Text

Annual Radioactive Effluent Release Rept for Jan-Dec 1998
	ML18016A933
Person / Time
Site:	Harris
Issue date:	12/31/1998
From:	Bates J, Denise Edwards; CAROLINA POWER & LIGHT CO.
To:	;
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ML18016A932	List: HNP-99-074, Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp; ML18016A933; ML18016A934;
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Carolina Power R Light Shearon Harris Nuclear Power Plant License No. NPF-063 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT January 1, 1998 to December 31, 1998 Prepared by:

Senior Analyst - Chemistry Reviewed by:

Superint dent - Chemistry Approved by:

General Manager

- Harris Plant 9905050090 99'0430 PDR ADQCK 05000400 R

PDR

t-

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.

Effluents Released 3.

Solid Waste Disposal 2/1 2/3 2/12 Appendix 3. Changes to Offsite Dose Calculation Manual (ODCM) 3/1 Appendix 4.

Changes to the Environmental Monitoring Program 1.

Environmental Monitoring Program 2.

Land Use Census 4/1 4/1 Appendix 1.

2.

3.

4.

5. Additional ODCM Operational Requirements Inoperability of Liquid Effluent Monitors Inoperability of Gaseous Effluent Monitors Unprotected Outdoor Tanks Exceeding Limits Gas Storage Tanks Exceeding Limits 5/1 5/2 5/2 5/2 Appendix 6. Major Modifications to Radwaste System Appendix 7. Meteorological Data 6/1 7/1 Appendix 1.

2.

3.

4,

8. Assessment of Radiation Doses Population Doses due to Effluent Releases Doses to the General Public Due to Activities Inside the Site Boundary Doses to Most Likely Exposed Member of the Public Major Assumptions used to Calculate Radiation Doses 8/1 8/2 8/4 8/8 Appendix 9. Correction to the 1997 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 9/1

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,

1998 to December 31, 1998.

During this period, the plant continued in Cycle 8 operation and refueled in October.

Cycle 9 was started in November.

The radiological dose assessment from radioactive releases during January 1,

1998 through December 31, 1998 is in Appendix 8 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.

~ '~

Sources of Radioactivity Released During normal operations of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding.

However, small quantities of radioactive fission and activation products are present in the primary coolant water.

The types of radioactive material released are noble gases, iodines and particulates, and tritium.

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

Small releases of radioactivity in liquids may occur from equipment associated with the primary coolant system.

These liquids are collected and processed for radioactivity removal prior to release.

3.

Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as krypton and xenon.

Noble gases are by nature inert and do not concentrate in humans or other organisms.

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.

Iodines and Particulates Annual releases of iodines, and those particulates with half-lives greater than 8 days are small. Factors such as chemical reactivity and solubility in water, combined with high processing efficiencies, minimize their discharge.

The main contribution of radioactive iodine to human exposure is to the thyroid gland, where the body concentrates iodine.

The principal radioactive particulates are Cobalt-58 and Cobalt-60 which contribute to internal exposure of tissues such as the muscle, liver, and intestines.

These particulates can also be a source of exposure if deposited on the ground.

5.

Tritium Tritium, a radioactive isotope of hydrogen, is the 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 ODCM Operational Requirements 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.

7.

Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material.

The major pathways of concern are those which could cause the highest calculated radiation dose.

The projected pathways are determined fxom 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 factors such as the amount of radioactive material released, the concentration beyond the site boundary, weather conditions at the time of release, locations of exposure

pathways, and usage factors.

The exposures calculated due to radioactive materials released in liquid effluents are calculated using factors such as the total volume of liquid, the total volume of dilution water, and usage factors.

4 1

8.

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

1)

Appendix B.

For the period January 1,

1998 through December 31, 1998 no solid waste was shipped offsite for burial. All radioactive solid waste generated at Harris Nuclear Plant (HNP) 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 8.

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

1998 through December 31, 1998.

During the period of January 1,

1998 through December 31,

1998, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

~

6.04 E-02 millirem, Total Body

~

9.21 E-02 millirem, Max Organ (Liver)

Gaseous Effluents:

~

1.86 E-03 mrad, Beta

~

5.62 E-04 mrad, Gamma 7.68 E-03 mrad, Total Body

~ '.44 E-03 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).

Appendix 1: Supplemental Information I.

Regulatory Limits A. Fission and Activation Gases:

ODCM Operational Requirements Maximum Instantaneous Release Rate Total Body Dose

<500 mrem/yr Skin Dose

<3000 mrem/yr

10CFR20, Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table II, Column 1. This is based on 100 mrem/yr.

10CFRSO, Appendix I For Calendar Quarter Gamma Dose

<5 mrad (Used for calculating percent of applicable limit.)

Beta Dose

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

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

Iodine 131 and 133, Tritium, and Particulates

>8 day half-lives:

ODCM Operational Requirements Maximum Instantaneous Release Rate Inhalation dose (only) to a child to any organ <1500 mrem/yr 10CFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table II, Column 1.

This is based on 50 mrem/yr.

10CFR50, Appendix I (Organ Doses)

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

For Calendar Year <15 mrem C.

Liquids:

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

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

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.

Measurements and Approximations of Total Radioactivity A.

Continuous Gaseous Releases 1.

Fission and activation gases The total activity released is determined from the net activity of gaseous monitors times the total stack flow. The activity of each radionuclide is determined by the fraction of that radioactive gas in the isotopic analysis for that sampling period. 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.

In September of 1998, the concentration of tritium in each batch release times the volume of the batch release was 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 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 de terminations

Appendix 1 (Continued):

Supplemental Information III.

Batch Releases (1998)

A. Liquid Batch Releases Jan

- June 1998 July - Dec 1998 Number of batch releases 1.70 E+Ol 1.90 E+01 Total time period for batch releases 1.13 E+04 minutes 1.41 E+04 minutes Maximum time of a batch release Average time for a batch release Minimum Time for a batch release Average stream flow during periods of release'.53 E+02 minutes 6.64 E+02 minutes 3.47 E+02 minutes 8.97 E+03 cfs 8.91 E+02 minutes 7.45 E+02 minutes 6.18 E+02 minutes 6.47 E+02 cfs

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

B.

Gaseous Batch Releases Jan

- June 1998 July - Dec 1998 Number of batch releases 6.00 E+00 2.00 E+00 Total time period for batch releases 3.78 E+03 minutes 6.55 E+02 minutes Maximum time of a batch release Average time for a batch release Minimum Time for a batch release 8.47 E+02 minutes 6.31 E+02 minutes 3.54 E+02 minutes 5.33 E+02 minutes 3.28 E+02 minutes 1.22 E+02 minutes C.

Abnormal Releases a.

Liquid No abnormal liquid releases were made during 1998.

b.

Gaseous No abnormal gaseous releases were made during 1998.

Appendix 2: Effluent and Waste Disposal Report Enclosure 1

LOWER LIMITS OF DETECTION (LLDs) 1.

LLDs for Gaseous Effluents Gross Alpha H"3 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 I-131 I-133 I-135 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Mo-99 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144

7. 76 E-17 4.74 E-09 1.18 E-08 3.32 E-06 9.02 E-09 2.65 E-08 3.29 E-08 2.25 E-07 1.32 E-08 6.21 E-08 8.26 E-09 1.60 E-08 9.64 E-08 2.47 E-13

1. 13 E-13 2.11 E-12

1. 05 E-12 1.08 E-13 1.05 E-13 2.60 E-13 1.79 E-13 7.95 E-13

3. 84 E-15 1.54 E-15 9'. 89 E" 14 6.02 E-13 2.18 E-12

4. 10 E-13 2.66 E-13 9.33 E-13 2.76 E-13 1.58 E-13 4.99 E-13

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1

LOWER LIMITS OF DETECTION (LLDs) 2.

LLDs for Liquid Effluents Hualis@

Gross Alpha Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Ni-63 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Mo-99 Tc-99m Ru-106 5.49 2.50

4. 91

2. 73 2.79 4.81

4. 12

2. 78 3.34 4.65 3.36 1.47 4.02 8.10 3.47 2.69 3.80 E-08 E-07 E-08 E"08 E-08 E-08 E-08 E-08 E"08 E-08 E-08 E-08 E-08 E-08 E-07 E-08 E-07 Sb-124 Sb-125 Sb-126 I-131 I-133 Te-132 Xe-133 Xe-133m Xe-135 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 7.02 8.82 2.96 2.73 5.61 2.81 6.54 2.25 2.36 2.02

1. 70 4.77 3.49

4. 11 1.68 E-08 E-08 E"08 E-08 E-08 E-08 E-08 E-07 E-08 E-08 E-08 E-08 E-08 E-08 E-07 2/2

Appendix 2 (Continued)t Effluent and Haste Disposal Report Enclosure 2

Effluents Released Table 1A GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES Unit Quarter 1

Quarter 2

Est. Total Error %

A.

Fission and activation ases 1.

Total release 2.

Avera e release rate for eriod 3.

Percent of ODCM 0 erational Re uirement limit Ci Ci/sec 2.19 E+01 2.82 E+00 4.47 E-02 3.58 E+00 4.56 E-01 7.60 E-03 5.27 E+01 B.

lodines 1.

Total iodine-131 2.

Avera o release rate for eriod 3.

Percent of ODCM Operational Requiremont limit'i Ci/sec 0.00 E+00 0.00 E+00 9.86 E-02 0.00 E+00 0.00 E+00 3.05 E-02 3.18 E+01 C.

Particulates 1.

Particulates with half-lives ) 8 da s

2.

Avera e release rate for eriod 3.

Percent of ODCM Operational Requirement limit" Ci Ci/sec 6.37 E-06 8.19 E-07 9.86 E-02 3.31 E-05 4.21 E.06 3.05 E-02 3.37 E+01 4.

Gross al ha radioactivit Ci

< LLD

< LLD D.

Tritium Total release Ci 5.45 E+00 1.51 E+00 5.22 E+01 2.

Avera e release rate for period 3.

Percent of ODCM Operational Requirement limit" Ci/sec 7.01 E-01 9.86 E-02 1.92 E-01 3.05 E.02 The Percent of ODCM Operational Requirement limits applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters.

Tho quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the lung.

4 Sg f

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

Effluents Released Table 1A GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES Unit Quarter 3

Quarter 4

Est. Total Error %

A.

Fission and activation ases 1.

Total release 2.

Avera e release rate for eriod 3.

Percent of ODCM 0 erational Re uirement limit Ci Ci/sec 1.81 E+00 2.28 E-01 3.76 E-03 3.38 E+00 4.25 E.01 6.86 E.03 5.27 E+01 B.

Iodines 1.

Total iodine-131 2.

Avera e release rate for eriod 3.

Percent of ODCM Operational Requirement limit" Ci Ci/sec 0.00 E+00 0.00 E+00 9.45 E-02 0.00 E+00 0.00 E+00 2.48 E-01 3.18 E+01 C.

Particulates 1.

Particulates with half-lives ) 8 da s

2.

Avera e release rate for eriod 3.

Percent of ODCM Operational Requirement limit" Ci Ci/sec 5.19 E-05 6.53 E-06 9.45 E-02 0.00 E+00 0.00 E+00 2.48 E-01 3.37 E+01 4.

Gross al ha radioactivit Ci

< LLD

< LLD D.

Tritium 1.

Total release Ci 4.96 E+00 1.38 E+01 5.22 E+01 2.

Avera e release rate for eriod Ci/sec 6.24 E-01 1.73 E+00 3.

Percent of ODCM Operational Requirement limit" 9.45 E-02 2.48 E.01 The Percent of ODCM Operational Requirement limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters.

The quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the lung.

2/4

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.

2/S

~

V

$ Mt'

A~dix 2 (Continued): Effluent and Waste Dis Report : Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released unit Quarter 1

Quarter 2 Quarter 1

Quarter 2

1. Fission ases xenon 131m xenon-133 xenon-133m xenon.135 xenon-135m xenon-138 ar on.41 Ci Ci Ci Ci Ci Ci Ci

< LLD 2.17 E+01

< LLD

< LLD 3.39 E+00

< LLD

< LLO

< LLD 4.35 E-04

< LLD 2.40 E-05

< LLD

< LLO

< LLD 6.07 E-04

< LLD 2.94 E.05

< LLD

< LLD kr ton.85 Ci

< LLD

< LLD 1.59 E.01 1.88 E.01 kr ton.asm kr ton.87 kr ton.88 Total for eriod Ci Ci Ci Ci

< LLD

< LLD 2.17 E+01

< LLD

< LLO

< LLD 3.39 E+00

< LLD

< LLD 1.59 E-01

< LLD

< LLO 1.89 E-01

2. Iodines iodine-131 iodine-133 iodine-135 Total for cried

3. Particulates Ci Ci Ci Ci

< LLD

< LLO

< LLD Note 1

Note 1

Moto 1 chromium 51 man anese-54 cobalt.58 iron.59 cobalt.60 zinc.65 strontium.89 strontium.90 Ci Ci Ci Ci Ci CI Ci Ci

< LLD

< LLO 6.37 E.06

< LLD

< LLO

< LLD

< LLD 3.31 E-05

< LLD

< LLD Note 1

Mote 1

Note 1

Mote 1

Note 1

niobium 95 Ci

< LLD

< LLD Note 1

Note 1

zirconium.95 mol bdenum.99 Ci Ci

< LLD

< LLD Note 1

Note 1

cesium.134 cesium.137 barium-140 lanthanum.140 cerium.141 cerium-144 Total for cried Ci Ci Ci Ci Ci Ci Ci

< LLD

< LLO

< LLD

< LLO

< LLD 6.37 E.06

< LLD

< LLD 3.31 E-05 Note 1

Note 1

No'te 1 -The particulate and iodine activities released from batch releases are included ln the determinations from the continuous releases.

J P

irma

A dix 2 (Continued): Effluent and Waste Disp Report : Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released

1. Fission gases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 xenon.131m Ci

< LLD

< LLD Note 2 xenon.133 xenon-133m xenon-135 xenon-135m xenon.138 Ci Ci Ci Ci Ci 1.76 E+00

< LLD

< LLD 3.38 E+00

< LLO

< LLD

< LLD 2.56 E-05

< LLO 1.22 E-05

< LLD

< LLD Note 2 Note 2 Note 2 Note 2 Note 2 ar on-41 kr ton 85 Ci Ci

< LLD

< LLO

< LLD

< LLD 5.23 E.02 Note 2 Note 2 kr ton.85m kr ton 87 kr ton.88 Total for eriod Ci Ci Ci Ci

< LLD

< LLO 1.76 E+00

< LLD

< LLD 3.38 E+00

< LLD

< LLD 5.23 E.02 Note 2 Note 2 Note 2 Note 2

2. lodines iodine-131 Ci

< LLD

< LLD Note 1

Note 1

iodine-133 iodine-135 Total for eriod Ci Ci Ci

< LLD

< LLO

< LLD Note 1

Note 1

3. Particu'lates

'hromium-51 Ci

< LLD

< LLD Note 1

Note 1

man anese.54 cobalt 58 Iron Sg cobalt 60 zinc-65 strontium.89 strontium.90 niobium.95 zirconium 95 mol bdenum 99 cesium 134 cesium-137 barium.140 lanthanum-140 cerium.141 cerium.144 Total for eriod Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

< LLD

< LLO

< LLD 5.19 E-05

< LLO

< LLD

< LLO

< LLD

< LLD 5.19 E.05

< LLD

< LLO

< LLD

< LLO

< LLD

<LLO

< LLD

< Li.D

< LLD

< LLO

< LLD

< LLD Note 1

Note 1

Mote 1 Note 1

Note 1

Mote 1 Mote 1 Note 1

Note 1

Mote 1 Note 1

Note 1

Note 1 - The Particulate and iodine activities released from batch releases are included in the determinations from the continuous releases.

Note 2 - No Batch Gaseous Releases were made during the Fourth Quarter.

2/7

Wgf

App 2 (Continued): Effl>ent and Waste Di al Report :

ffluents Released Table 2A: LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES (FIRST SIX MONTHS)

A.

Fission and Activation roducts Unit Quarter 1

Qua~ter Egt. Topi 1.

Total release (not including tritium,

ases, alpha) 2.

Averaqe diluted concentration during enod=

3.

Percent of a Iicable limit B.

Tritium Ci pCi/ml 3.70 E-02 7.16 E-03 3.28 E+01 5.69 E-09 1.02 E-09 5.29 E-01 2.85 E-03 1.

Total release 2.

Avqraqe diluted concentration during penod=

3.

Percent of a licable limit C.

Dissolved and entrained ases 1.

Total release 2.

Avqraqe diluted concentration during pe nod=

3.

Percent of a licable limit D.

Gross alpha radioactivit Ci pCi/ml Ci PCi/ml 1.90 E+02 2.92 E-05 2.92 E+00 8.76 E-05 1.35 E-11 6.75 E-06 7.17 E+01 1.02 E-05 1.02 E+00

< LLD

< LLD 0.00 5 ~ 50 E+01 3.28 E+01 1.

Total release Ci

< LLD

< LLD 3.28 E+01 E.

Volume of waste released (prior to dilution) liters 7.26 E+05 4.26 E+05 2.00 E+01 F.

Volume of dilution water used during period liters 6.50 E+09 7.04E+09 2.00 E+01

I sN

App 2 (Continued): Effl>ant and Waste Di al Report :

ftluents Released Table 2A: LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES (SECOND SIX MONTHS)

A.

Fission and Activation products Unit Quarter Quarter Egt. Topi rfof o

1.

Total release (not including tritium,

ases, alpha) 2.

Averaqe diluted concentration during enod=

3.

Percent of a licable limit B.

Tritium Ci yCI/ml 4.25 E-02 5.31 E-02 3.28 E+01 5.86 E-09 7.06 E-09 1.07 E-01 2.78 E-01 1.

Total release 2.

Avqraqe diluted concentration during enodg 3.

Percent of a licable limit C.

Dissolved and entrained ases Ci 5.63 E+01 7.80 E-01 yCI/ml 7.77 E-06 5.33 E+01 7.08 E-06 7.10 E-01 5.50 E+01 1.

Total release 2.

Average diluted concentration during enocP 3.

Percent of a licable limit D.

Gross alpha radioactivit Ci pCI/ml

< LLD

< LLD 0.00

< LLD

< LLD 0.00 3.28 E+01 1.

Total release Ci

< LLD

< LLD 3.28 E+01 E.

Volume of waste released (prior to dilution) liters 5.22 E+05 8.96 E+05 2.00 E+01 F.

Volume of dilution water used during enod liters 7.25 E+09 7.53 E+09 2.00 E+01

0

~ ~

App 2 (Continued): Effluent and Waste Di al Report : Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1

Quarter 2 Quarter 1

Quarter 2 man anese-54 iron-55 cobalt-57 cobalt-58 iron-59 cobalt-60 nickel-63 zinc-65 strontium-89 strontium.90 zirconium-95 niobium-95 technicium-99m mol bdenum-99 ruthenium-106 antimon -124 antimon -125 antimon -126 tellurium-132 iodine-131 iodine-133 cesium-1 34 cesium-1 37 barium.l 39 barium-140 lanthanum-140 corium-141 corium-144 TOTAL Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Note 1

Note 1

Note 1 ~

Note 1

Mote 1

Note 1

Mote 1

Note 1

1.42 E-04 1.47 E-03

< LLD 2.47 E-04

< LLD 3.08 E.03 1.02 E-03

< LLO

< LLD

< LLO

< LLD

<LLD

<LLD 3.49 E.03

<LLD

< LLD

< LLD 5.03 E.05 1.75 E-04

< LLD

<LLD

< LLO

< LLD

< LLO 9.68 E-03 9.95 E-05 9.47 E-04

< LLD 9.23 E.07

< LLD 2.96 E.03 6.04 E-04

< LLD

< LLD 2.29 E-03

< LLD

< LLD 6.18 E.05 1.81 E-04

< LLD

< LLD 7.14 E-03 Note 1 - AII < LLD xenon-133 xenon.133m xenon-135 TOTAL Note 1 - All < LLD Ci Ci Ci Ci Note 1

Note 1

8.76 E-05

< LLD

< LLD 8.76 E-05

< LLD

< LLO

< LLD

~ ~

endlx 2 (Continued): Effluent and Waste Dispos ort : Effiuents Released Table 2B: LIQUID EFFLUENTS C ninuusM d

Ba ch Mod Nl li e Rol sod hromi lm-61 ni Quar er 4 lief ef 3 LD lr r4 2.48

-03 44 TOTA 4P

-02

.31 Note 1 - All < LLD T TA Note 1 - All < LLD

f

)'i

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3

Solid Waste Disposal Table 3

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS NOTE:

HNP was prohibited from burying or disposing of radioactive solid waste materials at a licensed facility during 1998 with the exception of certain class A wastes.

HNP did not bury any processed solid radioactive waste during 1998.

Consequently, all values reported in Table 3 refer to radioactive solid waste materials processed and returned to HNP, during 1998, for interim storage awaiting future burial.

Table 3 includes Harris Environmental Energy Center (HEEC) solid radioactive wastes processed, commingled with HNP solid radioactive wastes, and returned to HNP during 1998 for interim storage awaiting future burial.

HEEC wastes are noted where applicable.

1.

Solid Waste Shipped for Burial or Disposal

(

WASTE CLASS A )

A. Type of Waste NOTE:

Concerning "Number of Shipments" described in 1.A.a, this shipment was part of the four 1.A.b shipments.

a.

Cartridge/Mechanical Filters (HNP ONLY)

Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 1

2.95 E+01 Ci 96%

8.60 E-01 m'/A NRC-Approved Package Dewatered, Compacted b.

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

(HNP and HEEC)

Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 4

6.55 E-01 Ci 96%'.07 E+01 m'/A NRC-Approved Package Dewatered, Compacted 2/12

0

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3

Solid Waste Disposal Table 3

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1.

Solid Waste Shipped for Burial or Disposal

(

WASTE CLASS A

)

A. Type of Waste 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.

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

Cartridge/Mechanical Filters (HNP ONLY)

Nuclide Percent Composition Total Activity (Ci)

H-3 C-14 Fe-SS Co-60 Ni-63 Sr-90 Cs-137 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-243 2.0 E-03 2.0 E-02 7.6 E+01

1. 9 E+01 4.0 E+00 9.0 E-04 4.0 E-02 4.0 E-04 4.0 E-04 9 '

E-02 3.0 E-04 2.0 E-04 7.0 E-04 5.29 E-04 6.92 E-03 2.26 E+01 5.61 E+00 1.24 E+00 2.93 E-04 1.04 E-02 1.39 E-04 5.32 E-05 2.51 E-02 7.55 E-05 6.73 E-05 2.25 E-04 2/13

t J

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3

Solid Waste Disposal Table 3

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal

(

WASTE CLASS A

)

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

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

(HNP and HEEC)

Nuclide Percent Composition Total Activity (Ci)

Cr-51 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Nb-95 Zr-95 Cs-134 Cs-137 Pu-241 1.0 E+00 3.0 E+00 5.4 E+01 4.0 E+00 2.0 E+01 4.0 E+00 5.0 E+00 3.0 E+00 2.0 E+00 3.0 E+00 1.0 E+00 7.25 E-03 2.24 E-02 3.51 E-01 2.75 E-02

1. 32 E-01 2.59 E-02 3.13 E-02 1.88 E-02 9.93 E-03 1.89 E-02 9.52 E-03 C. Solid Waste Disposal Number of Shipments Mode of Transportation Destination 4

Truck

HNP, New Hill NC (For Storage)

The four type 1.A.a and 1.A.b shipments were made from the GTS/Duratek processing facility in Oak Ridge, Tennessee.

2.

Solid Waste Shipped for Burial or Disposal

(

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.

4.

Irradiated Fuel Shipments (Disposition)

No irradiated fuel was shipped during this Report Period.

2/14

t

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

ODCM Operational Requirement 6.14.c During 1998, the ODCM was revised one time as revision 11.

A description of this revision is listed below.

ODCM Rev.11 Listof Changes Revision 11 to the ODCM incorporates the NGG procedures specific to the collection and analysis of samples specified in the Radiological Environmental Program into the ODCM as implementation procedures for the ODCM. This revision also includes an update to Table 3.2-2 based on the 1998 land use census, removal ofreference 3.11.2.5 (not applicable to the ODCM) from Section 3/4.3.3, and reference 3.11.2.6 in Appendix F.2 was changed to PLP-114, Attachment 5, due to Amendment No. 64 to the Technical Specifications.

ODCM REV. 11 CHANGES Section Title Pa e Pa e

Revised to Rev. 11 Descri tion LEP 1.0 vl, vll Chan ed revision numbers as a ro riate Added Nuclear Generation Group (NGG) procedures for implementation of this manual (ODCM).

Table 3.2-2 3 - 19 Updated the Distance to the nearest Special Locations for the Shearon Harris Power Plant based on the 1997 and 1998 Land Use Census.

3/4.3.3 D-7 In the Operational Requirement 3.3.3.11 removed the reference 3.11.2.5. This reference is in the Tech. Spec., and not an ODCM o erational re uirement.

Appendix F.2 F-4 Changed reference 3.11.2.6 to PLP-114, Attachment 5, in thelastsentenceof the a e.

/~

t t

Appendix 4

Changes to the Environmental Monitoring Program Enclosure 1

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 September

1998, no changes were required to the Environmental Monitoring Program.

Enclosure 2

Land Use Census Offsite Dose Calculation Manual Operational Requirements 3.12.2.a and 3.12.2.b The land-use census that was completed in September 1998 resulted in no changes to the Environmental Monitoring Program.

The ODCM was revised reflecting the lastest annual land-use census.

t t

Appendix 5

Additional ODCM Operational Requirements : Inoperability of Liquid Effluent Monitors ODCM Operational Requirement 3.3.3.10, Action b Monitors Out-of-Service

> 30 Days During this Report Period Radioactivity Monitors Providing Alarms and Automatic Termination of Release 1.

REM-01MD-3528 REM-01MD-3528, Turbine Building Drains Radiation Monitor, was made inoperable on 8/18/98 and was inoperable for greater than 30 days due to noise problems experienced with the new adjacent to line monitors.

ESR 97-00248 modified REM-01MD-3528 to resolve sample flow problems.

It was converted from an off-line sampling radiation monitor to an adjacent to line type radiation monitor.

This ESR was completed in

December, 1997, and while the sample flow problems were resolved, the new adjacent to line detector was found to be very sensitive to noise.

The monitor was declared inoperable on 8/18/98.

Extensive trouble-shooting was performed by engineering and maintenance using guidance provided by the radiation monitoring vendor.

The noise problems were unable to be resolved, and another design change was implemented.

ESR 97-00216 was initiated to provide a noise reject feature in the radiation monitor's firmware.

This had to be ordered from the radiation monitoring vendor and carried a long lead time.

The ESR was installed on 1/18/99.

REM-01MD-3528 was returned to service on 1/19/99.

2.

REM-21WS-3542 REM-21WS-3542, Secondary Waste Sample Tank Radiation Monitor, was made inoperable on 10/27/98 and was inoperable for greater than 30 days due to a clearance on the normal service water supply to the radiation monitor's heat exchanger.

The clearance was due to a leaking service water line.

The line was repaired and the clearance lifted on 11/19/98.

At that time the 18 month calibration was started on the monitor.

The calibration was field completed on 11/23/98.

The monitor was functional at this time but was not needed for a discharge.

The monitor was declared operable on 11/28/98.

Appendix 5

Additional ODCM Operational Requirements (continued)

Enclosure 2

Inoperability of Gaseous Effluent Monitors 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 1998 per the Condition Reporting Process.

None were inoperable for greater than 30 continuous days during this report period.

Enclosure 3

Unprotected Outdoor Tanks Exceeding Limits ODCM Operational Requirement 3.11.1.4, Action a No unprotected outdoor tank exceeded the ODCM Operational Requirement limit during this report period.

Enclosure 4

Gas Storage Tanks Exceeding Limits ODCM Operational Requirement 3.11.2.6, Action a No gas storage tank exceeded the ODCM Operational Requirement limit during this report period.

5/2

Appendix 6

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

Appendix 7

Meteorological Data ODCM Operational Requirement F.2 As allowed by the Footnote to Operational Requirement F.2, the annual summary of meteorological data will be retained electronically on file at Corporate headquarters.

This data will be provided to the NRC upon request.

~ '

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 1: Population Doses Due to Effluent Releases

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

A. 50 mile Ingestion Zone Sport Pish Com Pish Sport Invert Corn Invert Drinking Water Shoreline Swimming Boating Irri Veg Irri Leafy Veg Zrri Milk Zrri Meat All Pathways Bone 4.85 E-02 0.00 E+00

'0.00 E+00 0.00 E+00 1.93 E-02 4.57 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00

1. 14 E-01 Liver 5.11 E-02 0.00 E+00 0.00 E+00 0.00 E+00 6.73 E-01 4.57 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 7.70 E-01 T. Body 3.28 E-02 0.00 E+00 0.00 E+00 0.00 E+00 6.73 E-01 4.57 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 7.52 E-01 Thyroid 7.57 E-03 0.00 E+00 0.00 E+00 0.00 E+00 6.68 E-01 4.57 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 7.22 E-01 Kidney 2.10 E-02 0.00 E+00 0.00 E+00 0.00 E+00 6.68 E-01 5.47 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 7.36 E-01 Lung 1.30 E-02 0.00 E+00 0.00 E+00 0.00 E+00 6.68 E-01 5.47 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 K+00 0.00 E+00 7.29 E-01 GZ-LLI 2.56 E-02 0.00 E+00 0.00 E+00 0.00 E+00 6.94 E-01 4.57 E-02 2.34 E-04 1.18 E-04 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 7.65 E-01 Skin 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 5.37 E-02 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 5.37 E-02 Total B. Tritium (Hydrosphere)

Bone 0.00 E+00 Liver 4.97 E-03 T. Body 4.97 E-03 Thyroid 4.97 E-03 Kidney 4.97 E-03 Lung 4.97 E-03 GZ-LLZ 4.97 E-03

2. Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone Plume Ground Plane Inhalation Vegetation Cow Milk Meat

& Poultry T. Body 7.05 E-03 1.66 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.94 E-03 9.16 E-02 GI-LLI 7.05 E-03 1.66 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.97 E-03 9.17 E-02 Bone 7.05 E-03 1.66 E-03 0.00 E-OO 0.00 E-00 0.00 E-00 0.00 E-00 8.71 E-03 Liver 7.05 E-03 1.66 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.94 E-03 9.16 E-02 Kidney 7.05 E-03 1.66 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.94 E-03 9.16 E-02 Thyroid 7.05 E-03 1.66 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.94 E-03 9.16 E-02 Lung 7.57 E-03 1.66 E-03 5.57 E-02 1.72 E-02 3.72 E-03 6.94 E-03 9.27 E-02 Skin 2.53 E-02 1.95 E-03 5.51 E-02 1.72 E-02 3.72 E-03 6.94 E-03 1.10 E-01

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary

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

ADULT Fish Drinking Shoreline Boating Bone 2.51 E-02 1.90 E-06 7.96 E-03 1.06 E-04 3.32 E-02 Liver 2.88 E-02 8.60 E-05 7.96 E-03 1.06 E-04 3.70 E-02 T. Body 2.13 E-02 8.59 E-05 7.96 E-03 1.06 E-04 2.94 E-02 Thyroid 4.59 E-03 8.54 E-05 7.96 E-03 1.06 E-04 1.27 E-02 Kidney 1.21 E-02 8.55 E-05 7.96 E-03 1.06 E-04 2.03 E-02 7.51 E-03 8.55 E-05 7.96 E-03 1.06 E-04 1.57 E-02 GI-LLI 1.68 E-02 8.92 E-05 7.96 E-03 1.06 E-04 2.49 E-02 Skin 9.34 E-03 9.34 E-03 TEEN Fish Drinking Shoreline Boating TOTAL 2.78 E-02 2.60 E-06 6.63 E-03 1.06 E-04 3.45 E-02

~ 3.01 E-02 8.70 E-05 6.63 E-03 1.06 E-04 3.69 E-02 1.42 E-02 8.69 E-05 6.63 E-03 1.06 E-04 2.11 E-02 3.71 E-03 8.62 E-05 6.63 E-03 1.06 E-04 1.05 E-02 1.19 E-02 8.63 E-05 6.63 E-03 1.06 E-04 1.87 E-02 7.42 E-03 8.64 E-OS 6.63 E-03 1.06 E-04 1.42 E-02 1.27 E-02 8.98 E-05 6.63 E-03 1.06 E-04 1.95 E-02 7.78 E-03 7.78 E-03 CHILD Fish Drinking Shoreline Boating TOTAL 4.11 E-02 7.86 E-06 3.32 E-03 1.06 E-04 4.46 E-02 3.10 E-02 1.67 E-04 3.32 E-03 1.06 E-04 3.46 E-02 9.67 E-03 1.67 E-04 3.32 E-03 1.06 E-04 1.33 E-02 3.55 E-03 1.65 E-04 3.32 E-03 1.06 E-04 7.14 E-03 1.17 E-02 1.65 E-04 3.32 E-03 1.06 E-04 1.53 E-02 7.03 E-03 1.66 E-04 3.32 E-03 1.06 E-04 1.06 E-02 7.23 E-03 1.68 E-04 3.32 E-03 1.06 E-04 1.08 E-02 3.89 E-03 3.89 E-03 8/2

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary (Continued)

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

ADULT Plume Ground Plane Inhalation TOTAL T. Body 2.26 E-04 1.65 E-04 1.18 E-03 1.57 E-03 GZ-LLZ 2.26 E-04 1.65 E-04 1.18 E-03 1.57 E-03 Bone 2.26 E-04 1.65 E-04 0.00 B-OO 3.90 E-04 Iiver 2.26 E-04 1.65 E-04 1.18 E-03 1.57 E-03 Kidney 2.26 E-04 1.65 B-04 1.18 E-03 1.57 E-03 Thyroid 2.26 E-04 1.65 E-04 1.18 B-03 1.57 E-03 Lung 2.38 E-04 1.65 E-04 1.20 E-03 1.60 E-03 Skin 7.04 E-04 1.94 E-04

1. 18 E-03 2.08 E-03 TEENAGER Plurne Ground Plane Inhalation TOTAL 2.26 E-04 1.65 E-04 1.19 E-03 1.58 E-03 2.26 E-04 1.65 E-04 1.19 E-03 1.58 E-03 2.26 E-04 1.65 E-04 0.00 E-00 3.90 E-04 2.26 E-04 1.65 E-04 1.19 E-03 1.58 E-03 2.26 E-04 1.65 E-04 1.19 E-03 1.58 E-03 2.26 E-04 1.65 E-04 1.19 E-03 1.58 B-03 2.38 E-04 1.65 E-04 1.21 E-03 1.62 E-03 7.04 E-04 1.94 E-04

1. 19 E-03 2.08 E-03 CHILD Plume Ground Plane Inhalation TOTAL 2.26 E-04 1.65 E-04 1.05 B-03 1.44 E-03 2.26 E-04 1.65 E-04 1.05 E-03 1.44 E-03 2.26 E-04 1.65 E-04 0.00 E-00 3.90 E-04 2.26 E-04 1.65 E-04 1.05 E-03 1.44 E-03 2.26 E-04 1.65 E-04 1.05 E-03 1.44 E-03 2.26 E-04 1.65 E-04 1.05 E-03 1.44 E-03 2.38 E-04 1.65 E-04 1.07 E-03 1.47 E-03 7.04 B-04 1.94 E-04 1.05 E-03 1.95 E-03 8/3

l

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 3: Doses to Most Likely Exposed Member of the Public

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

ADULT Pish Drinking Shoreline Swimming Boating TOTAL Bone 5.27 E-02 1.39 E-04 4.77 E-03 2.55 E-04 2.92 E-04 5.82 E-02 Liver 6.06 E-02 6.28 E-03 4.77 E-03 2.55 E-04 2.92 E-04 7.22 E-02 T. Body 4.47 E-02 6.27 E-03 4.77 E-03 2.55 E-04 2.92 E-04 5.63 E-02 Thyroid 9.64 E-03 6.23 E-03 4.77 E-03 2.55 E-04 2.92 E-04 2.12 E-02 Kidney 2.55 E-02 6.24 E-03 4.77 E-03 2.55 E-04 2.92 E-04 3.70 E-02 Iung 1.58 E-02 6.24 E-03 4.77 E-03 2.55 E-04 2.92 E-04 2.73 E-02 Qi-LLI 3.52 E-02 6.51 E-03 4.77 E-03 2.55 E-04 2.92 E-04 4.71 E-02 Skin 5.60 E-03 5.60 E-03 TEEN Pish Drinking Shoreline Swimming Boating TOTAL 5.56 E-02 1.32 E-04 2.67 E-02 3.83 E-04 4.25 E-04 8.32 E-02 6.02 E-02 4.44 E-03 2.67 E-02 3.83 E-04 4.25 E-04 9.21 E-02 2.85 E-02 4.43 E-03 2.67 E-02 3.83 E-04 4.25 E-04 6.04 E-02 7.41 E-03 4.40 E-03 2.67 E-02 3.83 E-04 4.25 E-04 3.93 E-02 2.38 E-02 4.40 E-03 2.67 E-02 3.83 E-04 4.25 E-04 5.57 E-02 1.48 E-02 4.41 E-03 2.67 E-02 3.83 E-04 4.25 E-04 4.67 E-02 2.54 E-02 4.58 E-03 2.67 E-02 3.83 E-04 4.25 E-04 5.74 E-02 3.13 E-02 3.13 E-02 CHILD Fish Drinking Shoreline Swimming Boating TOTAL 7.09 E-02 4.01 E-04 5.57 E-03 1.28 E-04 1.60 E-04 7.72 E-02 5.35 E-02 8.50 E-03 5.57 E-03 1.28 E-04 1.60 E-04 6.79 E-02 1.67 E-02 8.50 E-03 5.57 E-03 1.28 E-04 1.60 E-04 3.10 E-02 6.)2 E-03 8.42 E-03 5.57 E-03 1.28 E-04 1.60 E-04 2.04 E-02 2.02 E-02 8.43 E-03 5.57 E-03 1.28 E-04 1.60 E-04 3.45 E-02 1.21 E-02 8.44 E-03 5.57 E-03 1.28 E-04 1.60 E-04 2.64 E-02 1.25 E-02 8.57 E-03 5.57 E-03 1.28 E-04 1.60 E-04 2.69 E-02 6.54 E-03 6.54 E-03 INFANT Fish Drinking Shoreline 0.00 E+00 3.19 E-04 0.00 E+00 3.19 E-04 0.00 E+00 8.36 E-03 0.00 Et00 8.36 E-03 0.00 E+00 8.34 E-03 0.00 E+00 8.34 E-03 0.00 E+00 8.26 E-03 0.00 E+00 8.26 E-03 0.00 E+00 8.27 E-03 0.00 E+00 8.27 E-03 0.00 E+00 8.29 E-03 0.00 E+00 8.29 E-03 0.00 E+00 8.35 E-03 0.00 E+00 8.35 E-03 0.00 E+00 0.00 E+00 8/4

I C

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses : Doses to Most Likely Exposed Member of the Public

2. Individual Dose Due to Gaseous Effluents tmrem/yr.)

A. Maximum Hypothetical Zndividual - Exposure from Noble Gases, Particulates,

Zodines, and Tritium ADULT Plume Ground Plane Inhalation Vegetation Cow Milk Meat

& Poultry TEENAGER Plume Ground Plane Inhalation Vegetation Cow Milk Meat a Poultry TOTAL CHILD Plume Ground Plane Inhalation Vegetation Cow Milk Meat a Poultry TOTAL INFANT Plume Ground Plane Inhalation Cow Milk T. Body 1.57 E-03 7.39 B-04 8.25 E-03 1.40 E-02 3.32 E-03 1.41 E-03 2.93 E-02 1.57 E-03 7.39 E-04 8.30 E-03 1.65 E-02 4.32 E-03 8.44 E-04 3.23 E-02 1.57 E-03 7.39 E-04 7.34 E-03 2.58 E-02 6.83 E-03 1.02 E-03 4.33 E-02 1.57 E-03 7.39 E-04 4.22 E-03 1.04 E-02 1.69 E-02 GZ-LLI 1.57 E-03 7.39 E-04 8'5 E-03 1.41 E-02 3.32 E-03 1.43 E-03 2.94 E-02 1.57 B-03 7.39 E-04 8.31 E-03 1.66 E-02 4.32 E-03 8.52 E-04 3.24 E-02 1.57 E-03 7.39 E-04 7.34 E-03 2.58 E-02 6.83 E-03 1.02 E-03 4.33 E-02 1.57 E-03 7.39 E-04 4.22 E-03 1.04 E-02 1.69 E-02 Bone 1.57 E-03 7.39 E-04 0.00 E-OO 0.00 E-OO 0.00 E-00 0.00 E-00 2.31 E-03 1.57 E-03 7.39 E-04 0.00 E-OO 0.00 E-00 0.00 E-00 0.00 E-00 2.31 E-03 1.57 E-03 7.39 E-04 0.00 E-OO 0.00 E-00 0.00 E-OO 0.00 E-00 2.31 E-03 1.57 E-03 7.39 E-04 0.00 E-OO 0.00 B-OO 2.31 E-03 Liver 1.57 E-03 7.39 E-04 8.25 E-03 1.40 E-02 3.32 E-03 1.41 E-03 2.93 E-02 1.57 E-03 7.39 E-04 8.30 E-03 1.65 E-02 4.32 E-03 8.43 E-04 3.23 E-02 1.57 E-03 7.39 E-04 7.34 E-03 2.57 E-02 6.83 E-03 1.02 E-03 4.32 E-02 1.57 E-03 7.39 E-04 4.22 E-03 1.04 E-02 1.69 E-02 Kidney 1.57 E-03 7.39 E-04 8.25 E-03 1.40 E-02 3.32 E-03 1.41 E-03 2.93 E-02 1.57 E-03 7.39 E-04 8.30 E-03 1.65 E-02 4.32 E-03 8.43 E-04 3.22 E-02 1.57 E-03 7.39 E-04 7.34 E-03 2.57 E-02 6.83 E-03 1.02 E-03 4.32 E-02 1.57 E-03 7.39 E-04 4.22 E-03 1.04 E-02 1.69 E-02 Thyroid 1.57 E-03 7.39 E-04 8.25 E-03 1.40 E-02 3.32 E-03 1.41 E-03 2.93 E-02 1.57 E-03 7.39 E-04 8.30 E-03 1.65 E-02 4.32 E-03 8.43 E-04 3.22 E-02 1.57 E-03 7.39 E-04 7.34 E-03 2.57 E-02 6.83 E-03 1.02 E-03 4.32 E-02 1.57 E-03 7.39 E-04 4.22 E-03 1.04 E-02 1.69 E-02 Lung 1.65 E-03 7.39 E-04 8.37 E-03 1.40 E-02 3.32 E-03 1.41 E-03 2.95 E-02 1.65 B-03 7.39 E-04 8.47 E-03 1.65 E-02 4.32 E-03 8.43 E-04 3.25 E-02 1.65 E-03 7.39 E-04 7.48 E-03 2.57 E-02 6.83 E-03 1.02 E-03 4.34 E-02 1.65 E-03 7.39 E-04 4.31 E-03 1.04 E-02 1.71 E-02 Skin 4.57 E-03 8.70 E-04 8.25 E-03 1.40 E-02 3.32 E-03 1.41 E-03 3.24 E-02 4.57 E-03 8.70 E-04 8.30 E-03 1.65 E-02 4.32 E-03 S.43 E-04 3.54 E-02 4.57 E-03 8.70 E-04 7.34 E-03 2.57 E-02 6.83 E-03 1.02 E-03 4.63 E-02 4.57 E-03 8.70 E-04 4.22 E-03 1.04 E-02 2.00 E-02 s/5

I

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 3: Doses to Most Likely Exposed Member of the Public

2. Individual Dose Due to Gaseous Effluents tmrem/yr.)

B. Maximum Real Individual - Exposure from Noble Gases, Particulates,

Iodines, and Tritium ADULT Plume Ground Plane Inhalation Vegetation Meat

& Poultry T. Body 3.28 8-04 2.44 8-04 1.72 8-03 2.92 8-03 2.95 8-04 5.51 8-03 GI-LLI 3.28 8-04 2.44 E-04 1.72 8-03 2.95 E-03 3.00 8-04 5.54 8-03 Bone 3.28 E-04 2.44 8-04 0.00 8-00 0.00 E-00 0.00 E-00 5.72 8-04 Liver 3.28 E-04 2.'44 8-04 1.72 E-03 2.92 8-03 2.94 8-04 5.50 E-03 Eidney 3.28 E-04 2.44 E-04 1.72 8-03 2.92 E-03 2.94 8-04 5.50 E-03 Thyroid 3.28 E-04 2.44 8-04 1.72 8-03 2.92 E-03 2.94 E-04 5.50 E-03 Lung 3.46 E-04 2.44 E-04 1.74 E-03 2.92 E-03 2.94 8-04 5.54 E-03 Skin 1.06 E-03 2.87 E-04 1.72 8-03 2.92 8-03 2.94 E-04 6.27 8-03 TEENAGER Plume Ground Plane Inhalation Vegetation Meat

& Poultry CHILD Plume Ground Plane Inhalation Vegetation Heat

& Puoltry TOTAL INFANT Plume Ground Plane Inhalation 3.28 8-04 2.44 8-04 1.73 8-03 3.43 8-03 1.76 8-04 5.91 E-03 3.28 8-04 8-04 1.53 8-03 5.37 8-03 2.13 8-04 7.68 8-03 3.28 E-04 2.44 E-04 8.79 E-04 1.45 8-03 3.28 E-04 2.44 8-04 1.73 E-03 3.46 E-03 1.78 8-04 5.94 8-03 3.28 E-04 2.44 E-04 1.53 E-03 5.38 E-03 2.13 E-04 7.69 8-03 3.28 E-04 2.44 E-04 8.79 E-04 1.45 8-03 3.28 8-04 2.44 E-04 0.00 8-00 0.00 8-00 0.00 8-00 5.72 E-04 3.28 E-04 2.44 E-04 0.00 E-OO 0.00 E-00 0.00 8-00 5.72 E-04 3.28 8-04 2.44 8-04 0.00 E-00 5.72 8-04 3.28 8-04 2.44 8-04 1.73 E-03 3.43 E-03 1.76 E-04 5.91 E-03 3.28 E-04 2.44 E-04 1.53 E-03 5.35 E-03 2.12 E-04 7.67 E-03 3.28 E-04 2.44 E-04 8.79 8-04 1.45 8-03 3.28 E-04 2.44 E-04 1.73 8-03 3.43 E-03 1.75 8-04 5.90 8-03 3.28 E-04 2.44 E-04 1.53 E-03 5.35 8-03 2.12 E-04 7.67 8-03 3.28 8-04 2.44 8-04 8.79 E-04 1.45 8-03 3.28 8-04 2.44 E-04 1.73 8-03 3.43 8-03 1.75 E-04 5.90 8-03 3.28 8-04 2.44 8-04 1.53 E-03 5.35 8-03 2.12 E-04 7.67 E-03 3.28 8-04 2.44 E-04 8.79 E-04 1.45 8-03 3.46 8-04 2.44 8-04 1.76 E-03 3.43 8-03 1.75 E-04 5.96 E-03 3.46 8-04 2.44 8-04 1.56 8-03 5.35 E-03 2.12 8-04 7.71 E-03 3.46 8-04 2.44 8-04 8.97 8-04 1.49 8-03 1.06 E-03 2.87 E-04 1.73 E-03 3.43 8-03 1.75 8-04 6.67 8-03 1.06 E-03 2.87 8-04 1.53 E-03 5.35 E-03 2.12 8-04 8.44 E-03 1.06 8-03 2.87 E-04 8.79 E-04 2.22 E-03 8/6

~ I

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses

3. Annual Air Dose (mrad)

Enclosure 3: Doses to Most Likely Exposed Member of the Public A. Maximum Hypothetical Individual:

B. Maximum Real Individual:

Beta

~

8.21 E-03 Beta

=

1.86 E-03 Gamma

~ 2.69 E-03 Gamma a 5.62 E-04

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.

e ~

.~

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 4

Ma)or Assumptions Used to Calculate Radiation Doses

1. Doses Due to Liquid Effluents A.

Dilution Factors Location Harris Lake Cape Fear River Cape Fear River/

Raven Rock Park Value 1.00 E+00 5.97 E+01+

5.97 E+01>>

Exposure Pathways Shoreline, Swimming, Boating, Fish Consumption Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Boating The dilution of 5.97 E+01 is calculated using the average flow of the Buckhorn Creek (measured at the gauging station at Corinth, N.C.)

which is the blowdown of Harris Lake (80.47 CFS) and the average flow of the Cape Fear River (480I.7 CFS) as measured at the gauging station at Lillington, N.C. The above information was provided by the United States Geological Service for 1998.

B.

Populations Affected Location Value Exposure Pathways Harris Lake Harnett County Dunn Zntake Fayetteville Area Fuquay-Varina Holly Springs Harris Lake/

Cape Fear River Cape Fear River/

Raven Rock Park Raven Rock Park 1.10 E+05 person-hours 4.52 E+04 persons 1.67 E+04 persons 1.40 E+05 persons 2.68 E+03 persons 2.27 E+02 persons Shoreline, Swimming, Boating Drinking Water Drinking Water Drinking Water Drinking Water Drinking Water 5.00 E+04 person-hours 4.40 E+05 person-hours Boating Shoreline 7.84 E+03 person-hours Fishing C.

The doses from liquid effluents for "Activities Inside the Site Boundary" use the Cape Fear River as the Drinking Water supply year d

and Harris Lake on site using the following assumptions:

Pathwa Usa e

Adult Teen Child Fish 10 Shoreline hr/

12 10 Boatin hr/

100 Drinkin Water 10 10 10 8/8

~

(

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 8: Assessment of Radiation Doses Enclosure 4 (Continued): Major Assumptions Used to Calculate Radiation Doses

2. Doses Due to Gaseous Effluents A.

The 50 mile Zngestion Zone population is 1.68 E+06 persons.

B.

The Maximum Real Zndividual is located at 2897 meters

(-2.8 miles) in the ENE sector.

This is based on the 1998 land use census with applicable pathways.

C.

The Maximum Hypothetical Zndividual is located on the site boundary at 2140 meters in the SSN sector.

D.

The dose calculations for the Znside 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 Hours/year Boating 100 Swimming 100 Pishing'80 Other" 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 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s/day for hiking, bird watching, a etc.

equals 196 hours0.00227 days 0.0544 hours 3.240741e-4 weeks 7.4578e-5 months .

E.

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

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

8/9

Annual Radioactive Effluent Release Report January 1,

1998 to December 31, 1998 Appendix 9: Correction to the 1997 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The attached page is a correction to the 1997 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT, Appendix 5,Enclosure 1,

Page 5/1.

This section stated that a corrective action via CR 9702983 was written to change the ODCM.and the sampling. procedure, LS-ER-31.

This statement was incorrect because no coxrective action was written to change LS-ER-31.

However, the sampling procedure was changed on October 1,

1998, when LS-ER-31 was converted to EVC-NGGC-000g3, Rev.

0.

0 e'

Appendix 5: Changes to the Environmental Monitoring Program : Environmental Monit rin Pro ram Operational Requirement

.12.1.c As a result of the annual. land-use census which was performed during September 199?, no changes were required to the Environmental Sampling Proqram or to.the ODCM. however, on Wlay 19,1997 frigg the time for the rpufiny milk 4.p mpi'mpling was to be. collected the technician was notitied that The Maple Kmoll uairy had gone out ot buSiness.

gmpensatqry sampling

( samp)es of three different kinds ot broad Ieaf vegqtation groyvn pearest each of twq ditferqnt 02 3) pfsite locations ot highest predicted annual average ground level l3/U) was imediately inst tutee and a Corrective Action R-9702983) was written to change the ODGM which was completed on December 1($

1987.

Vbe sampling procedure was changed when LS-R-31 was converted to EVC-NGGC-0003, Rev.0, on October 1, 1998.

Enc osure 2: Land Use Census I

Operational Requirements 3.1

.2.a and 3.12.2.b he.land-use census tl)at was completed in September, 1997, resulted in no changes to the ODCM or to the nvironmental Monitonng Program.

fe r

~

4

ML18016A933

Text

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