ML18010B018

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1992. W/930224 Ltr

ML18010B018
Person / Time
Site:	Harris
Issue date:	12/31/1992
From:	BARNES H E, VAUGHN G E CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-930060, NUDOCS 9303020422
Download: ML18010B018 (91)

Text

ACCEI ERA DOCUMENT DIST VTION SYSTEM REGULAT INFORMATION DISTRIBUTIO YSTEM (RIDS)A,Q ACCESSION NBR:9303020422 DOC.DATE: 9~12/31-NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VAUGHNiG.E.

Carolina Power&Light Co.BARNES,H.E.

Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400

SUBJECT:

"Shearon Harris Nuclear Power Plant Semi Effluent Release Rept,Jul-Dec 1992." 930224 Radioactive tr.DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL J SIZE: TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES:Application for permit renewal filed.05000400 RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL: A~C S G FILE 01 RGN2 E 02 EXTERNAL: BNL TICHLERiJ03 NRC PDR COPIES LTTR ENCL 3 3 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DRSS/PRPB11 RGN2 DRSS/RPB EGGG SIMPSON,F COPIES LTTR ENCL 1 1 2 2 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

(~,.e 0'0 i s C'E 4 g Carolina Power&Light Company P.O.Box 165~New Hill, NC 27562 G.E.VAUGHN Vice President Harris Nuctear Plant FEB 2 4 f993 Letter Number: HO-930060 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, D.C.20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:

In accordance with Technical Specification 6.9.1.4., the Semiannual Radioactive Effluent Release Report is attached for the Shearon Harris Nuclear Power Plant.This report covers the period from July 1, 1992 through December 31, 1992.Very truly yours, G.E.Vaughn Vice President Harris Nuclear Plant MGW:kls Attachment cc: Mr.S.D.Ebneter (NRC-RII)Mr.N.B.Le (NRR)Mr.J.E.Tedrow (NRC-SHNPP)020095 MEM/HO-930060/1/OS1 9303020422.

921231 PDR ADOCK 05000400 R',.PDR)

'V g, r Carolina Power&Light Shearon Harris Nuclear Power Plant License No.NPF-063 SKMIANNU AL&O)IOACTIVE EFFLUENT RELEASE REPORT July 1, 1992 to December 31, 1992 Prepared by: Prepared by: Reviewed by: Specialist

-E&C d'eP Manager-E&RC Support Reviewed by: Mana er-nvironmental

&iation Control Approved by: General Manager-Harris Plant C~r~1 t Cc Table of Contents Introducti'on Page No.Discussion Appendix 1.Supplemental Information Appendix 2.1.2.3.Effluent and Waste Disposal Report Lower Limits of Detection (LLD's)Effluents Released Solid Waste Disposal 2/1 2/3 2/10 Appendix 3.Changes to Process Control Program (PLP)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 2.Land Use Census S/1 S/2 Appendix 6 1.2.3.4 Additional Technical Specification Responsibilities Inoperability of Liquid Effluent Monitors Inoperability of Gaseous Effluent Monitors Unprotected Outdoor Tanks Exceeding Limits Gas Storage Tanks Exceeding Limits 6/1 6/2 6/3 6/4 Appendix 7.Major Modifications to Radwaste System Appendix 8.Meteorological Data 7/1 8/1 Appendix 9.1.3.Assessment of Radiation'Doses for Calendar Year 1992 Population Doses outside Site Boundary due to Effluent Releases Doses to the General Public Due to Activities Inside the Site Boundary Doses to the Likely Most Exposed Member of the Public Major Assumptions used to Calculate Radiation Doses 9/1 9/2 9/4 9/8 z I t J l, 4 tt~)

e Cg\Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Plant (SHNPP)Operating License No.NPF-63.It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987.This report covers the period from July 1, 1992 to December 31, 1992.During this period, the plant had a refueling outage and started Cycle 5 operation.

Discussion Appendices 1 and 2: The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev.1)Appendix B format.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.

Except for continuous noble gas releases, liquid and gaseous average concentrations (uCi/cc)and total curies released are for only those nuclides that were positively identified.

If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD)tables show a typical sensitivity level for detection of the nuclide.Continuous noble gas effluent activities were based on hourly average stack monitor readings (in uCi/cc)and stack flow rate estimates based on design fan flow rates, and are apportioned as per the GALE code (NUREG 0017)nuclide assumptions as given in the ODCM.When specific noble gas nuclides were identified in the stack gas grab samples, their activity was added to the activity based on stack monitor readings.Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.The"Percent of Technical Specification Limit" is calculated using ODCM default methodology and parameters.

A total of 44.35 m'f solid waste, containing 76.35 Ci of radioactivity, was shipped for burial during this Report period, compared with 26.76 m'nd 213.18 Ci shipped during the previous report period.

\'I le t)t Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Discussion (continued)

Appendix 3: ,No changes to the Process Control Program (PCP)were made during this Report period.Appendix 4: No changes to the Off-Site Dose Calculation Manual (ODCM)were made during this Report period.A change was submitted, but not approved, to incorporate the change descriped in Appendix 5, along with other minor changes.Appendix 5: A minor change was made to the Environmental Monitoring Program due to the relocation of a sample point.No changes to the Land Use Census were made during this Report period.Appendix 6: All effluent monitor inoperabilities greater than 30 days are given along with a brief explanation.

During these periods, compensatory sampling and flow rate estimations consistent with Technical Specification requirements have provided accountability and control of effluents.

No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this Report period.Appendix 7: No major modifications to the Radwaste System were made during this Report peri.od.Appendix 8: The 1992 annual summary of meteorological data is available to the NRC upon request.This summary is also used in the NRC approved program XOQDOQ, which is used in the Appendix 9 dose calculations.

1 t~~a I\Cl~((Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Discussion (continued)

Appendix 9: The effluent quantities reported for both semiannual periods in 1992 were combined for determining the annual dose impact from plant'perations.

The doses were calculated by the programs LADTAP II (for liquid effluents) and GASPAR (for gaseous effluents).

GASPAR and LADTAP II are NRC approved programs for implementing Reg.Guide 1.109 methodology, 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.).Enclosure 1 shows the integrated population doses within the 50-mile ingestion zone (in man-rem)due to liquid and gaseous releases for the various applicable pathways.Also, the tritium contribution to the hydrosphere is shown.Enclosure 2 shows the doses (in mrem/yr)to a hypothetical individual member of the general public due to'activities inside the site boundary.Since portions of Harris lake are within the site boundary, these doses result from the recreational usage of the lake.The highest whole body doses any individual could have received in this area were 0'15 mrem due to liquid effluents and 0.011 mrem due to gaseous effluents.

The corresponding values for CY 1991 were 0.0314 and 0.005 mrem respectively. shows the hypothetical doses (in mrem/yr)for the"Likely Most Exposed Individual".

For the liquid pathways, this calculation assumes that the Harnett County water supply intake (formerly Lillington), the closest downstream public water supply, is the source of drinking water and Harris Lake is the source of all other liquid exposure.The highest whole body and organ doses any individual could have received due to liquid effluents were 0.055 and 0.060 mrem respectively.

Corresponding values for CY 1991 were 0.0445 and 0.055 mrem respectively.

For the airborne pathways, the gaseous dose considers two types of individuals:

(1)the"Maximum Hypothetical Individual", who resides at the site boundary in the sector of highest plume exposure, and (2), the"Maximum Real Individual" who, based on the Land Use Census, had the highest combined dose from his actual exposure pathways, e.g.plume, ground, etc.In 1992, the"Maximum Real Individual" is located at 2414 meters ("1.5 miles)in the NNW sector.Previous to 1992, the"Maximum Real Individual" was located in the NNE sector at a distance of 1.8 miles.

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ti Y i g Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Discussion (continued)

Appendix 9 (Continued)

For the"Maximum Hypothetical Individual",, the highest whole body dose was 0.155 mrem, and the highest organ dose was 0.330 mrem.Beta and gamma annual air doses were 0.348 and 0.238 mrad respectively.

Corresponding, values for CY 1991 were 0.0785 whole body, 0.173 organ, 0.285 beta, and 0.102 gamma, respectively.

For the>>Maximum Real Individual", the highest whole body dose was 0.0373 mrem, and the highest organ dose was 0.0382 mrem.Beta and gamma annual air doses were 0.0900 and 0'.0577 mrad respectively.

Corresponding values for CY 1991 were 0.0157 whole body, 0.0421 organ, 0.0571 beta, and 0.0249 gamma, respectively. lists the major assumptions associated with the liquid and gaseous effluent doses.Where available, site specific information is used to derive these values.In other cases, parameter values or derivations are as given in Reg.Guide 1.109.

r h~4 Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 1: Supplemental Information Regulatory Limits A.Fission and activation gases (1)Calendar Quarter a.5 mrad gamma b.10 mrad beta (2)Calendar Year a.10 mrad gamma b.20 mrad beta B.-I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1)Calendar Quarter a.7.5 mrem to any organ (2)Calendar Year a.15 mrem to any organ Liquid effluents (1)Calendar Quarter a.1.5 mrem to total body b.5 mrem to any organ (2)Calendar Year a.3 mrem to total body b.10 mrem to any organ 1)t y s~g t I'

'n~Semia al Radioactive Effluent Relea eport July 1, 1992 to December 31, 1992 Appendix 1 (Continued):

Supplemental Information Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.A.Fission and activation'ases (1)500 mrem/year to total body (2)3000 mrem/year to the skin I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.1500 mrem/year to any organ C.Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 Uci/ml.Average Energy (E)N/A an.SHNPP.SHNPP determines doses and dose rate based on actual releases, not on an average energy value.Measurements and Approximations of Total Radioactivity A.Fission and activation gases Measurements by continuous monitors of activity concentrations times total stack flow, and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples.B.Iodines Continuous charcoal cartridge sampling and analysis by gamma spectroscopy for specific radionuclides times total stack flow.C.Particulates Continuous particulate sampling and analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides times total stack flow.D.Liquid Effluents Pre-release representative sampling and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides times total release.volume.1/2 0~c~t.~I h ls Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 1 (Continued):

Supplemental Information Batch Releases Liquid Batch Releases (1)Number of batch releases (2)Total time period for batch releases (3)Maximum time of a batch release (4)Average time for a batch release (5)Minimum Time for a batch release 1.16 E+02 7.92 E+04 min 1.32 E+03 min 6.83 E+02 min 1.00 E+00 min (6)Average stream flow during periods of release 1.31 E+04 gpm Gaseous Batch Releases (1)Number of batch releases P (2)Total time period for batch releases (3)Maximum time of a batch release (4)Average time for a batch release (5)Minimum Time for a batch release 1.00 E+01 8.07 E+03 min 3.01 E+03 min 8.07 E+02 min 1.22 E+02 min r~~~rt r QA AV'1 Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 1 (Continued):

Supplemental Information Abnormal Releases Liquid No abnormal liquid releases were made in this period.Gaseous Two abnormal releases occurred during the reporting period.In both releases, the activities associated with the release have been reported in the BATCH release part of Table 1C.The first release occurred from July 12, 1992 until July 14, 1992.A plant trip resulted in the Main Steam Power Operated Relief'Valve (PORV)opening and being used to maintain system pressure.During this time, the plant had a small primary-to-secondary steam generator tube leak, resulting in contamination in the secondary side.This contaminated water escaped as steam through the PORV.A source term was calculated and an activity of 4.35 E-01 curies was assigned to this release.Dose impact on the environment was calculated using the Non-Routine, Gaseous-(NRG)Release portion of ,the ODCM, and a release was generated to document the doses.The second release occurred on September 11, 1992, while operations was making preparations for plant shutdown.This release caused the plant vent stack monitors to momentarily go into High Alarm.As a result of the High Alarm, a dose evaluation was performed to assess the.impact to the population as a result of the release.The release was calculated to be-2.50 E+00 curies, and consisted of noble gases.Dose impact on the environment was calculated using the Non-Routine Gaseous (NRG)Release portion of the ODCM, and a release was generated to document the doses.

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Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 2: Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLD)1.LLD'S for Gaseous Effluents Nuclide uCi/cc Gross Alpha H-3 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 I-131 I-133 I-135 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 1.80 E-15 7.97 E-09 3.79 E-08 6.09 E-06 2.12 E-08 8.88 E-08 2.32 E-08 6.21 E-07 6.96 E-08 4.65 E-07 2.07 E-08 4.65 E-07, 5.94 E-07 3.22 E-14 2.73 E-14 7.97 E-14 1.17 E-13 1.66 E-14 1.33 E-14 3.87, E-14 1.86 E-14 7.55 E-14 3.00 E-15 1.00 E-15 1.48 E-13 1.01 E-14 2.63 E-14 4.13 E-14 2.41 E-14 1.26 E-14 3.89 E-14 r'/p p>>I.T r 4+p Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLD)2.'LD's for Liquid Effluents Nuclide Gross Alpha H-3 Be-7 Na-24 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Ni-63 Zn-65 Sr-89 Sr-90 Sr-92 Nb-95 Zr-95 Mo-99 Tc-99m Ru-103 Ag-110m Sb-122 Sb-124 Sb-125 I-131 I-132 I-133 I-135 Te-132 Xe-133 Xe-133m Xe-135 Cs-134 Cs-137 Cs-138 Ba-140 La-140 Ce-141 Ce-143 Ce-144 Pr-144 Hf-181 uCi 4.10 2.55 2.24 3.15 2.61 2.01 2.00 1.73 1.98 4.64 3.89 2.00 8.67 1.50 5.00 4.52 3.26 3.36 2.04 2.46 2.51 5.93 5.06 1.68 9.36 2.67 3.31 1.33 1.25 2.31 5.36 1.91 2.59 3.08 3.38 5.62 9.60 3'2 4.84 6.07 2.04 1.17 2.62/ml E-08 E-06 E-07 E-08 E-07 E-08 E-07 E-08 E-08 E-08 E-08 E-07 B-08 B-OS E-09 B-08 E-08 E-08 E-07 B-08 B-08 E-08, E-08 E-08 B-08 E-08 E-08 E-07 E-07 B-08 E-08 E-07 E-08 E-08 B-OS E-07 E-08 E-08 E-08 E-08 E-07 E-06 E"08 2/2 a

~I Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1A: GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1.Fission S Activation Gases A.Total Release B.Average Release Rate for Period C.Percent of Technical Specification Limit Ci 8.97 E+02 1.26 E+02 4.50 E+01 uCi/sec 1.13 E+02 1.58 E+01 7.04 E-01 3.74 E-01 Units Quarter Quarter Est.Total 3 4 Error 2.Iodines (I-131, I-133, I-135)A.Total Iodines B.Average Release Rate for Period C.Percent of Technical Specification Limit Ci uCi/sec 6.38 E-04 5.72 E-05 2.00 E+01 8;02 E-05 7.20 E-06See Footnote Below 3.Particulates A.Particulates with Tl/2)8 days B.Average Release Rate for Period C.Percent of Technical Specification Limit Ci uCi/sec 1.25 E-04 3.60 E-05 2.00 E+01 1.57 E-05 4.53 E-06 7.20'-01 9.33 E-02 D.'ross Alpha Radioactivity Ci LLD LLD 4.Tritium A.Total Release B.Average Release Rate for Period C.Percent of Technical Specification Limit Ci 4.36 E-01 7.85 E-05 3.00 E+01 uCi/sec 5.49 E-02 9.88 E-06 See Footnote Below The Percent of Technical Specification limit applies to Iodines, Tritium, and Particulates combined, and is calculated using ODCM default methodology and parameters.

The value for Iodines and Tritium is included in the Particulates summation.

2/3 e I ,t%g I,~E!

Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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 R,~)~4~p 4 I II Jl Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix Table 2 (Continued):

Bffluent and Waste Disposal Report Enclosure 2: Effluents Released 1C: GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 1.Fission and Activation Gases NUCLIDBS CONTINUOUS Units Q3 Q4 Q3 Q4 H-3 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci (LLD<LLD 7.44E+02 1.20E+01 4.19E+01 (LLD 5.99E+00<LLD<LLD 1.80E+01 5.99E+00 2.99E+00<LLD<LLD 1.03E+02 1.64E+00 8.33E+00<LLD 8.21E-01<LLD (LLD 2.46E+00 8.21E-01 4.11E+00 4.36E-01 2.29E+00 5.53E+01 1.14E-01 6.40E-01 1.49E-01 1.55E-01 6.05E-01 6.22E+00 1.02E-01 1.26E-01 1.93E-01 7.85E-05 4.02E-02 6.36E-02<LLD<LLD<LLD<I LD (LLD 4.43E+00<LLD<LLD<LLD Totals 2.Iodines Ci 8.31E+02 1.21E+02 6.63E+01 4.53E+00 I-131 I-133 I-135 Totals 3.Particulates Ci Ci Ci Ci 4.22E-04 5.72E-05 1.38E-04<LLD 6.04E-05<LLD 1.74E-05<LLD (LLD (LLD (LLD (LLD 4.82E-04 5.72E-05 1.55E-04<LLD Gr.Alpha, Sr-89 Sr-90 Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Mo-99 Cd-109 Cs-134 Cs-137 Ce-141 Ce-144 Ba-140 La-140 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci (LLD (LLD (LLD (LLD<LLD 3.63E-06<LLD 8.64E-OS<LLD<LLD 2.19E-OS<LLD (LLD<LLD (LLD<LLD<LLD (LLD<LLD (LLD 1.14E-05<LLD 2.05E-05<LLD 4.10E-06<LLD (LLD (LLD (LLD<LLD<LLD (LLD<LLD<LLD<LLD<LLD<LLD (LLD<LLD 1.13E-7<LLD<LLD (LLD (LLD (LLD 4.97E-06 7.50E-06<LLD (LLD<LLD<LLD (LLD<LLD (LLD (LLD<LLD (LLD<LLD<LLD (LLD (LLD<LLD (LLD<LLD (LLD (LLD<LLD<<LLD Totals Ci 1.12E"04 3.60E-05 1.26E-OS<LLD Table 1C also includes the activities released as abnormal releases.The abnormal release activities were included when determining dose from batch releases.These releases are described in Appendix 1,,Section 6.2/5 4 i

Semiannual Radioactive Effluent Release Report July 1, 1992 to'ecember 31, 1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUBNTS-SUMMATION OF ALL RELEASES 1.Fission 6 Activation Products Units Quarter Quarter Est.Total 3 4 Error B.C.Total Release (not including tritium, gases, or alpha)Average Diluted Concentration during Period Percent of Technical Specification Limit Ci 1.24 E-01 1.26 E-01 3.50 E+01 uCi/ml 1.67 E-08 1.89 B-08 4.82 E-01 1.88 B-01 2.Tritium A.Total Release B.Average Diluted Concentration during Period C.Percent of Technical Specification Limit Ci uCi/ml 3.88 E-05 8.27 E-06 1.29 E+00 2.76 E-01 2.88 8+02 5.54 E+01 3.50 E+01 Ci uCi/ml 3.Dissolved and Entrained Gases A.Total Release B.Average Diluted Concentration during Period C.Percent of Technical Specification Limit 3.70 E-02 1.08 E"03 3.50 B+01 4.99 E-09 1.62 E-10 2.50 E-03 8.09 E-05 4.Gross Alpha Radioactivity Total Release LLD LLD 3.50 E+01 2/6

'l 4/~i 0 k p V*'y yl$p C'I~I V Cg II'i P 4 Semiannual Radioactive Bffluent Release Report July 1, 1992 to December 31, 1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EPFLUBNTS-SUMMATION OP ALL" RELEASES Units Quarter Quarter 3 4 Est.Total Error 5.Volume of water released prior to dilution A.Batch Release liters 5.87 E+06 2.53 E+06 1.00 E+01 B.Continuous Release liters.2.60 E+07 2.40 B+07 1.00 E+01 C.Total Effluent Released liters 3.19,E+07 2.65 B+07 1.00 B+01 6.Volume of dilution water used during period.liters 7.38 E+09 6.68 E+09 1.00 E+01 7.Total Volume Released (Releases+Dilution)liters 7.41 E+09 6.70 B+09 2/7 I~g Il 1p~C Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 2 (Continued):

Effluent and Enclosure 2: Effluents Waste Disposal Report Released Table 2B LIQUID EFFLUENTS 1.Fission and Activation Products CONTINUOUS BATCH Nuclides Released Units Q3 Q4 Q3 Q4 Gr.Alpha H-3 Fe-55 Ni-63 Sr-89 Sr-90 Be-7 Na-24 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Sr-92 Zn-65 Y-93 Zr-95 Nb-95 Tc-99m Mo-99 Ru-103 Cd-109 Ag-110m,.Sn-113 Sb-122 Sb-124 Sb-125 Te-132 I-131 I-132 I-133 I-135 Cs-134 Cs-137 Cs-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci.Ci Ci Ci Ci<LLD 2.21E-O<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 1.95E-O<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<I LD<LLD'LLD<LLD<LLD<LLD<LLD<LLD<LLD.<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 2.878+02 9.678-03<LLD<LLD<LLD<LLD 2.64E-05 1.868-03 7.018-04 1.718-04 7.25E-02 5.298-05 1.338-02<LLD<LLD<LLD 7.108-05 1.348-04-3.748-05 4.288-05<LLD<LLD 2.018-05<LLD 7.558-05<LLD 1.45E-02 2.59E-05 9.288-03 3.398-07 1.078-04 1.06E-06 1.988-04 4.30E-04 3.218-08 TABLE CONTINUED ON NEXT PAGE<LLD 5.528+01 4.258-02<LLD<LLD<LLD<LLD<LLD 2.298-03 5.45E-04 1.128-04 4.248-02 1.238-04 1.328-02<LLD<LLD<LLD 2.478-04 4.448-04<LLD<LLD 1.948-05 1.178-04<LLD<LLD 2.50E-OS<LLD 2.03E-02 5.67E;06 3.35E-03<LLD 2.14E-04<LLD 1.35E-04 4.668-04<LLD 1 1~~~~~

Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS (Continued)

Fission and Activation Products (Continued)

CONTINUOUS BATCH Nuclides Released Units Q3 Q4 Q3 Cs-139 Ba-139 Ce-141 Ce-143 Ce-144 Pr-144 Ba-140 La-140 Hf-181 Ci Ci Ci Ci Ci Ci Ci Ci Ci<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 6.968-06<LLD 3.238-04<LLD 8.538-05<LLD<LLD<LLD<LLD<<LLD<LLD<LLD<LLD 3.688-05 2.868-05 Totals 2.218-01 1.958-01 2.888+02 5.53E+01 2.Dissolved and Entrained Gases Nuclides Released Units CONTINUOUS Q3 Q4 BATCH Q3 Xe-131m Xe-133 Xe'-133m Xe-135 Ci Ci Ci Ci<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD 4.33E-04 3.508-02 1.37E-03 2.298-04 1.858-05 1.048-03<LLD 2.59E-05 Totals Ci<LLD<LLD 3.70E-02 1.088-03 2/9 0 e I/

s~~Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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)Type of Waste a.Spent Resin, filter sludge, evaporator bottoms, etc.Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type A Shipment Form 5 2.18 E+01 Ci 10%'.29 E+01 m~N/A Strong Tight Package, NRC-Approved Package Dewatered Solidified b.Dry Compressible Waste, Contaminated Equipment, etc.(DAW)Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 58 1.44 E+00 Ci 10%1.76 E+01 m~N/A Strong Tight Package Dewatered Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)

No waste of this type shipped.2/10 0 1 kg J Semiannual Radioactive Effluent Release Report July 1, 1992 to'ecember 31, 1992 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)Estimate of Major Nuclide Composition (by type of Waste)Spent Resin, Nuclide H-3 C-14 Mn-54 Co-58 Co-60 Fe-55, Ni-63 Cs-137 Zr-95 Nb-95 Cs-134 filter sludge, Percent Composition 5.20 B-Ol~8.47 B-02 5.33 E+00 9.86 E+00 2.36 Ei01 4.47 E+01 1.50 E+01 4.53 E-01 1.35 B-01 3.02 E-01 5.64 E-02 evaporator bottoms, etc.Total Activity Ci 1.13 E-01 1.85 E-02 1.16 E+00 2.15 B+00 5.15 E+00 9.74 E+00 3.26 E+00 9.98 E-02 2.95 E-02 6.59 E-02 1.23 E-02 Nuclide H-3 C-14 Fe-55 Co-58 Co-60 Ni-59 Ni-63 Nb-95 Mn-54 Zr-95 Cs-134 Cs-137 Ce-144 Dry Compressible Waste, Percent Composition 5.38 E-01 1.86 E-01 6.18 E+01 9.41 E+00 2.03 E+01 4.42 E-01 2.80 B+00 1.52 E-01 1.62 E+00 1.29 E-01 3.12 E-01 1.38 8+00 8.79 E-01 Contaminated Equipment, etc.(DAW)Total Activity Ci 7.77 E-03 2.70 E-03 8.94 E-01 1.36 E-01 2.94 E-01 6.39 E-03 4.05 E-02 2.20 E-03 2.35 E-02 1.86 E-03 4.50 E-03 2.00 E-02 1.27 E-02 C.Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)

No waste of this type shipped 2/11 I-ll C lf Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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*Mode of Transportation Destination 63 Truck Barnwell, S.C.All five of the type 1.A.a shipments were made from the Harris Site.All 58 of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG)processing facility in Oak Ridge, Tennessee.

2/12

'44 4'l,l 4 I I~'4 tV)I'I 4'4g' J~~'Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31,.1992 Appendix 2 (Continued):

Effluent and Waste Disposal Report Enclosure 3: Solid Waste Disposal 2.Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal (WASTE CLASS B)Type of Waste Spent Resin, filter sludge, evaporator bottoms, etc.Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 1 5.31 E+01 Ci 10%3.85 E+00 m'/A NRC Approved Package Dewatered b.Dry Compressible Waste, Contaminated Equipment, etc.(DAW)d.No waste of this type shipped Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)

No waste of this type shipped 2/13 J J' S'emiannual Radioactive Effluent Release Report July 1 , 19 92 to December 3 1, 19 9 2 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 B)Estimate of Major Nuclide Composition (by'type of Waste)Spent Resin , filter sludge , evaporator bottoms, etc.Nuclide Percent Composition Total Activity Ci H-3 C"14 Mn-54 Co-60 Fe-55 Ni-63 Cs-137 Sr-90 Co-58 Cs-134 Am-241 7.78 E-03 5.69 E-01 4.84 E+00 1.69 E+01 4.01 E+01 3.29 E+01 1.39 E+00 5.22 E-03 2.54 E+00 6.61 E-01 1.30 E-05 4.13 E-03 3.02 E-01 2.57 E+00 8.99 E+00 2.13 E+01 1.75 E+01 7.37 E-01 2.77 E-03 1.35 E+00 3.51 E-01 6.85 E-06 b.Dry Compressible Waste, Contaminated Equipment, etc.(DAW)No waste of this typed shipped C.Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)

No waste of this type shipped Solid Waste Disposal Number of Shipments Mode of Transportation Destination 1 Truck Barnwell, S.C.2/14 Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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 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.

fc I E 1 t r Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 3: Changes to Process Control Program (PCP)Technical Specification 6.13 No changes to the Process Control Program (PCP)were made during this Report period.

t~g~vt Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 4: Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 No changes to the Off-Site Dose Calculation Manual (ODCM)were made during this Report period.A change to ODCM Table 4.1 has been submitted for approval.This change is described in Appendix 5.The change will be approved and included in the next Report.

L~y+I$4 4, I/

Semiannual Radioactive Effluent Release Report July 1, 1992 to>December 31, 1992 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 The location of water sample 40 was changed from U.S.Geological Survey stream gauging station on the Cape Fear River at Lillington, N.C.to an upstream location at the N.E.Harnett County Metro water treatment plant.The change was made to improve the consistency of sampling and personnel safety.A change to ODCM Table 4.1 has been submitted for approval.No change to Figure 4.1-3 is needed.

l~/g Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 2: Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No changes to the Land Use Census were made during this Report period.5/2 t I l\/L Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service

>30 Days During the Report Period Effluent Monitor Days Inop Reason for Inoperability REM-01SW-3500A Normal Service Water System Return from the Waste Processing Building to the Circulating Water System Radiation Monitor 30 Monitor was out of service to install improved flow switch.After several attempts, switch could not be correctly calibrated.

NED-vendor discussions revealed that the vendor could not supply switch to required cal specs and that old design switch should be installed.

Old design switch was not immediately available.

Old design switch was found and installed k~~I 1 6'S E Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service

>30 Days During the Report Period Effluent Monitor Days Inop Reason for Inoperability RM-01TV-3536-1 Turbine Building Vent Stack 3A Flow Rate Monitor , PNL-1WV-3546&PNL-1WV-3546-1 WPB Vent Stack 5 Flow Rate Monitor 30 Moisture interferences with the flow measurement system resulted in discrepancies between actual and expected flow rates.Modification initiated to correct has been completed and monitor has been returned to operability.

Flow monitor calculates flow rate based on inputs (on/off signal)from WPB ventilation fan breakers.The monitor was declared inoperable because one of the fan breakers had malfunctioned and could not provide input.The affected fan was also placed out of service during this time period.6/2 1 1 L'v~i 4 c l I Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : 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.6/3 l'f f~1 P t I I Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 6 (Continued):

Additional Technical Specification Responsibilities : 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.

4 4 g V f%lh~>~it 4 rg~I C/I'I h i, I C d1~gt't Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 7: Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications to the Radwaste System were made during this Report period.'

0 4 1~y l II I IT Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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 in a file.This data will be provided, to the NRC upon request.

~k 1~g%*5p C 1 w" Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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 Sport Fish Comm fish Sport Invert Comm Invert Drinking Water Shoreline Swimming Boating Irri Veg Irri Leafy Veg Irri Milk Zrri Meat Bone 9.61 0.00 0.00 0.00.3.41 8.71 5.01 2.56 0.00 0.00 0.00 0.00 8-03 8+00 8+00 E+00 8-03 8-03 E-05 8-05 E+00 E+00 E+00 8+00.Liver 1.68 8-02 0.00 E+00 0.00 E+00 0.00 E+00 9.42 8-01 8.71 E-03 5.01 E-OS 2.56 8-05 0.00 8+00 0.00 8+00 0.00 8+00 0.00 8+00 1.12 0.00 0.00 0.00 9.42 8.71 5.01 2.56 0.00 0.00 0.00 0.00 8-02 E+00 8+00 8+00 8-01 8-03 E-05 E-05 8+00 8+00 E+00 8+00 W.Body 3.61 0.00 0.00 0.00 9.43 8.71 5.01 2~56 0.00 0.00 0.00 0.00 E-03 E+00 8+00 8+00 E-Ol E-03 8-05 8-05 8+00 8+00 8+00 8+00 Thyroid 7.72 0.00 0.00 0.00 9.40 8.71 5.01 2.56 0.00 0 F 00 0.00 0.00 8-03 E+00 8+00 E+00 8-01 8-03 E-05 8-05 E+00 E+00 8+00 E+00 Kidney Lung 5.14 8-03 0.00 E+00 0.00 8+00 0.00 E+00 9.40 E-ol 8.71 E-03 5.01 E-05 2.56 E-05 0.00 8+00 0.00 8+00 0.00 E+00 0.00 8+00 GI-LLI 7.56 E-03 0.00 8+00 0.00 8+00 0.00 8+00 9.57 8-01 8.71 8-03 5.01 8-05 2.56 8-05 0.00 8+00 0.00 E+00 0.00 8+00 0.00 8+00 Skin 0.00 E+00 0.00 8+00~0.00 8+00~0.00 E+00 0.00 8+00 1.02 E-02 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 ALL PATHWAYS 2.18 8-02 9.68 E-01 9.62 E-01 9.56 8-01 9.56 E-01 9.54 E-01 9.73 8-01 1.02 E-02 Total Tritium (Hydrosphere)

Bone Liver~W.Body Thyroid Kidney 0.00 E+00 1.21 E-02 1.21 8-02 1.21 8-02 1.21 E-02 Lung GZ-LLZ 1.21 8-02 1.21 E-02 2.Integrated Population Dose Due to Gaseous Effluents (man-rem)50 mile Ingestion Zone W.Body GZ-LLZ Bone Liver Kidney Thyroid Lung Skin Plume Ground Plane Inhalation Vegetation Cow Milk Meat&Poultry 2.63 1.92 7.29 2.21 1.24 1.07 E-Ol E-03 8-04 8-04 E-04 8-04 2.63 1.92 7.37 2.43 1.07 1.41 8-01 2 8-03 1 8-04 2 8-04 2 8-04 3 E-04 4.63 E-ol.92 8-03.39 8-05.22 8-05.60 E-05.57'-06 2.63 1.92 7.43 2.30 1.48 1.06 8-01 8-03 8-04 8-04 E-04 8-04 2.63 8-01 1.92 E-03 7.54 8-04 2.24 8-04 1.41 8-04 1.01 E-04 2.63 8-01 1.92 8-03 8.66 8-03 4.12 E-03 6.33 8-03 5.93 E-04 2.79 1.92 1.29 1.99 1.03 9.67 E-01 8-03 8-03 8-04 8-04 E-05 8.65 E-01 2.25 E-03 7.09 8-04 1.97 E-04 9.99 E-OS 9.61 8-05 Total 2.66 E-01 2.66 8-01 2.65 E-01 2.66 8-01 2.66 8-01 2.85 E-ol 2.82 E-Ol 8.68 8-01 l~~I t Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 9: Assessment of Radiation Doses Enclosure'2: Doses to General Public Due to Activities Inside Site Boun'dary 1.Individual Dose Due to Liquid Effluents (mrem/yr.)

Ol~~ADULT Fish.Shoreline Swimming Boating Total Bone 9.83 E-03 8.41 E-04 5.47 E-05 6.26 E-05 1.08 E=02 Liver 1.88 E-02 8.41 E-04 5.47 E-05 6.26 E-05 1.98 E-02 W.Body 1.43 E-02 8.41 E-04 5.47 E-05 6.26 E-05 1.53 E-02 Thyroid 4.42 E-03 8.41 E-04 5.47 E-OS 6.26 E-05 5.38 E-03 Kidney 8.87 E-03 8.41 E-04 5.47 E-05 6.26 E-05 9.83 E-03 Lung 5.95 E-03 8.41 E-04 5.47 E-05 6.26 E-05 6.91 E-03 Gi-LLI 9.68 E-03 8.41 E-04 5.47 E-05 6.26 E-05 1.06 E-02 Skin 9.86 E-04 9".86 E-04 TEEN Fish Shoreline'wimming Boating 1.05 E-02 4.70.E-03 8'0 E-05 9.11 E-OS 1.83 E-02 4.70 E-03 8.20 E-05 9.11 E-05 9.14 E-03 4.70 E-03 8.20 E-05 9.11 E-05 3.44 E-03 4.70 E-03 8.20 E-05 9.11 E-05 8.07 E-03 4.70 E-03 8.20 E-05 9.11 E-OS 5.35 E-03 4.70 E-03 8.20 E-05 9.11 E-05 7.07 E-03 4.70 E-03 8.20 E-OS 9.11 E-05 5.50 E-03 Total 1.54 E-02.2.32 E-02 1'0 E-02 8.31 E-03 1.29 E-02 1.02 E-02 1.19 E-02 5.50 E-03 CHILD Fish Shoreline Swimming Boating 1.31 E-02 9.81 E-04 2.73 E-05 3.42 E-05 1.62 E-02 9.81 E-04 2.73 E-05 3.42 E-05 5.31 E-03 9.81 E-04 2.73 E-05 3.42 E-05 2.89 E-03 9.81 E-04 2.73 E-OS.3.42 E-05 6.81 E-03 9.81 E-04 2.73 E-05 3.42 E-05 4.38 E-03-9.81 E-04 2.73 E-05 3.42 E-05 4.01 E-03 9.81 E-04 2.73 E-05 3.42 E-05 Total 1.41 E-02 1.72 E-02 6.35 E-03 3.93 E-03 7.85 E-03 5.42 E-03 5.05 E-03 1.15 E-03 9/2 t~r Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 9: Assessment of Radiation Doses Bnclosure 2 (Continued):

Doses to General Public Due to Activities Inside Site Boundary 2.Individual Dose Due to Gaseous EfFluents (mrem/yr.)

ADULT Plume Ground Inhalation Total TEEN Plume Ground Inhalation W.Body 1.05 8-02 9.62 8-05 6.31 8-06 1.06 E-02 1.05 8-,02 9.62 E-05 6.39 8-06 GI-LLI 1.05 8-02 9.62 E-05 6.56 8-06 1.06 E-02 1.05 E-02 9'2 E-05 6.56 8-06 Bone 1.05 8-02 9.62 8-05 2.54 8-07 1.06 8-02 1.05 8-02 9'2 8-05 3.55 8-07 Liver 1.05 8-02 9.62 E-05 6.45 E-06 1.06 E-02 1.05 E-02 9.62 8-05 6.64 E-06 Kidney 1.05 8-02 9.62 E-05 6.59 E-06 1.06 8-02 1.05 8-02 9.62 8-05 6.82 E-06 Thyroid 1.05 8-02 9.62 E-05 9.90 E-05 1.07 E-02 1.05 8-02~9.62 E-05 1.21 8-04 Lung 1.07 8-02 9.62 E-05 1.49 8-05 1.08 8-02 1.07 E-02 9.62 E-05 1.90 8-05 Skin 2.21 8"02 1.13 8-~6.06 8-+2.22 8-02 2.21 8-02 1.13 E-04 6'0 8-06 Total 1.06 8-02 1.06 8-02 1.06 8-02" 1.06 E-02 1.06 8-02 1.07 E-02 1.09 8-02 2.22 E-02 CHILD.Plume Ground Inhalation Total INFANT Plume Ground Inhalation Total 1.05 E-02 9.62 8-05 5.66 8-06 1.06 8-02 1.05 8-02 9.62 8-05 3.28 8-06 1.06 8-02 1.05 E-02 9.62 8-05 5.57 E-06 1.06 8-02 1.05 E-02 9.62 8-05 3.16 8-06 1.06 8-02 1.05 8-02 9.62 E-05 4.81 8-07 1.06 8-02 1.05 E-02 9.62 8-05 3.61 E-07 1.06 8-02 1.05 E-02 9.62 E-05 5.91 8-06 1.06 E-02 1.05 8-02 9.62 8-05 3.55 8-06 1.06 E-02 1.05 8-02 9.62 8-05 6.07 E-06 1.06 E-02 1.05 8-02 9.62 E-05 3.54 8-06 1.06 8-02 1.05 E-02 9.62 E-05 1.33 E-04 1.07 E-02 1.05 E-02 9.62 8-05 1.20 E-04 1.07 E-02 1.07 8-02'.62 E-05 1.58 8-05 1.09 E-02 1.07 8-02 9.62 8-05 9.78 8-06 1.08 E-02 2.21 8-02 1.13 E-04 5.40 8-06 2.22 E-02 2.21 E-02 1.13 E-04 3.10 E-2.22 E-02 9/3 I~~o ,(11 K tl Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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.)

Bone Liver W.Body Thyroid Kidney Lung.GZ-LLI Skin ADULT Fish Drinking Shoreline Swimming Boating 9.83 1.11 8.41 5.47 6;26 E-03 E-04 E-04 E-05 E-05 1.88 E-02 3.97 E-02 8.41 E-04 5.47 E-05 6.26 E-05 1.43 3.97 8.41 5.47 6.26 E-02 E-02 E-04 E-05 E-05 4.42 3.98 8.41 5.47 6.26 E-03 E-02 E-04 E-05 E-05 8.87 E-03 3.96 E-02 8.41 E-04 5.47 E-05 6.26 E-OS 5.95 E-03 3.97 E-02 8.41 E-04 5.47 E-05 6.26 E-05 9.68 4.05 8.41 5.47 6.26 E-03 E-02 E-04 E-05 E-05 9.86 E-04 Total 1.09 E-02 5.95 E-02 5.50 E-02 4.52 E-02 4.95 E-02 4.66 E-02 5.11 E-02 9.86 E-04 TEEN Fish Shoreline Swimming Boating 1.05 E-02 4.70 E-03 8.20 E-05 9.11 E-05 1.83 E-02 4.70 E-'03 8.20 E-05 9.11 E-OS 9.14 E-03 3.44 E-03 8.07 E-03 4.70 E-03 4.70 E-03 4.70 E-03 8.20 E-05 8.20 E-OS,, 8.20 E-05 9.11 E-05.9.11 E-05 9.11 E-OS 5.35 E-03 4.70 E-03 8.20 E-OS 9.11 E-05 7.07 E-03 4.70 E-03 8.20 E-05 9.11 E-05 5.50 E-03 Total 1.53 E-02 2.32 E-02 1.40 E-02 8.31 E-03 1.29 E-02-1.02 E-02 1.19 E-02 5.50 E-03 CHILD Fish Shoreline Swimming Boating Total 1.31 E-02 9.81 E-04 2.73 E-05 3.42 E-05 1.42 E-02 1.62 E-02 9.81 E-04 2.73 E-05 3.42 E-05 1.72 E-02 5.31 E-03 9.81 E-04 2.73 E-05 3.42 E-05 6.36 E-03 2.89 E-03 9.81 E-04 2.73 E-05 3.42 E-05 3.93 E-03 6.81 E-03 9.81 E-04 2.73 E-05 3.42 E-05 7.86 E-03 4.38 E-03 9.81 E-04 2.73 E-05 3.42 E-05 5.42 E-03 4.01 E-03 9.81 E-04 2.73 E-05 3.42 E-05 5.05 E-03 1.15 E-03 1.15 E-03 9/4

~~f~g tt t l~t Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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 GZ-LLZ Bone Liver Kidney Thyroid Skin ADULT Plume Ground Inhalation Vegatation Milk Goat Milk Meat&Poultry Total 1.52 9.90 1.79 3.61 1.08 3.61 3.60 1.54 E-01 E-04 E-04 E-04 E-04 E-04 E-05 E-01 1.52 9.90 1.81 4.19 8.20 2.32 5.48 1.54 E-01 E-04 E-04 E-04 E-05 E-04 E-OS E-01 1.52 E-01 9.90 E-04 5.04 E-06 4.43 E-05 3.61 E-05 1.28 E-04 2.94 E-06 1.53 E-01 1.52 E-01 9.90 E-04 1.81 E-04 3.74 E-04-1.27 E-04 4.24 E-04 3.59 E-05 1.54 E-01 1.52 E-01 9.90 E-04 1.83 E-04 3.31 E-04 1.20 E-04 3.49 E-04 3.25 E-05 1.54 E-01 1.52 E-01 7.56 1.53 3.02 1.81 E-03 E-02 E-04 E-01 9.90 E-04 1.83-E-03 2.97 E-03 1.56 9.90 3.07 3.02 7.36 2.34 3.02 1.58 E-01 E-04 E-04 E-04 E-05 E-04 E-OS E-01 3.29 1.16 1.74 2.95 6.98 2.16 2.97 3.30 E-01 E-OS E-04 B-05 E-01 TEEN Plume Ground Znhalation Vegatation Milk Goat Milk Meat&Poultry Total 1.52 9.90 1.80 4.13 1.38 4.39 2.17 1.54 E-Ol E-04 E-04 E-04 E-04 E-04 E-05 E-01 1.52 9.90 1.82 4.77 1.06 3.02 3.12 1.54 E-01 E-04 E-04 E-04 E-04 E-04 E-05 E-01 1.52 9.90 7.05 6.78 6.49 2.30 2.42 1.54 E-01 E-04 E-06 E-05 E-05 E.-04 E-06 E-01 1.52 E-01 9.90 E-04 1.85 E-04 4.66 E-04 1.91 E-04 6.46 E-04 2.26 E-05 1.55 E-01 1.52 E-01 9.90 E-04 1.88 E-04 3.94 E-04 1.81 E-04 5.15 E-04 2.00 E-OS 1.54 E-01 1.52 9.90 2.21 2.61 1.19 2.41 2.15 1.94 E-01 E-04 E-03 E-03 E-02 E-02 E-04 E-01 1.56 9.90 3.70 3.60 9.85 3.17 1.81 1.58 B-01 E-04 B-04 E-04 E-OS E-04 E-05 E-01'.29 1.16 1.75 3.47 9.10 2.81 1.77 3.31 E-01 E-03 E-04 E-04 E-OS E-04 E-05 E-01 CHILD Plume Ground Znhalation Vegatation Milk Goat Milk Meat R Poultry Total INFANT Plume Ground Znhalation Milk Goat Milk Total 1.52 9.90 1.59 6.21 2.04 6.09 2.62 1.55 1.52 9.90 9.21 3.14 9.03 1.54 E-Ol E-04 E-04 E-04 E-04 E-04 E-OS E-01 E-01 E"04 E-OS E-04 E-04 B-01 1.52 9.90 1.57 6.26 1.55 4.61 2.82 1.55 1.52 9.90 8.98 2.29 6.90 1.54 E-01 E-04 E-04 E-04 E-04 E-04 E-05 E-01 E-01 E-04 E-05 E-04 E-04 E-01 1.52 9.90 9.52 1.57 1.56 5.48 4.41 1.54 1.52 9.90 7.02 2.84 9.47 1.54 E-01 E-04 E-06 E-04 E-04 E-04 E-06 E-01 E-01 B-04 E-06 E-04 E-04 E-01 1.52 E-01 9.90 E-04 1.65 E-04 7.36 E-04 3.15 E-04 1.06 E-03 2.76 E-OS 1.55 E-01 1.52 E-01 9.90 E-04 9.76 E-05 5.82 E-04 1.93 E-03 1.56 E-01 1.52 9.90 1.67 6.13 2.92 8.30 2.42 1.55 1.52 9.90 9.69 4.70 1.32 1.55 E-Ol E-04 E-04 E-04 E-04 E-04 E-OS E-01 E-01 E-04 E-OS E-04 E-03 E-01 1.52 9.90 2.43 4.02 2.35 4.75 3.19 2.31 1.52 9'.90 2.17 5.71 1.15 3.27 E-01 E-04 E-03 E-03 E-02 E-02 E-04 E-01 E-01 E-04 E-03 E-02 E-01 E-01 1.56 9.90 3.13 5.61 1.55 4.99 2.19 1.58 1.56 9.90 1.90 2.38 7.71 1.58 E-Ol E-04 E-04 E-04 E-04 E-04 E-05 E-01 E-01 E-04 E-04 E-04 E-04 E-Ol 3.29 1.16 1.55 5.41 1.44 44 2.14 3.31 3.29 1.16 8.89 2.18 6.74 3.31 E-01 E-03 E"04 E-05 B-01 B-01 E-03 E-05 E-04 E-04 E-01 9/5 C gl 4 ly i II Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 9: Assessment of Radiation Doses Enclosure 3 (Continued):

Doses to Likely Most Exposed Member of the Public 2.Zndividual Dose Due to Gaseous Effluents (mrem/yr.)

B.Maximum Real Zndividual

-Exposure from Noble Gases, Particulates, Iodines, and Tritium ADULT Plume Ground Inhalation Total TEEN Plume Ground Inhalation W.Body 3.68 B-02 3.82 E-04 1.27 B-04 3.73 E-02 3'8 E-02 3.82 E-04 1.27 E-04 GI-LLl 3.68 E-02 3.82 E-04 1.26 E-04 3.73 E-02 3.68 E-02 3.82 E-04 1.27 E-04 Bone 3.68 E-02 3.82 E-04 2.34 E-06 3.71 E-02 3.68 E-02 3.82 E-04 3.27 E-06 Liver 3.68-E-02 3.82 E-04 1.28 B-04 3.73 E-02 3.68 E-02 3.82 E-04 1.30 E-04 Kidney 3.68 E-02 3.82 E-04 1.28 E-04 3.73 E-02 3.68 E-02 3.82 E-04 1.30 E-04 Thyroid 3.68 E-02 3.82 E-04 7.26 E-04 3.79 E-02 3.68 E-02 3.82 E-04 8.66 E-04 3.77 E-02 3.82 E-04 1.53 E-04 3.82 E-02 3.77 E-02 3.82 E-04 1.67 E-04 Skin 8.23 E-4.49 E-0 1.24 E-04 8.29 E-02 8.23 E-02 4.49 E-04 1.25 E-04 Total 3.73 E-02 3.73 E-02 3.71 E-02 3.73 E-02 3.73 E-02 3.80 E-02 3.82 E-02 8.29 E-02 CHZLD Plume Ground Inhalation Total 3.68 E-02 3.82 E-04 1.12 E-04 3.73 B-02 3.68 B-02 3.82 E-04 1.11 E-04 I 3.73 E-02 3.68 E-02 3.82 E-04 4.40 E-06 3.71 E-02 3.68 E-02 3.82 E-04 1.15 E-04 3.73 E-02 3.68 E-02 3.82 E-04 1.15 E-04 3.73 E-02 3.68 E-02 3.82 E-04 9.37 E-04 3.81 E-02 3.77 E-02 8.23 E-02 3.82 E-04 4.49 E-04 1.45 E-04 1.11 E-04 3.82 E-02 8.28 E-02 INFANT Plume Ground Inhalation Total 3.68 E-02 3.82 E-04 6.48 E-OS 3.72 E-02 3.68 E-02 3.82 E-04 6.38 B-05 3.72 E-02 3.68 E-02 3.82 E-04 3.12 B-06 3.71 E-02 3.68 E-02 3.82 E-04 6.75 E-05 3.72 E-02 3.68 E-02 3.82 E-04 6.67 E-05 3'2 E-02 3.68 E-02 3.77 E-02 8.23 E-~3.82 E-04.3.82 E-04 4.49 E-~8.18 E-04 8.55 E-05 6.36 E-05 3.80 E-02 3.81 E-02 8.28 B-02 9/6

~pl.a Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 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=3.48 E-01 Gamma=2.38 E-01 B.Maximum Real Individual:

Beta=9.00 E-02 Gamma=5.77 E-02 4.Doses Due to Direct Radiation from the Harris Plant On-going environmental TLD dose measurements show that the offsite Direct Radiation Dose is negligible.

9/7 r>'-Ik l U'I.e I~l,~4y 4 I t Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 9: Assessment of Radiation Doses Enclosure 4: Major Assumptions Used to Calculate Radiation Doses 1.Doses Due to Liquid Effluents Dilution Factors Location Harris Lake Cape Fear River Cape Fear River/Raven Rock Park Value 1.00 E+01 2.06 E+02 2.06 E+02 t E osure Pathwa s Shoreline, Swimming, Boating, Fish Consumption Shoreline, Drinking Water (for Harnett County, Lillington, Dunn, and Fayetteville)

Boating B.Populations Affected Location Value E osure Pathwa s Harris Lake Harris Lake Harnett County Dunn Intake Fayetteville Area Fuquay-Varina Holly Springs Harris Lake/Cape Fear River Cape Fear River/Raven Rock Park Raven Rock Park 1.10 1.20 4.53 1.67 1.40 2.68 2.27 E+05 person-hours E+03 persons E+04 persons E+04 persons E+05 persons E+03 persons E+02 persons Shoreline, Swimming, Boating Drinking Water Drinking Water Drinking Water Drinking Water Drinking Water Drinking Water 5.00 E+04 person-hours 4.40 E+05 person-hours Boatinq Shoreline 7.84 E+03 person-hours Fishing C.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.9/8

)>Cs Semiannual Radioactive Effluent Release Report July 1, 1992 to December 31, 1992 Appendix 9: Assessment of Radiation Doses Enclosure 4 (Continued):

Major Assumptions Used to Calculate Radiation Doses 2.Doses Due to Gaseous Effluents B.C.D.The 50 mile Ingestion Zone population is 1.47 E+06 persons.The Maximum Real Individual is located at 2414 meters (-1.5 miles)in the NNW sector.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 NNE sector from the plant, which is the closes't 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.9/9

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