ML18011A802

Semiannual Radioactive Release Rept Jul-Dec 1994.

ML18011A802
Person / Time
Site:	Harris
Issue date:	12/31/1994
From:	Denise Edwards CAROLINA POWER & LIGHT CO.
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ML18011A800	List: ML18011A799 ML18011A802 ML18011A803
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NUDOCS 9503060120
Download: ML18011A802 (52)

Text

a Carolina Power dt Light Shearon Harris Nuclear Power Plant R

License No. NPF-063 AL 1UUMOACTD'E EFFLUENT RELEASE REPORT July 1, 1994 to December 31, 1994 Prepared by:

Specialist - E&C Reviewed by:

Man er - E&C Reviewed by:

Mana - Environmental & Radiation Control Approved by:

General Manage - Harris Plant 95030b0120 95022b PDR ADOCK 05000400 PDR

S

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 2/8 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 S/1

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

1. Inoperability of Liquid Effluent Monitors 6/1

2. Inoperability of Gaseous Effluent Monitors 6/2

3. Unprotected Outdoor Tanks Exceeding Limits 6/3

4. Gas Storage Tanks Exceeding Limits 6/4 Appendix 7. Major Modifications to Radwaste System 7/1 Appendix 8. Meteorological Data 8/1 Appendix 9. Assessment of Radiation Doses for Calendar Year 1994

1. Population Doses outside Site Boundary due to Effluent Releases 9/1 Doses to the General Public Due to Activities Inside the Site Boundary 9/2

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

Introduction This Semiannual Radioactive Effluent Release Report is prepared in accordance with Shearon Harris Nuclear Power Plant's 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 July 1, 1994 to December 31, 1994. During this period, the plant continued in Cycle 6 operation. The radiological dose assessment from radioactive releases during January 1, 1994 thru December 31, 1994 is in Appendix 9 of this report.

Discussion The quantities of radioactive gaseous and liquid effluents and solid waste are reported using the format per Regulatory Guide 1.21 (Rev. 1)

Appendix B. As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container, and solidification agent or absorbent.

The source term reported for both semiannual report periods in 1994 were combined for determining the annual radiological dose impact from plant operations. 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.

Appendix 1: Supplemental Information I. Re ulator Limits A. Fission and Activation Gases:

Tech. Spec ~ Maximum Instantaneous Release Rate Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr 10CRF20, Limits Annual Average Concentrations as specified in 10CRF20, Appendix B, Table II, Column 1. This is based on 100 mrem/yr.

10CFR50, Appendix I For Calendar Quarter Gamma Dose <5 mrad Beta Dose <10 mrad For Calendar Year Gamma Dose <10 mrad Beta Dose <20 mrad B. Iodine - 131 and 133, Tritium, and Particulates )8 day half-lives:

Tech. Spec. Maximum Instantaneous Release Rate Inhalation dose (only) to a child to any organ <1500 mrem/yr 10CFR20 Limits Annual Average Concentrations as specified in 10CRF20, Appendix B, Table II, Column 1. This is based on 50 mrem/yr.

10CFR50, Appendix I (Organ Doses)

For Calendar Quarter <7.5 mrem For Calendar Year <15 mrem C. Liquids:

Technical Specification Maximum Instantaneous Release Rate is ten times the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 pCi/ml total activity.

10CRF20 The annual average concentrations to be less than the concentrations specified in 10CFR20, Appendix B, Table II, Column 2. (Based on 50 mrem/yr) 10CFR50, Appendix I For Calendar Quarter Total Body Dose <1.5 mrem Any Organ Dose <5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 mrem

D. Average Energy (E)

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

8 Appendix 1 (Continued): Supplemental Information II. Measurements and Approximations of Total Radioactivity A. Continuous Gaseous Releases

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

3. Particulates The particulate activity released from batch releases are 1/3

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 Analysis are performed on quarterly composites times the volume released during the quarter to calculate the activity released.

D. Estimated Total Errors

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

2. Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, non-steady release flow rate, sampling and mixing losses, and volume determinations.

Appendix 1 (Continued): Supplemental Information III. Batch Releases A. Liquid Batch Releases

1. Number of batch releases 6.40 E+01

2. Total time period for batch releases 3.95 E+04 min

3. Maximum time of a batch release 9.29 E+02 min

4. Average time for a batch release 6.17 E+02 min

5. Minimum Time for a batch release 2.29 E+02 min

6. Average stream flow during periods of release 1.50 E+04 gpm B. Gaseous Batch Releases Number of batch releases 0.00 E+00

2. Total time period for batch releases 0.00 E+00 min

3. Maximum time of a batch release 0.00 E+00 min

4. Average time for a batch release 0.00 E+00 min

5. Minimum Time for a batch release 0.00 E+00 min

6. Abnormal Releases

a. Liquid No abnormal liquid releases were made in this period.

b. Gaseous No abnormal gaseous releases were made in this period.

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

1. LLDs for Gaseous Effluents Nuclide Ci cc Gross Alpha 1.80 E-15 H-3 7.97 E-09 Ar-41 3.79 E-08 Kr-85 6.09 E-06 Kr-85m 2.12 E-08 Kr-87 8.88 E-08 Kr-88 2.32 E"08 Xe-131m 6.21 E-07 Xe-133 6.96 E-08 Xe-133m 4.65 E-07 Xe-135 2.07 E-08 Xe-135m 4.65 E-07 Xe-138 5.94 E-07 I-131 3.22 E-14 I-133 2. 73 E-14 I-135 7.97 E-14 Cr-51 1.17 E-13 Mn-54 1.66 E-14 Co-58 1.33 E-14 Fe-59 3. 87 E-14 Co-60 1.86 E-14 Zn-65 7. 55 E" 14 Sr-89 3.00 E-15 Sr-90 1.00 E-15 Mo-99 1.48 E-13 Cs-134 1.01 E-14 Cs-137 2.63 E-14 Ba-140 4.13 E-14 La-140 2.41 E-14 Ce-141 1.26 E-14 Ce-144 3.89 E-14

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

LLDs for Liquid Effluents Nuclide ~Ci ml Nuclide Ci ml Gross Alpha 4.10 E-08 Sb-122 5.06 E-08 H- 3 2.55 E-06 Sb-124 1.68 E-08 Be- 7 2.24 E-07 Sb-125 9.36 E-08 Na-24 3.15 E-08 I-131 2.67 E-08 Cr-51 2.61 E-07 I-132 3.31 E"08 Mn-54 2.01 E-08 I-133 1;33 E-07 Fe-55 2.00 E-07 I-135 1.25 E-07 Co-57 1.73 E-08 Te-132 2.31 E-08 Co-58 1.98 E-08 Xe-131m 9.21 E-07 Fe-59 4.64 E-08 Xe-133 5.36 E-08 Co-60 3.89 E-08 Xe-133m 1.91 E-07 Ni-63 2.00 E-07 Xe-135 2.59 E-08 Zn-65 8.67 E-08 Cs-134 3.08 E-08 Sr-89 1.50 E-08 Cs-137 3.38 E-08 Sr-90 5.00 E-09 Cs-138 5.62 E-07 Sr-92 4.52 E-08 Ba-140 9.60 E-08 Y-93 1.34 E-07 La-140 3.02 E-08 Nb-95 3.26 E-08 Ce-141 4.84 E-08 Zr-95 3.36 E-08 Ce-143 6.07 E-08 Mo-99 2.04 E-07 Ce-144 2.04 E-07 Tc-99m 2.46 E-08 Pr-144 1.17 E-06 Ru-103 2.51 E-08 Hf-181 2.62 E-08 Ag-110m 5.93 E-08 2/2

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

A. Fission and activation gases

1. Total release Ci 3.80 E+01 3.82 E+01 3.43 E+01

2. Average release rate for period /rCi/sec 4.78 E+00 4.81 E+00

3. Percent of Tech Spec limit 9.26 E-02 1.15 E-01 B. lodines

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

2. Average release rate for period yCi/sec 0.00 E+00 0.00 E+00

3. Percent of Tech Spec limit " 1.86 E-03 2.08 E-03 C. Particulates

1. Particulates with half-lives ) 8 days Ci 1.77 E-05 2.02 E-05 3.37 E+01

2. Average release rate for period yCi/sec 2.22 E-06 2.54 E-06

3. Percent of Tech Spec limit " 1.86 E-03 2.08 E-03

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

1. Total release Ci 2.84 E-03 7.94 E-04 3.37 E+01

2. Average release rate for period /rCi/sec 3.58 E-04 9.99 E-05

3. Percent of Tech Spec limit " 1.86 E-03 2.08E-03 The Percent of Technical Specification limit applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly Technical Specification limit is 7.5 millirem. The most critical organ for both quarters was the lung.

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

2/4

Appendix 2 (Continued): Effluent and Waste Disposal Report 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 ases xenon-131m Ci < LLD < LLO Note 1 Note 1 xenon-133 Ci 3.23 E+01 2.44 E+01 Note 1 Note 1 xenon-133m Ci < LLD < LLD Note 1 Mote 1 xenon-135 Ci 5.67 E+00 1,38 E+01 Note 1 Note 1 xenon-135m Ci < LLD < LLD Note 1 Note 1 xenon-138 Ci < LLD < LLD Note 1 Note 1 ar on-41 Ci < LLD < LLD Note 1 Note 1 kr ton-85 Ci < LLD < LLD Note 1 Note 1 kr ton-85m Ci < LLD < LLD Note 1 Note 1 kr ton-87 Ci < LLD < LLO Note 1 Note 1 kr ton-88 Ci < LLD < LLD Note 1 Note 1 Total for cried Ci 3.80 E+01 3.82 E+01

2. lodines iodine-131 Ci < LLD < LLD No e1 Note 1 iodine-133 Ci < LLD < LLD Note 1 Note 1 iodine-1 35 Ci < LLD < LLD Note 1 Mote 1 Total for cried Ci < LLD < LLD

3. Particulates chromium.51 Ci < LLD < LLD Note 1 Note 1 man anese-54 Ci < LLD < LLD No e 1 Note 1 cobal -58 Ci < LLD < LLD No e 1 No e 1 iron.59 Ci < LLD < LLD Note 1 Note 1 cobalt-60 Ci 1.77 E-05 2.02 E-05 Note 1 Note 1 zinc-65 Ci < LLD < LLD Note 1 Note 1 strontium-89 Ci < LLD < LLD Note 1 Note 1 s ron ium-90 Ci < LLD < LLD Note 1 Note 1 mol bdenum-99 Ci < LLD < LLD Note 1 Note 1 cesium-1 34 Ci < LLD < LLD Note 1 Note 1 cesium-137 Ci < LLO < LLD Note 1 Note 1 barium-140 Ci < LLD < LLD No e 1 Note 1 lanthanum-140 Ci < LLO < LLD Note 1 Mote 1 cerium-141 Ci < LLD < LLD No e 1 Note 1 corium-144 Ci < LLD < LLD Note 1 Note 1 Total for cried 1.77 E-05 2.02 E-05 Note 1 - No Batch Releases were made during third or fourth quarters 2/S

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

A. Fission and Activation products

1. Total release (not including tritium, gases, Ci 1.05 E.02 6.24 E-03 3.53 E+01 alpha)

2. Average diluted concentration during period yCi/ml 1.32 E-09 8.87 E-10

3. Percent of applicable limit 2.00 E-02 1.00 E-02 B. Tritium

1. Total release Ci 8.41 E+01 2.49 E+02 3.53 E+01

2. Average diluted concentration during period yCi/ml 1.06 E-05 3.53 E-05

3. Percent of applicable limit 1.06 E+00 3.53 E+00 C. Dissolved and entrained gases

1. Total release Ci 7.27 E.04 8.15 E-03 3.53 E+01

2. Average diluted concentration during period yCi/ml 9.16 E-11 1.16 E*09

3. Percent of applicable limit 4.58 E-05 5.80 E-04 D. Gross alpha radioactivity

1. Total release Ci < LLD < LLD 3.53 E+01 E. Volume of waste released (prior to dilution) liters 2.15 E+06 1.70 E+06 1.00 E+01 F. Volume of dilution water used during period liters 7.94 E+09 7.03 E+09 1.00 E+01

Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B  : LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 chromium-51 Ci Note 1 Note 1 2.48 E-04 1.53 E-05 manganese-54 Ci Note 1 Note 1 5.83 E-05 5.90 E-05 iron-55 Ci Note 1 Note 1 <LLD 3.38 E-04 cobalt-58 Ci Note 1 Note 1 1.84 E-03 6.17 E-04 iron-59 Ci Note 1 Note 1 < LLD < LLD cobalt.60 Ci Note 1 Note 1 8.14 E-04 6.68 E-04 nicke!.63 Ci Note 1 Note 1 8.41 E-04 2.35 E-04 zinc-65 Ci Note 1 Note 1 < LLD < LLD strontium-89 Ci Note 1 Note 1 < LLD < LLD strontium-90 Ci Note 1 Note 1 < LLD < LLD zirconium-95 Ci Note 1 Note 1 1.06 E-05 1.06 E-05 niobium-95 Ci Note 1 Note 1 5.74 E-05 2.40 E-05 technicium-99m Ci Note 1 Note 1 < LLD < LLD molybdenum-99 Ci Note 1 Note 1 < LLD < LLD ruthenium-103 Ci Note 1 Note 1 1.60 E-05 < LLD antimony-125 Ci Note 1 Note 1 6.00 E-03 4.16 E-03 iodine-131 Ci Note 1 Note 1 2.00 E-04 6.68 E-06 iodine-133 Ci Note 1 Note 1 < LLD < LLD cesium-134 Ci Note 1 Note 1 1.93 E-04 9.42 E-05 cesium-137 Ci Note 1 Note 1 2.05 E-04 1.26 E-04 barium-140 Ci Note 1 Note 1 < LLD < LLD lanthanum-140 Ci Note 1 Note 1 < LLD < LLD cerium-141 Ci Note 1 Note 1 < LLD < LLD TOTAL Ci Note 1 Note 1 1.05 E-02 6.35 E-03 xenon-133 Ci Note 1 Note 1 6.27 E-04 7.66 E-03 xenon-133m Ci Note 1 Note 1 < LLD 1.72 E-04 xenon-135 Ci Note 1 Note 1 7.27 E-04 8.15 E-03 Note 1 - No Continuous Releases were made during third or fourth quarters

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

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

A. Type of Waste

a. Spent Resin, filter sludge, etc.

No waste of this type shipped

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

Number of Shipments 13 Activity Shipped 6.16 E-01 Ci Estimated Total Error 10%'.93 Quantity Shipped E+00 m~

Solidification Agent N/A Container Type Strong Tight Package NRC-Approved Package Shipment Form Dewatered

c. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/8

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

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

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

a. Spent Resin, filter sludge, etc.

No waste of this type shipped

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

Percent Total Activity Nuclide Composition Ci C-14 8.42 E-04 5.19 E-06 Fe-55 7.05 E+01 4.35 E-01 Co-57 4.91 E-03 3.03 E-05 Co-58 1.46 E+00 8.99 E"03 Co-60 2.27 E+01 1.40 E-01 Ni-63 4.93 E+00 3.04 E"02 Mn-54 1.17 E-01 7.21 E-04 Sr-89 4.29 E-03 2.65 E-05 Nb-95 6.31 E-02 3.89 E-04 Zr-95 3.20 E-02 1.97 E-04 Cs-134 8.61 E-03 5.31 E-05 Cs-137 9.77 E-02 6.02 E-04 Ce-144 2.80 E-03 1.73 E-05 Am-241 7.71 E-06 4.75 E-08 Pu-241 1.54 E-05 9.51 E-08 Cm-242 1.95 E-08 1.20 E-10

c. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/9

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

C. Solid Waste Disposal Number of Shipments

• 13 Mode of Transportation Truck Destination Barnwell, S.C.

The thirteen (13) type 1.A.b shipments were made from Scientific Ecology Group (SEG) Processing Facility in Oak Ridge, Tennessee.

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

No waste of this type was shipped during this report period.

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

No waste of this type was shipped during this report period.

Irradiated Fuel Shipments (Disposition)

No irradiated fuel was shipped during this report period.

2/10

Appendix 3 : Changes to Process Control Program (PCP)

Technical Specification 6.13 The SHNPP Process Control Program (PCP) has had no major changes for this report period.

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

Technical Specification 6.14 The following changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.

Title Page Revise to Rev. 5.

Table of Contents Change Page Numbers to match new pages.

List of Tables Change Page numbers Add Table 3.3.-3 Editorial Change to break out Tables A-5/A-6 from A-7/A-8 and correct the titles of the Tables. These titles were inadvertently combined into a single description in Rev. 4. No change to the content of the Tables.

List of Figures Change Page Numbers List of Effective Pages List revised Page Numbers Section 1 - Introduction No changes.

Section 2 - Liquid Effluents Section 2.0 Change the last sentence from:

"The SETP EQN option is set to STD" to "The SETP EQN option is set to LOW ACT" This change changes the method used to determine the setpoint adjustment factor (SAF), which is used in the liquid release setpoint calculation.

With the option set to STD, the SAF is calculated using the dilution required for all nuclides. With the option set to LOW ACT, the SAF is calculated using the dilution required for gamma emitters only.

Section 2.1, Equation 2.1-9 Revise the calculation of the setpoint adjustment factor S~) as described above.

Section 2.1, Equation 2.1-13 Change the background parameter from "B" to "Bkg". B refers to background in pCi/ml. Bkg refers to background in cpm. Error in the translation to Rev. 4

Section 3 - Gaseous Effluents Section 3.0 Change release point to discharge point to more closely tie the ODCM and Effluent Management System (EMS).

Section 3.1 Revised descriptive text.

Sections 3.1.1 and 3.1.2 These sections have been completely re-written to describe the methodology used by the EMS software.

Section 3.1.3 Deleted the set point value and its associated reference.

Table 3.1-1 Change column headings. Other minor editorial corrections and clean-up.

No change to any values.

Table 3.1-2 Editorial Changes and clean-up. No change to any values.

Table 3.1-3 New table to incorporate information out of section 3.1. The purpose is to clean up Section 3. 1 by removing a lot of redundant text and values and putting it in a tabular form.

Section 3.2 and 3.2.1 Editorial Changes Table 3.2-2 Table has been revised to show the results of the 1994 Land Use census.

Section 3.3.1 Add (2. 19 kilometers) in (1) .

Change the equation numbers for equations 3.3-3 through 3.3-12 to put them in order. Revision 4 moved some text around but the equation numbers did not change.

Equations 3.3-3 to 3.3-7 - No change to equations.

Equation 3.3-7a - Change the value for cc/ft3 from 28320 to 28316.85, the value the EMS uses.

Equations 3.3-8 to 3.3-9 - No change to equations.

Section 3.3.1 (3)

Revise to describe new methodology for projection of doses. Same as liquid, which was changed in Rev. 4.

Equations 3.3-10 to 3.3-12 Changes to match the current methodology of this section 4/2

Section 3.3.2 (1)

Editorial Changes.

Section 3.3.2 (2)

Revise to describe new methodology for projection of doses. Same as liquid, which was changed in Rev. 4.

Section 4 - Radiological Environmental Monitoring Program No Changes Section 5.0 - Interlaboratory Comparison Studies No changes.

Section 6.0 - Total Dose No Changes Section 7.0 - Changes to the ODCM No changes.

Appendix A No changes.

Appendix B Heading "B.1" had a typo ("2.1" to "B. 1")

Appendix B, B.2.1 Correct the units for the inhalation pathway R.

3.)

values.

Appendix C No Changes Various places General clean-up of text from Rev. 4, especially to the spacing of the X/Q AND D/Q terms, uCi to pCi, and pCi to pCi. These changes are not marked with rev bars.

4/3

ODCM Revision 5 Impact of Changes The ODCM is an administrative program set up to control the release of radioactive effluents to the environment. Nothing in the ODCM is concerned with the safe shutdown of .the plant or the mitigation of any analyzed accident. These changes to the ODCM do not have any affect on the probability of occurrence or the consequences of any analyzed accident. No equipment important to safety is affected in any way, nor is any possibility of a different accident created. This change does not have any impact on any Technical Specification margin of safety since there will be no change to the effluent mix or quantity.

Revision 5 to the Offsite Dose Calculation Manual makes the following changes:

Changes in methodology and terminology due to implementation of new EMS software for gaseous releases.

2. Changes to the Liquid Effluent Setpoint Adjustment Factor.

3. Incorporation of the 1994 Land Use Census data.

4. Editorial Changes Since the ODCM affects the release of effluents to the environment and the resulting dose to the public, the impact of each of the major changes is discussed below. A detailed description of all changes is included with the ODCM Rev. 5 submittal reviewed and approved by the Plant Nuclear Safety Committee (PNSC) .

Changes in methodology and terminology due to implementation of new EMS software.

Section 3.0, Gaseous Effluents, has been rewritten to reflect the new EMS. 1n some cases, the change has been to rename a parameter so that it matches the EMS terminology. In other cases, whole sections have been replaced with the new methodology and terminology.

Section 3.1 Monitor Alarm Setpoint Determination This section has been completely rewritten using EMS terms and equations to show the methodology of the new EMS software. The EMS takes a different approach to the set point. methodology than does the ODCM.

This results in different terms, intermediate calculations, and input requirements. However, both the previous ODCM software and the EMS software are built using the same basic assumptions. There are, therefore, few differences between either the set, point calculation or the dose calculated for each release.

4/4

Sections 3.3.1.3 and 3.3.2.2 Another change between the ODCM and EMS is the method used to calculate the 31-day projected dose. The ODCM method uses accumulated dose and a projection factor based on reactor power. The EMS uses the dose projected for in the open releases and a projection factor based on time. Both methods must compare the resulting dose against the same limits .

ODCM Method D1 = D2 or D1 ~

P2 ~ D2 P1 P2 P1 where:

Dl Dose of previous month D2 31 day projected dose Pl Average Power Level of previous month P2 Average Power Level of projected period EMS Method (D7', p) + D where:

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

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

Dar Additional Anticipated Dose (not normally used).

NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", says that "The calculation of projected cumulative dose impact that, could result from the proposed operation should use the methodology in section 4.3 of this manual".

Section 4.3 discusses the requirements for implementing 10CFRSO. Since both the ODCM and EMS use accepted methods for calculating the dose, and NUREG-0133 does not discuss the method for calculating the projection, both methods are equally valid.

Changing to use the EMS method of doing 31-day dose projections will not have any safety impact on the operation of the SHNPP.

Changes to the Liquid Effluent Setpoint Adjustment Factor.

This change revises the method used to determine the setpoint adjustment factor, S~>, which is used in the liquid release setpoint calculation. ODCM Revision 3 implemented a setpoint method that excluded H-3 from the setpoint adjustment factor. This methodology was changed to be more conservative with the incorporation of the EMS software in Revision 4. With the option set to STD, S~; is calculated using the dilution required by the entire mix of radionuclides including H-3 and other non-gamma emitters. With the option set to LOW ACT, S~> is calculated using the dilution required for gamma emitters only. Changing the S~~ to LOW ACT will be changing back to essentially the same as the Revision 3 method.

The radiation monitors used to control and terminate the effluent releases are gamma sensitive, and do not respond to H-3. Because of the high non-gamma (H-

3) component of typical liquid effluent and the low cooling tower discharge flow rates, the dilution factor needs to be based on the gamma emitters only, not the entire nuclide mix. Changing this will eliminate excess conservatism in the liquid effluent setpoint calculation. The excessive conservatism resulted in setpoints that were lower than the gamma concentration of the effluent, thus not allowing some releases to be made.

This change will not negatively impact the accuracy or reliability of the it setpoint calculations, nor will have any impact on the health and safety of the public since releases are still being monitored and doses calculated as before.

Incorporation of the 1994 Land Use Census data.

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

Editorial Changes Editorial Changes have no impact on the technical content of the ODCM. These changes correct typo's, make sure Section and Table names match the Table of Contents, and items of a similar nature. Editorial changes made to the ODCM include:

Break out Tables A-5/A-6 from A-7/A-8 and correct the titles of the Tables.

Section 2.1, Equation 2.1-13 Change the background parameter from "B" to II 8 Bkg ~

Appendix B Change the Appendix B heading from 2.1 to B.l and correct the units for the inhalation pathway R. values in B.2.1.

ig The following minor changes were also made throughout the ODCM:

Change Set Point to Setpoint.

Change uCi to pCi.

Change pCi to pCi.

Adjust the spacing of terms and equations, especially X/Q and D/Q.

Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program Technical Specifications 3. 11.2.3

3. 12. 1

3. 12. 1. c As a result of the annual land-use census, a new resident and garden were observed in the ENE sector at 1.8 miles. Because of the relatively high D/9 value at this location, the garden was added to the sampling program.

The control air sampling and TLD location (AC/AP-5 and TLD-5) were moved from CP&L's Pittsboro line and service site on highway 15-501 to the area office on US-64. The relocation was prompted by the closing of the former location.

These changes will be included in the 1995 ODCM changes.

Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Techno.cal Specxfxcatxo n s 3 .12.2.a 3 .12.2.b The land-use census was completed in August 1994.

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Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1 : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During this Report Period No liquid effluent monitoring instrumentation specified in Technical Specification Table 3.3-12 was inoperable for greater than 30 Days during this Report period.

Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service > 30 Days During this Report Period The instruments listed in Technical Specification 3.3.3.11 were reviewed for operability during 1994. None were inoperable for greater than 30 days during this report period.

6/2

Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.

1 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.

6/4

Appendix 7  : Major Modifications to Radwaste System Technical Specification 6. 15.1 No major modifications were made to the Radwaste System during this Report period.

Appendix 8 : Meteorological Data Technical Specification 6.9. 1.4 As allowed by the Footnote to Technical Specification 6.9.1.4, 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.

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9  : Assessment of Radiation Doses Enclosure 1: Population Doses Outside Site Boundary Due to Effluent Releases

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

A. 50 mile Ingestion Zone 1994 Bone Liver W. Body Thyroid Kidney Lung GI-LLI Skin Sport Fish 1.32 E-01 2.29 E-01 1.51 E-01 3.64 E-02 9. 95 E-02 5.82 E-02 8.00 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 1.93 E-02 3.83 E+00 3.82 E+00 3.82 E+00 3.82 E+00 3.82 E+00 3.86 E+00 0.00 E+00 Shoreline 3.14 E-02 3.14 E-02 3.14 E-02 3.14 E-02 3.14 E-02 3. 14 E-02 3.14 E-02 3.62 E-02 Swimming 2.16 E-04 2.16 E-04 2.16 E-04 2.16 E-04 2.16 E-04 2.16 E-04 2.16 E-04 0.00 E+00 Boating 1.09 E-04 1.09 E-04 1.09 E-04 1.09 E-04 1.09 E"04 1.09 E-04 1.09 E-04 0.00 E+00 Irri Irri Veg Leafy veg 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 E+00 0.00 E+00 Irri Irri Milk Meat 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 0.00 E+00 E+00 0.00 E+00 0.00 E+00 All Pathways 1.83 E-01 4.09 E+00 4.00 E+00 F 88 E+00 3.95 E+00 3.91 E+00 3.97 E+00 3 '2 E-02 B. Tritium (Hydrosphere)

Bone Liver W. Body Thyroid Kidney Lung GI-LL1 Total 0.00 E+00 1.35 E-02 1.35 E-02 1.35 E-02 1.35 E-02 1.35 E-02 1.35E-02

2. Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone W. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin Plume 4.61 E-02 4.61 E-02 4.61 E-02 .61 E-02 4.61 E-02 4.61 E-02 4.91 E-02 1.77 E-01 Ground Plane 1.83 E-03 1.83 E-03 1.83 E-03 .83 E-03 1.83 E-03 1.83 E-03 1.83 E-03 2.15 E-03 Inhalation 3.85 E-05 5.66 E-05 1.33 E-05 .55 E-05 5.63 E-05 5.68 E-03 7.34 E-04 2.69 E-05 Vegetation 2.12 E-05 5. 11 E-05 5.64 E-06 .99 E-05 2. 17 E" 05 2.26 E-03 9.95 E-06 9.95 E-06 Cow Milk 1.09 E-05 9.58 E-06 8.92 E-06 .51 E-05 2.21 E-05 3.46 E-03 4.16 E-06 4.16 E-06 Meat a Poultry 1.07 E"05 4.23 E-05 5.91 E-07 .89 E-06 6.08 E-06 2.57 E-04 4.76 E-06 4.76 E-06 TOTAL 4.80 E-02 4.81 E-02 4.79 E-02 4.80 E-02 4.80 E-02 5.96 4E-02 5.17 E-02 1.80 E-01

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary

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

Bone Liver W. Body Thyroid Kidney Lung Gi-LLZ Skin ADULT Fish 1.46E-01 2.75E-01 2.11E-01 4.70E-02 1.22E-01 7.20E-02 1.14E-01 Drinking 1.40E-04 3.57E-02 3.57E-02 3.56E-02 3.56E-02 3.56E-02 3.61E-02 Shoreline 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.25E"03 3.25E-03 3.75E-03 Swimming 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 Boating 2.70E-04 2.70E-04 2.70E-04 2.70E-04 2.70E-04 2.70E-04 2.70E-04 TOTAL 1.50E-01 3.01E-01 2.51E-01 8.63E-02 1.62E-01 1.11E-01 1.54E-01 3.75E-03 TEEN Fish 1.54E-01 2.71E-01 1.29E-01 3.62E-02 1.13E-01 6.61E-02 8.35E-02 Drinking 1.34E-04 2.52E-02 1.51E-02 2.51E-02 2.51E-02 2.56E-02 2.54E"02 Shoreline 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 2.10E-02 Swimming 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 Boating 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 TOTAL 1.73E-01 3.16E-01 1. 73E-01 8.02E-02 . 1.57E-01 1.10E-01 1.28E-01 2.10E-02 CHILD Fish 1.92E-01 2.37E-01 6.64E-02 3.00E-02 9.54E-02 5.36E-02 4.67E-02 Drinking 3 '6E-04 4.82E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.84E-02 Shoreline 3.80E-03 3.80E-03 3.80E-03 3.80E-03 3.80E-03 3.80E"03 3.80E-03 4.38E-03 Swimming 1.18E-04 1.18E-04 1.18E-04 1. 18E-04 1.18E-04 1. 18E-04 1.18E-04 Boating 1.47E-04 1.47E-04 1.47E-04 1.47E-04 1.47E"04 1.47E-04 1.47E-04 TOTAL 1.97E-01 2.89E-01 1. 19E-01 8.21E-02 1.48E-01 1.06E-01 9. 91E-02 4.38E-03 INFANTS are assumed to have no exposure via this pathway.

9/2

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 2 (Continued): Doses to General Public Due to Activities Inside Site Boundary

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

W. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.46 E-03 3.84 E-03 Ground Plane 1.17 E-04 1. 17 E-04 1.17 E-04 1. 17 E-04 1. 17 E-04 1.17 E-04 1.17 E-04 1.37 E-04 Inhalation 2.99 E-07 7.10 E-07 1.60 E-07 3.92 E-07 5.34 E-07 7.47 E-05 1.11 E-05 1.43 E-07 TOTAL 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.61 E-03 1.59 E-03 3.98 E-03 TEENAGER Plume 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 3..42 E-03 1.42 E-03 1.46 E-03 3.84 E-03 Ground Plane 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.38 E-04 Inhalation 3.47 E-07 6.66 E-07 2.24 E-07 4.85 E-07 6.79 E-07 9.18 E-05 1.62 E-05 1.44 E-07 TOTAL 1.54 E-03 1.54 E"03 1.54 E-03 1.54 E-03 1.54 E-03 1.63 E-03 1 '9 E-03 3.98 E-03 CHILD Plume 1.42 E"03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 "E-03 1.46 E-03 3.84 E-03 Ground Plane 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1 17

~ E-04 1.38 E-04 Inhalation 3.41 E"07 3.24 E-07 3.05 E-07 4.58 E-07 6.30 E-07 1.02 E-04 1.31 E" 05 1.28 E-07 TOTAL 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.64 E-03 1.59 E-03 3.98 E-03 ENFANT Plume 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.42 E-03 1.46 E-03 3.84 E-03 Ground Plane 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E-04 1.17 E"04 1.38 E-04 Inhalation 2.19 E-07 1.40 E-07 2.40 E-07 3.71 E-07 4.03 E-07 9.33 E-05 8.36 E-06 7.33 E-08 TOTAL 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.54 E-03 1.63 E"03 1.59 E-03 3.98 E-03 9/3

Semiannual Radioactive Effluent Release Report July 1,.1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 3: Doses to Likely Most Exposed Member of the Public

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

ADULT Bone Liver W. Body Thyroid Kidney Lung GI-LLI Skin Fish 1.46E-01 2.75E"01 2.11E-01 4.70E-02 1.22E-01 7.20E-02 1.14E-01 Drinking 1.40E-04 3.57E-02 3.57E-02 3.56E-02 3.56E-02 3.56E-02 3.61E-02 Shoreline 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.25E-03 3.75E-03 Swimming 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 2.35E-04 Boating 2.70E-04 2.70E-04 2.70E-'04 2.70E-04 2.70E-04 2.70E-04 2.70E-04 TOTAL 1.50E-01 3.15E-01 2. 51E-01 8.63E-02 1.62E-01 1.11E-01 1.54E-01 3.75E-03 TEEN Fish 1.54E"01 2.71E-01 1.29E-01 3.62E-02 1. 13E-01 6.61E-02 8.35E-02 Drinking 1.34E-04 2.52E-02 2.51E-02 2.51E-02 2.51E-02 2.51E-02 2.54E-02 Shoreline 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 2.10E-02 Swimming 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 3.53E-04 Boating 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 3.92E-04 TOTAL 1.73E-01 3.16E-01 1.73E-01 8.02E-02 1.57E-01 1.10E-01 1.28E-01 2.10E-02 CHILD Fish 1. 92E-01 2.37E-01 6.64E-02 3.00E-02 9.54E-02 5.36E-02 4.67E-02 Drinking 3.96E-04 4.82E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.84E-02 Shoreline 3.80E-03 3.80E-03 3.80E-03 3.80E-03 3.80E-03 3.80E-03 3.80E-03 4.38E-03 Swimming 1.18E-04 1. 18E-04 1. 18E-04 1.18E-04 1.18E-04 1.18E-04 1.18E-04 Boating 1.47E-04 1.47E-04 1.47E-04 1.47E-04 1.47E-04 1.47E-04 1.47E-04 TOTAL 1.97E-01 2.89E-01 1.19E-01 8.21E-02 1.48E-01 1.06E-01 9.91E-02 4.38E-03 INFANT Drinking 3.73E-04 4.74E-02 4.73E-02 4.73E-02 4.72E-02 4.73E-02 4.74E-02 TOTAL 2.32E-04 2.95E-02 2.94E-02 2.94E-02 2.94E-02 2.94E-02 2.94E-02 9/4

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Likely Most Exposed Member of the Public

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

A. Maximum Hypothetical Individual - Exposure from Noble Gases, Particulates, Iodines, and Tritium W. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT Plume 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.26 E-02 6.60 E-02 Ground Plane 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 1.05 E-03 Inhalation 8.97 E-06 1.54 E-05 2.49 E-06 1.04 E-05 1.26 E-05 1.17 E-03 1.77 E-04 6.55 E-06 Vegetation 2.68 E-05 1.26 E-04 2.87 E-06 2.13 E-05 1.82 E-05 1.36 E-03 1.11 E-05 1.11 E-05 Cow Milk 9.79 E-06 1.07 E-05 8.02 E-06 1.44 E-05 2.23 E-05 3.76 E-03 2.63 E-06 2.63 E-06 Meat & Poultry 4.05 E-06 2.42 E-05 2. 91 E-07 2.75 E-06 1.83 E-06 1.38 E-04 1.12 E-06 1. 12 E-06 TOTAL 2.28 E-02 2.29 E" 02 2.27 E-02 2.28 E-02 2.28 E-02 2.91 E-02 2.37 E-02 6.71 E-02 TEENAGER Plume 2.18 E-02 2. 18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.26 E-02 6.60 E-02 Ground Plane 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 1.05 E-03 Inhalation 9.74 E-06 1.47 E-05 3.50 E-06 1. 19 E-05 1.49 E-05 1.44 E-03 2.56 E-04 6.59 E-06 Vegetation 3.59 E-05 1.34 E-04 2.79 E-06 2.62 E-05 1.98 E-05 1.15 E-03 1.31 E-05 1.31 E-05 Cow Milk 1.54 E-05 1.34 E-05 1.46 E-05 2.43 E-05 3.85 E-05 5.95 E-03 3.43 E-06 3.43 E-06 Meat & Poultry 2.98 E-06 1.31 E-05 2.42 E-07 1.95 E-06 1.25 E-03 9.95 E-05 6.69 E-07 6.69 E-07 TOTAL 2.28 E-02 2.29 E-02 2.27 E-02 2.28 E-02 2.28 E-02 3.13 E-02 2.38 E-02 6.71 E-02 CHILD Plume Ground Plane 2.18 8.90 E-02 E-04 2.18 8.90 E-02 E-04 2.18 8.90 E-02 E-04 2.18 8.90 E-02 E-04 2.18 8.90 E-02 E-04

2. 18 8.90 E-02 E-04 2 '6 E-02 8.90 E-04 6.60 1.05 E-02 E-03 Inhalation 9.15 E-06 8.89 E-06 4.75 E-06 1.10 E-05 1.36 E-05 1.59 E-03 2.07 E-04 5.83 E-06 Vegetation Cow Milk 6.51 2.77 E-05 E-05 9.92 1.25 E-05 E-05 5.25 3.53 E-06 E-05 3.98 4.16 E-05 E-05

2. 91 6.37 E-05 E-05 1.77 1.17 E-03 E-02 2 '4 E-05 5.42 E-06 2.04 5.42 E-05 E-06 Meat & Poultry 4.38 E-06 7.08 E-06 4.49 E-07 2.38 E-06 1.54 E-06 1.50 E-04 8.08 E-07 8.08 E-07 TOTAL 2.28 E-02 2.28 E-02 2.27 E-02 2.28 E-02 2.28 E-02 3.79 E-02 2.37 E-02 6.71 E-02 ENFANT Plume 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2.18 E-02 2. 18 E-02 2.26 E-02 6.60 E-02 Ground Plane 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E-04 8.90 E"04 1.05 E-03 Inhalation 5.61 E-06 4.38 E-06 3.75 E-06 7.99 E-06 8.49 E-06 1.46 E-03 1.32 E-04 3.35 E-06 Cow Milk 4.98 E-05 1.47 E-05 7.37 E-05 9.65 E-05 1.10 E-04 2.85 E-02 8.22 E-06 8.22 E-06 TOTAL 2.28 E-02 2.27 E-02 2.28 E-02 2.28 E-02 2.28 E-02 5.27 E-02 2.37 E-02 6.71 E-02 9/5

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Likely Most Exposed Member of the Public

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

B. Maximum Real Individual - Exposure from Noble Gases, Particulates, Iodines, and Tritium W. Body GI-LLZ Bone Liver Kidney Thyroid Lung Skin ADULT Plume 3.76 E-03 3 .76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.91 E-03 1.22 E-02 Ground Plane 2.93 E-04 2 .93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 3.45 E-04 Inhalation 2.07 E-06 3 .13 E-06 4.22 E-07 2.31 E-06 2.69 E-06 1.99 E-04 3.02 E-05 1.66 E-06 Vegetation 7.98 E-06 4 .05 E-05 9.46 E-07 6.16 E-06 5.14 E-06 4.46 E-04 2.82 E-06 2.82 E-06 Meat & Poultry 1.25 E-06 7 .88 E-06 9.60 E-08 8.24 E-07 5. 19 E-07 4.53 E-05 2.84 E-07 2.84 E-07 TOTAL 4.07 E-03 4.11 E-03 4.06 E-03 4.06 E-03 4.07 E-03 4.75 E-03 4.24 E-03 1.26 E-02 TEENAGER Plume 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.91 E-03 1.22 E-02 Ground Plane 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 3.45 E-04 Inhalation 2.20 E"06 3.03 E-06 5.93 E-07 2.57 E-06 3.08 E-06 2.44 E-04 4.34 E-05 1.67 E-06 Vegetation 1.08 E-05 4.31 E-05 9.19 E-07 7.63 E-06 5.52 E-06 3.78 E-04 3.31 E-06 3.31 E-06 Meat a Poultry 9.33 E-07 4.26 E-06 7.98 E-08 5.93 E-07 3.62 E-07 3.28 E-05 1.69 E-07 1.69 E-07 TOTAL 4.07 E-03 4.11 E-03 4.06 E-03 4.07 E-03 4.07 E-03 4.71 E-03 4.25 E-03 1.26 E-02 CHILD Plume 3.76 E-03 3.76 E-03 3.76 E-03 -3. 76 E-03 3.76 E-03 3.76 E-03 3.91 E-03 1.22 E-02 Ground Plane 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 3.45 E-04 Inhalation 2.03 E-06 1.99 E-06 8.05 E-07 2.35 E-06 2.80 E-06 2.71 E-04 3.53 E-05 1.47 E-06 Vegetation 1.99 E-05 3.11 E-05 1.73 E-06 1.16 E-05 8.03 E-06 5.81 E-04 5.17 E-06 5.17 E-06 Meat & Puoltry 1.38 E-06 2.27 E-06 1.48 E-07 7.24 E-07 4.49 E-05 4.94 E-05 2.04 E-07 2.04 E-07 TOTAL 4.08 E-03 4.09 E-03 4:06 E-03 4.07 E-03 4.07 E-03 4.95 E-03 4.25 E-03 1.26 E-02 INFANT Plume 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.76 E-03 3.91 E-03 1.22 E-02 Ground Plane 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 2.93 E-04 3.45 E-04 Inhalation 1.23 E-06 1.02 E-06 6.35 E-07 1.63 E-06 1.72 E-06 2.47 E-04 2.24 E-05 8.48 E-07 TOTAL 4.06 E-03 4.06 E-03 4.06 E-03 4.06 E-03 4.06 E-03 4.30 E-03 4.23 E-03 1.26 E-02 9/6

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 3 (Continued): Doses to Likely Most Exposed Member of the Public

3. Annual Air Dose (mrad)

A. Maximum Hypothetical Individual: Beta = 1.14 E-01 Gamma = 6.94 E-02 B. Maximum Real Individual: Beta = 2.23 E-02 Gamma = 1.19 E-02

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

Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 4  : Major Assumptions Used to Calculate Radiation Doses

1. Doses Due to Liquid Effluents A. Dilution Factors Location Value E osure Pathwa s Harris Lake 1.00 E+00 Shoreline, Swimming, Boating, Fish Consumption Cape Fear River 8.28 E+01* Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Cape Fear River/

Raven Rock Park 5.75 E+01* Boating

• The dilution of 5.75 E+01 is calculated using the FSAR value for average blowdown of the lake (43 CFS) and the average flow of the Cape Fear River as measured at the gauging station at Lillington. The average flow of the Cape Fear River at this location is 2473 cfs (1994 average flow of the Cape fear River as provided by the United States Geological. Service).

B. Populations Affected Location Value Ex osure Pathwa s Harris Lake 1.10 E+05 person-hours Shoreline, Swimming, Boating Harris Lake 1.20 E+03 persons Drinking Water Harnett County 4.53 E+04 persons Drinking Water Dunn Intake 1.67 E+04 persons Drinking Water Fayetteville Area 1.40 E+05 persons Drinking Water Fuquay-Varina 2.68 E+03 persons Drinking Water Holly Springs 2.27 E+02 persons Drinking Water Harris Lake/

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

Raven Rock Park 5.00 E+04 person-hours Boating Raven Rock Park 4.40 E+05 person-hours Shoreline Doses for "Activities Inside the Site Boundary" and the "Likely Most Exposed Member of the Public" use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway doses.

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Semiannual Radioactive Effluent Release Report July 1, 1994 to December 31, 1994 Appendix 9 : Assessment of Radiation Doses Enclosure 4 (Continued): Major Assumptions Used to Calculate Radiation Doses

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

B. The Maximum Real Individual is located at 4667 meters (-2.9 miles) in the SW sector.

C. The Maximum Hypothetical Individual is located on the site boundary at 2140 meters in the SSW sector.

For the Inside Site Boundary Individual, access time is assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 1207 meters (3/4 mile) in the NE sector from the plant, which is the closest accessible lake location.

Concurrent meteorology is applied separately to batch and continuous release source terms. The dose commitment from each mode was summed to obtain annual dose.

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