ML12145A051

Annual Radiological Environmental Operating Report 2011, Section 5 - Page 1 Through End

ML12145A051
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/10/2012
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
Download: ML12145A051 (48)

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0 0* 5.0 QUALITY ASSURANCE 0* 5.1 SAMPLE COLLECTION 0EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental 0sample collections as specified by approved sample collection procedures.

0 5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures.

EnRad Laboratories is located in Huntersville, North Carolina, at Duke Energy Corporation's 0Environmental Center.0* 5.3 DOSIMETRY ANALYSIS Duke Energy Corporation's Environmental Center 0The Radiation Dosimetry and Records group performed environmental dosimetry 0measurements as specified by approved dosimetry analysis procedures.

0* 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE*5.4.1 DAILY QUALITY CONTROL*EnRad Laboratories has an internal quality assurance program which monitors*each type of instrumentation for reliability and accuracy.

Daily quality control checks ensure that instruments are in proper working order and these checks are*used to monitor instrument performance.

0 5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent 0counting 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.5.4.3 BATCH PROCESSING 0*Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium*analyses.

0 O Section 5 -Page 1 0 0 5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department 0 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 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 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 The McGuire Nuclear Station Radiological Environmental Monitoring Program was not audited by the Quality Assurance Group in 2011, but was audited in 2010. Procedure and report enhancements were identified as part of this audit (reference 6.12).0 5.9 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 5 S The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2011 (reference 6.14). There were no REMP findings identified by the 2011 audit.S 5.10 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. EnRad Laboratories sends air, surface water, milk, crops, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section.S 0 Section 5 -Page 2 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 5.11 TLD INTERCOMPARISON PROGRAM 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 group 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)Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure.

A summary of the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-D.Section 5 -Page 3 TABLE 5.0-A DUKE ENERGY INTERLABORATORY COMPARISON PROGRAM 2011 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "I Pass" indicates that one analysis of the cross check was performed If applicable, footnote explanations are included following this table.Gamma in Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 8/17/2011 Q113GWSL Cr-51 1.85-3.28 E5 2.47 E5 2.47 E5 3 Pass Mn-54 6.36 -11.28 E4 8.48 E4 8.62 E4 3 Pass Co-58 5.13-9.10 E4 6.84 E4 6.79 E4 3 Pass Fe-59 3.42- 6.07 E4 4.56 E4 4.76 E4 3 Pass Co-60 6.28- 11.13 E4 8.37 E4 8.26 E4 3 Pass Zn-65 0.78- 1.38 E5 1.04 E5 1.06 E5 3 Pass Cs-134 5.22-9.25 E4 6.96 E4 6.30 E4 3 Pass Cs-137 4.51- 8.00 E4 6.02 E4 5.59 E4 3 Pass Ce-141 4.89-8.68 E4 6.52 E4 6.51 E4 3 Pass 12/12/2011 Q1l4GWR Mn-54 2.31-4.09 E4 3.08 E4 3.25 E4 1 Pass Co-57 3.05- 5.40 E4 4.06 E4 4.34 E4 1 Pass Co-60 2.76- 4.89 E4 3.67 E4 3.65 E4 1 Pass Y-88 1.49- 2.65 E4 1.99 E4 2.03 E4 1 Pass Cd-109 0.00 -0.00 E3 0.OOE+00 6.46 E3 1/1 High ...Sn-113 1.60-2.84 E4 2.14 E4 2.12 E4 1 Pass Cs-137 2.39-4.23 E4 3.18 E4 3.01 E4 1 Pass Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/1 pCi/1 pCi/i 8/17/2011 Q13GWSL Cr-51 1.85-3.28 E5 2.47 E5 2.47 E5 3 Pass Mn-54 6.36- 11.28 E4 8.48 E4 8.79 E4 3 Pass Co-58 5.13-9.10 E4 6.84 E4 6.87 E4 3 Pass Fe-59 3.42- 6.07 E4 4.56 E4 4.90 E4 3 Pass Co-60 6.28 -11.13 E4 8.37 E4 8.35 E4 3 Pass Zn-65 0.78- 1.38 E5 1.04 E5 1.09 E5 3 Pass 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 Ce-141 4.89-8.68 E4 6.52 E4 6.40 E4 3 Pass 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Section 5 -Page 4 Gamma in Water 1.0 liter, continued 0 0 0 0 0 0 0 0 0 0 0 12/12/2011 Q114GWR Mn-54 2.31-4.09 E4 3.08 E4 3.18 E4 1 Pass Co-57 3.05- 5.40 E4 4.06 E4 4.22 E4 I Pass Co-60 2.76- 4.89 E4 3.67 E4 3.63 E4 I Pass 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 I/1 High "'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 Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/1 pCi/1 pCi/I 8/17/2011 Ql13GWSL 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 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- -E-.04- E5.. 1.08- E5 .3 Pass-Cs-134. -5.22z9.25 E4- 6.96 E4 -5.90 E4 3 Pass Cs,437. 4.51 8.,00 E4- -6.02 E4 5-.56 E4 3 Pass..........-

Ce-141 4.89- 8.68 .E4 6.52 E4 6.34 E4 3 Pass Gamma in Water 0.25 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status... .._pCi/1 pCi/1, pCi/I 8/17/2011 Q1l3GWSL 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 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 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 Cs-134 5.22-9.25 E4 6.96 E4 6.11 E4 3 Pass 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 Gamma in Filter ..... ..Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 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 El 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 El 2 Pass Section 5 -Page 5 Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/23/2011 Q111LIWl 1-131 2.63-4.66 E3 3.51 E3 3.62 E3 3 Pass 3/23/2011 QlilLIW2 1-131 5.26 -.33 E2 7.01 E2 7.04 E2 3 Pass 3/23/2011 Q1llLIW3 1-131 1.15-2.03 E2 1.53 E2 1.54 E2 3 Pass Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/1 pCi/l 8/2/2011 Q1l3LIM1 1-131 1.84-3.26 E3 2.45 E3 2.60 E3 4 Pass 8/2/2011 Q113LIM2 1-131 1.58-2.80 E2 2.10 E2 2.19 E2 4 Pass 8/2/2011 Q113LIM3 1-131 2.63-4.66 El 3.50 El 3.67 El 4 Pass Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 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 Date Range Value Value Status pCil1 pCi/l pCi/1 6/22/2011 Q112TWR1 H-3 2.82- 5.00 E6 3.76 E6 3.57 E6 3 Pass 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 12/12/2011 Q114TWR3 H-3 6.11-10.84 E3 8.15 E3 7.65 E3 3 Pass 12/14/2011 Ql14TWR1 H-3 0.93-1.66 E3 1.24 E3 1.23 E3 3 Pass 12/14/2011 Q114TWR2 H-3 3.18 -5.64 E5 4.24 E5 4.03 E5 3 Pass 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 Section 5 -Page 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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/I pCi/l 5/23/2011 Q112ABW1 Cs-137 5.05-8.95 El 6.73 El 6.84 El 3 Pass 5/23/2011 Qll2ABW2 Cs-137 6.60 -11.71 El 8.80 El 8.47 El 3 Pass 5/23/2011 Qll2ABW3 Cs-137 4.96-8.79 E2 6.61 E2 6.41 E2 3 Pass Section 5 -Page 7 Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q1 14GWR, Reference Date 12/12/2011 Cd-109 was identified in the cross-check sample and reported.

The cross check supplier does not include this radionuclide on the certificate of analysis for this 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 cross-check sample (reference 6.16).0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Section 5 -Page 8 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 S S S 0 0 0 0 S TABLE 5.0-B ECKERT & ZIEGLER ANALYTICS 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.

If applicable, footnote explanations are included following this table.Gamma in Water 3.5 liters Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/1 pCi/l Ratio Staus 9/15/2011 E8068-37 1-131 0.80- 1.20 8.01E+01 7.96E+01 0.99 Pass Ce-141 0.80- 1.20 9.15E+01 8.80E+01 0.96 Pass Cr-51 0.80- 1.20 3.10E+02 3.18E+02 1.02 Pass 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 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 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 (Co-60 0.80- 1.20 2.15E+02 2.02E+02 0.94 Pass 12/8/2011 E8184-37 1-131 0.80- 1.20 8.87E+01 9.46E+01 1.07 Pass Cr-51 0.80- 1.20 5.66E+02 5.57E+02 0.98 Pass 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 Gamma in Milk Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/I pCi/1 Ratio Staus 12/8/2011 E8186-37 1-131 0.80-1.20 9.02E+01 9.84E+01 1.09 Pass Cr-51 0.80- 1.20 5.66E+02 5.36E+02 0.95 Pass Cs-134 0.80- 1.20 1.71E+02 1.59E+02 0.93 Pass 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 Mn-54 0.80- 1.20 2.41E+02 2.45E+02 1.02 Pass 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 Co-60 0.80- 1.20 2.70E+02 2.74E+02 1.02 Pass Iodine in Milk Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/1 pCi/ Ratio Staus 9/15/2011 E8065-37 1-131 0.80-1.20 1.01Dt+02 9.88E+01 0.98 Pass Tritium in Water Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/I pCi/l Ratio Staus 9/15/2011 E8069-37 H-3 0.80- 1.20 9.01E+03 9.16E+03 1.02 Pass 12/8/2011 E8185-37 H-3 0.80- 1.20 1.09E+04 1.04E+04 0.95 Pass Gross Beta in Air Filter Acceptance Reference Reported Reference Range Value Value Cross Check Date Sample I.D. Nuclide Ratio pCi/1 pCi/I Ratio Staus 9/15/2011 E8067-37 Cs-137 0.80- 1.20 7.73E+01 7.60E+01 0.98 Pass 9/15/2011 E8066-37 Cs-137 0.80- 1.20 1.94E+02 1.80E+02 0.93 Pass S 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S Section 5 -Page 10 0 0 0 0 0 S 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 Table 5.0-B Footnote Explanations (1) Gamma in Water, Sample ID. E8068-37, Reference Date 9/15/2011 Zn-65 was identified in the cross-check sample but was not reported due to a summary report error (reference 6.17).Section 5 -Page 11 TABLE 5.0-C ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)QUIK T m RESPONSE PROGRAM 2011 PROFICIENCY TEST RESULTS FOR ENRAD LABORATORIES ERA LABORATORY CODE: D242401 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 are reported to ERA for evaluation.

ERA reports proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Drinking Water Laboratory Certification Program.If applicable, footnote explanations are included following this data table.Gamma Emitters in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/l pCi/i pCi/I 4/4/2011 RAD-85* Ba-133 6.30 -8.28 El 7.53 El 7.70 El Pass 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 Co-60 0.799 -1.00 E2 8.88 El 9.41 El Pass Zn-65 0.89 -1.18 E2 9.89 El 1.02 E2 Pass 10/7/2011 RAD-87** Ba-133 0.818 -1.06 E2 9.69 El 8.92 El Pass Cs-134 2.63 -3.67 El 3.34 El 3.33 El Pass Cs-137 3.94 -5.17 El 4.43 El 3.79 El Low (1)Co-60 1.07 -1.33 E2 1.19 E2 1.11 E2 Pass Zn-65 6.89 -9.25 El 7.68 El 7.95 El Pass 10/4/2010 Quik 122111A***

Ba-133 5.75 -7.58 El 6.89 El 7.14 El Pass Cs-134 3.45 -4.75 El 4.32 El 4.41 El Pass Cs-137 1.11 -1.38 E2 1.23 E2 1.23 E2 Pass 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)Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/l pCil pCi/I 4/4/2011 RAD-85* H-3 0.887 -1.12 E4 1.02 E4 9.76 E3 Pass 10/7/2011 RAD-87** H-3 1.52 -1.91 E4 1.74 E4 1.68 E4 Pass* ERA study period 4/4/2011 -5119/2011, ERA data report issue date 5/26/2011** ERA study period 1017/2011

-11/21/2011, ERA data report issue date 11/29/2011 ERA study period 12/21/2011

.2/23/2012, ERA data report issue date 2/23/2012 Section 5 -Page 12 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S Table 5.0-C Footnote Explanations 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) Gamma Emitters in Water, Sample ID RAD-87, Reference Date 10/7/2011 Reported result for Cs-137 was below the acceptance range limit (reference 6.18).(2) Gamma Emitters in Water, Sample ID QUIK 122111A, Reference Date 10/4/2010 Sample ID QUIK 12211 lA originated as an. evaluation sample for Sample ID RAD-87's low Cs-137 result. The reported Zn-65 result for QUIK 122111A was above the acceptance range limit (reference 6.18)Section 5 -Page 13 TABLE 5.0-D 2011 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102178 96.3 95.1 1.26 <+/-15% Pass 102194 99.4 95.1 4.50 <+/-15% Pass 102234 101.4 95.1 6.65 <+/-15% Pass 102162 99.7 95.1 4.88 <+/-15% Pass 102099 97.5 95.1 2.52 <+/-15% Pass Average Bias (B) 3.96 Standard Deviation (S) 2.10 Measure Performance IBI+S 6.07 <15% Pass 2nd Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102021 15.7 14.6 7.81 <+/-15% Pass 102026 15.6 14.6 6.85 <+/-15% Pass 102038 16.3 14.6 11.92 <+/-15% Pass 102057 14.4 14.6 -1.44 <+/-15% Pass 102213 15.1 14.6 3.15 <+/-15% Pass Average Bias (B) 5.66 Standard Deviation (S) 5.05 Measure Performance IBI+S 10.70 <15% Pass S 0 S 0 S S S 0 0 0 0 0 3rd Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102442 91.6 91.4 0.25 <+/-15% Pass 102257 94.9 91.4 3.85 <+/-15% Pass 102337 91.9 91.4 0.53 <+/-15% Pass 102221 95.1 91.4 4.00 <+/-15% Pass 102483 94.7 91.4 3.64 <+/-15% Pass Average Bias (B) 2.46 Standard Deviation (S) 1.89 Measure Performance 1BI+S 4.35 <15% Pass 4th Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 101285 72.0 70.0 2.84 <+/-15% Pass 100746 71.2 70.0 1.71 <+/-15% Pass 100087 70.7 70.0 0.97 <+/-15% Pass 101131 71.7 70.0 2.46 <+/-15% Pass 101356 72.5 70.0 3.59 <+/-15% Pass Average Bias (B) 2.31 Standard Deviation (S) 1.01 Measure Performance

[BI+S 3.32 <15% Pass S S 0 S S S 0 S S Section 5 -Page 14 5 S S Internal Crosscheck (Duke Energy)0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 1st Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102104 33.3 34.0 -2.15 <+/-15% Pass 102316 32.7 34.0 -3.85 <+/-15% Pass 102325 32.3 34.0 -5.12 <+/- 15% Pass 102434 32.8 34.0 -3.44 <+/-15% Pass 102009 33.6 34.0 -1.26 <+/-15% Pass 102149 32.3 34.0 -4.97 <+/-15% Pass 102419 31.8 34.0 -6.44 <+/-15% Pass 102160 34.8 34.0 2.47 <+/-15% Pass 102502 32.5 34.0 -4.38 <+/-15% Pass 102496 31.3 34.0 -7.88 <+/-15% Pass Average Bias (B) -3.70 Standard Deviation (S) 2.90 Measure Performance IBI+S 6.60 <15% Pass 2nd Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 100104 35.6 35.0 1.71 <+/-15% Pass 100054 34.3 35.0 -2.00 <+/-15% Pass 102410 34.4 35.0 -1.71 <+/-15% Pass 102363 34.6 35.0 -1.09 <+/-15% Pass 100816 34.2 35.0 -2.20 <+/-15% Pass 101311 32.6 35.0 -6.86 <+/-15% Pass 100432 36.1 35.0 3.03 <+/-15% Pass 100065 33.2 35.0 -5.29 <+/-15% Pass 100103 33.4 35.0 -4.54 <+/-15% Pass 100097 35.1 35.0 0.23 <+/-15% Pass Average Bias (B) -1.87 Standard Deviation (S) 3.09 Measure Performance IBI+S 4.96 <15% Pass I I 3rd Quarter 2011 TLD Reported Delivered Number (mR) (mR)102015 34.1 34.0 102468 33.4 34.0 102008 33.0 34.0 102496 31.2 34.0 102160 33.2 34.0 102156 33.6 34.0 102064 32.9 34.0 102419 32.4 34.0 102498 33.0 34.0 102340 32.9 34.0 Average Bias (B)Standard Deviation (S)Measure Performance IBI+S Bias Pass/Fail (% diff) Criteria Pass/Fail 0.35 <+/-15% Pass-1.91 <+/-15% Pass-3.03 <+/-15% Pass-8.21 <+/-15% Pass-2.32 <+/-15% Pass-1.26 <+/-15% Pass-3.32 <+/-15% Pass-4.79 <+/-15% Pass-3.06 <+/-15% Pass-3.29 <+/-15% Pass-3.09 2.27 5.35 <15% Pass 4th Quarter 2011 TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102005 38.8 40.0 -3.03 <+/-15% Pass 101364 39.2 40.0 -1.98 <+/-15% Pass 102164 37.5 40.0 -6.15 <+/-15% Pass 102163 38.2 40.0 -4.43 <+/-15% Pass 101252 37.6 40.0 -6.05 <+/-15% Pass 102104 38.5 40.0 -3.83 <+/-15% Pass 101297 38.0 40.0 -4.98 <+/-15% Pass 102178 39.0 40.0 -2.50 <+/-15% Pass 101305 38.3 40.0 -4.18 <+/-15% Pass 102243 37.9 40.0 -5.38 <+/-15% Pass Average Bias (B) -4.25 Standard Deviation (S) 1.44 Measure Performance IBI+S 5.68 <15% Pass Section 5 -Page 15 0 0* 6.1 McGuire Selected License Commitment Manual 6.2 McGuire Technical Specifications 0 6.3 McGuire Updated Final Safety Analysis Report 6.4 McGuire Offsite Dose Calculation Manual 6.5 McGuire Annual Radiological Environmental Operating Report 1979 -2010 6.6 McGuire Annual Radioactive Effluent Release Report 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 1OCFR50, 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 Radiological Effluents Controls INOS Audit 10-15(INOS)(REC)(MNS) 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 6.14 NRC Integrated Inspection Report (50-369/2011004, 50-370/2011004) 6 6.15 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-04-00134 6.16 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-12-00354 0 6.17 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-12-00015

• 6.18 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, G-1 1-01830 0*6.19 Problem Investigation Program Database, V 3.4.3, Duke Energy Company, M-11-05058 6.20 Nuclear System Directive (NSD) 701, Records Management 0 O ~Section 6 -Page 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX A ENVIRONMENTAL SAMPLING&ANALYSIS PROCEDURES Appendix A -Page 1 0 APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments.

Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.Environmental sampling and analyses were performed by EnRad Laboratories, Dosimetry and Records, and Fisheries and Aquatic Ecology.This appendix describes the environmental sampling frequencies and analysis procedures by media type.S I. CHANGE OF SAMPLING PROCEDURES TLD Location 191 (Special Interest) description updated (reference 6.19).0 H. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software.

Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy.

Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.0 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.

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.

0 0 0 0 Appendix A -Page 2 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 S 0 0 0 0 0 0 Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Tennelec XLB Series 5 gas-flow proportional counters.

Samples are batch processed with a blank to ensure sample contamination has not occurred.Ill. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2011.IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers.

Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge 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 gioss beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.Location 102 Location 103 Location 120 Location 121 Location 125 Location 133 Location 195 Amity Church Road (9.89 mi. WNW)Cottonwood (4.20 mi. NE)Site Boundary (0.46 mi. NNE)Site Boundary (0.47 mi. NE)Site Boundary (0.38 mi. SW)Cornelius (6.23 mi. ENE)Fishing Access Road (0.19 mi. N)A.2 DRINKING WATER Monthly composite samples were collected.

A gross beta and gamma analysis was performed on monthly composites.

Tritium analysis was performed on the quarterly composites.

The composites were collected monthly from the locations listed below.Location 101 Location 119 Location 132 Location 136 Location 194 North Mecklenburg Water Treatment Facility (3.31 mi E)Mt. Holly Municipal Water Supply (7.40 mi. SSW)Charlotte Municipal Water Supply (11.1 mi. SSE)Mooresville Municipal Water Supply (12.7 mi. NNE)East Lincoln County Water Supply (6.73 mi. NNW)Appendix A -Page 3 A.3 SURFACE WATER Monthly composite samples were collected.

A gamma analysis was performed on the monthly composites.

Tritium analysis was performed on the quarterly composites sample. The composites were collected monthly from the locations listed below.Location 128 Location 131 Location 135 Discharge Canal Bridge (0.45 mi. NE)Cowans Ford Dam (0.64 mi. WNW)Plant Marshall Intake Canal (11.9 mi. N)A.4 MILK Biweekly grab samples were collected at one location.

A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the location listed below.Location 141= Lynch Dairy -Cows (14.8 mi. WNW)A.5 BROADLEAF VEGETATION Monthly samples were collected as available and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.Location 102 Location 120 Location 125 Location 193 Amity Church Road (9.89 mi. WNW)Site Boundary (0.46 mi. NNE)Site Boundary (0.38 mi. SW)Site Boundary (0.19 mi. N)0 0 S 0 0 S 0 S S 0 0 0 0 S S 0 0 0 0 0 0 A.6 FOOD PRODUCTS Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the location listed below.Location 188= 5 mile radius Gardens (2.79 mi NNE)A.7 FISH Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions.

The samples were collected from the locations listed below.Location 129 Location 137 Discharge Canal Entrance to Lake Norman (0.51 mi. ENE)Pinnacle Access Area (12.0 mi. N)Appendix A -Page 4 0 0 0*A.8 SHORELINE SEDIMENT 0 Semiannual samples were collected and a gamma analysis was performed on each*following the drying and removal of rocks and clams. The samples were collected*from the locations listed below.*Location 129 = Discharge Canal Entrance to Lake Norman (0.51 mi. ENE)*Location 130 = Highway 73 Bridge Downstream (0.52 mi. SW)*Location 137 = Pinnacle Access Area (12.0 mi. N)0 A.9 DIRECT GAMMA RADIATION (TLD)Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations.

• A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.* An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locations in the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March, 1991.'0* An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8*kilometer range.* The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and control locations.

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

• The Nearest Residence* The Nearest Garden greater than 50 square meters or 500 square feet* The Nearest Milk-giving Animal (cow, goat, etc.)*The census was conducted during the growing season on 5/20/2011.

Results are*shown in Table 3.10. No changes were made to the sampling procedures during 2011*as a result of the 2011 census.In the environmental program, the air deposition parameters (D/Q) are used to 0determine air, broadleaf vegetation and milk sampling locations.

McGuire's sectors*with the three highest values did not change in 2011.A 0 0 0* Appendix A -Page 5 0 V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The McGuire site centerline used for GPS measurements was referenced from the McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1, Site Location.

Waypoint coordinates used for MNS GPS measurements were latitude 35°-25'-59"N and longitude 80'-56'-55"W.

Maps and tables were generated using North American Datum (NAD) 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement.

GPS field measurements were taken as close as possible to the item of interest.

Distances for the locations are displayed using three significant figures.Appendix A -Page 6 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 S S S S S 0 0 S S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2011 Appendix B -Page 1 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 Medium or Type and Location with Highest No.of Non-Total Lower All Indicator Locat w est Control Routine Sampled Number Detection Locations Name,Location Report of Distance, Direction Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Air Particulate 102 (9.89 mni WNW)(pCi/m3)BETA 364 1.OOE-02 1.90E-2 (312/312) 195 1.99E-2 (52/52) 2.00E-2 (52/52) 0 3.94E-3 -3.53E-2 (0.19 mi N) 1.06E-2 -3.53E-2 1.08E-2 -3.38E-2 CS-134 364 5.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00(0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 364 6.OOE-02 6.26E-3 (4/312) 120 7.06E-3 (1/52) 0.00(0/52) 0 3.66E-3 -1.02E-2 (0.46 mi NNE) 7.06E-3 -7.06E-3 0.00 -0.00 1-131 364 7.00E-02 1.55E-2 (18(312) 133 2.08E-2 (3/52) 1.54E-2 (3/52) 0 5.27E-3 -3.06E-2 (6.23 mi ENE) 1.03E-2 -3.06E-2 1.12E-2 -1.86E-2 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 1:44 PM Appendix B -Page 2 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 Type and iNo. of Non Meimo yead Lower Location with HighestNoofon Medium Total Lof All Indicator Local Mean Control Routine Mediumao Limit of Pathway Number Detection LocationsDistanc, Direction Location Report of , Meas.Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (LLD) Range !Code Range Range Air Radioiodine 102 (9.89 mi WNW)(pCi/m3)CS-134 364 5.OOE-02 0.00 (0/312) 0.00(0/52) 0.00(0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 364 6.OOE-02 0.00 (0/312) 0.00 (0/52) 0.00(0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 364 7.00E-02 5.63E-2 (24/312) 120 6.OOE-2 (4/52) 5.46E-2 (4/52) 0 1.18E-2 -1.05E-1 (0.46 mi NNE) 1.18E-2 -1.05E-1 1.36E-2 -9.57E-2 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 2:02 PM Appendix B -Page 3 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Drinking Water 136 (pCi/liter)

(12.7 mi NNE)BALA-140 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 BETA 65 4 1.71(52/52) 194 1.77 (13/13) 1.75 (13/13) 0 0.79 -2.81 (6.73 mi NNW) 0.79 -2.49 0.69 -3.33 CO-58 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00- 0.00 CS-134 65 15 0.00 (0/52) 0.00 (0/13) 0.00(0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 65 18 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 65 30 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 H-3 20 2000 750 (13/16) 101 997(4/4) 0.00(0/0) 0 169-1360 (3.31 mi E) 705-1360 0.00-0.00 1-131 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 NB-95 65 15 0.00(0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00- 0.00 0.00- 0.00 ZN-65 65 30 0.00(0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZR-95 65 15 0.00 (0/52) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 0 0 0 S S 0 0 0 0 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@

2/23/2012 8:41 AM Appendix B -Page 4 S 0 0 0 0 0 0 0 0 0 S 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location, Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Surface Water 135 (pCi/liter)

(11.9 mi N)BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 39 18 0.00(0/26) 0.00(0/13) 0.00(0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 H-3 12 2000 898 (8/8) 128 1191 (4/4) 294 (1/4) 0 418- 1990 (0.45 mi NE) 841-1990 294-294 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@

2/23/2012 8:46 AM Appendix B -Page 5 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Milk NO INDICATOR 141 (pCi/liter)

LOCATION (14.8 mi WNW)BALA-140 26 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 26 15 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 26 18 0.00 (0/26) 0.00 (0/26) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00- 0.00 1-131 26 15 0.00 (0/26) 0.00 (0/26) 9.49 (2/26) 0 0.00 -0.00 0.00- 0.00 8.98 -10.0 LLI-131 26 1 0.00 (0/26) 0.00 (0/26) 4.80 (3/26) 0 0.00 -0.00 0.00 -0.00 0.54 -9.23 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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

@ 2/23/2012 8:50 AM Appendix B -Page 6 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

McGulre Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone All IndicatorCotl Ruin Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (LD) Range Code Range Range Broadleaf 102 (9.89 mi WNW)Vegetation (pCi/kg-wet)

CS-134 48 60 0.00 (0/36) 0.00(0/12) 0.00 (0/12) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 48 80 22.9 (1/36) 125 22.9 (1/12) 0.00 (0/12) 0 22.9 -22.9 (0.38 mi SW) 22.9 -22.9 0.00 -0.00 1-131 48 60 231 (3/36) 120 316(1/12) 168(1/12) 0 97.9-316 (0.46 mi NNE) 316-316 168-168 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

@ 2/23/2012 8:58 AM Appendix B -Page 7 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (LLD) Range Code Range Range Food Products NO CONTROL (pCi/kg-wet)

LOCATION CS-134 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00- 0.00 0.00 -0.00 0.00 -0.00 CS-137 12 80 30.6(1/12) 188 30.6(1/12) 0.00(0/0) 0 30.6 -30.6 (2.79 mi NNE) 30.6 -30.6 0.00 -0.00 1-131 12 60 142 (1/12) 188 142 (1/12) 0.00 (0/0) 0 142- 142 (2.79 mi NNE) 142 -142 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

@ 2/23/2012 9:07 AM Appendix B -Page 8 0 0 S 0 S 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest Pathway Number Limit of All Indicator Annual Mean Loction Reort Sampled of Detection Locations Name, Distance, Direction Meas.Meas.Unit of Analyses (LD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Fish 137 (pCi/kg-wet)

(12.0 mi N)CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00(0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00- 0.00 0.00 -0.00 0.00 -0.00 CS-137 12 150 22.3 (1/6) 129 22.3 (1/6) 0.00(0/6) 0 22.3 -22.3 (0.51 mi ENE) 22.3- 22.3 0.00- 0.00 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00- 0.00 0.00 -0.00 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/23/2012 9:20 AM Appendix B -Page 9 Environmental Radiological Monitoring Program Summary Facility:

McGulre Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Leaor Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Shoreline 137 Sediment (12.0 mi N)(pCi/kg-dry)

MN-54 6 0 0.00(0/4) 0.00 (0/2) 0.00 (0/2)0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-58 6 0 0.00(0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 -0.00 0.00-0.00 0.00 -0.00 CO-60 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 6 150 0.00(0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 6 180 102(2/4) 130 102 (2/2) 0.00 (0/2) 0 43.6- 161 (0.52 mi SW) 43.6- 161 0.00-0.00 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated

@ 2/23/2012 9:31 AM Appendix B -Page 10 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 Type and Location with Highest No. of Non-Medium or Total Lower All Indicator Control Routine Limit of Annual Mean Pathway Sampled Number Dtt Locations Name,Location Report ofetinNae Distance, DirectionMes of Meas.Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Performed Range Code Range Range Direct Radiation 175 TLD (15.5 mi WNW)(mR/standard quarter)163 0.OOE+00 17.2 (159/159) 180 26.5 (4/4) 23.5 (4/4) 0 9.00 -36.0 (12.7 mi NNE) 25.0 -29.0 22.0- 25.0 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

@ 2/23/2012 11:03 AM Appendix B -Page 11 MCGUIRE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF 2011 RESULTS EXCLUDING RADIOACTIVITY ATTRIBUTABLE TO FUKUSHIMA DAIICHI S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S Appendix B -Page 12 Environmental Radiological Monitoring Program Summary *Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Medium or Type and Lower Location with Highest No.of Non-Ptwy Total Limiter All Indicator AnaMenControl Routine Pathway Number Alli ofAnnual MeanLcainRpr Sampled Totl Detection Locations NamrDIstance, Direction Location Reportas.of Detetio Unit of Analyses Mean (Fractiqnj.

ý- ittatibn I Mean (Fraction)

Mean (Fraction)

Measurement Performed (LLD) Range Code Range Range Air Particulate 102 (9.89 mi WNW)(pCi/m3)BETA 336 L.00E-02 1.85E-2 (288/288) 195 1.95E-2 (48/48) 1.94E-2 (48/48) 0 3.94E-3 -3.40E-2 (0.19 mi N) 1.06E-2 -3.40E-2 1.08E-2 -2.90E-2 CS-134 336 5.OOE-02 0.00 (0/288) 0.00 (0/48) 0.00 (0/48) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 336 6.OOE-02 0.00 (0/2&8) 0 .,L,0.00 (0/48)i 0.00(0/48) 0'0,00 o"O.O 0.00 000,, 0.00-0.00 1-131 336 7.00E-02 0.00 (0/288), ...0.00 (0/48) 0.00(0/48) 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

• Summary does not include samples collected during Fukushima Daiichi fallout period 3/14/2011

-4/11/2011 Report Generated

@ 4/23/2012 9:04 AM Appendix B -Page 13 Environmental Radiological Monitoring Program Summary *Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 Medium or Type and L L w No. of Non.Total Lower All Indicator Location with Highest Control Routine Mediumy or uTota Limit of LctosAnnual Mean LoainReport Sampled Number Detection Locations Name, Distance, Direction Location Meas.Sampledso Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Air Radioiodine 102 (9.89 mi WNW)(pCi/m3)CS-134 336 5.OOE-02 0.00 (0/288) 0.00 (0/48) 0.00 (0/48) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 336 6.OOE-02 0.00 (0/288) 0.00 (0/48) 0.00 (0/48) 0 0.00 -0.00 0.00-0.00 0.00 -0.00 1-131 336 7.00E-02 0.00 (0/288) 0.00 (0/48) 0.00 (0/48) 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

• Summary does not include samples collected during Fukushima Daiichi fallout period 3/14/2011

-4/11/2011 Report Generated

@ 4/2312012 9:05 AM Appendix B -Page 14 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 Environmental Radiological Monitoring Program Summary *Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 , No. of Non-Medium or Type and Total Lower All Indicator Location with Highest on Pathway Number Limit of Lci wiAthual Mean Control Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses Mean (Fraction)

Location Meani (Fracton).

Mean (Fraction)

Measurement Performed Range Code Range Range Milk NO INDICATOR 141 (pCi/liter)

LOCATION (14.8 mi WNW)BALA-140 23 15 0.00 (0/0) 0.00 (0/0) 0.00 (0123) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 23 15 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 CS-137 23 18 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 1-131 23 15 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 LLI-131 23 1 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 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

• Summary does not include samples collected during Fukushima Daiichi fallout period 3/28/2011

-4/25/2011 Report Generated

@ 4/23/2012 9:05 AM Appendix B -Page 15 Environmental Radiological Monitoring Program Summary *Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Broadleaf 102 (9.89 mi WNW)Vegetation (pCi/kg-wet)

CS-134 44 60 0.00 (0/33) 0.00 (0/11) 0.00(0/11) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 44 80 0.00(0/33) 0.00(0/11) 0.00(0/11) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 44 60 0.00(0/33) 0.00(0/11) 0.00 (0/11) 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

• Summary does not include samples collected during Fukushima Daiichi fallout period 4/4/2011.Report Generated

@ 4/23/2012 9:06 AM Appendix B -Page 16 S S S S S S S S S S S S S S S S S S S S S S 0 S S S S S 0 S S S S S S S S S 0 0 S S S Environmental Radiological Monitoring Program Summary *Facility:

McGuire Nuclear Station Location:

Mecklenburg County, North Carolina Docket No. 50-369,370 Report Period: 01-JAN-2011 to 31-DEC-2011 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet)

LOCATION CS-134 11 60 0.00(0/11) 0.00(0/11) 0.00(0/0) 0 0.00 -0.00 0.00 -0.00 0.00- 0.00 CS- 137 11 80 0.00(0/11) 0.00 (0/11) 0.00(0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 11 60 0.00(0/11) 0.00(0/11) 0.00(0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 0 0 0 0 0 0 0 0 0 0 0 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

• Summary does not include samples collected during Fukushima Daiichi fallout period 4/4/2011.Report Generated

@ 4/23/2012 9:06 AM Appendix B -Page 17

SUMMARY

OF RADIOACTIVITY ATTRIBUTABLE TO FUKUSHIMA DAIICHI DETECTED IN ENVIRONMENTAL MEDIA AT DUKE ENERGY FACILITIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Appendix B -Page 18 Fukushima Daiichi Radioactivity Detected in Environmental Media (2011)0 0 0 S 0 0 0 0 0 Airborne Particulate Annual Concentration with Annual Concentration without Fukushima Daiichi (pCi/m 3) Fukushima Daiichi (pCi/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 (pCCi/m 3 Fukushirma Daiichi (pCi/mr 3)Station Analysis Ijidicator,'

Control' Indicator Control 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 Oconee 1-131 5.05E-2 '. 4.13E-2 0.00 0.00 Annual Concentration with Annual Concentration without Th .. .l ukDsa ichi jv' "Fukushima Dalichi (pCi/l)Station Analysis 1 'Ihdicator Control Indicator Contr6l 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 Vegetation Annual Concentration with Annual Concentration without Fukushima Daiichi (pCi/kg) Fukushima Daiichi (pCi/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 (pCi/kg) Fukushima Daiichi (pCi/kg)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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Appendix B -Page 19 e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX C SAMPLING DEVIATIONS

&UNAVAILABLE ANALYSES Appendix C -Page 1 I APPENDIX C MCGUIRE NUCLEAR STATION SAMPLING DEVIATIONS

& UNAVAILABLE ANALYSES DEVIATION

& UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Tom Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Corrective Location Collection Dates Collection Dates Code Description Action Identity 120 Power to equipment 121 interrupted for about 1.25 195 9/26-10/3/2011 9/26 -10/3/2011 PI hours due to site overload.

G-11-01461 Power to sampling equipment interrupted due to blown fuse. Fuse replaced and normal sampling 120 10/31 -1117/2011 10/31 -11/4/2011 BF resumed 11/7/2011.

G-11-01638 Power to equipment was 11/7 -11/14/2011 11/7 -11/14/2011 interrupted due to blown 133 11/14- 11/21/2011 11/14- 11/21/2011 PO transformer at substation.

G-11-01674 Drinking Water Scheduled Actual Corrective Location Collection Dates Collection Dates Code Description Action Identity 101 119 Collection rescheduled due to 132 inclement weather creating 136 potentially unsafe site access 194 12/13- 1/10/2011 12/13- 1/12/2011 IW conditions.

G-11-00043 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Appendix C -Page 2 S S 0 0 0 0 S 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 0 0 Surface Water Scheduled Actual Corrective Location Collection Dates Collection Dates Code Description Action Identity Collection rescheduled due to inclement weather 128 creating potentially unsafe.131 12/13 -1/10/2011 12/13 -1/12/2011 1W site access conditions.

G-11-00043

-Power outage at beginning o"ollection period. Work request 85922 written.Power restored, normal sampling resumed 12/20/2010.

Collection rescheduled due to inclement weather.creatirng potentially unsafe -G-10-01578 135 12/13- 1/10/2011 12/20- 1/13/2011 PO, IW site access conditions.

G-11-00043 Estimated five day power outage during composite period. Work request 89483.written.'

Outage attributed to wet 6sprey (protected nest causing blown fuse. Power delivery system reconfigured to bypass nesting area.Normal sampling resumed 135 4/4 -5/2/2011 4/4 -5/2/2011 PO 4/20/2011.

G- 11-00740 C.2 UNAVAILABLE ANALYSES TLD.. Scheduled

... .. ...... Corrective Location Collection Dates Code Description Action Identity I 153 3/17 -6/16/2011 VN TLD missing. 3' uarter TLD placed. Not Applicable Appendix C -Page 3 S 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2011 Radiological Environmental Monitoring Program Appendix D -Page 1 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes sample analysis reports and supportive data generated from each sample medium. Appendix E is located separately from this report and is permanently archived in the Nuclear Electronic Document Library (NEDL) as described in reference 6.20.Appendix E -Page 1 e 0 S S S 0 S S S S S S 0 S 0 S S 0 0 S 0 0 S 0 S 0 S S S S S S APPENDIX F ERRATA TO PREVIOUS REPORTS Appendix F -Page 1 APPENDIX F 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ERRATA TO THE 2011 AREOR There are no errata to be appended to the 2011 AREOR.Appendix F -Page 2