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Annual Radiological Environmental Operating Report 2011 - Chapter 4.0 Through End
	ML12137A011
Person / Time
Site:	Catawba
Issue date:	05/14/2012
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML12137A011 (66)
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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 2011 CNS REMP samples. Only those samples that

were not affected by the Fukushima Daiichi fallout were used to calculate doses. 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 0concentration at the corresponding control location was subtracted. Regulatory Guide 01.109 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.

0Maximum dose estimates (Highest Annual Mean Concentration) based on broadleaf vegetation, 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.

0REMP-based dose estimates are not reported for airborne radioiodine, airborne particulate, milk, or ground water sample types because no radionuclides attributable to CNS operations were detected. Naturally occurring K-40 and Be-7 were detected in some samples but were not included in any REMP-based dose estimates. Dose 0estimates are not reported for surface water because sampled surface water is not considered to be a potable drinking water source although surface water tritium

concentrations are used in calculating doses from fish. Exposure estimates based upon REMP TLD results are discussed in Section 3.10.

0The maximum environmental organ dose estimate for any single sample type (excluding

TLD results) collected during 2011 was 2.23E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.

4.2 ESTIMATED DOSE FROM RELEASES 0

Throughout the year, dose estimates were calculated based on actual 2010 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. These doses are shown in Table 4.1-A along with the 0corresponding REMP-based dose estimates. Summaries of RETDAS dose calculations

are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

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The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. For iodine, particulate, and tritium S 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 0 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.

Additionally, in 2010 Catawba began reporting estimated dose from effluent Carbon 14 (C-14). This change came about with the issuing of Regulatory Guide 1.21, Revision 2, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste. A description of this change is found in the 2010 Annual Radiological Effluent Release Report. C-14 is not measured in the environment and therefore, environmental and effluent doses from C-14 cannot be compared directly.

In calculations based on liquid release pathways, drinking water, fish, and shoreline sediment were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2011 environmental sample results was 9.13E-2 mrem to the child liver. The maximum total organ dose of 1.90E-1 mrem for liquid effluent-based estimates was to the adult GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 4.75E0 mrem to the child bone. Vegetation was the predominant dose pathway for environmental samples. The maximum total organ dose for gaseous environmental estimates was 2.23E-1 mrem to the child bone.

0 The doses calculated do not exceed 40CFR190 or 10CFR50 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of CNS are being maintained well within regulatory limits.

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Section 4 - Page 2 0 0

TABLE 4.1-A Page 1 of 2 CATAWBA NUCLEAR STATION 2011 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

0 LIOUID RELEASE PATHWAY 0

Environmental or Critical Critical Maximum Dose (3)

Organ Effluent Data Age (1) Pathway (2) Location (mrem)

Skin Environmental Teen Shoreline Sediment 208 (0.45 mi S) 6.87E-04 Skin Effluent Teen Shoreline Sediment Discharge Pt. 1.64E-02 Bone Environmental Child Fish 208 (0.45 mi S) 4.87E-02 Bone Effluent Teen Shoreline Sediment Discharge Pt. 1.78E-02 Liver Environmental Child Fish 208 (0.45 mi S) 9.13E-02 Liver Effluent Child Drinking Water 7.30 mi SSE 1.45E-01 T. Body Environmental Adult Fish 208 (0.45 mi S) 7.41E-02 T. Body Effluent Child Drinking Water 7.30 mi SSE 1.42E-01 0

Thyroid Environmental Child Drinking Water 214 (7.30 mi SSE) 4.47E-02 Thyroid Effluent Child Drinking Water 7.30 mi SSE 1.39E-01 0

Kidney Environmental Child Drinking Water 214 (7.30 mi SSE) 5.99E-02 S Kidney Effluent Child Drinking Water 7.30 mi SSE 1.41E-01 S

0 Lung Environmental Child Drinking Water 214 (7.30 mi SSE) 5.01E-02 0 Lung Effluent Child Drinking Water 7.30 mi SSE 1.40E-01 0

GI-LLI Environmental Child Drinking Water 214 (7.30 mi SSE) 4.50E-02 0 GI-LLI Effluent Adult Fish 7.30 mi SSE 1.90E-01 0

(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

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Page 2 of 2 GASEOUS RELEASE PATHWAY 0 0

IODINE, PARTICULATE, and TRITIUM 0

S Environmental or Critical Critical Maximum Dose ()

Organ Effluent Data Age (1) Pathway (2) Location (mrem) 0 Skin Environmental 0.00E+00 0

Skin Effluent - 0.OOE+00 Bone Environmental Child Vegetation 201 (0.53 mi NE) 2.23E-01 Bone Effluent Child Vegetation 0.5 mi NE 4.75E+00 Liver Environmental Child Vegetation 201 (0.53 mi NE) 2.13E-01 Liver Effluent Child Vegetation 0.5 mi NE 2.01E+00 T. Body Environmental Adult Vegetation 201 (0.53 mi NE) 1.20E-01 T. Body Effluent Child Vegetation 0.5 mi NE 2.01E+00 Thyroid Environmental 0.00E+00 Thyroid Effluent Child Vegetation 0.5 mi NE 2.01E+00 Kidney Environmental Child Vegetation 201 (0.53 mi NE) 6.95E-02 Kidney Effluent Child Vegetation 0.5 mi NE 2.01E+00 0

Lung Environmental Child Vegetation 201 (0.53 mi NE) 2.50E-02 0 Lung Effluent Child Vegetation 0.5 mi NE 2.01E+00 0

GI-LLI Environmental Adult Vegetation 201 (0.53 mi NE) 3.54E-03 GI-LLI Effluent Child Vegetation 0.5 mi NE 2.01E+00 S

(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.

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Section 4 - Page 4 0

TABLE 4.1-B Maximum IndividualDose for 2011 based on EnvironmentalMeasurements (torer) for CatawbaNuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Drinking Water 0.00E+00 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 O.OOE+00 Milk O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL 0.00E+00 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 O.OOE+00 Child 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 O.OOE+00 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3.49E O.OOE+00 Milk 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Broadleaf Vegetation 2.23E-01 2.13E-01 3.15E-02 O.OOE+00 6.95E-02 2.50E-02 1.34E-03 O.OOE+00 Fish 4.87E-02 5.64E-02 1.66E-02 9.76E-03 2.50E-02, 1.52E-02 1.01E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 5.85E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.87E-04 TOTAL 2.72E-01 3.04E-01 8.36E-02 4.47E-02 1.29E-01 7.51E-02 4.63E-02 6.87E-04 Teen Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.23E-01 1.64E-01 5.71 E-02 O.OOE+00 5.58E-02 2.17E-02 2.33E-03 O.OOE+00 Fish 3.87E-02 6.33E-02 2.98E-02 1.18E-02 2.93E-02 1.86E-02 1.26E-02 0.00E+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.80E-03 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 3.29E-03 TOTAL 1.62E-01 2.46E-01 1.08E-01 3.OOE-02 1.03E-01 5.85E-02 3.31E-02 3.29E-03 Adult Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-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 1.34E-01 1.83E-01 1.20E-01 O.OOE+00 6.20E-02 2.06E-02 3.54E-03 O.OOE+00 Fish 3.62E-02 6.48E-02 4.78E-02 1.54E-02 3.22E-02 2.09E-02 1.63E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 5.01E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.89E-04 TOTAL 1.70E-01 2.74E-01 1.94E-01 4.12E-02 1.20E-01 6.73E-02 4.56E-02 5.89E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 5

CatawbaNuclear Station Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4ALE-06 NO DATA 7.311-06 ALL 0.00 0.OOE+00 0.00K-+00 0.00E+00 0.00OE+00 0.OE00EiC 0.0013O00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.OOE+00 0.0013+400 0.00E+00C 0.OOE+00 0.00E+00C 0.COE--00 O.00E00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.00E+00 0.00K400 0.00E+00 0.OOE+00 0.OE00KiC0.OE00KiC0.00E+00 CO-60 NO DATA 1.08E-05 2.55F,05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00OE+00 0.OOE+00 0.00E+00C 0.00OE+00 0.OE00KiC0.COE-i00 0.00E+00 Zn-65 1.84E-05 6.31E-05 2.9E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE-i0O 0.00K-i00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00K-O8 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 O.00Ei40 0.00E+00 0.00E+00 0.OOE-i00 0.OE00EiO0.00E,i00 Zr-9S 2.06E-07 5.021-08 356K-OS NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.OOE+O0 0.00E+00 0.00E+00 0.00E-i00 0.00K13-0O 0.OOE+00 1-131 3.59E-05 4.23E-05 86KE-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.00E+O 0.00+O0 0.00.OE+00 0.00E+00 0.OE00KiO0.OOE-a00 0.00K-iC00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.OE00KiC0.OOE--00 0.00OE+00 0.0013+O00.OOE-i0O 0.OOE+00 0.00OE+00 Cs-137 5.22E-04 6.1113-04 4.33E-05 NO DATA 1.64E-04 6.64F-05 1.91E-06 ALL 0.00 0.OOE--00 0.00E+00 0.00E+00 O.OOE+00 0.OE00KiO0.OE+00C 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.OOE-s00 0.00E-i00 0.00OE+00 0.00OE+00 0.00+O00 0.00K-i-0 0.00E_+O0 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 214 337 0.OE00-iC 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 3.43E-02 Dose Commitment (mrem]I = 0.00K-s00 3.43E-02 3.43E-02 3.4313-02 3.43E-02 3.43E-02 3.43E-02 Section 4 - Page 6

CatawbaNuclear Station Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (torem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCiJi) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mni-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E,+00 0.OOE+00 0.OOE+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.OOE+00 0-00E+00 000OE+00 0.00E+00O0.00K+00 0.00E+00 Fe-59 1.65E-05 2,6'7E-05 1-33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.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 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6AIE-06 ALL 0.00 0.OOE+00 0.00E+00 0.00K+00 0.00K+00 0.O0E+00 0.OOE+00 0.O0E+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.OOE+00 0.00E+00 000OE+00 0.00E+00 0.00E+00 O.OOE+00 Zr-95 1.16E-07 2.5SE-OS 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.00E+00 0.OOE+00 0-00E+00 0.OOE+00 0.00E+00 000KE+00 0.00E+00 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.OOE+00 000OE+00 0.00E+00 0.O0E+00 O.OOE+00 0.00E+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 0.00E+00 0.00E+00 0.00K+00 0.00E+00 0.00E+00 0.OOE+00 0.00K+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-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 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.00E+00 0.OOE+00 000KOOE00.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 H1-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 214 337 0.00E+00 3.49E-02 3.49E-02 3.49E-02 3.49E-02 3A9E.02 3.49E-02 Dose Commitment (mrem) = O.OOE+00 3.49E-02 3.49E-02 3.49E-02 3.49E-O2 3.49E-02 3.49E-02 Section 4 -Page 7

CatawbaNuclear Station Dose from Broadleaf Vegetation Pathwayfor 2011 Data Maximum Exposed Child Child Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) = 26 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+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.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+-0 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 201 26.2 2.23E-01 2.13E-01 3.15E-02 0.OOE+00 6.95E-02 2.50E-02 1.34E-03 Dose Commitment (mrem) = 2.23E-01 2.13E-01 3.15E-02 O.00E+00 6.95E-02 2.50E-02 1.34E-03 Section 4 - Page 8

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CatawbaNuclear Station Dosefrom Fish Pathwayfor 2011 Data Maximum Exposed Child Child 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 7744 pCi/A x 0.9 = 6970 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion 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 GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00OE+ 0.00OOE+000.00E+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 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00OOE+000.00E+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 0.00OOE+000.OOE+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00OOE+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.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 0.00E+00 0.00E+00 0.00E+00 0.00OOE+000.0013+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 208 21.6 4.87E-02 4.66E-02 6.89E-03 0.00E+00 1.52E-02 5.47E-03 2.92E-04 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 208 6970 0.OOE+00 9.76E-03 9.76E-03 9.76E-03 9.76E-03 9.76E-03 9.7613-03 Dose Commitment (mrem) = 4.87E-02 5.64E-02 1.66E-02 9.76E-03 2.50E-02 1.52E-02 1.01E-02 Section 4 - Page 9

Catawba NuclearStation Dosefrom Shoreline Sediment Pathwayfor 2011 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.2 2

Sediment Surface Mass = 40 kg/r Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mr) x Shore Width Factor x Sediment Surface Mass (kg/rn) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2 ) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.OOE+00

Co-57 9.10E-10 1.OOE-09 208 10.5 1.07E-06 1.18E-06 Co-58 7.OOE-09 8.20E-09 208 83.6 6.55E-05 7.68E-05 Co-60 1.70E-08 2.OOE-08 208 236 4.49E-04 5.29E-04 Cs-134 1.20E-08 1.40E-08 208 36.2 4.87E-05 5.68E-05 Cs-137 4.20E-09 4.90E-09 208 43.3 2.04E-05 2.38E-05 Dose Commitment (in rem) = 5.85E-04 6.87E-04

Dose Factor from Reference 6.17 Section 4 - Page 10 OOOOOOO0OOOO0OOOOOO0OOOO 0OOOOOOOO OOO 0

CatawbaNuclearStation Dosefrom Drinking Water Pathwayfor 2011 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mremrpCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E.06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.00E+00 0.00k+00 0.00k+00 0.OOE+00 0.00k+00 0.0013+00 0.00k+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 0.00k+00 0.OOE+00 0.OOk+00 0.00E+00 0.OOE+00 0.00k+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.00E+00 0.00E+O0 0.00k+00 0.00k+00 0.0011+00 0.00E+00 0.00k+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 0.0011+00 0.00k+00 0.OOE+00 0.00R+00O0.OOk+00 0.00ki-00 Zn-65 5.76E-06 2.00k-O5 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 O.00E+00 0.00E+00 0.0013+00 0.OOE+00 0.00E+OO 0.0011+00 0.00ki-00 Nb-95 8.22E-09 4.56E-09 2.5113-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.00E+00 0.00k+00 0.0013+00 0.OOE+00 0.00E+00 0.0011+00 0.00k+00 Zr-95 4.12E-08 1.3011-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ALL 0.00 O.00E+00 0.00k+00 0.0013+00 0.OOE+00 0.00E+00 0.0013+00 0.00k+00 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 IA1.-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.0011+00 0.00k+00 0.OOE+00 0.OOE+00 0.0011+00 0.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 0.00E+00 0.00E+00 0.00k+00 0.OOE+00 0.00E+00 0.00k+00 0.00k+00 Cs-137 1.12E-04 1.49E-04 5.1913-05 NO DATA 5.07E-05 1.97k-05 2.12E-06 ALL 0.00 0.00E+00 0.00k+00 0.OO13+00 0.00E+00 0.00E+OO O.00k+00 0.OOE+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 0.00E+00 0.00k+00 0.00k+00 0.OOE+00 0.00R+00 0.00k+00 0.00k+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 214 337 0.00E+00 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.8213-02 1.82F-02 Dose Commitment (mrem)= O.00k+00 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 1.82E-02 Section 4 - Page II

Catawba Nuclear Station Dosefrom Broadleaf Vegetation Pathwayfor 2011 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) = 42 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 5.85E-06 8.19E-06 4AOE-06 2.39E-03 1AIE-05 NO DATA 1.62E-06 ALL 0.00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.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 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 201 26.2 1.23E-01 1.64E-01 5.71E-02 0.00E+00 5.58E-02 2.17E-02 2.33E-03 Dose Commitment (mrem) = 1.23E-01 1.64E-01 5.71E-02 0.00E+00 5.58E-02 2.17E-02 2.33E-03 Section 4 -Page 12

O@OeOO@@@@@@@O@@ 0 0 0* 0 0 0 0 0 0 0 00 9 00 0

Catawba NuclearStation Dosefrom Fish Pathwayfor 2011 Data Maximum Exposed Teen Teen 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 7744 pCi/I x 0.9 = 6970 pCi/kg Usage (intake in one year) = 16 kg Highest Annual Ingestion 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 GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21lE-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+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 0.00E+00 0.OOE+00 0.00E+400 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 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE-*00 0.00E+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 0.00E+00 0.00E+60 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E05 2.12E-06 208 21.6 3.87E-02 5.15E-02 1.79E-02 0.00E+00 1.75E-02 6.81E-03 7.33E-04 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 208 6970 0.OOE+00 1.18E-02 1.18E-02 1.18E-02 1.1SE-02 1.18E-02 1.18E-02 Dose Commitment (mrem) = 3.87E-02 6.33E-02 2.98E-02 1.18E-02 2.93E-02 1.86E-02 1.26E-02 Section 4 - Page 13

Catawba Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2011 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/r 2 ) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2) Indicator Sediment (mrern)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.OOE+00 0.OOE+00

Co-57 9.10E-10 1.OOE-09 208 10:5 5.12E-06 5.63E-06 Co-58 7.00E-09 8.20E-09 208 83.6 3.14E-04 3.67E-04 Co-60 1.70E-08 2.OOE-08 208 236 2.15E-03 2.53E-03 Cs-134 1.20E-08 1.40E-08 208 36.2 2.33E-04 2.72E-04 Cs-137 4.20E-09 4.90E-09 208 43.3 9.75E-05 1.14E-04 Dose Commitment (mrem) = 2.80E-03 3.29E-03

Dose Factor from Reference 6.17 Section 4 - Page 14 0 Is 0 4 0 00 0 0 040 00 0 40 00 0 0 00 0 0 00 0 40

O@*@@@eO@O@Oee@@@O@@@O@Oe@S@@e@@@S@@Oo@@@O@

CatawbaNuclear Station Dose from Drinking Water Pathwayfor 2011 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-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.OOE+00 0.OOE+00 0.00E+00 0.00K+00 0.00E+00 0.0011+00 0.00E+00 Co-58 NO DATA 7A45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.0011+00 0.00Ki-00 0.00E+00 0.00K+00 0.O0E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+OO 0.00E-t00 0.00K+00 0.OOE+00 0.00E+OO 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.OOE+00 0.00K+00 0.00E+00 0.00E+00 0.00E+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.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00K+00 0.00E+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.OOE+00 0.OOE+00 0.00E+00 0.0013+00 0.00E+00 0.OOK-fOO 0.0011+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.O0E+O0 000OE+00 0.OOE+00 0.00E+00 0.OOE+O0 0.00E+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.00E+00 0.00E+OO 0.00K+00 0.00E+00 0.OOE+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.791-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.00K+00 0.0013+00 0.00E+00 0.00E+00 0.00K+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00K+00 0.00K+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18F,05 ALL 0.00 0.00E+00 0.OOE+00 0.00K+00 0.00E+00 0.00E+00 0.O0E+00 0.00E+00 H-3 NO DATA 1.0513-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 214 337 0.00E+00 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 Dose Commitment (mrem) = 0.00K+00 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.5811-02 2.58E-02 Section 4 -Page 15

CatawbaNuclear Station Dose from BroadleafVegetation Pathwayfor 2011 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mremlpCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) = 64 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+0O 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.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.OOE+00 0.OOE+00 0.00E+0O 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 201 26.2 1.34E-01 1.83E-01 1.20E-01 0.OOE+00 6.20E-02 2.06E-02 3.54E-03 Dose Commitment (mrem) = 1.34E-01 1.83E-01 1.20E-01 0.OOE+00 6.20E-02 2.06E-02 3.54E-03 Section 4 - Page 16

CatawbaNuclear Station Dose from Fish Pathwayfor 2011 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/l = 7744 pCi/! x 0.9 = 6970 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion 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 GI-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.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+0O Co-58 NO DATA 7A5E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+0O 0.OOE+0O 0.OOE+00 0.OOE+O0 0.OOE+O0 0.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.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+0O 0.OOE+O0 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.OOE+00 0.OOE+00 0.OOE+0O 0.00E+0O 0.OOE+00 0.OOE+00 0.OOE+0O 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.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 CS-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 208 21.6 3.62E-02 4.94E-02 3.24E-02 0.OOE+00 1.68E-02 5.58E-03 9.57E-04 H-3 NO DATA 1.05E-07 1.OSE-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 208 6970 0.OOE+00 1.54E-02 1.54E-02 1.54E-02 1.54E-02 1.54E-02 1.54E-02 Dose Commitment (mrem) = 3.62E-02 6.48E-02 4.78E-02 1.54E-02 3.22E-02 2.09E-02 1.63E-02 Section 4 - Page 17

CatawbaNuclear Station Dosefrom Shoreline Sediment Pathwayfor 2011 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 2 Sediment Surface Mass = 40 kglm Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2 ) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)

(mrem/hr per pCi/mz) Indicator Sediment Radionudide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.OOE+00 0.00E+00

Co-57 9.10E-10 1.00E-09 208 10.5 9.17E-07 1.01E-06 Co-58 7.OOE-09 8.20E-09 208 83.6 5.62E-05 6.58E-05 Co-60 1.70E-08 2.00E-08 208 236 3.85E-04 4.53E-04 Cs-134 1.20E-08 1.40E-08 208 36.2 4.17E-05 4.87E-05 Cs-137 4.20E-09 4.90E-09 208 43.3 1.75E-05 2.04E-05 Dose Commitment (mrem) = 5.01E-04 5.89E-04

Dose Factor from Reference 6.17 Section 4 - Page 18

0 0

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.

0 S5.2 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 Energy Corporation's Environmental

Center.

0Duke Energy Corporation's

5.3 DOSIMETRY ANALYSIS Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry 0measurements as specified by approved dosimetry analysis procedures.

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0

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 0 are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION 0

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.

0 0

0

Section 5 -Pagel1 0

0

0 0

0 5.4.3 BATCH PROCESSING 0 0

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

0 5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2011. Interlaboratory cross-check standards, including Marinelli beakers, air filters, air cartridges, gross beta in water, and tritium in water samples were analyzed at various times of the year. A summary of the EnRad Laboratory program results for 2011 is documented in Table 5.0-A.

5.6 ECKERT & ZIEGLER ANALYTICS CROSS CHECK PROGRAM 0 0

EnRad Laboratories participated in the Eckert & Ziegler Analytics Cross Check Program during 2011. Cross-check standards including, Marinelli beakers, air filters, tritium in water, and Iodine in milk samples were analyzed at various times of the year. A summary of the EnRad Laboratory program results for 2011 is documented in Table 5.0-B.

5.7 ERA PROFICIENCY TESTING 0 0

EnRad Laboratories performed method proficiency testing through a program administered by Environmental Resource Associates (ERA) of Arvada, CO. ERA supplied requested method proficiency samples for analysis and nuclide concentration determination. ERA reported proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Health Drinking Water Laboratory Certification Program. A summary of these proficiency test data for 2011 is documented in Table 5.0-C.

5.8 DUKE ENERGY AUDITS 0 0

The Catawba Radiation Protection Section was not audited by the Quality Assurance Group in 2011, but was audited in 2010. Procedure and sampling equipment enhancements were identified as part of this audit (reference 6.14).

5.9 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 0 0

The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2011 (reference 6.12). No findings were noted in the report.

S 0

0 Section 5 -Page 2 0 0

0

5.10 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM S

Catawba Nuclear Station routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an Sintercomparison program. The Memorandum of Agreement (MOA) between SC

DHEC and Duke Energy describes the sampling frequency and analysis parameters for drinking water, surface water, milk, fish, vegetation, and shoreline sediment samples collected by EnRad Laboratories. Samples are routinely split with DHEC for Sintercomparison analysis. DHEC collects air samples near two of the locations

sampled for air by CNS. Results of the analyses performed on split and duplicate

samples are sent to DHEC.

0 5.11 TLD INTERCOMPARISON PROGRAM 0*5.11.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM

Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

of Roswell, GA. Nuclear Technology Services irradiates environmental

dosimeters quarterly and sends them to the Radiation Dosimetry and Records 5group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-D.

5.11.2 INTERNAL CROSSCHECK (DUKE ENERGY)

S

Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The SDosimetry Lab Staff irradiates environmental dosimeters quarterly and submits 0them for analysis of the unknown estimated delivered exposure. A summary of

the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-D.

S 0

S S

0 S

S 0

Section 5 -Page 3 S

S

0 0

S S

TABLE 5.0-A 0 DUKE ENERGY S INTERLABORATORY COMPARISON PROGRAM S 2011 CROSS-CHECK RESULTS FOR S

ENRAD LABORATORIES S Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all S

three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one S analysis of the cross check was performed S

If applicable, footnote explanations are included following this table. S S

Gamma in Water 3.5 liters S

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range pCi/I Value pCi/l Value pCi/I Status S

8/17/2011 Q113GWSL Cr-51 1.85-3.28 E5 2.47 E5 2.47 E5 3 Pass S Mn-54 Co-58 6.36- 11.28 E4 5.13-9.10 E4 8.48 E4 6.84 E4 8.62 E4 6.79 E4 3

3 Pass Pass S

Fe-59 3.42- 6.07 E4 4.56 E4 4.76 E4 3 Pass S Co-60 Zn-65 6.28- 11.13 E4 0.78- 1.38 E5 8.37 E4 1.04 E5 8.26 E4 1.06 E5 3

3 Pass Pass S

Cs-134 5.22- 9.25 E4 6.96 E4 6.30 E4 3 Pass S Cs-137 Ce-141 4.51- 8.00 E4 4.89-8.68 E4 6.02 E4 6.52 E4 5.59 E4 6.51 E4 3

3 Pass Pass S

S 12/12/2011 Q114GWR Mn-54 Co-57 2.31-4.09 3.05- 5.40 E4 E4 3.08 4.06 E4 E4 3.25 4.34 E4 E4 1 Pass 1 Pass S

Co-60 2.76- 4.89 E4 3.67 E4 3.65 E4 1 Pass S Y-88 Cd-109 1.49-2.65 0.00 - 0.00 E4 E3 1.99 E4 0.OOE+00 2.03 6.46 E4 E3 1 Pass 1/1 High '"

S Sn-113 1.60-2.84 E4 2.14 E4 2.12 E4 1 Pass S Cs-137 2.39-4.23 E4 3.18 E4 3.01 E4 1 Pass S S

Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S

Date Range Value Value Status S pCi/1 8/17/2011 Q113GWSL Cr-51 1.85-3.28 E5 pCi/l 2.47 E5 pCi/l 2.47 E5 3 Pass S

Mn-54 6.36-11.28 E4 8.48 E4 8.79 E4 3 Pass S Co-58 Fe-59 5.13-9.10 3.42- 6.07 E4 E4 6.84 4.56 E4 E4 6.87 E4 4.90 E4 3

3 Pass Pass S

Co-60 6.28 - 11.13 E4 8.37 E4 8.35 E4 3 Pass S Zn-65 0.78- 1.38 E5 1.04 E5 1.09 E5 3 Pass S Cs-134 5.22-9.25 E4 6.96 E4 6.12 E4 3 Pass Cs-137 4.51- 8.00 E4 6.02 E4 5.65 E4 3 Pass S Ce-141 4.89- 8.68 E4 6.52 E4 6.40 E4 3 Pass S I I S S

S Section 5 - Page 4 S

S

0 0

Gamma in Water 1.0 liter, continued 0

12/12/2011 Q114GWR Mn-54 2.31-4.09 E4 3.08 E4 3.18 E4 1 Pass 0 Co-57 Co-60 3.05- 5.40 2.76- 4.89 E4 E4 4.06 E4 3.67 E4 4.22 3.63 E4 E4 I Pass 1 Pass 0 Y-88 1.49-2.65 E4 1.99 E4 1.97 E4 1 Pass Cd-109 0.00- 0.00 E3 0.00E+00 7.68 E3 1/1 High"'

0 Sn-113 1.60-2.84 E4 2.14 E4 2.09 E4 1 Pass Cs-137 2.39-4.23 E4 3.18 E4 2.94 E4 1 Pass 0

0 Gamma in Water 0.5 liter 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0 pCi/l pCi/1 pCi/1 8/17/2011 QI13GWSL Cr-51 1.85-3.28 E5 2.47 E5 2.46 E5 3 Pass Mn-54 6.36 - 11.28 E4 8.48 E4 8.60 E4 3 Pass 0 Co-58 5.13-9.10 E4 6.84 E4 6.69 E4 3 Pass Fe-59 3.42- 6.07 E4 4.56 E4 4.82 E4 3 Pass Co-60 6.28- 11.13 E4 8.37 E4 8.17 E4 3 Pass Zn-65 0.78- 1.38 E5 1.04 E5 1.08 E5 3 Pass 0 Cs-134 5.22- 9.25 E4 6.96 E4 5.90 E4 3 Pass Cs-137 4.51- 8.00 E4 6.02 E4 5.56 E4 3 Pass 0 Ce-141 4.89-8.68 E4 6.52 E4 6.34 E4 3 Pass 0 Gamma in Water 0.25 liter 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status pCi/i pCi/I pCi/1 8/17/2011 Q113GWSL Cr-51 1.85-3.28 E5 2.47 E5 2.51 E5 3 Pass Mn-54 6.36-11.28 E4 8.48 E4 8.76 E4 3 Pass 0 Co-58 5.13- 9.10 E4 6.84 E4 6.85 E4 3 Pass Fe-59 3.42- 6.07 E4 4.56 E4 4.93 E4 3 Pass 0 Co-60 6.28- 11.13 E4 8.37 E4 8.25 E4 3 Pass Zn-65 0.78- 1.38 E5 1.04 E5 1.09 E5 3 Pass 0 Cs-134 5.22-9.25 E4 6.96 E4 6.11 E4 3 Pass 0 Cs-137 4.51- 8.00 E4 6.02 E4 5.65 E4 3 Pass Ce-141 4.89-8.68 E4 6.52 E4 6.38 E4 3 Pass 0

0 Gamma in Filter 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi Value pCi Value pCi Status 6/16/2011 E7882-37 Cr-51 0.96-2.59 E2 1.58 E2 1.39 E2 2 Pass Mn-54 0.80-1.41 E2 1.06 E2 0.93 E2 2 Pass Co-58 0.88 - 1.56 E2 1.17 E2 0.96 E2 2 Pass Fe-59 7.10 - 12.60 E1 9.47 El 8.62 El 2 Pass Co-60 1.12-1.98 E2 1.49 E2 1.32 E2 2 Pass Zn-65 1.50-2.66 E2 2.00 E2 1.73 E2 2 Pass Cs-134 1.10-1.94 E2 1.46 E2 1.21 E2 2 Pass Cs-137 0.80-1.41 E2 1.06 E2 0.92 E2 2 Pass Ce-141 4.61- 8.17 E1 6.14 E1 4.90 E1 2 Pass Section 5 - Page 5

0 0

Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 3/23/2011 Q1l1LIWI 1-131 pCi/i 2.63-4.66 E3 pCi/I 3.51 E3 pCi/l 3.62 E3 3 Pass S

3/23/2011 Q111LIW2 1-131 5.26-9.33 E2 7.01 E2 7.04 E2 3 Pass S 3/23/2011 Q1l1LIW3 1-131 1.15-2.03 E2 1.53 E2 1.54 E2 3 Pass 0

0 Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range pCi/I Value pCi/i Value pCi/i Status S 8/2/2011 Q113LIM1 1-131 1.84-3.26 E3 2.45 E3 2.60 E3 4 Pass 0 8/2/2011 Qll3LIM2 1-131 1.58-2.80 E2 2.1 2 2.19 E2 4 Pass 0

S 8/2/2011 Q113LIM3 1-131 2.63-4.66 El 3.50 El 3.67 El 4 Pass Iodine on Cartridge 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status pCi pCi pCi 0 6/16/2011 E7883-37 1-131 6.50-11.52 El 8.66 El 8.12 El 2 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/l pCi/il pCi/I 0 6/22/2011 Q112TWR1 H-3 2.82-5.00 E6 3.76 E6 3.57 E6 3 Pass 0 6/22/2011 Q112TWR2 H-3 4.57-8.11 E5 6.10 E5 5.77 E5 3 Pass 6/22/2011 Q112TWR3 H-3 3.73-7.63 E2 5.33 E2 5.10 E2 3 Pass 0

S 12/12/2011 Qll4TWR3 H-3 6.11- 10.84 E3 8.15 E3 7.65 E3 3 Pass 0 12/14/2011 Q114TWRI H-3 0.93-1.66 E3 1.24 E3 1.23 E3 3 Pass 0 12/14/2011 Q1l4TWR2 H-3 3.18-5.64 E5 4.24 E5 4.03 E5 3 Pass 0

0 0

Section 5 - Page 6

0 0

0 Gross Beta in Water

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/1 pCi/l pCi/1

5/23/2011 Qll2ABW1 Cs-137 5.05- 8.95 El 6.73 El 6.84 El 3 Pass 05/23/2011 Qll2ABW2 Cs-137 6.60-11.71 El 8.8 El 8.47 El Pass

5/23/2011 Qll2ABW3 Cs-137 4.96- 8.79 E2 6.61 E2 6.41 E2 3 Pass 0

0 0

0 Section 5-Page 7

0 0

Table 5.0-A Footnote Explanations 0 0

(1) Gamma in Water, Sample ID Q1 14GWR, Reference Date 12/12/2011 0

0 Cd-109 was identified in the cross-check sample and reported. The cross check 0 supplier does not include this radionuclide on the certificate of analysis for this 0 cross-check sample. The radionuclide Cd-109 was determined to be a misidentification by the software and was determined not to be present in the 0 cross-check sample (reference 6.18).

0 0

Section 5 - Page 8 0

0

0 TABLE 5.0-B 0 ECKERT & ZIEGLER ANALYTICS 0 CROSS CHECK PROGRAM 2011 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are received, prepared, and analyzed. Results are report directly to Eckert & Ziegler Analytics.

0 0 If applicable, footnote explanations are included following this table.

0 0

Gamma in Water 3.5 liters 0 Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/I pCil1 Ratio Staus 0 9/15/2011 E8068-37 1-131 Ce-141 0.80 - 1.20 0.80- 1.20 8.01 E+01 9.15E+01 7.96E+01 8.80E+01 0.99 0.96 Pass Pass Cr-51 0.80- 1.20 3.10E+02 3.18E+02 1.02 Pass 0 Cs-134 0.80- 1.20 1.76E+02 1.70E+02 0.97 Pass Cs-137 0.80- 1.20 1.56E+02 1.57E+02 1.01 Pass 0 Co-58 0.80- 1.20 1.34E+02 1.37E+02 1.02 Pass Mn-54 0.80- 1.20 2.07E+02 2.17E+02 1.05 Pass 0 Fe-59 0.80- 1.20 7.52E+01 8.34E+01 1.11 Pass Zn-65 0.80- 1.20 2.47E+02 Not Reported Not Reported Failed (1) 0 Co-60 0.80- 1.20 2.15E+02 2.02E+02 0.94 Pass S 12/8/2011 E8184-37 1-131 0.80- 1.20 8.87E+01 9.46E+01 1.07 Pass 0 Cr-51 0.80- 1.20 5.66E+02 5.57E+02 0.98 Pass 0 Cs-134 0.80- 1.20 1.71E+02 1.76E+02 1.03 Pass Cs-137 0.80- 1.20 2.10E+02 2.03E+02 0.97 Pass Co-58 0.80- 1.20 2.21E+02 2.15E+02 0.97 Pass Mn-54 0.80- 1.20 2.41E+02 2.52E+02 1.05 Pass Fe-59 0.80- 1.20 1.83E+02 1.88E+02 1.03 Pass Zn-65 0.80- 1.20 2.91E+02 2.97E+02 1.02 Pass Co-60 0.80- 1.20 2.70E+02 2.87E+02 1.06 Pass Section 5 - Page 9

S S

S Gamma in Milk S

Acceptance Reference Reported 0 Reference Date Sample I.D. Nuclide Range Ratio Value pCi/l Value pCi/1 Ratio Cross Check Staus S

12/8/2011 E8186-37 1-131 0.80- 1.20 9.02E+01 9.84E+01 1.09 Pass S Cr-51 0.80- 1.20 5.66E+02 5.36E+02 0.95 Pass S Cs-134 0.80 - 1.20 1.71E+02 1.59E+02 0.93 Pass S Cs-137 0.80- 1.20 2.10E+02 2.01E+02 0.96 Pass Co-58 0.80- 1.20 2.21E+02 2.13E+02 0.96 Pass S

Mn-54 0.80- 1.20 2.41E+02 2.45E+02 1.02 Pass S Fe-59 0.80- 1.20 1.83E+02 1.89E+02 1.03 Pass Zn-65 0.80- 1.20 2.91E+02 2.95E+02 1.01 Pass S Co-60 0.80- 1.20 2.70E+02 2.74E+02 1.02 Pass S

S Iodine in Milk S

S S

S Tritium in Water S Acceptance Reference Reported S Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/1 pCi/l Ratio Staus S 9/15/2011 E8069-37 H-3 0.80- 1.20 9.01E+03 9.16E+03 1.02 Pass S 12/8/2011 E8185-37 H-3 0.80- 1.20 1.09E+04 1.04E+04 0.95 Pass S

S Gross Beta in Air Filter S Acceptance Reference Reported S Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/l pCi/l Ratio Staus 0 9/15/2011 E8067-37 Cs-137 0.80- 1.20 7.73E+01 7.60E+01 0.98 Pass S 9/15/2011 E8066-37 Cs-137 0.80- 1.20 1.94E+02 1.80E+02 0.93 Pass S

I I S S

0 S

S 0

S S

Section 5 - Page 10 S

S

0 0

0 Table 5.0-B Footnote Explanations 0

0 (1) Gamma in Water, Sample ID. E8068-37, Reference Date 9/15/2011 0

0 Zn-65 was identified in the cross-check sample but was not reported due to a 0 summary report error (reference 6.19).

0 0

0 S

0 0

S 0

0 0

S 0

0 0

Section 5 - Page 11

0 0

0 TABLE 5.0-C 0 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) 0 QUIKTm RESPONSE PROGRAM 0 2011 PROFICIENCY TEST RESULTS FOR 0 ENRAD LABORATORIES 0

ERA LABORATORY CODE: D242401 0

Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates as described in the "Quik" Response instruction package within the study period. Proficiency test data 0

are reported to ERA for evaluation. ERA reports proficiency test results to the North Carolina Department of 0 Health and Human Services, North Carolina Public Drinking Water Laboratory Certification Program. 0 If applicable, footnote explanations are included following this data table.

0 Gamma Emitters in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status 0 pCi/l pCi/l pCi/1 0 4/4/2011 RAD-85* Ba-133 6.30 - 8.28 El 7.53 El 7.70 El Pass 0

Cs-134 5.95 - 8.02 El 7.29 El 7.28 El Pass Cs-137 6.93 - 8.74 El 7.70 El 7.66 El Pass 0

Co-60 0.799 - 1.00 E2 8.88 El 9.41 El Pass 0 Zn-65 0.89 - 1.18 E2 9.89 El 1.02 E2 Pass 0 0

10/7/2011 RAD-87** Ba-133 0.818 - 1.06 E2 9.69 E1 8.92 El Pass 0 Cs-134 2.63 - 3.67 El 3.34 El 3.33 El Pass 3.79 El Low ()

S Cs-137 3.94 - 5.17 El 4.43 El Co-60 1.07 - 1.33 E2 1.19 E2 1.11 E2 Pass 0

Zn-65 6.89 - 9.25 El 7.68 El 7.95 El Pass 0 0

10/4/2010 Quik 12211lA*** Ba-133 5.75 - 7.58 El 6.89 El 7.14 El Pass 0 Cs-134 3.45 - 4.75 El 4.32 El 4.41 El Pass 0 Cs- 137 1.11 - 1.38 E2 1.23 E2 1.23 E2 Pass 0

Co-60 4.81 - 6.13 El 5.34 El 6.00 El Pass Zn-65 0.918 - 1.22 E2 1.02 E2 1.24 E2 High (2) 0 0

Tritium in Water 0

Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check 0 Date Range Value Value Status 0 pCi/l pCi/I pCi/l 4/4/2011 RAD-85* H-3 0.887 - 1.12 E4 1.02 E4 9.76 E3 Pass 0

0 10/7/2011 RAD-87** H-3 1.52 - 1.91 E4 1.74 E4 1.68 E4 Pass 0 0

ERA study period4/4/2011 - 5/19/2011, ERA data reportissue date 526/2011 ERA study period 107/12011 - 11/21/2011, ERA data reportissue date 11/29/2011 ERA study period 12/21/2011 - 2/23/2012, ERA data reportissue date 2/23/2012 Section 5 -Page 12

0 0

0 Table 5.0-C Footnote Explanations 0

0 (1) Gamma Emitters in Water, Sample ID RAD-87, Reference Date 10/7/2011 0 Reported result for Cs-137 was below the acceptance range limit (reference 6.20).

0 (2) Gamma Emitters in Water, Sample ID QUIK 12211 IA, Reference Date S 10/4/2010 0

Sample ID QUIK 122111A originated as an evaluation sample for Sample ID 0 RAD-87's low Cs-137 result. The reported Zn-65 result for QUIK 122111 A was above the acceptance range limit (reference 6.20)

S 0

0 0

0 S

0 0

0 Section 5 - Page 13

S 0

0 TABLE 5.0-D 0 2011 ENVIRONMENTAL DOSIMETER 0 CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2011 2nd Quarter 2011 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102178 96.3 95.1 1.26 <+/-15% Pass 102021 15.7 14.6 7.81 <+/-15% Pass 102194 99.4 95.1 4.50 <+/-15% Pass 102026 15.6 14.6 6.85 <+/-15% Pass 102234 101.4 95.1 6.65 <+/-15% Pass 102038 16.3 14.6 11.92 <+/-15% Pass 102162 99.7 95.1 4.88 <+/-15% Pass 102057 14.4 14.6 -1.44 <+/-15% Pass 102099 97.5 95.1 2.52 <+/-15% Pass 102213 15.1 14.6 3.15 <+/-15% Pass Average Bias (B) 3.96 Average Bias (B) 5.66 Standard Deviation (S) 2.10 Standard Deviation (S) 5.05 Measure Performance IBI+S 6.07 <15% Pass Measure Performance IBI+S 10.70 <15% Pass S 3rd Quarter 2011 4th Quarter 2011 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail S Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 0 102442 91.6 91.4 0.25 <+/-15% Pass 101285 72.0 70.0 2.84 <+/-15% Pass 102257 94.9 91.4 3.85 <+/-15% Pass 100746 71.2 70.0 1.71 <+/-15% Pass 0 102337 91.9 91.4 0.53 <+/-15% Pass 100087 70.7 70.0 0.97 <+/-15% Pass 0 102221 95.1 91.4 4.00 <+/-15% Pass 101131 71.7 70.0 2.46 <+/-15% Pass 102483 94.7 91.4 3.64 <+/-15% Pass 101356 72.5 70.0 3.59 <+/-15% Pass 0 Average Bias (B) 2.46 Average Bias (B) 2.31 0 Standard Deviation (S) 1.89 Standard Deviation (S) 1.01 0 Measure Performance 1B1+S 4.35 <15% Pass Measure Performance IBI+S 3.32 <15% Pass 0

S S

S 0

0 Section 5 - Page 14

Internal Crosscheck (Duke Energy) 0 1st Quarter 2011 2nd Quarter 2011 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (%diff) Criteria Pass/Fail 102104 33.3 34.0 -2.15 <+/-15% Pass 100104 35.6 35.0 1.71 <+/-15% Pass 102316 32.7 34.0 -3.85 <+/-15% Pass 100054 34.3 35.0 -2.00 <+/-15% Pass 102325 32.3 34.0 -5.12 <+/-15% Pass 102410 34.4 35.0 -1.71 <+/-15% Pass 102434 32.8 34.0 -3.44 <+/-15% Pass 102363 34.6 35.0 -1.09 <+/-15% Pass 102009 33.6 34.0 -1.26 <+/-15% Pass 100816 34.2 35.0 -2.20 <+/-15% Pass 102149 32.3 34.0 -4.97 <+/-15% Pass 101311 32.6 35.0 -6.86 <+/-15% Pass 102419 31.8 34.0 -6.44 <+/-15% Pass 100432 36.1 35.0 3.03 <+/-15% Pass 102160 34.8 34.0 2.47 <+/-15% Pass 100065 33.2 35.0 -5.29 <+/-15% Pass 102502 32.5 34.0 -4.38 <+/-15% Pass 100103 33.4 35.0 -4.54 <+/-15% Pass 102496 31.3 34.0 -7.88 <+/-15% Pass 100097 35.1 35.0 0.23 <+/-15% Pass Average Bias (B) -3.70 Average Bias (B) -1.87 Standard Deviation (S) 2.90 Standard Deviation (S) 3.09 Measure Performance IBI+S 6.60 <15% Pass Measure Performance IBI+S 4.96 <15% Pass 0

3rd Quarter 2011 4th Quarter 2011 0 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (%diff) Criteria Pass/Fail 0 102015 34.1 34.0 0.35 <+/-15% Pass 102005 38.8 40.0 -3.03 <+/-15% Pass 0 102468 33.4 34.0 -1.91 <+/-15% Pass 101364 39.2 40.0 -1.98 <+/-15% Pass 102008 33.0 34.0 -3.03 <+/-15% Pass 102164 37.5 40.0 -6.15 <+/-15% Pass 102496 31.2 34.0 -8.21 <+/-15% Pass 102163 38.2 40.0 -4.43 <+/-15% Pass 102160 33.2 34.0 -2.32 <+/-15% Pass 101252 37.6 40.0 -6.05 <+/-15% Pass 0 102156 33.6 34.0 -1.26 <+/-15% Pass 102104 38.5 40.0 -3.83 <+/-15% Pass 102064 32.9 34.0 -3.32 <+/-15% Pass 101297 38.0 40.0 -4.98 <+/-15% Pass 102419 32.4 34.0 -4.79 <+/-15% Pass 102178 39.0 40.0 -2.50 <+/-15% Pass S 102498 33.0 34.0 -3.06 <+/-15% Pass 101305 38.3 40.0 -4.18 <+/-15% Pass 0 102340 32.9 34.0 -3.29 <+/-15% Pass 102243 37.9 40.0 -5.38 <+/-15% Pass Average Bias (B) -3.09 Average Bias (B) -4.25 0 Standard Deviation (S) 2.27 Standard Deviation (S) 1.44 0 Measure Performance IBI+S 5.35 <15% Pass Measure Performance IBI+S 5.68 <15% Pass 0

0 0

0 Section 5 - Page 15

0 0

0 *

6.0 REFERENCES

6.1 Catawba Selected License Commitment Report 6.2 Catawba Technical Specifications 6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 0 6.5 Catawba Annual Environmental Operating Report 1985 - 2010 6.6 Catawba Annual Effluent Report 1985 - 2011 6.7 Probability and Statistics in Engineering and Management Science, Hines and

Montgomery, 1969, pages 287-293.

0 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, Canberra

Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report 05000413/2011004 and 05000414/2011004 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 0

6.14 Radiological Effluents Controls INOS Audit 10-13(INOS)(REC)(CNS) 6.15 Nuclear System Directive (NSD) 701, Records Management 0

6.16 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G- 11-01190 6.17 NUREG/CR-1276, User's Manual for LADTAP II - A Computer Program for Calculating Radiation Exposure to Man from Routine release of Nuclear Reactor Liquid Effluents 6.18 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-12-00354 6.19 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-12-0015 6.20 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-1 1-001830 6.21 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-1 1-00452 0 Section 6 - Page 1 0

0 0

0 0 APPENDIX A 0

0 0 ENVIRONMENTAL SAMPLING 0 &

0 ANALYSIS PROCEDURES 0

0 0

0 0 Appendix A - Page 1 0

0

0 0

APPENDIX A 0 ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES 0

Adherence to established procedures for sampling and analysis of all environmental media at Catawba 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, Fisheries and Aquatic Ecology.

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

I. CHANGE OF SAMPLING PROCEDURES 00 Indicator location 252 (Ground Water) removed from the program (reference 6.21).

Indicator location 260 (Crops) added as a replacement for indicator location 253 (Crops), which was removed from the program (reference 6.16).

II. DESCRIPTION OF ANALYSIS PROCEDURES 0 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.

Low-level iodine analyses are performed by passing a designated sample aliquot through a pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

0 Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system or Perkin-Elmer 2900TR liquid scintillation system. Tritium samples are distilled and batch processed with a tritium spike and blank to verify instrument performance and sample preparation technique are acceptable.

A 0

Appendix A - Page 2 5 0

0 0

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Tennelec XLB Series 5 gas-flow proportional counters.

Samples are batch processed with a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES

No analysis procedures were changed during 2011.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE 0Airborne particulate and radioiodine samples at each of five 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 positioned 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 separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta

analysis was performed on each filter. The continuous composite samples were

collected from the locations listed below.

Location 200 Site Boundary (0.63 mi. NNE)

Location 201 = Site Boundary (0.53 mi. NE)

Location 205 = Site Boundary (0.25 mi. SW)

Location 212 = Tega Cay (3.32 mi. E)

Location 258 = Fairhope Road (9.84 mi. W)

A.2 DRINKING WATER

Monthly composite drinking water samples were collected at each of two locations. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The

composites were collected monthly from the locations listed below.

0

Location 214 = Rock Hill Water Supply (7.30 mi. SSE)

Location 218 = Belmont Water Supply (13.5 mi. NNE)

A.3 SURFACE WATER 0

Monthly composite samples were collected at each of three locations. A gamma analysis was performed on the monthly composites. Tritium analysis was A

0

Appendix A -Page 3 0

S S

0 performed on the quarterly composites. The composites were collected monthly 0 from the locations listed below. 0 Location 208 Discharge Canal (0.45 mi. S) S Location 211 Wylie Dam (4.06 mi. ESE)

Location 215 River Pointe - Hwy 49 (4.21 mi. NNE)

A.4 GROUND WATER Grab samples were collected quarterly from a residential well at one location. A gamma analysis and tritium analysis were performed on each sample. The 0

samples were collected from the location listed below.

0 Location 252 = Residence (0.64 mi. SW) 0 Programmaticsampling terminated5/11/2011, reference 6.21 Location 254 = Residence (0.82 mi. N)

A.5 MILK 0

Biweekly grab samples were collected at one location. A gamma and low-level S Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the location listed below. 0 Location 221 = Dairy (14.5 mi. NW) 0 A.6 BROADLEAF VEGETATION 0 Monthly samples were collected at each of five locations. A gamma analysis 0

was performed on each sample. The samples were collected from the locations 0 listed below.

0 Location 200 Site Boundary (0.63 mi. NNE) 0 Location 201 Site Boundary (0.53 mi. NE)

Location 222. Site Boundary (0.70 mi. N) 0 Location 226 Site Boundary (0.48 mi. S)

Location 258 Fairhope Road (9.84 mi. W)

A.7 FOOD PRODUCTS Monthly samples were collected when available during the harvest season at one location. A gamma analysis was performed on each sample. The samples were collected from the location listed below.

Location 253 = Irrigated Gardens (1.90 mi SSE)

Programmaticsampling terminated8/2/2011, reference 6.16 Location 260 = Irrigated Gardens (2.00 mi. SSE)

Programmaticsampling initiated8/2/2011, reference 6.16 Appendix A - Page 4

0 0

A.8 FISH Semiannual samples were collected at each of two locations. A gamma analysis

was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.

0

Location 208 = Discharge Canal (0.45 mi. S)

Location 216 = Hwy 49 Bridge (4.19 mi. NNE)

A.9 SHORELINE SEDIMENT Semiannual samples were collected at each of three locations. A gamma analysis was performed on each sample following the drying and removal of

rocks and clams. The samples were collected from the locations listed below.

Location 208 = Discharge Canal (0.45 mi. S)

Location 210 = Ebenezer Access (2.31 mi. SE)

Location 215 = River Pointe - Hwy 49 (4.21 mi. NNE) 0

A.10 DIRECT GAMMA RADIATION (TLD) 0Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one

locations. A gamma exposure rate was determined for each TLD. TLD locations

are listed in Table 2.1-B. The TLDs were placed as indicated below.

An inner ring of 16 TLDs, one in each meteorological sector in the general area of the site boundary.

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 at three

control locations.

A.11 ANNUAL LAND USE CENSUS 0

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 Garden greater than 50 square meters or 500 square feet 0

Appendix A -Page 5 0

S S

The Nearest Milk-giving Animal (cow, goat, etc.)

S S

The census was conducted during the growing season from 7/13 to 7/14/2011. S Results are shown in Table 3.11. No changes were made to the sampling procedures during 2011 as a result of the 2011 census.

S S

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS S S

The Catawba site centerline used for GPS measurements was referenced from the S Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location. Waypoint coordinates used for CNS GPS S measurements were latitude 35'-3'-5"N and longitude 81'-4'-10"W. Maps and S tables were generated using North American Datum (NAD) 27. Data normally S reflect accuracy to within 2 to 5 meters from point of measurement. All GPS field measurements were taken as close as possible to the item of interest. Distances for S

the locations are displayed using three significant figures. S S

S S

Appendix A - Page 6 S S

0 0

0 0 APPENDIX B 0

0 0 RADIOLOGICAL 0

ENVIRONMENTAL MONITORING 0

0 PROGRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0 2011 0

0 0

0 Appendix B - Page 1 0

S 0

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 0 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 Medium or Type and Lower Location with Highest No. of Non- 0 Medium Total Low All Indicator Locat w est Control Routine Paha ubr Limit of Locations Annual Mean Location Report Sampled Number Detection Name, Distance, Direction 0 of Meas.

Unit of Analyses LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range Air Particulate 258 (pCi/m3) (9.84 mi W)

BETA 260 1.00E-02 1.84E-2 (208/208) 201 1.98E-2 (52/52) 1.92E-2 (52/52) 0 3.95E 3.43E-2 (0.53 mi NE) 7.42E 2.92E-2 6.09E 3.14E-2 CS-134 260 5.OOE-02 0.00 (0/208) 0.00(0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00-0.00 0.00- 0.00 CS-137 260 6.00E-02 3.21E-3 (2/208) 201 3.92E-3 (1/52) 0.00(0/52) 0 0

2.50E 3.92E-3 (0.53 mi NE) 3.92E 3.92E-3 0.00-0.00 0 1-131 260 7.00E-02 1.19E-2 (10/208) 201 1.39E-2 (3/52) 1.04E-2 (2/52) 0 4.89E 2.00E-2 (0.53 mi NE) 4.89E 2.00E-02 1.04E 1.05E-02 0

0 Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0 0

0 0

0 Report Generated @4/2/2012 1:33 PM 0

Appendix B - Page 2

0 0

S Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 S

Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0

0 Medium or Type and Total Lower All Indicator Location with Highest Control No. of Non-Pathway Number Limnt of Locations Annual Mean Location Routine Sampled of Detection Name, Distance, Direction Report Meas.

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

Measurement Performed Range Code Range Range Air Radioiodine 258 (pCi/m3) (9.84 mi W)

CS-134 260 5.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 260 6.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 260 7.OOE-02 4.21E-2 (17/208) 200 5.53E-2 (4/52) 5.65E-2 (4/52) 0 S 7.06E 9.32E-2 (0.63 mi NNE) 2.74E 8.19E-2 2.5 1E 9.24E-2 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 3/1/2012 11:25 AM Appendix B - Page 3

0 0

Environmental Radiological Monitoring Program Summary 0

Facility: Catawba Nuclear Station Docket No. 50-413,414 S

Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0

No. of Non-Type and Total Lower Location with Highest ControlNone Medium or Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

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

Measurement Performed (LLD) Range Code Range Range Drinking Water 218 0

(pCi/liter) (13.5 mi NNE) 0 BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 BETA 26 4 0.00 - 0.00 2.01 (13/13) 214 0.00 - 0.00 2.01 (13/13) 0.00 - 0.00 1.71 (13/13) 0 0

1.15-2.64 (7.30 mi SSE) 1.15- 2.64 0.68-2.73 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00- 0.00 0.00- 0.00 0 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00- 0.00 0.00- 0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00- 0.00 0.00- 0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 H-3 8 2000 973 (4/4) 214 973 (4/4) 636 (4/4) 0 0 783-1150 (7.30 mi SSE) 783- 1150 519-779 1-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 0 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

Report Generated @ 2/13/2012 1:21 PM Appendix B - Page 4

0 0

0 0 Environmental Radiological Monitoring Program Summary 0 Facility: Catawba Nuclear Station Docket No. 50-413,414 S Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 Medium or Type and Total Lower Location with Highest ControlNone No. of Non-Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code Range Range Surface Water 215 (pCi/liter) (4.21 mi NNE)

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 8.75 (1/26) 208 8.75 (1/13) 0.00 (0/13) 0 8.75 - 8.75 (0.45 rni S) 8.75 - 8.75 0.00 - 0.00 CO-60 39 15 19.6 (1/26) 208 19.6 (1/13) 0.00 (0/13) 0 19.6 - 19.6 (0.45 mi S) 19.6 - 19.6 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 0 FE-59 39 30 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

H-3 12 2000 4631 (8/8) 208 8285 (4/4) 541 (4/4) 0 792-11300 (0.45 mi S) 4770-11300 433-629 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 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 3/1/2012 11:25 AM Appendix B - Page 5

S 0

S Environmental Radiological Monitoring Program Summary S

S Facility: Catawba Nuclear Station Docket No. 50-413,414 S Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 S No. of Non-S Medium or Type and Total Lower Location with Highest ControlNone S Annual Mean Pathway Number Limit of Locations Name, Distance, Direction Location Report S

Sampled of Detection Meas. S Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) S Measurement Performed Range Code Range Range S S

Ground Water NO CONTROL (pCi/liter) LOCATION S S

BALA-140 4 15 0.00(0/4) 0.00 (0/4) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S

CO-58 4 15 0.00 (0/4) 0.00 (0/4) 0.00 (0/0) 0 S 0.00 -0.00 CO-60 4 15 0.00 - 0.00 0.00 (0/4) 0.00 (0/4) 0.00 - 0.00 0.00(0/0) 0 S

0.00 - 0.00 0.00 -0.00 0.00 - 0.00 S CS-134 4 15 0.00 (0/4) 0.00 - 0.00 0.00(0/4) 0.00 - 0.00 0.00(0/0) 0.00 - 0.00 0 S CS-137 4 18 0.00 (0/4) 0.00 (0/4) 0.00 (0/0) 0 S FE-59 4 30 0.00 - 0.00 0.00 (0/4) 0.00 - 0.00 0.00 (0/4) 0.00 - 0.00 0.00 (0/0) 0 S

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S H-3 4 2000 0.00 (0/4) 0.00(0/4) 0.00 (0/0) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 4 15 0.00(0/4) 0.00 (0/4) 0.00 (0/0) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S MN-54 4 15 0.00 (0/4) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S NB-95 4 15 0.00 (0/4) 0.00 (0/4) 0.00 (0/0) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 4 30 0.00 (0/4) 0.00(0/4) 0.00(0/0) 0 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S ZR-95 4 15 0.00 (0/4) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

0 Mean and range based upon detectable measurements only S

Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) S Zero range indicates no detectable activity measurements S S

S S

S Report Generated @ 2/13/2012 1:43 PM S

Appendix B - Page 6 S S

S

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 No. of Non-Lower Location with Highest ControlNone Medium or Type and Total 0 Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled 0 Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range Milk NO INDICATOR 221 (pCi/liter) LOCATION (14.5 mi NW)

BALA-140 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 CS-134 26 15 0.00 - 0.00 0.00 (0/0) 0.00 - 0.00 0.00 - 0.00 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 0 1-131 26 15 0.00 (0/0) 0.00-0.00 0.00 (0/0) 0.00-0.00 10.5 (2/26) 7.13-13.8 0

0 LLI-131 26 1 0.00(0/0) 0.00 (0/0) 6.86 (3/26) 0 0 0.00 - 0.00 0.00 - 0.00 1.09 - 14.7 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

0 0

0 S

0 Report Generated @ 2/13/2012 1:46 PM Appendix B - Page 7

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0

0 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0

No. outine of Non-Medium or Type and Total Lower Location with Highest Cnr All IndicatorCotl Ruin Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code Range Range Broadleaf 258 Vegetation (9.84 mi W)

(pCi/kg-wet) 0 CS-134 60 60 12.8 (1/48) 200 12.8 (1/12) 0.00 (0/12) 0 0 12.8 - 12.8 (0.63 mi NNE) 12.8 - 12.8 0.00- 0.00 CS-137 60 80 22.1 (5/48) 201 26.2 (3/12) 0.00 (0/12) 0 0

11.6-38.8 (0.53 mi NE) 19.2-38.8 0.00-0.00 0 1-131 60 60 117 (4/48) 96.3-132 200 (0.63 mi NNE) 132 (1/12) 132-132 156 (1/12) 156-156 0 0 0

0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0 0

0 0

0 Report Generated @4/2/2012 1:34 PM Appendix B - Page 8

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0

0 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 Location with Highest Cnr No. of Non-oftin-Medium or Type and Total Lower 0 Pathway Number Limit of Annual Mean Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed (LLD) Range Code Range Range 0 Food Products NO CONTROL 0 (pCi/kg-wet) LOCATION CS-134 5 60 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 5 80 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 5 60 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 2/13/2012 2:22 PM Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ContoolNone Number Limit of Annual Mean Pathway of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code Range Range Fish 216 (pCi/kg-wet) (4.19 mi NNE)

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 CO-60 12 130 0.00 (0/6) 0.00 -0.00 0.00 (0/6) 0 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 0 CS-137 12 150 21.6(1/6) 208 21.6(1/6) 0.00(0/6) 0 21.6-21.6 (0.45 mi S) 21.6-21.6 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 0 MN-54 12 130 0.00(0/6) 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 0 0 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 0

Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 2/13/2012 2:25 PM Appendix B - Page 10 0

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Type and Total Lower Location with Highest Cnr outine Medium or Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed Range Code Range Range Shoreline 215 Sediment (4.21 mi NNE)

(pCi/kg-dry)

MN-54 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-57 6 0 10.5 (1/4) 208 10.5 (1/2) 0.00 (0/2) 0 0 10.5 - 10.5 (0.45 mi S) 10.5 - 10.5 0.00 - 0.00 CO-58 6 0 83.6 (2/4) 208 83.6 (2/2) 0.00 (0/2) 0 0 75.9-91.2 (0.45 mn S) 75.9-91.2 0.00- 0.00 CO-60 6 0 236 (2/4) 208 236 (2/2) 0.00 (0/2) 0 152-320 (0.45 mi S) 152-320 0.00- 0.00 CS-134 6 150 36.2 (1/4) 208 36.2 (1/2) 0.00 (0/2) 0 0 36.2 - 36.2 (0.45 ml S) 36.2 - 36.2 0.00 - 0.00 CS-137 6 180 43.3 (2/4) 208 43.3 (2/2) 0.00 (0/2) 0 0 27.8 - 58.8 (0.45 mi S) 27.8 - 58.8 0.00 - 0.00 0

0 Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 0

0 0

0 Report Generated @ 3/19/2012 5:15 PM Appendix B - Page 11

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 Y F U q Type and No. of Non-Lower Location with Highest Medium or Total All Indicator Control Routine Limit of Annual Mean Pathway Sampled Number Locations Location Report Detection Name, Distance, Direction of Meas.

Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Unit of Measurement (LLD)

Performed Range Code Range Range w

Direct Radiation 217 (10.3 mi SSE)

TLD 247 (7.33 mniESE) 0 (mR/standard quarter) 251 (9.72 mi WNW) 0 164 0.OOE+00 18.3 (152/152) 237 23.3 (4/4) 14.6 (12/12) 0 0

11.0- 26.0 (4.75 mi SSE) 20.0-25.0 11.0- 19.0 0 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

0 0

Report Generated @ 3/1/2012 11:28 AM Appendix B - Page 12

0 0

0 CATAWBA 0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0

0 PROGRAM 0

0 0

0

SUMMARY

OF 2011 RESULTS 0

0 EXCLUDING 0 RADIOACTIVITY ATTRIBUTABLE 0

0 TO FUKUSHIMA DAIICHI 0

0 0

0 0 Appendix B - Page 13 0

0

0 0

0 Environmental Radiological Monitoring Program Summary

0 0

Facility: Catawba Nuclear Station Docket No. 50-413,414 0

Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 Medium or Type and Lower Location with Highest No. of Non-Medium Total Low All Indicator Locat w est Control Routine Pathway Number Lmteof Locations annual Mea n Location Report Sampled of Detection Name, Distance, Direction Meas.

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

Measurement Performed Range Code Range Range 0 Air Particulate 258 0

(pCi/m3) (9.84 mi W) 0 BETA 235 1.OOE-02 1.84E-2 (188/188) 201 1.95E-2 (47/47) 1.90E-2 (47/47) 0 0

3.95E 3.43E-2 (0.53 mi NE) 7.42E 2.92E-2 6.09E 3.14E-2 0 CS-134 235 5.OOE-02 0.00 (0/188) 0.00 - 0.00 0.00(0/47) 0.00 - 0.00 0.00 (0/47) 0.00 - 0.00 0

0 CS-137 235 6.00E-02 0.00 (0/188) 0.00 (0/47) 0.00 (0/47) 0 0 1-131 235 7.00E-02 0.00 - 0.00 0.00 (0/188) 0.00-0.00 0.00(0/47) 0.00-0.00 0.00 (0/47) 0 0

0.00-0.00 0.00-0.00 0.00 - 0.00 0 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

Summary does not include samples collected during Fukushima Daiichi fallout period 3/15/2011 - 4/19/2011 0 0

0 0

0 Report Generated @4/19/2012 1:32 PM Appendix B - Page 14

Environmental Radiological Monitoring Program Summary

Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 Medium or Type and Lower Location with Highest No. of Non-Total All Indicator Control Pathway Number Limit of Locations Annual Mean Location Routine Sampled of Detection Name, Distance, Direction Report Meas.

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

Measurement Performed Range Code Range Range Air Radioiodine 258 0 (pCi/m3) (9.84 mi W) 0 CS-134 235 5.OOE-02 0.00 (0/188) 0.00 (0/47) 0.00 (0/47) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 235 6.00E-02 0.00 (0/188) 0.00 (0/47) 0.00 (0/47) 0 S 1-131 235 7.00E-02 0.00 - 0.00 0.00 (0/188) 0.00 - 0.00 0.00 (0/47) 0.00 - 0.00 0.00 (0/47) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S

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 0

Summary does not include samples collected during Fukushima Daiichi fallout period 3/15/2011 - 4/19/2011 0

0 0

Report Generated @ 4/19/2012 1:33 PM Appendix B - Page 15

Environmental Radiological Monitoring Program Summary

0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0

0 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 ControlNone No. of Non- 0 Location with Highest Medium or Pathway Type and Total Number Lower Limit of Annual Mean 0 Locations Report Sampled of Detection Name, Distance, Direction Location ceaor 0 Meas.

0 Unit of Measurement Analyses Performed (LLD)

Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range 0

0 Milk NO INDICATOR 221 0 (pCi/liter) LOCATION (14.5 mi NW) 0 BALA-140 23 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/23) 0 0 CS-134 23 15 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 0.00 (0/0) 0.00 (0/0) 0.00 (0/23) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 23 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/23) 0 0 0.00 - 0.00 0.00-0.00 0.00 - 0.00 1-131 23 15 0.00(0/0) 0.00(0/0) 0.00(0/23) 0 0

0.00 - 0.00 0.00-0.00 0.00-0.00 0 LLI-131 23 1 0.00 (0/0) 0.00 - 0.00 0.00 (0/0) 0.00-0.00 0.00 (0/23) 0.00 - 0.00 0

0 0

Mean and range based upon detectable measurements only 0

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

Zero range indicates no detectable activity measurements

Summary does not include samples collected during Fukushima Daiichi fallout period 3/29/2011 - 4/26/2011 0

0 0

0 Report Generated @ 4/19/2012 1:33 PM 0 Appendix B - Page 16 0

0

0 0

0 Environmental Radiological Monitoring Program Summary

0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0 Location: York County, South Carolina Report Period: 01-JAN-2011 to 31-DEC-2011 0 Location with Highest ControlNone No. of Non-Medium or Type and Total Lower All IndicatorCotl Ruin Annual Mean 0 Pathway Number Limit of Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

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

Measurement Performed Range Code Range Range Broadleaf 258 Vegetation (9.84 mi W)

(pCi/kg-wet)

CS-134 55 60 0.00(0/44) 0.00(0/11) 0.00(0/11) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 56 80 26.2 (3/45) 201 26.2 (3/12) 0.00 (0/11) 0 0 19.2- 38.8 (0.53 mi NE) 19.2- 38.8 0.00 -0.00 1-131 55 60 0.00(0/44) 0.00(0/11) 0.00(0/11) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements

Summary does not include samples collected during Fukushima Daiichi fallout period 4/5/2011 but does include Cs-137 results for location 201 (Bluebird Lane) during this period.

0 0

0 Report Generated @ 4/19/2012 1:33 PM Appendix B - Page 17

6 0

0 0

0

SUMMARY

OF RADIOACTIVITY 0 0

ATTRIBUTABLE 0

TO 0

FUKUSHIMA DAIICHI 0 DETECTED IN 0 0

ENVIRONMENTAL MEDIA AT 0 DUKE ENERGY FACILITIES 0 0

0 0

0 Appendix B - Page 18 0

0

Fukushima Daiichi Radioactivity Detected in Environmental Media (2011)

Airborne Particulate Annual Concentration with Annual Concentration without Fukushima Dalichi (pCi/m3) Fukushima Daiichi (pCi/m 3)

Station Analysis Indicator Control Indicator Control Catawba 1-131 1.39E-2 1.04E-2 0.00 0.00 Catawba Cs-137 3.92E-3 0.00 0.00 0.00 McGuire 1-131 2.08E-2 1.54E-2 0.00 0.00 McGuire Cs-137 7.06E-3 0.00 0.00 0.00 Oconee 1-131 1.46E-2 2.01E-2 0.00 0.00 Oconee Cs-134 1.44E-2 0.00 0.00 0.00 Oconee Cs- 137 8.08E-3 0.00 0.00 0.00 Airborne Radioiodine Annual Concentration with Annual Concentration without Fukushima Daiichi (pCi/m 3) Fukushima Daiichi (pCi/m 3) 0 Station Analysis Indicator Control Indicator Control 0 Catawba 1-131 5.53E-2 5.65E-2 0.00 0.00 McGuire 1-131 6.00E-2 5.46E-2 0.00 0.00 0 Oconee 1-131 5.05E-2 4.13E-2 0.00 0.00 Milk S Annual Concentration with Fukushima Daiichi (pCi/!)

Annual Concentration without Fukushima Daiichi (pCi/1)

Station Analysis Indicator Control Indicator Control Catawba LLI-131 NA 6.86 NA 0.00 McGuire LLI-131 NA 4.80 NA 0.00 Oconee LLI-131 NA 0.81 NA 0.00 Broadleaf VY etation Annual Concentration with Annual Concentration without Fukushima Daiichi (pCi/kg) Fukushima Daiichi (pC/kg)

Station Analysis Indicator Control Indicator Control Catawba 1-131 132 156 0.00 0.00 Catawba Cs-134 12.8 0.00 0.00 0.00 Catawba Cs-137 26.2 0.00 26.2 0.00 McGuire 1-131 316 168 0.00 0.00 McGuire Cs-137 22.9 0.00 0.00 0.00 Oconee 1-131 398 150 0.00 0.00 Oconee Cs-134 42.9 0.00 0.00 0.00 Oconee Cs-137 66.8 33.5 0.00 0.00 Food Products (Crops)

Annual Concentration with Annual Concentration without Fukushima Daiichi (Ci/kg) Fukushimra Daiichi (pCilkg)

Station Analysis Indicator Control Indicator Control McGuire 1-131 142 NA 0.00 0.00 McGuire Cs-137 30.6 NA 0.00 0.00 Appendix B - Page 19

0 0

0 APPENDIX C 0

0 0

0 SAMPLING DEVIATIONS 0 &

0 UNAVAILABLE ANALYSES 0

0 0

0 0 Appendix C - Page 1 0

I S S

APPENDIX C 0 0

0 CATAWBA NUCLEAR STATION 0 SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES S DEVIATION & UNAVAILABLE REASON CODES S

BF Blown Fuse PO Power Outage S

FZ Sample Frozen PS Pump out of service / Undergoing Repair S IW LC Inclement Weather Line Clog to Sampler SL SM Sample Loss/Lost due to Lab Accident Motor / Rotor Seized S

OT Other TF Tom Filter S PI PM Power Interrupt Preventive Maintenance VN CN Vandalism Construction S

WO Well Unavailable/Out of Service S S

C.1 SAMPLING DEVIATIONS S S

Air Particulate and Air Radioiodines S Scheduled Actual Location Collection Dates Collection Dates Code Description Corrective Action Identity S 200 Collection rescheduled due S 201 212 to inclement weather creating potentially unsafe S

258 1/5 - 1/11/2011 1/5 - 1/14/2011 IW site access conditions. G-11-00047 S Power outage to sampling equipment likely S

attributable to severe S 201 4/26 - 5/3/2011 4/26 - 5/3/2011 PO weather. G-1 1-00809 Power outage to sampling S

equipment likely S attributable to severe 200 5/10 - 5/17/2011 5/10 - 5/15/2011 PO weather. G-11-00810 S

Power outage to sampling S equipment likely attributable to severe S 201 5/10 - 5/17/2011 5/10 - 5/11/2011 PO weather. G-11-00811 S Power outage to sampling equipment likely S attributable to severe S 200 5/24 - 6/1/2011 5/24 - 5/26/2011 PO weather. G- 11-00883 Power interruption to S sampling equipment likely S attributable to severe 201 6/21 -6/28/2011 6/21 -6/28/2011 PI weather. G-11-01038 S S

S S

S Appendix C - Page 2 S

S S

0 0 Drinking Water 0 Scheduled Actual Corrective Action Identity Location Collection Dates Collection Dates Code Description 0 Collection rescheduled due to inclement weather 214 creating potentially unsafe 0 218 12/14 - 1/11/2011 12/14 - 1/13/2011 IW site access conditions. G-I 1-00047 0 Surface Water Scheduled Actual Corrective 0 Location Collection Dates Collection Dates Code Description Action Identity 0 Collection rescheduled due 208 to inclement weather 211 creating potentially unsafe 0 215 12/14 - 1/11/2011 12/14 - 1/13/2011 IW site access conditions. G-11-00047 0

0 C.2 UNAVAILABLE ANALYSES 0 Ground Water 0 Location Scheduled Collection Dates Code Description Corrective Action Identity 0 Well at this location (residence) out of service. Residence vacant, sample 0 unattainable due to absence of power 252 3/8/2011 WO to operate well pump. G-1 1-00393 0

Appendix C - Page 3

0 0

S 0

0 0

0 APPENDIX D 0

0 ANALYTICAL DEVIATIONS 0

0 0

No Analytical deviations were incurred for the 0 2011 Radiological Environmental Monitoring Program 0

0 0

S 0

0 0

Appendix D - Page 1

0 0

0 APPENDIX E 0

0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0 PROGRAM RESULTS 0

0 This appendix includes sample analysis reports and supportive data 0 generated from each sample medium. Appendix E is located separately 0 from this report and is permanently archived in the Nuclear Electronic 0 Document Library (NEDL) as described in reference 6.15.

0 0

0 Appendix E - Page I

S S

0 S

S S

0 APPENDIX F S

S S ERRATA TO S PREVIOUS REPORTS S

S S

0 S

S S

S Appendix F - Page 1 S

S

APPENDIX F ERRATA TO THE 2011 AREOR

1. Section 3.9, Shoreline Sediment, Table 3.9 (Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)) located on page 23 0 Row for year 2005 Cs-137 concentration originally reported as 0.OOEO. The corrected year 2005 Cs-137 concentration is 3.04E1 pCi/kg.

0 0

S 0

0 0

S 0

Appendix F - Page 2

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