2.846E-12 NH'M 1.875E 08 3.841E.09 1.0036-09 4.503E-10 2.548E-10 9.797E-11 2.834E-11 1.123E-11 5.998E-12 3.713E-12 N 2.760E.08 5.652E-09 1.4766-09 6.627E-10 3.749E-10 1.442E.10 4 ~ 171E-11 1.653E-11 8.828E-12 5.464E-'12 HNE 3.369E-OS 6.901E-09 1.801E.09 8.091E.10 4.577E-10 1.760E-10 5.092E-11 2.018E-1'I 1.078E-11 6.671E-12 HE 3.080E-OS 6.309E-09 1.647E-09 7.397E-10 4.185E-10 1.609E-10 4.655E-11 1.845E-11 9.853E-12 6.099E-12 0 tI rt EHE 2.661E-08 5.451E-09 1.423E-09 6.391E-10 3.615E-10 1 3906-10 4.022E-11 1.594E-11 8.513E-12 5.269E-12 O~0)

E 1.628E.08 3.335E-09 8.707E-10 3.911E-10 2. 212E-10 8.507E-11 2.461E-11 9.754E-12 5.209E-12 3 ~ 224E-12 g ESE 1.703E-08 3.4876-09 9.104E-10 4.089E-10 2.313E-10 8.895E-11 2.573E-11 1.020E-11 5.447E-12 3.3716-12 SE 2.155E.OS 4.414E-09 1;152E-09 5 ~ 176E-10 2.928E-10 1.126E-10 3.257E-11 1.291E-11 6.894E-12 4 ~ 267E-12 d SSE 2.628E.08 5.383E-09 1.405E-09 6.311E-10 3.570E-10 1.373E-10 3.972E-11 1.574E-11 8.406E-12 5 ~ 203E-12 P

lD V

~ lP Ol CP

TABLE A-13 0 U)

W 5 Joint Hind Frequency Distribution by Pasquill Stability Classes at SHNPP rrt e0 tA 8

-- SHHPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 DÃ XOODOO 0 JOINT FREQUENCY DISTRIBUTION OF MIND SPEED AHD DIRECTION 1h O

ATHOSPHERIC STABILITY CLASS A n M I 'Z 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 ~ 000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0 C 0

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 0 rt P 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 I tt 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 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.004 0.004 0.008 0.000 0.001 0.018 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 gfP TOTAL 0.75 0.66 0.50 0.29 0.19 0.16 0 ~ 16 0.21 0.47 0.61 0.78 0.97 0.36 0.49 Q.75 0.74 8.09 C

ATHOSPHERIC STABILITY CLASS 8 0 p 0.34 1.56 0.000 0.014 0.000 o.aIS 0.000 0.023 0.000 0.022 0.000 0.017 0.000 0.021 0.000 0.017 0.000 0.018 0.000 0.022 0.000 0.020 0.000 0.032 0.000 0.021 0.000 0.025 0.000 0.013 0.000 0.018 0 ~ 000 0.017 0.000 0.314 n-U Q M 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 'z 5.59 0.109 0.087 0.061 0.022 0.021 0.008 0.020 0.022 0.047 0.099 0.160 0.196 0.102 0.151 0.216 0.158 1.478 8.27 0.006 0.000 0.001 0.000 0.000 0.000 0.000 0.001 0.004 0.005 0.031 0.026 0.032 0.053 0.028 0.019 0.205 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.002 0.001 0.003 0.001 0.001 0.010 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.001 TOTAL 0.44 0.37 0.29 0.23 0.19 0.15 0.12 0.17 0.31 0.41 0.55 0.56 0.27 0.36 0.48 0.41 5.31 ATHOSPHERIC STABILITY CLASS C 0.34 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.56 0.031 0.03'I 0.035 0.028 0.023 0.031 0.041 0.037 0.050 0.057 0.069 0.045 0.035 0.029 0.033 0.038 0.610 3.35 0.347 0.287 0.245 0.220 0.152 0.131 0.121 0.158 0.261 0.332 0.375 0.369 0.175 0.192 Q.246 0.261 3.874 5.59 0.139 0.081 0.039 0.036 0.008 0.009 0.014 0.027 0.029 0.112 0.160 0.192 0.117 0.115 0.199 0.145 1.423 8.27 0.007 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0 ~ 001 0.008 0.019 O.Q23 0.012 O.Q55 0.024 a.a1s 0.164 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.003 0.002 0.002 0.000 0.000 0.009 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 O.OOQ Q.aaa a.aoo o.aoo o.oao 0.000 0.000 TOTAL 0.52 0.40 0.32 0.28 0.18 0.17 O. 18 0.22 0.34 0.51 0.63 0.63 0.34 0.39 0.50 0.46 6.08 ATHOSPHERIC STABILITY CLASS 0 H H N SM 0.34 a.oo2 o.oa2 o.ao2 o.oo2 0.001 0.001 0.001 0.001 0.002 0.002 0.002 0.001 0.001 0.001 0.001 0.001 0.025 1.56 0.434 0.506 0.444 0.370 0.329 0.266 0.278 0.300 0.362 0.481 0.465 0.346 0.287 0.258 0 '69 0.346 5.739 3.35 1.759 2.054 1.350 0.964 0.624 0.523 0.556 0.742 1.058 1.346 1.316 1.177 0.647 0.583 0.746 1.025 16.471 5.59 0.556 0.491 0.330 0.114 0.066 0.076 0.100 0.190 0.220 0.376 0.550 0.462 0 ~ 260 0.402 0.523 0.558 5.271 8.27 0.055 0.023 0.004 0.011 0.004 0.006 0.005 0.023 0.032 0.047 0.069 0.075 0.042 0.092 0.062 0.063 0.610 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.001 0.001 0.008 0.017 0.000 0.004 0.000 0.000 0.032 11.62 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 TOTAL 2.81 3.08 2.13 1.46 1.02 0.87 0.94 1.26 1.68 '.25 2.41 2.08 1.24 1.34 1.60 1.99 28. 15

TABLE A-13 o v) m III III Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP rr 0 rI III

-- SHHPP GROUND-LEVEL HISTORICAL DATA, 1976-1987 UK XDQDOQ 0 fo JOINT FREQUENCY DISTRIBUTION OF WINO SPEED AND DIRECTION III III I

ATHOSPMERIC STABILITY CLASS E O III W'W W I Z 0.34 0.005 0.007 0.006 0.005 0.004 O.OD3 D.004 D.006 0.009 0.009 0.005 0.004 0.003 0.002 0.003 0.003 0.079 0 I C 0 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 I I 3.35 1.028 0.855 0.549 0.329 0.309 0.266 0.356 0.577 1.058 1.547 1.029 0.744 0.488 0.459 0.660 0.667 10.920 III 0 rr 0 5.59 0. 124 0.032 0.046 0.029 0.019 0.028 0.032 0.080 0.138 0.148 0.216 0.145 0.067 0.101 0.085 0.131 1.421 r 0

v 8.27 O.Q07 0.003 0.000 O.OQ2 O.Q02 Q.004 a.aa6 o.oo6 o.o16 o.o1o 0.015 0.026 0.010 0.003 0.003 0.008 0.120

11. 18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.003 0.004 0.000 0.001 . 0.000 0.000 0.008 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 O.OQQ O.QQQ 0.000 0.000 Z Z III III TOTAL 1.91 1.86 1.42 1.06 0.85 0.78 0.93 1.49 2.47 2.90 1.99 1.41 0.98 0.88 1.16 1.28 23.36 I I III ATHOSPMERIC STABILITY CLASS F A 0 rr 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 U 1.56 0.777 0.788 O.T35 0.621 0.500 0 414 0.489 0.66T 0.803 0.857 0.553 0.395 0.341 0.291 0.321 0.467 9.0'I7 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 0 154 1 925 z

'II 5.59 0.003 O.Q01 0.000 0.001 0.000 0.000 0.000 O.OQQ 0.000 o.ao1 o.ao6 o.oo1 0.000 0.000 0.000 0.002 0.015 'Q 8.27 0.000 0.000 O.OQQ 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 O.OQO 0.000 0.000 0.000 O.QQO 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 ATHOSPMERIC STABILITY CLASS 0 MA 0.34 0.360 0.317 0.316 0.284 0.214 0.154 0.12'I 0.108 0.128 0.128 0.112 0.085 O.OTT 0.071 0.085 0.176 2.737 1.56 1.932 1.699 1.692 1.522 1.146 0.823 0.649 0.580 0.684 0.688 0.600 0.457 0.414 0.381 0.455 0.945 14.668 3.35 0.162 0.032 0.024 O.Q21 0.009 0.012 O.Q12 O.QOT 0.007 o.aae o.a26 0.023 0.014 0.015 0.021 0.04T 0.439 5 '9 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.001 0.001 0.003 8.27 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 11.18 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 11.62 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 2.45 2.05 2.03 1.83 1.37 0.99 0.78 0.70 0.82 o.e2 0.74 0.57 0.51 0.47 0.56 1.17 17.85 OVERALL 'WIND DIREC'TIOH FREQUENCY W W HH FREQUENCY: 1o.o 9.4 T.s 5.9 4.4 3.6 3.7 r.e T.o e.6 T.e 6.8 4.1 4.3 s.s 6.7 Too.o P

C G

Ch CP

TABLE A-13 0 IA W O Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP rt 0 O

U X Period of Record : Ol/Ol/76 - 12/31/87 0 ill t5

"*~~* 0 TOTAL HOURS CONSIDERED ARE r.

O (n W 'Z n c G n OVERALL WIND SPEED FREQUENCY HAX WIND SPEED (H/S): 0.335 1.565 3.353 5.588 8.270 11.176 11.623 0 W

AVE MIND SPEED (H/S): 0.168 0.950 2.459 4.470 6.929 9.723 11.400 I.g 0

Dl MIND SPEED FREQUENCY: 3.05 41.38 41.23 12.79 1.48 0.08 0.00 THE CONVERSIOH FACTOR APPLIED TO THE MIND SPEED CLASSES IS 0.447 0 Z C 0

C DISTANCES AND TERRAIN HEIGHTS IH HETERS AS FUNCTIONS OF DIRECTION FROH THE SITE:

DIRECTIOH = S SSM SW WSM M WN'M NM NNM N NNE NE ENE E ESE SE SSE DISTAHCE 2189. 2140. 2140. 2140. 2140. 2140. 2028. 2028. 2124. 2140. 2140. 2'I40. 2140. 2140. 2140. 2140. 0 rt

0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. U ELEVATION 0. O Q Vl z

'0 VENT AND BUILDIHG PARAHETERS:

RELEASE HEIGHT (HETERS) 0.00 DIAMETER (HETERS) 0.00 EXIT VELOCITY (HETERS) 0.00 REP. MIND HEIGHT (HETERS) 10.0 BUILDING HEIGHT (HETERS) 55.0 BLDG.HIN.CRS.SEC.AREA (SQ.NETERS) 2161.0 HEAT EHISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

WINO HEASUREO AT 12.0 HETERS.

0 vl TABLE A-14 W 0 lh Dl I

Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rt 0 Calculations with the NRC XOQDOQ Program 8 UK 0

Ul Pl 0

Card Type Columns Variable Name Format Description Value used in 0

r fh XOQDOQ W 'Z Card Type 1 is an array (KOPT) of options, such that 1 = DO, 0 = BYPASS.

n c 0

These options remain in effect for all release points run. Thus, all release oints must have the same assumptions. 0 rr p KOPT(1) Option to distribute calms as the first wind-speed class r 0

r~

(if calms are already distributed by direction in Card 0

Type 6, KOPT(1) ~ 0, and Card Type 5 is blank). If KOPT(l) = 1, the calm values of Card Type 5 are tD distributed by direction in the same proportion as the r-direction fre uenc of wind-speed class two. I KOPT(2) Option to input joint frequency distribution data as 0 0 rt ercent frequency. aO~

Q Ul 3 . KOPT(3) Option to compute a sector spread for comparison with K centerline value in pur e calculation (Normall = 1). tQ KOPT(4) Option to plot short-term X/0 values versus probability 0 of occurrence (Normall = 0).

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

1).

KOPT(6) Option to punch radial segment X/0 and D/Q values (Normally = 1).

KOPT(7) Option to punch output of X/Q and D/0 values of the points of interest (Normail ~ 1).

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

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

~, ~ ~ ~

~ ~

~ ~ I~ ~ o

~ ~ ~

~ ~ I~ ~

I ~ ~ ~

' ~

~ ~ ~ ~ I ~ ~

~ ~ ~

- ~ ~ ~

~ ~ ~ ~ ~

~ '

%55% ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ' ~ ~

~ ~ ~ ~ ~

~ ' ~

~ ~ s I ~ ~

~ ~

~ ' ~ ~ ~ ~ ~ ~ ~

~

~ ~

~ ~ ~

~ I

~ ~ ' ~ ~ ~

~

' ~

~ ~ ~ ~

Q V)

TABLE A-14 M8 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rrt w0 tO lU Calculations with the NRC XOQDOQ Program 0 U K 0

Ol lI Card Type Columns Variable Name Format Description Value used in 8 XOQDOQ O Ol AI W 'Z 6-20 3F5.0 For each I: The half-life (days) used in the X/Q 101.00 0 c DECAYS(I)

I = 1,3 calculations:.if DECAYS > 100, no decay will occur; if 2.30 r 0 r r0 DECAYS < 0, depletion factor will be used in the X/Q -8.00 rt I

calculations; if DECAYS = 0, X/Q will not be calculated. 0 (Normally, DECAYS(1) = 101, (2) 2.26, (3) = -8.00.) 0 Z

fU Z

(D 21 -25 PLG BAD 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 t>> W in meters. If PLGRAD < 0.0, DIST in miles and HT data in feet above plant grade. If PLGRAD > 0.0 above DIST 0 N aO~

in miles and HT data in feet above sea level.

Z U) 1-35 CALM(l) 7F5.0 The number of hours, or percent. of calm for each BLANK z I = 1,NSTA stability category; if KOPT(1) = 0, insert blank card. PQ (Note: I 1 is stabilit 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(1)=0) combination of wind-speed class (I) and stability class (J).

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

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ' ~

~ ~

I~ I~ ~

~ ~ ~ ~

' ~ ~ ~

~ ~ ~ ~ I I II

~ ~

~ ~ ~

' ~ 'I ~ ~ ~

~ ~ ~ ' ~ ~ ~

~ ~

~RI

~ ~ ~ ~ ~ ~ ~

~ ~

' ~ ~ 0 ' ' ~

RR ~ ~

~

+

~

~ ~

~

. ~ ~

~

~ ~

~

~ . ~

I

~ ~ II~

~ ~ I . ~ ~ ~ ~

~ ~

' I ~ ~ . ~

~ 'I ' ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

' ~ ~ ~ ~ ~

' ~ I

~ ~ I ~ ~

~ ~ ~ ~

' ~ ~ ~

~ ~ ~ 4 ~ ~

~

a o ~ ~ ~ ~

' ~ ~ ~ ~ '

0 th K cA TABLE A-14 th 0 Ol k'A Shearon Harris Plant Site Input information for Continuous Ground Level Releases rt 0 Calculations with the NRC XOQDOQ Program C7 K 0

Vl Card Type Columns Variable Name Format Description Value used in V XOQDOQ O tn wK 1-25 5I5 The number (maximum of 30) of receptor locations for a 0 c 12 NPOINT(I) 16,15,13,2,0,11 0 I = 1,NPTYPE particular receptor type (such as the number of cows, (D ardens, or site boundaries). ~ Ql I

0 ard Types 1 3 and 14 are read in for each r eceptor t pe, thus I ~ 1,NPTYPE 0

13 1 -16 TITLPT(I,J) The title (cows, gardens, etc.) of the receptor type for the Site Boundary = 16 g Z 0

receptor locations (Card Type 14) (a maximum of 16 Nearest Resident = r-spaces). 15 MI Garden = 13 Cow Milk = 2 0 rt j

Goat Milk = 0 aO~

Meat 5 Poultr = 11 g lA z

1 -80 KDIR(I,N) 8(IS,F5.0) The receptor direction and distance. KDIR is the direction See Table A-1 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 Types 13 and 14 are repeated for the remainin receptor types.

Card Types 15, 16 and 17 are read in for each plant release point, 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 100% ground-level release is assumed, set EXIT = 0, DIAMTR = 0, and SLEV = 10 meters).

16 6-10 DIAMTR F5.0 The vent inside diameter (meters).

16 11 - 15 H STACK(I) F5.0 The height of the vent release point (meters, plant grade 0.0 level). If release is 100% elevated, input negative of hei ht.

16 16-20 HBLDG(I) F5.0 The height of the vent's building (meters, above plant 55.0 grade level).

0 V)

TABLE A-14 W 8 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases rr 0 (D

Calculations with the NRC XOQDOQ Program D A 0 lV Ol Card Type Columns Variable Name Format Description Value used in 0 XOQDOQ neV I

21 -25 CRSEC(I) F5.0 The minimum cross-sectional area for the vent's building 2161.0 0 c 0

(s uare meters). 8 16 26- 30 SLEV(I) F5.0 The wind height used for the vent elevated release 1 0.0 r 0

g (meters, above lant rade level).

0 16 31 -35 HEATR(l) F5.0 The vent heat emission rate (cal/sec) (Normall = 0). 0.0 Z Z O

l=

17 RLSID(I) A1 A one letter identification for the release oint.

17 2-5 IP URGE(l) l4 IPURGE = 1, 2 or 3 if the vent has intermittent releases.

The 1, 2, or 3 corresponds to DECAYS(l), DECAYS(2), 0 rt Cl or DECAYS(3) (Card Type 4), respectively, whichever is n Ul used as the base for intermittent release calculations gx (normally no decay/no deplete X/Q, such that IPURGE(l) z

= 1; if a vent has no intermittent releases, IPURGE = 0.

17 6-10 NPURGE(l) l5 The number of intermittent releases per year for this release point.

11 - 15 NPRGHR(l) l5 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 ma be repeated 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 RADIOIODINES, PARTICULATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with ODCM Operational Requirement 3.11.2.1.b and Appendix I of 10CFR50 for gaseous effluents.

These dose parameters, P< and Rz, 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 P< and Rf values foz 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 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.l.b is to restrict the dose to the child's thyroid via inhalation to s 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 factozs for the child, DFQ, are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi .

I The total body is considered as an organ in the selection of DFA,.

Shearon Harris Nuclear Power Plant (SHNPP) August Offsite Dose Calculation Manual (ODCM) 199'ev.

5 APPENDIX B Sheet 2 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, 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 K'BR) DFAi (B. 1-1) where:

P.

ig ~

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 radionuclide "i," mrem/pCi.

The incorporation of breathing rate of a child (3700 m'/yr) and the unit conversion factor results in the following equation:

P.

ig 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, PARTICULATES, AND TRITIUM B.2 Calculation of R The bases for ODCM Operational Requirement 3. 11 '.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 exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. Underestimation of the dose can be avoided by assigning a theoretical individual to the exclusion boundary in the sector with the highest X/Q and D/Q values and employing all of the likely exposure pathways, e.g., inhalation, cow milk, meat, vegetation, and ground plane.

Rq 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'ND TRITIUM B.2.1 Inhalation Pathwa The dose factor from the inhalation pathway is calculated by:

R.

K'BR) a (DFJ4) a (B. 2-1) where:

R.

4 Dose factor for each identified radionuclide "i" of the organ of interest, mrem/yr per pCi/m';

K A constant of unit conversion; 10'Ci/pCi; (BR) Breathing rate of the receptox of age group "a,"

m'/yr; (DFQ) ~ Or'gan inhalation dose factor for radionuclide "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 (DFQ), for the various age groups are given in Tables E-7 thxough 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 RADIOZODZNES J PARTI CULATES ~ AND TRITIUM B.2.2 Ground Plane Pathwa The ground plane pathway dose factor is calculated by:

-L t K'K" (SF) where:

R ~

iG i Z. DFG.

i (1-e ) /X (B.2-2)

Dose factor for the ground plane 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; K" 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);

DFGg The ground plane dose conversion factor for radionuclide "i, "

mrem/hr per pci/m~;

A tabulation of DFG~ values is presented, in Table E-6 of Regulatory Guide 1.109, Revision l.

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 of 15 DOSE PARAMETERS FOR RADIOIODINESf PARTICULATES f AND TRITIUM B. 2. 2 Ground Plane Pathwa (continued)

Factor to account for fractional deposition of radionuclide If If 1

For radionuclides other than iodine, the factor I~ is equal to one. For radioiodines, the value of Iz may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133)

B-6

Shearon Harris Nuclear Power plant (SHNPP) June 1994 Offsite Dose Calculation Manual (ODCM) Rev. 4 APPENDIX B Sheet 7 of 15 DOSE PARAMETERS FOR RAD1OIODINES, PARTICULATES, AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa The dose factor for the cow milk or goat milk pathway for each radionuclide for each ozgan is calculated by:

-X tf f fs r(1-e Ei t e) Biv (1-e i b) iKQFUap ap Fm m (DFLi a e + +

p iEEi PAi

-h.itb Ei t e) Biv(1-e (B.2-3)

(1"fpfs) ( r (1-e ~ith )

)

+ ) e YS XE Phi where:

R.

4 Dose factor for the cow milk or goat milk identified radionuclide "i" for the organ pathway, for each 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 ap The receptor's milk consumption rate for age group "a,"

liters/yr; Yp The agricultural productivity by unit area of pasture feed grass, kg/m~;

The agricultural productiv5.ty by unit area of stored feed, kg/m';

B-7

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

APPENDIX B Sheet 8 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES~ AND TRITIUM 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; (DFLi) a The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pci; AE I

= Xi++;

The radiological decay constant for radionuclide "i,"

sec ';

The decay constant foz removal of activity on leaf and plant surfaces by weathering, sec ';

5.73 E-07 sec 'l4 day half-life);

The transport time from feed to cow, oz 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 Sheet 9 of 15 DOSE PARAMETERS FOR RADZOZODINES~ PARTICULATES~ AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa (continued)

Ef fective surface density for soil, Kg (dry soil) /m~;

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; Factor to account for fractional deposition of radionuclide "i."

For radionuclides other than iodine, the factor Z.1 is equal to one. Foz radioiodines, the value of Z. may vary. However, a value of 1.0 was used in calculat'ing the R values in Tables 3.3-8 through 3.3-15. (Reference NUREG 0133)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109, Revision 1, the value of f, was considered unity in lieu of site-specific information. The value of 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 RADIOIODINESi PARTICULATES~ AND TRITIUM B.2.3 Grass Cow or Goat Milk Pathwa (continued)

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R< is based on X/Q:

R K'K' 'F~QrUap (DFLs) a 0.75 (0. 5/H) (B. 2-4) where:

R 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; 10s gm/kg 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

Shearon Harris Nuclear Power plant (SHNPP) June Of fsite Dose Calculation Manual (ODCM) 199'ev.

APPENDIX B Sheet 11 of 15 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TR1'TIUM 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:

~its f r(l,-e Ei e) iv (1-e ~i b)

Ri = IiK

3. QF Uaap Ff (DFLi a e Psfs + +

Y ZE ph'i Ei

-h.i tb (1 fp fs ) (

r(1-e -XE ite') +

iv(1-e

) e

~ith ) (B.2-5)

Ys ~E phi where:

R Dose factor for the meat ingestion pathway for radionuclide "i" for any organ of interest, mrem/yr per pCi/sec per m';

The stable element transfer coefficients, pci/Kg per pci/day; U

ap The receptor's meat consumption rate for age group "a,"

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 RADIOIODINES, PARTICULATES, AND TRITIUM B.2.4 Grass-Cow-Meat Pathwa (continued) th Transport time from harvest to animal consumption, sec; te Period of pasture grass and crop exposure during the growing season, sec; Factor to account for fractional deposition of radionuclide Ili fl For radionuclides other than iodine, I~ is equal to one. For radioiodines, the value of Iq may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-5 through 3.3-7.

All other terms remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating R~ for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the Rg is based on X/Q.

R K'K' 'F<QrUap(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) Rev. 4 APPENDIX B Sheet 13 of 15 DOSE PARAMETERS FOR RADIOIODINE S I PARTICULATES I AND TRITIUM B.2.5 Ve etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

t (1-e Ei e) iv (1-e i b) v E ~ i Ei t e)

-A.itb

-),. t h r(1-e Biv(l-e S

Uaf e i ( +

Phi

)

(B. 2-7)

Yv hE i

where:

R 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'pci/pci; B-13

Shearon Harris Nuclear Power Plant (SHNPP) June 19gg Offsite Dose Calculation Manual (ODCM) Rev.

APPENDIX B Sheet 14 of ].5 DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM B.2.5 Ve etation Pathwa (continued)

The consumption rate of fresh leafy vegetation by the receptor in age group "a, " kg/yr; The consumption rate of stored vegetation by the receptor in age group "a," kg/yr; The fraction of the annual intake of fzesh 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; The vegetation a real density, kg/m';

Period of leafy vegetable exposure during growing season, sec; Factor to account for fractional deposition of radionuclide Ill II All other factors as defined before.

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

APPENDIX B Sheet 15 of 15 DOSE PARAMETERS FOR RADIOIODINES~ PARTICULATES~ AND TRITIUM B.2.5 Ve etation Pathwa (continued)

For radionuclides 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 Tables 3.3-2 through 3.3-4.

Table B-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

In lieu of site-specific data default values for f and f~, 1.0 and 0.76, respectively, were used in the calculations on R~. 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 R~ is based on X/Q:

RT K<K'i i U + U (DFL ) 0.75(0.5/H) (B.2.8)

V L where:

R Dose factor for the vegetable pathway for 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

( seconds) 1.73 E+05 (2 days) Table E-15 1.0 (radioiodines) Table E-15 0.2 (particulates) Tabl E-15 i

(DFL.) a (mrem/pCi) Each radionuclide Table E-11 to E-14 F

m (pCi/liter per pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

T (seconds) 4.75 E+08 (15 yr) Table E-15 Y

s (kr/m') 2.0 Table E-15 t (seconds) 7.78 E+06 (90 days) Table E-15 U

ap (liters/yr) 330 infant Table E-5 330 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.

iv (pCi/kg [wet weight] Each stable element Table E-1 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

ap (kg/yr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-S Each radionuclide i

(DFL.) a (mrem/pCi) Tables E-11 to E-14 Y (kg/m') 0.7 Table E-15 P

Y s

(kr/m') 2.0 Table E-15 T (seconds) 4.73 E+08 (15 yr) Table E-15 T

t s

(seconds) soil/m'alue (seconds) 1.73 7.78 E+06 (20 days)

E+06 (90 days)

Table E-15 Table 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 B.

iv (pCi/kg [wet weight) Each stable element Table E-l per pCi/kg [dry soil])

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 (rad'iodines) Table E-1 0.2 (particulates) Table E-1 (DFL.)

ia (mrem/pCi) Each radionuclide Tables E-11 to E-14 Q (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 U"

a (kg/yr) Znfant 0 Table E-5 Child 26 Table E-5 Teen 42 Table E-5 Adult 64 Table E-5 U'kr/hr) a Znfant 0 Table E-5 Child 520 Table E-5 Teen 630 Table E-5

- Adult 520 Table E-S T (seconds) 8.6 E+04 (1 day) Table E-15 t (seconds) 5.18 E+06 (60 day) Table E-15 Y

v (kg/m') 2.0 Table E-15 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 RADZOACTZVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Monitor Li uid Effluent Monitorin Instruments Identification A. Treated Laundry and Hot shower Tank REM-1WL-3540 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 Outdoor Tank Area Drain Transfer Pump Monitor REM-1MD-3530 G. Turbine Building Floor Drains Effluent REM-1MD-3528 IX ~ Gaseous Effluent Monitorin Instruments A. Plant Vent Stack 1 REM-1AV-3509-SA

RM-21AV-3509-1SA Turbine Building Vent Stack 3A RM-1TV-3536-1 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 l995 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.l Instrumentation D.2 - Radioactive Effluents D.3 - Radiological Environmental Monitoring

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 D.1 INSTRUMENTATION 3/4.3.3 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 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFPSITE 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 radi.oactive 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 Sn the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-8.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9 3 3-0 C V U D U 0 0 G STR N ON MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION Radioactivity Monitors ProViding Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Lines Treated Laundry and Hot Shower 35 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 Effluent 36 Line 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 Cixculating 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 Shower 38 Tanks Discharge

2) Waste Monitor Tanks and Waste 38 Evaporator Condensate Tanks Discharge

3) Secondary Waste Sample Tank 38

b. Cooling Towex Blowdown 38 When the Secondary Waste System is in the continuous release mode and releases are occurring, Action 36 shall be taken when the monitor is inoperable. In the batch release mode, Action 35 is applicable.

D-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a ~ At least two independent samples are analyzed in accordance with Operational Requirement 4.11.1.1.1, and At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 10 'icroCurie/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 microCurie/gram DOSE EQUIVALENT Z-131.

ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may con'tinue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 10 7 microCurie/ml.

ACTION 38 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

ACTION 39 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the weekly Cooling Tower Blowdown weir surveillance is performed as required by Operational Requirement 4.11.1.1.1. Otherwise, follow the ACTION specified in ACTZON 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 DZGZTAL 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) Q(1)

Shower Tanks Discharge Monitor

2) Waste Monitor Tanks and R (3) Q (1)

Waste Evaporator Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tank D P, M(5) R(3) Q(1)

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) Q(1)

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. Normal Service Water System R(3) Q(2)

Return From the Reactor Auxiliary Building to the Circulating Water System Flow Rate Measuzement 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 Waste Evaporator Condensate D (4)'.A. N.A.

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) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9

.3-8 Co t'ed 0 S (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate automatic isolation of this pathway (or, for the Outdoor Tank Area Drains Monitor, automatic stop signal to the discharge pump) and control room alarm annunciation* occur if any of the following conditions exists (liquid activity channel only):

a Instrument indicates measured levels above the Alarm/Trip Setpoint, Circuit failure (monitor loss of communications (alarm only),

detector loss of counts (Alarm only) and monitor loss of power),

Detector check source test failure (alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only).

(2) The DIGITAL CHANNEL OPERATZONAL TEST shall also demonstrate that control room alarm annunciation" occurs (liquid activity channel only):

if any of the following conditions exists Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications , detector loss of counts, and monitor loss of power),

c. Detector check source test failure,

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which 'continuous, periodic, or batch releases are made.

(5) When the Secondary Waste System is being used in the batch release mode, the source check shall be prior to release. When the system is being used in the continuous release mode, the source check shall be monthly.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-11 terminal (i.e., a change in color).

D-6

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3 '1 Radioactive Gaseous Effluent Monitorin Instrumentation OPERATIONAL REQUIREMENT 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Operational Requirements 3.11.2.1 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:

With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Operational Requirement, immediately (1) suspend the release of radioactive gaseous effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by b.

below.

b. With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to, OPERABLE status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section 'F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated'PERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and a DIGITAL CHANNEL OPERATIONAL TEST or an ANALOG CHANNEL'PERATIONAL 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 RADZOACTZVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MIN. CHANNELS INSTRUMENT 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 47

b. Zodine Sampler c ~ Particulate Sampler

d. Flow Rate Monitor 46

e. Sampler Flow Rate Monitor

3. PLANT VENT STACK

a. Noble Gas Activity Monitor 47

b. Iodine Sampler

c. Particulate Sampler

d. Flow Rate Monitor.

e. Sampler Flow Rate Monitor

4. WASTE PROCESSING BUILDING VENT STACK 5 Noble Gas Activity Monitor (PZG) 45, 51 a.2 Noble Gas Activity Monitor (WRGM) MODES I, 2, 3 52 Zodine Sampler c Particulate Sampler Flow Rate Monitor Sampler Flow Rate Monitor WASTE PROCESSING BUILDING STACK SA Noble Gas Activity Monitor Iodine Sampler Particulate Sampler Flow Rate Monitor Sampler Flow Rate Monitor TABLE NOTATIONS

At all times.

D-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 45 - With the number channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the waste gas decay tank(s) may be released to the environment provided that prior to initiating the release:

a ~ At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 - Not Used in the ODCM.

ACTION 49 With the number of c hannels 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 '.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 6.9.2, within the next 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channel(s) to OPERABLE status.

D-9

Shearon Harris Nuclear Power Plant (SHNPP) August 3.995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES FOR WHICH DIGITAL CHANNEL SURVEILLANCE CHANNEL SOURCE CHANNEL OPEltlITIONAL ~IS IIX tltED INSTRUMENT CHECK ~ CHECK CALIBRATION TEST

l. GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALY2ERS Not Used in the ODCM.

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity R(3) Q(2)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. 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 Monitor D R(3) Q(2)

b. Iodine Sampler

c. Particulate Smpler

d. Flow Rate Monitor N.A.

e. Sampler Flow Rate Monitor D

4. WASTE PROCESSING BUILDING VENT STACK 5

a. 1 Noble Gas Activity Monitor D R(3) Q(l)

(PIG) a.2 Noble Gas Activity Monitor D R(3) Q(2)

(WRGM)

b. Iodine Sampler N.A.

c. Particulate Sampler

d. Flow Rate Monitor

e. Sampler Flow Rate Monitor D WASTE PROCESSING BUILDING VENT STACK 5A

a. Noble Gas Activity Monitor M R(3) Q(2)

b. Iodine Sampler N.A.

c. Particulate Sampler N.A.

d. Flow Rate Monitor N.A.

e. Sampler Flow Rate Monitor N.A.

At all times.

D-10

Shearon Harris Nuclear Power Plant (SHNPP) August 1996 Offsite Dose Calculation Manual (ODCM) Rev. 9 (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation" occur if any of the following conditions exists (gas activity and gas effluent channels only):

a. Instrument indicates measured levels above the Alarm/Trip Setpoint,

b. Circuit failure (monitor loss of communications - (alarm only),

detector loss of counts (alarm only) and monitor loss of power),

Detector check source test failure (gas activity channel only),

(alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exists (gas activity and gas effluent channels only):

Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications (alarm only),

detector loss of counts, and moni.tor loss of power),

c. Detector check source test failure (gas activity channel only),

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) Not used in the ODCM.

(5) Not used. in the ODCM.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-11 terminal (i.e., a change in color).

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

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 UNRESTR1CTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Operational Requirement 3.11.1.1.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D"12

~ ~

~ ~ ~

~ I ~ ~ ~

~ ~

~ ~ ~

~ ~ 0 4 0

~ ~ ~

~ ~

~ ~ ~

~ ~

0 ~ ~

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 sb LLD E ' ' '2 x 10~ ' exp (-)h~t)

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),

the counting efficiency (counts per disintegration),

the sample size (units of mass or volume),

2.22 x 10' the number of disintegrations per minute per 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.

lt should be recognized that the LLD is defined as an ~ariori Ibefore 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.

Sheazon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCMI Rev. 6 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued)

(3) The principal gamma emittezs 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 zelease pathways. The potential contamination points are in the Normal Service Water (NSW) and Secondary Waste (SW) Systems. Action under this Operational Requirement is as follows:

a) If the applicable (NSW or SW) monitors in Table 3.3-12 are OPERABLE and not in alarm, then no analysis under thi.s Operational Requirement is required but weekly composites will be collected.

b) If the applicable monitor is out of service, then the weekly analysis for principal gamma emitters will be performed.

c) If the applicable monitor is in alarm or if the principal gamma emitter analysis indicates the presence of radioactivity as defined in the ODCM, then all other analyses of this Operational Requirement shall be performed at the indicated frequency as long as the initiating conditions exist.

(8) The Secondary Waste System releases can be either batch or continuous.

The type of sample required is determined by the mode of operation being used.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.2 Dose OPERATIONAL REQUIREMENT 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) shall be limited:

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 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.

3LCTEON:

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 OPERATXONAL 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:

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Li.quid 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 radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s)- taken to restore the inoperable equipment to OPERABLE status, and Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRXCTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Operational Requirements 3.11.1.1 and 3.11.1.2.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-17

Sheazon Harris Nuclear Power Plant (SHNPP) Augus t 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate OPERATIONAL REQUIREMENT 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-1) shall be limited to the following:

a For noble gases: Less than oz equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particular form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all zadionuclides 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 suzveillance interval with a maximum allowable extension not to exceed 258 of the specified surveillance interval.

D-18

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS DETECTION (LLD)())

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pCi/ml)

1. Waste Gas Storage P P Principal Gamma Emitters Tank Each Tank Each Tank Grab Sample lxlO-'xlo"

2. Containment Purge P P Principal Gamma Emitters(~) ~

or Vent(~0) Each PURGE(~) Each PURGE Grab Sample H-3 (oxide) lxlO s

3. a. Plant Vent Principal Gamma Emitters( lxlO ~

Stack lxlo s

'-3 Grab Sample (oxide)

b. Turbine Bldg M Principal Gamma Emitters( ) lxlO ~

Vent Stack, Grab Sample Waste Proc.

Bldg. Vent H-3 (oxide) (Turbine Bldg. lxlo s

'xlO Stacks 5 & 5A Vent Stack)

4. All Release Types Continuous W() ) I-131 >>

as listed in 1.,2.,

and 3. above Charcoal I-133 lxlO->>

(8). (9), (10) Sample Continuous w(') Principal Gamma Emitters( lxlO >>

Particulate Sample Continuous M Gross Alpha lxlO->>

Composite Particulate Sample Continuous(s) Sr-89, Sr-90 lxlO->>

Composite Particulate Sample

Shearon Harris Nuclear Power Plant (SHNPP) Augus" 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 sb LLD-E ' '22 < 10 Y exp ()ddt)

Where:

LLD = the "a priori" lower limit of detection (microCurie per unit mass or volume),

Si, the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

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, 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.

It should be recognised that the LLD is defined as an ~ariori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

D-20

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(2) The principal gamma emittezs for which the LLD Operational Requi ement 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, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in Iodine 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 phriod.

(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 foz the time period covered by each dose or dose rate calculation made in accordance with Operational Requirements 3.11.2.1, 3.11.2.2, and 3.11.2.3.

~ (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months a fter changing, or a fter removal fzom sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-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 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(10) The requirement to sample the containment atmosphere prior to release for normal and pre-entry containment purge operations (that is, to "permit" the release per the ODCM) is required on initial system startup, and prior to system restart following any system shutdown due to radiological changes in the containment (e.g. valid high alarms on leak detection or containment area monitors) . System shutdown occurring on changes in containment pressure, equipment malfunctions, operational convenience, sampling, and so forth, do not require new samples or release permits.

D-22

Sheazon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose - Noble Gases OPERATIONAL REQUIREMENT 3:11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

Pith 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 foz the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-23

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form OPERATIONAL REQUIREMENT 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Zodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose, from the release of Iodine-131, Zodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Zodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-24

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.4 Gaseous Radwaste Treatment, 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 0.4 mrad to. air from beta radiation, or c 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

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,

)

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 VENTZLATION EXHAUST TREATMENT SYSTEM and GASEOUS RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Operational Requirements 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-25

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.11.4 TOTAL DOSE OPERATIONAL REQUIREMENT 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

With the calculated doses fzom the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Operational Requizement 3. 11. 1.2a., 3. 11. 1 2b., 3. 11.2.2a.g 3 11 2

~ 'b p or 3.11.2.3b., calculations shall be made including direct radiation 3 11 2 3a.,

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,'ursuant to Technical Specification 6.9.2, a Special Report, that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

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 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT 3.12.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Section F.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBL1C 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) + ...c 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted 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 2g 3 11 2 2g or 3 11 2 3 This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Ssection F.l.

The methodology and parameters used to estimate the'potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

D-27

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/4.12.1 MONZTORZNG PROGRAM OPERATZONAL REQUZREMENT ACTZON (Continued)

C. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to ODCM, Appendix E, 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 location(s) with supporting information identifying the cause of the new unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

SURVEZLLANCE REQUZREMENTS

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*

Q 0)

Ph K th lD EXPOSURE PATHWAY OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY Ql I

O'

'8 AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONSn~ COLLECTION FREQUENCY OF ANALYSIS Radiation"'UMBER 0

1. Direct Forty routine monitoring stations Quarterly. Gamma dose quarterly. UX either with two or more dosimeters 0 N

or with one instrument for 0 V

measuring and recording dose rate O 4 continuously, placed as follows: 0 c Z

An inner ring of stations, one in I 0

each meteorological sector in the rt (D

P general area of the SITE BOUNDARY; 0

't7 An outer ring of stations, one in 0 Z Z0 each meteorological sector in the 6- to 8-km range from the site; and C The balance of the stations to be placed in special interest OW areas such as population centers, n-U g, M nearby residences, schools, and in one or two areas to serve as z control stations.

TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM O M W (D EXPOSURE PATHWAY th NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS~u COLLECTION FREQUENCY OF ANALYSIS rt 0 (D

2. Airborne Samples from five locations: Continuous sampler Radioiodine Cannister: UK 0

Radioiodine and operation with sample I-131 analysis weekly. Ql Particulates collection weekly, or 8 Three samples from close to the three SITE BOUNDARY more frequently required by dust if O rZ Ol locations, in different n c sectors, of the highest loading. Particulate Sam ler: c n Gross beta radioactivity rt 0

calculated annual average analysis following Q ground-level D/Q; filter change;'" and I

0 gamma isotopic 0 One sample from the vicinity composite (by location) analysis"'f Z 0Z of a community having the quarterly. C highest calculated annual re average ground-level D/Q; and a0O rr One sample from a control location, as for example 15 to 3,'M 30 km distant and in the 'z U

I least prevalent wind 4l O

direction.

3. Waterborne

a. Surface"'ne sample upstream. Composite sample over Gamma isotopic 1-month period.'" Composite analysis"'onthly.

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 LOCATIONS~>> COT LECTION 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."'omposite beta and gamma isotopic analyses'" monthly.

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'" and 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, then one sample from milking at other times. animals are on pasture; 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 EXPOSURE PAT%'/AY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY SAMPLES AND SAMPLE LOCATIONS I COLLECTION FREQUENCY OF ANALYSIS AND/OR SAMPLE

4. Ingestion (Continued)

b. Fish and One sample of Sunfish, Catfish, and Sample in season, or Gamma isotopic Invertebrates Large-Mouth Bass species in vicinity semiannually if they analysis'" on of plant discharge area. aze not seasonal. edible portions.

One sample of same species in areas not influenced by plant discharge.

c. Food Products samples of three different kinds Monthly during Gamma isotopic"'nd of broad leaf vegetation grown growing season. I-131 analysis.

nearest each of two different.

offsite locations of highest predicted annual average ground level D/Q if not performed.

milk sampling is one sample of each of the similar Monthly during Gamma isotopic"'nd broad leaf vegetation grown 15 to growing season. I-131 analysis.

30 km distant in the least prevalent wind direction if milk sampling is not performed.

Shearon Harris Nuclear Power Plant (SHNPP) August 3.995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE 3.12-1 (Continued)

TABLE NOTATIONS Specific parameters of distance and direction sect oxx from tth e centerline of one actor, and additional description where pertin t s h a 11 b e provided for eac h reacto and every sample location in Table 3.12-1 in a t a bl e an d igure(s) in the ODCM.

f'n, Reefer to NUREG>>0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants I " October 1978 an d to Radiolo ical Assessment Branch Technical Position, Revision 1 Nove mb er 1979. Deviations due to circumstances such as hazardous cond't' if axe permitted from the required sampling schedule i specimens are unobtai'nable o i ions, seasonal unavailabilit y, and a malfunction of automatic sampling equipment

'n, eeffort or sshall If specimens are unobtainab axnable due to sampling equipment malfunction, be made to complete corrective action sampling schedule shall be documented in Op t' o t u u t to s ifi

'h a

'on prior to the end of the next sampling period. All deviations from e Annua 1 Radiological Envixonmenta tion 6.9.1.3. It is recognized that, at a

times it may ma not be possible or practicable to continue t o o b tain sam P les of the media of choice at the most desired location or ime. In these instances t'on s uitable alternative media and locations may bee c h osen for the particular paathwaway in question u s a

and appropriate substitutions made w'th'0 i in d ays in the Radiolo g'ica Environmental Monitoring Program. Pursuant t o OD CM, Appendix F, Section F.2 submit in the next Annual Radioactive Efflueen t R e 1 ease Report documentation for or a cchaange in the ODCM including a revised figure(s) s an d t a bl e for the ODCM reflectin g the new location(s) with supporting information dos'.

dentifying the cause of the unavailability of samples for that pathwa and justifying the selection of the new location(s) fox obtaining samples samp es.

One or more instruments, such as a pressurized ion chamber, for measurin and integrating dosimeters. For the purposes oof thiss ta i

recoxding dose rate continuously may be u se d n p 1 ace of, or in addition to, t bl e, a thermoluminescent dosimeter e ( TLD ) is considered to be one phosphor two or more m p h osp h ors in a k t are considered as two or more dosimeter p acket F'i m b a d ges shall not be used as dosimeters for measuring direct radiation. (The 40 e number of direct radiation monitoring stations ions mayma bee reduced according to geographical limitations; ns; e. g., at an ocean site, some sectors will i bee over ove water so that the number of dosimeters may b e re d uce d accoxdin g 1 y.. The requency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

Airborne particulate sample filters shall be analyzed foor gross b eta radioactivit y 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for ra radon on an a d t h oron daughter decay. If gross eta activity ross beta a in air particulate samples is greater th an 10 times the y earl y mean o f control samples, gamma isotopic analysis shall b e 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 program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

D-34

TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Q 0) th W th lD WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS rt 0 ANALYSIS (pCi/1) OR GASES (pCi/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet) 0 H-3 20,000* 0 Gl 0 tt Mn-54 V.

1, 000 30, 000 O 8 M 'Z Fe-59 400 10, 000 0 C c 0 Ml Co-58 1, 000 30, 000 Q ill rt Q V

0 Co-60 300 10,000 0 Z

Q 0 8

En-65 300 20, 000 C

Zr-Nb-95 400 Ml I-131 0.9 100 0 rt tl O ~

Cs-134 g M 30 10 1, 000 60 1, 000 x

Cs-137 50 20 2, 000 70 2, 000 Ba-La-140 200 300

+For drinking water samples: This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/1 may be used.

- Ifno drinking water pathway exists, a value of 20 pCi/1 may be used.

TABLE 4. 12-1 DETECTION CAPABXLITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS O ol th) P wS LOWER LIMIT OF DETECTION LLD M Y'

ct 0 WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT tl 0

'X ANALYSIS (pCi/1) OR GASES (pCi/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/k , dry) M tj 0

Gross Beta 0. 01 neV H-3 2000* P 'Z n C cn Mn-54 15 130 0 rt Q 0

Fe-59 30 260 0

Co-58, 60 130 0 l1 Zn-65 30 260 Zr-Nb-95 15 0 ct aO~

I-131 0. 07 60 g lh Cs-134 15 0. 05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15

Xf no drinking water pathway exists, a value of 3000 pCi/1 may be used.

- Xf no 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) Rev. 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.l.

(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 with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

~

For a particular measurement system, which may include radiochemical separation:

4.66 sb LLD =

E V 2.22 Y exp (-Mt)

Where:

LLD = the "a priori" lower limit of detection (picoCurie per unit mass or volume),

Sb the standard Meviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picoCurie, the fractional radiochemical yield, when applicableg the radioactive decay constant for the particular radionuclide (sec '), and the elapsed time between environmental collection, 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) Rev. 6 TABLE 4.12-1 (Continued)

TABLE NOTATEONS (Continued)

Zt should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact( limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. Zn such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

D-38

Sheazon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 3/a.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, puzsuant to ODcM, Appendix F,. Section F.2, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20%

greater than at a location from which samples are currently being obtained in accordance with Operational Requirement 3.12.1, add the new location(s) within 30 days to the Radiologi.cal Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the speci. fied 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 3la.12.3 INTERLABORATORY COMPARISON PROGRAM OPERATIONAL REQUIREMENT 3.12.3 ~

Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

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 Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-40

Shearon Harris Nuclear Power Plant (SHNPP) August l995 Offsite Dose Calculation Manual (ODCM) Rev.

APPENDIX E PROGRAMMATIC CONTROL BASES The Bases for the ODCM Operational Requirements are detailed in Sections:

E. 1 - Instrumentation E.2 Radioactive Effluents E.3 - Radiological. Environmental Monitoring

shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.l XNSTRUMENTATION BASES 3/4.3.3 MONXTORING ZNSTRUMENTATZON 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 Part 50.

3/4.3.3.11 Radioactive Gaseous Effluent Monit orin Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Set Points for these instzuments 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 OPERABXLXTY 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 aze measurable.

E-2

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 E RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUZD EFFLUENTS 3/4.11.1.1 Concentration This Operational Requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section ZX.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THF 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 (subm6rsion) 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 aze tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 Dose This Operational Requirement is provided to implement the requirements of Sections XI.A, XZI.A, and ZV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section IZ.A of Appendix Z. The ACTZON statements provide the required operating flexibility and at the same time implement the guides set forth in Section XV.A of Appendix X to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLXC through appropriate pathways is unlikely to be substantially underestimated.

E-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIoAcTIvE EFFLUENTs BAsEs 3/4.11.1 LIQUID EFFLUENTS 3/4. 11. 1.2 Dose (continued)

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

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 radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in.Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

'I

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES 3/4 '1 ' 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 ZI, "Column Z. 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 ZI of 10 CFR Part 20 [10 CFR .Pazt 20. 106(b)]. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole. body or to less than or equal to 3000 mrems/year to the skin.

These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

e The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection be found in HASL Procedures Manual, HASL-300 (revised annually),

limits,'an 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).

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

-.2 E RADIOACTIVE EFFLUENTS BASES 3l4. 11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose - Noble Gases This Operational Requirement is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures. based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 E RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form This Operational Requirement is provided to implement the requirements of Sections ZI.C, IZI.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirements are the guides set forth in Section II.C of Appendix Z. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix Z 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 aze consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, "

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate Operational Requirements for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater .than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY,. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition of the ground with subsequent exposure of man.

E-7

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

"=.2 E RADIOACTIVE EFFLUENTS BASES (continued) 3/n.11.2 GASEOUS EFFLUENTS 3/4.11.2.4 Gaseous Radwaste Treatment S stem The OPERABILXTY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section IX.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

E-8

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.3 SOLID RADIOACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a, 10 CFR 61, and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

Sheazon 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. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, 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 Ha ris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Operational Requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest Potential radiation exPosure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implements section 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 4a 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) limit repreaenting the capability oi 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 Hartwelly J K y Detection Limits for Radioanalytical Counting Techniques" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.12.2 LAND USE CENSUS This Operational Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made, if required, by the results of this census. The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 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 br'oad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/~.

Shearon Harris Nuclear Po~er Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 E.3 E RADIOLOGICAL ENVIRONMENTAL MONITORING BASES (continued) 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of .radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

E-12

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 APPENDIX F ADMINISTRATIVE CONTROLS The Reporting Requirements pertaining to the ODCM Operational Requirements are detailed in Sections:

F.1 Annual Radiological Environmental Operating Report F.2 - Annual Radioactive Effluent Release Report F.3 - Major changes to the Radwaste Treatment System (liquid and gaseous)

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 Annual Radiolo ical Envizonmental O 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. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible all sampling locations keyed to a table giving distances and maps'overing directions from 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.

Shearon Harris Nuclear Power Plant (SHNPP) August Offsite Dose Calculation Manual (ODCM) 199'ev.

6

":.2 F 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 of each year. The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioacpive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents zeleased 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 wit'h 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.

F-3

Shearon Harris Nuclear Power Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 F.2 Annual Radioactive Effluent Release Report (continued)

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the ODCM, pursuant to Technical Specification 6.14, as well as any major change to Liquid and Gaseous Radwaste Treatment Systems pursuant to ODCM, Appendix F, Section F.3. Xt shall also include a listing of new locations for dose calculations and/or environmental identified by the Land Use Census pursuant to Operational Requirementmonitoring 3.12.2.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or effluent monitoring instrumentation was not corrected within the timegaseous in Operational Requirement 3.3.3.10 or 3 '.3.11, respectively; and a specified 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) Rev. 6 Ma'or Chan es to Li uid and Gaseous Radwaste Treatment S part of Specification 6.15) stems'Formerly 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.

Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

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.

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 di'ffer from those previously estimated in the License application and amendments thereto.

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.

An estimate of the exposure to plant operating personnel as a result of the change.

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.

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 tzip 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 CALXBRATZON 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 CALXBRATZON shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

DIGITAL CHANNEL OPERATIONAL TEST A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation to verify OPERABILITY of alarm and/or trip functions.

OSE EQUXVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of X-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, Z-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table IZI of T1D-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

=KCLUSION 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-l.

Sheazon 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 from the primary system and providing for delay or holdup for 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 poztions of the site for recreational, occupational, or other purposes not associated with the plant.

CFFSITE 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 or have OPERABILITY when all necessary it is capable of performing its specified OPERABLE function(s),and when attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that aze required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

CPERATZONAL 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 oz simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.

PURGE - PURGING PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

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 UNRESTRZCTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTZNG shall be the controlled process of discharging air or gas from a confinement'to maintain temperature, pressure, humidity, concentration, oz other operating condition, in such a manner that replacement air or gas is not provided oz required during VENTING. Vent, used in system names, does not imply a VENTING process.

G-3

Sheazon Harris Nuclear Powez Plant (SHNPP) August 1995 Offsite Dose Calculation Manual (ODCM) Rev. 6 TABLE G-l FREQUENCY NOTATZON NOTATXON 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 pez 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor staztup.

N.A. Not applicable.

Completed prior to each release.

Each Surveillance Requirement shall be performed within the specified surveillance

'nterval with a maximum allowable extension not to exceed 25% of the specified 4

uzveillance interval.

~ ~

~ ~ ~ ~

8

~ ~ ~ ~

~ ~ ~ I

~ ~ ~ ~

~ 0 ~ ~

~ ~ - - ~

0 ~ I ~ ~

~ 0 I ~ 0 0 ~ ~ ~

~ ~ I

~

I

~ ~ ~

~ ~

~ 0 ~ ~ 0

f 0

ML18022B014

Text

SUBJECT:

Dear Sir or Madam:

1.0 INTRODUCTION

1.0 INTRODUCTION

Navigation menu

Search