ML031330779
| ML031330779 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/31/2002 |
| From: | Duke Power Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031330779 (36) | |
Text
5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.
5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad Laboratories is located in Huntersville, North Carolina, at Duke Power Company's Environmental Center.
5.3 DOSIMETRY ANALYSIS Duke Power Company's Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.
5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.
5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.
5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.
Section - Page I
5.5 DUKE POWI'ER INTERCOMPARISON PROGRAMI EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2002. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2002 is documented in Table 5.0-A.
5.6 DUKE POWI'ER AUDITS The Oconee Radiation Protection Section was audited by the Quality Assurance Group in February of 2002. There were no findings as a result of this 2002 audit.
EnRad Laboratories was audited by the Quality Assurance Group in June of 2002.
Laboratory practices and procedures were reviewed. No significant problems were identified as a result of this 2002 audit.
5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Oconee Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in November of 2002 (reference 6.12). The 2001 AREOR was reviewed. Air, broadleaf vegetation, and milk collections were inspected. No findings of significance were noted in the report. EnRad Laboratories was not audited by the NRC in 2002.
5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. Water, milk, vegetation, sediment, and fish samples collected by EnRad Laboratories are routinely split with DHEC for intercomparison analysis. DHEC collects air samples near two of the locations sampled for air by ONS. Results of the analyses performed on split and duplicate samples are sent to DHEC.
5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 NUCLEAR TECH1NOLOGY SERV1CES NTERCOM1\'ARISON 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 Section 5 - Page 2
unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.
5.9.2 STATE OF NORTI-H CAROINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2002 is documented in Table 5.0-B.
5.9.3 INTERNAI, CROSSCHECK( (DUKE POWVER)
Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered intemally 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 Intemal Cross Check (Duke Power) Result is documented in Table 5.0-B.
Section 5 - Page 3
TABLE 5.0-A DUKE POWIIER COMPANY INTERLABORATORY COMPARISON PROGRAM 2002 CROSS-CIIECK RESULTS FOR ENRAD LA1BORATORIES 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 "1 Pass" indicates that one analysis of the cross-check was performed.
Footnote explanations are included following this data table.
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Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiIl pCi/l pCi/l 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 E5 1.27 E5 1.25 E5 3 Pass Mn-54 0.82- 1.45 E5 1.09 E5 1.13 E5 3 Pass Fe-59 4.17 - 7.40 E4 5.56 E4 5.78 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.68 E4 3 Pass Zn-65 0.80- 1.43 ES 1.07 E5 1.12 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.36 E4 3 Pass Cs-137 0.97 - 1.72 ES 1.29 E5 1.24 E5 3 Pass Ce-139 0.00 - 0.100 EQ 0.00 EQ 1.82 E3 3 Pass"'
Ce-141 1.17-2.07 E5 1.56 E5 1.55 E5 3 Pass 5/14/2002 Q022GWR Cr-51 6.77- 12.01 E3 9.03 E3 9.32 E3 3 Pass Mn-54 1.38 - 2.45 E3 1.84 E3 1.98 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.48 E3 3 Pass Fe-59 1.75 - 3.10 E3 2.33 E3 2.44 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.38 E3 3 Pass Zn-65 2.66 - 4.71 E3 3.54 E3 3.73 E3 3 Pass Cs-134 1.68 - 2.98 E3 2.24 E3 2.10 E3 3 Pass Cs-137 1.24 - 2.20 E3 1.65 E3 1.60 E3 3 Pass Ce-141 2.32-4.11 E3 3.09 E3 3.13 E3 3 Pass 8/1612002 Q023GWS Cr-51 1.58 -2.80 ES 2.10 E5 2.10 E5 3 Pass Mn-54 5.73 - 10.16 E4 7.64 E4 8.16 E4 3 Pass Co-58 4.47 - 7.93 E4 5.96 E4 6.20 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.85 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.20 E4 3 Pass Zn-65 7.16- 12.70 E4 9.55 E4 1.03 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.78 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.76 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 E5 1.38 E5 3 Pass Section 5 -Page 4
Gamma in IVater 3.5 liters continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCill pCi/I pCi/I 11/19/2002 Q024GVR Cr-51 2.08 - 3.70 E4 2.78 E4 3.09 E4 3 Pass Mn-54 5.96- 10.56 E3 7.94 E3 9.12 E3 3 Pass Co-57 0.00 - 0.00 EQ 0.00 EQ 6.65 El 3 Pass"'
Co-58 6.54- 11.60 E3 8.72 E3 9.79 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 5.95 E3 3 Pass Co-60 6.68 - 11.85 E3 8.91 E3 1.02 E4 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.22 E4 3 Pass Cs-134 4.04 -7.16 E3 5.38 E3 5.46 E3 3 Pass Cs-137 0.89 - 1.58 E4 1.19 E4 1.27 E4 3 Pass Ce-141 6.32- 11.21 E3 8.43 E3 9.56 E3 3 Pass Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiA pCi/l pCi/l 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 E5 1.27 E5 1.28 E5 3 Pass Mn-54 0.82- 1.45 E5 1.09 E5 1.16 E5 3 Pass Fe-59 4.17 -7.40 E4 5.56 E4 5.85 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.70 E4 3 Pass Zn-65 0.80- 1.43 E5 1.07 E5 1.13 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.51 E4 3 Pass Cs-137 0.97- 1.72 E5 1.29 ES 1.27 E5 3 Pass Ce-139 0.00 - 0.00 EQ 0.00 E0 1.84 E3 3 Pass"'
Ce-141 1.17-2.07 E5 1.56 E5 1.60 E5 3 Pass 5/14/2002 Q022GWR Cr-51 6.77- 12.01 E3 9.03 E3 9.07 E3 3 Pass Mn-54 1.38 - 2.45 E3 1.84 E3 2.00 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.43 E3 3 Pass Fe-59 1.75 - 3.10 E3 2.33 E3 2.57 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.44 E3 3 Pass Zn-65 2.66 - 4.71 E3 3.54 E3 3.86 E3 3 Pass Cs-134 1.68 -2.98 E3 2.24 E3 1.98 E3 3 Pass Cs-137 1.24 - 2.20 E3 1.65 E3 1.57 E3 3 Pass
.________ _________ Ce-141 2.32-4.11 E3 3.09 E3 3.13 E3 3 Pass 8/16/2002 Q023GWS Cr-51 1.58 -2.80 E5 2.10 E5 2.11 E5 3 Pass Mn-54 5.73 - 10.16 E4 7.64 E4 8.09 E4 3 Pass Co-58 4.47 -7.93 E4 5.96 E4 6.17 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.67 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.02 E4 3 Pass Zn-65 7.16- 12.70 E4 9.55 E4 1.01 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.82 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.76 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 E5 1.37 E5 3 Pass Section 5 -Page 5
Gamma in ater 1.0 liter continued Reference Sample ID. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi_ pCi/l pCi/l 11/19/2002 Q024GWR Cr-51 2.08 -3.70 E4 2.78 E4 3.15 E4 3 Pass Mn-54 5.96- 10.56 E3 7.94 E3 9.12 E3 3 Pass Co-57 0.00 - 0.00 E0 0.00 EQ 3.87 El 3 Pass"'
Co-58 6.54- 11.60 E3 8.72 E3 9.71 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 6.07 E3 3 Pass Co-60 6.68- 11.85 E3 8.91 E3 1.01 E4 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.22 E4 3 Pass Cs-134 4.04-7.16 E3 5.38 E3 5.24 E3 3 Pass Cs-137 0.89 - 1.58 E4 1.19 E4 1.29 E4 3 Pass Ce-141 6.32 - 11.21 E3 8.43 E3 9.53 E3 3 Pass Gamma in WVater 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/l pCi/l 3/15/2002 Q021GWSL Cr-51 0.95 - 1.69 E5 1.27 E5 1.25 E5 3 Pass Mn-54 0.82- 1.45 E5 1.09 E5 1.14 E5 3 Pass Fe-59 4.17 -7.40 E4 5.56 E4 5.91 E4 3 Pass Co-60 5.75 - 10.20 E4 7.67 E4 7.65 E4 3 Pass Zn-65 0.80- 1.43 E5 1.07 E5 1.14 E5 3 Pass Cs-134 4.46-7.91 E4 5.95 E4 5.06 E4 3 Pass Cs-137 0.97 - 1.72 E5 1.29 E5 1.23 E5 3 Pass Ce-139 0.00 - 0.00 Eo 0.00 EO 1.76 E3 3 Pass")
Ce-141 1.17 -2.07 E5 1.56 E5 1.54 E5 3 Pass 5/14/2002 Q022GWR Cr-51 6.77- 12.01 E3 9.03 E3 9.29 E3 3 Pass Mn-54 1.38 - 2.45 E3 1.84 E3 1.96 E3 3 Pass Co-58 1.82 - 3.24 E3 2.43 E3 2.47 E3 3 Pass Fe-59 1.75 -3.10 E3 2.33 E3 2.51 E3 3 Pass Co-60 1.71 - 3.04 E3 2.28 E3 2.40 E3 3 Pass Zn-65 2.66 - 4.71 E3 3.54 E3 3.76 E3 3 Pass Cs-134 1.68 - 2.98 E3 2.24 E3 2.03 E3 3 Pass Cs-137 1.24 - 2.20 E3 1.65 E3 1.62 E3 3 Pass Ce-141 2.32-4.11 E3 3.09 E3 3.11 E3 3 Pass 8/16/2002 Q023GWS Cr-51 1.58-2.80 E5 2.10 E5 2.10 E5 3 Pass Mn-54 5.73 - 10.16 E4 7.64 E4 8.06 E4 3 Pass Co-58 4.47 - 7.93 E4 5.96 E4 6.02 E4 3 Pass Fe-59 4.76 - 8.44 E4 6.34 E4 6.77 E4 3 Pass Co-60 5.29 - 9.38 E4 7.06 E4 7.09 E4 3 Pass Zn-65 7.16 - 12.70 E4 9.55 E4 1.03 E5 3 Pass Cs-134 4.79 - 8.49 E4 6.39 E4 5.48 E4 3 Pass Cs-137 4.48 - 7.95 E4 5.98 E4 5.65 E4 3 Pass Ce-141 1.00- 1.78 E5 1.34 E5 1.34 E5 3 Pass Section 5 -Page 6
Gamma in WVater 0.5 liter continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/i pCi/I pCi/i 11/19/2002 Q024GWR Cr-51 2.08 -3.70 E4 2.78 E4 3.10 E4 3 Pass Mn-54 5.96 - 10.56 E3 7.94 E3 8.98 E3 3 Pass Co-57 0.00 - 0.00 EQ 0.00 EQ 6.61 El 3 Pass"'
Co-58 6.54 - 11.60 E3 8.72 E3 9.64 E3 3 Pass Fe-59 3.72 - 6.60 E3 4.96 E3 5.92 E3 3 Pass Co-60 6.68- 11.85 E3 8.91 E3 9.97 E3 3 Pass Zn-65 0.75 - 1.33 E4 1.00 E4 1.19 E4 3 Pass Cs-134 4.04 -7.16 E3 5.38 E3 5.08 E3 3 Pass Cs-137 0.89- 1.58 E4 1.19 E4 1.24 E4 3 Pass Ce-141 6.32 - 11.21 E3 8.43 E3 9.15 E3 3 Pass Gamma in Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/total pCi/total pCi/total 6/13/2002 E3197-37 Cr-51 1.05 -2.42 E2 1.59 E2 1.79 E2 3 Pass Mn-54 4.80-8.51 El 6.40 El 6.72 El 3 Pass Co-58 5.03 - 8.91 El 6.70 El 6.78 El 3 Pass Fe-59 3.89 -7.51 El 5.40 El 6.46 El 1/3 High 2 ,
Co-60 6.30- 11.17 El 8.40 El 8.70 El 3 Pass Zn-65 0.91 - 1.61 E2 1.21 E2 1.30 E2 3 Pass Cs-134 6.08 - 10.77 E1 8.10 E1 7.99 E1 3 Pass Cs-137 4.58-8.11 E1 6.10 E1 5.73 El 3 Pass Ce-141 4.58-8.11 El 6.10 E1 6.84 El 3 Pass 12/5/2002 E3459-37 Cr-51 1.80 - 3.28 E2 2.43 E2 2.55 E2 3 Pass Mn-54 0.75 - 1.33 E2 1.00 E2 1.01 E2 3 Pass Co-58 7.35 - 13.03 El 9.80 El 9.61 El 3 Pass Fe-59 3.83 - 6.78 El 5.10 El 5.71 El 3 Pass Co-60 0.87- 1.54 E2 1.16 E2 1.19 E2 3 Pass Zn-65 0.95 - 1.68 E2 1.26 E2 1.28 E2 3 Pass Cs-134 5.25 -9.31 El 7.00 El 6.50 El 3 Pass Cs-137 1.16-2.06 E2 1.55 E2 1.45 E2 3 Pass Ce-141 5.85 - 10.37 El 7.80 El 8.05 El 3 Pass Iodine in WVater Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi/ pci/I 5/28/2002 Q022LIW1 I-131 1.38 -2.59 EQ 1.89 EQ 2.31 EO 3 Pass 5/28/2002 Q022LIW2 I-131 2.03 - 3.60 El 2.71 E 3.87 El 3/3 High 3 '
5/28/2002 Q022LIW3 1-131 3.33-5.91 E2 4.44 E2 4.72 E2 3 Pass Section 5 -Page 7
Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCil 1115/2002 Q024LIM1 I-131 2.80-4.97 E2 3.73 E2 3.52 E2 3 Pass 11/5/2002 Q024LIM2 I-131 0.00 -0.00 EQ 0.00 EO 0.00 E 3 Pass Iodine Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pci 3/8/2002 A15502-04 I-131 1.47-2.61 E5 1.96 E5 2.31 E5 3 Pass 6/13/2002 E3198-37 I-131 6.98- 12.37 El 9.30 El 10.7 E 3 Pass 8/9/2002 A16102-04 l I-131 1.89 - 3.35 E5 2.52 E5 2.95 E5 3 Pass 12/5/2002 E3460-37 l I-131 7.28 - 12.90 El 9.70 El 1.12 E2 3 Pass Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiAl pCi/l pCi/l 6/13/2002 E3199-37 Beta 2.10- 3.72 E2 2.80 E2 2.59 E2 3 Pass 6/13/2002 l E3258-37 Beta 2.10 - 3.72 E2 2.80 E2 2.63 E2 3 Pass Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pci pci pci 2/15/2002 A15504-04 Gross Beta 5.64 - 10.00 E3 7.52 E3 7.97 E3 3 Pass Section 5 - Page 8
Tritiuim in lVater Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/I 3/15/2002 Q021TWSL1 H-3 0.93 - 1.66 E4 1.25 E4 1.26 E4 3 Pass 3/15/2002 Q21TWSL21 H-3 0.00 -0.00 EQ 0.00 EQ 0.00 E0 l 3 Pass 5/14/2002 Q022TWR1 H-3 4.25 - 8.20 E2 5.90 E2 5.60 E2 3 Pass 5/14/2002 Q022TWR2 H-3 0.00 - 0.00 EO 0.00 EQ 0.00 EQ 3 Pass 5/14/2002 Q022TWR3 H-3 2.06 - 3.66 E3 2.75 E3 2.84 E3 3 Pass 8/15/2002 Q023TWSL1 H-3 0.00 - 0.00 EO 0.00 EO 0.00 EQ 3 Pass 8/15/2002 1Q023TWSL21 H-3 2.94 -5.21 E4 3.92 E4 3.37 E4 3 Pass 11/22/2002 Q024TWR1 H-3 0.00 - 0.00 EO 0.00 E 0.00 EQ 3 Pass 11/22/2002 Q024TWR2 H-3 1.65 -2.93 E3 2.20 E3 1.89 E3 3 Pass Section 5 -Page 9
Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q021GWSL, Reference Date 3/15/2002: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, Ce-139 was observed in cross-checks and was attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.
Gamma in Water, Sample ID Q024GWR, Reference Date 11/19/2002: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli Co-57 was observed in cross-checks and was attributed to a contaminant arriving with the source. The nuclide was determined to be present, but there was no reference activity applicable to the results.
(2) Gamma in Filter, Sample ID E3197-37, Reference Date 6/13/2002 Three results for Fe-59 [1099.2 keV] were reported, with one being above acceptance limit. Calibration verifications for detector 4 (SN: 35-P31076A) were evaluated and yielded acceptable results. General Office PIP G-02-00278 was written to record investigative actions.
(3) Iodine in Water, Sample ID Q022LIW2, Reference Date 5/28/2002 Three results were reported for this cross-check, all of which were above the cross-check acceptance limit. Investigation yielded the most likely cause for the high results was failure to shake resin dish prior to analysis. General Office PIP G-02-00254 was written to record investigative actions.
Section - Page 10
TABLE 5.0-B 2002 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Teclhnlolog) Services 1st Quarter 2002 2nd Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100141 88 88.1 0.11 <+/-15% Pass 100340 99 93.9 -5.15 <+/-15% Pass 100157 88 92.8 5.45 <+/-15% Pass 101179 99 97.5 -1.52 <+/-15% Pass 100215 88 91.1 3.52 <+/-15% Pass 100349 99 96.3 -2.73 <+1-15% Pass 100145 88 91.2 3.64 <+/-15% Pass 100397 99 98.9 -0.10 <+1-15% Pass 100463 88 90.7 3.07 <+/-15% Pass 100022 99 98.5 -0.51 <+/-15% Pass Average Bias (B) 3.16 Average Bias (B) -2.00 Standard Deviation (S) 1.93 Standard Deviation (S) 2.03 Measure Performance IBI+S 5.09 <15% Pass Measure Performance IBI+S 4.03 <15% Pass 3rd Quarter 2002 4th Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100601 66 64.0 -3.03 <+/-15% Pass 101275 70 63.5 -9.29 <+/-15% Pass 100841 66 65.1 -1.36 <+1-15% Pass 100478 70 64.2 -8.29 <+/-15% Pass 100868 66 65.3 -1.06 <+/-15% Pass 100503 70 63.1 -9.86 <+/-15% Pass 100880 66 68.2 3.33 <+/-15% Pass 101011 70 64.6 -7.71 <+1-15% Pass 100989 66 65.4 -0.91 <+/-15% Pass 100538 70 67.0 -4.29 <+1-15% Pass Average Bias (B) -0.61 Average Bias (B) -7.89 Standard Deviation (S) 2.36 Standard Deviation (S) 2.18 Measure Performance BI+S 2.97 <15% Pass Measure Performance IB1+S 10.06 <15% Pass State Or North Carolina, Division or Radiation Protection Spring 2002 Fall 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100008 90 80.8 -10.22 <+/-15% Pass 100777 151.6 127.3 -16.03 <+1-15% Fail 100030 90 83.1 -7.67 <+/-15% Pass 100704 151.6 127.9 -15.63 <+/-15% Fail 100050 90 81.3 -9.67 <+/-15% Pass 100740 151.6 130.9 -13.65 <+1-15% Pass 100064 90 84.6 -6.00 <+/-15% Pass 100680 151.6 132.4 -12.66 <+/-15% Pass 100117 90 82.6 -8.22 <+/-15% Pass 101020 151.6 123.7 -18.40 <+1-15% Fail 100166 90 81.1 -9.89 <+/-15% Pass 100747 151.6 131.3 -13.39 <+1-15% Pass 100208 90 79.9 -11.22 <+/-15% Pass 100759 151.6 130.6 -13.85 <+/-15% Pass 101122 90 82.5 -8.33 <+/-15% Pass 100103 151.6 128.6 -15.17 <+1-15% Fail Average Bias (B) -8.90 Average Bias (B) -14.85 Standard Deviation (S) 1.67 Standard Deviation (S) 1.85 Measure Performance Bl+S 10.57 <15% Pass Measure Performance IBI+S 16.70 <15% Fail ()
Section 5 - Page 11
Internial Crosscheck (I)ic Power) 1st Quarter 2002 2nd Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 101102 40 37.0 -7.50 <+/-15% Pass 100103 33 31.5 -4.55 <+/-15% Pass 100109 40 37.1 -7.25 <+/-15% Pass 100740 33 31.6 -4.24 c+/-15% Pass 101122 40 38.4 -4.00 <+/-15% Pass 100747 33 31.9 -3.33 <+1-15% Pass 100268 40 37.1 -7.25 <+/-15% Pass 100770 33 31.3 -5.15 <+1-15% Pass 100807 40 39.8 -0.50 <+/-15% Pass 100772 33 32.4 -1.82 <+1-15% Pass 100810 40 37.7 -5.75 <+1-15% Pass 101017 33 31.7 -3.94 <+/-15% Pass 100169 40 37.3 -6.75 <+/-15% Pass 101020 33 30.8 -6.67 <+1-15% Pass 100366 40 38.1 -4.75 <+/-15% Pass 101025 33 32.3 -2.12 <+/-15% Pass 100815 40 37.2 -7.00 <+/-15% Pass 101035 33 31.3 -5.15 <+1-15% Pass 100823 40 38.8 -3.00 <+/-15% Pass 101036 33 32.3 -2.12 <+/-15% Pass Average Bias (B) -5.38 Average Bias (B) -3.91 Standard Deviation (S) 2.31 Standard Deviation (S) 1.57 Measure Performance Bl+S 7.68 <15% Pass Measure Performance IBI+S 5.48 <15% Pass 3rd Quarter 2002 4th Quarter 2002 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100792 106 100.8 -4.91 <+/-15% Pass 100389 66 64.5 -2.27 <+/-15% Pass 101274 106 100.0 -5.66 <+/-15% Pass 101114 66 62.3 -5.61 <+/-15% Pass 100314 106 100.0 -5.66 <+/-15% Pass 100114 66 66.6 0.91 <+/-15% Pass 100460 106 100.9 -4.81 <+/-15% Pass 100649 66 63.0 -4.55 <+/-15% Pass 100101 106 101.9 -3.87 <+/-15% Pass 100469 66 65.2 -1.21 <+/-15% Pass 100783 106 101.8 -3.96 <+/-15% Pass 100763 66 62.0 -6.06 <+/-15% Pass 100760 106 100.8 -4.91 <+/-15% Pass 100304 66 62.8 -4.85 <+/-15% Pass 101349 106 98.1 -7.45 <+/-15% Pass 100068 66 67.2 1.82 <+/-15% Pass 100794 106 101.1 -4.62 <+/-15% Pass 100203 66 65.0 -1.52 <+/-15% Pass 100012 106 100.1 -5.57 <+/-15% Pass 100418 66 64.7 -1.97 <+/-15% Pass Average Bias (B) -5.14 Average Bias (B) -2.53 Standard Deviation (S) 1.03 Standard Deviation (S) 2.69 Measure Performance Bl+S 6.17 <15% Pass Measure Performance Bl+S 5.22 <15% Pass Secfion 5-Page 12
Table 5.0-B Footnote Explanations (1) State of NC Division of Radiation Protection TLD Cross-Check, Fall 2002 There was an unusual amount of time between anneal, irradiation and readout for the Fall 2002 Environmental Crosscheck with the State of NC Division of Radiation Protection. Normal times between irradiation and readout are typically less than 7 days. In the Fall 2002 crosscheck, due to the ice storm and holiday season, the time between irradiation and readout was 18 days. Fading correction was not applied for the report results; fading correction is typically NOT USED.
When fading correction was applied, the cross-checks were within acceptance criteria. Fading correction will be applied to future cross-checks.
Additional information is documented in PIP G-03-00021.
Section 5 - Page 13
6.0 REFERENCES
6.1 Oconee Selected License Commitments 6.2 Oconee Technical Specifications 6.3 Oconee Updated Final Safety Analysis Report 6.4 Duke Power Company Offsite Dose Calculation Manual 6.5 Oconee Annual Radiological Environmental Operating Report 1969-2001 6.6 Oconee Annual Radioactive Effluent Release Report 2002 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.
6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.
6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.
6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Vertechs Version 3.5.0, Duke Power Revision # 3.0 6.12 NRC Integrated Inspection Report 50-269/02-05, 50-270/02-05, 50-287/02-05 6.13 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page I
APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PRO CEDURES Appendix A -Page I
APPENDIX A ENVIRONAENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Oconee Nuclear Station is 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.
Section IV of this appendix describes the environmental sampling frequencies and analysis procedures by media type.
I. CHANGE OF SAMPLING PROCEDURES A new surface water site, 063.1 (0.78 miles E) was added to the REMP in the vicinity of the existing site 063 (0.8 miles ESE). The new site was added due to safety concerns and equipment reliability with the existing site 063 on the highway 183 bridge. Sampling from site 063 was suspended on 8/29/2002.
II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy.
Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.
Low-level iodine analyses are performed by passing a designated sample aliquot through an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.
Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. Tritium samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable.
Appendix A - Page 2
Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.
III. CIHANGE OF ANALY7SIS PROCEDURE,S No analysis procedures were changed during 2002.
Il. SAMPLING AND ANALYSIS PROCEDURES A.1 AlRIBORNE PARTICULATI', ANI) RADIOTODINE Airborne particulate and radioiodine samples at each of six 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 weekly gamma analysis was performed on each charcoal cartridge and a weekly gross beta analysis was performed on each filter. Filters were segregated by location and a quarterly gamma analysis was performed on the filter composite. The continuous composite samples were collected from the locations listed below.
Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)
Location 074 - Keowee Key Resort (2.3 mi. NNW)
Location 077 = Skimmer Wall (1.0 mi. SW)
Location 078 = Recreation Site (0.6 mi. WSW)
Location 079 = Keowee Dam (0.5 mi. NE)
Location 081 = Clemson Operations Center (9.3 mi. SE)
A.2 DRINKING WN'ATER Monthly composite samplers were operated to collect an aliquot at least every two hours. Gross beta and gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected monthly from the locations listed below.
Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)
Location 064 = Seneca (6.7 mi. SSW)
Location 066 - Anderson (19.0 mi SSE)
Appendix A - Page 3
A.3 SURZFACE WNIATlR Monthly composite samplers were operated to collect an aliquot at least every two hours. 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 062 = Lake Keowee/Hydro Intake (0.8 mi. ENE)
Location 063 = Lake Hartwell Hwy 183 Bridge (0.8 mi. ESE)
Location 063.1 = Lake Hartwell Hwy 183 Bridge (0.78 mi. E)
A.4 MILK Semimonthly grab samples were collected at each dairy. A gamma and low-level Iodine-131 analysis was performed on each sample. The semimonthly grab samples were collected from the locations listed below.
Location 071 = Clemson Dairy (10.3 mi. SSE)
Location 080 = Martin's Dairy (17.2 mi. SE)
Location 082 = Oakway Dairy (17.8 mi SSW)
A.5 1BROADIl,Al l,GETATrON Monthly samples were collected and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.
Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)
Location 077 - Skimmer Wall (1.0 mi. SW)
Location 079 = Keowee Dam (0.5 mi. NE)
Location 081 = Clemson Operations Center (9.3 mi. SE)
A.6 FISh-l Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. The samples were collected from the locations listed below.
Location 060 = New Greenville Water Intake Rd. (2.6 mi. NNE)
Location 063 = Lake Hartwell - Hwy 183 Bridge (0.8 mi. ESE)
Location 067 = Lawrence Ramsey Bridge, Hwy 27 (4.2 mi. SSE)
Appendix A -Page 4
A.7 S-IORELINE SEI)IMENT Semiannual samples were collected and 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 063 = Lake Hartwell - Hwy 183 Bridge (0.8 mi. ESE)
Location 067 = Lawrence Ramsey Bridge, Hwy 27 (4.2 mi. SSE)
Location 068 = High Falls County Park (2.0 mi. W)
A.8 1)1REC' GAMMA RADIATION (Tl,l))
Thermoluminescent dosimeters (TLD) were collected quarterly at forty-two locations. A gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.
- An inner ring of 17 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 control locations.
TLD Locations are listed in Table 2.1-B.
A.9 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 following locations in each of the sixteen meteorological sectors:
- The Nearest Residence
- The Nearest Meat Animal
- The Nearest Milk-giving Animal (cow, goat, etc.) where milk is used for human consumption The census was conducted during the growing season from 7/16 to 7/18/2002.
Results are shown in Table 3.9. No changes were made to the sampling procedures during 2002.
Appendix A - Page 5
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 2002 Appendix B - Page I
Environmental Radiological Monitoring Program Summary
~- Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Mediumor Totealn owrLii Location with Highest ControoRoutn Pathway Tuera Lower Limit All Indicator Locations Annual Mean Control Rotn Sampled Number of Detection Name, Distance, Direction Location Report of Meas.
Unit of Analyses LD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed ( ) Range Code Range Range Air Particulate (pCi/m3) 081 (9.3 mi SE)
BETA 310 .OOE-02 1.91E-2 (257/258) 074 2.01E-2 (52/52) 1.84E-2 (52/52) 0 4.36E 2.85E-2 (2.3 mi NNW) 8.42E 2.68E-2 6.60E 2.60E-2 CS-134 24 5.OOE-02 0.00 (0/20) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 24 6.OOE-02 0.00 (0/20) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 24 7.00E-02 0.00 (0/20) 0.00(0/4) 0.00(0/4) 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 @ 41112003 10:02 AM Appendix B - Page 2
Environmental Radiological Monitoring Program Summary
'-.- Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of All Indicator Annual Mean Control Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses (LLD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed (L ) Range Code Range Range Air Radioiodine (pCi/m3) 081 (9.3 mi SE)
CS-134 310 5.OOE-02 0.00 (0/258) 0.00(0/52) 0.00(0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 310 6.OOE-02 0.00 (0/258) 0.00 (0/52) 0.00(0/52) 0 0.00 -0.00 0.00 - 0.00 0.00 - 0.00 1-131 310 7.00E-02 0.00(0/258) 0.00 (0/52) 0.00(0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @4/12003 10:02 AM Appendix B -Page 3
Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of All Indicator Annual Mean Control Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed Range Code Range Range Drinking Water 064 (pCi/liter) (6.7 mi SSW)
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 BETA 39 4 1.44 (25/26) 066 1.61 (13/13) 1.21 (12/13) 0 0.63 - 2.27 (19.0 mi SSE) 1.06 - 2.09 0.72 - 1.96 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 15 2000 338 (5/10) 066 338 (5/5) 0.00 (0/5) 0 213 - 444 (19.0 mi SSE) 213 - 444 0.00 - 0.00 1-131 39 15 0.00(0/26) 0.00(0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 l 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 30 0.00 (0/26) 0.00 (0/13) -0.00 (0/13) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.001 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 @ 411/2003 10:02 AM Appendix B - Page 4
Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 o
Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower All Idit Location with Highest Control No. of Non-Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses LLD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed (L ) Range Code Range Range Surface Water 062 (pCi/liter) (0.8 mi ENE)
BALA-140 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 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 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 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 10 2000 9498 (5/5) 063 10000 (313) 0.00 (0/5) 0 5060 - 13700 (0.8 mi ESE) 5060 - 13700 0.00 - 0.00 1-131 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 MN-54 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 NB-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 ZN-65 26 30 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 ZR-95 26 30 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 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 @ 411/2003 10:02 AM Appendix B - Page 5
Environmental Radiological Monitoring Program Summary
'~ Facility: Oconee Nuclear Station Docket No. 50-269, 270, 287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower All Idt Location with Highest Control Nro f Nn-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 Milk 080 (pCi/liter) (17.2 mi SE)
BALA-140 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 78 18 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 78 15 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 78 1 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only
\.- Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements Report Generated @ 411/2003 10:02 AM Appendix B - Page 6
Environmental Radiological Monitoring Program Summary
'~' Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of locator Annual Mean Lontion Rot Sampled of Detection Locations Name, Distance, Direction Location RMepaos Unit of Analyses LD Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LD) Range Code Range Range Broadleaf Vegetation 081 (9.3 mi SE)
(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 84.4 (1/36) 077 84.4 (1/12) 0.00 (0/12) 0 84.4 - 84.4 (1.0 mi SW) 84.4 - 84.4 0.00 - 0.00 1-131 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 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 @ 4/1/2003 10:03 AM Appendix B -Page 7
Environmental Radiological Monitoring Program Summary V. Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Location with Highest No. of Non-
.. All Indicator Control Routine Pathway Number Limit of . Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LLD) Range Code Range Range Fish 060 (pCi/kg-wet) (2.6 mi NNE)
CO-58 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 83.7 (8/8) 063 93.7 (4/4) 21.0 (1/4) 0 59.1-110 (0.8miESE) 69.0-110 21.0-21.0 FE-59 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 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 @ 4/1/2003 10:03 AM Appendix B - Page 8
Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2002 to 31-DEC-2002 Medium or Type and Total Lower Location with Highest No. of Non-Pathway Number Limit of All Indicator Annual Mean Control Routine Sampled of Detection Locations Name, Distance, Direction Location Report Meas.
Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Measurement Performed (LLD) Range Code Range Range Shoreline 068 Sediment (2.0 mi W)
(pCi/kg-dry)
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 49.6 (4/4) 067 69.6 (2/2) 0.00 (0/2) 0 22.5 - 83.3 (4.2 mi SSE) 56.0 - 83.3 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 @ 4/1/2003 10:03 AM Appendix B - Page 9
Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Rcport Period: 01-JAN-2002 to 31-DEC-2002 Typc and Total . . Location with Highest No. of Non-Medium or Typ e Lower Limi All Indicator Locat w est Control Routine Pathway Sampled Number of Detection Locations Annual Mean Location Report of of Detection Locations Name, Distance, Direction Meas.
Unit of Measurement Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)
Performed Range Code Range Range Direct Radiation TLD 058 (9.4 mi WSW)
(mRlstandard quarter) 081 (9.3 mi SE) 166 0.OOE+00 20.3 (1581158) 048 26.0 (4/4) 27.0 (8/8) 0 13.0 - 28.5 (4.0 mi W) 22.7 - 28.5 18.7 - 34.7 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 Repon Generated @ 4/1/2003 10:03 AM Appendix B -Page 10
APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C -Page I
APPENDIX C OCONEE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance C.] SAMPLING DEV'IATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was interrupted. Work request 2019480 was 079 8/26 - 9/3/02 8/26 - 8/26/02 PI written to restore power.
Power to sampling equipment was interrupted. Work request 2020926 was 078 9/16 - 9/23/02 9/16 - 9/18/02 PO written to restore power.
Power to sampling equipment was interrupted. Work request 2020913 was 081 9/16 - 9/23/02 9/16 - 9/19/02 PO written to restore power.
Power to sampling equipment was interrupted. Work request 2020926 was 078 9/23 - 9/30/02 9/25 - 9/30/02 PO written to restore power.
Drinking Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Sampling equipment did not collect sufficient volume. A grab sample was collected. Sampling equipment was reset 066 1/21 - 2/18/02 2/18 - 2/18/02 OT and verified operable.
Power to sampling equipment was lost during the composite period. Loss suspected due to plant maintenance. A grab sample was collected. Power was restored and normal sampling resumed on 060 5/13 - 6/10/02 6/10 - 6/10/02 PO 6/10/2002.
Appendix C -Page 2
Drinking Water, continued Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was lost during the composite period. Loss suspected due to plant maintenance and construction. A grab sample was collected. Power was restored and normal 064 5/13 - 6/10/02 6/10 - 6/10/02 PO sampling resumed on 6/10/2002.
Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Reservoir pump not sampling at time of collection. Suspected cause was a line clog to intake line. Work request 063* 12/26- 1/21/02 12/26- 1/17/02 PS 98218295 was written.
Sampling equipment was inoperative from previous collection period due to intake line clog. Grab samples were collected from 1/22/02 through 1/25/02. Sampling equipment was returned to normal operation on 1/26/02. During operation the sampling equipment tripped internal float after 22 days, 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of operability. Sampling equipment was verified operable at time of collection and 063* 1/21 - 2/18/02 1/22 - 2/13/02 OT normal sampling resumed.
Power supply to sampling equipment was interrupted and insufficient sample volume was available. Sampler tubing was replaced and sampling equipment recalibrated. A grab sample was collected 062 2/18 - 3/18/02 3/18 - 3/18/02 PI and normal sampling resumed.
Sampling equipment was not functional at time of collection. A grab sample was 062 5/13 - 6/10/02 6/10 - 6/10/02 OT collected and normal sampling resumed.
Reservoir pump was not functional at time of collection. Work request 98234702 was written to restore equipment. Daily grabs were collected from 5/13 - 5/19102.
The reservoir pump was repaired and 063* 5/13 - 6/10/02 5/13 - 6/10/02 PS normal sampling resumed on 5/20/02.
The reservoir pump was not functional at time of collection. Work request 98238830 was written to restore the equipment. Daily grab samples were collected from 6/11 - 6/17/02. Normal 063* 6/10 - 7/8/02 6/11 - 7/8/02 PS sampling was resumed on 6/17/02.
Sampling equipment was not functional at start of collection period. The reservoir pump was not functional. Daily grab samples were collected from 7/8 - 7/9/02.
063* 7/8 - 8/5/02 7/8 - 8/5/02 PS Normal sampling was resumed 7/10/02.
Appendix C - Page 3
Surface Water, continued Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action The reservoir pump was removed from service due to safety concerns.
Composite sample was obtained from 8/3
- 8/29/02. Daily grab samples were 063* 8/5 - 9/3/02 8/5 - 9/3/02 PS collected from 8/29 - 9/3/02.
- A newv surface water site, 063.1 (0.78 miles E), was added o the REMP in the vicinlity of the existing site 063 (0.8 miles ESE). The new site vas added due lo safety concerns anid equipment reliability vilh te existing site 063 on the highway 183 bridge. The existing site 063 was removedfromn service effective 8/29/2002. The new site 063.1 began operation effective 7/12/2002.
C.2 UNAVAILABLE ANALYSES Air Particulate and Air Radioiodines Scheduled Reason Location Collection Dates Code Corrective Action Power to sampling equipment was interrupted during previous sampling period and had not been restored.
079 9/3 - 9/9/02 PI Work request 2019480 was written to restore power.
TLD Scheduled Reason Location Collection Dates Code Corrective Action TLD was found on ground and had been tampered with. The TLD case was open. TLD examination lead to the conclusion the subsequent data would not 040 3/18 - 6/17/02 VN be reliable. TLD considered unavailable.
029 9/16 - 12/16/02 VN TLD missing. 1 quarter 2003 TLD placed in field.
Appendix C - Page 4
APPENDIX D ANALYTICAL DEVIATIONS Appendix D - Page I
D.1 ANALYTICAI, DEVIATIONS Air Particulate and Air Radioiodines Scheduled Reason Location Collection Dates Code Corrective Action This sample was determined to be unavailable for analysis.
The air particulate filter was returned to the laboratory and appeared clean. Conversation with the sample collector for the end date of the composite period (4/29/2002) revealed that the clean filter was observed by the collector. No indication of the clean filter was recorded in writing on the transmittal or sample envelope. The clean filter was returned to the lab and gross beta analysis was not possible since the filter could not achieve detection limit for gross beta. It is unknown why the filter was returned clean.
The secondary filter was discarded by laboratory personnel prior to the discovery of the clean filter by laboratory personnel. The filter [LIMS # 22013248] and the corresponding cartridge [LIMS # 22013249] were considered ANALYTICAL DEVIATIONS since the analysis of the secondary samples could have prevented this unavailable sample.
078 4/22 - 4/29/02 OT This information is identified in GO PIP G-02-00160.
Appendix D - Page 2
APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2002. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.
Appendix E -Page I