ML13141A480: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 48: | Line 48: | ||
None of the effluent controls associated with liquid or gaseous effluents were exceeded during the reporting period, as confirmed by conservative dose assessments performed at weekly and monthly intervals. | None of the effluent controls associated with liquid or gaseous effluents were exceeded during the reporting period, as confirmed by conservative dose assessments performed at weekly and monthly intervals. | ||
Conformance to the PNPS ODCM effluent control limits ensures that releases of radioactivity in liquid and gaseous effluents are kept as low as reasonably achievable in accordance with 10 CFR Part 50, Appendix I. Compliance with the ODCM also demonstrates that requirements of the Environmental Protection Agency's nuclear fuel cycle standard, 40CFR190.10, Subpart B, have been met. Based on the dose assessment results for 2012, there was no significant radiological impact on the general public from PNPS operation. | Conformance to the PNPS ODCM effluent control limits ensures that releases of radioactivity in liquid and gaseous effluents are kept as low as reasonably achievable in accordance with 10 CFR Part 50, Appendix I. Compliance with the ODCM also demonstrates that requirements of the Environmental Protection Agency's nuclear fuel cycle standard, 40CFR190.10, Subpart B, have been met. Based on the dose assessment results for 2012, there was no significant radiological impact on the general public from PNPS operation. | ||
Page 7 2.0 RADIOACTIVE EFFLUENT DATA Radioactive gaseous and liquid releases for the reporting period are given in the standard format presented in Tables 1A, 1B, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference | Page 7 | ||
===2.0 RADIOACTIVE=== | |||
EFFLUENT DATA Radioactive gaseous and liquid releases for the reporting period are given in the standard format presented in Tables 1A, 1B, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference | |||
: 1) format.2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1.2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities. | : 1) format.2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1.2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities. | ||
Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows:* Noble gases: 0.65 Ci, 0.021 gCi/sec* lodines and particulates with 0.0041 Ci, 0.00013 iiCi/sec half-life greater than 8 days" Tritium: 29.7 Ci, 0.94 I.Ci/sec" Carbon-14: | Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows:* Noble gases: 0.65 Ci, 0.021 gCi/sec* lodines and particulates with 0.0041 Ci, 0.00013 iiCi/sec half-life greater than 8 days" Tritium: 29.7 Ci, 0.94 I.Ci/sec" Carbon-14: | ||
Line 54: | Line 58: | ||
Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 10CFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide. | Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 10CFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide. | ||
Although Carbon-14 (C-14) had been exempted from gaseous effluent calculations in the 1970s, industry assessments in 2009 revealed that Carbon-14 would qualify as a principal radionuclide. | Although Carbon-14 (C-14) had been exempted from gaseous effluent calculations in the 1970s, industry assessments in 2009 revealed that Carbon-14 would qualify as a principal radionuclide. | ||
Based on this 2009 re-assessment, licensees were required to begin reporting C-14 gaseous effluents in the Annual Radioactive Effluent Release Report beginning with calendar-year 2010. Carbon-14 releases for 2012 are summarized in Tables 2.2-A through 2.2-C, and the dose consequences from C-14 are incorporated into the dose assessments documented in Section 4.2 of this report.Page 8 2.3 Liquid Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building.Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were five discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows: " Total Effluent Volume: 180,000 Liters" Total Dilution Volume: 616 billion Liters* Fission/Activation products: | Based on this 2009 re-assessment, licensees were required to begin reporting C-14 gaseous effluents in the Annual Radioactive Effluent Release Report beginning with calendar-year 2010. Carbon-14 releases for 2012 are summarized in Tables 2.2-A through 2.2-C, and the dose consequences from C-14 are incorporated into the dose assessments documented in Section 4.2 of this report.Page 8 | ||
===2.3 Liquid=== | |||
Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building.Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were five discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows: " Total Effluent Volume: 180,000 Liters" Total Dilution Volume: 616 billion Liters* Fission/Activation products: | |||
0.00 Ci, 0.00 [.Ci/mL" Tritium: 0.0988 Ci, 0.000000000160 | 0.00 Ci, 0.00 [.Ci/mL" Tritium: 0.0988 Ci, 0.000000000160 | ||
[tCi/mL" Dissolved/entrained noble gases: 0.00 Ci, 0.00 ýiCi/mL One discrepancy was noted with the analysis of radioactivity contained in liquid effluents discharged in 2012. The monthly composite sample collected from the five neutralizing sump discharges that occurred in January 2012 was not shipped to the vendor laboratory for the monthly analysis of tritium and gross alpha activity, and the quarterly analysis of Iron-55 and Strontium-89/90. This discrepancy is described in Condition Report CR-PNP-2013-1538. | [tCi/mL" Dissolved/entrained noble gases: 0.00 Ci, 0.00 ýiCi/mL One discrepancy was noted with the analysis of radioactivity contained in liquid effluents discharged in 2012. The monthly composite sample collected from the five neutralizing sump discharges that occurred in January 2012 was not shipped to the vendor laboratory for the monthly analysis of tritium and gross alpha activity, and the quarterly analysis of Iron-55 and Strontium-89/90. This discrepancy is described in Condition Report CR-PNP-2013-1538. | ||
Line 114: | Line 121: | ||
Ci Na-24 NDA N/A N/A N/A NDA Cr-51 NDA N/A N/A N/A NDA Mn-54 NDA N/A N/A N/A NDA Fe-55 NDA N/A N/A N/A NDA Fe-59 NDA N/A N/A N/A NDA Co-58 NDA N/A N/A N/A NDA Co-60 NDA N/A N/A N/A NDA Zn-65 NDA N/A N/A N/A NDA Zn-69m NDA N/A N/A N/A NDA Sr-89 NDA N/A N/A N/A NDA Sr-90 NDA N/A N/A N/A NDA Zr/Nb-95 NDA N/A N/A N/A NDA Mo/Tc-99 NDA N/A N/A N/A NDA Ag-110m NDA N/A N/A N/A NDA Sb-124 NDA N/A N/A N/A NDA 1-131 NDA N/A N/A N/A NDA 1-133 NDA N/A N/A N/A NDA Cs-134 NDA N/A N/A N/A NDA Cs-137 NDA N/A N/A N/A NDA Ba/La-140 NDA N/A N/A N/A NDA Ce-141 NDA N/A N/A N/A NDA Ce-144 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 NDA N/A N/A N/A NDA Xe-1 35 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA Notes for Table 2.3-B: 1. N/A stands for not applicable. | Ci Na-24 NDA N/A N/A N/A NDA Cr-51 NDA N/A N/A N/A NDA Mn-54 NDA N/A N/A N/A NDA Fe-55 NDA N/A N/A N/A NDA Fe-59 NDA N/A N/A N/A NDA Co-58 NDA N/A N/A N/A NDA Co-60 NDA N/A N/A N/A NDA Zn-65 NDA N/A N/A N/A NDA Zn-69m NDA N/A N/A N/A NDA Sr-89 NDA N/A N/A N/A NDA Sr-90 NDA N/A N/A N/A NDA Zr/Nb-95 NDA N/A N/A N/A NDA Mo/Tc-99 NDA N/A N/A N/A NDA Ag-110m NDA N/A N/A N/A NDA Sb-124 NDA N/A N/A N/A NDA 1-131 NDA N/A N/A N/A NDA 1-133 NDA N/A N/A N/A NDA Cs-134 NDA N/A N/A N/A NDA Cs-137 NDA N/A N/A N/A NDA Ba/La-140 NDA N/A N/A N/A NDA Ce-141 NDA N/A N/A N/A NDA Ce-144 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 NDA N/A N/A N/A NDA Xe-1 35 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA Notes for Table 2.3-B: 1. N/A stands for not applicable. | ||
: 2. NDA stands for No Detectable Activity.3. LLDs for liquid radionuclides listed as NDA are as follows: Strontium: | : 2. NDA stands for No Detectable Activity.3. LLDs for liquid radionuclides listed as NDA are as follows: Strontium: | ||
5E-08 jiCi/mL lodines: 1E-06 p.Ci/m L Noble Gases: 1E-05 ptCi/mL All Others: 5E-07 ýiCi/mL Page 18 3.0 METEOROLOGICAL DATA Meteorological data are summarized for the reporting period in Appendix A, in the standard joint frequency distribution format as given in NRC Regulatory Guide 1.21.The predominant meteorological conditions observed during the annual reporting period can be summarized with their corresponding frequencies as follows: " Stability Class: Class D, 51%* 33-ft Wind Direction (from): South-southwest, 15%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 14%* 220-ft Wind Speed: 12.5-18.5 mph, 35%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 66%, which did not meet the 90% annual data recovery goal specified by the NRC. A break occurred in the wiring supplying power to the aspirator fan in the upper-level temperature sensor on 18-Mar-2012 and was repaired on 19-Jul-2012. | 5E-08 jiCi/mL lodines: 1E-06 p.Ci/m L Noble Gases: 1E-05 ptCi/mL All Others: 5E-07 ýiCi/mL Page 18 | ||
===3.0 METEOROLOGICAL=== | |||
DATA Meteorological data are summarized for the reporting period in Appendix A, in the standard joint frequency distribution format as given in NRC Regulatory Guide 1.21.The predominant meteorological conditions observed during the annual reporting period can be summarized with their corresponding frequencies as follows: " Stability Class: Class D, 51%* 33-ft Wind Direction (from): South-southwest, 15%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 14%* 220-ft Wind Speed: 12.5-18.5 mph, 35%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 66%, which did not meet the 90% annual data recovery goal specified by the NRC. A break occurred in the wiring supplying power to the aspirator fan in the upper-level temperature sensor on 18-Mar-2012 and was repaired on 19-Jul-2012. | |||
This event is described in Condition Reports CR-PNP-2012-2884 and CR-PNP-2012-4759. | This event is described in Condition Reports CR-PNP-2012-2884 and CR-PNP-2012-4759. | ||
This resulted in invalid delta-temperature readings during this period, for a loss of 2954 hours of joint data for the year. Although the loss of the delta-temperature data affected the calculation of atmospheric stability class, wind speed and wind direction data were unaffected and were used to summarize wind speed and wind direction values for the quarterly and annual summary tables.Page 19 4.0 MAXIMUM INDIVIDUAL DOSES Doses to the maximum exposed individual resulting from radionuclides in effluents released offsite were calculated using methods presented in the PNPS Offsite Dose Calculation Manual (ODCM, Reference 2), NRC Regulatory Guide 1.109 (Reference 3), NRC Regulatory Guide 1.111 (Reference 4), and the Pilgrim Station Unit 1 Appendix I Evaluation (Reference 5). Maximum individual doses are calculated separately for: (1) noble gases in gaseous effluents, (2) particulates, iodines, and tritium in gaseous effluents; and, (3) liquid effluents. | This resulted in invalid delta-temperature readings during this period, for a loss of 2954 hours of joint data for the year. Although the loss of the delta-temperature data affected the calculation of atmospheric stability class, wind speed and wind direction data were unaffected and were used to summarize wind speed and wind direction values for the quarterly and annual summary tables.Page 19 | ||
===4.0 MAXIMUM=== | |||
INDIVIDUAL DOSES Doses to the maximum exposed individual resulting from radionuclides in effluents released offsite were calculated using methods presented in the PNPS Offsite Dose Calculation Manual (ODCM, Reference 2), NRC Regulatory Guide 1.109 (Reference 3), NRC Regulatory Guide 1.111 (Reference 4), and the Pilgrim Station Unit 1 Appendix I Evaluation (Reference 5). Maximum individual doses are calculated separately for: (1) noble gases in gaseous effluents, (2) particulates, iodines, and tritium in gaseous effluents; and, (3) liquid effluents. | |||
Maximum consumption and use factors for various pathways from Table E-5 of the PNPS ODCM are used for calculating the doses to the maximum exposed individual. | Maximum consumption and use factors for various pathways from Table E-5 of the PNPS ODCM are used for calculating the doses to the maximum exposed individual. | ||
Information related to liquid and gaseous effluent releases are summarized Section 2 of this report.These effluent release data were used as input to computer programs to calculate the resulting doses. PNPS ODCM methodologies were used to calculate the dose contributions to the various organs in each age class from major exposure pathways.4.1 Doses From Noble Gas Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters. | Information related to liquid and gaseous effluent releases are summarized Section 2 of this report.These effluent release data were used as input to computer programs to calculate the resulting doses. PNPS ODCM methodologies were used to calculate the dose contributions to the various organs in each age class from major exposure pathways.4.1 Doses From Noble Gas Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters. | ||
Line 123: | Line 137: | ||
For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.000013 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.000062 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building). | For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.000013 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.000062 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building). | ||
Page 20 Table 4.1 Maximum Doses From Noble Gas Releases Durina 2 0 1 2 (a)Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location) (location) (location) (location) | Page 20 Table 4.1 Maximum Doses From Noble Gas Releases Durina 2 0 1 2 (a)Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location) (location) (location) (location) | ||
Jan-Mar 0.00E+00 0.O0E+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)5.78E-07 8.89E-07, 3.64E-07 8.75E-07 Apr-Jun (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)6.88E-07 1.31E-06 4.19E-07 1.03E-06 Jul-Sep (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)Oct-Dec 2.50E-05 9.27E-05 1.65E-05 8.96E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 2.58E-05 9.31E-05 1.70E-05 9.03E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)(a) All directions and distances are with respect to the reactor building vent.Page 21 4.2 Doses From Gaseous Effluent Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters. | Jan-Mar 0.00E+00 0.O0E+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)5.78E-07 8.89E-07, 3.64E-07 8.75E-07 Apr-Jun (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)6.88E-07 1.31E-06 4.19E-07 1.03E-06 Jul-Sep (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)Oct-Dec 2.50E-05 9.27E-05 1.65E-05 8.96E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 2.58E-05 9.31E-05 1.70E-05 9.03E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)(a) All directions and distances are with respect to the reactor building vent.Page 21 | ||
===4.2 Doses=== | |||
From Gaseous Effluent Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters. | |||
Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the"AEOLUS-3" computer program (Reference 6). This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.The maximum individual doses resulting from radioactive particulates, radioiodines, tritium and carbon-14 released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively. | Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the"AEOLUS-3" computer program (Reference 6). This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.The maximum individual doses resulting from radioactive particulates, radioiodines, tritium and carbon-14 released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively. | ||
Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM.Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and analysis of doses resulting from noble gases are addressed in Section 4.1 of this report.Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways. | Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM.Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and analysis of doses resulting from noble gases are addressed in Section 4.1 of this report.Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways. | ||
Line 145: | Line 162: | ||
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: | Bound Resident Garden Cow/Goat Cow/Meat Meat Direction: | ||
NW ESE SE WSW W S Distance': | NW ESE SE WSW W S Distance': | ||
0.54 km 0.80 kW 0.84 km 3.97 km 5.77 km 3.80 km Pathway 2: DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 8.29E-04 6.16E-04 2.60E-02 9.51E-03 8.28E-03 1.44E-02 GI-LLI 3.51E-03 2.38E-03 1.08E-02 2.38E-03 1.94E-03 3.21E-03 Kidney 3.47E-03 2.35E-03 1.05E-02 2.37E-03 1.94E-03 3.20E-03 Liver 3.46E-03 2.35E-03 1.05E-02 2.37E-03 1.93E-03 3.20E-03 Lung 3.63E-03 2.46E-03 1.06E-02 2.36E-03 1.93E-03 3.20E-03 Thyroid 5.43E-03 3.65E-03 1.55E-02 3.86E-03 2.74E-03 3.53E-03 T.Body 3.46E-03 2.35E-03 1.06E-02 2.37E-03 1.93E-03 3.20E-03 Age Class: Teen Bone 1.18E-03 8.76E-04 4.14E-02 1.60E-02 1.25E-02 2.03E-02 GI-LLI 3.61E-03 2.45E-03 1.43E-02 3.73E-03 2.81E-03 4.40E-03 Kidney 3.57E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Liver 3.56E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Lung 3.84E-03 2.60E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Thyroid 6.06E-03 4.08E-03 1.86E-02 5.91E-03 3.96E-03 4.68E-03 T.Body 3.55E-03 2.41E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Age Class: Child Bone 1.62E-03 1.20E-03 9.82E-02 3.85E-02 2.93E-02 4.68E-02 GI-LLI 3.26E-03 2.22E-03 2.71E-02 8.41E-03 6.27E-03 9.79E-03 Kidney 3.25E-03 2.22E-03 2.69E-02 8.41 E-03 6.28E-03 9.78E-03 Liver 3.25E-03 2.21E-03 2.69E-02 8.41E-03 6.27E-03 9.78E-03 Lung 3.49E-03 2.37E-03 2.69E-02 8.40E-03 6.27E-03 9.78E-03 Thyroid 6.22E-03 4.18E-03 3.34E-02 1.26E-02 8.50E-03 1.02E-02 T.Body 3.24E-03 2.21E-03 2.70E-02 8.41 E-03 6.28E-03 9.79E-03 Age Class: Infant Bone 1.18E-03 8.77E-04 7.30E-04 2.40E-02 1.66E-02 3.18E-04 GI-LLI 1.93E-03 1.32E-03 9.93E-04 5.48E-03 3.73E-03 1.1OE-04 Kidney 1.93E-03 1.32E-03 9.95E-04 5.52E-03 3.74E-03 1.1OE-04 Liver 1.93E-03 1.32E-03 9.94E-04 5.51E-03 3.74E-03 1.1OE-04 Lung 2.15E-03 1.47E-03 1.1OE-03 5.49E-03 3.73E-03 1.16E-04 Thyroid 4.66E-03 3.13E-03 2.33E-03 1.50E-02 8.69E-03 1.77E-04 T.Body 1.93E-03 1.32E-03 9.91E-04 5.50E-03 3.73E-03 1.1OE-04 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V C = Cow Milk G = Goat Milk M= Vegetable Garden= Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.Page 27 4.3 Doses From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses. The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E. These tables cover the individual calendar quarters and the total calendar year, respectively. | 0.54 km 0.80 kW 0.84 km 3.97 km 5.77 km 3.80 km Pathway 2: DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 8.29E-04 6.16E-04 2.60E-02 9.51E-03 8.28E-03 1.44E-02 GI-LLI 3.51E-03 2.38E-03 1.08E-02 2.38E-03 1.94E-03 3.21E-03 Kidney 3.47E-03 2.35E-03 1.05E-02 2.37E-03 1.94E-03 3.20E-03 Liver 3.46E-03 2.35E-03 1.05E-02 2.37E-03 1.93E-03 3.20E-03 Lung 3.63E-03 2.46E-03 1.06E-02 2.36E-03 1.93E-03 3.20E-03 Thyroid 5.43E-03 3.65E-03 1.55E-02 3.86E-03 2.74E-03 3.53E-03 T.Body 3.46E-03 2.35E-03 1.06E-02 2.37E-03 1.93E-03 3.20E-03 Age Class: Teen Bone 1.18E-03 8.76E-04 4.14E-02 1.60E-02 1.25E-02 2.03E-02 GI-LLI 3.61E-03 2.45E-03 1.43E-02 3.73E-03 2.81E-03 4.40E-03 Kidney 3.57E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Liver 3.56E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Lung 3.84E-03 2.60E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Thyroid 6.06E-03 4.08E-03 1.86E-02 5.91E-03 3.96E-03 4.68E-03 T.Body 3.55E-03 2.41E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Age Class: Child Bone 1.62E-03 1.20E-03 9.82E-02 3.85E-02 2.93E-02 4.68E-02 GI-LLI 3.26E-03 2.22E-03 2.71E-02 8.41E-03 6.27E-03 9.79E-03 Kidney 3.25E-03 2.22E-03 2.69E-02 8.41 E-03 6.28E-03 9.78E-03 Liver 3.25E-03 2.21E-03 2.69E-02 8.41E-03 6.27E-03 9.78E-03 Lung 3.49E-03 2.37E-03 2.69E-02 8.40E-03 6.27E-03 9.78E-03 Thyroid 6.22E-03 4.18E-03 3.34E-02 1.26E-02 8.50E-03 1.02E-02 T.Body 3.24E-03 2.21E-03 2.70E-02 8.41 E-03 6.28E-03 9.79E-03 Age Class: Infant Bone 1.18E-03 8.77E-04 7.30E-04 2.40E-02 1.66E-02 3.18E-04 GI-LLI 1.93E-03 1.32E-03 9.93E-04 5.48E-03 3.73E-03 1.1OE-04 Kidney 1.93E-03 1.32E-03 9.95E-04 5.52E-03 3.74E-03 1.1OE-04 Liver 1.93E-03 1.32E-03 9.94E-04 5.51E-03 3.74E-03 1.1OE-04 Lung 2.15E-03 1.47E-03 1.1OE-03 5.49E-03 3.73E-03 1.16E-04 Thyroid 4.66E-03 3.13E-03 2.33E-03 1.50E-02 8.69E-03 1.77E-04 T.Body 1.93E-03 1.32E-03 9.91E-04 5.50E-03 3.73E-03 1.1OE-04 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V C = Cow Milk G = Goat Milk M= Vegetable Garden= Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.Page 27 | ||
===4.3 Doses=== | |||
From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses. The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E. These tables cover the individual calendar quarters and the total calendar year, respectively. | |||
Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways. | Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways. | ||
NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways. | NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways. | ||
Therefore, doses for this age class are not included in any of the tables.It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters. | Therefore, doses for this age class are not included in any of the tables.It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters. | ||
Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given quarter, the resulting concentration for that quarter will be higher than concentrations from other quarters. | Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given quarter, the resulting concentration for that quarter will be higher than concentrations from other quarters. | ||
This will result in a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses.Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (adult age class) of 0.0000000919 mrem. The maximum organ dose (adult age class, all organs) was 0.0000000919 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2012 Age Class Organ Dose -mrem *Organ Adult J Teen Child Bone 0.OE+00 0.OOE+00 0.OOE+00 GI-LLI 9.26E-08 6.85E-08 5.91E-08 Kidney 9.26E-08 6.85E-08 5.91E-08 Liver 9.26E-08 6.85E-08 5.91E-08 Lung 9.26E-08 6.85E-08 5.91 E-08 Thyroid 9.26E-08 6.85E-08 5.91 E-08 T.Body 9.26E-08 6.85E-08 5.91 E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 29 Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2012 Age Class Organ Dose -mrem Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.0OE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.OOE+00 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2012 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 O.OOE+00 0.OOE+00 Liver O.OOE+00 O.OOE+00 0.OOE+00 Lung O.OOE+00 O.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.00E+00 Page 31 Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2012 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 O.OOE+00 Kidney 0.OOE+00 0.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 O.OOE+00 Lung 0.OOE+00 0.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 O.OOE+00 0.OOE+00* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during these months.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 32 Table 4.3-E Maximum Individual Organ Doses -mrem From Liquid Release Period: Jan-Dec 2012 Age Class Organ Dose -mrem *Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 9.19E-08 6.79E-08 5.86E-08 Kidney 9.19E-08 6.79E-08 5.86E-08 Liver 9.19E-08 6.79E-08 5.86E-08 Lung 9.19E-08 6.79E-08 5.86E-08 Thyroid 9.19E-08 6.79E-08 5.86E-08 T.Body 9.19E-08 6.79E-08 5.86E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 33 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure. | This will result in a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses.Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (adult age class) of 0.0000000919 mrem. The maximum organ dose (adult age class, all organs) was 0.0000000919 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2012 Age Class Organ Dose -mrem *Organ Adult J Teen Child Bone 0.OE+00 0.OOE+00 0.OOE+00 GI-LLI 9.26E-08 6.85E-08 5.91E-08 Kidney 9.26E-08 6.85E-08 5.91E-08 Liver 9.26E-08 6.85E-08 5.91E-08 Lung 9.26E-08 6.85E-08 5.91 E-08 Thyroid 9.26E-08 6.85E-08 5.91 E-08 T.Body 9.26E-08 6.85E-08 5.91 E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 29 Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2012 Age Class Organ Dose -mrem Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.0OE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.OOE+00 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2012 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 O.OOE+00 0.OOE+00 Liver O.OOE+00 O.OOE+00 0.OOE+00 Lung O.OOE+00 O.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.00E+00 Page 31 Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2012 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 O.OOE+00 Kidney 0.OOE+00 0.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 O.OOE+00 Lung 0.OOE+00 0.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 O.OOE+00 0.OOE+00* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during these months.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 32 Table 4.3-E Maximum Individual Organ Doses -mrem From Liquid Release Period: Jan-Dec 2012 Age Class Organ Dose -mrem *Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 9.19E-08 6.79E-08 5.86E-08 Kidney 9.19E-08 6.79E-08 5.86E-08 Liver 9.19E-08 6.79E-08 5.86E-08 Lung 9.19E-08 6.79E-08 5.86E-08 Thyroid 9.19E-08 6.79E-08 5.86E-08 T.Body 9.19E-08 6.79E-08 5.86E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 33 | ||
===5.0 OFFSITE=== | |||
AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure. | |||
However, Regulatory Guide 1.21 (Reference | However, Regulatory Guide 1.21 (Reference | ||
: 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man.Thermoluminescent dosimeters (TLDs) are located at 83 sites beyond the boundary of the PNPS restricted/protected area. A number of these TLDs are located within the site boundary, on Entergy property in close proximity to the station proper. The TLDs are collected on a quarterly basis and used to calculate the ambient radiation exposure in milliRoentgen (mR) over the exposure period.These TLDs are grouped into four zones of increasing distance from the station. Average exposure values for each of these zones were calculated for each calendar quarter and the total year. The average exposure values (mR) for the four zones are presented in Table 5.0.In addition to responding to ambient radiation exposure, TLDs will also record radiation resulting from noble gases (plume and immersion exposure), particulate materials deposited on the ground, cosmic rays from outer space, and from naturally-occurring radioactivity in the soil and air.Typically, the exposure from cosmic rays and other natural radioactivity components is about 40 to 70 mR/year. As calculated in Sections 4.1 and 4.2 of this report, the ambient radiation component of doses from PNPS effluent emissions are below 1 mrem/yr and would not be discernible above the natural radiation exposure levels.The major source of ambient radiation exposure from PNPS results from high-energy gamma rays emitted from nitrogen-16 (N-16) contained in steam flowing through the turbine. Although the N-16 is enclosed in the process lines and turbine and is not released into the environment, the ambient radiation exposure and sky shine from this contained source accounts for the majority of the radiation dose, especially in close proximity to the station. Other sources of ambient radiation exposure include radiation emitted from contained radioactive materials and/or radwaste at the facility. | : 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man.Thermoluminescent dosimeters (TLDs) are located at 83 sites beyond the boundary of the PNPS restricted/protected area. A number of these TLDs are located within the site boundary, on Entergy property in close proximity to the station proper. The TLDs are collected on a quarterly basis and used to calculate the ambient radiation exposure in milliRoentgen (mR) over the exposure period.These TLDs are grouped into four zones of increasing distance from the station. Average exposure values for each of these zones were calculated for each calendar quarter and the total year. The average exposure values (mR) for the four zones are presented in Table 5.0.In addition to responding to ambient radiation exposure, TLDs will also record radiation resulting from noble gases (plume and immersion exposure), particulate materials deposited on the ground, cosmic rays from outer space, and from naturally-occurring radioactivity in the soil and air.Typically, the exposure from cosmic rays and other natural radioactivity components is about 40 to 70 mR/year. As calculated in Sections 4.1 and 4.2 of this report, the ambient radiation component of doses from PNPS effluent emissions are below 1 mrem/yr and would not be discernible above the natural radiation exposure levels.The major source of ambient radiation exposure from PNPS results from high-energy gamma rays emitted from nitrogen-16 (N-16) contained in steam flowing through the turbine. Although the N-16 is enclosed in the process lines and turbine and is not released into the environment, the ambient radiation exposure and sky shine from this contained source accounts for the majority of the radiation dose, especially in close proximity to the station. Other sources of ambient radiation exposure include radiation emitted from contained radioactive materials and/or radwaste at the facility. | ||
Despite these sources of ambient radiation exposure at PNPS, increases in exposure from ambient radiation are typically not observable above background levels at locations beyond Entergy controlled property.The average exposure values presented in Table 5.0 appear to indicate an elevation in ambient exposures in Zone 1, those TLDs within 2 miles of PNPS. Most of this elevation is due to increases in exposure levels measured at TLD locations on Entergy property in close proximity to the station proper. For example, the annual exposure at TLD location OA, located at the Overlook Area near the PNPS Health Club (I&S Building), was 185 mR for the entire year. This location is immediately adjacent to the station proper and overlooks the turbine building, therefore receiving the highest direct ambient and sky shine exposure. | Despite these sources of ambient radiation exposure at PNPS, increases in exposure from ambient radiation are typically not observable above background levels at locations beyond Entergy controlled property.The average exposure values presented in Table 5.0 appear to indicate an elevation in ambient exposures in Zone 1, those TLDs within 2 miles of PNPS. Most of this elevation is due to increases in exposure levels measured at TLD locations on Entergy property in close proximity to the station proper. For example, the annual exposure at TLD location OA, located at the Overlook Area near the PNPS Health Club (I&S Building), was 185 mR for the entire year. This location is immediately adjacent to the station proper and overlooks the turbine building, therefore receiving the highest direct ambient and sky shine exposure. | ||
When the near-site TLDs (those located within 0.6 km of the Reactor Building) are removed from the calculation of averages, the mean annual exposure in Zone 1 falls from 71.7 +/- 24.7 mR/yr to 60.7 +/- 68.8 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.8 +/- 7.3 mR/yr, and is indicative of natural background radiation. | When the near-site TLDs (those located within 0.6 km of the Reactor Building) are removed from the calculation of averages, the mean annual exposure in Zone 1 falls from 71.7 +/- 24.7 mR/yr to 60.7 +/- 68.8 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.8 +/- 7.3 mR/yr, and is indicative of natural background radiation. | ||
Although the annual exposure at TLD location OA was 124 mR above the average Zone 4 exposure, members of the general public do not continuously occupy this area. When adjusted for such occupancy, a hypothetical member of the public who was at this location for 40 hours per year would only receive an incremental dose of 0.57 mrem over natural background radiation levels. At the nearest residence 0.8 kilometers (0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 59.9 +/- 6.2 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.8 +/- 7.3 mR. Statistically, there is no difference between these two values.Page 34 It must be emphasized that the projected ambient exposures discussed on the previous page are calculated to occur to a maximum-exposed hypothetical individual. | Although the annual exposure at TLD location OA was 124 mR above the average Zone 4 exposure, members of the general public do not continuously occupy this area. When adjusted for such occupancy, a hypothetical member of the public who was at this location for 40 hours per year would only receive an incremental dose of 0.57 mrem over natural background radiation levels. At the nearest residence | ||
===0.8 kilometers=== | |||
(0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 59.9 +/- 6.2 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.8 +/- 7.3 mR. Statistically, there is no difference between these two values.Page 34 It must be emphasized that the projected ambient exposures discussed on the previous page are calculated to occur to a maximum-exposed hypothetical individual. | |||
Even thlough conservative assumptions are made in the projection of these dose consequences, all of the projected doses are well below the NRC dose limit of 100 mrem/yr specified in 1OCFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190. | Even thlough conservative assumptions are made in the projection of these dose consequences, all of the projected doses are well below the NRC dose limit of 100 mrem/yr specified in 1OCFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190. | ||
Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.In 1994, Pilgrim Station opened the old training facility (I&S Building) overlooking the plant as a health club for its employees. | Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.In 1994, Pilgrim Station opened the old training facility (I&S Building) overlooking the plant as a health club for its employees. | ||
Line 164: | Line 191: | ||
As stated earlier, TLDs at and beyond the site boundary do not indicate elevated ambient radiation levels resulting from the operation of Pilgrim Station.Although some of the TLDs in close proximity to PNPS indicate increases in exposure levels from ambient radiation, such increases are localized to areas under Entergy control. For members of the general public who are not employed or contracted with Entergy and are accessing Entergy controlled areas (e.g., parking lots, etc.), such increases in dose from ambient radiation exposure are estimated as being less than 1.0 mrem/year. | As stated earlier, TLDs at and beyond the site boundary do not indicate elevated ambient radiation levels resulting from the operation of Pilgrim Station.Although some of the TLDs in close proximity to PNPS indicate increases in exposure levels from ambient radiation, such increases are localized to areas under Entergy control. For members of the general public who are not employed or contracted with Entergy and are accessing Entergy controlled areas (e.g., parking lots, etc.), such increases in dose from ambient radiation exposure are estimated as being less than 1.0 mrem/year. | ||
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2012 Average Exposure +/- Standard Deviation: | Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2012 Average Exposure +/- Standard Deviation: | ||
mR/period Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km- 3-8 km 8-15 km >15 km Jan-Mar 17.7 +/- 5.7 14.1 +/- 1.8 13.9 +/- 1.5 15.5 +/- 1.8 Apr-Jun 18.0 +/- 5.9 14.6 +/- 1.6 14.3 +/- 2.0 14.9 +/- 2.0 Jul-Sep 18.1 +/- 7.2 14.2 +/- 1.9 14.2 +/- 1.8 15.1 +/- 2.1 Oct-Dec 17.9 +/- 6.1 14.2 +/- 1.8 14.4 +/- 1.4 15.3 +/- 1.9 Jan-Dec 71.7 +/- 24.7** 57.1 +/- 7.1 56.7 +/- 6.4 60.8 +/- 7.3 Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 60.7 +/- 6.8 mR/yr.Page 36 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and concentration limits for radioactive effluents. | mR/period Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km- 3-8 km 8-15 km >15 km Jan-Mar 17.7 +/- 5.7 14.1 +/- 1.8 13.9 +/- 1.5 15.5 +/- 1.8 Apr-Jun 18.0 +/- 5.9 14.6 +/- 1.6 14.3 +/- 2.0 14.9 +/- 2.0 Jul-Sep 18.1 +/- 7.2 14.2 +/- 1.9 14.2 +/- 1.8 15.1 +/- 2.1 Oct-Dec 17.9 +/- 6.1 14.2 +/- 1.8 14.4 +/- 1.4 15.3 +/- 1.9 Jan-Dec 71.7 +/- 24.7** 57.1 +/- 7.1 56.7 +/- 6.4 60.8 +/- 7.3 Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 60.7 +/- 6.8 mR/yr.Page 36 | ||
===6.0 PERCENT=== | |||
OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and concentration limits for radioactive effluents. | |||
In addition, the effluent controls specified ensure that radioactive releases are maintained as low as reasonably achievable. | In addition, the effluent controls specified ensure that radioactive releases are maintained as low as reasonably achievable. | ||
The percentage of the PNPS ODCM Control limit values were determined from doses calculated in Section 4, the effluent releases summarized in Section 2, and the ODCM Control limits/objectives listed in Tables 6.1 and 6.2.The percent of applicable control limit values are provided to supplement the information provided in the Section 2 of this report. The format for the percent of applicable limits is modified from that prescribed in Regulatory Guide 1.21 (Reference | The percentage of the PNPS ODCM Control limit values were determined from doses calculated in Section 4, the effluent releases summarized in Section 2, and the ODCM Control limits/objectives listed in Tables 6.1 and 6.2.The percent of applicable control limit values are provided to supplement the information provided in the Section 2 of this report. The format for the percent of applicable limits is modified from that prescribed in Regulatory Guide 1.21 (Reference | ||
Line 180: | Line 210: | ||
7.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.22E-02 2.17E-02 2.23E-02 3.20E-02 Fraction of Limit 2.95E-01%2.90E-01%2.97E-01%4.27E-01%Annual Dose Objective | 7.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.22E-02 2.17E-02 2.23E-02 3.20E-02 Fraction of Limit 2.95E-01%2.90E-01%2.97E-01%4.27E-01%Annual Dose Objective | ||
-Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: | -Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: | ||
15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 9.82E-02 Fraction of Limit 6.55E-01%Page 39 6.2 Liquid Effluent Releases Liquid effluent concentration limits and dose objectives from the PNPS ODCM are shown in Table 6.2. The quarterly average concentrations from Table 2.3-A were used to calculate the percent concentration limits. The maximum quarterly and annual whole body and organ doses from Tables 4.3-A through 4.3-E were used to calculate the percentages shown in Table 6.2. The resulting concentrations, as well as organ and total body doses from Pilgrim Station's liquid releases during the reporting period were a small percentage of the corresponding effluent controls.Page 40 Table 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -jiCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit 0.OOE+00%0.OOE+00%O.OOE+00%0.OOE+00%O.OOE+00%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 pCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -j.Ci/mL 6.47E-10 0.OOE+00 O.OOE+00 0.OOE+00 1.60E-10 Fraction of Limit 6.47E-05%0.OOE+00%0.OOE+00%0.OOE+00%1.60E-05%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 ltCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/mL O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit O.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%Page 41 Table 6.2 (continued) | 15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 9.82E-02 Fraction of Limit 6.55E-01%Page 39 | ||
===6.2 Liquid=== | |||
Effluent Releases Liquid effluent concentration limits and dose objectives from the PNPS ODCM are shown in Table 6.2. The quarterly average concentrations from Table 2.3-A were used to calculate the percent concentration limits. The maximum quarterly and annual whole body and organ doses from Tables 4.3-A through 4.3-E were used to calculate the percentages shown in Table 6.2. The resulting concentrations, as well as organ and total body doses from Pilgrim Station's liquid releases during the reporting period were a small percentage of the corresponding effluent controls.Page 40 Table 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -jiCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit 0.OOE+00%0.OOE+00%O.OOE+00%0.OOE+00%O.OOE+00%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 pCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -j.Ci/mL 6.47E-10 0.OOE+00 O.OOE+00 0.OOE+00 1.60E-10 Fraction of Limit 6.47E-05%0.OOE+00%0.OOE+00%0.OOE+00%1.60E-05%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 ltCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/mL O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit O.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%Page 41 Table 6.2 (continued) | |||
Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: | Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: | ||
1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 O.OOE+00 O.OOE+00 Fraction of Limit 6.17E-06%0.OOE+00%0.OOE+00%0.OOE+00%E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: | 1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 O.OOE+00 O.OOE+00 Fraction of Limit 6.17E-06%0.OOE+00%0.OOE+00%0.OOE+00%E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective: | ||
3 mrem Total Body Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 3.06E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: | 3 mrem Total Body Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 3.06E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective: | ||
5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 0.OOE+00 S0.OOE+00 Fraction of Limit 1.85E-06%0.OOE+00%0.OOE+00%0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: | 5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 0.OOE+00 S0.OOE+00 Fraction of Limit 1.85E-06%0.OOE+00%0.OOE+00%0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective: | ||
10 mrem Organ Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 9.19E-07%Page 42 7.0 RADIOACTIVE WASTE DISPOSAL DATA Radioactive wastes that were shipped offsite for processing and disposal during the reporting period are described in Table 7.0, in the standard NRC Regulatory Guide 1.21 format.The total quantity of radioactivity in Curies and the total volume in cubic meters are summarized in Table 7.0 for the following waste categories: | 10 mrem Organ Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 9.19E-07%Page 42 | ||
===7.0 RADIOACTIVE=== | |||
WASTE DISPOSAL DATA Radioactive wastes that were shipped offsite for processing and disposal during the reporting period are described in Table 7.0, in the standard NRC Regulatory Guide 1.21 format.The total quantity of radioactivity in Curies and the total volume in cubic meters are summarized in Table 7.0 for the following waste categories: | |||
* Spent resins, filter sludges, and evaporator bottoms;* Dry activated wastes, contaminated equipment, etc.;* Irradiated components, control rods, etc.; and,* Other.During the reporting period approximately 54.6 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 779 Curies were shipped from PNPS for processing and disposal. | * Spent resins, filter sludges, and evaporator bottoms;* Dry activated wastes, contaminated equipment, etc.;* Irradiated components, control rods, etc.; and,* Other.During the reporting period approximately 54.6 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 779 Curies were shipped from PNPS for processing and disposal. | ||
Dry activated wastes and contaminated equipment shipped during the period totaled 412 cubic meters and contained 0.56 Curies of radioactivity. | Dry activated wastes and contaminated equipment shipped during the period totaled 412 cubic meters and contained 0.56 Curies of radioactivity. | ||
Line 196: | Line 233: | ||
Erwin, TN Tractor-trailer Studsvik/RACE, LLC z (Hittman Transport) | Erwin, TN Tractor-trailer Studsvik/RACE, LLC z (Hittman Transport) | ||
Memphis, TN This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.Remaining radioactive wastes will be shipped to Chem Nuclear Systems, Inc. in Barnwell, SC, or Envirocare, Inc.in Clive, UT for final disposal.B. IRRADIATED FUEL SHIPMENTS | Memphis, TN This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.Remaining radioactive wastes will be shipped to Chem Nuclear Systems, Inc. in Barnwell, SC, or Envirocare, Inc.in Clive, UT for final disposal.B. IRRADIATED FUEL SHIPMENTS | ||
& DISPOSITION Number of Shipments Mode of Transportation Destination None N/A N/A Page 44 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS The PNPS Offsite Dose Calculation Manual (ODCM) was not revised during the calendar year of 2012. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45 9.0 PROCESS CONTROL PROGRAM REVISIONS There were no changes to the PNPS Process Control Program (PCP) during the calendar year of 2012. Although Pilgrim Station adopted the Entergy fleet-wide PCP in 2010 as indicated in the 2010 Annual Effluent Release Report, fleet procedure EN-RW-105, "Process Control Program", was not revised until 2011 to reflect the inclusion of Pilgrim Station under the fleet-wide PCP. This revision was strictly administrative in nature, and did not impact the requirements or conduct of the PCP.Page 46 | & DISPOSITION Number of Shipments Mode of Transportation Destination None N/A N/A Page 44 | ||
===8.0 OFFSITE=== | |||
DOSE CALCULATION MANUAL REVISIONS The PNPS Offsite Dose Calculation Manual (ODCM) was not revised during the calendar year of 2012. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45 | |||
===9.0 PROCESS=== | |||
CONTROL PROGRAM REVISIONS There were no changes to the PNPS Process Control Program (PCP) during the calendar year of 2012. Although Pilgrim Station adopted the Entergy fleet-wide PCP in 2010 as indicated in the 2010 Annual Effluent Release Report, fleet procedure EN-RW-105, "Process Control Program", was not revised until 2011 to reflect the inclusion of Pilgrim Station under the fleet-wide PCP. This revision was strictly administrative in nature, and did not impact the requirements or conduct of the PCP.Page 46 | |||
==10.0 REFERENCES== | ==10.0 REFERENCES== |
Revision as of 01:41, 13 October 2018
ML13141A480 | |
Person / Time | |
---|---|
Site: | Pilgrim |
Issue date: | 05/14/2013 |
From: | Lynch J R Entergy Nuclear Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
2.13.045 | |
Download: ML13141A480 (77) | |
Text
SEn tergy Entergy Nuclear Operations, Inc.600 Rocky Hill Road Plymouth, MA 02360 Pilgrim Nuclear Power Station May 14, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35 Annual Radioactive Effluent Release Report for January 1 through December 31, 2012 LETTER NUMBER: 2.13.045
Dear Sir or Madam:
In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations, Inc submits the attached Annual Radioactive Effluent Release Report for January 1, 2012 through December 31, 2012.This letter contains no commitments.
Should you have questions or require additional information, I can be contacted at (508) 830-8403.Sincerely, Licensing Manager
Attachment:
Pilgrim Annual Radioactive Effluent Release Report for January 1, 2012 through December 31, 2012 cc: U.S. Nuclear Regulatory Commission Region 1 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 USNRC Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 11555 Rockville Pike Rockville, MD. 20852-r1q Attachment I Letter Number 2.13.045 Pilgrim Annual Radioactive Effluent Release Report for January 1, 2012 through December 31, 2012 PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2012*Entergy Ente&gy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2012 Prepared by: K.1i. Sejkora- -, /'Senior HP/Chemistry Specialist S&I Reviewed by: Reviewed by: 6W." Blankenbiller Chemistry Manager.E. Brewer Radiation Protection Manager Page 2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2012 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 2.0 2.1 2.2 2.3 3.0 4.0 4.1 4.2 4.3 5.0 6.0 6.1 6.2 7.0 8.0 9.0 10.0 APPENDIX A APPENDIX B APPENDIX C APPENDIX D EXECUTIVE
SUMMARY
RADIOACTIVE EFFLUENT DATA Supplemental Effluent Release Data Gaseous Effluent Data Liquid Effluent Data METEOROLOGICAL DATA MAXIMUM INDIVIDUAL DOSES Doses From Noble Gas Releases Doses From Gaseous Effluent Releases Doses From Liquid Effluent Releases OFFSITE AMBIENT RADIATION MEASUREMENTS PERCENT OF ODCM EFFLUENT CONTROL LIMITS Gaseous Effluent Releases Liquid Effluent Releases RADIOACTIVE WASTE DISPOSAL DATA OFFSITE DOSE CALCULATION MANUAL REVISIONS PROCESS CONTROL PROGRAM REVISIONS REFERENCES Meteorological Joint Frequency Distributions Onsite Groundwater Monitoring Program Corrections to Previous Effluent Reports Changes to PNPS Offsite Dose Calculation Manual 5 8 8 8 9 19 20 20 22 28 34 37 37 40 43 45 46 47 48 69 74 75 Page 3 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2012 LIST OF TABLES TABLE TABLE TITLE PAGE 2.1 Supplemental Information 10 2.2-A Gaseous Effluents
-Summation of All Releases 11 2.2-B Gaseous Effluents
-Elevated Releases 12 2.2-C Gaseous Effluents
-Ground Level Releases 14 2.3-A Liquid Effluents
-Summation of All Releases 16 2.3-B Liquid Effluents 17 4.1 Maximum Doses from Noble Gas Releases During 2012 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2012 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2012 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 Jul-Sep 2012 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2012 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2012 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2012 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2012 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2012 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2012 4.3-E Maximum Individual Organ Doses from Liquid Effluents 33 Jan-Dec 2012 5.0 Average TLD Exposures by Distance Zone During 2012 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2012 6.2 Percent of ODCM Effluent.Control Limits for Liquid Effluent Releases 41 During 2012 7.0 Solid Waste and Irradiated Fuel Shipments 44 A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 48 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 58 220-ft Level of the 220-ft Tower Page 4 EXECUTIVE
SUMMARY
PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2012 INTRODUCTION This report quantifies the radioactive gaseous, liquid, and radwaste releases, and summarizes the local meteorological data for the period from January 01 through December 31, 2012. This document has been prepared in accordance with the requirements set forth in the Pilgrim Nuclear Power Station (PNPS) Technical Specifications and Revision 1 of Regulatory Guide 1.21,"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants". This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3.The quantity of radioactive material released from PNPS was determined from sample analyses and continuous on-line monitoring of gaseous releases from the main stack, reactor building vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal.The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation.
The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station.GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 0.65 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0041 Curies, tritium releases totaled 29.7 Curies, and carbon-14 totaled 8.6 Curies. No gross alpha radioactivity was detected in gaseous effluents.
Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.000017 mrem, with a corresponding skin dose of 0.000090 mrem. The release of radioactive particulates, iodines, tritium, and carbon-14 in gaseous effluents from PNPS during the reporting period resulted in a total body dose to the maximum-exposed hypothetical individual of about 0.027 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.098 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.027 mrem.The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 0.00047% of the corresponding 1 OCFR50 dose objectives.
Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.66% of corresponding 10CFR50 objectives.
Page 5 LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B. Five discharges of liquid effluents containing radioactivity occurred during the reporting period. These discharges contained 0.099 Curies of tritium. There were no detectable fission and activation products.
The resulting maximum total body dose was 0.0000000919 mrem, with a corresponding organ dose of 0.0000000919 mrem. All doses from liquid discharges were less than 0.0000031%
of corresponding 10CFR50 objectives.
METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 66% for the 33-ft and 100% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 14% of the time during the reporting period. The predominant stability class was Class D, which occurred about 51% of the time during the reporting period OFFSITE AMBIENT RADIATION MEASUREMENTS Ambient radiation exposure was evaluated to complete the assessment of radiological impact on humans. A small number of thermoluminescent dosimeters (TLDs) indicated an elevation in ambient radiation exposure on Entergy property in close proximity to the station, when compared to background levels in the region. This elevation is due to nitrogen-16 contained within the plant steam system, as opposed to radioactive effluent released from the plant. The dose to the maximum-exposed member of the public at the PNPS Health Club, even though they are within the owner-controlled area, was estimated as being about 1.4 mrem during 2012. There was no measurable increase during 2012 in ambient radiation measurements at the location of the nearest resident 0.8 km southeast of PNPS.COMBINED DOSE IMPACT The collective total body dose to a maximum-exposed hypothetical member of the public from airborne radioactivity, liquid-borne radioactivity, and ambient radiation exposure resulting from PNPS operation during 2012 was calculated as being about 0.60 mrem. This amount is about 0.17% of the typical dose of 300 to 400 mrem received each year by an average person from other sources of natural and man-made radiation.
Although this calculated collective dose occurs to a maximum-exposed hypothetical individual, it is also well below the NRC dose limit of 100 mrem/yr specified in 10CFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190.Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.RADIOACTIVE SOLID WASTE DISPOSAL Solid radioactive wastes shipped offsite for processing and disposal during the reporting period are described in Table 7.0. Approximately 467 cubic meters of solid waste, containing almost 780 Curies of radioactivity, were shipped during the reporting period.Page 6 ONSITE GROUNDWATER MONITORING PROGRAM In response to the Nuclear Energy Institute Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007. Four monitoring wells were installed onsite during the fourth quarter of 2007, and the first samples were collected in late November 2007. Additional sampling wells were added in 2010, 2011, and 2012. As of the end of 2012, samples are being collected from a total of 21 monitoring wells. Low levels of tritium, a radioactive isotope of hydrogen, were detected in several of these onsite wells. No other plant-related radioactivity was detected in the samples. Concentrations of tritium ranged from non-detectable at less than 337 picoCuries per Liter up to 8,400 picoCuries per Liter. The average concentration of tritium detected in these onsite monitoring wells was well below the voluntary communications reporting level established by the EPA Drinking Water Standard of 20,000 pCi/L. Although the EPA Standard provides a standard for comparison, no drinking water sources are affected by this tritium.Results of the groundwater monitoring program are presented in Appendix B.CONCLUSION The PNPS Offsite Dose Calculation Manual contains effluent controls to limit doses resulting from releases of radioactivity to the environment.
None of the effluent controls associated with liquid or gaseous effluents were exceeded during the reporting period, as confirmed by conservative dose assessments performed at weekly and monthly intervals.
Conformance to the PNPS ODCM effluent control limits ensures that releases of radioactivity in liquid and gaseous effluents are kept as low as reasonably achievable in accordance with 10 CFR Part 50, Appendix I. Compliance with the ODCM also demonstrates that requirements of the Environmental Protection Agency's nuclear fuel cycle standard, 40CFR190.10, Subpart B, have been met. Based on the dose assessment results for 2012, there was no significant radiological impact on the general public from PNPS operation.
Page 7
2.0 RADIOACTIVE
EFFLUENT DATA Radioactive gaseous and liquid releases for the reporting period are given in the standard format presented in Tables 1A, 1B, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference
- 1) format.2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1.2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities.
Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows:* Noble gases: 0.65 Ci, 0.021 gCi/sec* lodines and particulates with 0.0041 Ci, 0.00013 iiCi/sec half-life greater than 8 days" Tritium: 29.7 Ci, 0.94 I.Ci/sec" Carbon-14:
8.6 Ci, 0.27 uCi/sec Effluent releases from the main stack are detailed in Table 2.2-B. The main stack is 335 feet tall, and represents an elevated release point with a total height of approximately 400 feet above sea level. The main stack is located about 700 feet west-northwest of the reactor building.Ground-level effluent releases are detailed in Table 2.2-C. Data in this table include releases from the reactor building vent, turbine building, and assorted equipment decontamination facilities (e.g., hot machine shop, carbon dioxide pellet decon trailer, plastic media decon trailer, etc.) used during the period. Due to the close proximity of the reactor building, all of these release points are considered to be mixed-mode/ground level release points.Following the revision of Regulatory Guide 1.21 in 2009, the nuclear industry re-assessed their gaseous effluent releases in accordance with the new definition of "principal radionuclide".
Under this new definition, any radionuclide that contributed greater than 1% of the effluent dose calculated to demonstrate compliance with 10CFR50 Appendix I, or contributed more than 1% of the total activity for that type of effluent release, would be classified as a principal radionuclide.
Although Carbon-14 (C-14) had been exempted from gaseous effluent calculations in the 1970s, industry assessments in 2009 revealed that Carbon-14 would qualify as a principal radionuclide.
Based on this 2009 re-assessment, licensees were required to begin reporting C-14 gaseous effluents in the Annual Radioactive Effluent Release Report beginning with calendar-year 2010. Carbon-14 releases for 2012 are summarized in Tables 2.2-A through 2.2-C, and the dose consequences from C-14 are incorporated into the dose assessments documented in Section 4.2 of this report.Page 8
2.3 Liquid
Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building.Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were five discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows: " Total Effluent Volume: 180,000 Liters" Total Dilution Volume: 616 billion Liters* Fission/Activation products:
0.00 Ci, 0.00 [.Ci/mL" Tritium: 0.0988 Ci, 0.000000000160
[tCi/mL" Dissolved/entrained noble gases: 0.00 Ci, 0.00 ýiCi/mL One discrepancy was noted with the analysis of radioactivity contained in liquid effluents discharged in 2012. The monthly composite sample collected from the five neutralizing sump discharges that occurred in January 2012 was not shipped to the vendor laboratory for the monthly analysis of tritium and gross alpha activity, and the quarterly analysis of Iron-55 and Strontium-89/90. This discrepancy is described in Condition Report CR-PNP-2013-1538.
These five discharges were in support of feed-and-bleed activities to reduce chloride levels in the Turbine Building Closed Cooling Water (TBCCW) system. Each of the five discharges was analyzed for gamma radioactivity prior to discharge, and no detectable gamma activity was identified in any of the samples. In addition, no gamma activity has been detected in routine sampling of the TBCCW system. Therefore, it is reasonable to conclude that there would be no detectable activity of gross alpha, Fe-55, or Sr-89/90, as these would have been co-indicated by the presence of gamma-emitting nuclides such as Mn-54, Co-60, and Cs-137, which were not detected in any of the samples. In addition, tritium samples were being collected from the TBCCW during the month of January to monitor the feed-and-bleed operation.
Tritium levels in TBCCW during this period ranged from 0.000357 uCi/mL to 0.000843 uCi/mL, for an average concentration of 0.000548 uCi/mL. Based on this average tritium concentration, the total quantity of tritium discharged during the period was 0.0988 Curies.Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2012 FACILITY:
PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35 1. REGULATORY LIMITS a. Fission and activation gases: 500 mrem/yr total body and 3000 mrem/yr for skin at site boundary b,c. lodines, particulates with half-life:
1500 mrem/yr to any organ at site boundary>8 days, tritium d. Liquid effluents:
0.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)
- 2. EFFLUENT CONCENTRATION LIMITS a. Fission and activation gases: 1OCFR20 Appendix B Table II b. lodines: 10CFR20 Appendix B Table II c. Particulates with half-life
> 8 days: 10CFR20 Appendix B Table II d. Liquid effluents:
2E-04 pCi/mL for entrained noble gases;1OCFR20 Appendix B Table II values for all other radionuclides
- 3. AVERAGE ENERGY Not Applicable
- 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY
- a. Fission and activation gases: High purity germanium gamma spectroscopy for all b. lodines: gamma emitters; radiochemistry analysis for H-3, c. Particulates:
Fe-55 (liquid effluents), Sr-89, and Sr-90 d. Liquid effluents:
- 5. BATCH RELEASES Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec 2012 2012 2012 2012 2012 a. Liquid Effluents 1. Total number of releases:
5 0 0 0 5 2. Total time period (minutes):
5.45E+02 N/A N/A N/A 5.45E+02 3. Maximum time period (minutes):
1.35E+02 N/A N/A N/A 1.35E+02 4. Average time period (minutes):
1.09E+02 N/A N/A N/A 1.09E+02 5. Minimum time period (minutes):
9.50E+01 N/A N/A N/A 9.50E+01 6. Average stream flow during periods of release of 1.17E+06 N/A N/A N/A 1.17E+06 effluents into a flowing stream (Liters/min):
- b. Gaseous Effluents None None None None None 6. ABNORMAL RELEASES a. Liquid Effluents None None None None None b. Gaseous Effluents None None None None None Page 10 Table 2.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Summation of All Releases January-December 2012 Est.RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2012 2012 2012 2012 2012 Error A. FISSION AND ACTIVATION GASES Total Release: Ci 0.00E+00 1.54E-01 2.61E-01 2.35E-01 6.50E-01 Average Release Rate: pCi/sec 0.00E+00 1.95E-02 3.31 E-02 2.98E-02 2.06E-02 _+/-22%Percent of Effluent Control Limit* .....B. IODINE-131 Total Iodine-131 Release: Ci 1.77E-04 2.OOE-04 2.29E-04 1.78E-04 7.83E-04 Average Release Rate: pCCi/sec 2.24E-05 2.53E-05 2.90E-05 2.26E-05 2.48E-05 +/-20%Percent of Effluent Control Limit* ......C. PARTICULATES WITH HALF-LIVES
> 8 DAYS Total Release: Ci 3.69E-04 1.06E-04 2.08E-04 4.02E-04 1.08E-03 Average Release Rate: pCi/sec 4.68E-05 1.34E-05 2.64E-05 5.1OE-05 3.44E-05 Percent of Effluent Control Limit* .....Gross Alpha Radioactivity:
Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 4.62E+00 9.37E+00 6.95E+00 8.79E+00 2.97E+01 Average Release Rate: gCi/sec 5.86E-01 1.19E+00 8.82E-01 1.12E+00 9.43E-01 +/-20%Percent of Effluent Control Limit* .....E. CARBON-14 Total Release: Ci 2.09E+00 2.05E+00 2.12E+00 2.30E+00 8.55E+00 Average Release Rate: gCi/sec 2.65E-01 2.60E-01 2.68E-01 2.91E-01 2.71E-01 N/A Percent of Effluent Control Limit* .....Notes for Table 2.2- A:* Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.1. NDA stands for No Detectable Activity.2. LLD for airborne gross alpha activity listed as NDA is 1 E-1 1 [tCi/cc.3. N/A stands for not applicable.
Page 11 Table 2.2-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Elevated Release January-December 2012 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2012 Apr-Jun 2012-T Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-85 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Kr-85m 0.OOE+00 2.15E-02 2.99E-02 0.OOE+00 5.14E-02 Kr-87 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-88 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 0.OOE+00 Xe-131m 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-133 0.OOE+00 1.15E-01 2.31E-01 0.OOE+00 3.46E-01 Xe-133m 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-135 0.00E+00 1.69E-02 0.OOE+00 0.OOE+00 1.69E-02 Xe-135m 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-1 37 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Xe-1 38 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period 0.OOE+00 1.54E-01 2.61E-01 0.00E+00 4.15E-01 2. IODINES: Ci 1-131 8.59E-06 1.11E-05 1.28E-05 6.06E-06 3.86E-05 1-133 3.1OE-06 6.98E-06 1.71E-05 0.OOE+00 2.72E-05 Total for Period 1.17E-05 1.81 E-05 3.00E-05 6.06E-06 6.58E-05 3. PARTICULATES WITH HALF-LIVES
> 8 DAYS: Ci Cr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Fe-59 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Co-60 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Zn-65 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Ru-103 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Cs-134 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba/La-140 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 4. TRITIUM: Ci H-3 2.69E-02 2.41E-02 2.52E-02 2.38E-02 1.00E-01 5. CARBON-14:
Ci C-14 2.03E+00 1.99E+00 2.05E+00 2.23E+00 8.29E+00 Notes for Table 2.2-B: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for airborne radionuclides listed as NDA are as follows: Fission Gases: 1 E-04 pCi/cc lodines: 1 E-12 pCi/cc Particulates:
1E-11 pCi/cc Page 12 Table 2.2-B (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Elevated Release January-December 2012 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2012 Apr-Jun 2012 Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-1 33 N/A N/A N/A N/A N/A Xe-1 33m N/A N/A N/A N/A N/A Xe-1 35 N/A N/A N/A N/A N/A Xe-1 35m N/A N/A N/A N/A N/A Xe-1 37 N/A N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 3. PARTICULATES WITH HALF-LIVES
> 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A 5. CARBON-14:
Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-B: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for airborne radionuclides listed as NDA are as follows: Fission Gases: 1 E-04 piCi/cc lodines: 1 E-12 IXCi/cc Particulates:
1 E-11 p 1 Ci/cc Page 13 Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Ground-Level Release January-December 2012 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar 2012 Apr-Jun 2012 Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-85 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Kr-85m O.00E+00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 Kr-87 0.00E+00 O.00E+00 O.00E+00 O.OOE+00 O.OOE+00 Kr-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-131 m O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Xe-1 33 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-1 33m O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Xe-1 35 O.OOE+00 0.00E+00 O.OOE+00 2.35E-01 2.35E-01 Xe-1 35m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total for period 0.OOE+00 O.OOE+00 O.OOE+00 2.35E-01 2.35E-01 2. IODINES: Ci 1-131 1.68E-04 1.88E-04 2.16E-04 1.72E-04 7.45E-04 1-133 4.96E-04 4.59E-04 6.87E-04 5.75E-04 2.22E-03 Total for period 6.64E-04 6.47E-04 9.03E-04 7.47E-04 2.96E-03 3. PARTICULATES WITH HALF-LIVES
> 8 DAYS: Ci Cr-51 2.84E-06 O.OOE+00 0.00E+00 0.OOE+00 2.84E-06 Mn-54 1.16E-05 0.OOE+00 2.15E-06 O.OOE+00 1.38E-05 Fe-59 1.45E-06 O.OOE+00 0.OOE+00 0.00E+00 1.45E-06 Co-58 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Co-60 6.21 E-06 0.OOE+00 9.01E-07 O.OOE+00 7.11E-06 Zn-65 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 2.95E-05 3.29E-05 1.57E-05 3.95E-04 4.73E-04 Sr-90 0.OOE+00 O.OOE+00 O.OOE+00 7.26E-06 7.26E-06 Ru-103 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Cs-134 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cs-137 3.38E-06 O.OOE+00 O.OOE+00 1.60E-07 3.54E-06 Ba/La-140 3.14E-04 7.30E-05 1.89E-04 O.OOE+00 5.76E-04 Total for period 3.69E-04 1.06E-04 2.08E-04 4.02E-04 1.08E-03 4. TRITIUM: Ci H-3 4.59E+00 9.35E+00 6.93E+00 8.77E+00 2.96E+01 5. CARBON-14:
Ci C-14 6.27E-02 6.15E-02 6.35E-02 6.89E-02 2.57E-01 Notes for Table 2.2-C: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for airborne radionuclides listed as NDA are as follows: Fission Gases: 1 E-04 iiCi/cc lodines: 1 E-12 iiCi/cc Particulates:
1E-11 p.Ci/cc Page 14 Table 2.2-C (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Ground-Level Release January-December 2012 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar 2012 Apr-Jun 2012 Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe-i 37 N/A N/A N/A N/A N/A Xe- 138 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 3. PARTICULATES WITH HALF-LIVES
> 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A N/A Cs- 134 N/A N/A N/A N/A N/A Cs- 137 N/A N/A N/A N/A N/A Ba/La- 140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A 5. CARBON-14:
Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-C: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for airborne radionuclides listed as NDA are as follows: Fission Gases: 1 E-04 pCi/cc lodines: 1 E-12 pCi/cc Particulates:
1E-11 plCi/cc Page 15 Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents
-Summation of All Releases January-December 2012 Est.RELEASE PERIOD Jan-Mar Apr-Jun Ju1-Sep Oct-Dec Jan-Dec Total 2012 2012 2012 2012 2012 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including NDA N/A N/A N/A NDA tritium, gases, alpha): Ci Average Diluted Concentration NDA N/A N/A N/A NDA +/-12%During Period: tiCi/mL Percent of Effluent Concentration Limit* 0.00E+00%
N/A N/A N/A 0.00E+00%B. TRITIUM Total Release: Ci 9.88E-02 N/A N/A N/A 9.88E-02 During Period: jiCi/mL +/-9.4%Percent of Effluent Concentration 6.47E-05%
N/A N/A N/A 1.60E-05%Limit*C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA N/A N/A N/A NDA Average Diluted Concentration NDA N/A N/A N/A NDA During Period: gCi/mL +/-16%Percent of Effluent Concentration O.OOE+OO%
N/A N/A N/A O.OOE+OO%Limit* 0.00E+00%
N/A N/A N/A 0.00__00%D. GROSS ALPHA RADIOACTIVITY Total Release: Ci NDA N/A N/A N/A NDA +/-34%E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters 1.80E+05 0.OOE+00 0.OOE+00 0.OOE+00 1.80E+05 +/-5.7%F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters I 1.53E+11 I 1.53E+11 I 1.55E+11 1.55E+11 6.16E+11 +/-10%Notes for Table 2.3-A:* Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLD for dissolved and entrained gases listed as NDA is 1E-05 p.Ci/mL.4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 jiCi/mL.Page 16 Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2012 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2012 Apr-Jun 2012 Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION PRODUCTS:
Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-55 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Zn-69m N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Zr/Nb-95 N/A N/A N/A N/A N/A Mo/Tc-99 N/A N/A N/A N/A N/A Ag-110m N/A N/A N/A N/A N/A Sb-124 N/A N/A N/A N/A N/A 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Ce-141 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A Notes for Table 2.3-B: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for liquid radionuclides listed as NDA are as follows: Strontium:
5E-08 pLCi/mL lodines: 1E-06 Noble Gases: 1 E-05 p.Ci/mL All Others: 5E-07 gCi/mL Page 17 Table 2.3-B (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2012 BATCH MODE RELEASES Nuclide Released Jan-Mar 2012 Apr-Jun 2012 Jul-Sep 2012 Oct-Dec 2012 Jan-Dec 2012 1. FISSION AND ACTIVATION PRODUCTS:
Ci Na-24 NDA N/A N/A N/A NDA Cr-51 NDA N/A N/A N/A NDA Mn-54 NDA N/A N/A N/A NDA Fe-55 NDA N/A N/A N/A NDA Fe-59 NDA N/A N/A N/A NDA Co-58 NDA N/A N/A N/A NDA Co-60 NDA N/A N/A N/A NDA Zn-65 NDA N/A N/A N/A NDA Zn-69m NDA N/A N/A N/A NDA Sr-89 NDA N/A N/A N/A NDA Sr-90 NDA N/A N/A N/A NDA Zr/Nb-95 NDA N/A N/A N/A NDA Mo/Tc-99 NDA N/A N/A N/A NDA Ag-110m NDA N/A N/A N/A NDA Sb-124 NDA N/A N/A N/A NDA 1-131 NDA N/A N/A N/A NDA 1-133 NDA N/A N/A N/A NDA Cs-134 NDA N/A N/A N/A NDA Cs-137 NDA N/A N/A N/A NDA Ba/La-140 NDA N/A N/A N/A NDA Ce-141 NDA N/A N/A N/A NDA Ce-144 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 NDA N/A N/A N/A NDA Xe-1 35 NDA N/A N/A N/A NDA Total for period NDA N/A N/A N/A NDA Notes for Table 2.3-B: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.3. LLDs for liquid radionuclides listed as NDA are as follows: Strontium:
5E-08 jiCi/mL lodines: 1E-06 p.Ci/m L Noble Gases: 1E-05 ptCi/mL All Others: 5E-07 ýiCi/mL Page 18
3.0 METEOROLOGICAL
DATA Meteorological data are summarized for the reporting period in Appendix A, in the standard joint frequency distribution format as given in NRC Regulatory Guide 1.21.The predominant meteorological conditions observed during the annual reporting period can be summarized with their corresponding frequencies as follows: " Stability Class: Class D, 51%* 33-ft Wind Direction (from): South-southwest, 15%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 14%* 220-ft Wind Speed: 12.5-18.5 mph, 35%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 66%, which did not meet the 90% annual data recovery goal specified by the NRC. A break occurred in the wiring supplying power to the aspirator fan in the upper-level temperature sensor on 18-Mar-2012 and was repaired on 19-Jul-2012.
This event is described in Condition Reports CR-PNP-2012-2884 and CR-PNP-2012-4759.
This resulted in invalid delta-temperature readings during this period, for a loss of 2954 hours0.0342 days <br />0.821 hours <br />0.00488 weeks <br />0.00112 months <br /> of joint data for the year. Although the loss of the delta-temperature data affected the calculation of atmospheric stability class, wind speed and wind direction data were unaffected and were used to summarize wind speed and wind direction values for the quarterly and annual summary tables.Page 19
4.0 MAXIMUM
INDIVIDUAL DOSES Doses to the maximum exposed individual resulting from radionuclides in effluents released offsite were calculated using methods presented in the PNPS Offsite Dose Calculation Manual (ODCM, Reference 2), NRC Regulatory Guide 1.109 (Reference 3), NRC Regulatory Guide 1.111 (Reference 4), and the Pilgrim Station Unit 1 Appendix I Evaluation (Reference 5). Maximum individual doses are calculated separately for: (1) noble gases in gaseous effluents, (2) particulates, iodines, and tritium in gaseous effluents; and, (3) liquid effluents.
Maximum consumption and use factors for various pathways from Table E-5 of the PNPS ODCM are used for calculating the doses to the maximum exposed individual.
Information related to liquid and gaseous effluent releases are summarized Section 2 of this report.These effluent release data were used as input to computer programs to calculate the resulting doses. PNPS ODCM methodologies were used to calculate the dose contributions to the various organs in each age class from major exposure pathways.4.1 Doses From Noble Gas Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters.
Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the"AEOLUS-3" computer program (Reference 6). This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.The maximum individual doses resulting from radioactive noble gases released in gaseous effluents are presented in Table 4.1 according to specific receptor locations.
This table includes all noble gas doses for the individual calendar quarters and total calendar year.Noble gases released in gaseous effluents from PNPS during 2012 resulted in a maximum total body dose of 0.000017 mrem. The maximum skin dose was 0.000090 mrem. Both of these doses occurred to a hypothetical individual, assumed to be present 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 365 days per year, at the site boundary location yielding the highest dose (0.64 km ESE of the Reactor Building).
For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.000013 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.000062 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building).
Page 20 Table 4.1 Maximum Doses From Noble Gas Releases Durina 2 0 1 2 (a)Gamma Beta Total Release Air Dose Air Dose Body Dose Skin Dose Period mrad/period mrad/period mrem/period mrem/period (location) (location) (location) (location)
Jan-Mar 0.00E+00 0.O0E+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)5.78E-07 8.89E-07, 3.64E-07 8.75E-07 Apr-Jun (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)6.88E-07 1.31E-06 4.19E-07 1.03E-06 Jul-Sep (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW)Oct-Dec 2.50E-05 9.27E-05 1.65E-05 8.96E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 2.58E-05 9.31E-05 1.70E-05 9.03E-05 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)(a) All directions and distances are with respect to the reactor building vent.Page 21
4.2 Doses
From Gaseous Effluent Releases Gaseous effluent release data presented in Tables 2.2-A, 2.2-B, and 2.2-C from this effluent release report were used as input to a dose assessment computer program to calculate radiation doses. These data include gaseous releases from the PNPS main stack, reactor building vent, and turbine building roof exhausters.
Meteorological data obtained from the PNPS 220-foot meteorological tower during the 10-year period from 1994 through 2003 were used as input to the"AEOLUS-3" computer program (Reference 6). This program was used to calculate the annual average atmospheric dispersion and deposition factors used in the dose assessment computer program to calculate maximum individual doses.The maximum individual doses resulting from radioactive particulates, radioiodines, tritium and carbon-14 released in gaseous effluents are presented in Tables 4.2-A through 4.2-E. These tables cover the individual calendar quarters and the total calendar year, respectively.
Doses resulting from releases of noble gases are addressed independently in the PNPS ODCM.Therefore, none of these tables for maximum individual doses include any dose contribution from noble gases. The presentation and analysis of doses resulting from noble gases are addressed in Section 4.1 of this report.Tables 4.2-A through 4.2-E summarize the maximum total body and organ doses for the adult, teen, child, and infant age classes resulting from the major gaseous exposure pathways.
These tables present the dose data according to specific receptor location and the exposure pathways assumed to occur at that location.
For example, the second column of the tables presents the information for the hypothetical maximum-exposed at the most restrictive site boundary location, where only inhalation and ground deposition exposure pathways are assumed to occur. Since this is a shoreline location controlled by Entergy, the other pathways of garden vegetable production, milk production, and meat production are assumed not to occur. Doses for other offsite locations not under Entergy control, where other exposure pathways can and do occur, are presented in subsequent columns of the tables, and represent the potential maximum doses to individuals at these locations.
For consistency, all distances listed in the first row of Tables 4.2-A through 4.2-E are measured from the Reactor Building Vent. However, doses at the specific receptor locations are calculated based on the actual distances from the applicable release points (PNPS main stack, reactor building vent, and turbine building roof exhausters).
Radioactivity (particulates, radioiodines, tritium, and carbon-14) released in gaseous effluents from PNPS during 2012 resulted in a maximum total body dose of 0.027 mrem (child age class at nearest garden location, 0.84 kilometers SE from the Reactor Building), while the maximum organ dose was 0.098 mrem (child bone at nearest garden location, 0.84 kilometers SE from the Reactor Building).
Carbon-14 contributed 0.018 mrem (66%) of the 0.027 mrem child total body dose, and 0.089 mrem (91%) of the 0.098 mrem child bone dose at the location of the nearest garden.Page 22 Table 4.2-A Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Mar 2012 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NW ESE SE WSW W S Distance 1: 0.54 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV 3 DIVCG' DIVCM 3 DIVM'Age Class: Adult Bone 1.92E-04 1.43E-04 5.74E-03 2.29E-03 2.OOE-03 3.48E-03 GI-LLI 5.66E-04 3.85E-04 2.08E-03 5.35E-04 4.47E-04 7.52E-04 Kidney 5.52E-04 3.75E-04 2.05E-03 5.35E-04 4.46E-04 7.49E-04 Liver 5.51 E-04 3.74E-04 2.05E-03 5.35E-04 4.46E-04 7.50E-04 Lung 5.94E-04 4.03E-04 2.06E-03 5.34E-04 4.46E-04 7.50E-04 Thyroid 9.93E-04 6.67E-04 3.17E-03 8.71 E-04 6.27E-04 8.24E-04 T.Body 5.49E-04 3.73E-04 2.05E-03 5.34E-04 4.46E-04 7.49E-04 Age Class: Teen Bone 2.75E-04 2.05E-04 9.27E-03 3.85E-03 3.02E-03 4.91E-03 GI-LLI 5.87E-04 4.OOE-04 2.87E-03 8.58E-04 6.55E-04 1.04E-03 Kidney 5.73E-04 3.90E-04 2.84E-03 8.59E-04 6.55E-04 1.04E-03 Liver 5.71E-04 3.89E-04 2.85E-03 8.59E-04 6.55E-04 1.04E-03 Lung 6.41E-04 4.35E-04 2.87E-03 8.57E-04 6.55E-04 1.04E-03 Thyroid 1.13E-03 7.62E-04 3.87E-03 1.35E-03 9.17E-04 1.1OE-03 T.Body 5.69E-04 3.88E-04 2.84E-03 8.57E-04 6.54E-04 1.04E-03 Age Class: Child Bone 3.79E-04 2.83E-04 2.22E-02 9.28E-03 7.11E-03 1.13E-02 GI-LLI 5.36E-04 3.67E-04 5.78E-03 1.98E-03 1.49E-03 2.34E-03 Kidney 5.31E-04 3.64E-04 5.77E-03 1.98E-03 1.49E-03 2.34E-03 Liver 5.30E-04 3.63E-04 5.78E-03 1.98E-03 1.49E-03 2.34E-03 Lung 5.89E-04 4.02E-04 5.78E-03 1.98E-03 1.49E-03 2.34E-03 Thyroid 1.20E-03 8.06E-04 7.24E-03 2.93E-03 1.99E-03 2.44E-03 T.Body 5.28E-04 3.62E-04 5.77E-03 1.98E-03 1.49E-03 2.34E-03 Age Class: Infant Bone 2.79E-04 2.09E-04 1.74E-04 5.83E-03 4.05E-03 7.75E-05 GI-LLI 3.21E-04 2.21E-04 1.67E-04 1.30E-03 8.93E-04 2.28E-05 Kidney 3.21E-04 2.21E-04 1.67E-04 1.31 E-03 8.97E-04 2.28E-05 Liver 3.21E-04 2.21E-04 1.67E-04 1.31 E-03 8.98E-04 2.28E-05 Lung 3.73E-04 2.55E-04 1.92E-04 1.30E-03 8.93E-04 2.41E-05 Thyroid 9.34E-04 6.27E-04 4.67E-04 3.46E-03 2.01E-03 3.77E-05 T.Body 3.19E-04 2.19E-04 1.66E-04 1.31 E-03 8.94E-04 2.28E-05 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V = Vegetable Garden C = Cow Milk G = Goat Milk M = Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.Page 23 Table 4.2-B Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Apr-Jun 2012 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NW ESE SE WSW W S Distance 1: 0.54 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway2 DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 1.88E-04 1.40E-04 5.63E-03 2.25E-03 1.97E-03 3.41E-03 GI-LLI 1.08E-03 7.35E-04 2.98E-03 6.04E-04 4.86E-04 7.94E-04 Kidney 1.08E-03 7.33E-04 2.96E-03 6.05E-04 4.86E-04 7.93E-04 Liver 1.08E-03 7.32E-04 2.96E-03 6.04E-04 4.86E-04 7.93E-04 Lung 1.09E-03 7.40E-04 2.96E-03 6.03E-04 4.85E-04 7.93E-04 Thyroid 1.55E-03 1.04E-03 4.21E-03 9.81E-04 6.89E-04 8.77E-04 T.Body 1.08E-03 7.31E-04 2.96E-03 6.04E-04 4.85E-04 7.93E-04 Age Class: Teen Bone 2.68E-04 2.01E-04 9.1OE-03 3.78E-03 2.97E-03 4.82E-03 GI-LLI 1.11E-03 7.52E-04 3.86E-03 9.33E-04 6.95E-04 1.08E-03 Kidney 1.11E-03 7.51E-04 3.84E-03 9.35E-04 6.96E-04 1.08E-03 Liver 1.11E-03 7.50E-04 3.84E-03 9.33E-04 6.95E-04 1.08E-03 Lung 1.13E-03 7.64E-04 3.84E-03 9.32E-04 6.94E-04 1.08E-03 Thyroid 1.70E-03 1.14E-03 4.97E-03 1.49E-03 9.89E-04 1.15E-03 T.Body 1.10E-03 7.49E-04 3.84E-03 9.33E-04 6.95E-04 1.08E-03 Age Class: Child Bone 3.71E-04 2.77E-04 2.17E-02 9.11 E-03 6.97E-03 1.11E-02 GI-LLI 1.OOE-03 6.81E-04 7.12E-03 2.07E-03 1.54E-03 2.38E-03 Kidney 1.OOE-03 6.82E-04 7.11E-03 2.08E-03 1.54E-03 2.38E-03 Liver 1.OOE-03 6.81E-04 7.11E-03 2.08E-03 1.54E-03 2.38E-03 Lung 1.02E-03 6.93E-04 7.11E-03 2.07E-03 1.54E-03 2.38E-03 Thyroid 1.70E-03 1.14E-03 8.74E-03 3.14E-03 2.1OE-03 2.49E-03 T.Body 1.OOE-03 6.80E-04 7.11E-03 2.07E-03 1.54E-03 2.38E-03 Age Class: Infant Bone 2.73E-04 2.04E-04 1.70E-04 5.71E-03 3.97E-03 7.61E-05 GI-LLI 5.90E-04 4.02E-04 3.02E-04 1.34E-03 9.08E-04 3.OOE-05 Kidney 5.92E-04 4.04E-04 3.02E-04 1.35E-03 9.13E-04 3.OOE-05 Liver 5.91E-04 4.03E-04 3.02E-04 1.35E-03 9.12E-04 3.OOE-05 Lung 6.08E-04 4.14E-04 3.10E-04 1.34E-03 9.08E-04 3.04E-05 Thyroid 1.23E-03 8.26E-04 6.14E-04 3.76E-03 2.16E-03 4.55E-05 T.Body 5.90E-04 4.02E-04 3.02E-04 1.35E-03 9.1OE-04 2.99 E-05 1 Distances are measured with respect to the reactor building vent.2 Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V= Vegetable Garden= Meat C = Cow Milk G = Goat Milk M Page 24 Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2012 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NW ESE SE WSW W S Distance 1: 0.54 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 1.94E-04 1.45E-04 5.77E-03 2.32E-03 2.03E-03 3.52E-03 GI-LLI 8.20E-04 5.56E-04 2.54E-03 5.79E-04 4.75E-04 7.87E-04 Kidney 8.14E-04 5.52E-04 2.52E-03 5.79E-04 4.75E-04 7.86E-04 Liver 8.12E-04 5.51E-04 2.52E-03 5.78E-04 4.74E-04 7.86E-04 Lung 8.33E-04 5.65E-04 2.52E-03 5.78E-04 4.74E-04 7.86E-04 Thyroid 1.40E-03 9.38E-04 3.98E-03 1.01E-03 7.1OE-04 8.84E-04 T.Body 8.1OE-04 5.50E-04 2.52E-03 5.78E-04 4.74E-04 7.86E-04 Age Class: Teen Bone 2.77E-04 2.07E-04 9.32E-03 3.90E-03 3.06E-03 4.97E-03 GI-LLI 8.43E-04 5.73E-04 3.38E-03 9.11E-04 6.88E-04 1.08E-03 Kidney 8.38E-04 5.69E-04 3.37E-03 9.13E-04 6.89E-04 1.08E-03 Liver 8.35E-04 5.68E-04 3.37E-03 9.12E-04 6.88E-04 1.08E-03 Lung 8.70E-04 5.90E-04 3.38E-03 9.11E-04 6.87E-04 1.08E-03 Thyroid 1.58E-03 1.06E-03 4.71E-03 1.55E-03 1.03E-03 1.17E-03 T.Body 8.33E-04 5.66E-04 3.37E-03 9.11E-04 6.88E-04 1.08E-03 Age Class: Child Bone 3.82E-04 2.86E-04 2.23E-02 9.40E-03 7.19E-03 1.15E-02 GI-LLI 7.65E-04 5.22E-04 6.53E-03 2.07E-03 1.54E-03 2.41E-03 Kidney 7.66E-04 5.22E-04 6.52E-03 2.07E-03 1.55E-03 2.41E-03 Liver 7.63E-04 5.21E-04 6.52E-03 2.07E-03 1.55E-03 2.41E-03 Lung 7.93E-04 5.40E-04 6.53E-03 2.07E-03 1.54E-03 2.41 E-03 Thyroid 1.65E-03 1.11E-03 8.44E-03 3.30E-03 2.20E-03 2.54E-03 T.Body 7.62E-04 5.19E-04 6.52E-03 2.07E-03 1.55E-03 2.41E-03 Age Class: Infant Bone 2.82E-04 2.11E-04 1.76E-04 5.90E-03 4.10E-03 7.86E-05 GI-LLI 4.54E-04 3.11E-04 2.34E-04 1.35E-03 9.20E-04 2.67E-05 Kidney 4.56E-04 3.12E-04 2.35E-04 1.36E-03 9.24E-04 2.67E-05 Liver 4.55E-04 3.12E-04 2.35E-04 1.36E-03 9.24E-04 2.67E-05 Lung 4.82E-04 3.29E-04 2.47E-04 1.35E-03 9.20E-04 2.73E-05 Thyroid 1.27E-03 8.51E-04 6.33E-04 4.14E-03 2.37E-03 4.66E-05 T.Body 4.53E-04 3.1OE-04 2.34E-04 1.35E-03 9.21E-04 2.66E-05 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V= Vegetable Garden= Meat C = Cow Milk G = Goat Milk M Page 25 Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2012 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NW ESE SE WSW W S Distance':
0.54 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway2:
DI DI DIV 3 DIVCG3 DIVCM 3 DIVM3 Age Class: Adult Bone 2.56E-04 1.88E-04 8.83E-03 2.66E-03 2.28E-03 3.97E-03 GI-LLI 1.04E-03 7.05E-04 3.19E-03 6.61E-04 5.34E-04 8.81E-04 Kidney 1.02E-03 6.93E-04 2.98E-03 6.49E-04 5.28E-04 8.69E-04 Liver 1.02E-03 6.92E-04 2.98E-03 6.48E-04 5.27E-04 8.69E-04 Lung 1.11E-03 7.50E-04 3.02E-03 6.50E-04 5.28E-04 8.70E-04 Thyroid 1.49E-03 1.01 E-03 4.15E-03 9.93E-04 7.12E-04 9.45E-04 T.Body 1.02E-03 6.92E-04 3.04E-03 6.51 E-04 5.29E-04 8.72E-04 A e Class: Teen Bone 3.58E-04 2.63E-04 1.37E-02 4.44E-03 3.43E-03 5.60E-03 GI-LLI 1.07E-03 7.24E-04 4.17E-03 1.03E-03 7.68E-04 1.20E-03 Kidney 1.05E-03 7.12E-04 3.93E-03 1.01E-03 7.61E-04 1.19E-03 Liver 1.05E-03 7.11E-04 3.93E-03 1.01E-03 7.60E-04 1.19E-03 Lung 1.20E-03 8.12E-04 4.OOE-03 1.02E-03 7.62E-04 1.19E-03 Thyroid 1.65E-03 1.11E-03 5.OOE-03 1.52E-03 1.03E-03 1.26E-03 T.Body 1.05E-03 7.10E-04 4.01E-03 1.02E-03 7.63E-04 1.19E-03 Age Class: Child Bone 4.86E-04 3.58E-04 3.20E-02 1.07E-02 8.05E-03 1.29E-02 GI-LLI 9.60E-04 6.54E-04 7.64E-03 2.29E-03 1.70E-03 2.65E-03 Kidney 9.54E-04 6.50E-04 7.46E-03 2.28E-03 1.70E-03 2.64E-03 Liver 9.52E-04 6.49E-04 7.45E-03 2.28E-03 1.70E-03 2.64E-03 Lung 1.09E-03 7.39E-04 7.51E-03 2.28E-03 1.70E-03 2.64E-03 Thyroid 1.67E-03 1.13E-03 9.OOE-03 3.25E-03 2.21E-03 2.74E-03 T.Body 9.53E-04 6.49E-04 7.64E-03 2.29E-03 1.70E-03 2.65E-03 Age Class: Infant Bone 3.43E-04 2.53E-04 2.09E-04 6.54E-03 4.51E-03 8.62E-05 GI-LLI 5.66E-04 3.87E-04 2.91E-04 1.49E-03 1.01E-03 3.1OE-05 Kidney 5.66E-04 3.86E-04 2.90E-04 1.49E-03 1.01E-03 3.09E-05 Liver 5.65E-04 3.86E-04 2.90E-04 1.49E-03 1.01 E-03 3.09E-05 Lung 6.90E-04 4.69E-04 3.51E-04 1.49E-03 1.01E-03 3.39E-05 Thyroid 1.23E-03 8.25E-04 6.14E-04 3.68E-03 2.14E-03 4.70E-05 T.Body 5.64E-04 3.85E-04 2.90E-04 1.49E-03 1.01E-03 3.09E-05 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V C = Cow Milk G = Goat Milk N= Vegetable Garden= Meat Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.Page 26 Table 4.2-E Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jan-Dec 2012 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
NW ESE SE WSW W S Distance':
0.54 km 0.80 kW 0.84 km 3.97 km 5.77 km 3.80 km Pathway 2: DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 8.29E-04 6.16E-04 2.60E-02 9.51E-03 8.28E-03 1.44E-02 GI-LLI 3.51E-03 2.38E-03 1.08E-02 2.38E-03 1.94E-03 3.21E-03 Kidney 3.47E-03 2.35E-03 1.05E-02 2.37E-03 1.94E-03 3.20E-03 Liver 3.46E-03 2.35E-03 1.05E-02 2.37E-03 1.93E-03 3.20E-03 Lung 3.63E-03 2.46E-03 1.06E-02 2.36E-03 1.93E-03 3.20E-03 Thyroid 5.43E-03 3.65E-03 1.55E-02 3.86E-03 2.74E-03 3.53E-03 T.Body 3.46E-03 2.35E-03 1.06E-02 2.37E-03 1.93E-03 3.20E-03 Age Class: Teen Bone 1.18E-03 8.76E-04 4.14E-02 1.60E-02 1.25E-02 2.03E-02 GI-LLI 3.61E-03 2.45E-03 1.43E-02 3.73E-03 2.81E-03 4.40E-03 Kidney 3.57E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Liver 3.56E-03 2.42E-03 1.40E-02 3.72E-03 2.80E-03 4.39E-03 Lung 3.84E-03 2.60E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Thyroid 6.06E-03 4.08E-03 1.86E-02 5.91E-03 3.96E-03 4.68E-03 T.Body 3.55E-03 2.41E-03 1.41 E-02 3.72E-03 2.80E-03 4.39E-03 Age Class: Child Bone 1.62E-03 1.20E-03 9.82E-02 3.85E-02 2.93E-02 4.68E-02 GI-LLI 3.26E-03 2.22E-03 2.71E-02 8.41E-03 6.27E-03 9.79E-03 Kidney 3.25E-03 2.22E-03 2.69E-02 8.41 E-03 6.28E-03 9.78E-03 Liver 3.25E-03 2.21E-03 2.69E-02 8.41E-03 6.27E-03 9.78E-03 Lung 3.49E-03 2.37E-03 2.69E-02 8.40E-03 6.27E-03 9.78E-03 Thyroid 6.22E-03 4.18E-03 3.34E-02 1.26E-02 8.50E-03 1.02E-02 T.Body 3.24E-03 2.21E-03 2.70E-02 8.41 E-03 6.28E-03 9.79E-03 Age Class: Infant Bone 1.18E-03 8.77E-04 7.30E-04 2.40E-02 1.66E-02 3.18E-04 GI-LLI 1.93E-03 1.32E-03 9.93E-04 5.48E-03 3.73E-03 1.1OE-04 Kidney 1.93E-03 1.32E-03 9.95E-04 5.52E-03 3.74E-03 1.1OE-04 Liver 1.93E-03 1.32E-03 9.94E-04 5.51E-03 3.74E-03 1.1OE-04 Lung 2.15E-03 1.47E-03 1.1OE-03 5.49E-03 3.73E-03 1.16E-04 Thyroid 4.66E-03 3.13E-03 2.33E-03 1.50E-02 8.69E-03 1.77E-04 T.Body 1.93E-03 1.32E-03 9.91E-04 5.50E-03 3.73E-03 1.1OE-04 1 2 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation V C = Cow Milk G = Goat Milk M= Vegetable Garden= Meat 3 Doses are conservative since it is unlikely for vegetables to be grown outside or for animals to be fed on pasture during winter months.Page 27
4.3 Doses
From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses. The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E. These tables cover the individual calendar quarters and the total calendar year, respectively.
Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways.
NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways.
Therefore, doses for this age class are not included in any of the tables.It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters.
Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given quarter, the resulting concentration for that quarter will be higher than concentrations from other quarters.
This will result in a proportionally higher dose for that quarter. However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller. In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses.Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (adult age class) of 0.0000000919 mrem. The maximum organ dose (adult age class, all organs) was 0.0000000919 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2012 Age Class Organ Dose -mrem *Organ Adult J Teen Child Bone 0.OE+00 0.OOE+00 0.OOE+00 GI-LLI 9.26E-08 6.85E-08 5.91E-08 Kidney 9.26E-08 6.85E-08 5.91E-08 Liver 9.26E-08 6.85E-08 5.91E-08 Lung 9.26E-08 6.85E-08 5.91 E-08 Thyroid 9.26E-08 6.85E-08 5.91 E-08 T.Body 9.26E-08 6.85E-08 5.91 E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 29 Table 4.3-B Maximum Individual Organ Doses -- mrem From Liquid Release Period: Apr-Jun 2012 Age Class Organ Dose -mrem Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.0OE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.OOE+00 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2012 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney 0.OOE+00 O.OOE+00 0.OOE+00 Liver O.OOE+00 O.OOE+00 0.OOE+00 Lung O.OOE+00 O.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.OOE+00 0.00E+00 Page 31 Table 4.3-D Maximum Individual Organ Doses -- mrem From Liquid Release Period: Oct-Dec 2012 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 0.OOE+00 0.OOE+00 O.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 O.OOE+00 Kidney 0.OOE+00 0.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 O.OOE+00 Lung 0.OOE+00 0.OOE+00 0.OOE+00 Thyroid 0.OOE+00 0.OOE+00 O.OOE+00 T.Body 0.OOE+00 O.OOE+00 0.OOE+00* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during these months.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 32 Table 4.3-E Maximum Individual Organ Doses -mrem From Liquid Release Period: Jan-Dec 2012 Age Class Organ Dose -mrem *Organ Adult [ Teen Child Bone 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 9.19E-08 6.79E-08 5.86E-08 Kidney 9.19E-08 6.79E-08 5.86E-08 Liver 9.19E-08 6.79E-08 5.86E-08 Lung 9.19E-08 6.79E-08 5.86E-08 Thyroid 9.19E-08 6.79E-08 5.86E-08 T.Body 9.19E-08 6.79E-08 5.86E-08* These doses are conservative since the same usage factor was applied for each quarter.In reality, it is unlikely that anyone would be swimming or boating during the entire year.However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose.Page 33
5.0 OFFSITE
AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure.
However, Regulatory Guide 1.21 (Reference
- 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man.Thermoluminescent dosimeters (TLDs) are located at 83 sites beyond the boundary of the PNPS restricted/protected area. A number of these TLDs are located within the site boundary, on Entergy property in close proximity to the station proper. The TLDs are collected on a quarterly basis and used to calculate the ambient radiation exposure in milliRoentgen (mR) over the exposure period.These TLDs are grouped into four zones of increasing distance from the station. Average exposure values for each of these zones were calculated for each calendar quarter and the total year. The average exposure values (mR) for the four zones are presented in Table 5.0.In addition to responding to ambient radiation exposure, TLDs will also record radiation resulting from noble gases (plume and immersion exposure), particulate materials deposited on the ground, cosmic rays from outer space, and from naturally-occurring radioactivity in the soil and air.Typically, the exposure from cosmic rays and other natural radioactivity components is about 40 to 70 mR/year. As calculated in Sections 4.1 and 4.2 of this report, the ambient radiation component of doses from PNPS effluent emissions are below 1 mrem/yr and would not be discernible above the natural radiation exposure levels.The major source of ambient radiation exposure from PNPS results from high-energy gamma rays emitted from nitrogen-16 (N-16) contained in steam flowing through the turbine. Although the N-16 is enclosed in the process lines and turbine and is not released into the environment, the ambient radiation exposure and sky shine from this contained source accounts for the majority of the radiation dose, especially in close proximity to the station. Other sources of ambient radiation exposure include radiation emitted from contained radioactive materials and/or radwaste at the facility.
Despite these sources of ambient radiation exposure at PNPS, increases in exposure from ambient radiation are typically not observable above background levels at locations beyond Entergy controlled property.The average exposure values presented in Table 5.0 appear to indicate an elevation in ambient exposures in Zone 1, those TLDs within 2 miles of PNPS. Most of this elevation is due to increases in exposure levels measured at TLD locations on Entergy property in close proximity to the station proper. For example, the annual exposure at TLD location OA, located at the Overlook Area near the PNPS Health Club (I&S Building), was 185 mR for the entire year. This location is immediately adjacent to the station proper and overlooks the turbine building, therefore receiving the highest direct ambient and sky shine exposure.
When the near-site TLDs (those located within 0.6 km of the Reactor Building) are removed from the calculation of averages, the mean annual exposure in Zone 1 falls from 71.7 +/- 24.7 mR/yr to 60.7 +/- 68.8 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.8 +/- 7.3 mR/yr, and is indicative of natural background radiation.
Although the annual exposure at TLD location OA was 124 mR above the average Zone 4 exposure, members of the general public do not continuously occupy this area. When adjusted for such occupancy, a hypothetical member of the public who was at this location for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per year would only receive an incremental dose of 0.57 mrem over natural background radiation levels. At the nearest residence
0.8 kilometers
(0.5 miles) southeast of the PNPS Reactor Building, the annual exposure was calculated as being 59.9 +/- 6.2 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.8 +/- 7.3 mR. Statistically, there is no difference between these two values.Page 34 It must be emphasized that the projected ambient exposures discussed on the previous page are calculated to occur to a maximum-exposed hypothetical individual.
Even thlough conservative assumptions are made in the projection of these dose consequences, all of the projected doses are well below the NRC dose limit of 100 mrem/yr specified in 1OCFR20.1301, as well as the EPA dose limit of 25 mrem/yr specified in 40CFR190.
Both of these limits are to be applied to real members of the general public, so the fact that the dose to the hypothetical maximum-exposed individual is within the limits ensures that any dose received by a real member of the public would be smaller and well within any applicable limit.In 1994, Pilgrim Station opened the old training facility (I&S Building) overlooking the plant as a health club for its employees.
This site is immediately adjacent to the protected area boundary near monitoring location OA and receives appreciable amounts of direct ambient and sky shine exposure from the turbine building.
Although personnel using this facility are employees of Entergy, they are considered to be members of the public. Due to their extended presence in the facility (500 hr/yr, assuming utilization of the facility for 2 hr/day, 5 days a week, for 50 weeks/yr), these personnel represent the most conservative case in regards to ambient radiation exposure to a member of the public within the PNPS owner controlled area. Their annual incremental radiation dose above background during 2012 is estimated as being about 1.4 mrem, based on the average exposure measured by the TLD in the building.The exposures measured by the TLD located in the health club would also include any increase in ambient radiation resulting from noble gases and/or particulate activity deposited on the ground from gaseous releases.
However, they would not indicate any internal dose received by personnel in this facility from inhalation of small amounts of PNPS-related radioactivity contained in the air.An environmental air sampler located immediately adjacent to the health club did not indicate any PNPS-related activity during 2012. Dose calculations performed in the same manner as those outlined in Section 4.2 for airborne effluent releases yielded a projected total body dose to the maximum-exposed individual (500 hr/yr exposure) of about 0.00075 mrem, resulting from inhalation.
Again, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy. Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR190.This regulation expressly applies to areas at or beyond the owner-controlled property, and is not applicable in this situation.
As stated earlier, TLDs at and beyond the site boundary do not indicate elevated ambient radiation levels resulting from the operation of Pilgrim Station.Although some of the TLDs in close proximity to PNPS indicate increases in exposure levels from ambient radiation, such increases are localized to areas under Entergy control. For members of the general public who are not employed or contracted with Entergy and are accessing Entergy controlled areas (e.g., parking lots, etc.), such increases in dose from ambient radiation exposure are estimated as being less than 1.0 mrem/year.
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2012 Average Exposure +/- Standard Deviation:
mR/period Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km- 3-8 km 8-15 km >15 km Jan-Mar 17.7 +/- 5.7 14.1 +/- 1.8 13.9 +/- 1.5 15.5 +/- 1.8 Apr-Jun 18.0 +/- 5.9 14.6 +/- 1.6 14.3 +/- 2.0 14.9 +/- 2.0 Jul-Sep 18.1 +/- 7.2 14.2 +/- 1.9 14.2 +/- 1.8 15.1 +/- 2.1 Oct-Dec 17.9 +/- 6.1 14.2 +/- 1.8 14.4 +/- 1.4 15.3 +/- 1.9 Jan-Dec 71.7 +/- 24.7** 57.1 +/- 7.1 56.7 +/- 6.4 60.8 +/- 7.3 Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 60.7 +/- 6.8 mR/yr.Page 36
6.0 PERCENT
OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and concentration limits for radioactive effluents.
In addition, the effluent controls specified ensure that radioactive releases are maintained as low as reasonably achievable.
The percentage of the PNPS ODCM Control limit values were determined from doses calculated in Section 4, the effluent releases summarized in Section 2, and the ODCM Control limits/objectives listed in Tables 6.1 and 6.2.The percent of applicable control limit values are provided to supplement the information provided in the Section 2 of this report. The format for the percent of applicable limits is modified from that prescribed in Regulatory Guide 1.21 (Reference
- 1) to accommodate the Radioactive Effluents Technical Specifications (RETS) that became effective March 01, 1986. The percentages have been grouped according to whether the releases were via liquid or gaseous effluent pathways.6.1 Gaseous Effluent Releases Dose-based effluent controls related to exposures arising from gaseous effluent releases are presented in Table 6.1. The maximum quarterly air doses and annual whole body doses listed in Table 4.1 were used to calculate the percentage values shown in Table 6.1. All doses resulting from noble gas exposure were a small percentage of the applicable effluent control.Organ dose limits for the maximum-exposed individual from radioactive particulates, iodines, and tritium from the PNPS ODCM are also shown in Table 6.1. The maximum quarterly and annual organ doses from Tables 4.2-A through 4.2-E were used to calculate the percentages shown in Table 6.1. The resulting organ doses from Pilgrim Station's gaseous releases during 2012 were a small percentage of the corresponding effluent control.Page 37 Table 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2012 A. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1.a Limit: 500 mrem/yr Total Body Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 1.70E-05 3.39E-06%B. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1.a Limit: 3000 mrem/yr Skin Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 9.03E-05 3.01E-06%C. Instantaneous Dose Rate Limit -Particulates, lodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 9.82E-02 6.55E-03%D. Quarterly Dose Objective
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective:
5 mrad Gamma Air Dose Period Value -mrad Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 5.78E-07 1.16E-05%Jul-Sep 6.88E-07 1.38E-05%Oct-Dec 2.50E-05 5.01 E-04%E. Annual Dose Objective
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective:
10 mrad Gamma Air Dose Period Value -mrad/vr Fraction of Limit Jan-Dec 2.58E-05 2.58E-04%Page 38 Table 6.1 (continued)
Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2012 F. Quarterly Dose Objective
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective:
10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrad 0.OOE+00 8.89E-07 1.31E-06 9.27E-05 Fraction of Limit 0.OOE+00%8.89E-06%1.31 E-05%9.27E-04%G. Annual Dose Objective
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective:
20 mrad Beta Air Dose Period Jan-Dec Value -mrad/vr 9.31 E-05 Fraction of Limit 4.66E-04%H. Quarterly Dose Objective
-Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective:
7.5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.22E-02 2.17E-02 2.23E-02 3.20E-02 Fraction of Limit 2.95E-01%2.90E-01%2.97E-01%4.27E-01%Annual Dose Objective
-Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective:
15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 9.82E-02 Fraction of Limit 6.55E-01%Page 39
6.2 Liquid
Effluent Releases Liquid effluent concentration limits and dose objectives from the PNPS ODCM are shown in Table 6.2. The quarterly average concentrations from Table 2.3-A were used to calculate the percent concentration limits. The maximum quarterly and annual whole body and organ doses from Tables 4.3-A through 4.3-E were used to calculate the percentages shown in Table 6.2. The resulting concentrations, as well as organ and total body doses from Pilgrim Station's liquid releases during the reporting period were a small percentage of the corresponding effluent controls.Page 40 Table 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -jiCi/mL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit 0.OOE+00%0.OOE+00%O.OOE+00%0.OOE+00%O.OOE+00%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 pCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -j.Ci/mL 6.47E-10 0.OOE+00 O.OOE+00 0.OOE+00 1.60E-10 Fraction of Limit 6.47E-05%0.OOE+00%0.OOE+00%0.OOE+00%1.60E-05%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 ltCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/mL O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fraction of Limit O.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%0.OOE+00%Page 41 Table 6.2 (continued)
Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2012 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective:
1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 O.OOE+00 O.OOE+00 Fraction of Limit 6.17E-06%0.OOE+00%0.OOE+00%0.OOE+00%E. Annual Total Body Dose Objective PNPS ODCM Control 3.2.2.b Objective:
3 mrem Total Body Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 3.06E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective:
5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 9.26E-08 0.OOE+00 0.OOE+00 S0.OOE+00 Fraction of Limit 1.85E-06%0.OOE+00%0.OOE+00%0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective:
10 mrem Organ Dose Period Jan-Dec Value -mrem 9.19E-08 Fraction of Limit 9.19E-07%Page 42
7.0 RADIOACTIVE
WASTE DISPOSAL DATA Radioactive wastes that were shipped offsite for processing and disposal during the reporting period are described in Table 7.0, in the standard NRC Regulatory Guide 1.21 format.The total quantity of radioactivity in Curies and the total volume in cubic meters are summarized in Table 7.0 for the following waste categories:
- Spent resins, filter sludges, and evaporator bottoms;* Dry activated wastes, contaminated equipment, etc.;* Irradiated components, control rods, etc.; and,* Other.During the reporting period approximately 54.6 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 779 Curies were shipped from PNPS for processing and disposal.
Dry activated wastes and contaminated equipment shipped during the period totaled 412 cubic meters and contained 0.56 Curies of radioactivity.
No shipment of irradiated components was shipped during the reporting period. No shipments of irradiated fuel were made during the reporting period.Estimates of major radionuclides, those comprising greater than 1% of the total activity in each waste category shipped, are listed in Table 7.0. There were 12 shipments to Energy Solutions' Bear Creek Facility; 2 shipments to Energy Solutions' Gallaher Road Facility; 8 shipments to Studsvik Processing Facility in Erwin, TN and 1 shipment to Energy Solutions Facility in Memphis, TN.Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2012 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)1. Estimate of volume and activity content by type of waste Jan-Dec 2012 Type of waste Volume -m3 Curies I Total Error a. Spent resins, filters, filter sludges, 5.46 E+01 7.79 E+02 _ 25%evaporator bottoms, etc.b. Dry activated waste, contaminated 4.12 E+02 5.60 E-01 +/- 25%equipment, etc.c. Irradiated components, control rods, etc. 0.00E+00 0.00E+00 N/A d. Other (describe):
Hi-Rad Trash/Metals 0.00E+00 0.00E+00 N/A 2. Estimate of major nuclide composition by type of waste 1 Type of waste J Radionuclide J Abundance Total Error a. Spent resins, filters, filter sludges, Mn-54 9.44% +/- 25%evaporator bottoms, etc. Fe-55 65.65% +/- 25%Co-60 20.21% +/- 25%Zn-65 3.20% +/- 25%b. Dry activated waste, contaminated Mn-54 8.23% +/- 25%equipment, etc. Fe-55 50.35% +/- 25%Co-60 24.95% +/- 25%Ni-63 4.05% +/- 25%Zn-65 3.39% +/- 25%Cs-137 8.54% +/- 25%c. Irradiated components, control rods, etc. Not Applicable Not Applicable N/A d. Other (describe):
Hi-Rad Trash/Metals Not Applicable Not Applicable N/A"Major" is defined as any radionuclide comprising
>1% of the total activity in the waste category.3. Solid Waste Disposition Number of Shipments J Mode of Transportation J Destination Tractor-trailer Energy Solutions Bear Creek FacilityL (Hittman Transport)
Oak Ridge, TN Tractor-trailer Energy Solutions Gallaher Road Facility" (Hittman Transport)
Kingston, TN Tractor-trailer Studsvik Processing Facility, L (Hittman Transport)
Erwin, TN Tractor-trailer Studsvik/RACE, LLC z (Hittman Transport)
Memphis, TN This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc.Remaining radioactive wastes will be shipped to Chem Nuclear Systems, Inc. in Barnwell, SC, or Envirocare, Inc.in Clive, UT for final disposal.B. IRRADIATED FUEL SHIPMENTS
& DISPOSITION Number of Shipments Mode of Transportation Destination None N/A N/A Page 44
8.0 OFFSITE
DOSE CALCULATION MANUAL REVISIONS The PNPS Offsite Dose Calculation Manual (ODCM) was not revised during the calendar year of 2012. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45
9.0 PROCESS
CONTROL PROGRAM REVISIONS There were no changes to the PNPS Process Control Program (PCP) during the calendar year of 2012. Although Pilgrim Station adopted the Entergy fleet-wide PCP in 2010 as indicated in the 2010 Annual Effluent Release Report, fleet procedure EN-RW-105, "Process Control Program", was not revised until 2011 to reflect the inclusion of Pilgrim Station under the fleet-wide PCP. This revision was strictly administrative in nature, and did not impact the requirements or conduct of the PCP.Page 46
10.0 REFERENCES
- 1. U.S. Nuclear Regulatory Commission, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants", Regulatory Guide 1.21, Revision 1, June 1974.2. "Pilgrim Nuclear Power Station Offsite Dose Calculation Manual", Revision 9, June 2003.3. U.S. Nuclear Regulatory Commission, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix I", Regulatory Guide 1.109, Revision 1, October 1977.4. U.S. Nuclear Regulatory Commission, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Regulatory Guide 1.111, July 1977.5. Boston Edison Company, "Pilgrim Station Unit 1 Appendix I Evaluation", April 1977.6. Entech Engineering Inc., P100-R19, "AEOLUS-3
-A Computer Code for the Determination of Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents During Continuous, Intermittent and Accident Conditions in Open-Terrain Sites, Coastal Sites and Deep-River Valleys" Page 47 APPENDIX A Meteorological Joint Frequency Distributions TABLE TABLE TITLE PAGE A-1 Joint Frequency Distribution of Wind Directions and Speeds for the 48 33-ft Level of the 220-ft Tower A-2 Joint Frequency Distribution of Wind Directions and Speeds for the 58 220-ft Level of the 220-ft Tower Page 48 Table A-1 Joint Frequency Distribution of Wind Directions and Speeds For the 33-ft level of the 220-ft Tower Jan-Mar 2012 Class A Fre 0.003 mph N NEI NE [ENEI E IESE] SE ISSE S ISSvW SW I[sW W Iv vNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 2 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 4 7.5-12.5 0 0 1 0 0 0 0 0 0 1 0 0 0 0 0 0 2 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 01 1 0 0 0 0 0 0 1 0 0 1 11 1 01 0 6 Class B Fre 0.005 mp. N NNE I5NE ENE E ESE SE SSE IS I [ SW [WSWIWIWNW NW] NNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 3 0 0 0 0 0 0 0 0 1 0 1 1 0 0 0 6 7.5-12.5 0 1 1 0 1 0 0 0 0 0 0 0 0 0 0 0 3 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3T 1 1 l 11 0 0 0 ol 9 Class C Fr 0 0.020 amp.9 N 5 NNE [E ENSE SSE I SSW I SW Iwsw] W I WNW NW NNW TOTAL Ca0m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 3.5-7.5 4 5 5 0 0 0 0 0 1 1 0 0 2 2 1 1 22 7.5-12.5 0 3 4 0 1 2 0 0 0 1 0 0 2 2 0 0 15 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4[ 8[ 9 0 1 1 2Io lo 1 2 o0 o0 51 4 11 11 38 Class D Fr_ 0.672 mph I N I NNEN NE IENE I IESE SE SSE S I W S SW I W sW I W IVWNW NW INNWl TOTA_Calm-0.95 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0.95-3.5 6 2 4 5 8 2 9 11 10 17 11 21 16 14 15 7 158 3.5-7.5 43 49 17 13 23 22 27 10 41 65 66 82 133 72 79 31 773 7.5-12.5 15 19 4 6 10 5 6 2 7 44 54 22 46 25 32 1 298 12.5-18.5 0 0 0 0 0 0 0 0 0 13 11 0 0 0 0 0 24 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 164[ 70 I 251 24 41 29 [42 [ 23 [ 59 I 1391 142 125 195 111 i 126 1 39I 1254 Page 49 Table A-1 (continued)
Jan-Mar 2012 Class E Fre 0.273 mph IN I NNE INEI ENEI E ESE ISEI SSEI S I SSvvISW WSWI W I WNWI NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 1 0 0 1 0 0 0 2 0.95-3.5 5 11 5 4 5 2 8 10 22 19 17 23 31 12 7 4 185 3.5-7.5 3 6 2 2 4 4 17 19 24 30 53 54 30 16 10 1 275 7.5-12.5 0 0 0 0 1 0 0 0 2 23 16 1 4 1 0 0 48 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I8 17 I 7 16 1 101 6 1251 29 1 48 1 73 1 86 1 78 1 661 29 1 17 I 5 I 510 Class F F 0.024 mph IN I NNE INEI ENEI El ESEISEI SSEI S I SSW ISWv WSW IW I WNW Iw N v NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 1 0 0 0 0 0 1 2 2 0 2 1 1 0 0 10 3.5-7.5 0 0 1 0 0 0 0 1 0 1 17 2 0 0 1 0 23 7.5-12.5 0 0 0 0 0 0 0 0 0 4 7 0 0 0 0 0 11 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I0 1 i11 0 0 0 1 0212 7 24 4 I 1 i 0 44 Class G Fre 0.002 mph I N I NNE INEI ENEI E ESE sEI SSE I S I S SW WSWI W I WNW INWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 0.95-3.5 0 0 0 0 1 0 0 0 0 0 0 0 1 0 0 0 2 3.5-7.5 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I0 I 0 0 1 l[ 0 1 0 0[ 0 01 0 I1 0 0 0 4 All+Missing 1.000__mph I N I NNE INEI ENEI El ESEISE] SSE S[ SSW JSW WSW Iw I WNW lNWI NNWI TOTAL Calm-0.95 0 0 0 0 0 0 1 0 1 1 1 0 1 0 0 0 5 0.95-3.5 19 17 13 19 19 7 21 26 39 43 33 53 56 37 26 14 442 3.5-7.5 71 65 36 30 40 34 46 33 73 107 150 151 174 100 95 42 1247 7.5-12.5 17 23 10 6 13 7 6 2 11 86 108 30 52 28 49 13 461 12.5-18.5 0 0 0 0 0 0 0 0 0 13 15 0 0 0 0 0 28 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 107 ] 105 1591 55 1721 48 1741 ] 1 11241 250 13071 234 12831 165 [1701 69 2183 Page 50 Table A-1 (continued)
Apr-Jun 2012 Class A Freq: ####mph N NNEI NE IENEI E ESEI SE I SSE[ S Is SW IwSwl W IWNW T NW IONNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Class B Frec ####mph N NNE NE ENE E ESE SE SSE S I SW IWSWl W IWNWl NW INNW TOTAL Calm-0.95 0 0 '0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Class C Freq ####mph I N I NNEI NE I ENI E IESEI SE I SSE I S ISSWI SW IWSWl W IWNW[ NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALI 1 0 0 0 0 0 0 0 0 Class D Fre ##mphI N _ NNE NE ENE E [ESE SE ISSE] S ISSW[ SW IWSWI W IWNW[ NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 51 Table A-1 (continued)
Apr-Jun 2012 Class E Freq ####Mph IN NNEI NE IENE E ESE SE ISSEI S I SSW SW IVWSWI W IWNWI NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 Class F Freq ####N I NNE I NE I ENE I ESEI SE SSE I S ISSWv SW IWSWI W IWNWI NW INNWv TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL [01 01 1 1 1 1 0o 0 0 0 0 0 0 0 1 0o 0 Class G Freq ####__Mph N NNE NE ENE E ESE SE ISSEI S ISSWvI SW IVWSW[ IWNWV NW INNWv TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL [01 0 1 00 0 0 o o o o o o o o I 01 0 AIl+Missing F.a: 1.000 mph L N NNEI NE [ENEI E IESE] SE [SSE S ISSWI SW IWSW[ W IWNwl NW INNNWV TOTAL Calm-0.95 0 0 0 0 0 0 0 1 0 0 0 1 0 0 0 1 3 0.95-3.5 53 30 35 35 71 36 36 53 68 42 37 56 70 45 39 32 738 3.5-7.5 42 98 85 39 65 44 49 37 89 212 148 111 66 64 40 34 1223 7.5-12.5 0 3 7 0 0 1 9 1 17 113 35 7 16 10 0 0 219 12.5-18.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 195 131 127 [74 1136 I 81 I 94 92 174 368 1220 1175 1152 119I 79 1 67 I 2184 Page 52 Table A-1 (continued)
Jul-Sep 2012 Class A Freq: 0.060 mph N INNE NE ENEI EI ESE[ SE [ SSEI S ISsWl SW IVWsvv W IWNWI NW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 12 10 15 10 5 0 0 0 0 0 0 0 0 0 0 5 57 3.5-7.5 5 7 14 7 4 3 0 0 3 2 0 0 0 1 2 0 48 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 117 117 29 117 9 3 0 0 3 2 0 0 0 I1 2 5 105 Class B Freq 0.027 mph IN I NNE I NE I ENEI E I ESEI SE I SSEI S ISSW SW IWSWI W IWNWI NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 2 1 2 5 0 1 0 0 1 0 1 0 2 3 3 22 3.5-7.5 0 1 0 2 3 2 3 1 2 7 1 1 0 2 0 0 25 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 11 3 1 4 8 2 4 1 2 8 0 4 3 3 47 Class C Freq 0.034 mph IN NNE NE [ENE I E ESEI SE I SSE I S ISSWI SW IVWSWI WIWNWIVNW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 0 7 8 4 0 0 0 0 0 0 0 1 2 0 0 25 3.5-7.5 0 0 0 0 2 1 1 1 7 14 6 0 0 1 1 0 34 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 0 7 8 1 1 1 7 14 61 0 1 3 1 Class D Fre 0 0.352 mph N I NNEI NE I ENE I E IESEl SE SSE S I SSWvI SW IWSWI W IwNw NW INNWE TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 25 26 20 14 33 9 8 7 3 18 6 16 13 23 28 21 270 3.5-7.5 0 3 2 2 1 13 12 7 63 127 46 10 6 0 5 1 298 7.5-12.5 0 0 0 0 0 0 0 0 24 26 1 0 0 0 0 0 51 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I 25 29 ] 22 I16 [34 I22I 20 14 90 171 53 I 26 119 [23 33 I 22[ 619 Page 53 Table A-1 (continued)
Jul-Sep 2012 Class E Freq 0.322 mph IN INNEI NE ENE E IESEI SEI SSEI S ISSWl SW I wsw W IwNwl NW I NNW TOTAL Calm-0.95 0 1 1 0 1 2 1 1 0 1 0 1 1 0 1 0 11 0.95-3.5 11 13 8 23 16 15 19 14 41 28 19 24 16 14 19 5 285 3.5-7.5 1 1 8 0 1 2 3 2 29 113 69 16 5 5 7 3 265 7.5-12.5 0 0 0 0 0 0 0 0 0 3 2 0 0 0 0 0 5 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 112I 15] 17 23 18 19 23 17 70 1 145 1 90 I 41 1 22 [ 19 [ 27 J8a 566 Class F Freq 0.165-mph I N NNE NE I ENEI E ESE SE I SSEI S ISSW ISWIWSWI W I WNWV NW INNW TOTAL Calm-0.95 0 1 0 0 2 1 1 1 1 2 1 4 1 1 0 1 17 0.95-3.5 2 3 0 2 2 2 1 13 16 19 19 36 22 14 6 3 160 3.5-7.5 0 1 0 0 0 0 0 0 2 18 75 11 1 3 0 0 111 7.5-12.5 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 2 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 I5 I0 2 I4 3 I2 14 i19 39 97I 51 24 18 6 14 290 Class G Fre: 0.040 N I NNE NE ENE I SEI I SE SSEI S I SSW SW IWSWv W IWNWl NW I[NNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0.95-3.5 0 0 0 0 0 0 0 0 0 5 11 15 8 3 0 0 42 3.5-7.5 0 0 0 0 0 0 0 0 0 1 20 7 0 0 0 0 28 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 01 0 01 0 0 0 6 o 0 31 221 9 3 101 0 71 AII+Missing F 1.000 mph IN NNEI NE IENE E I ESE SE ISSE S ISSWI SW IWSWI W IWNWI NW INNWJ TOTAL Calm-0.95 0 2 1 0 3 3 2 2 1 3 1 6 3 1 1 1 30 0.95-3.5 64 71 66 77 76 39 38 38 68 79 67 128 80 72 68 44 1075 3.5-7.5 6 16 26 16 24 24 20 13 113 352 307 67 16 13 15 7 1035 7.5-12.5 0 0 0 0 0 0 0 0 25 32 11 0 0 0 0 0 68 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I 70 89 93 93 11031 66 60 53 207 1 466 1 386 1201 99 1 86 J 84 1521 2208 Page 54 Table A-1 (continued)
Oct-Dec 2012 Class A Fe:0.053 mph IN' NNE NE ENE E ESE SE SSEI S ISSWl SW Iwswl W IwNwI NW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 7 3 3 0 1 0 0 0 0 0 0 0 0 1 4 1 20 3.5-7.5 13 13 20 4 1 1 0 0 0 0 0 0 5 15 11 10 93 7.5-12.5 0 1 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2 12.5-18.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1201 17] 2 4 I4 2 I1 0 0 0 I0 0 0 ] 5 117115 lI 116 Class B Fr 0.024 ph IN INNE INE I ENEI E I ESEI SESSE SSI S ISSWl SW IVWSW] W IVWNWV NW I[NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 3 1 1 0 0 0 0 0 0 0 0 0 1 1 9 3.5-7.5 2 7 7 1 1 1 0 0 1 0 0 0 3 5 3 2 33 7.5-12.5 0 3 1 0 1 0 0 0 0 0 0 0 2 1 0 1 9 12.5-18.5 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 111 13 2 3 1 I 0 1 0 I0 I0 I 6 4 4 53 Class C Freq 0.033 mph N ENEI E IESEISE I SSE S I SSW [ SW IvWSWI W IWNWI NW I[NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 1 1 0 0 1 0 0 0 0 0 0 0 0 0 5 3.5-7.5 3 10 4 2 1 1 1 0 0 2 0 1 14 7 2 2 50 7.5-12.5 0 3 1 0 0 3 0 0 0 0 0 0 3 6 1 0 17 12.5-18.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4 14 71 3 1 4 2 0 0 2 0 1 17 13 3 2 73 Class D 0.491 mph [ N INNE NEENE I E I ESEI SE I SSE] S I SSW [ SW IWSWI W VIvNW NW I[NNW TOTAL Calm-0.95 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 4 9 9 10 12 5 6 9 3 16 8 5 12 13 7 6 134 3.5-7.5 15 66 72 46 31 25 20 9 36 68 34 45 72 43 67 15 664 7.5-12.5 6 27 25 12 11 15 0 0 11 32 9 4 30 30 32 5 249 12.5-18.5 7 15 8 0 3 2 1 0 0 0 0 0 0 0 0 0 36 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 33 1117 11141 68 157 47 [27 118 150 116 151 [54 114 86 1106 126 I 1084 Page 55 Table A-1 (continued)
Oct-Dec 2012 Class E Fre( 0.307 mph N NNE( NE I ENE] E I ESE [E SSI SEI S ISSwI SW Iwswl W IWNWI NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 0 1 0 1 1 1 1 6 0.95-3.5 5 6 9 5 12 15 16 20 21 26 22 24 22 25 13 5 246 3.5-7.5 3 8 15 2 12 7 19 11 24 48 56 115 47 17 6 4 394 7.5-12.5 0 0 1 0 2 2 1 0 5 7 2 1 0 0 0 0 21 12.5-18.5 0 0 2 3 5 0 0 0 0 0 0 0 0 0 0 0 10 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 8 14 27I 10 31124 36 31 1 51 I 81 81 140 70 1 43 20 10 677 Class F Fre! 0.079__Mph N I NNE I NE I ENE E! ESEI SE I SSE I S ISSWI SW IVWSWI W IWNW_ NW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 1 1 2 0 2 1 0 0 0 7 0.95-3.5 0 0 0 0 1 0 2 12 19 22 20 20 7 2 0 0 105 3.5-7.5 0 0 0 0 0 0 0 0 0 19 39 5 0 0 0 0 63 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 01 010 1 01 11 0 2 131 201 431 59 271 1 21 01 01 175 Class G Freq 0.014 mph IN] NNEI NE I ENEI E I ESEI SE I SSE S Isswl SW IWSW[ W IWNWI NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 1 0 0 0 1 5 12 5 1 0 0 25 3.5-7.5 0 0 0 0 0 0 0 0 0 1 4 0 0 0 0 0 5 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 01 01 01 0 1 01 0 2 1 9 1 121 51 11 01 0[ 30 AII+Missing F,: 1.000 mph IN ENE E ESE SSE S ISSWvl SW IWsvv W IVVVI NW I NNW TOTAL Calm-0.95 1 0 0 0 0 0 0 1 2 2 1 2 2 1 1 1 14 0.95-3.5 18 20 25 17 27 21 25 41 43 65 55 61 46 42 25 13 544 3.5-7.5 36 104 118 55 46 35 40 20 61 138 133 166 141 87 89 33 1302 7.5-12.5 6 34 28 12 14 20 1 0 16 39 11 5 35 38 33 6 298 12.5-18.5 7 15 14 3 8 2 1 0 0 0 0 0 0 0 0 0 50 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1681 173 185 87 [ 95 I 78 6 67 6 62 122 2441200 234 1 224 [1681148 1 53 I 2208 Page 56 Table A-1 (continued)
Jan-Dec 2012 Class A Fre: 0.039 mph IN1 NNEI NE IENE1 I ESEI SE SSEI S I SSWv SW IvWSWl IWWNW[ NW I NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 19 13 18 10 6 0 0 0 0 0 0 0 0 1 4 6 77 3.5-7.5 20 20 34 11 5 4 0 0 3 2 0 0 6 17 13 10 145 7.5-12.5 0 1 1 0 0 0 0 0 0 1 0 0 0 1 0 0 4 12.5-18.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1391 34 54 121 11 [4 100 3131 0 0 6 19 17 161 227 Class B Freq 0.019 mph!L N I NNE] NE ENE[ E[ ESE SE I SSE S I ISSW ISW Iwsw[ W (WNWI NW INNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 3 4 3 6 0 1 0 0 1 0 1 0 2 4 4 31 3.5-7.5 5 8 7 3 4 3 3 1 3 8 1 2 4 7 3 2 64 7.5-12.5 0 4 2 0 2 0 0 0 0 0 0 0 2 1 0 1 12 12.5-18.5 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL [7 15 115 12 3 4 1 3 I9 1 1 3 1 6 10 7 7 109 Class C Fre: 0.029 mph N 1 NNE 1 NE [ENE E ESE ISE SSEIS I SSW ISWL WSW [ W I WNWI NWJI NNW ITOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 1 8 9 4 0 1 0 0 0 0 0 2 2 0 0 31 3.5-7.5 7 15 9 2 3 2 2 1 8 17 6 1 16 10 4 3 106 7.5-12.5 0 6 5 0 1 5 0 0 0 1 0 0 5 8 1 0 32 12.5-18.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I11 22 123 11 8 I7 3 1 8 18 6 1 23 120 I 5 1 3 170 Class D Fre0 0.507 mph N 1 NNEI NE [ENE jE IESE] SE ISSEIS I SSW ILSW[IWSWI W I WNWj NW I NNW I TOTAL Calm-0.95 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 2 0.95-3.5 35 37 33 29 53 16 23 27 16 51 25 42 41 50 50 34 562 3.5-7.5 58 118 91 61 55 60 59 26 140 260 146 137 211 115 151 47 1735 7.5-12.5 21 46 29 18 21 20 6 2 42 102 64 26 76 55 64 6 598 12.5-18.5 7 15 8 0 3 2 1 0 0 13 11 0 0 0 0 0 60 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1122 216 161 [108 1132 98 ] 89 55 199 [426 [246 [205 328 1 220 265 ] 87 [ 2957 Page 57 Table A-1 (continued)
Jan-Dec 2012 Class E F :0.301 mh N NNE INE IENE E ESE SE SSE S SSW SW IWSW W WNW NW NNW TOTAL Calm-0.95 0 1 1 0 1 2 1 1 1 2 1 1 3 1 2 1 19 0.95-3.5 21 30 22 32 33 32 43 44 84 73 58 71 69 51 39 14 716 3.5-7.5 7 15 25 4 17 13 39 32 77 191 178 185 82 38 23 8 934 7.5-12.5 0 0 1 0 3 2 1 0 7 33 20 2 4 1 0 0 74 12.5-18.5 0 0 2 3 5 0 0 0 0 0 0 0 0 0 0 0 10 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 28 46 ] 51 39 59] 49 84 1 77 11691 299 1 257 [ 259 11581 91 1 64 1 23 1 1753 Class F Freq 0.087 mph I N ( NNE NE ENE E ESE SE SSE I S I SSW I SW I WSW I W I WNW I NWI NNW I TOTAL Calm-0.95 0 1 0 0 2 1 1 2 2 4 1 6 2 1 0 1 24 0.95-3.5 2 4 0 2 3 2 3 26 37 43 39 58 30 17 6 3 275 3.5-7.5 0 1 1 0 0 0 0 1 2 38 131 18 1 3 1 0 197 7.5-12.5 0 0 0 0 0 0 0 0 0 4 9 0 0 0 0 0 13 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 I 1 I 2 I5 I3 I4 I29 41 89 1180 1 82 33 21 1 7 4 509 Class G Freq 0.018 mph IN NNE NE ENE E ESE SE SSE S SSW SW I WSW I W N Iv INWv NNW TOTAL-Calm-0.95 0 0 0 0 0 0 1 0 0 0 0 0 1 0 0 0 2 0.95-3.5 0 0 0 0 1 1 0 0 0 6 16 27 14 4 0 0 69 3.5-7.5 0 0 0 1 0 0 0 0 0 2 24 7 0 0 0 0 34 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 I1 1I 1 I1 0 j 0 8 40 34 115 1 4 0 0I 105 AIl+Missing 1.000_mph I NIi E I EsI SE I NE E E E SE S S SSW I SW I WSW I W IWNWNI W NNW TOTAL Calm-0.95 1 2 1 0 3 3 3 4 4 6 3 9 6 2 2 3 52 0.95-3.5 154 138 139 148 193 103 120 158 218 229 192 298 252 196 158 103 2799 3.5-7.5 155 283 265 140 175 137 155 103 336 809 738 495 397 264 239 116 4807 7.5-12.5 23 60 45 18 27 28 16 3 69 270 165 42 103 76 82 19 1046 12.5-18.5 7 15 14 3 8 2 1 0 0 14 15 0 0 0 0 0 79 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 340 1 498 14641 3091 4061 273 12951 268 1271 13281 11131 844 17581 538 14811 241 1 8783 Page 58 Table A-2 Joint Frequency Distribution of Wind Directions and Speeds For the 220-ft level of the 220-ft Tower Jan-Mar 2012 Class A Fre: 0.003 mph N NNE NE ENEI E ] ESEI SE [SSE[ S ISSWI SW IWSWI W IvNWl NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 1 0 1 0 0 0 0 0 0 0 0 0 1 0 0 1 4>24 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 2 TOTALI 1 0 1[01 on ol .ol o lo l l .11 l o l l 11 6 Class B FreL 0.005 mp.I N [ NNEI NE I ENE I E ESE SE I SSE S I SSW I SW IvvWSW W IWNVI NW INNNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 1 0 0 0 .0 0 0 0 0 1 0 0 0 0 0 0 2 12.5-18.5 1 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 2 18.5-24 0 0 1 0 0 0 0 0 0 0 0 0 0 1 0 1 3>24 0 1 0 0 1 0 0 0 0 0 0 0 0 0 0 0 2 TOTAL 2 1 1 0 11o o o l o l0 0 0 1 o0 1 o 1 o n 1 9 Class C Fre 0 0.020 mph IN NNE NE ENE E ESE SE SSE S ISSW Ivv IS ] WSWIW IWNWI NW I[NNWvI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 1 0 0 0 0 0 0 0 .0 0 0 1 0 0 0 0 2 12.5-18.5 0 4 6 1 0 0 0 0 2 0 0 0 2 1 1 0 17 18.5-24 3 2 1 0 1 0 0 0 0 1 0 0 0 2 0 2 12>24 0 2 0 0 2 0 0 0 0 0 0 0 2 1 0 0 7 TOTAL 41 81 71 1 3 [0 1 211 0 11 41 41 1 21 38 Class D Fre0 0.672 mph IN I NNEI NE ENEI E [ESEI SE I SSE I S ISSW]I SW IvWSWv IVWNWV [ I NNWvI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 2 0 0 0 0 0 0 0 2 0 0 0 0 0 6 3.5-7.5 2 4 5 6 4 3 7 4 3 2 4 5 6 2 3 4 64 7.5-12.5 7 12 7 11 12 20 10 2 13 32 24 27 24 22 19 16 258 12.5-18.5 27 12 5 0 5 15 10 6 25 52 75 41 86 50 41 17 467 18.5-24 13 8 2 2 3 3 15 1 1 21 40 15 37 46 44 25 276>24 24 6 0 7 14 0 1 0 0 13 24 5 21 32 31 5 183 TOTAL I741 43 ] 21 26 [38 [ 41 I 43 13 42] 120 1.169 1 93 [ 174 1 152 1 1381 67 1254 Page 59 Table A-2 (continued)
Jan-Mar 2012 Class E Fr 0.273 mph I N INNE IN EEI E I ESE ISE SSE IS SSW SW WSW I WI WNW INW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 3 1 2 1 0 3 1 0 0 0 1 0 2 3 3 23 3.5-7.5 13 4 3 3 8 3 11 4 3 5 6 7 2 12 10 5 99 7.5-12.5 1 2 0 0 1 5 8 6 15 21 8 12 21 23 11 4 138 12.5-18.5 0 0 0 0 0 4 10 11 12 15 27 17 40 14 6 1 157 18.5-24 0 0 0 1 0 0 7 3 1 11 26 2 7 12 2 1 73>24 0 0 0 1 0 0 0 0 0 3 10 0 2 3 0 1 20 TOTAL I17 9 1 4 [ 7 [101 12 139[ 25 1311 55 1677 39 172 1 66 132 1 15 510 Class F Fr 0.024 mph I NJ NNE INEI ENE EI ESE ISEI SSE IS SSW SW WSW W WNW INWI NNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 2 7.5-12.5 0 0 0 0 0 0 0 1 0 3 0 2 1 2 1 0 10 12.5-18.5 0 0 0 0 0 0 0 1 1 1 8 5 3 1 0 0 20 18.5-24 0 0 0 0 0 0 0 0 0 1 4 3 0 0 0 0 8>24 0 0 0 0 0 0 0 0 0 1 2 0 0 0 0 0 3 TOTAL I 1 0 10 0 101 0 10 2 121 141 10 1 4 1 3 1 1 1 44 Class G Fr 0.002 mph I N I N ENE IE IESISE ISSE IS ISSW SWvI WSW W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 2 7.5-12.5 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 2 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 101 0 100J 10 111 0 0 01 3101 0 10]1 0 10101 4 Al+Missing F 1.000__ mh IN INNE INEI ENE IE IESE ISEI SSE IS1 SSW ISW IWSW I[WI WNW INWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 5 3 2 1 0 4 1 0 0 6 1 0 3 3 3 38 3.5-7.5 15 9 16 17 15 8 23 10 9 9 11 15 12 17 16 11 213 7.5-12.5 14 21 14 18 23 37 24 11 29 65 37 47 47 49 39 23 498 12.5-18.5 34 19 11 3 6 21 20 26 40 76 123 80 131 72 51 27 740 18.5-24 21 10 5 3 4 3 22 4 3 39 76 27 46 67 52 35 417>24 26 9 0 8 17 0 1 0 0 20 58 7 25 37 51 18 277 TOTAL 1161 73 1491 51 166[ 9 1 941 52 181] 209 1311] 177 1261 [ 245 12121 117 1 2183 Page 60 Table A-2 (continued)
Apr-Jun 2012 Class A Fre ####CamphI95 NNE NE ENE 1 E SE SSE S I0 0 I 0 INW TOTAL Ca0m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL Iol o o o o ol ol l o o ol 0 o1 [1 o Class B Fre ####Nm- N NNE .NE 5ENEIEI ESE SE SSE I S I SS I SW ]WSWIWIWNWI NW [ NNW TOTAL Ca0m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0I W 0 0L 0 L0 0 Class C Freq #::##: N INNE NE ENE E ESE 0SE SSE S 0SSW] SW IWSW0 W WNWL NW I NNW0 TOTAL Ca3m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTA.- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 [ 0 0 Class D Fret :::: ###-N ]NNEINE ENE E ESE 0SE SSE]SISSWI SW I0WSW[W [WNW[ NWI NNWI TOTAL Ca1m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0- 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ý0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0I 0 0 0 0 0 0 0 01 00 0o 0 0~ 0lo0 0 Page 61 Table A-2 (continued)
Apr-Jun 2012 Class E Fren ###mph I N I NNE NEENE E ESE ISE ISSE S ISSW IBSWI WSW Iv WJI WNW INW IvNNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0o I o 0 o ol0 0 0 0 0Z 0i 0 0 1 IoIW 0 Class F Freq ###m. N I9NNE5INEENE E ESE I SE] SSE I S I SwSWI WSWIWI WNW I NWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Class G r: mph7. N INNEINEIENE]E[ESEISEISSEISISSWISW[
WSW IWI WNW INWI NNW 00TOTAL Ca.m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 16 0 10 120 0 140 10 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I03I 0 0 0 0 00 [ 08 i 0 10 11551 i05. 0 1[ 0 AiI+Missinq Freg: 1.000 h N NNE INEI ENE IE IESE ISE ISSE IS ISSW ISW IWSW I WI WNW I NW[I NNW ITOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 10 10 1 4 5 3 5 6 2 2 2 1 2 3 5 67 3.5-7.5 25 30 34 2831 25 17 27 23 25 15 6 7 13 27 19 352 7.5-12.5 40 45 40 22 46 60 47 47 54 64 21 35 38 47 23 29 658 12.5-18.5 39 28 8 8 4 11 27 39 74 178 65 67 82 64 22 19 735 18.5-24 17 22 2 1 0 6 14 4 11 66 3 5 9 ý25 30 14 23 279>24 4 4 0 0 0 1 11 0 0 15 13 10 2 116 6 21 93 TOTAL 1131 1 139 [ 94[ 60181 108O~ 1 119 122 11681 350]1151[
119 11551 172]195[ L11-6 2-184 Page 62 Table A-2 (continued)
Jul-Sep 2012 Class A FreE E 0.060 Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 5 6 4 8 3 0 0 0 0 0 0 0 0 0 0 1 27 7.5-12.5 9 6 15 4 5 5 0 0 2 0 0 0 0 1 0 4 51 12.5-18.5 6 2 2 1 0 2 2 0 1 2 0 0 0 1 0 3 22 18.5-24 2 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 5>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I 22I 14 [21 13 8 7 2 0 3 [2 0 0 1 0 3 0 10I 105 Class B Fre: 0.027 Cm0 N I9NNE NE ENE E I ESE SE SSE I [SSW I SW W W WNWJ NW 1 TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 2 2 0 2 2 0 0 0 0 2 1 0 0 1 1 0 13 7.5-12.5 1 1 0 1 2 5 2 0 3 1 0 2 0 3 0 1 22 12.5-18.5 0 0 0 0 1 1 3 0 3 1 0 0 0 1 0 2 12 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 3[ [ l 31 51 61 51 0l 61 41 11 21 o0 51 1. 31 47 Class C Fre: 0.034 Cmp. N NNE NE ENE JE ESE I SE I SSE S ISSW SW I WSW W 0WNWJ NW I NNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0.0 0 -0 0 0 0 3.5-7.5 1 1 2 3 4 1 0 0 0 1 1 0 2 1 0 1 18 7.5-12.5 0 0 3 0 3 4 1 0 6 6 4 0 0 1 0 0 28 12.5-18.5 1 0 0 0 0 0 0 2 6 1 1 0 0 1 0 1 13 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 21 11 51 31 71 51 1[ 2[ 121 81 6I 01 2 3 0 2 59 Class D Fre: 0.352 mh IN I NNE INE IENE E I ESE I SE I SSE IS I SSW I SW IWSW W IWNWI NW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 3 2 1 1 1 0 0 0 0 0 0 0 0 0 2 12 3.5-7.5 10 4 5 9 7 13 7 2 1 8 11 8 12 2 7 7 113 7.5-12.5 8 8 8 3 5 7 11 3 22 33 21 9 12 13 13 5 181 12.5-18.5 11 4 3 3 3 7 9 6 33 89 41 4 4 4 7 19 247 18.5-24 1 00 0 0 5 1 3 13 21 3 0 0 1 1 4 53>24 0 0 0 0 0 0 0 9 3 1 0 0 0 0 0 0 13 TOTAL 1321 19 118 ] 16 16 33 28 23 72 11521 76 121 28 120 28 37 619 Page 63 Table A-2 (continued)
Jul-Sep 2012 Class~ Ff.322 C-l-s- E mph I N I NNE INEI ENEI E IESEI SEISSEI S ISSW SW WSW IW WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 1 4 3 5 1 1 1 0 1 0 0 1 1 1 0 23 3.5-7.5 2 5 3 6 9 5 5 6 4 2 5 1 2 3 3 4 65 7.5-12.5 5 7 0 6 14 10 14 10 19 38 16 7 5 10 13 3 177 12.5-18.5 4 2 8 3 4 1 3 9 9 79 40 13 8 15 3 9 210 18.5-24 1 1 0 0 0 0 1 1 1 37 27 3 0 1 7 4 84>24 1 0 0 0 0 0 0 0 0 1 0 0 0 0 3 2 7 TOTAL 1 16 1 1 1151 18 132 1 17 1241 27 133 I 158 188 1 24 1161 30 130 [ 22 [ 566 Class F Fre 0__ ph I N I NNE INEI ENEI E I ESE I EIs SSEEI S ISSW ISW] WSW IWI WNW vNW[ NNW l TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 3 1 0 1 0 2 1 1 0 1 0 1 0 0 1 12 3.5-7.5 7 4 2 4 2 5 1 1 6 6 1 0 4 3 0 6 52 7.5-12.5 3 4 0 1 10 8 8 3 3 7 0 4 5 15 13 4 88 12.5-18.5 2 0 0 0 0 0 2 5 6 7 26 24 15 5 1 5 98 18.5-24 1 3 0 0 0 0 0 0 0 6 18 4 0 0 7 0 39>24 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTAL 1 13 1 14 3 5 1 13 ] 13 1 131 10 1 16 I 47 1 3 2 I 2 5 1 2 3 I 2 1 i 1 6 1 290 Class G Fre 0.040_p_ IIN I NNE INEIENEIE I ESE[ISEISSEII S ISSWISW vSW IW[ WNW INWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 1 0 2 1 1 0 0 0 0 0 0 1 0 0 8 3.5-7.5 2 2 2 0 0 0 1 0 1 2 0 0 1 1 1 0 13 7.5-12.5 0 4 0 0 0 0 0 1 1 1 5 4 6 7 1 0 30 12.5-18.5 0 0 0 0 0 0 0 0 0 1 6 3 7 3 0 0 20 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 7 7 3 1211 1211 I121 4 Il Ll .7 1141 12 I21 0. I 71 AIl+Missing F 1.000__mph N I NNE INE ENEI E ESE SSE S ISSW SW WSW IWI WNW IvNWINNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 8 9 11 5 10 4 5 2 1 2 2 1 2 3 2 4 71 3.5-7.5 33 29 21 39 36 31 19 12 14 26 21 16 24 17 14 25 377 7.5-12.5 32 36 27 19 45 48 53 20 61 103 62 37 34 62 53 23 715 12.5-18.5 28 10 15 8 9 12 19 23 69 201 141 64 49 52 14 48 762 18.5-24 8 5 1 0 0 5 2 4 16 96 86 8 0 4 15 12 262>24 1 0 0 0 0 0 0 9 3 2 1 0 0 0 3 2 21 TOTAL 1 110 1 89 1751 711 1001 1001 981 70 11641 430 13131 126 11091 138 11011 114 1 2208 Page 64 Table A-2 (continued)
Oct-Dec 2012 Class A Freq: 0.053 mp I N NNER NE [ ENE( E I ESEI SE I SSE S Issw) SW Iwswl W IWNWI NW IFNNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 4 6 5 3 1 0 0 0 0 0 0 0 0 1 4 3 27 7.5-12.5 3 5 11 0 0 0 0 0 0 0 0 0 1 4 5 4 33 12.5-18.5 8 3 1 0 0 2 0 0 0 0 0 0 3 5 5 9 36 18.5-24 3 0 0 0 0 0 0 0 0 0 0 0 1 9 3 2 18>24 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 2 TOTAL 119 114 118 3 I1 2 0 I0 I0 0 0 0 0 5 I19 17 118 116 Class B Freq 0.024 mph N l INNE] NE ENE E IESEl SESSE I ss SW Is SW IWSW W IWNW NW INNWl TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 0 3 1 1 0 0 0 0 0 0 0 0 0 1 1 1 8 7.5-12.5 1 2 4 1 1 2 0 0 0 1 0 0 0 2 1 0 15 12.5-18.5 1 4 0 0 0 0 0 0 0 0 0 0 1 2 1 2 11 18.5-24 0 0 3 0 0 0 0 0 0 0 0 0 2 3 1 1 10>24 3 0 2 0 1 0 0 0 0 0 0 0 0 1 0 1 8 TOTAL 51 9111 2 1 2 1 2 1 0 0 1 0 1 0 0 31 9 41 51 53 Class C Freq 0.033 p IN NNEI NE I ENE I E [ESEI SE ISSEI S ISSWI W I WNW[ NW I vNNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 3.5-7.5 3 0 1 0 0 0 0 0 0 0 0 0 0 1 0 0 5 7.5-12.5 1 4 3 1 0 1 1 0 0 1 0 1 5 1 0 0 19 12.5-18.5 2 3 0 0 0 1 0 0 0 1 0 0 6 3 0 2 18 18.5-24 0 2 0 2 0 1 0 0 0 0 0 0 4 4 2 0 15>24 2 0 2 1 2 0 0 0 0 0 0 0 0 6 1 1 15 TOTAL 8 91 6 41 21 3 1 0 01 31 0 1 15 1151 31 31 73 Class D Freq: 0.491 mph N [NNEI NE I ENE] E I ESE SE jSSE S ISSSWI SW IWSwl W IWNWJ NW INNW- TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 2 0 1 2 0 0 1 0 0 0 0 0 0 0 1 9 3.5-7.5 1 5 8 7 4 3 3 2 2 8 6 5 4 5 0 2 65 7.5-12.5 4 26 36 18 7 16 6 4 13 25 19 8 12 9 5 4 212 12.5-18.5 19 21 11 36 17 8 13 4 25 57 27 34 35 27 43 10 387 18.5-24 8 20 1 6 24 11 9 6 1 7 18 8 3 30 20 26 12 209>24 27 13 21 13 16 8 1 0 0 0 0 0 9 34 46 14 202 TOTAL 6 61 187 821 99] 57 4 4 [ 29 I12 47 1081 60 [50 i 90 95 1120 1431 1084 Page 65 Table A-2 (continued)
Oct-Dec 2012 Class E Freq: 0.307 mph IN I NNEI NE [ENEI E ] ESEI SE [ SSE I S ISSW] SWlwswl W IwNw NW INNW[ TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 0 3 2 3 1 0 0 0 1 0 0 0 0 1 13 3.5-7.5 0 6 12 3 11 4 4 2 3 4 0 3 2 7 6 5 72 7.5-12.5 3 6 15 6 5 9 7 4 5 16 17 12 11 15 10 10 151 12.5-18.5 7 2 1 4 8 4 23 15 15 31 35 60 66 43 15 7 336 18.5-24 0 1 0 0 5 3 3 1 5 14 7 13 14 15 5 1 87>24 0 0 2 4 8 1 1 0 0 1 0 0 0 0 1 0 18 TOTAL 10.I 17 I 30 20 39 J 24 ] 39 22 I 28 ]6 6 8 8 93 [ 80 37 124 677 Class F Frec 0.079 mphI N NNEI NE IENE E ESEI SE I SSE S ISS SWV IWSWV W IWVNWI NW I NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 1 0 1 0 1 0 2 2 0 0 0 0 0 0 8 3.5-7.5 0 1 1 0 5 6 2 1 4 3 5 1 2 4 2 1 38 7.5-12.5 2 0 0 0 0 2 10 8 5 11 9 3 4 6 3 0 63 12.5-18.5 1 0 0 0 0 1 4 4 1 6 17 16 3 6 0 0 59 18.5-24 0 0 0 0 0 0 0 0 0 0 6 1 0 0 0 0 7>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4 4 I 1 2 0 6 1 9 17 13 12 22 37 21 9 16 I 1I 175 Class G Freq 0.014 phI N I NNE NE ENE I E IESE SE] SSEI S ISSWvI SW IvWSW] W IWNW[ NW INNWv TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 0 0 1 0 0 0 1 1 0 1 0 0 0 1 6 3.5-7.5 1 1 0 0 0 0 0 1 0 3 0 1 1 0 1 2 11 7.5-12.5 0 0 0 0 0 0 0 0 2 2 2 1 0 0 0 0 7 12.5-18.5 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 1 3 18.5-24 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0 1 3>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 21 1101 0 0 11 01 b 1 4 86 5 41 1 011 [41 30 Class All Freq 1.000 mph N NNE I NE I ENEI E I ESEI SE I SSE S I SSW [ SW IVSV VV IWNWI NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 4 2 4 6 3 2 1 3 4 1 1 0 0 0 3 38 3.5-7.5 9 22 28 14 21 13 9 6 9 18 11 10 9 19 14 14 226 7.5-12.5 14 43 69 26 13 30 24 16 25 56 47 25 33 37 24 18 500 12.5-18.5 38 33 13 40 25 16 40 23 42 95 80 110 114 86 64 31 850 18.5-24 11 23 9 26 16 13 9 2 12 32 23 18 51 51 37 16 349>24 33 13 28 18 27 9 2 0 0 1 0 0 9 41 48 16 245 TOTAL I 109 [138 149 128 ] 108 I84 861 48 91 206 162 164 216] 234 1871 98 2208 Page 66 Table A-2 (continued)
Jan-Dec 2012 Class A Fre: 0.039 aph I NI NNEI NE 1ENEI E ESE SE IS 1 S W SSEv SS IV v W ISNW NW I NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 9 12 9 11 4 0 0 0 0 0 0 0 0 1 4 4 54 7.5-12.5 12 11 26 4 5 5 0 0 2 0 0 0 1 5 5 8 84 12.5-18.5 14 5 3 1 0 4 2 0 1 2 0 0 3 6 5 12 58 18.5-24 6 0 1 0 0 0 0 0 0 0 0 0 2 10 3 5 27>24 1 0 1 0 0 0 0 0 0 1 0 0 0 1 0 0 4 TOTAL 142 28 ]40 116 9 [ 9 2 0 3 3 0 1 0 6 23 17 29 227 Class B Fre: 0.019 Nph ]NNNE] NE IENE[ E [ESEISEISSE I S I SSWISWlIWSW[
W I[WNW[ NW I NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 2 5 1 3 2 0 0 0 0 2 1 0 0 2 2 1 21 7.5-12.5 3 3 4 2 3 7 2 0 3 3 0 2 0 5 1 1 39 12.5-18.5 2 4 0 0 1 1 3 0 3 1 0 1 1 3 1 4 25 18.5-24 0 0 4 0 0 0 0 0 0 0 0 0 2 4 1 2 13>24 3 1 2 0 2 0 0 0 0 0 0 0 0 1 0 1 10 TOTAL 110 113 12 5 [ 8 8 5 1 0 6 6 1 3 3 1 15 5 I9 109 Class C Fre 0.029 mphINIINNNE INEIENELIE I ES SEISEISSE I SISSW[ISW[I WSWI W IWNWI NW I NNW jTOTAL-Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 3.5-7.5 4 1 3 3 4 1 0 0 0 1 1 0 2 2 0 1 23 7.5-12.5 2 4 6 1 3 5 2 0 6 7 4 2 5 2 0 0 49 12.5-18.5 3 7 6 1 0 1 0 2 8 2 1 0 8 5 1 3 48 18.5-24 3 4 1 2 1 1 0 0 0 1 0 0 4 6 2 2 27>24 2 2 2 1 4 0 0 0 0 0 0 0 2 7 1 1 22 TOTAL 14 [ 18 18 8 12 8 ] 2 2 14 [ 12 [ 6 2 I 21 221 4 T 7I 170 Class D Fre0 0.507 mph I NI NNE N[ IN ENE E ESE SE SSE S ISSW ISW IWsWl W IWNWv NW INNWv TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 0.95-3.5 5 6 4 2 3 1 0 1 0 0 2 0 0 0 0 3 27 3.5-7.5 13 13 18 22 15 19 17 8 6 18 21 18 22 9 10 13 242 7.5-12.5 19 46 51 32 24 43 27 9 48 90 64 44 48 44 37 25 651 12.5-18.5 57 37 19 39 25 30 32 16 83 198 143 79 125 81 91 46 1101 18.5-24 22 28 8 26 14 17 22 5 21 60 51 18 67 67 71 41 538>24 51 19 21 20 30 8 2 9 3 14 24 5 30 66 77 19 398 TOTAL , 167 149 121 141 I 111 1 118 100 [ 48 161 380 305 1 164 2 292 1267 286 1 147 2957 Page 67 Table A-2 (continued)
Jan-Dec 2012 Class E Fr 0.301__ph I N NNE NE ENE E ESE SE SSE S SSW SW I WSW I W IWN NWI NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 6 5 8 8 4 5 2 0 1 1 1 1 3 4 4 59 3.5-7.5 15 15 18 12 28 12 20 12 10 11 11 11 6 22 19 14 236 7.5-12.5 9 15 15 12 20 24 29 20 39 75 41 31 37 48 34 17 466 12.5-18.5 11 4 9 7 12 9 36 35 36 125 102 90 114 72 24 17 703 18.5-24 1 2 0 1 5 3 11 5 7 62 60 18 21 28 14 6 244>24 1 0 2 5 8 1 1 0 0 5 10 0 2 3 4 3 45 TOTAL 143 42 149 451811 5311021 74 1921 27912251 151 11811 176 1991 61 1 1753 Class F r 0.087 mph I N ]NNE NE ENEI E ESEI SE I SSEI S I SSW SWI WSWI W WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 3 2 0 2 0 3 1 3 2 1 0 1 0 0 1 21 3.5-7.5 7 5 3 4 7 11 3 2 11 9 6 1 6 7 2 8 92 7.5-12.5 5 4 0 1 10 10 18 12 8 21 9 9 10 23 17 4 161 12.5-18.5 3 0 0 0 0 1 6 10 8 14 51 45 21 12 1 5 177 18.5-24 1 3 0 0 0 0 0 0 0 7 28 8 0 0 7 0 54>24 0 0 0 0 0 0 0 0 0 1 3 0 0 0 0 0 4 TOTAL 18 15 5 5 19 22 30 25 30 54 98 I63 38 42 27 18 509 Class G Fr 0.018N NNE NE I ENE I E ESE sI SE I SSE I S I SSW [SW I WSW I WI WNW NW NW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 1 1 0 3 1 1 0 1 1 0 1 0 1 0 1 14 3.5-7.5 3 3 2 0 0 0 1 1 1 7 0 1 2 1 2 2 26 7.5-12.5 0 4 0 0 0 1 0 1 3 4 7 5 6 7 1 0 39 12.5-18.5 0 0 0 0 0 0 0 0 1 1 7 3 7 3 0 1 23 18.5-24 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0 3>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 151 8 1 3 0 31 21 21 2 61 113116 11 151 12131 41 105 AIl+Missing 1.000 m2h IN INNE INE I ESE I SE I SSE I S I SSW I SW I WSW I WV I WN I vv NNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 24 28 26 12 21 12 14 9 10 8 11 5 3 8 8 15 214 3.5-7.5 82 90 99 98 103 77 68 55 55 78 58 47 52 66 71 69 1168 7.5-12.5 100 145 150 85 127 175 148 94 169 288 167 144 152 195 139 93 2371 12.5-18.5 139 90 47 59 44 60 106 111 225 550 409 321 376 274 151 125 3087 18.5-24 57 60 17 30 20 27 47 14 42 233 220 62 122 152 118 86 1307>24 64 26 28 26 44 10 14 9 3 38 72 7 36 94 108 57 636 TOTAL 1 466 1 439 13671 310 1 3591 361 1 3 9 7 1 292 15041 119519371 586 17411 789 15951 445 1 8783 Page 68 APPENDIX B Results of Onsite Groundwater Monitoring Program In response to the Nuclear Energy Institute (NEI) Groundwater Protection Initiative, Pilgrim Station instituted a groundwater monitoring program during 2007. Four monitoring wells were installed during the fourth quarter of 2007, and the first samples were collected in late November 2007. All four wells were installed onsite, within the protected area fence. Since these are onsite wells, they are not considered part of the Radiological Environmental Monitoring Program (REMP), and data from these wells are being reported in the annual Radiological Effluent Release Report. Also, there were no leaks or spills of radioactive material at Pilgrim Station during 2012 that could have affected onsite or offsite groundwater Two pre-existing wells were incorporated into the groundwater monitoring program in early 2008.Monitoring well MW3 is located in the owner-controlled area near Rocky Hill Road, and was added to the program during the first quarter of 2008. Since monitoring well MW3 is located slightly uphill of Pilgrim Station approximately 0.2 mile southwest of the power block, it is upgradient of the PNPS power block and outside of natural groundwater flow direction.
As such, it is considered to be a control well indicative of baseline levels in the vicinity of Pilgrim Station. Monitoring well MW4 is located within the protected area near the main transformer, and was added to the program during the 2nd quarter of 2008 as an additional onsite monitoring well.In response to recommendations from assessments performed in 2009 by Entergy and NEI, six new monitoring wells were installed within the Pilgrim Station protected area in April 2010 to better characterize groundwater flow characteristics and perform monitoring closer to selected systems, structures and components (SSCs) the contain radioactive material and could lead to groundwater contamination if leaks were to develop. Six additional sampling wells were installed in August 2010 to address additional SSCs, and perimeter locations to the northeast of the plant process buildings.
Two more wells were installed in November 2011 in locations to characterize groundwater flowing along the deep foundation along the west side of the process buildings.
The most recent addition to the well sampling network occurred in November 2012 to characterize groundwater flowing along the deep foundation along the east side of the process buildings.
At the end of 2012, the groundwater monitoring well network at Pilgrim Station consisted of twenty-one monitoring wells.Additional efforts were undertaken to try to identify potential sources of the elevated tritium detected in the monitoring wells. A technical team was assembled to review various systems and processes that might influence introduction of tritium into groundwater, and Pilgrim Station has contracted the services of a professional hydrogeological firm to assist in the effort. Samples of roof runoff, storm drain runoff, and accumulated water in manholes were collected and analyzed for tritium, but provided inconclusive results. Soil samples were collected from borings performed in the vicinity of wells MW205 and MW206 to determine the possibility of "pockets" of tritium that might be suspended above the water table that could lead to "spikes" of tritium as precipitation percolated through the soil. Soil samples were also collected during borings for installation of additional monitoring wells in 2011 and 2012, as well as during excavation activities to inspect the integrity of protective coating on sections of underground piping. These results also proved inconclusive, as no detectable tritium was detected in the soil samples. A dye tracer study was conducted in January 2011 on four underground systems to detect any potential for leakage in these systems that might carry tritium to the monitoring wells. However, due to slow rate of water movement through the soil (approximately 6-inches/day), it may take several months for dye to migrate from the underground systems to the monitoring wells. Despite the extensive efforts to date, no likely candidates for the sources of tritium in the groundwater have been identified.
Page 69 All samples collected were analyzed for tritium, a radioactive isotope of hydrogen, and well as for gamma emitting radionuclides and hard-to-detect beta emitting nuclides.
In accordance with industry practice established under the NEI initiative, lower limits of detection (LLDs) used for analysis of REMP samples were used when assessing these samples for the presence of radioactivity.
Analyses for hard-to-detect nuclides, such as iron-55 (Fe-55), nickel-63 (Ni-63), strontium-89 (Sr-89), strontium-90 (Sr-90), and gross alpha were performed on samples collected from all wells between 06-Mar and 08-Mar-2012.
Analyses for these hard-to-detect radionuclides were also performed on initial samples collected from MW216 following its installation in Sep-2012.Tritium was the only radionuclide detected in the samples that is attributed to operations of Pilgrim Station. No plant-related gamma emitting radionuclides or hard-to-detect beta emitting radioactivity was detected in any of the samples. Naturally-occurring radioactivity was detected in the samples.Such levels of natural radioactivity are expected as these radionuclides are dissolved into the groundwater from the rocks and soil. The fact that these low levels of naturally-occurring radioactivity can be detected demonstrated the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater.
If any plant-related gamma activity was contained in the groundwater, the analytical techniques used would be able to detect them.Results of the tritium analyses are presented in the following tables. In these tables, a value of"NDA < xx" in the columns indicates that no activity was detected in the sample when analyzed to the minimum-detectable level following the "<" sign. For example, the sample collected from MW201 on 07-Feb-2012 contained no detectable tritium, and a minimum detectable concentration of 411 pCi/L was achieved on that sample. The achieved sensitivity of 411 pCi/L is well below the required REMP LLD of 3000 pCi/L, and no tritium was detected even when counted to this more sensitive level of detection.
In many instances, the detection sensitivity was even below 350 pCi/L, with no detection of tritium at these very low levels.The following tables list the tritium concentrations observed in the samples collected from the monitoring wells during 2012. The first table lists the results from the priority wells sampled on a more frequent basis, while the second and third tables list results from the non-priority wells sampled on a less frequent basis. There were a few instances during which sampling wells were inaccessible due to temporary storage of shipping containers (MW206 on 05/02 and 05/15) or due to onsite construction activities (MW212 on 06/28, 08/22, and 11/15).Low levels of tritium, a radioactive isotope of hydrogen, were detected in the many of the onsite wells. Although gamma spectroscopy and gross alpha analyses indicated the presence of naturally-occurring radioactivity, such as potassium-40 and radon daughters from the uranium/thorium decay chains, there was no indication of any plant-related radioactivity in the samples, other than tritium.Page 70 Sample Tritium Concentration by Monitoring Well -pCi/Liter Value +/- 1-si ma uncertainty Date MW201 MW205 MW206 MW209 MW211 MW215 MW216 MW217 01/04/12 348 +/- 107 7570+/- 244 2420 +/- 158 967 +/- 125 1290 +/- 134 1480 +/- 139 442 +/- 112 01/10/12 407 +/- 117 4990+/- 207 2890 +/- 171 967 +/- 131 1170 +/- 136 1320 +/- 139 NDA<343 01/19/12 582+/-115 5780+/-224 2830+/-170 1180+/-133 1250+/-136 1440+/-137 504+/-111 01/24/12 646 +/- 139 2500 +/- 188 3250 +/-204 938 148 852 145 1390 +/- 160 434 +/- 133 02/07/12 NDA<411 8400+/- 305 2890 +/-206 933 155 1200 164 1170 +/- 162 492 +/- 143 02/21/12 707 +/- 124 4380+/- 209 2180 +/- 163 1200 139 1380 143 1600 +/- 150 901 +/- 130 03/06/12 514 +/- 124 5090 +/-240 2480 +/- 185 1250 +/-154 1220 153 1490 +/- 161 517 +/- 132 03/20/12 NDA<370 2260 +/- 189 1440 +/- 162 769 151 951 154 1200 +/- 162 520 +/- 141 04/03/12 NDA<393 6940 +/-253 2360 +/- 176 1050 148 1230 153 1310+/- 154 494 +/- 132 04/17/12 780 +/- 129 3860 +/- 199 1930 +/- 159 1010 +/- 137 1590 151 1320 +/- 144 695 +/- 128 05/02/12 674 +/- 139 5440 +/- 247 Inaccessible 1030 +/- 150 1230 +/- 156 1730 +/- 169 660 +/- 139 05/15/12 592 +/- 146 1820 +/- 179 Inaccessible 985 +/- 159 1140 +/-163 1200 +/- 164 666 +/- 147 05/29/12 629 +/- 150 5760+/- 248 1550 +/- 170 887 +/- 156 1190 +/-160 1470 +/- 169 462 +/- 140 06/19/12 554+/-123 6440+/-216 1010+/-132 1050+/-132 1130+/-163 900+/-157 865+/-130 07/11/12 648 +/- 125 1220 +/- 136 1240 +/- 137 889 158 1360 +/- 139 1360 140 NDA<444 07/26/12 2310+/-218 4220+/-277 977+/-173 1111+/-179 1310+/-184 1230+/-183 925+/-172 08/07/12 616 +/- 153 1180 +/- 145 1480 155 907 +/-136 826 +/- 159 1210 145 657 +/- 124 08/22/12 438 +/- 127 1670 +/- 161 1320 +/-150 696 +/-134 866 +/- 138 1090 145 657 +/- 133 09/07/12 NDA<448 1400 +/- 192 1080 +/-146 800 +/-137 951 +/- 175 831 +/-174 526 +/- 124 09/20/12 438 +/-120 2260 +/- 167 1640 152 1060 +/-139 901 +/- 132 1060 139 3150 +/- 186 440 +/- 119 09/26/12 3230 +/- 186 10/03/12 NDA<411 1050 +/- 156 1080 +/-156 613 +/-143 704 +/- 145 1050 +/-155 2250 +/- 181 436 +/- 140 10/09/12 2670 +/- 190 10/17/12 NDA<351 1900 +/- 179 1360 +/-153 584 130 985 +/- 142 1110 146 4800+/- 224 424 +/- 124 10/25/12 4430 +/- 249 11/01/12 407+/-121 3520+/-198 4300+/-212 864+/-140 1040+/-140 1030+/-140 7620+/-263 485+/-124 11/06/12 3060 +/- 189 11/15/12 551 +/- 128 1210 +/- 144 1510 151 714 130 1070 +/- 143 1070 +/-137 2460 +/- 172 NDA<381 11/21/12 3670 +/- 211 11/29/12 NDA<371 3680 +/- 210 1970 175 810 143 986 +/- 148 1010 +/- 148 3960 +/- 216 NDA<372 12/04/12 3740 +/- 212 12/14/12 NDA<379 1040 +/- 144 2820+/- 205 928 +/- 139 685 +/- 134 1220 +/- 147 5540 +/- 261 12/21/12 5430 +/- 233 12/27/12 507 +/- 121 3510 +/- 199 3670+/- 202 669 +/- 137 1230 +/- 152 1130 +/- 148 5240 +/-227 Sample Tritium Concentration by Monitoring Well -pCi/Liter Value +/- 1-sigma uncertainty Date MW202 MW202-1 MW203 MW204 MW207 MW208-S MW208-1 03/06/12 942 +/- 148 NDA<385 NDA<379 NDA<384 447 +/- 130 NDA<378 NDA<382 06/28/12 985 +/- 161 541 +/- 128 NDA<430 NDA<420 488 +/- 148 NDA<372 NDA<427 08/22/12 871 +/- 138 NDA<346 NDA<347 NDA<341 537 +/- 129 NDA<345 NDA<354 11/15/12 1160 +/- 145 NDA<365 NDA<363 NDA<370 NDA<389 NDA<387 NDA<387 Sample Tritium Concentration b Monitoring Well -pCi/Liter Value +/- 1-sigma uncertainty Date MW210 MW212 MW213 MW214 MW3 MW4 03/06/12 1080 +/- 151 534 +/- 135 NDA<385 NDA<379 NDA<379 408 +/- 130 06/28/12 1010 +/- 163 Inaccessible NDA<428 NDA<434 NDA<427 421 +/- 140 08/22/12 738 +/- 136 Inaccessible NDA<345 NDA<337 NDA<347 419 +/- 124 11/15/12 .844 +/- 137 Inaccessible NDA<363 NDA<381 NDA<388 696 +/- 127 Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 337 pCi/L, up to a maximum concentration of 8,400 pCi/L. The average concentrations from these onsite wells are well below the voluntary communication reporting level of 20,000 pCi/L as established by the EPA Drinking Water Standard.
Although the EPA Standard provides a baseline for comparison, no drinking water sources are affected by this tritium. All of the affected wells are onsite, and the general groundwater flow pathway is under Pilgrim Station and out into the salt Page 71 water of Cape Cod Bay. As such, there is no potential to influence any off-site drinking water wells.Even if worst-case assumptions were made and the water from monitoring well MW-216 (average concentration
= 4083 pCi/L) was consumed as drinking water for an entire year, the maximum dose consequence would be less than 0.35 mrem/yr. In actuality, any dose consequence would be much less than this, as any tritium-laden water potentially leaving the site would be diluted into the seawater of Cape Cod Bay before being incorporated into any ingestion pathways.
No drinking water ingestion pathway exists at the Pilgrim Station site.Although there are no indications that the groundwater containing low concentrations of tritium is actually migrating offsite, a bounding calculation was performed to assess the potential dose impact of such a scenario.
Based on the tritium concentrations detected during 2012, the annual average concentrations of tritium in groundwater in the four monitoring wells most closely adjacent to the shoreline (MW204, MW205, MW202, and MW201) were used to estimate tritium migration into the intake bay. Hydrological characteristics of the compacted backfill in the vicinity of these wells were measured in 2010 and indicate the hydraulic conductivity ranges from 0.002 cm/sec to about 0.006 cm/sec. When coupled with the hydraulic slope of 0.014 and average porosity of 0.3, the flow velocity was calculated as being between 0.08 and 0.23 meters per day. Using an assumed horizontal shoreline interface area 236 meters long by 3 meters deep that could potentially transmit groundwater into the intake bay, the annual discharge of groundwater would be about 12.5 million Liters of water per year. Assuming this volume of 12.5 million liters contained the segment-weighted average concentration of 1180 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.0148 Curies. This activity represents less than 0.050%of the annual airborne effluent of tritium released from the reactor building vent (see Table 2.2-C).Such airborne effluents can be washed down to the ground surface during precipitation events and infiltrate into the ground, thereby introducing tritium into the groundwater.
In the hypothetical scenario described above, the 0.0148 Curies of tritium entering the intake bay would be further diluted into the circulating water flow of the plant. As documented in Table 2.3-A, the total volume of circulating water flow during 2012 was 616 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.024 pCi/L. Such a concentration would be well below the detection sensitivity of about 450 pCi/L used to analyze water collected from the discharge canal as part of the radiological environmental monitoring program (REMP). The calculated dose to the maximum-exposed member of the public from such a hypothetical release would be 0.000000014 millirem, resulting from tritium incorporated into fish and shellfish.
Since the tritium would be incorporated into seawater, there is no drinking water ingestion pathway in the described scenario.The following table lists the hydrological characteristics in the vicinity of each of the monitoring wells used to estimate tritium migration.
Predicted flow velocities, annual discharge volumes, average tritium concentrations, and hypothetical tritium discharges are listed for each shoreline segment represented by each monitoring well. Although all four samples collected from monitoring well MW204 indicated no detectable activity, for purposes of conservatism the well was assumed to contain tritium at the average of the detection limits achieved on the four quarterly samples.Page 72 Shoreline Segment Number 1 2 3 4 Monitoring Well Number MW204 MW205 MW202 MW201 Hydraulic Conductivity
-cm/sec 1.99E-03 4.27E-03 3.13E-03 5.64E-03 Hydraulic Slope 0.014 0.014 0.014 0.014 Porosity 0.300 0.300 0.300 0.300 Flow Velocity -m/day 8.02E-02 1.72E-01 1.26E-01 2.27E-01 Flow Velocity -ft/yr 9.61 E+01 2.06E+02 1.51 E+02 2.72E+02 Length of Shoreline Segment -m 61.0 38.1 45.7 91.4 Thickness of Water Layer -m 3.0 3.0 3.0 3.0 Volumetric Discharge
-m 3/day 4.40E+00 5.90E+00 5.19E+00 1.87E+01 Volumetric Discharge
-Liter/yr 1.61 E+06 2.16E+06 1.90E+06 6.84E+06 Annual Average H-3 Concentration
-pCi/L 3.79E+02 3.67E+03 9.90E+02 6.50E+02 Annual Segment Tritium Discharge
-Ci/yr 6.09E-04 7.91 E-03 1.88E-03 4.44E-03 Total Volumetric Discharge
-L/yr 1.25E+07 Total H-3 Discharge
-Ci/yr 1.48E-02 Annual Circulating Water Flow -Liter/yr 6.16E+1 1 Discharge Canal H-3 Concentration
-Ci/L 2.41E-14 Discharge Canal H-3 Concentration
-pCi/L 2.41E-02 Max. Indiv. Dose Factor -mrem/yr per Ci/L 5.73E+05 Maximum Individual Dose -mrem/yr 1.38E-08 In conclusion, there were no known leaks or spills of radioactive material at Pilgrim Station during 2012 that could have affected onsite or offsite groundwater.
The only radionuclide detected in groundwater during the 2012 monitoring effort that is attributable to Pilgrim Station operations is tritium, and all concentrations were well below any reporting criteria established in the Pilgrim Station Offsite Dose Calculation Manual and through EPA safe drinking water standards.
Page 73 APPENDIX C CORRECTIONS TO PREVIOUS EFFLUENT REPORTS There were no corrections to past effluent reports to include in the 2012 annual report.Page 74 APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2012.Page 75