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| number = ML12137A011
| number = ML12137A011
| issue date = 05/14/2012
| issue date = 05/14/2012
| title = Catawba Nuclear Station Units 1 and 2, Annual Radiological Environmental Operating Report 2011 - Chapter 4.0 Through End
| title = Annual Radiological Environmental Operating Report 2011 - Chapter 4.0 Through End
| author name =  
| author name =  
| author affiliation = Duke Energy Carolinas, LLC
| author affiliation = Duke Energy Carolinas, LLC
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| page count = 66
| page count = 66
}}
}}
=Text=
{{#Wiki_filter:0
* 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).
0              O                                      ~Section 4 -Pagel1 0
0 0
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.
S 0
0 0
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
0 0
0 0
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.
0 S
0 0
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
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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
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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
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.
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* 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
S S
0 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
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0                                                      Section 5-Page 7
0 0
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
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Section 5 - Page 8 0
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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
S S
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).
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Section 5 - Page 11
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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 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
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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
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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
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==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
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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.
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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.
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*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
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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
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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.
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*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
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* The Nearest Milk-giving Animal (cow, goat, etc.)
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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.
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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
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ENVIRONMENTAL MONITORING 0
0          PROGRAM 0
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==SUMMARY==
OF RESULTS 0
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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
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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 0
0 0
0 0
0 0
0 0
0 Report Generated @ 3/1/2012 11:25 AM Appendix B - Page 3
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
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 0
0 0
0 0
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 0
0 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 0
0 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
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
Report Generated @ 3/1/2012 11:28 AM Appendix B - Page 12
0 0
0 0
0 0
0 0
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
0 0
0 0
0 0
0 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 0
0 0
0 0
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
0 0
0 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 0
0 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.
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0 Report Generated @ 4/19/2012 1:33 PM Appendix B - Page 17
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==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
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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
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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
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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
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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.
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Latest revision as of 03:29, 12 November 2019

Annual Radiological Environmental Operating Report 2011 - Chapter 4.0 Through End
ML12137A011
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 05/14/2012
From:
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
Download: ML12137A011 (66)
v • d • e


Text

0

  • 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

0 O ~Section 4 -Pagel1 0

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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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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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0 0

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
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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

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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

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.

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0 Section 5 -Page 2 0 0

0

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.

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S S

S S

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  • Section 5 -Page 3 S

S

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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 0

0 0

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(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).

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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.

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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

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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

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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).

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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

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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)

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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

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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

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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

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

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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.

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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

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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

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

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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

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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)

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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

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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 0

0 0

0 0

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 0

0 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 0

0 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

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

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

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0 CATAWBA 0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0

0 PROGRAM 0

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0

SUMMARY

OF 2011 RESULTS 0

0 EXCLUDING 0 RADIOACTIVITY ATTRIBUTABLE 0

0 TO FUKUSHIMA DAIICHI 0

0 0

0 0

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0 0

0 0

0 0

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0 0 Appendix B - Page 13 0

0

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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 0

0 0

0 0

0 0

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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

0 0

0 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 0

0 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

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

6 0

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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

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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

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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

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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

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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

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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.

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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.

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