ML031390555

From kanterella
Jump to navigation Jump to search
Annual Radiological Environmental Operating Report - 2002, 4.0 Evaluation of Dose
ML031390555
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 05/05/2003
From: Jamil D
Duke Power Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML031390555 (51)
v • d • e


Text

4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2002 MNS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program dose estimates.

Doses based on sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses. Where applicable, average background concentration at the corresponding control location was subtracted.

Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. When the guide listed "NO DATA" as the dose factor for a given radionuclide and organ, a dose factor of zero was assumed.

Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, fish, and shoreline sediment sample results are reported in Table 4.1-A. The individual critical population and pathway dose calculations are reported in Table 4.1-B.

REMP-based dose estimates are not reported for airborne radioiodine, airborne particulate, milk, or broadleaf vegetation sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates are not reported for surface water because sampled surface water is not considered to be a potable drinking water source. Exposure estimates based upon REMP TLD results are discussed in Section 3.9.

The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2002 was 5.84E-02 mrem to the maximum exposed child's liver, total body, thyroid, kidney, lung and GI-LLI from drinking water.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2002 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. The 2002 MNS Annual Radioactive Effluent Release Report (reference 6.6) included calendar year dose estimates for the location with the highest individual organ dose from liquid and gaseous effluent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

Section 4 - Page I

The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas exposure there is no critical age group; as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, inhalation, milk and vegetation pathways.

4.3 COMPARISON OF DOSES The environmental and effluent dose estimates given in Table 4.1-A agree reasonably well. The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways. This indicates that effluent program dose estimates are both valid and reasonably conservative.

There are some differences in how effluent and environmental doses are calculated that affect the comparison. Doses calculated from environmental data are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.

In calculations based on liquid release pathways, drinking water and fish consumption were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2002 environmental sample results was 1.09E-01 mrem to the child liver. The maximum total organ dose of 7.82E-02 mrem for liquid effluent-based estimates was to the child liver.

No environmental doses resulted from the gaseous pathway in 2002 because broadleaf vegetation, milk, and airborne radioiodines and particulates indicated no activity. The gaseous effluent dose is due to tritium on broadleaf vegetation.

Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.

The doses calculated do not exceed the 40CFR190 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of MNS are being maintained well within regulatory limits.

Section 4 - Page 2

TABLE 4.1-A Page 1 of 3 MCGUIRE NUCLEAR STATION 2002 ENV7IRONMENTAL AND EFFLUENT DOSE COMPARISON LIOUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose (3)

Organ Effluent Data Age () Pathway (2) Location (mrem)

Skin Environmental Teen Shoreline Sediment 130 (0.5 mi SW) 2.05E-04 Skin Effluent Teen Shoreline Sediment 0.5 mi. ENE 5.22E-04 Bone Environmental Child Fish 129 (0.5 mi ENE) 5.26E-02 Bone Effluent Child Fish 0.5 mi. ENE 1.09E-02 Liver Environmental Child Drinking Water 101 (3.3 mi E) 1.09E-01 Liver Effluent Child Drinking Water 0.5 mi. ENE 7.82E-02 T. Body Environmental Adult Drinking Water 101 (3.3 mi E) 7.93E-02 T. Body Effluent Child Drinking Water 0.5 mi. ENE 6.94E-02 Thyroid Environmental Child Drinking Water 101 (3.3 mi E) 5.9 1E-02 Thyroid Effluent Child Drinking Water 0.5 mi. ENE 6.76E-02 Kidney Environmental Child Drinking Water 101 (3.3 mi E) 7.55E-02 Kidney Effluent Child Drinking Water 0.5 mi. ENE 7.10E-02 Lung Environmental Child Drinking Water 101 (3.3 mi E) 6.50E-02 Lung Effluent Child Drinking Water 0.5 mi. ENE 6.88E-02 GI-LLI Environmental Child Drinking Water 101 (3.3 mi E) 5.95E-02 GI-LLI Effluent Child Drinking Water 0.5 mi. ENE 6.97E-02 (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.

Section 4 - Page 3

Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, an( TRITIUM Environmental or Critical Critical Maximum Dose (3) rgan Effluent Data Age () Pathivay (2) Location (mrem)

Skin Environmental - O.OOE+00 Skin Effluent All Ground Plane 0.5 mi. E 7.70E-07 Bone Environmental - O.OOE+00 Bone Effluent Child Vegetation 0.5 mi. E 8.87E-07 Liver Environmental - O.OOE+00 Liver Effluent Child Vegetation 0.5 mi. E 7.42E-01 T. Body Environmental - O.OOE+00 T. Body Effluent Child Vegetation 0.5 mi. E 7.42E-01 Thyroid Environmental - O.OOE+00 Thyroid Effluent Child Vegetation 0.5 mi. E 7.42E-01 Kidney Environmental - O.OOE+00 Kidney Effluent Child Vegetation 0.5 mi. E 7.42E-01 Lung Environmental - O.OOE+00 Lung Effluent Child Vegetation 0.5 mi. E 7.42E-01 GI-LLI Environmental - O.OOE+00 GI-LLI Effluent Child Vegetation 0.5 mi. E 7.42E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.

Section 4 - Page 4

Page 3 of 3 NOBLE GAS Air Environmental or Critical Critical Location Maximum Dose Dose Effluent Data Age Pathway (mrad)

Beta Environmental - - - Not Sampled Beta Effluent N/A Noble Gas 0.5 mi.NNE 2.58E-02 Gamma Environmental - - - Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi.NNE 7.1 E-02 Section 4 - Page 5

CC C C r ( rC CS C C (C (C (C C ( CCC C C C C.CiC Cv( C ( (, C ( ( C C\C TABLE 4.1-B Maxilintin Indiiidital Dose for 2002 based ont En vironm,ental Measitsurelnets (nre,n) for McGinire Ntcleari Stationi Age Sample Medium Bone Liver T. Body Tlhyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Drinking Water 0.00E+00 5.73E-02 5.73E-02 5.73E-02 5.73E-02 5.73E-02 5.73E-02 O.OOE+00 Milk 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 TOTAL 0.00E+00 5.73E-02 5.73E-02 5.73E-02 5.73E-02 5.73E-02 5.73E-02 0.00E+00 Child Airborne O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 5.84E-02 5.84E-02 5.84E-02 5.84E-02 5.84E-02 5.84E-02 0.00E+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 5.26E-02 5.10E-02 8.14E-03 7.13E-04 1.71E-02 6.61E-03 1.03E-03 0.00E+00 Shoreline Sediment 3.67E-05 3.67E-05 3.67E-05 3.67E-05 3.67E-05 3.67E-05 3.67E-05 4.29E-05 TOTAL 5.26E-02 1.09E-01 6.66E-02 5.91E-02 7.55E-02 6.50E-02 5.95E-02 4.29E-05 Teen Airborne O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water 0.00E+00 3.05E-02 3.05E-02 3.05E-02 3.05E-02 3.05E-02 3.05E-02 0.00E+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Fish 4.18E-02 5.64E-02 2.02E-02 8.63E-04 1.98E-02 8.21E-03 1.65E-03 O.OOE+00 Shoreline Sediment 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 1.75E-04 2.05E-04 TOTAL 4.20E-02 8.71E-02 5.09E-02 3.15E-02 5.05E-02 3.89E-02 3.23E-02 2.05E-04 Adult Airborne 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Drinking Water 0.00E+00 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fish 3.90E-02 5.45E-02 3.61E-02 1.12E-03 1.92E-02 7.14E-03 2.15E-03 0.00E+00 Shoreline Sediment 3.14E-05 3.14E-05 3.14E-05 3.14E-05 3.14E-05 3.14E-05 3.14E-05 3.67E-05 TOTAL 3.90E-02 9.77E-02 7.93E-02 4.44E-02 6.24E-02 5.04E-02 4.54E-02 3.67E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

( ( [ ( ( ( ( ( ( ( [ c ( ( ( cc ( c ( (r ( r( r( ( r( r( r r r rc c ( r[ ( (

McGuire Nuclear Station Dosefrom Drinking Water Pathlwayfor 2002 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathlway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake In one year)= 330 1 Highest Annual Net Mean Ineestion Dose Factor Concentration Dose (mrem)

Indicator NVater Radionuclde Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCI) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA l.99E05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA S.97E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Fe-59 3.08E-05 5.38E-05 2.12E-OS NO DATA NO DATA 1.59E.05 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Co-60 NO DATA 1.08E05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zn.65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Nb.95 4.20E-08 1.73E-08 1.OOE08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 1.131 3.59E05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Cs.134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E04 7.42E-05 1.91E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOF.+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E07 4.20E-OS ALL 0.00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 11.3 NO DATA 3.08E-07 3.08E07 3.08E07 3.08E07 3.08E-07 3.08E07 101 564.00 O.OOE+00 5.73E02 5.73E-02 5.73E-02 5.73E02 5.73E.02 5.73E-02 Dose Commitment (mrem) = O.OOE+00 5.73E.02 5.73E-02 5.73E-02 5.73E-02 5.73E02 5.73E-02 Secion 4 -Page 7

c( ( ((c((r((( rrc crrrcC (( ( ( (f ( crc c r ( ( ( (( ( (c McGuire NuclearStation Dosefrom Drinking Water Patlway for 2002 Data Maximum Exposed Chiild Child Dose from Drinking Water Pathway (mrem) = Usage () x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year)= 510 1 Highest Annual Net Mean Ineestion Dose Factor Concentration Dose (mreni)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCI) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E.06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 1-37E-05 3.65E-05 2.27E-05 NO DATA 230E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.131 1.72E-05 1.73E-05 9.83E06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Cs-1.34 2.34E-04 3.84E-04 8.10E-5 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 3.27E.04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96F-06 ALI, 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 BaLa-140 831E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 11-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 101 564.00 0.OOE+00 5.84E-02 5.84E-02 5.84E-02 5.84E-02 5.4E-02 5.4E-02 Dose Commitment (mrem) = 0.OOE+00 5.84E-02 5.84E-02 5.84E-02 5.4E-02 5.84E-02 5.84E-02 Section 4 -Page 8

r cr r r r r c c r c c C c r Cc C CCCC Cc C C c Cc C c ( ( C ( ( c McGuire Nuclear Station Dose from Fish Pathway for 2002 Data Maximum Exposed Chlild Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/i x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 565 pCi/l x 0.9 = 509 pCi/kg Usage (intake In one year) = 6.9 kg lighest Annual Net Mean Iniestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCI/kg) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E.06 ALL 0.00 O.OOE+00 0.OOE+00 O.OOE+00 O.OO+00 0.OOE+00 O.OOE+00 O.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 Fe-59 1.65E-05 2.67E-05 1.331-5 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 129 23.30 5.26E-02 5.03E-02 7.43E-03 0.00E+00 1.64E-02 5.90E-03 3.ISE-04 11-3 NO DATA 2.03F,07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 128 509.00 0.OOE+00 7.13E-04 7.13E-04 7.13E-04 7.13E-04 7.13E-04 7.13E-04 Dose Commitment (mre m) = 5.26E.02 5.10E-02 8.14E-03 7.13E-04 1.71E02 6.61E-03 1.03E-03 Section 4 -Page 9

rc ( ( r ( r r f ( ( r ( r r rc r ( ( rc ( r r( r r r ( r c rc ((

McGuire Nuclear Station Dosefrom Shoreline Sediment Pathzway for 2002 Data Maximum Exposed Chzild Shoreline Recreation 14 hr (in one year)

Shore Width Factor = 0.3 (lake shore - location 129)

Shore Width Factor = 0.2 (river shoreline - location 130)

Sediment Surface Mass = 40 kg/m2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremlhr per pCi/rm 2 ) x Shore Width Factor x Sediment Surface Mass (kg/id) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m 2 ) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCI/kg) T. Body Skin Mn-54 5.80E-09 6.80E.09 130 22.40 1.46E-05 1.71E-05 Co-58 7.OOE-09 8.20E-09 ALL 0.00 O.OOE+00 O.OOE+00 Co.60 1.70E-08 2.OOE-08 ALL 0.00 O.OOE+00 O.O0E+OO Cs-134 1.20E-08 1.40E-08 ALL 0.00 O.OOE+00 O.0OE+OO Cs-137 4.20E-09 4.90E-09 130 47.00 2.21E.05 2.58E-05 Dose Commitment (mrem) = 3.67E.05 4.29E-05 Section 4 - Page 10

c( r r r c r c c r r ccc c cc r rrr c rc ( ( rr ( (

McGuire Nuclear Station Dosefrom Drinking Water Patlwayfor2002 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/1)

Usage (intake In one year)= 510 1 Ilighest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung Cl-LLI Location pCI/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E06 1.17E06 NO DATA 1.76E46 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 134E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9-33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Nb-95 8.22E-09 4.56F-09 2.51E-09 NO DATA 4.42E.09 NO DATA 1.95E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E-08 130E-08 8.94E-09 NO DATA 1.91E08 NO DATA 3.OOE-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 1-131 5.85E-06 8.19E06 4.40E-06 2-39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Cs-1.34 8-37E-05 1.97E.04 9.14E-05 NO DATA 6.26E05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.0OE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07F-05 1.97E-05 2.12E-06 ALL 0.00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 11.3 NO DATA 1.06E-07 1.06E-07 1.06E07 1.06E-07 1.06E-07 1.06E-07 101 564.00 0.OOE+00 3.05E-02 3.05E-02 3.05E-02 3.05E-02 3.05E-02 3.05E-02 Dose Commitment (mrem)= 0.00E+00 3.05E-02 3.05E02 3.05E-02 3.05E-02 3.05E-02 3.05E-02 Section 4 - Page II

c r r r r cr r r c r c c r cc r c r r c r c r r r r r r c r r r rc c r r r c c C McGuire Nuclear Station Dose from Fish Patl way for 2002 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrenmpCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/i = 565 pCi/i x 0.9 = 509 pCi/kg Usage (intake In one year)= 16 kg lighest Annual Inrestion Dose Factor Net Mean Dose mrem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung G-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 O.OOE+00 .OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.OOE+00 O.OoE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E.05 ALL 0.00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97K-05 2.12E06 129 23.30 4.18E-02 5.55E-02 1.93E-02 O.OOE+00 1.89E-02 7.34E-03 7.90E-04 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06F-07 128 509.00 0.00E+00 8.63E-04 8.63E-04 8.63E-04 8.6.1E-04 8.63E-04 8.63E-04 Dose Commitment (mrelim)= 4.18E-02 5.64E-02 2.02E-02 8.63E-04 1.98E-02 8.21E-03 1.65E.03 Section 4 -Page 12

McGuire Nuclear Station Dosefrom Shioreline Sediment Pathlwayfor 2002 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.3 (lake shore - location 129)

Shore Width Factor = 0.2 (river shoreline - location 130)

Sediment Surface Mass = 40 kg/m2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mi2 ) x Shore Widthi Factor x Sediment Surface Mass (kg/rr) x Sediment Concentration (pCi/kg)

External Dose Factor Standing lighest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCVnm) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCiVkg) T. Body Skin Mn-54 5.80E-09 6.80E-09 130 22.40 6.96E-05 8.16E-05 Co-58 7.OOE-09 8.20E-09 ALL 0.00 O.OOE+00 0.OOE+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.00E+00 O.OOE+00 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 O.OOE+00 Cs-137 4.20E-09 4.90E-09 130 47.00 1.06E-04 1.23E-04 Dose Commitment (mrem) = 1.75E-04 2.05E-04 Section 4 - Page 13

c r c rrrrrcr rrc c c r r c r rC r r r c r rcr( r cr r c r McGuire Nuclear Station Dose from Drinking Water Pathiwayfor 2002 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake In one year) = 730 1 lighest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Vater Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI.LLI Location (pCilt) Bone Liver T. Body Thyroid Kidney Lung Gl-LLI Mn.54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.5IE-05 ALI, 0.00 0.00E+00 0.00E-i0 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Fe.59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40r-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 1-131 4.16E-06 5.95E06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E.05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Cs-137 7.97E05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 BaLa-140 2.03E4-5 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 11-3 NO DATA 1.05E-07 1.05E07 1.05E-07 1.05E-07 1.OSE-07 1.05E-07 101 564.00 0.00E+00 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E.02 Dose Commitment (mrem) = 0.00E+00 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 Section 4 -Page 14

crec r rr crrccccrrcrrrrrcc crcrcr(c(r_rcc McGuire Nuclear Station Dosefrom Fish Pathwayfor 2002 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 565 pCi/I x 0.9 = 509 pCi/kg Usage (intake inone year) = 21 kg Ilighest Annual Net Mean Inuestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GILLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Fe-59 4.34E.06 1.02E.05 3.91E06 NO DATA NO DATA 2.85E.06 3.40E-05 ALL 0.00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Co.60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Zn-65 4.84E06 1.54E-05 6.96F-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-134 6.22E05 1.48E04 1.21E.04 NO DATA 4.79E05 1.59E-05 2.59E-06 ALL 0.00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOF+00 0.OOE+00 O.OOE+00 Cs-137 7.97E.05 1.09E04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 129 23.30 3.90E-02 5.33E-02 3.49E-02 O.OOE+00 1.81E-02 6.02E,03 1.03E-03 11-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 128 509.00 O.OOE+00 1.12E-03 1.12E-03 1.12E-03 1.12E-03 1.12E-03 1.12E-03 Dose Commitment (mrem) = 3.90E-02 5.45E02 3.61E-02 1.12E-03 1.92E-02 7.14E03 2.15E-03 Section 4 -Page 15

cr r rr r rr rr crrr r r r cr r rrrrr rrrrrrrr rr McGuire Nuclear Station Dose from Shoreline Sediment Pathiwayfor 2002 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.3 (lake shore -location 129)

Shore Width Factor = 0.2 (river shoreline -location 130)

Sediment Surface Mass = 40 kg/m2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremfhr per pCi/rm2 ) x Shore Width Factor x Sediment Surface Mass (kg/n?) x Sediment Concentration (pCi/kg)

External Dose Factor Standing I1[ighest Annual Net Dose on Contaminated Ground klean Concentration (mrem)

(mrern/hr per pCim 2) Indicator Sediment Radionuclide T. Body Skin ILocation (pCUkg) T. Body Skin Mn-54 5.80E-09 6.80E-09 130 22.40 1.25E.05 1.46E05 Co-58 7.00E.09 8.20E-09 ALL 0.00 O.OOE+00 O.OOE+00 Co-60 1.70E-08 2.OOE-08 ALL 0.00 0.OOE+00 O.OOR+00 Cs-134 1.20E-08 1.40R-08 ALL 0.00 O.OOE+O0 O.OOE+00 Cs-137 4.20E-09 4.90E-09 130 47.00 1.90E-05 2.21E-05 Dose Commitment (mrem) 3.14E-05 3.67E-05 Section 4 - Page 16

5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad Laboratories is located in Huntersville, North Carolina, at Duke Power Company's Environmental Center.

5.3 DOSIMETRY ANALYSIS Duke Power Company's Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.

Section 5 - Page I

5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 DUKE POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2002. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2002 is documented in Table 5.0-A.

5.6 DUKE POWVER AUDITS The McGuire Radiation Protection Section was audited by the Quality Assurance Group in January of 2002. There were no findings as a result of this 2002 audit.

EnRad Laboratories was audited by the Quality Assurance Group in June of 2002.

Laboratory practices and procedures were reviewed. No significant problems were identified as a result of this 2002 audit.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The McGuire Nuclear Station Radiological Environmental Monitoring Program was not audited by the NRC in 2002. EnRad Laboratories was not audited by the NRC in 2002.

5.8 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis.

5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

Section 5 - Page 2

of Roswell, GA. Nuclear Technology Services irradiates environmental dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.

5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2002 is documented in Table 5.0-B.

5.9.3 INTERNAL CROSSCHECK (DUKE POWER)

Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Power) Result is documented in Table 5.0-B.

Section 5 -Page 3

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRANM 2002 CROSS-CIECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "I Pass" indicates that one analysis of the cross-check was performed.

Footnote explanations are included following this data table.

rnmmn " Vntor S li'tore Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/Il pCiA 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 ES 1.27 E5 1.25 E5 3 Pass Mn-54 0.82- 1.45 ES 1.09 E5 1.13 E5 3 Pass Fe-59 4.17-7.40 E4 5.56 E4 5.78 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.68 E4 3 Pass Zn-65 0.80- 1.43 E5 1.07 E5 1.12 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.36 E4 3 Pass Cs-137 0.97 - 1.72 E5 1.29 E5 1.24 E5 3 Pass Ce-139 0.00 - 0.00 EQ 0.00 EO 1.82 E3 3 Pass"'

Ce-141 1.17-2.07 E5 1.56 E5 1.55 E5 3 Pass 5/14/2002 Q022GWR Cr-51 6.77 - 12.01 E3 9.03 E3 9.32 E3 3 Pass Mn-54 1.38 - 2.45 E3 1.84 E3 1.98 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.48 E3 3 Pass Fe-59 1.75 - 3.10 E3 2.33 E3 2.44 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.38 E3 3 Pass Zn-65 2.66 - 4.71 E3 3.54 E3 3.73 E3 3 Pass Cs-134 1.68 - 2.98 E3 2.24 E3 2.10 E3 3 Pass Cs-137 1.24 - 2.20 E3 1.65 E3 1.60 E3 3 Pass Ce-141 2.32-4.11 E3 3.09 E3 3.13 E3 3 Pass 8/1612002 Q023GWS Cr-51 1.58-2.80 E5 2.10 E5 2.10 E5 3 Pass Mn-54 5.73- 10.16 E4 7.64 E4 8.16 E4 3 Pass Co-58 4.47 - 7.93 E4 5.96 E4 6.20 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.85 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.20 E4 3 Pass Zn-65 7.16 - 12.70 E4 9.55 E4 1.03 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.78 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.76 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 ES 1.38 E5 3 Pass Section 5 - Page 4

Gamma in Water 3.5 liters continued Reference Sample ID. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCiA pCi/I 11/19/2002 Q024GWR Cr-51 2.08 -3.70 E4 2.78 E4 3.09 E4 3 Pass Mn-54 5.96- 10.56 E3 7.94 E3 9.12 E3 3 Pass Co-57 0.00 - 0.00 EO 0.00 EO 6.65 El 3 Pass"'

Co-58 6.54 - 11.60 E3 8.72 E3 9.79 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 5.95 E3 3 Pass Co-60 6.68- 11.85 E3 8.91 E3 1.02 E4 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.22 E4 3 Pass Cs-134 4.04 - 7.16 E3 5.38 E3 5.46 E3 3 Pass Cs-137 0.89- 1.58 E4 1.19 E4 1.27 E4 3 Pass Ce-141 6.32 - 11.21 E3 8.43 E3 9.56 E3 3 Pass Gamma in WVater 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status CiA _CiIl pCi/I 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 E5 1.27 E5 1.28 E5 3 Pass Mn-54 0.82- 1.45 E5 1.09 E5 1.16 E5 3 Pass Fe-59 4.17 -7.40 E4 5.56 E4 5.85 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.70 E4 3 Pass Zn-65 0.80- 1.43 E5 1.07 E5 1.13 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.51 E4 3 Pass Cs-137 0.97 - 1.72 E5 1.29 E5 1.27 E5 3 Pass Ce-139 0.00 - 0.00 EQ 0.00 EQ 1.84 E3 3 Pass" Ce-141 1.17 - 2.07 E5 1.56 E5 1.60 E5 3 Pass 5/14/2002 Q022GWR Cr-51 6.77- 12.01 E3 9.03 E3 9.07 E3 3 Pass Mn-54 1.38 - 2.45 E3 1.84 E3 2.00 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.43 E3 3 Pass Fe-59 1.75 - 3.10 E3 2.33 E3 2.57 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.44 E3 3 Pass Zn-65 2.66 - 4.71 E3 3.54 E3 3.86 E3 3 Pass Cs-134 1.68 - 2.98 E3 2.24 E3 1.98 E3 3 Pass Cs-137 1.24-2.20 E3 1.65 E3 1.57 E3 3 Pass Ce-141 2.32-4.11 E3 3.09 E3 3.13 E3 3 Pass 8/16/2002 Q023GWS Cr-51 1.58-2.80 E5 2.10 E5 2.11 E5 3 Pass Mn-54 5.73 - 10.16 E4 7.64 E4 8.09 E4 3 Pass Co-58 4.47 - 7.93 E4 5.96 E4 6.17 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.67 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.02 E4 3 Pass Zn-65 7.16- 12.70 E4 9.55 E4 1.01 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.82 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.76 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 E5 1.37 E5 3 Pass Section 5 -Page

Gamma in Water 1.0 liter continued Reference Sample ID. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCi/l pCiA 11/19/2002 Q024GWR Cr-51 2.08 -3.70 E4 2.78 E4 3.15 E4 3 Pass Mn-54 5.96- 10.56 E3 7.94 E3 9.12 E3 3 Pass Co-57 0.00 - 0.00 EO 0.00 EQ 3.87 El 3 Pass"'

Co-58 6.54- 11.60 E3 8.72 E3 9.71 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 6.07 E3 3 Pass Co-60 6.68- 11.85 E3 8.91 E3 1.01 E4 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.22 E4 3 Pass Cs-134 4.04 - 7.16 E3 5.38 E3 5.24 E3 3 Pass Cs-137 0.89- 1.58 E4 1.19 E4 1.29 E4 3 Pass Ce-141 6.32 - 11.21 E3 8.43 E3 9.53 E3 3 Pass Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCiA pCi/I 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 E5 1.27 E5 1.25 E5 3 Pass Mn-54 0.82- 1.45 E5 1.09 E5 1.14 E5 3 Pass Fe-59 4.17-7.40 E4 5.56 E4 5.91 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.65 E4 3 Pass Zn-65 0.80- 1.43 E5 1.07 E5 1.14 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.06 E4 3 Pass Cs-137 0.97- 1.72 E5 1.29 E5 1.23 E5 3 Pass F Ce-139 Ce-141 0.00-0.00 EO 1.17 -2.07 E5 0.00 1.56 EQ E5 1.76 1.54 E3 E5 3 Pass")

3 Pass 5/14/2002 Q022GWR Cr-51 6.77 - 12.01 E3 9.03 E3 9.29 E3 3 Pass Mn-54 1.38 -2.45 E3 1.84 E3 1.96 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.47 E3 3 Pass Fe-59 1.75 -3.10 E3 2.33 E3 2.51 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.40 E3 3 Pass Zn-65 2.66 -4.71 E3 3.54 E3 3.76 E3 3 Pass Cs-134 1.68 -2.98 E3 2.24 E3 2.03 E3 3 Pass Cs-137 1.24-2.20 E3 1.65 E3 1.62 E3 3 Pass Ce-141 2.32-4.11 E3 3.09 E3 3.11 E3 3 Pass 8/16/2002 Q023GWS Cr-51 1.58 -2.80 E5 2.10 E5 2.10 E5 3 Pass Mn-54 5.73 - 10.16 E4 7.64 E4 8.06 E4 3 Pass Co-58 4.47 - 7.93 E4 5.96 E4 6.02 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.77 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.09 E4 3 Pass Zn-65 7.16- 12.70 E4 9.55 E4 1.03 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.48 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.65 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 E5 1.34 E5 3 Pass Section 5 -Page 6

Gamma in Water 0.5 liter continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiAI pCi/ pci/i 11/1912002 Q024GWR Cr-SI 2.08 -3.70 E4 2.78 E4 3.10 E4 3 Pass Mn-54 5.96 - 10.56 E3 7.94 E3 8.98 E3 3 Pass Co-57 0.00 - 0.00 EO 0.00 EO 6.61 El 3 Pass"'

Co-58 6.54 - 11.60 E3 8.72 E3 9.64 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 5.92 E3 3 Pass Co-60 6.68- 11.85 E3 8.91 E3 9.97 E3 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.19 E4 3 Pass Cs-134 4.04 - 7.16 E3 5.38 E3 5.08 E3 3 Pass Cs-137 0.89- 1.58 E4 1.19 E4 1.24 E4 3 Pass Ce-141 6.32- 11.21 E3 8.43 E3 9.15 E3 3 Pass Gamma in Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/total pCiltotal pCi/total 6/13/2002 E3197-37 Cr-51 1.05 -2.42 E2 1.59 E2 1.79 E2 3 Pass Mn-54 4.80-8.51 El 6.40 El 6.72 El 3 Pass Co-58 5.03-8.91 El 6.70 El 6.78 El 3 Pass Fe-59 3.89 -7.51 El 5.40 El 6.46 El 1/3 High 2 Co-60 6.30- 11.17 El 8.40 El 8.70 El 3 Pass Zn-65 0.91 - 1.61 E2 1.21 E2 1.30 E2 3 Pass Cs-134 6.08 - 10.77 El 8.10 El 7.99 El 3 Pass Cs-137 4.58-8.11 El 6.10 El 5.73 El 3 Pass Ce-141 4.58-8.11 El 6.10 El 6.84 El 3 Pass 1215/2002 E3459-37 Cr-51 1.80- 3.28 E2 2.43 E2 2.55 E2 3 Pass Mn-54 0.75 - 1.33 E2 1.00 E2 1.01 E2 3 Pass Co-58 7.35 - 13.03 El 9.80 El 9.61 El 3 Pass Fe-59 3.83 - 6.78 El 5.10 El 5.71 El 3 Pass Co-60 0.87 - 1.54 E2 1.16 E2 1.19 E2 3 Pass Zn-65 0.95 - 1.68 E2 1.26 E2 1.28 E2 3 Pass Cs-134 5.25 -9.31 El 7.00 El 6.50 El 3 Pass Cs-137 1.16-2.06 E2 1.55 E2 1.45 E2 3 Pass Ce-141 5.85 - 10.37 El 7.80 El 8.05 El 3 Pass Iodine in Water Reference Sample ID. Nuclide Acceptance Reference Mean Reported Cross Check Date 5/28/2002 Q022LIW1 I-131 Range pCiAl 1.38 -2.59 EO Value pCiA 1.89 EO Value pCi/l 2.31 EO j Status 3 Pass 5/28/2002 Q022LIW2 I-131 2.03 - 3.60 El 2.71 El 3.87 El 3/3 High' 5/28/2002 Q022LIW3 I-131 3.33 -5.91 E2 4.44 E2 4.72 E2 3 Pass Section 5 - Page 7

Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range. Value Value Status pCiA pCi/l pCi/i 11/5/2002 Q024LIM1 I-131 2.80-4.97 E2 3.73 E2 3.52 E2 3 Pass 11/5/2002 Q024LIM2 I-131 0.00 -0.00 EO 0.00 EO 0.00 EO 3 Pass Iodine Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 3/8/2002 A15502-04 1-131 1.47-2.61 E5 1.96 E5 2.31 E5 3 Pass 6/13/2002 E3198-37 I-131 6.98 - 12.37 El 9.30 El 10.7 E 3 Pass 8/9/2002 A16102-04 I-13 1 1.89 - 3.35 E 2.52 E 2.95 E5 3 Pass 12/5/2002 E3460-37 I-131 7.28 - 12.90 El 9.70 El 1.12 E2 3 Pass Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCiA pCii 6/13/2002 E3199-37 Beta 2.10-3.72 E2 2.80 E2 2.59 E2 3 Pass 6/13/2002 E3258-37 Beta 2.10- 3.72 E2 2.80 E2 2.63 E2 3 Pass Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pci pci pci 2/15/2002 A15504-04 Gross Beta 5.64 - 10.00 E3 7.52 E3 7.97 E3 3 Pass Section 5 -Page 8

Tritium in Water

- Reference Sample ID. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi pCi/I

- 3/15/2002 Q021TWSL1 H-3 0.93 - 1.66 E4 1.25 E4 1.26 E4 3 Pass 3/15/2002 QO21TWSL21 H-3 0.00 - 0.00 EQ 0.00 E0 0.00 EQ 1 3 Pass 5/14/2002 Q022TWRI H-3 4.25 - 8.20 E2 5.90 E2 5.60 E2 3 Pass

- 5/14/2002 Q022TWR2 H-3 0.00 - 0.00 EQ 0.00 EO 0.00 EQ 3 Pass 5/14/2002 Q022TWR3 H-3 2.06 - 3.66 E3 2.75 E3 2.84 E3 3 Pass

- 8/15/2002 Q023TWSLI H-3 0.00 - 0.00 EQ 0.00 EQ 0.00 EO 3 Pass 8/15/2002 lQO23TWSL21 H-3 2.94 - 5.21 E4 3.92 E4 3.37 E4 3 Pass 11/22/2002 Q024TWR1 l H-3 0.00-0.00 EQ 0.00 EQ 0.00 EQ 3 Pass

  1. 11/22/2002 Q024TWR2 H-3 1.65 -2.93 E3 2.20 E3 1.89 E3 3 Pass U

- Section 5 -Page 9

Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q021GWSL, Reference Date 3/15/2002: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, Ce-139 was observed in cross-checks and was attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.

Gamma in Water, Sample ID Q024GWR, Reference Date 11/19/2002: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli Co-57 was observed in cross-checks and was attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.

(2) Gamma in Filter, Sample ID E3197-37, Reference Date 6/13/2002 Three results for Fe-59 [1099.2 keV] were reported, with one being above acceptance limit. Calibration verifications for detector 4 (SN: 35-P31076A) were evaluated and yielded acceptable results. General Office PIP G-02-00278 was written to record investigative actions.

(3) Iodine in Water, Sample ID Q022LIW2, Reference Date 5/28/2002 Three results were reported for this cross-check, all of which were above the cross-check acceptance limit. Investigation yielded the most likely cause for the high results was failure to shake resin dish prior to analysis. General Office PIP G-02-00254 was written to record investigative actions.

Section 5 -Page 10

TABLE 5.0-B 2002 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Teclinology Services 1st Quarter 2002 2nd Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100141 88 88.1 0.11 <+1-15% Pass 100340 99 93.9 -5.15 <+/-15% Pass 100157 88 92.8 5.45 <+/-15% Pass 101179 99 97.5 -1.52 <+/-15% Pass 100215 88 91.1 3.52 <+/-15% Pass 100349 99 96.3 -2.73 <+1-15% Pass 100145 88 91.2 3.64 <+/-15% Pass 100397 99 98.9 -0.10 <+/-15% Pass 100463 88 90.7 3.07 <+/-15% Pass 100022 99 98.5 -0.51 <+/-15% Pass Average Bias (B) 3.16 Average Bias (B) -2.00 Standard Deviation (S) 1.93 Standard Deviation (S) 2.03 Measure Performance IBI+S 5.09 <15% Pass Measure Performance Bl+S 4.03 <15% Pass 3rd Quarter 2002 4th Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100601 66 64.0 -3.03 <+1-15% Pass 101275 70 63.5 -9.29 <+/-15% Pass 100841 66 65.1 -1.36 <+1-15% Pass 100478 70 64.2 -8.29 <+/-15% Pass 100868 66 65.3 -1.06 <+/-15% Pass 100503 70 63.1 -9.86 <+1-15% Pass 100880 66 68.2 3.33 <+/-15% Pass 101011 70 64.6 -7.71 <+1-15% Pass 100989 66 65.4 -0.91 <+1-15% Pass 100538 70 67.0 -4.29 <+/-15% Pass Average Bias (B) -0.61 Average Bias (B) -7.89 Standard Deviation (S) 2.36 Standard Deviation (S) 2.18 Measure Performance IBI+S 2.97 <15% Pass Measure Performance IBI+S 10.06 <15% Pass State of North Carolina, Division of Radiation Protection Spring 2002 Fall 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100008 90 80.8 -10.22 <+1-15% Pass 100777 151.6 127.3 -16.03 <+1-15% Fail 100030 90 83.1 -7.67 <+1-15% Pass 100704 151.6 127.9 -15.63 <+1-15% Fail 100050 90 81.3 -9.67 <+1-15% Pass 100740 151.6 130.9 -13.65 <+/-15% Pass 100064 90 84.6 -6.00 <+1-15% Pass 100680 151.6 132.4 -12.66 <+/-15% Pass 100117 90 82.6 -8.22 <+/-15% Pass 101020 151.6 123.7 -18.40 <+/-15% Fail 100166 90 81.1 -9.89 <+/-15% Pass 100747 151.6 131.3 -13.39 <+/-15% Pass 100208 90 79.9 -11.22 <+/-15% Pass 100759 151.6 130.6 -13.85 <+1-15% Pass 101122 90 82.5 -8.33 <+1-15% Pass 100103 151.6 128.6 -15.17 <+1-15% Fail Average Bias (B) -8.90 Average Bias (B) -14.85 Standard Deviation (S) 1.67 Standard Deviation (S) 1.85 Measure Performance IBI+S 10.57 <15% Pass Measure Performance IBI+S 16.70 <15% Fail ° Section 5 - Page 11

Internal Crosscheck (Duke Power) 1st Quarter 2002 2nd Quarter2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 101102 40 37.0 -7.50 <+1-15% Pass 100103 33 31.5 -4.55 <+1-15% Pass 100109 40 37.1 -7.25 <+1-15% Pass 100740 33 31.6 -4.24 <+1-15% Pass 101122 40 38.4 -4.00 <+1-15% Pass 100747 33 31.9 -3.33 <+/-15% Pass 100268 40 37.1 -7.25 <+1-15% Pass 100770 33 31.3 -5.15 <+1-15% Pass 100807 40 39.8 -0.50 <+/-15% Pass 100772 33 32.4 -1.82 <+1-15% Pass 100810 40 37.7 -5.75 <+/-15% Pass 101017 33 31.7 -3.94 <+/-15% Pass 100169 40 37.3 -6.75 <+/-15% Pass 101020 33 30.8 -6.67 <+1-15% Pass 100366 40 38.1 -4.75 <+/-15% Pass 101025 33 32.3 -2.12 <+1-15% Pass 100815 40 37.2 -7.00 <+/-15% Pass 101035 33 31.3 -5.15 <+1-15% Pass 100823 40 38.8 -3.00 <+/-15% Pass 101036 33 32.3 -2.12 <+/-15% Pass Average Bias (B) -5.38 Average Bias (B) -3.91 Standard Deviation (S) 2.31 Standard Deviation (S) 1.57 Measure Performance BI+S 7.68 <15% Pass Measure Performance IBI+S 5.48 <15% Pass 3rd Quarter 2002 4th Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fai Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100792 106 100.8 -4.91 <+/-15% Pass 100389 66 64.5 -2.27 <+1-15l I Pass 101274 106 100.0 -5.66 <+/-15% Pass 101114 66 62.3 -5.61 <+-159% Pass 100314 106 100.0 -5.66 <+/-15% Pass 100114 66 66.6 0.91 <+1-15 I Pass 100460 106 100.9 -4.81 <+1-15% Pass 100649 66 63.0 -4.55 <+1-159% Pass 100101 106 101.9 -3.87 <+/-15% Pass 100469 66 65.2 -1.21 <+1-159  % Pass 100783 106 101.8 -3.96 <+/-15% Pass 100763 66 62.0 -6.06 <+1-159% Pass 100760 106 100.8 -4.91 <+/-15% Pass 100304 66 62.8 -4.85 <+1-159 I Pass 101349 106 98.1 -7.45 <+/-15% Pass 100068 66 67.2 1.82 <+/-159 % Pass 100794 106 101.1 -4.62 <+/-15% Pass 100203 66 65.0 -1.52 <+1-159  % Pass 100012 106 100.1 -5.57 <+/-15% Pass 100418 66 64.7 -1.97 <+-15c% Pass Average Bias (B) -5.14 Average Bias (B) -2.53 Standard Deviation (S) 1.03 Standard Deviation (S) 2.69 Measure Performance IBI+S 6.17 <15% Pass Measure Performance IBI+S 5.22 <15% 0 Pass Section 5 - Page 12

Table 5.0-B Footnote Explanations (1) State of NC Division of Radiation Protection TLD Cross-Check, Fall 2002 There was an unusual amount of time between anneal, irradiation and readout for the Fall 2002 Environmental Crosscheck with the State of NC Division of Radiation Protection. Normal times between irradiation and readout are typically less than 7 days. In the Fall 2002 crosscheck, due to the ice storm and holiday season, the time between irradiation and readout was 18 days. Fading correction was not applied for the report results; fading correction is typically NOT USED.

When fading correction was applied, the cross-checks were within acceptance criteria. Fading correction will be applied to future cross-checks.

Additional information is documented in PIP G-03-00021.

Section 5 - Page 13

6.0 REFERENCES

6.1 McGuire Selected License Commitments 6.2 McGuire Technical Specifications 6.3 McGuire Updated Final Safety Analysis Report 6.4 Duke Power Company McGuire Offsite Dose Calculation Manual 6.5 McGuire Annual Radiological Environmental Operating Report 1979 - 2001 6.6 McGuire Annual Radioactive Effluent Release Report 2002 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Vertechs Version 3.5.0, Duke Power Revision # 3.0 6.12 NRC Integrated Inspection Report (no audit performed in 2002) 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page I

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A- Page I

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.

Environmental sampling and analyses were performed by EnRad Laboratories, Dosimetry and Records, and Fisheries and Aquatic Ecology.

This appendix describes the environmental sampling frequencies and analysis procedures by media type.

1. CANGE OF SAMPLING PROCEDURES No changes were made to the sampling procedures during 2002.
11. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.

Low-level iodine analyses are performed by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable.

Appendix A -Page 2

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.

Ill. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2002.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE P'ARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge situated behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A weekly gross beta analysis was performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. Filters were segregated by location and a quarterly gamma analysis was performed on the filter composite. The filter and charcoal cartridge were analyzed independently. The continuous composite samples were collected from the locations listed below.

Location 120 = Site Boundary (0.5 mi. NNE)

Location 121 = Site Boundary (0.5 mi. NE)

Location 125 = Site Boundary (0.4 mi. SW)

Location 133 = Cornelius, NC (6.2 mi. NE)

Location 134 = East Lincoln Junior High School (8.8 mi. WNW)

Location 192 = Peninsula development (2.8 mi. NNE)

Location 195 = Fishing Access Road (0.2 mi. N)

A.2 DRINKING WATER Biweekly composite samples were collected. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.

Location 101 - North Mecklenburg Water Supply (3.3 mi E)

Location 119 - Mt. Holly Municipal Water Supply (7.4 mi. SSW)

Location 132 - Charlotte Municipal Water Supply (11.2 mi. SSE)

Location 136 = Mooresville Municipal Water Supply (12.7 mi. NNE)

Location 194 - East Lincoln Water Supply (6.7 mi. NNW)

Appendix A - Page 3

A.3 SURFACE WA'ER Biweekly composite samples were collected. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites sample. The composites were collected biweekly from the locations listed below.

Location 128 = Discharge Canal Bridge (0.4 mi. NE)

Location 131 = Cowans Ford Dam (0.6 mi. WNW)

Location 135 = Plant Marshall Intake Canal (11.9 mi. N)

A.4 MILK Biweekly grab samples were collected at each dairy. A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the locations listed below.

Location 138 = Henry Cook Dairy - COWS (3.1 mi. ESE)

Location 139 = William Cook Dairy - COWS (2.5 mi. E)

Location 141 = Lynch Dairy - COWS (14.8 mi. WNW)

A.5 1BROADLEAF VEGETATION Monthly samples were collected as available and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.

Location 120 = Site Boundary (0.5 mi. NNE)

Location 125 = Site Boundary (0.4 mi. SW)

Location 134 = East Lincoln Junior High School (8.8 mi. WNW)

Location 193 = Site Boundary (0.2 mi. N)

A.6 FOOD PRODUCTS Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the location listed below.

Location 188 = Garden (2.8 mi N)

A.7 FISH Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole Appendix A -Page 4

minus the head and tail portions. The samples were collected from the locations listed below.

Location 129 = Discharge Canal Entrance to Lake Norman (0.5 mi.ENE)

Location 137 = Pinnacle Access Area (12.0 mi. N)

A.8 SHORELINTE SEDIMENT Semiannual samples were collected and a gamma analysis was performed on each following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 129 = Discharge Canal Entrance to Lake Norman (0.5 mi. ENE)

Location 130 = Highway 73 Bridge Downstream (0.5 mi. SW)

Location 137 = Pinnacle Access Area (12.0 mi. N)

A.9 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations. A gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.

  • An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March, 1991.
  • An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.
  • The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and control locations.

TLD locations are listed in Table 2.1-B.

A.10 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

  • The Nearest Residence
  • The Nearest Meat Animal Appendix A - Page 5
  • The Nearest Garden greater than 50 square meters or 500 square feet
  • The Nearest Milk-giving Animal (cow, goat, etc.)

This census was initiated on June 12, 2002 and completed on June 14, 2002.

Results are shown in Table 3.10.

In the environmental program, the air deposition parameters (D/Q) are used to determine air, broadleaf vegetation and milk sampling locations. McGuire's sectors with the three highest values did not change in 2002.

Appendix A - Page 6

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2002 Appendix B - Page I

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 t I Location: Mfecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower All Idt Location with Highest Control R Non-Pathway Number Limit of . Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Air Particulate 134 (pCi/m3) (8.8 mi WNW)

BETA 364 L.OOE-02 1.54E-2 (3121312) 121 1.57E-2 (52/52) 1.72E-2 (52/52) 0 3.68E 2.38E-2 (0.5 mi NE) 4.56E 2.19E-2 7.48E 2.59E-2 CS-134 28 5.00E-02 0.00 (0/24) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 28 6.OOE-02 0.00 (0/24) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 28 7.OOE-02 0.00 (0/24) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 L...~' Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26/2003 1:29 PM Appendix B - Page 2

EnviroDmental Radiological Monitoring Program Summary

"' Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mfecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Lower Location with Highest No. of Non Pathway Total Numb Limit Loweof All Indicator LoncatornnaMa Annual Mean Control Location Routine Report Sampled Number Detection Locations Name, Distance, Direction Reas.

Sampled of Meas.

Unit of Analyses LLD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Air Radioiodine 134 (pCi/m3) (8.8 mi WNW)

CS-134 364 5.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 364 6.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 364 7.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26/2003 1:51 PM Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370

, , Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Locaton with Highest No. of Non-All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LLD) Range Code Range Range Drinking Water 136 (pCi/liter) (12.7 mi NNE)

BALA-140 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 65 4 2.32 (52/52) 194 2.47 (13/13) 2.08 (13/13) 0 1.15 - 3.23 (6.7 mi NNW) 1.92 - 2.91 1.07 - 2.65 CO-58 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 65 18 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0113) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 20 2000 450 (12/16) 101 564 (4/4) 0.00 (0/4) 0 279 - 643 (3.3 mi E) 509 - 643 0.00 - 0.00 1-131 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26/2003 1:51 PM Appendix B - Page 4

Environmental Radiological Monitoring Program Summary

\.-1 Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower All Idt Location with Highest Control No. of Non-Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses LLD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (D) Range Code Range Range Surface Water 135 (pCilliter) (11.9 mi N)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12 2000 492 (8/8) 128 565 (4/4) 0.00 (0/4) 0 408 - 736 (0.4 mi NE) 420 - 736 0.00 - 0.00 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only v-' Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

, Zero range indicates no detectable activity measurements Report Generated @3/26/2003 1:52 PM Appendix B - Page 5

Environmental Radiological Monitoring Program Summary

'- Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 No. of Non-Medium or Type and Total Lower Location with Highest Contro R on Pathway Number Limit of locator Annual Mean Lontion Rot Sampled of Detection Locations Name, Distance, Direction Location RMepaosrt Unit of Analyses LD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Milk 141 (pCiliter) (14.8 mi WNW)

BALA-140 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0126) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 78 18 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 78 15 0.00 (0/52) 0.00 (0126) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 78 1 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26/2003 1:52 PM Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower A Location with Highest No. of Non-Pathway Number Limit of All Indicator Annual Mean Control Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed GAD) Range Code Range Range Broadleaf 134 Vegetation (8.8 mi WNW)

(pCilkg-wet)

CS-134 28 60 0.00 (0/21) 0.00 (017) 0.00 (on) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 28 80 0.00 (0/21) 0.00 (017) 0.00 (017) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 28 60 0.00 (0/21) 0.00 (O7) 0.00 (0/7) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/2612003 1:52 PM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower All Idit Location with Highest Control No. of Non-Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Food Products No Control (pCilkg-wet) Location CS-134 11 60 0.00 (0/11) 0.00 (/11) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 11 80 0.00 (0/11) 0.00 (0/11) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 11 60 0.00 (0/11) 0.00 (0/11) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26/2003 1:52 PM Appendix B -Page 8

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 No. of Non-Medium or Type and Total Lower All Idt Location with Highest Control Routine Pathway Number Limit of locator Annual Mean Lontion Rot Sampled of Detection Locations Name, Distance, Direction Loation RMepaos Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LLD) Range Code Range Range Fish 137 (pCi/kg-wet) (12.0 mi N)

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 23.3 (2/6) 129 23.3 (2/6) 0.00 (0/6) 0 22.2 - 24.4 (0.5 ni ENE) 22.2 - 24.4 0.00 - 0.00 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00

'-' Mean and range based upon detectable measurements only

_, Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/26t2003 1:52 PM Appendix B - Page 9

Environmental Radiological Monitoring Program Summary

~-' Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower A Location with Highest Control No. of Non-Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Shoreline 137 Sediment (12.0 mi N)

(pCi/kg-dry)

MN-54 6 0 22.4 (1/4) 130 22.4 (1/2) 0.00 (0/2) 22.4 - 22.4 (0.5 mi SW) 22.4 - 22.4 0.00 - 0.00 CO-58 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 6 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6 180 90.0 (4/4) 130 159 (212) 112 (1/2) 0 19.8-248 (0.5miSW) 71.5-248 112- 112 Mean and range based upon detectable measurements only i'~' Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 3/26/2003 1:52 PM Appendix B -Page 10

Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Type and Lower Location with Highest No. of Non-Medium or Total Limit of All Indicator Annual Mean Control Routine Pathway Sampled Number Deton Locations N A, an en Location Report of Detection Name, Distance, Directon Meas.

Uni of Measurement Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Unit of Measurement Performed (LLD) Range Code Range Range Direct Radiation 175 TLD (15.5 mi WNW)

(mR/standard quarter) 164 O.OOE+00 16.9 (160/160) 173 24.3 (4/4) 23.7 (4/4) 0 9.80 - 29.5 (8.4 mi NNW) 22.1 - 26.0 22.2 - 24.8 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @3/26/2003 1:52 PM Appendix B -Page II

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page I

APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power outage to sampling equipment 121 6/19 - 6/26/2002 6/19 - 6/26/2002 occurred during the composite period.

Power was cut due to a tree falling on the 195 6/19 - 6/26/2002 6/19 - 6/26/2002 main service line to the McGuire site.

Power was interrupted for approximately 120 6/19 - 6/26/2002 6/19 - 6/26/2002 PO three hours.

Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power outage to sampling equipment occurred during the composite period.

Power was cut due to a tree falling on the main service line to the McGuire site.

Power was interrupted for approximately 128 6/12 - 7/10/2002 6/12 - 7/10/2002 PO three hours.

C.2 UNAVAILABLE ANALYSES There were no unavailable analyses for the 2002 REMP.

Appendix C - Page 2

APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 2002 Radiological Environmental Monitoring Program Appendix D - Page I

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2002. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

Appendix E -Page I

Retrieved from "https://kanterella.com/w/index.php?title=ML031390555&oldid=2692807"