ML18016A412

Annual Radioactive Effluent Release Rept for Jan-Dec 1997.

ML18016A412
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Site:	Harris
Issue date:	12/31/1997
From:	CAROLINA POWER & LIGHT CO.
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ML18016A410	List: ML18016A409 ML18016A412 ML18016A413
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,Carolina Power 8c Light Shearon Harris Nuclear Power Plant License No. NPF-063 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 1997 to December 31, 1997 Prepared by Senior Analyst - Chemistry Reviewed by uperintenden Chemistry Reviewed by:

Manag - E5 Approved by: (

General Manager - Harris Plant 9aoioeoo77 9aocso fl pDR ADQGK 05000400 R PORE

Table of Contents Page No.

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

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

2. Effluents Released 2/3

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

1. Environmental Monitoring Program 5/1

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

1. Inoperability of Liquid Effluent Monitors 6/1 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, 1997 to December 31, 1997. The radiological dose assessment from radioactive releases during January 1, 1997 through December 31, 1997 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.

3. Noble Gas Some of the fission p ro ducts released in airborne effluents n s are ra isoto e of noble gases, ioactive isotopes radioactive such as krypton, argon, and xenon. N incr an o not concentrate in humans or other organisms.'sms. Their eir contribution to human radiation i n exposure ex is as an external exposure. Xenon-133 an and Xenon-135 with half-lives of a ro 'po y y e e major isotopes released. Half-life e ined as the time required for a

- i e is defined radioactive isotope to loseose 50 percent of its radioactivit ivi y b y decaecay. . Noble gases are readily dispersed in the atmosphere.

lodines and Particulates

'odines, and those particulates with Annual releases of iodines i - i s greater than 8 days are small.

half-live as c emical reactivity and solubility in water,, corn combine ined with high processing eir isc arge. The main contribution oof radioactive iodine to human exposure is to thee th yroi roid gland, I where the body concentrates iodine. The rti I t Cob It-58 an d Cob o alt-60 It-60 which contribute to internal exposureex of tissues such as the muscle, liver, and intest' es ines. Th ese particulates can also so be a source of exposure if deposited on the ground.

5. Tritium Tritium, a radioactive isoto p e oof hhydrogen, is the predominate radionuclideionuc i e in liquid li and gaseous effluents. Tritium is produceduce in tthee reactor coolant as a result of neu ron interaction with neutron isoto e'nd (also a hydrogenn isotope) and boron, b both of which are p resen ent in the primary coolant.

'euterium Tritium contributes very little i e raradiiation exposure to the human bod, and w di d ho roug hoout theh bbody until eliminated.

Cl 0

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 Technical Specification requirements, (typically at less than 50 percent) 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 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 plarits 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.

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, 1997 through December 31, 1997 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, 1997 through December 31, 1997.

During the period of January 1, 1997 through December 31, 1997, the estimated maximum individual offsite dose due to radioactivity released in effluents was:

Liquid Effluents:

~ 3.50 E-02 millirem, Total Body

~ 4.46 E-02 millirem, Max Organ (Liver)

Gaseous Effluents:

~ 2.58 E-03 mrad, Beta ~ 4.02 E-03 millirem, Total Body

~ 1.04 E-03 mrad, Gamma ~ 5.29 E-03 millirem, Skin These doses are much lower than anyone would have received from natural background in the area surrounding the Harris Nuclear Plant (300 millirem per year).

, A. Fission and Activation Gases:

Appendix 1: Supplemental Information Technical Specifications Maximum Instantaneous Release Rate Total Body Dose s 600 mrem/yr Skin Dose s 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 5 mrad (Used for calculating percent of applicable limit.)

Beta Dose c 10 mrad (Used for calculating percent of applicable limit.)

For Calendar Year Gamma Dose c 10 mrad Beta Dose c 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 s 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 z 7.5 mrem (Used for calculating percent of applicable limit.)

For Calendar Year c 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 c 1.5 mrem Any Organ Dose s 6 mrem For Calendar Year Total Body Dose s 3 mrem Any Organ Dose s 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 136 is based on isotopic analysis of the charcoal cartridge plus the particulate filter times the total vent flow for each sample period (typically weekly).

3. Particulates The activity released as particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters times the total vent flow for each sample period (minimum weekly or more frequently if plant conditions requires it).

4. Tritium 1

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: Supplemental Information (Continued)

A. Liquid Batch Releases Jan - June 1997 Jul - Dec 1997 Number of batch releases 2.50 E+01 2.30 E+01 Total time eriod for batch releases 1.94 E+04 minutes 1.74 E+ 04 minutes Maximum time of a batch release 1.04 E+03 minutes 8.77 E+02 minutes Avera e time for a batch release 7.76 E+02 minutes 7.55 E+02 minutes Minimum Time for a batch release 4.32 E+02 minutes 6.20 E+02 minutes Average stream flow during periods of 4.57 E+03 cfs 1.56 E+03 cfs release

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

B. Gaseous Batch Releases Jan - June 1997 July - Dec 1997 Number of batch releases 1.30 E+01 4.00 E+00 Total time period for batch releases 3.67 E+04 minutes 3.56 E+03 minutes Maximum time of a batch release 2.85 E+04 minutes 1.66 E+03 minutes Avera e time for a batch release 2.82 E+03 minutes 8.91 E+02 minutes Minimum Time for a batch release 2.00 E+01 minutes 1.00 E+00 minutes C. Abnormal Releases

a. Liquid No abnormal liquid releases were made during 1997.

b. Gaseous One abnormal gaseous release was made during 1997. Reactor Auxiliary Building (RAB) had positive pressure from February 26, 1997 520:00 hours through March 18, 1997

@14:50 hours. This was presented to the PNSC and based on the evaluation the results are as follows:

Curies released: 1) 1.79 E-03 Ci of noble gas

2) No iodines or particulates were released Offsite Dose: Total Body: 1.02 E-07 mrem Skin: 2.40 E-07 mrem Gamma Air Dose: 1.22 E-07 mrad Beta Air Dose: 3.63 E-07 mrad

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

1. LLDs for Gaseous Effluents

~tub Gross Alpha

~I~

9.27 E-16 H-3 6.65 E-09 Ar-41 :1.10 E-08 Kr-85 3.17 E-06 Kr-85m 1.01 E-08 Kr-87 2.33 E-08 Kr-88 3.13 E-08 Xe-131m 2.78 E-07 Xe-133 1.12 E-08 Xe-133m 7.97 E-08 Xe-135 9.42 E-09 Xe-135m 1.77 E-08 Xe-138 1.15 E-07 I-131 2.09 E-13 l-133 1.23 E-13 l-135 6.00 E-12 Cr-51 5.16 E-13 Mn-54 1.44 E-13 Co-58 5.16 E-14 Fe-59 1.28 E-13 Co-60 8.77 E-14 Zn-65 1.43 E-13 Sr-89 3.52 E-15 Sr-90 1.62 E-15 Nb-95 1.32 E-13 Zr-95 8.60 E-'l4 Mo-99 4.13 E-13 Cs-134 5.85 E-14 Cs-137 4.79 E-14 Ba-140 3.63 E-13 La-140 3.25 E-13 Ce-141 7.77 E-14 Ce-144 3.75 E-13

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 1: LOWER LIMITS OF DETECTION (LLDs)

2. LLDs for Liquid Effluents

~lhh aLrrml Gross Alpha 9.18 E-08 Cr-51 3.29 E-07 Mn-54 1.81 E-08 Fe-55 2.72 E-08 Co-57 2.08 E-08 Co-58 2.61 E-08 Fe-59 1.12 E-07 Co-60 9.53 E-08 Ni-63 3.48 E-08 Zn-65 4.65 E-08 Sr-89 2.85 E-08 Sr-90 1.35 E-08 Nb-95 5.73 E-08 Zr-95 8.00 E-08 Mo-99 3.47 E-07 Tc-99m 2.14 E-08 Ru-106 3. 80 'E-07 Sb-124 7.02 E-08 Sb-125 1.03 E-07 Sb-126 3.00 E-08 I-131 3.45 E-08 l-133 1.41 E-08 Te-132 2.96 E-08 Xe-133 7.54 E-08 Xe-133m 2.07 E-07 Xe-135 3.34 E-08 Cs-134 2.02 E-08 Cs-137 4.64 E-08 Ba-140 4.77 E-'08 La-140 3 49 E-08 Ce-141 4.35 E-08 Ce-144 1.38 E-07

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

A. Fission and activation ases

1. Total release Ci 9.66 E+00 1.21 E+01 5.27 E+01

2. Avera e release rate for eriod Ci/sec 1.24 E+00 1.53 E+00

3. Percent of Tech S ec limit 3.63 E-02 2.50 E-02 B. lodines

1. Total iodine-131 Ci 5.42 E.06 4.91 E-05 3.18 E+01

2. Avera e release rate for eriod Ci/sec 6.98 E.07 6.24 E-06

3. Percent of Tech S ec limit 3.00 E.02 2.36 E-01 Particulates

1. Particulates with half. lives ) 8 da s Ci 3.87 E-05 8.19 E-05 3.37 E+01

2. Avera e release rate for eriod Ci/sec 4.98 E-06 1.04 E-05

3. Percent of Tech S ec limit 3.00 E-02 2.36 E-01

( LLD ( LLD Gross al ha radioactivit Ci D. Tritium

1. Total release Ci 7.11 E-01 7.09 E+00 5.22 E+01

2. Avera e release rate for eriod Ci/sec 9.14 E-02 9.02 E-01

3. Percent of Tech S ec limit " 3.00 E-02 2.36 E-01 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly Technical Specification limit is 7.5 millirem. The most critical organ for both quarters was the Thyroid.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 1A: GASEOUS EFf LUENTS - SUMMATION Of ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation ases

1. Total release Ci 3.20 E+00 1.24 E+01 5.27 E+01

2. Avera e release rate for eriod Ci/sec 4.02 E-01 1.56 E+00

3. Percent of Tech S ec limit 6.78 E-03 2.54 E-03 B. lodines

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

2. Avera e release rate for oriod Ci/soc 0.00 E+00 0.00 E+00

3. Percent of Tech S ec limit 3.70 E-02 6.99 E-06 Particulates

1. Particulates with half-lives ) 8 da s Ci 1.19 E-04 0.00 E+00 3.37 E+01 2.

3. Percent of Tech S ec limit Gross al ha radioactivit

'i/sec Avera e rolease rate for eriod Ci 1.50 E-05 3.70 E-02

< LLD 0.00 E+00 6.99 E-06

< LLD D. Tritium

1. Total release Ci 1.38 E+00 3.88 E.04 5.22 E+01

2. Avera e roleaso rate for oriod Ci/sec 1.73 E-01 4.89 E-05

3. Percent of Tech S ec limit 3.70 E-02 6.99 E-06 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly Technical Specification limit is 7.5 millirom. Tho most critical organ for first quarter was tho lung and tho second quarter was tho thyroid.

2/4

Appendix 2: Effluent and Waste Disposal Report {Continued)

Enclosure 2: Effluents Released Table 1B: GASEOUS EFFLUENTS - ELEVATED RELEASES All releases at Shearon Harris Nuclear Power Plant are made as ground releases.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 7 1

2. Iodines 4 4

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

'loathe and particulate radionuclides in this column are due to the refueling outage and were not released via the normal Plant Vent Stacks. pathway.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuciides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission gases I f ri

2. Iodines

'I r

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

2/7

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (FIRST SIX MONTHS)

Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and Activation products

1. Total release (not including tritium, Ci 9.62 E-03 2.53 E-02 3.28 E+01 ases, al ha)

2. Average diluted concentration during yCi/ml 1.59 E-09 4.64 E-09 pano'.

Percent of applicable limit 2.03 E-01 2.82 E-01 B. Tritium

1. Total release Ci 1.29 E+02 9.30 E+01 5.50 E+01

2. Averaqe diluted concentration during yCi/ml 2.13 E-05 1.71 E-05 enod

3. Percent of applicable limit 2.1 3 E+ 00 1.71 E+ 00 C. Dissolved and entrained ases

1. Total release Ci 1.07 E-04 9.77 E-06 3.28 E+01

2. Averaqe diluted concentration during yCi/ml 1.76 E-11 1.79 E-12 period=

3. Percent of a plicable limit 8.80 E-06 8.97 E-07 D. Gross al ha radioactivity

1. Total release Ci < LLD ( LLD 3.28 E+01 E. Volume of waste released (prior to dilution) liters 6.03 E+05 1.22 E+06 2.00 E+01 F. Volume of dilution water used durin period liters 6.07 E+09 5.45 E+09 2.00 E+01

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (SECOND SIX MONTHS)

Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and Activation roducts

1. Total release (not including tritium, Ci 2.33 E-02 7.14 E-03 3.28 E+01 ases, alpha)

2. Average diluted concentration during yCI/ml 3.11 E-09 1.03 E-09 penod

3. Percent of applicable limit 1.37 E-01 3.34 E-02 B. Tritium

1. Total release Ci 4.99 E+01 2.73 E+01 5.50 E+01

2. Average diluted concentration during yCI/ml 6.66 E-06 3.92 E-06 period

3. Percent of applicable limit 6.70 E-01 3.90 E-01 C. Dissolved and entrained ases

1. Total release Ci < LLD < LLD 3.28 E+01

2. Average diluted concentration during pCI/ml < LLD < LLD period

3. Percent of applicable limit 0.00 0.00 D. Gross alpha radioactivit

1. Total release Ci < LLD < LLD 3.28 E+01 E. Volume of waste released (prior to dilution) liters 1.13 E+06 5.78 E+05 2.00 E+01 F. Volume of dilution water used durin period liters 7.50 E+09 6.96 E+09 2.00 E+01

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 tritium Ci 1.39 E-02 < LLD 1.29 E+02 9.30 E+01 man anese-54 Ci Note 1 Note 1 4.47 E.05 2.52 E-04 iron-55 Ci Mote 1 Note 1 1.17 E-03 2.12 E-03 cobalt-57 Ci Note 1 Mote 1 < LLD < LLD cobalt-58 Ci Note 1 Note 1 1.73 E-04 7.66 E-03 iron.59 Ci Note 1 Note 1 < LLD 3.68 E-05 cobalt.60 Ci Note 1 Note 1 1.42 E-03 5.60 E-03 nickel-63 Ci Mote 1 Note 1 3.25 E-04 1.32 E-03 zinc-65 Ci Note 1 Note 1 < LLD < LLD strontium-89 Ci Mote 1 Mote 1 < LLD < LLD strontium.90 Ci Note 1 Note 1 < LLD < LLD zirconium.95 Ci Note 1 Note 1 < LLD 6.17 E-05 niobium 95 Ci Note 1 Note 1 < LLD 9.12 E-05 technicium-99m Ci Note 1 Note 1 < LLD < LLD mol bdenum.99 Ci Mote 1 Note 1 < LLD < LLD ruthenium-106 Ci Mote 1 Note 1 <LLD < LLD antimon -124 Ci Note 1 Note 1 <LLD 1.14 E-04 antimon -125 Ci Note 1 Note 1 6.30 E-03 6.80 E-03 antimon -126 Ci Note 1 Note 1 <LLD < LLD iodine-131 Ci Note 1 Note 1 < LLD 3.52 E-04 iodine-133 Ci Note 1 Note 1 < LLD < LLD cesium-134 Ci Note 1 Note 1 1.80 E-05 < LLD cesium-137 Ci Note 1 Note 1 3.92 E-05 3.05 E-05 barium-140 Ci Note 1 Note 1 <LLD < LLD lanthanum-140 Ci Note 1 Note 1 < LLD < LLD corium-141 Ci Note 1 Note 1 < LLD < LLD cerium.144 Ci Note 1 Note 1 < LLD < LLD TOTAL Ci Note 1 Note 1 9.62 E-03 2.53 E-02 xenon-133 Ci Mote 1 Note 1 1.07 E-04 9.77 E-06 xenon.133m Ci Note 1 Note 1 < LLD < LLD xenon-135 Ci Note 1 Note 1 < LLD < LLD TOTAL Ci 1.07 E-04 9.77 E-06 Note 1 - No Continuous Releases were made during first or second quarters of1$ 97and the tritium is from the Primary System diffusing via Steam Generator tubes.

2/io

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS N Ii R ni r4 r4 hr mi )m- 4 ~ 4 Note 1 - No Continuous Releases were made during third or fourth quarters of 1997 and the tritium is from the Primary System diffusing via Steam Generator tubes.

Appendix 2: Effluent and Waste Disposal Report (Continued)

Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS HNP was prohibited from burying or disposing of radioactive solid waste materials at a licensed facility during 1997. Consequently, all values reported in Table 3 refer to radioactive solid waste materials processed and returned to HNP, during 1997, 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 1997 for interim storage awaiting future burial. HEEC wastes are noted where applicable.

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

A. Type of Waste Concerning "Number of Shipments" described in 1.A.a, these shipments were part of the five 1.A.b shipments.

Cartridge/Mechanical Filters (HNP ONLY)

Number of Shipments 2 Activity Shipped 3.24 E+00 Ci Estimated Total Error 96%

Quantity Shipped 4.1 E-01 m~

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

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

(HNP and HEEC)

Number of Shipments 5 Activity Shipped 6.76 E+00 Ci Estimated Total Error 101 ohio Quantity Shipped 2.69 E+01 Solidification Agent m'oncrete Container Type NRC-Approved Package Shipment Form Dewatered, Compacted, or Solidified

c. Irradiated Components, Control Rods, etc.

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

d. Other (Describe)

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

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

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

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

a. Cartridge/Mechanical Filters (HNP ONLY)

Percent Total Activity Nuclide Composition Ci H-3 1.4 E-01 4.64 E - 03 C-14 3.1 E-02 1.01 E - 03 Mn-54 1.9 E+00 6.28 E -02 Fe-55 8.6 E+01 2.77 E+00 Co-58 1.7 E-02 5.52 E- 04 Co-60 3.6 E+00 1.18 E - 01 Ni-63 8.5 E+00 2.74 E - 01 Sr-90 1.0 E-03 3.23 E -05 Nb-95 1.8 E-02 5.80 E- 04 Zr-95 9.6 E-03 3.12 E -04 Cs-134 7.8 E-03 2.52 E - 04 Cs-137 3.5 E-02 1.12 E - 03 Pu-238 3.1 E-04 1.00 E -05 Pu-239 1.9 E -04 6.00 E -06 Pu-241 1.4 E-01 4.54 E - 03 Am-241 1.7 E -04 5.50 E -06 Cm-242 5.5 E-04 1.79 E-05 Cm-243 64 E-04 2.06 E - 05

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

(1) {HNP ONLY)

Percent Total Activity Nuclide Composition Ci H-3 1.6 E-01 1.09 E-02 C-14 7.0 E-03 4.75 E -04 Mn-54 2.6 E+00 1.78 E-01 Fe-55 5.9 E+01 3.95 E+00 Co-58 8.3 E-01 5.60 E - 02 Co-60 3.0 E+01 2.00 E+00 Ni-63 5.5 E+00 3.73 E - 01 Sr-90 1.2 E-03 7.77 E - 05 Nb-95 7.4 E-01 5.01 E -02 Zr-95 40 E-01 2.71 E -02 Cs-134 4.2 E-01 2.84 E - 02 Cs-137 7.6 E-01 5.12 E -02 Pu-241 4.0 E-01 2.68 E -02 Cm-242 2.3 E-04 1.56 E-05 Cm-243 2.9 E-04 1.96 E - 05

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

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

(Continued)

(2) (HEEC ONLY)

Percent Total Activity Nuclide Composition Ci C-14 1.2 E-01 1.43 E-05 Cr-51 2.7 E-02 3.20 E-06 Mn-54 3.9 E+00 4.63 E-04 Fe-55 7.1 E+01 8.31 E-03 Co-57 8.5 E-04 1.00 E-07 Co-58 3.6 E+00 4.29 E-04 Fe-59 5.3 E-01 6.26 E-05 Co-60 1.6 E+01 1.90 E-03 Ni-63 2.4 E+00 2.84 E-04 Zn-65 ,8.7 E - 02 1.02 E-05 Nb-95 1.3 E+00 1.57 E-04 Zr-95 1.6 E-01 1.91 E-05 I-131 8.5 E-04 1.00 E-07 Ce-141 3.6 E-02 4.20 E-06 Ce-144 4.2 E-02 4.90 E-06 Cs-134 40 E-01 4.65 E-05 Cs-137 5.1 E-01 5.95 E-05 Am-241 8.5 E-04 1.00 E-07 Irradiated Components, Control Rods, etc.

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

Other (Describe)

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

2/14

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

C. Solid Waste Disposal Number of Shipments 5 Mode of Transportation Truck Destination HNP, New Hill NC {For Storage)

The five 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 ( WASTE CLASS B )

A. 'ype of Waste Spent Resin (HNP ONLY)

Number of Shipments 2 Activity Shipped 2.99 E+01 Ci Estimated Total Error 97%

Quantity Shipped 3.4 E+00 m~

Solidification Agent Metal Container Type NRC-Approved Package Shipment Form Solid Dry Compressible Waste {DAW), Contaminated Equipment, etc.

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

C. Irradiated Components, Control Rods, etc.

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

Other (Describe)

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

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

Estimate of Major Nuclide Composition (by type of Waste)

Spent Resin (HNP ONLY)

Percent Total Activity Nuclide Composition Ci Mn-54 5.1 E-01 1.52 E - 01 Fe-55 4.0 E+01 1.20 E+01 Co-60 3.1 E+ 01 9.25 E+00 Ni-63 2.2 E+01 6.62 E+00 Sr-89 3.3 E-05 9.97 E-06 Sr-90 1.5 E-01 4.53 E -02 Zr-95 2.7 E-04 8.07 E -05 Nb-95 4.3 E-04 1.29 E -04 Sb-125 1.9 E -01 5.67 E-02 Ce-144 3.0 E-05 8.85 E -06 Cs-134 1.4 E+00 4.13 E -01 Cs-137 4.3 E+00 1.30 E+00 Pu-238 2.8 E-04 8.24 E - 05 Pu-241 6.1 E-02 1.83 E - 02 Cm-242 3.3 E-05 9.86 E -06

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

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

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.

Solid Waste Disposal Number of Shipments 2 Mode of Transportation Truck Destination HNP, New Hill NC (For Storage)

The two type 2.A.a shipments were made from Molten Metal Technologies (MMT) processing facility in Oak Ridge, Tennessee.

Appendix 2: Effluent and Waste Disposal Report (Continued)

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

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

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.

Appendix 3: Changes to Process Control Program {PCP)

Technical Specification 6.13

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

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

Technical Specification 6.14.c During 1997, the ODCM was revised one time as revision,10. A description of this revision is listed below.

Revision 10 to the ODCM included the new Turbine Building Drains Rad Monitor sensitivity due to ESR 97-00248 and updated the Radiological Environmental Program due to the last milk sample location within ten miles of the Harris Nuclear Plant discontinued operations.

ODCM REV. 10 CHANGES Section Pa e Descri tion Title Pa e Revised to Rev. 10 LEP vi, vii Chan ed revision numbers as a ro riate Table 2.1-4 2 - 21 Due to ESR 97-00248, added the Turbine Building Drains Rad through Monitor sensitivity to the Nuclide Parameters list.

2-23 Table 4.1 4-8 Deleted "I-131 analysis is normally performed weekly on these sam les" in Note because not re uired.

Table 4.1 4- 11 Added "is no longer in business" to Milk Sample Point ID No. 42 (CR 97-02983). Also Control Station ID No. 5 was changed to Manco's Dairy, WNW sector ) 12 mi. from site, because Stroud's farm is no lon er in business.

Table 4.1 4- 14 Added two broad Iaaf vegetation locations (Sample Point ID No.

65 5 66) at site boundary. When milk sampling is not possible, samples of three different kinds of broad leaf vegetation grown nearest each of two different offsite locations ofghighest redicted annual avera e round level D/Q is re uired.

Fi ure 4.1-4 4 - 19 Added Station Number 65 5. 66 Figure 4.1-5 4- 20 Added Station Number 65 5 66. Sample Type BL (Broad Leaf Ve etation)

Table 4.3-8 D-6 In Notation (1)e., added "(Not applicable for Turbine Building Table Notations Drains Rad Monitor)" because this monitor is mounted to the effluent rocess i e and sam le flow is not a licable.

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 September 1997, no changes were required to the Environmental Sampling Program or to the ODCM. However, on May 19,1997, during the time for the routine milk sampling was to be collected the technician was notified that the Maple Kmoll Dairy had gone out of business. Compensatory sampling ( samples of three different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/0) was imediately instituted and a Corrective Action (CR-9702983) was written to change the ODCM and the sampling procedure (LS-ER-31).

r Offsite Dose Calculation Manual Operational Requirements 3.12.2.a and 3.12.2.b The land-use census that was completed in September, 1997, resulted in no changes to the ODCM or to the Environmental Monitoring Program.

Appendix 6: Additional ODCM Operational Requirements n i ii ffl M D M Operationa Requirement ..3.1, Action Monitors Out-of-Service ) 30 Days During this Report Period Radioactivity Monitors Providing Alarms but not Providing Termination of Release REM-01 SW-3500B REM-01SW-3500B is the radiation monitor for the normal service water return from the RAB and TB. This monitor was removed from service when the NSW system was shutdown and drained during RFO7. The monitor was returned to service after the NSW system was refilled and started.

The monitor could not function while the NSW water system was out of service because there was no water to monitor.

REM-01MD-3530 REM-01MD-3530 (Outdoor Tank Area Drain Monitor) was declared inoperable on May 15, 1997, and was out of service for greater than 30 days due to a spill from the Refueling Water Storage Tank during the refueling outage. REM-01MD-3530 monitors the outdoor tank area drains from the Refueling Water Storage Tank and the Primary Water Storage Tank pits due to rain water.

During this period of time the rain water was sent to Radwaste until the pits and the monitor could be cleaned.

Radioactivity Monitors Providing Alarms and Automatic Termination of Release

3. REM-01MD-3528 REM-01MD-3528 was made inoperable on 3/10/97 and was inoperable for greater than 30 days due to problems with maintaining sample flow. REM-01MD-3528 monitors the Turbine Building Drains discharge to the oily waste separator for radioactivity. It is required to be operable at all times per the Off Site Dose Calculation Manual (ODCM). It is set to alarm at a preset limit and terminate the discharge on high radiation. This monitor takes a sample from a loop seal in the turbine building drains discharge line. The monitor runs continuously because the turbine building industrial waste sump pumps will start automatically on a high sump level.

The radiation monitor has sample flow measuring instrumentation to ensure that an adequate sample flow is maintained. A loss of sample flow alarm indicates that the sample flow to the radiation monitor has dropped below the low sample flow alarm. The monitor is not operable when it is not getting adequate sample flow or when the sample flow instrumentation is not operable.

REM-01MD-3528 has problems maintaining sample flow. Extensive troubleshooting has been done by maintenance and engineering. A summary of the findings are listed below:

1. The flow instrumentation is accurate and reliable and is not part of the problem. ESR 95-00583 replaced the flow instrumentation and it has been verified to be accurate.

2. The loss of sample flow alarms are real and have several different causes.

The different causes of the Iow flow include debris in the sample line, air in the sample lines, and flow perturbations caused by the running of the turbine building industrial waste sump pumps.

No single corrective action can be found for the loss of sample flow problems. Engineering proposes that the turbine building drain radiation monitor be replaced with an adjacent to line radiation monitor. This will eliminate the need for sampling and therefore the loss of sample flow problems.

REM-01MD-3528 was modified by ESR 97-00248 to an adjacent to line type radiation monitor.

This type of monitor uses a detector installed adjacent to the discharge piping. It measures the radiation of the discharge stream directly. No sampling is required. This eliminates the need for maintaining sample flow and resolves this problem permanently. Implementation of the ESR was completed on 12/18/97 and REM-01MD-3528 was declared operable.

I 1' f ODCM Operationa Requirement ..3.10, Action b Icontinued)

Flow Rate Measurement Devices FT-21 WL-61 1 9 FT-21WL-6119 flow rate measurement device was worked under 97-AFJE1. After completion of this ticket, MST-I0302 was satisfactorily performed on 6-19-97. The last liquid release was done on 6-9-97. OST-2044 was unable to be performed due to no water available for release.

This flow rate measurement device was functional but could not be declared operable due to the unavailability of water to release. Therefore, the flow rate measurement device could not be declared operable.

ODCM perational Requirement .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 1997 per the Condition Reporting Process, None were inoperable for greater than 30 continuous days during this report period.

echnical Specification .11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this report period.

n ec nica Specification .11, Action I a

I 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 1.) ESR 95-00565 DEMIN. SKID ENHANCEMENT ( SUMMARy )

BACKGROUND The liquid waste processing system at HNP currently has a Modular Fluidized Transfer Demineralization System (MFTDS) for filtering, treating and demineralizing the Floor Drain Tank and other Waste Tank effluents. This system consists of a control module with a three stage filtration system with four in-line ion exchange vessels and finally a post-filtration (fines). The effluent is then discharged to the Waste Monitoring Tank or the Treated Laundry and Hot Shower Tanks (TLHST) depending on system line-up. The pre-filter stage consists of both bag and cartridge filter elements.

The exchange vessels contain activated carbon or resins serving as three cation beds and one mixed bed. These vessels are operated in various lineups depending on the quality and radioactivity of the waste being processed. The current configuration has an undesirable feature where the polymer is continually added to the Floor Drain Tanks (FDT) through a polyelectrolyte feed tank and is causing a condition of either oyer or under dosing the tanks. In addition, the suspended solids are settling in the FDTs and are not being removed forming a continual sludge buildup. This sludge buildup decreases the effectiveness of the polymer.

Objective This project will remove the existing upstream filtration component of the MFTDS and replace it with the Applied Chemical Technologies (ACT) System. The system will include: a Polymer Feed Skid, Mixing Skid, Filter Vessel Skid and associated support equipment. The filter housing will be shielded and a shield bell will be provided for removing the filters. An AAQ frame crane will be provided to position the shield bell and extract the filters.

The change will allow the polymer injection process to move from the tanks to just prior to the filters, allowing the realization of the polymers full effectiveness and the complete removal of the polymer

.trapped in the filter bags, at change-out.

The objectives of the MFTDS Enhancement are:

1. Eliminate the need to desludge the Laundry 5 Hot Shower Tanks (2 each), the Floor Drain Tanks (4 each), and the Waste Holdup Tank every four years.

Reduce the volume of Low Level Radioactive Waste by increasing the through put of the radioactive waste filters.

3. Reduce the radiation exposure associated with the operation and maintenance of the system.

2.) 10 CFR 50.59 Safety Evaluation (Summary)

This modification to the Liquid Waste Processing System meets design, material and construction standards applicable to the existing system as clarified in the proposed FSAR changes. The design meets the intent of the Reg. Guide 1.143 as clarified and will not increase the likelihood of accident occurrence.

The system is addressed in Chapter 15.7.2 of the FSAR and the accident analysis assumes a complete failure, as a result of a safe shutdown earthquake event. The spilled liquids are contained within the Waste Process Building with the assumed releases to the atmosphere to be only noble gases of iodides to volatilize from the liquids. This modification to the MFTD System will not increase the probability of a loss of inventory event because of design, construction and.testing as defined in this modification and is bounded by the current analysis in Chapter 15.7.2.

The modification will not alter the integrity of the Waste Process Building as evaluated in the structural loading analysis or introduce additional radioactive liquids into the Liquid Waste Processing System or provide any un-monitored release path, therefore the modification is bounded by the Chapter 15 analysis.

The accident consequences remain unchanged.

The modification to the Liquid Waste Processing System will not alter any safety related equipment and is located in an area that does not contain safety related equipment. The types of accidents this modification could create are: flooding, release of liquid within the building, fire and spurious circuits.

All of the above possible accidents have been evaluated in the FSAR, therefore an accident of a different type has not been introduced.

This modification to the Liquid Waste Processing System meets design, material and construction standards applicable to the existing system and will not increase the likelihood of an accident occurring.

The single failure and separation criteria are not impacted or compromised. The system components will not pose structural loading beyond the design limits or defeat and protective features analyzed in the FSAR. Electrical power is provided from a non-vital bus equipped with overload and short circuit I'otection. The equipment will not generate heat loads requiring additional cooling. The system will add ess that 10 cfm of drying air to the existing HVAC system on an intermittent basis. The drying air is discharged via Waste Process Building Filtered Exhaust which is a monitored and controlled release path.

This change to the HVAC is non-safety and will not impact safety related equipment. The demineralized water, instrument and service air systems are loaded only intermittently to support this new system and failures of these support systems have been previously analyzed in the FSAR. The interfacing support systems are non-safety and are not accident initiators and are not relied upon as accident mitigators.

The change makes an apparent reduction in the original Design Margin for the Floor Drain Treatment System. However, the original licensing calculations were based on assumptions pertaining to the volume of wastes to be processed and the inaccuracies in the capability of the installed MFTDs system.

The actual volumes of wastes have been steadily decreasing due to previous modifications to eliminate HVAC condensates and other operational improvements. The waste volumes listed in the FSAR are very conservative and are considered the most bounding for the highest expected input volumes. The new Design Margin Calculation supports the realistic margin being 1.5 times for processing the maximum inputs and the system's ability of increasing to 3.0 times the maximum, for off normal condition processing. The system possess excess capability to process the maximum expected inputs.

The modification to the Liquid Waste Processing System will not change the ability to load the demineralizer vessels to the configuration as described in Chapter 11.2 to treat the one percent failed fuel event. The modification will not impact or interface with any equipment important to safety. No malfunction of equipment important to safety will be impacted by this modification in a way that could increase radiological consequences to the public, The modification to the Liquid Waste Processing System will not alter any safety related equipment and is located in an area that does not contain safety related equipment. The types of malfunctions this modification could create are: flooding, release of liquid within the building, fire and spurious circuits.

All of the above possible malfunction accidents have been evaluated in the FSAR, therefore a malfunction accident of a different type has not been introduced. The modification to the Liquid Waste Processing System will not connect to or affect equipment important to safety, therefore no increase in the probability of equipment malfunction will be realized.

The Liquid Waste Processing System remains in conformance with Technical Specification 6.8.4 for compliance with the ODCM, therefore no change will be realized in the margin of safety as defined in the Technical Specifications.

REFERENCES:

FSAR Chapters 1.8, 11.2 and 15.7.2, Reg. Guide 1.143, BTP ETSB 11.1, NUREG 800 SRP Section 11.2 and Tech. Specs. 3/4.11., 8.4, 6.14 and 6.15.

7/2

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 3.) Major Components A fully operational shop-tested system consisting of the skid mounted equipment, accessories and controls defined in the following sections of this specification will be provided. The major components shall include:

Polymer Feed Skid Mixing Skid Filter Vessel Skid Drying System Instrument IIi Control Package Interconnecting Hoses A Frame Hoist and Accessories Engineering Documentation including drawings, Engineering and Design Data (including all design calculations i.e. Decontamination Factors)

Instruction Manuals and Operator Training will be provided to the owner.

System Performance Requirements

a. Design flow (influent) - 15 gpm

b. Design throughput - 2,000,000 gal/yr

c. Design pressure - 150 psig

d. Design temperature 105 oF

e. Maximum foot print for all skids - 14 ft. wide by 15 ft long Polymer Feed Skid A separate system to feed polymer (Betz 1175) to liquid waste stream feed. System consists of a conical bottom (15 degrees) 304 stainless steel or cross-linked polypropylene tank (on a stand) with mixer, and a positive displacement feed pump. The capacity of the polymer tank is 100 gallons.

Tank to be fitted with tubular gage glass with stainless steel fittings and protective rods or polypropylene fittings and tube consistent with tank material and application. Vendor shall provide graduated level markings on tank exterior adjacent to level glass. Tank package to include level switches and relays to trip chemical feed pumps on low level to prevent pumps from running dry with subsequent damage. Feeds are interlocked to influent waste stream feed.

Relays will also be provided to trip purchaser's process inlet isolation valve on tank low level.

Chemical feed pumps shall be positive displacement type with a flow capacity between 6 and 75 gal./day. The maximum design pressure of the connected system is 150 psig, minimum system pressure will be approximately 35-50 psig. Accordingly, pump discharge pressure must be able to operate within these values. Pump internal relief valve to be set at factory for 150 psig. (This valve may be termed "bleed valve", the intent is to assure pressure protection at 150 psig and greater than 150 psig.)

Covers are to be provided for polymer drums and polymer mixing tank or piping is to be designed to prevent a splashing hazard.

The Polymer Feed Skid will require single phase, 60hz, 120VAC electrical service, to be provide by Purchaser. Vendor will provide termination and protective equipment for connecting to Purchasers electrical system.

Piping/Valves The piping, valves and fittings associated with the Polymer Feed skid are excluded from the B31.1 code requirements. Suction piping shall be either 304 or 304L stainless steel piping. Diameter to be appropriate for process conditions but not less than 1/2". Suction piping shall include pump suction and tank drain valves and a valved hose connection piped to pump suction for admission of flush water. Discharge piping shall be 304 or 304L stainless steel high density polyethylene or polypropylene tubing with diameter appropriate to the process conditions but not less than 1/2". Piping shall be run neat and straight with, all runs parallel to sides of skid. Pipe to be routed from pump discharge to edge of skid. Demin water supply piping to be type 304 or 304L, A312SS, sched 40 or 80.

7/3

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 Mixing Skid The purpose of this skid is to allow adequate time for the polymer to mix with and agglomerate the insolubles in the influent prior to exit from the skid. The design flow rate is 15 gpm and the retention time for coagulant reaction of approximately 1 minute must be provided. Design must provide specifically located inlet and outlet and a separate polymer addition inlet. Sampling ports are placed after the process and polymer inlets.

Mixing Skid configuration is intended to provide a system for conveying low level radioactive waste water at a maximum inlet pressure of (150 psig and a maximum inlet temperature of (105 F while utilizing 2" stainless steel (Tp 304) Schedule 10 piping. Polymer injection piping 3/4" stainless steel (gTp. 304) Schedule 40 admits proprietary chemicals at one (1) separate point along the process. The process flowrate of the bundle ranges from 10-30 GPM. The vendor will provide calculated pressure drop including valves, fittings, static mixers, etc., for 10 GPM and 30 GPM. The piping, equipment and components are supported by means of carbon steel angle support which are in turn supported by rectangular tubing columns. The 3/4" injection piping is routed from the process admission point to the top of the unit, terminating in admission check and isolation valves and 3/4" NPT male pipe stub for interface with Polymer Feed Skid flexible hoses. In addition to the injection valves, vendor shall also provide piping and valves associated with process inlet/outlet/vents/drains and sample ports. Also, vendor will supply an in-line static mixer injection point and piping/fittings to accommodate process instruments provided by VENDOR as described elsewhere herein. A time delay chamber and air separator is to be supplied on the mixing skid. A vent connection from the air separator shall also be supplied with a demisting device to assure no moisture carry over will be realized in the plants HVAC exhaust duct.

The Mixing Skid will require single phase, 60hz, 120VAC electrical service, to be provide by Purchaser. Vendor will provide termination and protective equipment for connecting to Purchasers electrical system, in accordance with applicable requirements of the National Electrical Code (NEC).

Static Mixer Immediately following the chemical injection point associated with the Mixing Skid, a Static In-Line Mixer is located to assure complete mixing of injected chemicals. It will be vendor's responsibility to procure and incorporate the Static Mixer into the mixing bundle.

An air drying system complete with (air pressure regulator [125psig in/75psig out) tubing, valves and fittings) with an air flow r'equirements at 10-20 cfm (compressed air supplied by purchaser)will be supplied. This system is attached to the inlet to the filter vessels (inlet) and the vent lines off filter vessels (outlet). It is used to render bag filter media free of water after filter vessels are drained. A demisting device is provided to assure no moisture carry over will be realized in the plants HVAC exhaust duct.

Appendix 7: Major Modifications to Radwaste System (continued)

ODCM Operational Requirement F.3 Filter Vessel Skid This skid assembly consists of two filter vessels, the associated pipe, valves and fittinqs and 4 inch square carbon steel tubing which serves as the skid frame. The first filter is an in-line stainless steel vessel containing 8 bag filter assemblies. Inlet and outlet flanges are sized for two inch piping and are mounted on the same side of the housing. The housing is vented and includes provisions for drying. Each filter bag is contained within a re-usable 304 stainless steel basket (pleated design) Each bag filter is 8 inch diameter and 30 inches long and has a volume of 0.87

~

cubic feet.

The second filter is an in-line stainless steel vessel containing 6 pleated bag filter assemblies. Inlet and outlet flanges are sized for 2 inch piping and are mouted on the same side of the housing. The hosing is vented and includes provisions for vacuum drying. Each filter bag is contained within a re-useable 304 stainless steel basket (pleated design), Each bag filter is 8 inch diameter and 30 inches long and has a volume of .87 cubic feet. Efforts are currently in progress by HNP Engineering personnel to improve the performance of these filters.

The vendor shall provide the necessary pipe, valves and fittinqs to control flow to and from each vessel as well as to isolate each. These valves should be air operated. Valves and piping must also be provided to allow for the drying of filter bags utilizing vacuum or air drying system. This skid will consist of a compressed air dryer system (air pressure regulator [125 psig in / 75 psig out], tubing, valves, and fittings). Air flow requirements are 10-20 cfm (compressed air supplied by purchaser).

The system is attached to the filter vessel inlet and the vent lines off the filter vessel outlet. The outlet vent will enter an air separator, demister and flow through a pressure reducing orifice prior to entering the Owner's HVAC system at approximately 1/4 to 1/8 inwc at 10 to 20 cfm. The system will render bag filter media free of excess water after the filter vessels are drained.

7/5

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement.F.3 Instrumentation & Controls This package will consist of a single phase, 60 Hz, 120 VAC control panel that will be mounted on the Mixing Skid. This panel will include a NEMA 4 enclosure and house the electrical disconnect switch, applicable motor and equipment starters, valve equipment control units, audible alarms and visual alarms. The use of hard drawn copper, Schedule L, for instrument air and compressed air is acceptable. Threaded compression type fittings are acceptable provided they meet testing requirements. Purchaser will provide 120VAC electrical service to the control panel.

Motor starters (NEMA Type) and protection circuits for equipment motors on each skid will be rovided by vendor and combined into a common control panel. The enclosure shall be rated for

!V EMA 4 classification I and mounted to the skid frame.

Wiring from motors to panel shall be run in rigid or liquid tight conduit. Conduit shall be run neat and straight with all runs parallel to sides of skid. Wiring connections at Mixer motor shall have adequate flexibility to allow for adjustment of mixer as necessary.

The panel front shall incorporate control switches for starting/stopping pumps and mixers, running lights and nameplates. The mixing pump and mixer control switches may be located within the panel since they are an integral part of the Programmable Logic Controller. Panel height above mounting skid shall be selected for convenience of operation of controls.

Panel materials, wiring and terminations shall be in accordance with good engineering practice.

A power supply receptacle shall be provided for convenient connection to purchasers electrical system.

Vendor shall provide system controls (including motor start/stop and electrical disconnect described in 2.4) in a stand-alone panel with a sing1e power connection (to be defined by Vendor).

Controls shall have 4-20 ma outputs Vendor as a minimum will provide the following instrumentation and control features:

Pressure indicator, pump at skid inlet header Level Switches (hi/Iow), Polymer tank Relays/Interlocks to Polymer Feed pump 5 inlet isolation valve Influent flow monitoring and control Includes flow element, flow transmitter, flow integrator, flow controller and air operated flow control valve w/air set. (2 inch process pipe, 10-30 gpm 5 117psig/70 F, liquid-contaminated water)

Conductivity monitor and alarm ( 50-2000:S/cm )

Turbidity monitor, control and alarm ( 10 - 200 NPU )

pH monitor, control and alarm Interconnecting Hoses The Liquid Waste Processing System will be connected to the owners permanent plant piping and equipment through the use of durable, high strength flexible hoses the equivalent size of the plant piping and with the same type end connections as the plant pipe (e.g. quick disconnects). The interconnection between system skids may be through the use of similar hoses.

A Frame Hoist and Accessories A standard industrial A Frame Hoist will be provided for the lifting of the filter vessel heads and shield. This will include specialized tools for the removal of the vessel heads to assure personnel dose rates are ALARA during filter change out. The Hoist will require three phase, 60hz, 480 VAC electrical service, and a disconnect switch, to be provide by Purchaser. Vendor will provide interconnecting cables, wiring, plug, and ground buses required to connect and operate hoist.

Electrical plug and receptacle shall be permanently labeled to identify correct connection. Vendor shall provide mechanical strain relief for electrical connection from the Purchasers disconnect switch to the hoist assembly. Vendor is responsible for interconnecting to Purchasers electrical service. Purchaser will provide a receptacle for the electrical service of the Hoist.

7/e

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 Valves Relief Valves Two ASME Section Vill relief valves factory set at 150 psig shall be located on the filter vessel inlets and one relief valve factory set at 80 psig shall be located on the air supply to protect the filter vessels. One relief valve factory set at 150 psig shall be located at the effluent inlet to provide protection for the Demineralizer Vessels. The valves shall be Kunkle Valve Division model no. 911 or equivalent. The relief valves should be flanged in to allow for ease of maintenance/replacement.

Motor Specifications Each motor shall have a nameplate in accordance with NEMA Standard MG 1-1978 Part One.

Motors provided by the Vendor shall meet the applicable requirements contained in NEMA Standard MG 1-1978.

Piping/Welding Specifications In general all materials are to be identified by ASTM/ASME Specification and Grade. All welding, including structural shall be by qualified welders. All structural steel shall be ASTM A36 or approved equivalent.

When not described elsewhere in this specification the materials of construction shall be in compliance with the codes and standards listed Section 3.

Certified Material Test Reports (CMTR) are required for all pressure retaining parts in the Radwaste Piping System. In cases where CMTRs are not obtainable, manufacture s Certificate of Compliance (C of C) indicating that the material conforms to the requirements of ASME Section II Specifications may be accepted.

Materials for pressure-retaining components will conform to Section II of the ASME Boiler and Pressure Vessel Code; whereas malleable, wrought, or cast iron materials and plastic pipe will not be used.

Welding procedures and welder qualifications shall be in accordance with the requirements of ANSI/ASME B(liPVC,Section IX. Qualified procedures, operators and procedures will be employed for this work.

Vendor procedure per ASME Section IX for qualifying Welding Procedure Specifications (WPS) and supporting Procedure Qualification Record (PQR) must be reviewed and approved by purchaser prior to commencing work.

Vendor welder performance qualification records must be reviewed by purchaser and copies included in the vendor data package.

Two (2) inch and under pipe and fittings shall be butt welded (except for fittings and valves that can only be furnished with socket weld ends) and with exception of non-radwaste pressure boundary items.

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 Wiring Standards All electrical equipment shall be UL approved where applicable.

Wiring shall be free of abrasions and tool marks and shall have a minimum bending radius of 1/4".

All wiring shall be adequately supported in rigid or liquid tight conduit.

Wire shall be of adequate rating for the current to be carried. All cable/wire within the skids shall be continuous with no splicing permitted.

Wire size is dictated by circuit requirement. Wire/cable shall be copper, rated for 600 volts AC, with heat, moisture, and flame resistant insulation. Vendor shall use cable which is capable of passing the applicable flame-resistant test specified in IEEE 383 (Standard for Type Test of Class 1E Electric Cables, field Splices, and Connections for Nuclear Generating Stations. Cable which complies with the flame resistant test specified in UL 910 or NFPA 262 is also acceptable. Use of PVC insulation and/or jacketing is not permitted without prior approval by CPRL.

All electrical equipment shall have individual AC power disconnect features, other than removal of conductors from terminals, to facilitate isolation for maintenance.

Terminal blocks shall be phenolic or listed (UL) poly-plastic, multi-terminal, barrier type. Pressure or clamp type terminals are not acceptable.

Permanent markings shall identify each terminal in accordance with wiring diagrams.

Identification of terminal blocks and terminal points shall be numeric and alphanumeric (ie TB1),

with each terminal block having a unique identifying letter(s) or number(s), and each terminal point having a unique identifying number.

All copper wire terminations at the terminal blocks shall be made with solder less ring-tongue, compression-type connectors with insulated ferrules.

No more than two wires shall be connected to each terminal point.

The vendor shall provide all interconnecting cables, wiring and ground buses required to connect and operate all equipment supplied for installation. Outgoing cables will be supplied and installed by others.

Mating plugs and receptacles shall be permanently labeled to identify correct connection.

Mechanical strain relief shall be provided where needed.

All cabinet or panel cable openings shall be provided with listed (UL) grommets.

All wiring for interface connections shall terminate on terminal block or plug sockets.

Each wire shall be identified at both ends with the wire designation corresponding to the wire number shown on the wire diagrams. Termination conductors for three phase motor leads shall be designated with wire marker tape, utilizing black for A phase, white for 8 phase, and red for C phase.

Nameplates shall be provided for each cabinet, console, and terminal.

All conduit boxes shall be weathertight. Conduit boxes shall be made corrosion resistant.

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 Testing Sufficient vendor testing will be performed on the completed skids to assure that problems are identified in the shop rather than at the job-site. As a minimum the following factory testing will be performed.

Tanks and pressure vessels will be hydrostatically tested 1.5 times the design pressure in accordance with the requirements of latest edition ASME 85PVC, Section Vill.

1. Piping designated as 831.1 will be hydrostatically tested in accordance with the requirements of latest edition of ANSI/ASME 831.1.

2. All other piping will be leak tested prior to shipment.

A Functional Test shall be performed to display the proper electrical and mechanical operation of the equipment and assure system integrity. Purchaser or Purchaser's agent may witness Functional Testing.

Skid Mounting and Factory Preassembly Vendor will mount skid equipment and components on a suitably designed structural skid with due consideration given to lifting and transporting. Design and fabrication to be in accordance with AISC Standards. It is important from a layout standpoint to minimize, to the extent practicable, the area footprint of the skids. Access to chemical tank top for addition of chemicals shall be by means of inclined stairs supported from skid base. Stair design shall be such that tank top is waist-high. If applicable, stairs shall meet minimum requirements of OSHA.

Skid mounted components shall be arranged such that the rear side of large items such as tanks can be located adjacent to a wall without compromising access to components for required operation and maintenance.

Structural frame to be covered with non-skid Diamond deck plate. In addition to lift lugs, the skid will have slots for forklifting capabilities. The mounting skid structural fabrication shall be controlled such that the mounting skid is square and level within plus or minus 1/4 inch of distortion and exhibit high quality workmanship in welding and assembly.

Equipment Location The equipment will be placed as not to interfere with existing plant equipment and provide for the ease of maintenance.

The skids will be placed per Sketch No.SK-9500565-M-2001 - Equipment Location.

Tagging The vendor shall provide valve and component designators.

4.) Evaluation of the Change for releases The modification to the Liquid Waste Processing System will not change the ability to load the demineralizer vessels to the configuration as described in Chapter 11.2 to treat the one percent failed fuel event. The modification will not impact or interface with any equipment important to safety. No malfunction of equipment important to safety will be impacted by this modification in a way that could increase radiological consequences to the public.

5.) Expected maximum exposures to the General Public The expected maximum exposure to a member of the public in the unrestricted area is the same as previously predicted in the FSAR. The design base calculations for the input for the GALE code does not take credit for radioactivity removal by filtration.

Appendix 7: Major Modifications to Radwaste System (Continued)

ODCM Operational Requirement F.3 6.) Comparison of Predicted Releases to Actual Releases for the Period Prior to Change Not applicable to this modification.

7.) Estimate of Exposure to Plant Operating Personnel as a Result of the Change The current dose of 1 filter change out has equaled 0.218 person-rem with an expected changeout to occur 1 every 5 weeks and equates to approximately 2.267 person-rem per year.

8.) Documentation of Review/Approval of the Change in accordance with Technical Specification 6.5 See Attached ESR ¹ 9500565 Rev. 0 Approval Form.

7/10

Page 1 of+

Form I ENGINEERING SERVlCE REQUEST ESR ¹ 9500565 Rov ¹ 0 WR/JO ¹ Other Documents (CR, OEF, etc.)

I /ziti rj Qg/[Sr&/ 6 feud / I/am Primary System ¹ Prfmary System Name Plant/unit HNP 1 6235 RADIOACTtVE FLOOR DRAINS SYSTEM

~ Affected Multiple Systems Title Originator/Phono Demin Skid Enhancement MANESS, JAMES A (TONYI /362-2666 PlantCustomers (PrintName,Sign ate Engineering/Plant Programs (Print Name, Sign, ate)

Mech Maint PITS ALARA '-/%

Etoc/I&C Maint 5 ISI E&RC Regulatory Affairs ( ~@~stssM Installer 7-3-7 Eo iis Review Ikrli 0

-Operations Rsdwasto Mgmt MACS

~~~~~o.<g,(,, se Reviews {Print Name, Sign, Date)

Design VeriTication OgC~

Q Other Reviews Requfred Engineering Disciplines gg Records Attached

{Print Name, Slg Ws/fs AIM. da w Mechanical Electrical/IAC Q7 Civil/Seismic Welding Plant/System Plant/System Plant/System Response Typo DC-MOD ESR BILLYHARREL Quality Class Team ED MCLEAN C Non-Safety Rsd Q BILLYPRIDGEN RALPH PALUMBO e

Due Date EDDIE EGGERS APPROVALS P/J54, revved ors 9-5-VP> <784c7 Is a 10CFR 60.69 Safety Review requfred per ry'AS Before Approval/Imptementation (plant specffic procedural?

NAS Before Closeout PNSC Before Approvaf/Imptementatton

. g Yes Q Safety Screen ONLY NRC Before Implementation Q uSaD N/A {Engineering Disposition Only)

Plant General Manager Q Rosponslbto Engineer MARK W HALE Responsible Manager (Print Name, Sign, Date)

Plant General Manager (Print Name, Sign, Date) pQ r

t~~ (

DCM01a2a 12/19/96

.III'C REcElvm MAR 2 1 1997

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, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses n l r 1P I i

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

A. 50 mile Ingestion Zone Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Skin Sport Fish 2.49 E-02 2.23 E-02 1.67 E - 02 8.77 E-03 1.27 E-02 1.02 E - 02 1.87 E-02 0.00 E+00 Com Fish 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Sport Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Com Invert 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Drinking Water 1.61 E - 02 7.80 E - 01 7.81 E - 01 7.79 E -01 7.78 E -01 7.79 E - 01 7.98 E -01 0.00 E+00 Shoreline 2.36 E - 02 2.36 E-02 2.36 E - 02 2.36 E-02 2.36 E-02 2.36 E-02 2.36 E-02 2.76 E -02 Swimming 1.37 E-04 1.37 E-04 1.37 E-04 1.37 E-04 1.37 E-04 1.37 E-04 1.37 E - 04 0.00 E+00 Boating 6.89 E - 05 6.89 E-05 6.89 E-05 6.89 E -05 6.89 E-05 6.89 E-05 6.89 E-05 0.00 E+00 Irri Veg 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 . 0.00 E+00 Irri 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 0.00 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 Irri Meat 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 ~

0.00 E+00 All Pathways 6.49 E-02 8.27 E-01 8.21 E -01 8.11 E-01 8.15 E-01 8.14 E - 01 8.40 E-01 2.76 E-02 B. Tritium (Hydrosphere)

Bone Liver W. Body Thyroid Kidney Lung Gl-LLI Total 0.00 E+00 4.00 E-03 4.00 E - 03 4.00 E - 03 4.00 E-03 4.00 E - 03 4.00 E-03

2. Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin Plume 1.07 E-02 1.07 E-02 1.07 E-02 1.07 E-02 1.07 E-02 1.07 E-02 1.14 E-02 3.85 E-02 Ground Plane 3.79 E-03 3.79 E-03 3.79 E-03 3.79 E-03 3.79 E-03 3.79 E-03 3.79 E-03 4.45 E-03 Inhalation 2.55 E-02 2.56 E-02 2.84 E-06 2.55 E-02 2.55 E-02 2.67 E-02 2.72 E-02 2.55 E-02 Vegetation 7.95 E-03 8.01 E-03 9.28 E-07 7.94 E-03 7.94 E-03 8.30 E-03 7.94 E-03 7.94 E-03 Cow Milk 1.60 E-03 1.60 E-03 9.13 E-08 1.60 E-03 1.60 E-03 1.64 E-03 1.60 E-03 1.60 E-03 Meat 5 Poultry 3.44 E-03 3.49 E-03 7.32 E-08 3A3 E-03 3.43 E-03 3.46 E-03 3.43 E-03 3.43 E-03 TOTAL 5.30 E-02 5.32 E-02 1.45 E-02 5.30 E-02 5.30 E-02 5.46 E-02 5.54 E-02 8.14 E-02 9/1

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses n I er lie D ivii ni i B n

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

Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Skin ADULT Fish 1.29 E-02 1.28 E-02 1.05 E-02 5.31 E-03 7.53 E-03 6.10 E-03 1.22 E-02 Drinking 1.68 E-06 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 1.05 E-04 1.08 E-04 Shoreline 4.10 E-03 4.10 E-03 4.10 E-03 4.10 E-03 4.10 E-03 4.10 E-03 4.10 E-03 4.78 E-03 Boating 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 TOTAL 1.70 E-02 1.71 E-02 1.48 E-02 9.58 E-03 1.18 E-02 1.04 E-02 1.64 E-02 4.78 E-03 TEEN Fish 1.41 E-02 1.25 E-02 7.69 E-03 4.30 E-03 6.71 E-03 5.30 E-03 9.34 E-03 Drinking 2.29 E-06 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.06 E-04 1.09 E-04 Shoreline 3.42 E-03 3.42 E-03 3.42 E-03 3.42 E-03 3.42 E-03 3A2 E-03 3 42 E-03 3.98 E-03 Boating 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 TOTAL 1.76 E-02 1.61 E-02 1.13 E-02 7.88 E-03 1.03 E-02 8.89 E-03 1.29 E-02 3.98 E-03 CHILD Fish 2.12 E-02 1.27 E-02 6.35 E-03 4.12 E-03 6.52 E-03 5.05 E-03 6.16 E-03 Drinking 6.92 E-06 2.03 E-04 2.03 E-04 2.03 E-04 2.03 E-04 2.03 E-04 2.05 E-04 Shoreline 1.71 E-03 1.71 E-03 1.71 E-03 1.71 E-03 1.71 E-03 1.71 E-03 1.71 E-03 1.99 E-03 Boating 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 6.21 E-05 TOTAL 2.29 E-02 1.47 E-02 8.32 E-03 6.10 E-03 8.50 E-03 7.03 E-03 8.13 E-03 1.99 E-03 9/2

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses n I r ra P Ii Du A ivi i In i i B n a n in

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

T. Body Gl-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 5.05 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.26 E-04 1.46 E-03 Ground Plane 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 4.64 E-04 Inhalation 5.24 E-04 5.26 E-04 6.71 E-08 5.24 E-04 5.24 E-04 5.53 E-04 5.73 E-04 5.23 E-04 TOTAL 1A2 E-03 1.43 E-03 9.00 E-04 1A2 E-03 1.42 E-03 1.45 E-03 1.49 E-03 2.45 E-03 TEENAGER Plume 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.05 E-04 5.26 E-04 1.46 E-03 Ground Plane 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 4.64 E-04 Inhalation 5.27 E-04 5.29 E-04 9A4 E-08 5.27 E-04 5.27 E-04 5.64 E-04 5.99 E-04 5.27 E-04 TOTAL 1.43 E-03 1.43 E-03 9.00 E-04 1.43 E-03 1.43 E-03 1.46 E-03 1.52 E-03 2.45 E-03 CHILD Plume 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.06 E-04 5.26 E-04 1.46 E-03 Ground Plane 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 3.94 E-04 4.64 E-04 Inhalation 4.66 E-04 4.66 E-04 1.28 E-07 4.66 E-04 4.66 E-04 5.07 E-04 5.24 E-04 4.66 E-04 TOTAL 1.37 E-03 1.37 E-03 9.00 E-04 1.37 E-03 1.37 E-03 1.41 E-03 1.44 E-03 2.39 E-03 9/3

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses I sur Dos Mo i h li

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

Bone Liver T. Body Thyroid Kidney Lung Gi-LLI Skin ADULT Fish 2.70 E-02 2.69 E-02 2.20 E-02 1.12 E-02 1.58 E-02 1.28 E-02 2.55 E-02 Drinking 1.22 E-04 7.66 E-03 7.67 E-03 7.65 E-03 7.65 E-03 7.66 E-03 7.87 E-03 Shoreline 2.46 E-03 2.46 E-03 2.46 E-03 2.46 E-03 2.46 E-03 2.46 E-03 2.46 E-03 2.87 E-03 Swimming 1.49 E-04 1.49 E-04 1.49 E-04 1.49 E-04 1.49 E-04 1.49 E-04 1.49 E-04 Boating 1.71 E-04 1.71 E-04 1.71 E-04 1.71 E-04 1.71 E-04 1.71 E-04 1.71 E-04 TOTAL 2.99 E-02 3.74 E-02 3.25 E-02 2.16 E-02 2.62 E-02 2.32 E-02 3.62 E-02 2.87 E-03 TEEN Fish 2.83 E-02 2.50 E-02 1.54 E-02 8.59 E-03 1.34 E-02 1.06 E-02 1.87 E-02 Drinking 1.17 E-04 5 41 E-03 5.41 E-03 5.39 E-03 5.39 E-03 5.40 E-03 5.54 E-03 Shoreline 1.37 E-02 1.37 E-02 1.37 E-02 1.37 E-02 1.37 E-02 1.37 E-02 1.37 E-02 1.60 E-02 Swimming 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 2.24 E-04 Boating 2.48 E-04 2.48 E-04 2.48 E-04 2.48 E-04 2 48 E-04 2.48 E-04 2.48 E-04 TOTAL 4.26 E-02 4.46 E-02 3.50 E-02 2.82 E-02 3.30 E-02 3.02 E-02 3.84 E-02 1.60 E-02 CHILD Fish 3.65 E-02 2.19 E-02 1.09 E-02 7.11 E-03 1.13 E-02 8.71 E-03 1.06 E-02 Drinking 3.53 E-04 1.04 E-02 1.04 E-02 1.03 E-02 1.03 E-02 1.03 E-02 1.05 E-02 Shoreline 2.87 E-03 2.87 E-03 2.87 E-03 2.87 E-03 2.87 E-03 2.87 E-03 2.87 E-03 3.35 E-03 Swimming 7.45 E-05 7.45 E-05 7.45 E-05 7.45 E-05 7.45 E-05 7.45 E-05 7.45 E-05 Boating 9.32 E-05 9.32 E-05 9.32 E-05 9.32 E-05 9.32 E-05 9.32 E-05 9.32 E-05 TOTAL 3.99 E-02 3.53 E-02 2.44 E-02 2.05 E-02 2.46 E-02 2.21 E-02 2 41 E-02 3.35 E-03 INFANT Fish 0.00 E+00 0.00 E joo 0.00 E+00 0.00 E j00 0.00 E+00 0.00 E+00 0.00 E+00 Drinking 2.83 E-04 1.02 E-02 1.02 E-02 1.01 E - 02 1.01 E-02 1.02 E-02 1.02 E-02 Shoreline 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E joo 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 TOTAL 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 E-02 000 E+00 9/4

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses I re D s h P

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

A. Maximum Hypothetical Individual - Exposure from Noble Gases, Particulates, lodines, and Tritium T. Body Gl-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.31 E-03 1.19 E-02 Ground Plane 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.90 E-03 Inhalation 4.44 E-03 4.46 E-03 5.54 E-07 4.44 E-03 4.44 E-03 4.69 E-03 4.84 E-03 4.44 E-03 Vegetation 7.57 E-03 7.76 E-03 4.55 E-07 7.56 E-03 7.55 E-03 7.76 E-03 7.55 E-03 7.55 E-03 Cow Milk 1.79 E-03 1.79 E-03 1.69 E-07 1.79 E-03 1.79 E-03 1.87 E-03 1.79 E-03 1.79 E-03 Meat 5 Poultry 7.65 E-04 7.99 E-04 3.44 E-08 7.63 E-04 7.61 E-04 7.77 E-04 7.61 E-04 7.61 E-04 TOTAL 2.03 E-02 2.06 E-02 5.77 E-03 2.03 E-02 2.03 E-02 2.09 E-02 2.09 E-02 2.83 E-02 TEENAGER Plume 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.31 E-03 1.19 E-02 Ground Plane 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.90 E-03 Inhalation 4.47 E-03 4.49 E-03 7.79 E-07 4.47 E-03 4.47 E-03 4.78 E-03 5.06 E-03 4.47 E-03 Vegetation 8.91 E-03 9.09 E-03 4.42 E-07 8.89 E-03 8.87 E-03 9.05 E-03 8.87 E-03 8.87 E-03 Cow Milk 2.33 E-03 2.33 E-03 3.07 E-07 2.33 E-03 2.33 E-03 2.45 E-03 2.33 E-03 2.33 E-03 Meat 8c Poultry 4.57 E-04 4.74 E-04 2.86 E-08 4.55 E-04 4.54 E-04 4.65 E-04 4.54 E-04 4.54 E-04 TOTAL 2.19 E-02 2.22 E-02 5.77 E-03 2.19 E-02 2.19 E-02 2.25 E-02 2.26 E-02 2.99 E-02 CHILD Plume 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.31 E-03 1.19 E-02 Ground Plane 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.90 E-03 Inhalation 3.96 E-03 3.96 E-03 1.06 E-06 3.96 E-03 3.96 E-03 4.30 E-03 4.43 E-03 3.95 E-03 Vegetation 1.39 E-02 1.40 E-02 8.33 E-07 1.39 E-02 1.39 E-02 1.41 E-02 1.39 E-02 1.39 E-02 Cow Milk 3.68 E-03 3.68 E-03 7.46 E-07 3.68 E-03 3.68 E-03 3.92 E-03 3.68 E-03 3.68 E-03 Meat 5 Poultry 5.54 E-04 5.58 E-04 5.31 E-08 5.50 E-04 5.48 E-04 5.66 E-04 5.48 E-04 5.48 E-04 TOTAL 2.79 E-02 2.80 E-02 5.77 E-03 2.78 E-02 2.78 E-02 2.87- E-02 2.84 E-02 3.58 E-02 INFANT Plume 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.15 E-03 4.31 E-03 1.19 E-02 Ground Plane 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.62 E-03 1.90 E-03 Inhalation 2.27 E-03 2.28 E-03 8.35 E-07 2.28 E-03 2.27 E-03 2.59 E-03 2.58 E-03 2.27 E-03 Cow Milk 5.58 E-03 5.58 E-03 1.56 E-06 5.58 E-03 5.58 E-03 6.18 E-03 5.58 E-03 5.58 E-03 TOTAL 1.36 E-02 1.36 E-02 5.77 E-03 1.36 E-02 1.36 E-02 1.45 E-02 1.41 E-02 2.17 E-02 9/5

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses En I f P i

2. Individual Dose Due to Gaseous Effluents (mrem/yr.l B. Maximum Real Individual - Exposure from Noble Gases, Particulates, lodines, and Tritium T. Body Gl-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.62 E-04 1.83 E-03 Ground Plane 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 6 47 E-04 Inhalation 6.80 E-04 6.83 E-04 8.39 E-08 6.80 E-04 6.80 E-04 7.18 E-04 7.40 E-04 6.80 E-04 Vegetation 1.16 E-03 1.23 E-03 1.55 E-07 1.16 E-03 1.16 E-03 1.23 E-03 1.16 E-03 1.16 E-03 Meat 5 Poultry 1.18 E-04 1.29 E-04 1.17 E-08 1.17 E-04 1.17 E-04 1.22 E-04 1.17 E-04 1.17 E-04 TOTAL 3.15 E-03 3.23 E-03 1.19 E-03 3.14 E-03 3.14 E-03 3.25 E-03 3.22 E-03 4.43 E-03 TEENAGER Plume 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.62 E-04 1.83 E-03 Ground Plane 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 6.47 E-04 Inhalation 6.85 E-04 6.87 E-04 1.18 E-07 6.85 E-04 6.85 E-04 7.31 E-04 7.72 E-04 6.85 E-04 Vegetation 1.37 E-03 1.43 E-03 1.50 E-07 1.36 E-03 1.36 E-03 1.42 E-03 1.36 E-03 1.36 E-03 Meat 5 Poultry 7.07 E-05 7.64 E-05 9.75 E-09 7.00 E-05 6.95 E-05 7.35 E-05 6.95 E-05 6.95 E-05 TOTAL 3.31 E-03 3.38 E-03 1.19 E-03 3.31 E-03 3.30 E-03 3.41 E-03 3A1 E-03 4.59 E-03 CHILD Plume 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.62 E-04 1.83'-03 Ground Plane 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 5.50 E-04 6.47 E-04 Inhalation 6.06 E-04 6.06 E-04 1.60 E-07 6.06 E-04 6.06 E-04 6.57 E-04 6.76 E-04 6.05 E-04 Vegetation 2.15 E-03 2.17 E-03 2.84 E-07 2.13 E-03 2.12 E-03 2.22 E-03 2.12 E-03 2.12 E-03 Meat Ik Poultry 8.58 E-05 8.74 E-05 1.81 E-08 8.46 E-05 8.40 E-05 8.99 E-05 8.39 E-05 8.39 E-05 TOTAL 4.02 E-03 4.05 E-03 1.19 E-03 4.01 E-03 4.00 E-03 4.15 E-03 4.09 E-03 5.29 E-03 INFANT Plume 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.36 E-04 6.62 E-04 1.83 E-03 Ground Plane 5.50 E-04 4.50 E-04 4.50 E-04 4.50 E-04 4.50 E-04 4.50 E-04 4.50 E-04 6.47 E-04 Inhalation 3.48 E-04 3.48 E-04 1.27 E-07 3.48 E-04 3.48 E-04 3.96 E-04 3.94 E-04 3.48 E-04 TOTAL 1.53 E-03 1.53 E-03 1.19 E-03 1.53 E-03 1.53 E-03 1.58 E-03 1.61 E-03 2.82 E-03 9/6

Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses re D

3. Annual Air Dose (mrad)

A. Maximum Hypothetical Individual: Beta = 1.68 E-02 Gamma = 6.79 E-03 B. Maximum Real Individual: Beta = 2.58 E-03 Gamma = 1.04 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.

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Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses I 4 MaorA I 'I i i o

1. Doses Due to Liquid Effluents A. Dilution Factors x r w Harris Lake 1.00 E+00 Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 5.60 E+01" Shoreline, Drinking Water

{for Harnett County, Liilington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 5.60 E+014 Boating

" The dilution of 5.60 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 {54.7 CFS) and the average flow of the Cape Fear River {3062.7 CFS) as measured at the gauging station at Lillington, N.C. The above information was by provided by the United States Geological Service for 1997.

B. Populations Affected 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 Fuquay-Varina 2.68 E+03 persons Drinking Water Holly Springs 2.27 E+02 persons Drinking Water Harris Lake/

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

Raven Rock Park 5.00 E+04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shoreline 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:

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Annual Radioactive Effluent Release Report January 1, 1997 to December 31, 1997 Appendix 9: Assessment of Radiation Doses I 4 m i n I i D s ni

2. Doses Due to Gaseous Effluents A. The 50 mile Ingestion Zone population is 1.68 E+06 persons.

The Maximum Real Individual is located at 2897 meters ("2.8 miles) in the ENE sector. This is based on the 1997 land use census with applicable pathways.

C. The Maximum Hypothetical Individual is located on the site boundary at 2140 meters in the SSW 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 <br />0.243 hours <br />0.00145 weeks <br />3.33318e-4 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s/day equals 480hours/year.

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

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.

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