ML15138A373: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(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 2014, 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 2014, 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, lC, 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, lC, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference  
: 1) format.2.1 Supolemental 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 Supolemental 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: 1.68 Ci, 0.0532 gCi/sec* lodines and particulates with 0.00149 Ci, 0.0000473  
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: 1.68 Ci, 0.0532 gCi/sec* lodines and particulates with 0.00149 Ci, 0.0000473  
Line 113: Line 117:
Ci Na-24 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cr-51 N/A O.00E+00 N/A N/A 0.00E+00 Mn-54 N/A 2.21 E-06 N/A N/A 2.21 E-06 Fe-55 N/A 0.00E+00 N/A N/A 0.00E+00 Fe-59 N/A 0.OOE+00 N/A N/A 0.00E+00 Co-58 N/A 0.OOE+00 N/A N/A 0.OOE+00 Co-60 N/A 4.64E-06 N/A N/A 4.64E-06 Zn-65 N/A 0.00E+00 N/A N/A 0.OOE+00 Zn-69m N/A O.OOE+00 N/A N/A 0.OOE+00 Sr-89 N/A 0.OOE+00 N/A N/A 0.OOE+00 Sr-90 N/A 0.OOE+00 N/A N/A 0.OOE+00 Zr/Nb-95 N/A 0.OOE+00 N/A N/A 0.OOE+00 Mo/Tc-99 N/A 0.OOE+00 N/A N/A 0.00E+00 Ag-11Om N/A 0.OOE+00 N/A N/A 0.OOE+00 Sb-124 N/A 0.OOE+00 N/A N/A 0.OOE+00 1-131 N/A 0.00E+00 N/A N/A 0.OOE+00 1-133 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 34 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 37 N/A 6.39E-07 N/A N/A 6.39E-07 Ba/La-1 40 N/A 0.OOE+00 N/A N/A 0.OOE+00 Ce-141 N/A 0.00E+00 N/A N/A 0.OOE+00 Ce-144 N/A 0.OOE+00 N/A N/A 0.OOE+00 Total for period N/A 7.50E-06 N/A N/A 7.50E-06 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 N/A NDA N/A N/A NDA Xe-135 N/A NDA N/A N/A NDA Total for period N/A NDA N/A N/A NDA Notes for Table 2.3-B: 1. N/A stands for not applicable.
Ci Na-24 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cr-51 N/A O.00E+00 N/A N/A 0.00E+00 Mn-54 N/A 2.21 E-06 N/A N/A 2.21 E-06 Fe-55 N/A 0.00E+00 N/A N/A 0.00E+00 Fe-59 N/A 0.OOE+00 N/A N/A 0.00E+00 Co-58 N/A 0.OOE+00 N/A N/A 0.OOE+00 Co-60 N/A 4.64E-06 N/A N/A 4.64E-06 Zn-65 N/A 0.00E+00 N/A N/A 0.OOE+00 Zn-69m N/A O.OOE+00 N/A N/A 0.OOE+00 Sr-89 N/A 0.OOE+00 N/A N/A 0.OOE+00 Sr-90 N/A 0.OOE+00 N/A N/A 0.OOE+00 Zr/Nb-95 N/A 0.OOE+00 N/A N/A 0.OOE+00 Mo/Tc-99 N/A 0.OOE+00 N/A N/A 0.00E+00 Ag-11Om N/A 0.OOE+00 N/A N/A 0.OOE+00 Sb-124 N/A 0.OOE+00 N/A N/A 0.OOE+00 1-131 N/A 0.00E+00 N/A N/A 0.OOE+00 1-133 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 34 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 37 N/A 6.39E-07 N/A N/A 6.39E-07 Ba/La-1 40 N/A 0.OOE+00 N/A N/A 0.OOE+00 Ce-141 N/A 0.00E+00 N/A N/A 0.OOE+00 Ce-144 N/A 0.OOE+00 N/A N/A 0.OOE+00 Total for period N/A 7.50E-06 N/A N/A 7.50E-06 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 N/A NDA N/A N/A NDA Xe-135 N/A NDA N/A N/A NDA Total for period N/A NDA 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 pCi/mL lodines: 1 E-06 ptCi/mL Noble Gases: 1E-05 pCi/mL All Others: 5E-07 pCi/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, 44%* 33-ft Wind Direction (from): South-southwest, 16%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 15%* 220-ft Wind Speed: 12.5-18.5 mph, 38%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 100%, which met the 90% annual data recovery goal specified by the NRC.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.
5E-08 pCi/mL lodines: 1 E-06 ptCi/mL Noble Gases: 1E-05 pCi/mL All Others: 5E-07 pCi/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, 44%* 33-ft Wind Direction (from): South-southwest, 16%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 15%* 220-ft Wind Speed: 12.5-18.5 mph, 38%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 100%, which met the 90% annual data recovery goal specified by the NRC.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 120: Line 131:
For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.000054 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.00026 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 0.000054 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.00026 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building).
Page 20 Table 4.1 Maximum Doses From Noble Gas Releases During 2 0 1 4 (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 During 2 0 1 4 (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.OOE+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Apr-Jun (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Jul-Sep (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Oct-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (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.OOE+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Apr-Jun (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Jul-Sep (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Oct-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (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 139: Line 153:
ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway: DI DI DIV3 DIVCG 3  DIVCM3 DIVM3 Age Class: Adult Bone 2.19E-04 1.47E-04 5.87E-03 2.36E-03 2.06E-03 3.58E-03 GI-LLI 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Kidney 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Liver 2.61E-03 1.71 E-03 5.58E-03 8.41E-04 6.34E-04 9.83E-04 Lung 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Thyroid 2.79E-03 1.82E-03 5.96E-03 9.46E-04 6.90E-04 1.01E-03 T.Body 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Age Class: Teen Bone 3.13E-04 2.1OE-04 9.49E-03 3.96E-03 3.11E-03 5.05E-03 GI-LLI 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Kidney 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.67E-04 1.29E-03 Liver 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Lung 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Thyroid 2.88E-03 1.88E-03 7.12E-03 1.37E-03 9.47E-04 1.31E-03 T.Body 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Age Class: Child Bone 4.32E-04 2.90E-04 2.27E-02 9.56E-03 7.32E-03 1.17E-02 GI-LLI 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Kidney 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81 E-03 2.72E-03 Liver 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Lung 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Thyroid 2.64E-03 1.73E-03 1.18E-02 2.82E-03 1.96E-03 2.75E-03 T.Body 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Age Class: Infant Bone 3.18E-04 2.14E-04 1.79E-04 5.99E-03 4.17E-03 7.99E-05 GI-LLI 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Kidney 1.38E-03 9.06E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Liver 1.38E-03 9.05E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Lung 1.38E-03 9.06E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Thyroid 1.63E-03 1.06E-03 7.92E-04 2.25E-03 1.38E-03 5.69E-05 T.Body 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 1 2 3 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation C = Cow Milk G = Goat Milk K= Vegetable Garden 1 = 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 2014 Receptor:
ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway: DI DI DIV3 DIVCG 3  DIVCM3 DIVM3 Age Class: Adult Bone 2.19E-04 1.47E-04 5.87E-03 2.36E-03 2.06E-03 3.58E-03 GI-LLI 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Kidney 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Liver 2.61E-03 1.71 E-03 5.58E-03 8.41E-04 6.34E-04 9.83E-04 Lung 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Thyroid 2.79E-03 1.82E-03 5.96E-03 9.46E-04 6.90E-04 1.01E-03 T.Body 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Age Class: Teen Bone 3.13E-04 2.1OE-04 9.49E-03 3.96E-03 3.11E-03 5.05E-03 GI-LLI 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Kidney 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.67E-04 1.29E-03 Liver 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Lung 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Thyroid 2.88E-03 1.88E-03 7.12E-03 1.37E-03 9.47E-04 1.31E-03 T.Body 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Age Class: Child Bone 4.32E-04 2.90E-04 2.27E-02 9.56E-03 7.32E-03 1.17E-02 GI-LLI 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Kidney 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81 E-03 2.72E-03 Liver 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Lung 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Thyroid 2.64E-03 1.73E-03 1.18E-02 2.82E-03 1.96E-03 2.75E-03 T.Body 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Age Class: Infant Bone 3.18E-04 2.14E-04 1.79E-04 5.99E-03 4.17E-03 7.99E-05 GI-LLI 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Kidney 1.38E-03 9.06E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Liver 1.38E-03 9.05E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Lung 1.38E-03 9.06E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Thyroid 1.63E-03 1.06E-03 7.92E-04 2.25E-03 1.38E-03 5.69E-05 T.Body 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 1 2 3 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation C = Cow Milk G = Goat Milk K= Vegetable Garden 1 = 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 2014 Receptor:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:
ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 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 8.42E-04 5.66E-04 2.26E-02 9.12E-03 7.99E-03 1.39E-02 GI-LLI 1.05E-02 6.90E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Kidney 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Liver 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Lung 1.06E-02 6.92E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Thyroid 1.13E-02 7.36E-03 2.40E-02 3.81E-03 2.76E-03 3.96E-03 T.Body 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Age Class: Teen Bone 1.21 E-03 8.11E-04 3.66E-02 1.53E-02 1.21 E-02 1.96E-02 GI-LLI 1.07E-02 7.00E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Kidney 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Liver 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Lung 1.08E-02 7.04E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Thyroid 1.16E-02 7.60E-03 2.86E-02 5.51E-03 3.78E-03 5.15E-03 T.Body 1.07E-02 6.99E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Age Class: Child Bone 1.66E-03 1.12E-03 8.75E-02 3.70E-02 2.83E-02 4.52E-02 GI-LLI 9.56E-03 6.26E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Kidney 9.56E-03 6.26E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Liver 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Lung 9.61 E-03 6.29E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Thyroid 1.07E-02 6.98E-03 4.69E-02 1.13E-02 7.79E-03 1.07E-02 T.Body 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Age Class: Infant Bone 1.23E-03 8.25E-04 6.89E-04 2.32E-02 1.61 E-02 3.09E-04 GI-LLI 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-04 Kidney 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Liver 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Lung 5.61E-03 3.67E-03 2.73E-03 6.18E-03 4.04E-03 2.04E-04 Thyroid 6.60E-03 4.31 E-03 3.20E-03 9.35E-03 5.68E-03 2.28E-04 T.Body 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-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.
ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 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 8.42E-04 5.66E-04 2.26E-02 9.12E-03 7.99E-03 1.39E-02 GI-LLI 1.05E-02 6.90E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Kidney 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Liver 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Lung 1.06E-02 6.92E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Thyroid 1.13E-02 7.36E-03 2.40E-02 3.81E-03 2.76E-03 3.96E-03 T.Body 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Age Class: Teen Bone 1.21 E-03 8.11E-04 3.66E-02 1.53E-02 1.21 E-02 1.96E-02 GI-LLI 1.07E-02 7.00E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Kidney 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Liver 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Lung 1.08E-02 7.04E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Thyroid 1.16E-02 7.60E-03 2.86E-02 5.51E-03 3.78E-03 5.15E-03 T.Body 1.07E-02 6.99E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Age Class: Child Bone 1.66E-03 1.12E-03 8.75E-02 3.70E-02 2.83E-02 4.52E-02 GI-LLI 9.56E-03 6.26E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Kidney 9.56E-03 6.26E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Liver 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Lung 9.61 E-03 6.29E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Thyroid 1.07E-02 6.98E-03 4.69E-02 1.13E-02 7.79E-03 1.07E-02 T.Body 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Age Class: Infant Bone 1.23E-03 8.25E-04 6.89E-04 2.32E-02 1.61 E-02 3.09E-04 GI-LLI 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-04 Kidney 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Liver 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Lung 5.61E-03 3.67E-03 2.73E-03 6.18E-03 4.04E-03 2.04E-04 Thyroid 6.60E-03 4.31 E-03 3.20E-03 9.35E-03 5.68E-03 2.28E-04 T.Body 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-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 quarters 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 0.00000029 mrem. The maximum organ dose (adult age class, GI-LLI) was 0.00000087 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2014 Age Class Organ Dose -mrem *Organ Adult Teen I 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 0.OOE+00 Liver 0.OOE+00 O.OOE+00 0.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 0.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 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 2014 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 5.28E-08 2.14E-07 6.49E-08 GI-LLI 8.67E-07 7.17E-07 2.39E-07 Kidney 6.18E-08 2.21E-07 6.15E-08 Liver 1.49E-07 3.03E-07 1.34E-07 Lung 4.15E-08 2.02E-07 4.59E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1 .44E-07 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2014 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 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone O.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney O.OOE+00 O.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 5.27E-08 2.14E-07 6.47E-08 GI-LLI 8.66E-07 7.16E-07 2.39E-07 Kidney 6.17E-08 2.21E-07 6.14E-08 Liver 1.49E-07 3.02E-07 1.34E-07 Lung 4.14E-08 2.01 E-07 4.58E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1.44E-07* 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 quarters 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 0.00000029 mrem. The maximum organ dose (adult age class, GI-LLI) was 0.00000087 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2014 Age Class Organ Dose -mrem *Organ Adult Teen I 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 0.OOE+00 Liver 0.OOE+00 O.OOE+00 0.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 0.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 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 2014 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 5.28E-08 2.14E-07 6.49E-08 GI-LLI 8.67E-07 7.17E-07 2.39E-07 Kidney 6.18E-08 2.21E-07 6.15E-08 Liver 1.49E-07 3.03E-07 1.34E-07 Lung 4.15E-08 2.02E-07 4.59E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1 .44E-07 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2014 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 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone O.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney O.OOE+00 O.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 5.27E-08 2.14E-07 6.47E-08 GI-LLI 8.66E-07 7.16E-07 2.39E-07 Kidney 6.17E-08 2.21E-07 6.14E-08 Liver 1.49E-07 3.02E-07 1.34E-07 Lung 4.14E-08 2.01 E-07 4.58E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1.44E-07* 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 173 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 173 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 72.6 +/- 23.1 mR/yr to 62.2 + 8.1 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.0 +/- 7.7 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 72.6 +/- 23.1 mR/yr to 62.2 + 8.1 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.0 +/- 7.7 mR/yr, and is indicative of natural background radiation.
Although the annual exposure at TLD location OA was 113 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 0.52 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 65.8 +/- 8.6 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.0 +/- 7.7 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 113 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 0.52 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 65.8 +/- 8.6 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.0 +/- 7.7 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 though 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 though 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 158: Line 182:
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 1.3 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 1.3 mrem/year.
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2014 Average Exposure +/- Standard Deviation:
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2014 Average Exposure +/- Standard Deviation:
mR/ eriod Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.9 +/- 5.5 14.3 +/- 2.1 13.9 +/- 1.3 14.6 +/- 1.6 Apr-Jun 18.0 +/- 5.4 14.2 +/- 2.0 13.7 +/- 1.9 14.3 +/- 2.2 Jul-Sep 19.0 +/- 6.7 15.1 +/- 2.0 15.0 +/- 1.6 16.0 +/- 2.3 Oct-Dec 17.6 +/- 5.4 14.4 +/- 2.4 13.6 +/- 1.8 15.2 +/- 1.6 Jan-Dec 72.6 +/- 23.1** 58.1 +/- 8.4 56.1 +/- 6.7 60.0 +/- 7.7 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 62.2 +/- 8.1 mR/yr.Page 36 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS The PNPS ODCM contains dose and concentration limits for radioactive effluents.
mR/ eriod Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.9 +/- 5.5 14.3 +/- 2.1 13.9 +/- 1.3 14.6 +/- 1.6 Apr-Jun 18.0 +/- 5.4 14.2 +/- 2.0 13.7 +/- 1.9 14.3 +/- 2.2 Jul-Sep 19.0 +/- 6.7 15.1 +/- 2.0 15.0 +/- 1.6 16.0 +/- 2.3 Oct-Dec 17.6 +/- 5.4 14.4 +/- 2.4 13.6 +/- 1.8 15.2 +/- 1.6 Jan-Dec 72.6 +/- 23.1** 58.1 +/- 8.4 56.1 +/- 6.7 60.0 +/- 7.7 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 62.2 +/- 8.1 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 177: Line 204:
7.5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar 2.23E-02 2.98E-01%Apr-Jun 2.1OE-02 2.80E-01%Jul-Sep 2.15E-02 2.86E-01%Oct-Dec 2.27E-02 3.02E-01%Annual Dose Objective  
7.5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar 2.23E-02 2.98E-01%Apr-Jun 2.1OE-02 2.80E-01%Jul-Sep 2.15E-02 2.86E-01%Oct-Dec 2.27E-02 3.02E-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 Value -mrem/yr Fraction of Limit Jan-Dec 8.75E-02 5.83E-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 2014 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -PCi/mL O.OOE+00 4.89E-14 O.OOE+00 O.OOE+00 1.22E-14 Fraction of Limit 0.OOE+00%1.47E-06%0.OOE+00%0.OOE+00%3.68E-07%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 piCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LICi/mL 0.OOE+00 2.52E-1 1 0.OOE+00 0.OOE+00 6.30E- 12 Fraction of Limit 0.OOE+00%2.52E-06%0.OOE+00%0.OOE+00%6.30E-07%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 jiCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/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%0.OOE+00%0.OOE+00%0.OOE+00%Page 41 Table 6.2 (continued)
15 mrem Organ Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 8.75E-02 5.83E-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 2014 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -PCi/mL O.OOE+00 4.89E-14 O.OOE+00 O.OOE+00 1.22E-14 Fraction of Limit 0.OOE+00%1.47E-06%0.OOE+00%0.OOE+00%3.68E-07%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 piCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LICi/mL 0.OOE+00 2.52E-1 1 0.OOE+00 0.OOE+00 6.30E- 12 Fraction of Limit 0.OOE+00%2.52E-06%0.OOE+00%0.OOE+00%6.30E-07%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 jiCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/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%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 2014 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 2014 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective:
1.5 mrem Total Body Dose Period Value -mrem Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 2.89E-07 1.93E-05%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 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 Value -mrem Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 2.89E-07 1.93E-05%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 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 Value -mrem Fraction of Limit Jan-Dec 2.89E-07 9.62E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective:
3 mrem Total Body Dose Period Value -mrem Fraction of Limit Jan-Dec 2.89E-07 9.62E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective:
5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar O.OOE+00 0.OOE+00%Apr-Jun 8.67E-07 1.73E-05%Jul-Sep O.OOE+00 0.OOE+00%Oct-Dec 0.OOE+00 0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective:
5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar O.OOE+00 0.OOE+00%Apr-Jun 8.67E-07 1.73E-05%Jul-Sep O.OOE+00 0.OOE+00%Oct-Dec 0.OOE+00 0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective:
10 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Dec 8.66E-07 8.66E-06%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 Value -mrem Fraction of Limit Jan-Dec 8.66E-07 8.66E-06%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 67.4 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 680 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 67.4 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 680 Curies were shipped from PNPS for processing and disposal.
Dry activated wastes and contaminated equipment shipped during the period totaled 543 cubic meters and contained 1.66 Cures of radioactivity.
Dry activated wastes and contaminated equipment shipped during the period totaled 543 cubic meters and contained 1.66 Cures of radioactivity.
Line 194: Line 228:
Kingston, TN 4 Tractor-trailer Energy Solutions, Erwin Resin Solutions, 2 (Hittman Transport)
Kingston, TN 4 Tractor-trailer Energy Solutions, Erwin Resin Solutions, 2 (Hittman Transport)
Erwin, TN 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal.B. IRRADIATED FUEL SHIPMENTS  
Erwin, TN 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc Remaining radioactive wastes will be shipped to 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 2014. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45 9.0 PROCESS CONTROL PROGRAM REVISIONS The following list summarizes changes made during 2014 to various procedures related to the Process Control Program (PCP): EN-RW-1 02, "Radioactive Shipping Procedure", Rev. 11:* Step 5.1[9](e):
& 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 2014. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45  
 
===9.0 PROCESS===
CONTROL PROGRAM REVISIONS The following list summarizes changes made during 2014 to various procedures related to the Process Control Program (PCP): EN-RW-1 02, "Radioactive Shipping Procedure", Rev. 11:* Step 5.1[9](e):
inserted the word "Radioactive" and corrected grammatical error (changed"affects" to "effects")
inserted the word "Radioactive" and corrected grammatical error (changed"affects" to "effects")
* Step 5.1[11]: revised step to correct Type B Package types* Step 5.1[12]: added step for Grand Gulf shipment of waste for free release* Steps 5.2[14] and 5.2[14](b):
* Step 5.1[11]: revised step to correct Type B Package types* Step 5.1[12]: added step for Grand Gulf shipment of waste for free release* Steps 5.2[14] and 5.2[14](b):
Line 200: Line 240:
* Step 5.2[18]: corrected regulatory reference* Step 6.0[5]: corrected procedure reference* Section 8.0: updated site-commitments for Grand Gulf, W3 and RBS per Commitment Review response from GGNS and RBS* Attachment 9.1: added field for document package completion
* Step 5.2[18]: corrected regulatory reference* Step 6.0[5]: corrected procedure reference* Section 8.0: updated site-commitments for Grand Gulf, W3 and RBS per Commitment Review response from GGNS and RBS* Attachment 9.1: added field for document package completion
* Attachment 9.1: added field for disposition of Emergency Response information
* Attachment 9.1: added field for disposition of Emergency Response information
* Attachment 9.1 expanded parenthetical in Waste Profile Form to include other companies and deleted empty rows.* Attachment 9.9 and 9.14: field for recording shipment number is reworded so as to be consistent with other attachments EN-RW-104, "Scaling Factors", Rev.10:* This is a complete rewrite of the procedure in order to bring the format into compliance with EN-AD-101-01 and to add instructions for using the new version (version 9.0) of RADMAN software.
* Attachment  
 
===9.1 expanded===
parenthetical in Waste Profile Form to include other companies and deleted empty rows.* Attachment 9.9 and 9.14: field for recording shipment number is reworded so as to be consistent with other attachments EN-RW-104, "Scaling Factors", Rev.10:* This is a complete rewrite of the procedure in order to bring the format into compliance with EN-AD-101-01 and to add instructions for using the new version (version 9.0) of RADMAN software.
No change bars are used.EN-RW-105, "Process Control Program", Rev.4:* Editorial revision to address the issue identified in CR-HQN-2013-00858, CA-02 (Develop a draft procedure that includes instructions for vendors processing waste still owned by Entergy to comply with the PCP program.)* Reworded Step 5.1[1](b) to improve clarity: inserted text "processed on-site OR off-site by vendors" EN-RW-1 06, "Integrated Transportation Security Plan", Rev. 3: " Total rewrite in order to accomplish the following:
No change bars are used.EN-RW-105, "Process Control Program", Rev.4:* Editorial revision to address the issue identified in CR-HQN-2013-00858, CA-02 (Develop a draft procedure that includes instructions for vendors processing waste still owned by Entergy to comply with the PCP program.)* Reworded Step 5.1[1](b) to improve clarity: inserted text "processed on-site OR off-site by vendors" EN-RW-1 06, "Integrated Transportation Security Plan", Rev. 3: " Total rewrite in order to accomplish the following:
o Bring the procedure into compliance with EN-AD-101-01 o Incorporate changes required by recent revision of 10CFR37 o Correct internal section references" The primary change involves replacing section 5.6 for Quantities of Concern in Rev. 2 with a new section 5.7 for Category 1 and Category 2 Quantities in Rev. 3 Page 46  
o Bring the procedure into compliance with EN-AD-101-01 o Incorporate changes required by recent revision of 10CFR37 o Correct internal section references" The primary change involves replacing section 5.6 for Quantities of Concern in Rev. 2 with a new section 5.7 for Category 1 and Category 2 Quantities in Rev. 3 Page 46  

Revision as of 00:55, 11 October 2018

Pilgrim - Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2014
ML15138A373
Person / Time
Site: Pilgrim
Issue date: 05/13/2015
From: Perkins E
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.15.034
Download: ML15138A373 (79)


Text

S"Entergy Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 May 13, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Entergy's Annual Radioactive Effluent Release Report for January 1 through December 31, 2014 Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 LETTER NUMBER 2.15.034

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 through December 31, 2014.This letter contains no new regulatory commitments.

Should you have any questions concerning the content of this letter, please contact me at (508) 830-8323.Sincerely, Everett (Chip) Perkins Manager, Regulatory Assuranc EP/rmb

Attachment:

Pilgrim's Annual Radioactive Effluent Release Report for January 1 through December 31, 2014 PNPS Letter 2.15.034 Page 2 of 2 cc: Mr. Daniel H. Dorman Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 U. S. Nuclear Regulatory Commission ATTN: Director, Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Ms. Nadiyah Morgan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 Mr. John Giarrusso Jr.Planning, Preparedness

& Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 ATTACHMENT To PNPS Letter 2.15.034 PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radioactive Effluent Release Report January 1 through December 31, 2014 ft~e SEntergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2014 Prepared by: Reviewed by: Reviewed by: K. J (.j%,j k" IV Senior HPTChemistry Specialist GPW. Blankenbiller Chemistry Manager dZ'aeX e.Lf/2q//i A. Zece Radia~on Protection Manager Page 2 SECTION 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 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2014 TABLE OF CONTENTS SECTION TITLE 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 PAGE 5 8 8 8 9 19 20 20 22 28 34 37 37 40 43 45 46 47 48 69 75 76 Page 3 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2014 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 2014 21 4.2-A Maximum Individual Organ Doses from Gaseous Effluents 23 Jan-Mar 2014 4.2-B Maximum Individual Organ Doses from Gaseous Effluents 24 Apr-Jun 2014 4.2-C Maximum Individual Organ Doses from Gaseous Effluents 25 Jul-Sep 2014 4.2-D Maximum Individual Organ Doses from Gaseous Effluents 26 Oct-Dec 2014 4.2-E Maximum Individual Organ Doses from Gaseous Effluents 27 Jan-Dec 2014 4.3-A Maximum Individual Organ Doses from Liquid Effluents 29 Jan-Mar 2014 4.3-B Maximum Individual Organ Doses from Liquid Effluents 30 Apr-Jun 2014 4.3-C Maximum Individual Organ Doses from Liquid Effluents 31 Jul-Sep 2014 4.3-D Maximum Individual Organ Doses from Liquid Effluents 32 Oct-Dec 2014 4.3-E Maximum Individual Organ Doses from Liquid Effluents 33 Jan-Dec 2014 5.0 Average TLD Exposures by Distance Zone During 2014 36 6.1 Percent of ODCM Effluent Control Limits for Gaseous Effluent 38 Releases During 2014 6.2 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases 41 During 2014 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, 2014 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, 2014. 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 1.7 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0015 Curies, tritium releases totaled 90 Curies, and carbon-14 totaled 8.3 Curies. No gross alpha radioactivity was detected in gaseous effluents.

Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.000069 mrem, with a corresponding skin dose of 0.00038 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 0.045 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.088 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.045 mrem.The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 0.0048% of the corresponding 1OCFR50 dose objectives.

Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.58% 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. One discharge of liquid effluents containing radioactivity occurred during the reporting period. This discharge contained 0.0039 Curies of tritium, and 0.0000075 Curies of fission and activation products.

The resulting maximum total body dose was 0.00000029 mrem, with a corresponding organ dose of 0.00000087 mrem. All doses from liquid discharges were less than 0.00002% of corresponding 10CFR50 objectives.

METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 100% 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 15% of the time during the reporting period. The predominant stability class was Class D, which occurred about 44% 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 1.3 mrem during 2014. There was no measurable increase during 2014 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 2014 was calculated as being about 0.57 mrem. This amount is about 0.11% 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 630 cubic meters of solid waste, containing almost 682 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, 2012, 2013, and 2014. As of the end of 2014, samples are being collected from a total of 23 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 groundwater samples. The average concentration of tritium detected in these onsite monitoring wells during 2014 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. The maximum hypothetical dose resulting from tritium in groundwater presumed to enter Cape Cod Bay is calculated to be 0.0000000050 mrem/yr. 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 2014, 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, lC, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference

1) format.2.1 Supolemental 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: 1.68 Ci, 0.0532 gCi/sec* lodines and particulates with 0.00149 Ci, 0.0000473

ýiCi/sec half-life greater than 8 days* Tritium: 90.1 Ci, 2.86 iiCi/sec* Carbon-14:

8.33 Ci, 0.264 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 1OCFR50 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 2014 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 Table 3.1-2 of the PNPS ODCM requires that if any of the gaseous effluent monitors are inoperable for more than 30-days, such events are to be reported in the Annual Radioactive Effluent Release Report with an explanation of why the affected monitor was not returned to operable status in a timely manner. During 2014 the Turbine Building Gaseous Effluent Monitoring System (GEMS, unit C-3003) was inoperable from 01-Jan-2014 through 16-Feb-2014 (47 days).During 2014, the Feed Pump Gaseous Effluent Monitoring System (GEMS, unit C-3004) was inoperable from 01-Jan-2014 through 14-Aug-2014 (226 days). During each of these periods of inoperability, compensatory sampling activities were performed during the duration of the inoperability, including manually sampling the effluent release points twice per week for noble gases, and continuous sampling of the effluent release points twice per week for particulates and radioiodines.

In both of these situations, repairs to each of the monitors were delayed due to difficulty in obtaining replacement components necessary to fix the monitor. Appendix C of this report also contains details about inoperable effluent monitors during the 2012 and 2013 reporting periods.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 was one discharge 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: 22,800 Liters* Total Dilution Volume: 614 billion Liters* Fission/Activation products:

0.00000750 Ci, 0.0000000000000122 1 iCi/mL* Tritium: 0.00387 Ci, 0.00000000000630 IpCi/mL* Dissolved/entrained noble gases: 0.00 Ci, 0.00 jiCi/mL Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2014 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: 10CFR20 Appendix B Table II b. lodines: 1OCFR20 Appendix B Table II c. Particulates with half-life

> 8 days: 1OCFR20 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 2014 2014 2014 2014 2014 a. Liquid Effluents 1. Total number of releases:

N/A 1 N/A N/A 1 2. Total time period (minutes):

N/A 1.44E+03 N/A N/A 1.44E+03 3. Maximum time period N/A 1.44E+03 N/A N/A 1.44E+03 (minutes):

4. Average time period (minutes):

N/A 1.44E+03 N/A N/A 1.44E+03 5. Minimum time period (minutes):

N/A 1.44E+03 N/A N/A 1.44E+03 6. Average stream flow during periods of release of 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 2014 Est.RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2014 2014 2014 2014 2014 Error A. FISSION AND ACTIVATION GASES Total Release: Ci NDA NDA NDA 1.68E+00 1.68E+00 Average Release Rate: ViCi/sec N/A N/A N/A j 2.13E-01 5.32E-02 _+/-22%Percent of Effluent Control Limit* .....B. IODINE-131 Total Iodine-131 Release: Ci 3.91 E-05 7.04E-05 9.16E-05 5.25E-05 2.54E-04 Average Release Rate: latCi/sec 4.96E-06 8.93E-06 1.16E-05 6.66E-06 8.04E-06 +/-20%Percent of Effluent Control Limit* .....C. PARTICULATES WITH HALF-LIVES

> 8 DAYS Total Release: Ci 2.41E-05 5.27E-05 2.11E-04 1.79E-05 3.05E-04 Average Release Rate: ltCi/sec 3.05E-06 6.68E-06 2.67E-05 2.26E-06 9.68E-06 Percent of Effluent Control Limit* .NAND Gross Alpha Radioactivity:

Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 2.32E+01 2.38E+01 2.07E+01 2.23E+01 9.01E+01 Average Release Rate: pCi/sec 2.95E+00 3.02E+00 2.62E+00 2.83E+00 2.86E+00 _+/-20%Percent of Effluent Control Limit* .....E. CARBON-14 Total Release: Ci 2.14E+00 2.01 E+00 2.04E+00 2.15E+00 8.33E+00 Average Release Rate: pCi/sec 2.71 E-01 2.55E-01 2.59E-01 2.73E-01 2.64E-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 pCi/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 2014 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014 1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Kr-85 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-88 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133m O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 Xe-135m O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-138 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 Total for Period 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2. IODINES: Ci 1-131 2.92E-07 2.69E-06 O.OOE+00 0.OOE+00 2.98E-06 1-133 0.OOE+00 6.83E-06 1.97E-06 0.OOE+00 8.80E-06 Total for Period 2.92E-07 9.52E-06 1.97E-06 0.OOE+00 1.18E-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 O.OOE+00 O.OOE+00 0.OOE+00 Fe-59 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Co-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 Zn-65 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 Cs-1 34 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Cs-1 37 0.OOE+00 0.OOE+00 0.OOE+00 O.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.OOE+00 0.OOE+00 3.31 E-02 1.08E-01 4. TRITIUM: Ci H-3 1.23E-02 2.87E-02 3.40E-02 3.31E-02 i1.08E-01 5. CARBON-14:

Ci C-14 2.07E+00 1.95E+00 1.98E+00 2.09E+00 8.08E+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-1i1 pCi/cc Page 12 Table 2.2-B (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents

-Elevated Release January-December 2014 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014 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-137 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: 1E-04 pCi/cc lodines: 1 E-12 pCi/cc Particulates:

1 E-1 1 pCi/cc Page 13 Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents

-Ground-Level Release January-December 2014 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014 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.OOE+00 0.00E+00 0.OOE+00 Kr-85m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-87 O.00E+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 Kr-88 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 Xe-131m 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133 0.00E+00 0.OOE+00 0.OOE+00 8.31E-01 8.31E-01 Xe-133m 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135 0.OOE+00 0.OOE+00 0.OOE+00 8.48E-01 8.48E-01 Xe-135m O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-138 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Total for period 0.OOE+00 0.00E+00 0.OOE+00 1.68E+00 1.68E+00 2. IODINES: Ci 1-131 3.88E-05 6.78E-05 9.16E-05 5.25E-05 2.51E-04 1-133 1.34E-04 2.16E-04 3.23E-04 2.51 E-04 9.24E-04 Total for period 1.73E-04 2.84E-04 4.15E-04 3.03E-04 1.17E-03 3. PARTICULATES WITH HALF-LIVES

> 8 DAYS: Ci Cr-51 0.OOE+00 9.87E-06 0.00E+00 9.96E-06 1.98E-05 Mn-54 0.OOE+00 3.26E-05 5.29E-06 O.OOE+00 3.79E-05 Fe-59 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 4.25E-06 9.34E-06 0.OOE+00 0.OOE+00 1.36E-05 Zn-65 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 Sr-89 0.OOE+00 8.70E-07 1.32E-05 2.72E-06 1.68E-05 Sr-90 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ru-103 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Cs-134 0.OOE+00 0.OOE+00 0.OOE+00 O.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 1.98E-05 0.OOE+00 1.92E-04 5.17E-06 2.17E-04 Total for period 2.41 E-05 5.27E-05 2.11 E-04 1.79E-05 3.05E-04 4. TRITIUM: Ci H-3 2.32E+01 2.38E+01 2.06E+01 2.23E+01 9.OOE+01 5. CARBON-14:

Ci C-14 6.41E-02 6.02E-02 6.12E-02 6.52E-02 2.51E-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: 1E-04 pCi/cc lodines: 1 E-12 piCi/cc Particulates:

1E-1i1 pCi/cc Page 14 Table 2.2-C (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents

-Ground-Level Release January-December 2014 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar2014 Apr-Jun2014 Jul-Sep2014 Oct-Dec2014 Jan-Dec2014

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- 137 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-1 03 N/A N/A N/A N/A N/A Cs-1 34 N/A N/A N/A N/A N/A Cs-1 37 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: I E-12 iCi/cc Particulates:

1E-1i1 pCi/cc Page 15 Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents

-Summation of All Releases January-December 2014 Est.RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2014 2014 2014 2014 2014 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including N/A 7.50E-06 N/A N/A 7.50E-06 tritium, gases, alpha): Ci Average Diluted Concentration N/A 4.89E-14 N/A N/A 1.22E-14 +/-12%During Period: pCi/mL Percent of Effluent Concentraton Efflt* N/A 1.47E-06%

N/A N/A 3.68E-07%Concentration Limit*B. TRITIUM Total Release: Ci N/A 3.87E-03 N/A N/A 3.87E-03 Average Diluted Concentration N/A 2.52E-11 N/A N/A 6.30E-12 During Period: pCi/mL +/-9.4%Percent of EffluentI Concentrton Elimt* N/A 2.52E-06%

N/A N/A 6.30E-07%Concentration Limit*C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A NDA N/A N/A NDA Average Diluted Concentration N/A NDA N/A N/A NDA Durinn Period: gCi/mL +/-16%Concentron limit N/A O.OOE+00%

N/A N/A O.OOE+00%Concentration Limit*D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A NDA N/A N/A NDA +/-34%E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters N/A 2.28E+04 N/A N/A 2.28E+04 +/- 5.7%F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 I1.53E+11 I1.55E+11 1.55E+11 6.14E+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 gCi/mL.4. LLD for liquid gross alpha activity listed as NDA is 1E-07 pCi/mL.Page 16 Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2014 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014 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-1 34 N/A N/A N/A N/A N/A Cs-1 37 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-1 33 N/A N/A N/A N/A N/A Xe-1 35 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 pCi/mL lodines: 1E-06 pCi/mL Noble Gases: 1E-05 pCi/mL All Others: 5E-07 pCi/mL Page 17 Table 2.3-B (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2014 BATCH MODE RELEASES Nuclide Released Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014 1. FISSION AND ACTIVATION PRODUCTS:

Ci Na-24 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cr-51 N/A O.00E+00 N/A N/A 0.00E+00 Mn-54 N/A 2.21 E-06 N/A N/A 2.21 E-06 Fe-55 N/A 0.00E+00 N/A N/A 0.00E+00 Fe-59 N/A 0.OOE+00 N/A N/A 0.00E+00 Co-58 N/A 0.OOE+00 N/A N/A 0.OOE+00 Co-60 N/A 4.64E-06 N/A N/A 4.64E-06 Zn-65 N/A 0.00E+00 N/A N/A 0.OOE+00 Zn-69m N/A O.OOE+00 N/A N/A 0.OOE+00 Sr-89 N/A 0.OOE+00 N/A N/A 0.OOE+00 Sr-90 N/A 0.OOE+00 N/A N/A 0.OOE+00 Zr/Nb-95 N/A 0.OOE+00 N/A N/A 0.OOE+00 Mo/Tc-99 N/A 0.OOE+00 N/A N/A 0.00E+00 Ag-11Om N/A 0.OOE+00 N/A N/A 0.OOE+00 Sb-124 N/A 0.OOE+00 N/A N/A 0.OOE+00 1-131 N/A 0.00E+00 N/A N/A 0.OOE+00 1-133 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 34 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cs-1 37 N/A 6.39E-07 N/A N/A 6.39E-07 Ba/La-1 40 N/A 0.OOE+00 N/A N/A 0.OOE+00 Ce-141 N/A 0.00E+00 N/A N/A 0.OOE+00 Ce-144 N/A 0.OOE+00 N/A N/A 0.OOE+00 Total for period N/A 7.50E-06 N/A N/A 7.50E-06 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 N/A NDA N/A N/A NDA Xe-135 N/A NDA N/A N/A NDA Total for period N/A NDA 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 pCi/mL lodines: 1 E-06 ptCi/mL Noble Gases: 1E-05 pCi/mL All Others: 5E-07 pCi/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, 44%* 33-ft Wind Direction (from): South-southwest, 16%* 33-ft Wind Speed: 3.5-7.5 mph, 55%* 220-ft Wind Direction (from): South-southwest, 15%* 220-ft Wind Speed: 12.5-18.5 mph, 38%Joint data recovery for both the 33-ft level and 220-ft level of the tower was 100%, which met the 90% annual data recovery goal specified by the NRC.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 2014 resulted in a maximum total body dose of 0.000069 mrem. The maximum skin dose was 0.00038 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 0.000054 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building), while the maximum skin dose was 0.00026 mrem (nearest residence, 0.80 kilometers ESE from the Reactor Building).

Page 20 Table 4.1 Maximum Doses From Noble Gas Releases During 2 0 1 4 (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.OOE+00 0.OOE+00 0.OOE+00 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Apr-Jun (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Jul-Sep (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Oct-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE)Jan-Dec 1.07E-04 4.75E-04 6.91 E-05 3.77E-04 (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 2014 resulted in a maximum total body dose of 0.045 mrem (child age class at nearest garden location, 0.84 kilometers SE from the Reactor Building), while the maximum organ dose was 0.088 mrem (child bone at nearest garden location, 0.84 kilometers SE from the Reactor Building).

Carbon-14 contributed 0.017 mrem (39%) of the 0.045 mrem child total body dose, and 0.087 mrem (99%) of the 0.088 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 2014 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway2:

DI DI DIV 3 DIVCG 3 DIVCM 3 DIVM 3 Age Class: Adult Bone 2.15E-04 1.45E-04 5.77E-03 2.34E-03 2.05E-03 3.55E-03 GI-LLI 2.72E-03 1.78E-03 5.75E-03 8.53E-04 6.40E-04 9.89E-04 Kidney 2.72E-03 1.78E-03 5.75E-03 8.53E-04 6.40E-04 9.88E-04 Liver 2.72E-03 1.78E-03 5.75E-03 8.52E-04 6.40E-04 9.88E-04 Lung 2.72E-03 1.78E-03 5.75E-03 8.52E-04 6.40E-04 9.88E-04 Thyroid 2.83E-03 1.85E-03 6.01E-03 9.29E-04 6.81E-04 1.01E-03 T.Body 2.72E-03 1.78E-03 5.75E-03 8.52E-04 6.40E-04 9.88E-04 Age Class: Teen Bone 3.08E-04 2.07E-04 9.34E-03 3.93E-03 3.09E-03 5.01 E-03 GI-LLI 2.76E-03 1.81E-03 6.95E-03 1.23E-03 8.71E-04 1.30E-03 Kidney 2.76E-03 1.81 E-03 6.95E-03 1.23E-03 8.71E-04 1.30E-03 Liver 2.76E-03 1.81E-03 6.95E-03 1.23E-03 8.71E-04 1.30E-03 Lung 2.77E-03 1.81 E-03 6.95E-03 1.23E-03 8.71E-04 1.30E-03 Thyroid 2.90E-03 1.90E-03 7.19E-03 1.34E-03 9.30E-04 1.31 E-03 T. Body 2.76E-03 1.81 E-03 6.95E-03 1.23E-03 8.71E-04 1.30E-03 Age Class: Child Bone 4.25E-04 2.86E-04 2.23E-02 9.47E-03 7.26E-03 1.16E-02 GI-LLI 2.47E-03 1.61 E-03 1.15E-02 2.53E-03 1.81 E-03 2.72E-03 Kidney 2.47E-03 1.61 E-03 1.15E-02 2.53E-03 1.81E-03 2.72E-03 Liver 2.47E-03 1.61E-03 1.15E-02 2.53E-03 1.81E-03 2.72E-03 Lung 2.47E-03 1.62E-03 1.15E-02 2.53E-03 1.81E-03 2.72E-03 Thyroid 2.64E-03 1.72E-03 1.18E-02 2.75E-03 1.92E-03 2.74E-03 T.Body 2.47E-03 1.61E-03 1.15E-02 2.53E-03 1.81E-03 2.72E-03 Age Class: Infant Bone 3.13E-04 2.11E-04 1.76E-04 5.94E-03 4.13E-03 7.92E-05 GI-LLI 1.44E-03 9.40E-04 6.99E-04 1.59E-03 1.04E-03 5.24E-05 Kidney 1.44E-03 9.40E-04 7.OOE-04 1.59E-03 1.04E-03 5.24E-05 Liver 1.44E-03 9.40E-04 7.OOE-04 1.59E-03 1.04E-03 5.24E-05 Lung 1.44E-03 9.43E-04 7.02E-04 1.59E-03 1.04E-03 5.25E-05 Thyroid 1 .59E-03 1.04E-03 7.74E-04 2.07E-03 1.29E-03 5.60E-05 T.Body t_1 .44E-03 9.40E-04 6.99E-04 1.59E-03 1.04E-03 5.24E-05 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 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 2014 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

ESE ESE SE WSW W S Distance 1: 0.33 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 2.02E-04 1.36E-04 5.43E-03 2.19E-03 1.92E-03 3.34E-03 GI-LLI 2.78E-03 1.82E-03 5.81 E-03 8.34E-04 6.21 E-04 9.53E-04 Kidney 2.78E-03 1.82E-03 5.79E-03 8.34E-04 6.21 E-04 9.52E-04 Liver 2.78E-03 1.82E-03 5.79E-03 8.34E-04 6.21 E-04 9.52E-04 Lung 2.80E-03 1.83E-03 5.80E-03 8.34E-04 6.21 E-04 9.52E-04 Thyroid 2.97E-03 1.94E-03 6.25E-03 9.69E-04 6.93E-04 9.82E-04 T.Body 2.78E-03 1.82E-03 5.79E-03 8.34E-04 6.20E-04 9.52E-04 Age Class: Teen Bone 2.89E-04 1.95E-04 8.78E-03 3.69E-03 2.90E-03 4.71E-03 GI-LLI 2.82E-03 1.85E-03 6.97E-03 1.19E-03 8.40E-04 1.24E-03 Kidney 2.82E-03 1.85E-03 6.96E-03 1.19E-03 8.40E-04 1.24E-03 Liver 2.82E-03 1.85E-03 6.96E-03 1.19E-03 8.40E-04 1.24E-03 Lung 2.84E-03 1.86E-03 6.96E-03 1.19E-03 8.40E-04 1.24E-03 Thyroid 3.06E-03 2.OOE-03 7.38E-03 1.39E-03 9.45E-04 1.27E-03 T.Body 2.82E-03 1.85E-03 6.96E-03 1.19E-03 8.40E-04 1.24E-03 Age Class: Child Bone 3.99E-04 2.69E-04 2.1OE-02 8.90E-03 6.82E-03 1.09E-02 GI-LLI 2.52E-03 1.65E-03 1.14E-02 2.43E-03 1.73E-03 2.59E-03 Kidney 2.52E-03 1.65E-03 1.14E-02 2.43E-03 1.73E-03 2.59E-03 Liver 2.52E-03 1.65E-03 1.14E-02 2.43E-03 1.73E-03 2.59E-03 Lung 2.54E-03 1.66E-03 1.14E-02 2.43E-03 1.73E-03 2.59E-03 Thyroid 2.81E-03 1.83E-03 1.20E-02 2.81E-03 1.93E-03 2.63E-03 T.Body 2.52E-03 1.65E-03 1.14E-02 2.43E-03 1.73E-03 2.59E-03 Age Class: Infant Bone 2.94E-04 1.98E-04 1.65E-04 5.58E-03 3.88E-03 7.44E-05 GI-LLI 1.46E-03 9.59E-04 7.13E-04 1.52E-03 9.87E-04 5.23E-05 Kidney 1.47E-03 9.60E-04 7.14E-04 1.52E-03 9.89E-04 5.23E-05 Liver 1.47E-03 9.60E-04 7.14E-04 1.52E-03 9.89E-04 5.23E-05 Lung 1.48E-03 9.66E-04 7.19E-04 1.52E-03 9.87E-04 5.26E-05 Thyroid 1.73E-03 1.13E-03 8.39E-04 2.38E-03 1.44E-03 5.85E-05 T.Body 1.46E-03 9.59E-04 7.14E-04 1.52E-03 9.88E-04 5.23E-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 N Page 24 Table 4.2-C Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Jul-Sep 2014 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway 2: DI DI DIV DIVCG DIVCM DIVM Age Class: Adult Bone 2.07E-04 1.39E-04 5.56E-03 2.23E-03 1.96E-03 3.40E-03 GI-LLI 2.43E-03 1.59E-03 5.20E-03 7.89E-04 5.96E-04 9.27E-04 Kidney 2.42E-03 1.58E-03 5.18E-03 7.89E-04 5.96E-04 9.25E-04 Liver 2.42E-03 1.58E-03 5.18E-03 7.89E-04 5.96E-04 9.25E-04 Lung 2.44E-03 1.60E-03 5.19E-03 7.89E-04 5.96E-04 9.26E-04 Thyroid 2.68E-03 1.75E-03 5.81E-03 9.69E-04 6.92E-04 9.65E-04 T.Body 2.42E-03 1.58E-03 5.18E-03 7.88E-04 5.96E-04 9.25E-04 Age Class: Teen Bone 2.96E-04 1.99E-04 8.98E-03 3.76E-03 2.95E-03 4.79E-03 GI-LLI 2.46E-03 1.61E-03 6.31E-03 1.14E-03 8.16E-04 1.22E-03 Kidney 2.46E-03 1.61 E-03 6.29E-03 1.15E-03 8.16E-04 1.22E-03 Liver 2.45E-03 1.61E-03 6.29E-03 1.14E-03 8.15E-04 1.22E-03 Lung 2.49E-03 1.63E-03 6.31E-03 1.14E-03 8.16E-04 1.22E-03 Thyroid 2.79E-03 1.82E-03 6.87E-03 1.41E-03 9.54E-04 1.25E-03 T.Body 2.45E-03 1.61E-03 6.29E-03 1.14E-03 8.15E-04 1.22E-03 Age Class: Child Bone 4.09E-04 2.75E-04 2.15E-02 9.06E-03 6.94E-03 1.11E-02 GI-LLI 2.20E-03 1.44E-03 1.05E-02 2.37E-03 1.71 E-03 2.57E-03 Kidney 2.20E-03 1.44E-03 1.05E-02 2.38E-03 1.71 E-03 2.57E-03 Liver 2.20E-03 1.44E-03 1.05E-02 2.38E-03 1.71 E-03 2.57E-03 Lung 2.23E-03 1.46E-03 1.05E-02 2.37E-03 1.71 E-03 2.57E-03 Thyroid 2.60E-03 1.70E-03 1.13E-02 2.88E-03 1.97E-03 2.62E-03 T.Body 2.19E-03 1.44E-03 1.05E-02 2.37E-03 1.71E-03 2.57E-03 Age Class: Infant Bone 3.01E-04 2.03E-04 1.69E-04 5.68E-03 3.95E-03 7.57E-05 GI-LLI 1.28E-03 8.38E-04 6.24E-04 1.49E-03 9.80E-04 4.76E-05 Kidney 1.28E-03 8.38E-04 6.24E-04 1.50E-03 9.82E-04 4.76E-05 Liver 1.28E-03 8.38E-04 6.24E-04 1.50E-03 9.82E-04 4.76E-05 Lung 1.31 E-03 8.56E-04 6.37E-04 1.49E-03 9.80E-04 4.83E-05 Thyroid 1.65E-03 1.08E-03 8.01 E-04 2.64E-03 1.57E-03 5.63E-05 T.Body 1.28E-03 8.37E-04 6.23E-04 1.49E-03 9.81E-04 4.76E-05 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 C = Cow Milk G = Goat Milk M = Meat Page 25 Table 4.2-D Maximum Individual Organ Dose at Receptor Location -- mrem From Gaseous Release Period: Oct-Dec 2014 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 0.84 km 3.97 km 5.77 km 3.80 km Pathway: DI DI DIV3 DIVCG 3 DIVCM3 DIVM3 Age Class: Adult Bone 2.19E-04 1.47E-04 5.87E-03 2.36E-03 2.06E-03 3.58E-03 GI-LLI 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Kidney 2.61E-03 1.71E-03 5.59E-03 8.41E-04 6.34E-04 9.83E-04 Liver 2.61E-03 1.71 E-03 5.58E-03 8.41E-04 6.34E-04 9.83E-04 Lung 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Thyroid 2.79E-03 1.82E-03 5.96E-03 9.46E-04 6.90E-04 1.01E-03 T.Body 2.61 E-03 1.71 E-03 5.58E-03 8.41 E-04 6.34E-04 9.83E-04 Age Class: Teen Bone 3.13E-04 2.1OE-04 9.49E-03 3.96E-03 3.11E-03 5.05E-03 GI-LLI 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Kidney 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.67E-04 1.29E-03 Liver 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Lung 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Thyroid 2.88E-03 1.88E-03 7.12E-03 1.37E-03 9.47E-04 1.31E-03 T.Body 2.65E-03 1.74E-03 6.77E-03 1.22E-03 8.66E-04 1.29E-03 Age Class: Child Bone 4.32E-04 2.90E-04 2.27E-02 9.56E-03 7.32E-03 1.17E-02 GI-LLI 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Kidney 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81 E-03 2.72E-03 Liver 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Lung 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Thyroid 2.64E-03 1.73E-03 1.18E-02 2.82E-03 1.96E-03 2.75E-03 T.Body 2.37E-03 1.55E-03 1.13E-02 2.52E-03 1.81E-03 2.72E-03 Age Class: Infant Bone 3.18E-04 2.14E-04 1.79E-04 5.99E-03 4.17E-03 7.99E-05 GI-LLI 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Kidney 1.38E-03 9.06E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Liver 1.38E-03 9.05E-04 6.74E-04 1.59E-03 1.04E-03 5.11E-05 Lung 1.38E-03 9.06E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 Thyroid 1.63E-03 1.06E-03 7.92E-04 2.25E-03 1.38E-03 5.69E-05 T.Body 1.38E-03 9.05E-04 6.74E-04 1.58E-03 1.04E-03 5.11E-05 1 2 3 Distances are measured with respect to the reactor building vent.Pathway designations are as follows: D = Deposition (Ground Plane) I = Inhalation C = Cow Milk G = Goat Milk K= Vegetable Garden 1 = 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 2014 Receptor:

Bound Resident Garden Cow/Goat Cow/Meat Meat Direction:

ESE ESE SE WSW W S Distance 1: 0.33 km 0.80 km 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 8.42E-04 5.66E-04 2.26E-02 9.12E-03 7.99E-03 1.39E-02 GI-LLI 1.05E-02 6.90E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Kidney 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Liver 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Lung 1.06E-02 6.92E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Thyroid 1.13E-02 7.36E-03 2.40E-02 3.81E-03 2.76E-03 3.96E-03 T.Body 1.05E-02 6.89E-03 2.23E-02 3.32E-03 2.49E-03 3.85E-03 Age Class: Teen Bone 1.21 E-03 8.11E-04 3.66E-02 1.53E-02 1.21 E-02 1.96E-02 GI-LLI 1.07E-02 7.00E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Kidney 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Liver 1.07E-02 7.OOE-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Lung 1.08E-02 7.04E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Thyroid 1.16E-02 7.60E-03 2.86E-02 5.51E-03 3.78E-03 5.15E-03 T.Body 1.07E-02 6.99E-03 2.70E-02 4.78E-03 3.39E-03 5.05E-03 Age Class: Child Bone 1.66E-03 1.12E-03 8.75E-02 3.70E-02 2.83E-02 4.52E-02 GI-LLI 9.56E-03 6.26E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Kidney 9.56E-03 6.26E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Liver 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Lung 9.61 E-03 6.29E-03 4.46E-02 9.85E-03 7.06E-03 1.06E-02 Thyroid 1.07E-02 6.98E-03 4.69E-02 1.13E-02 7.79E-03 1.07E-02 T.Body 9.55E-03 6.25E-03 4.46E-02 9.86E-03 7.06E-03 1.06E-02 Age Class: Infant Bone 1.23E-03 8.25E-04 6.89E-04 2.32E-02 1.61 E-02 3.09E-04 GI-LLI 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-04 Kidney 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Liver 5.56E-03 3.64E-03 2.71E-03 6.19E-03 4.05E-03 2.03E-04 Lung 5.61E-03 3.67E-03 2.73E-03 6.18E-03 4.04E-03 2.04E-04 Thyroid 6.60E-03 4.31 E-03 3.20E-03 9.35E-03 5.68E-03 2.28E-04 T.Body 5.56E-03 3.64E-03 2.71E-03 6.18E-03 4.04E-03 2.03E-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 quarters 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 0.00000029 mrem. The maximum organ dose (adult age class, GI-LLI) was 0.00000087 mrem.Page 28 Table 4.3-A Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jan-Mar 2014 Age Class Organ Dose -mrem *Organ Adult Teen I 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 0.OOE+00 Liver 0.OOE+00 O.OOE+00 0.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 0.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 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 2014 Age Class Organ Dose -mrem Organ Adult Teen Child Bone 5.28E-08 2.14E-07 6.49E-08 GI-LLI 8.67E-07 7.17E-07 2.39E-07 Kidney 6.18E-08 2.21E-07 6.15E-08 Liver 1.49E-07 3.03E-07 1.34E-07 Lung 4.15E-08 2.02E-07 4.59E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1 .44E-07 Page 30 Table 4.3-C Maximum Individual Organ Doses -- mrem From Liquid Release Period: Jul-Sep 2014 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 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone O.OOE+00 O.OOE+00 0.OOE+00 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 Kidney O.OOE+00 O.OOE+00 O.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 Lung 0.OOE+00 0.OOE+00 O.OOE+00 Thyroid 0.OOE+00 0.OOE+00 0.OOE+00 T.Body 0.OOE+00 0.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 2014 Age Class Organ Dose -mrem *Organ Adult Teen Child Bone 5.27E-08 2.14E-07 6.47E-08 GI-LLI 8.66E-07 7.16E-07 2.39E-07 Kidney 6.17E-08 2.21E-07 6.14E-08 Liver 1.49E-07 3.02E-07 1.34E-07 Lung 4.14E-08 2.01 E-07 4.58E-08 Thyroid 3.87E-08 1.98E-07 4.32E-08 T.Body 1.43E-07 2.89E-07 1.44E-07* 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 173 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 72.6 +/- 23.1 mR/yr to 62.2 + 8.1 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.0 +/- 7.7 mR/yr, and is indicative of natural background radiation.

Although the annual exposure at TLD location OA was 113 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 0.52 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 65.8 +/- 8.6 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.0 +/- 7.7 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 though 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 2014 is estimated as being about 1.3 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 2014. 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 0.0022 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 40CFR1 90.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 1.3 mrem/year.

Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2014 Average Exposure +/- Standard Deviation:

mR/ eriod Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.9 +/- 5.5 14.3 +/- 2.1 13.9 +/- 1.3 14.6 +/- 1.6 Apr-Jun 18.0 +/- 5.4 14.2 +/- 2.0 13.7 +/- 1.9 14.3 +/- 2.2 Jul-Sep 19.0 +/- 6.7 15.1 +/- 2.0 15.0 +/- 1.6 16.0 +/- 2.3 Oct-Dec 17.6 +/- 5.4 14.4 +/- 2.4 13.6 +/- 1.8 15.2 +/- 1.6 Jan-Dec 72.6 +/- 23.1** 58.1 +/- 8.4 56.1 +/- 6.7 60.0 +/- 7.7 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 62.2 +/- 8.1 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 2014 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 2014 A. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1.a Limit: 500 mrem/yr Total Body Dose Period Jan-Dec Value -mrem/yr 6.91 E-05 Fraction of Limit 1.38E-05%.... .. ..... .....................................................

...... ..........


B. Instantaneous Dose Rate Limit -Noble Gases PNPS ODCM Control 3.3.1 .a Limit: 3000 mrem/yr Skin Dose Period Jan-Dec Value -mrem/yr 3.77E-04 Fraction of Limit 1.26E-05%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 8.75E-02 5.83E-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 0.OOE+00 0.OOE+00%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 1.07E-04 2.13E-03%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/yr Fraction of Limit Jan-Dec 1.07E-04 1.07E-03%Page 38 Table 6.1 (continued)

Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2014 F. Quarterly Dose Objective

-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective:

10 mrad Beta Air Dose Period Value -mrad Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 0.OOE+00 0.OOE+00%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 4.75E-04 4.75E-03%G. Annual Dose Objective

-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective:

20 mrad Beta Air Dose Period Value -mrad/vr Fraction of Limit Jan-Dec 4.75E-04 2.37E-03%H. Quarterly Dose Objective

-Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective:

7.5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar 2.23E-02 2.98E-01%Apr-Jun 2.1OE-02 2.80E-01%Jul-Sep 2.15E-02 2.86E-01%Oct-Dec 2.27E-02 3.02E-01%Annual Dose Objective

-Particulates, lodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective:

15 mrem Organ Dose Period Value -mrem/yr Fraction of Limit Jan-Dec 8.75E-02 5.83E-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 2014 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 10CFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -PCi/mL O.OOE+00 4.89E-14 O.OOE+00 O.OOE+00 1.22E-14 Fraction of Limit 0.OOE+00%1.47E-06%0.OOE+00%0.OOE+00%3.68E-07%B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.OE-03 piCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LICi/mL 0.OOE+00 2.52E-1 1 0.OOE+00 0.OOE+00 6.30E- 12 Fraction of Limit 0.OOE+00%2.52E-06%0.OOE+00%0.OOE+00%6.30E-07%C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.OE-04 jiCi/mL Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -LtCi/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%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 2014 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective:

1.5 mrem Total Body Dose Period Value -mrem Fraction of Limit Jan-Mar 0.OOE+00 0.OOE+00%Apr-Jun 2.89E-07 1.93E-05%Jul-Sep 0.OOE+00 0.OOE+00%Oct-Dec 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 Value -mrem Fraction of Limit Jan-Dec 2.89E-07 9.62E-06%F. Quarterly Organ Dose Objective PNPS ODCM Control 3.2.2.a Objective:

5 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Mar O.OOE+00 0.OOE+00%Apr-Jun 8.67E-07 1.73E-05%Jul-Sep O.OOE+00 0.OOE+00%Oct-Dec 0.OOE+00 0.OOE+00%G. Annual Organ Dose Objective PNPS ODCM Control 3.2.2.b Objective:

10 mrem Organ Dose Period Value -mrem Fraction of Limit Jan-Dec 8.66E-07 8.66E-06%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 67.4 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 680 Curies were shipped from PNPS for processing and disposal.

Dry activated wastes and contaminated equipment shipped during the period totaled 543 cubic meters and contained 1.66 Cures of radioactivity.

There were no shipments of irradiated components during the reporting period. Other wastes (contaminated oil and water) totaled 19.2 cubic meters and contained 0.016 Curies of radioactivity.

There were no shipments of irradiated fuel 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 23 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 5 shipments to Energy Solutions' Gallaher Road Facility in Kingston, TN; and 4 shipments to Energy Solutions Erwin Resin Solutions' Facility in Erwin, TN.Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2014 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 2014 Typeof waste Volume -m' Curies Total Error a. Spent resins, filters, filter sludges, 6.74E+01 6.80 E+02 +/- 25%evaporator bottoms, etc.b. Dry activated waste, contaminated 543 E+02 1.66 E+00 +/- 25%equipment, etc.c. Irradiated components, control rods, etc. 0.OOE+00 0.00E+00 N/A d. Other (describe):

1.92E+01 1.65E-02 N/A 2. Estimate of major nuclide composition by type of waste'Type of waste Radionuclide

[ Abundance Total Error a. Spent resins, filters, filter sludge's, Mn-54 18.58% +/- 25%evaporator bottoms, etc. Fe-55 39.31% +/- 25%Co-58 1.03% +/- 25%Co-60 30.00% +/- 25%Zn-65 7.83% +/- 25%b. Dry activated waste, contaminated H-3 9.76% +/- 25%equipment, etc. C-14 1.34% +/- 25%Mn-54 2.76% +/- 25%Fe-55 60.24% +/- 25%Co-60 18.11% +/- 25%Ni-63 1.23% +/- 25%Zn-65 3.97% +/- 25%Cs-137 1.08% +/- 25%c. Irradiated components, control rods, etc. I N/A N/A N/A d. Other (describe):

Contaminated oil and water Mn-54 5.13% +/- 25%Fe-55 69.86% +/- 25%Co-60 17.17% +/- 25%Ni-63 1.47% +/- 25%Zn-65 4.15% +/- 25%Cs-137 1.23% +/- 25%'"Major" is defined as any radionuclide comprising

>1% of the total activity in the waste category.3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2 Tractor-trailer Energy Solutions, Bear Creek Facility 2 (Hittman Transport)

Oak Ridge, TN 5 Tractor-trailer Energy Solutions, Gallaher Road Facility (Hittman Transport)

Kingston, TN 4 Tractor-trailer Energy Solutions, Erwin Resin Solutions, 2 (Hittman Transport)

Erwin, TN 2 This processor provides volume reduction services for dry compressible waste, contaminated equipment, etc Remaining radioactive wastes will be shipped to 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 2014. Information regarding revisions to the ODCM can be found attached as Appendix D of this report.Page 45

9.0 PROCESS

CONTROL PROGRAM REVISIONS The following list summarizes changes made during 2014 to various procedures related to the Process Control Program (PCP): EN-RW-1 02, "Radioactive Shipping Procedure", Rev. 11:* Step 5.1[9](e):

inserted the word "Radioactive" and corrected grammatical error (changed"affects" to "effects")

  • Step 5.1[11]: revised step to correct Type B Package types* Step 5.1[12]: added step for Grand Gulf shipment of waste for free release* Steps 5.2[14] and 5.2[14](b):

corrected procedure reference* Step 5.2[15]: flow charts are redrawn (no content change) in Microsoft Visio format to enhance editing capability

  • Step 5.2[18]: corrected regulatory reference* Step 6.0[5]: corrected procedure reference* Section 8.0: updated site-commitments for Grand Gulf, W3 and RBS per Commitment Review response from GGNS and RBS* Attachment 9.1: added field for document package completion
  • Attachment 9.1: added field for disposition of Emergency Response information
  • Attachment

9.1 expanded

parenthetical in Waste Profile Form to include other companies and deleted empty rows.* Attachment 9.9 and 9.14: field for recording shipment number is reworded so as to be consistent with other attachments EN-RW-104, "Scaling Factors", Rev.10:* This is a complete rewrite of the procedure in order to bring the format into compliance with EN-AD-101-01 and to add instructions for using the new version (version 9.0) of RADMAN software.

No change bars are used.EN-RW-105, "Process Control Program", Rev.4:* Editorial revision to address the issue identified in CR-HQN-2013-00858, CA-02 (Develop a draft procedure that includes instructions for vendors processing waste still owned by Entergy to comply with the PCP program.)* Reworded Step 5.1[1](b) to improve clarity: inserted text "processed on-site OR off-site by vendors" EN-RW-1 06, "Integrated Transportation Security Plan", Rev. 3: " Total rewrite in order to accomplish the following:

o Bring the procedure into compliance with EN-AD-101-01 o Incorporate changes required by recent revision of 10CFR37 o Correct internal section references" The primary change involves replacing section 5.6 for Quantities of Concern in Rev. 2 with a new section 5.7 for Category 1 and Category 2 Quantities in Rev. 3 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 10, May 2009.3. 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 2014 Class A Freq 0.070 mph N NN"El E ENE E ESE SE ISSE I S IsWsv v I wl W IvNvv 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 1 2 0 0 0 0 0 0 0 0 0 0 0 1 0 2 6 3.5-7.5 6 18 6 4 5 0 0 0 0 0 2 0 8 39 22 17 127 7.5-12.5 1 0 0 0 1 0 0 0 0 0 0 0 4 8 4 0 18 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 8 [201 6 4 6 0 0 0 0 I0 2 0 112 48 26 19 151 Class B Fre 0.023 mph I NNEI NE ENE E ESE I SE SSE I S IjsSWv SW Iwsw W IWNWv NW IINNW[ 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 0 0 0 0 0 1 1 0 0 3 3.5-7.5 2 4 3 3 1 0 0 0 0 0 1 0 7 2 2 2 27 7.5-12.5 1 2 1 1 0 0 0 1 1 0 0 0 4 5 1 3 20 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, 3 [7 4 1 0 0 1 1 0 1 1 0 112 1 8 3 T-5 50 Class C Frec 0.040 mphN. I NNE E INENEI E ESEI SE ISSE S I SSW I SVV IWsv V IWN0v0 0 I0NNW 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 0 0 0 0 0 0 0 0 0 1 2 1 8 3.5-7.5 1 4 0 2 0 0 0 1 1 0 1 5 13 8 1 4 41 7.5-12.5 4 5 3 3 0 0 0 0 3 3 3 3 3 2 1 3 36 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 I7 10 4 5 00 0 0 1 4 1 4 I 4 I8 I 16 4 IT I 86 Class D Fr e 0.491 -- ENE IE I Nph NE ENE E ESE SE ISSE S ISSWI SW IWSWv W IVWNWV N 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 9 11 6 3 5 7 3 2 4 2 14 24 11 10 6 1 118 3.5-7.5 23 25 14 11 10 7 10 7 41 69 57 101 131 50 48 17 621 7.5-12.5 20 44 10 4 1 2 2 1 20 42 20 11 63 29 20 6 295 12.5-18.5 5 9 2 0 0 0 0 0 2 2 3 0 0 0 1 2 26 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 57 89 32 18 16 1 6 1 15 i 10 [ 67 j115 1 94 1136 1 205 1 89[ 75 1 261 1060 Page 49 Table A-1 (continued)

Jan-Mar 2014 Class E Frq 0.320 mph I N I NNE INE IENE E I ESE SE I SSE I S I SSW I SW S I WSN I W I WNW INW I NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 1 0 0 1 0 0 0 0 0 2 0.95-3.5 4 5 1 1 2 5 7 28 22 21 27 32 14 15 15 11 210 3.5-7.5 4 11 0 3 17 11 11 22 20 41 59 114 65 17 12 3 410 7.5-12.5 2 8 2 3 0 0 4 10 10 11 4 2 3 4 1 0 64 12.5-18.5 0 0 0 0 0 0 0 0 3 2 0 0 0 0 0 0 5 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 10 24 3 7 1191 16 1221 61 155 1 75 191 1 148 182 1 36 128 1 14 691 Class F Fr 0 0.050 mph N [ NNE I NEI ENE [ EI ESEISE]I SSE [I S ISW ]I W WS IW 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 0 0 0 2 1 7 5 5 14 22 8 5 0 0 69 3.5-7.5 0 0 0 0 0 0 3 6 3 5 17 5 0 0 0 0 39 7.5-12.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 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 0 0 0 0] 2 [ 4 113 9 I10 31I 27 8 5 0 I0I 109 Class G Fre 0.006 mh N jNNE NE ENE E jESE I SE SSE S ISSWISW WSWIWIWNWINW 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 1 0 2 2 1 2 1 0 0 0 9 3.5-7.5 0 0 0 0 0 0 1 0 0 0 3 0 0 0 0 0 4 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 0I 00 0 0 1o o o 0 2 01212 4 2 1110 I0 o l 13 Class All Fre 1.000 mph N [NNE]I NEIj ENE I El IESE I SEl1 I SS IS lS ISWIWSW I WIWNW1INW I NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 1 0 0 1 0 0 0 0 0 2 0.95-3.5 16 20 8 4 7 14 12 37 33 30 56 80 35 33 23 15 423 3.5-7.5 36 62 23 23 33 18 25 36 65 115 140 225 224 116 85 43 1269 7.5-12.5 28 59 16 11 2 2 6 12 35 56 27 16 77 48 27 12 434 12.5-18.5 5 9 2 0 0 0 0 0 5 5 3 0 0 0 1 2 32 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 5 150 1 49 1 38 1421 34 1431 861 1381 206 12271 321 1 13361 97 1 136 1 72 2160 Page 50 Table A-1 (continued)

Apr-Jun 2014 Class A Frec: 0.115 a N' I NNE I NE ENEI E IESEI SE SSE S IssE[ IsSWl svv W swl W IwNw 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 9 10 6 4 8 0 0 0 0 0 0 0 0 1 2 2 42 3.5-7.5 16 23 41 19 15 8 13 1 2 6 2 3 6 10 5 5 175 7.5-12.5 3 2 14 0 0 0 0 4 3 3 0 0 0 1 3 2 35 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 128 35 61 23 23 8 13 5 5 I9 2 I3 6 112 110 1 9 252 Class B Frec 0.037 mph I IN NE NE IENE E IESEI SE ISEISSI S Iw SW IWS 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 2 3 1 3 0 0 0 0 0 0 0 1 1 2 2 15 3.5-7.5 1 1 8 5 6 2 3 0 6 2 6 3 2 3 2 0 50 7.5-12.5 0 1 2 0 0 0 0 0 1 9 0 0 0 0 0 1 14 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 1 14 113 6 9 2 3 0 7 12 6 1 3 3 4 1 4 13I 80 Class C Fre: 0.053 mph I N NNE NE ENE E ESE SE SSE S ISSW SW IWSW W IWNWv 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 4 1 5 4 5 2 2 1 0 2 0 2 0 2 2 2 34 3.5-7.5 0 2 13 6 6 5 3 3 1 5 6 1 2 0 2 2 57 7.5-12.5 0 0 9 0 0 0 0 0 4 6 1 0 0 0 2 0 22 12.5-18.5 0 0 0 0 0 0 0 0 2 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 1 4 I3 I27 10 I 11 I7 I5 4 7 I13 7 I3 2 I2 6 I4I 115 Class D Fre0 0.365 aMh I N NNENEI ENEIE I ESE S SE ISIS ISSW ISW IWsI W IWINW INNWI TOTAL Calm-0.95 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 11 17 25 24 26 28 24 15 16 9 10 3 5 6 9 12 240 3.5-7.5 13 24 30 18 18 23 32 23 31 74 30 12 22 19 10 1 380 7.5-12.5 5 7 2 1 2 0 0 0 25 92 5 1 10 4 11 0 165 12.5-18.5 0 0 0 0 0 0 0 0 4 6 1 0 0 0 0 0 11 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 29 48 1 57 44 46 51 56 38 76 [181 46 16 37 29 30 13 797 Page 51 Table A-1 (continued)

Apr-Jun 2014 Class E F! 0.295 mph I NINNEI NE I ENEI E ESEI SE SSEI S ISSWvl SW IVsvv W IVNVI NW I NNWl TOTAL Calm-0.95 0 3 0 2 1 0 0 0 1 0 0 0 1 1 0 0 9 0.95-3.5 9 9 11 27 17 10 22 22 14 12 13 23 18 22 15 8 252 3.5-7.5 13 10 5 5 8 6 4 13 7 58 45 40 34 21 19 11 299 7.5-12.5 0 0 0 0 0 0 5 0 3 32 28 1 0 4 5 1 79 12.5-18.5 0 0 0 0 0 0 0 0 5 1 0 0 0 0 0 0 6 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 122 22 16 34 26 16 31 35 30 103 1 86 1 64 1 53 1 48 1 39 1 20 1 645 Class F F r: 0.099 mph IN NNEI NE ENE[ E ]E SEl SE SISS S I S IWSWI W INW NW INNW TOTAL Calm-0.95 0 0 0 0 1 1 0 0 0 0 0 1 0 0 0 0 3 0.95-3.5 0 2 1 3 0 3 3 4 1 3 17 41 15 3 4 2 102 3.5-7.5 0 2 7 2 1 0 1 1 1 6 43 20 1 1 3 2 91 7.5-12.5 0 0 0 0 0 0 0 0 0 7 13 1 0 0 0 0 21 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 4 8 15 2 414 1 5 12 1161731631161 4 14 217 Class G Fre: 0.036 mph N NNE I NE ENE I E ESE I SE ISSEI S ISSWvl SW IVSV VV IVNWl NW JNNWv 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 1 0 0 0 0 1 4 11 19 4 1 0 0 41 3.5-7.5 0 0 0 2 1 0 0 0 0 1 17 2 0 0 0 0 23 7.5-12.5 0 0 0 0 0 0 0 0 0 0 14 0 0 0 0 0 14 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 TOTAL 0 I 0 I3 I1 0I 0 I0 I 1 5 142121 4 I 1 0I0I 78 Class All Fre: 1.000 mph IN NNE NE ENE E ESE SE SSE S ISSWl SW Iwswl W IvNwl NW INNWl TOTAL Calm-0.95 0 3 0 3 2 1 0 0 1 0 0 1 1 1 0 0 13 0.95-3.5 33 41 51 64 59 43 51 42 32 30 51 88 43 36 34 28 726 3.5-7.5 43 62 104 57 55 44 56 41 48 152 149 81 67 54 41 21 1075 7.5-12.5 8 10 27 1 2 0 5 4 36 149 61 3 10 9 21 4 350 12.5-18.5 0 0 0 0 0 0 0 0 11 8 1 0 0 0 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 84 11 6 182I 125 I118 I 88 112 I87 128 I339 I262I 173 121I 100 J 96 [ 53 2184 Page 52 Table A-1 (continued)

Jul-Sep 2014 Class A Fr 0.074 mph I N INNEI NE ENE E IESEI SE ISSEI S SSW SW w W WIW NW I NWI 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 16 18 4 8 0 0 0 0 0 0 0 1 6 6 4 75 3.5-7.5 8 27 14 7 10 0 0 0 3 3 1 2 7 0 0 3 85 7.5-12.5 0 0 0 0 0 0 0 0 0 3 1 0 0 0 0 0 4 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 20 43 32 11 18 0 I0 I0 3 I 6 2 2 I 8 I I 6I 7I 164 Class 13 Freq 0.031 mph N NNE NE I ENE E ESE SE SSE S ISSWl SW Iwswl W IwNwl 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 8 5 8 1 2 0 0 0 0 0 0 0 0 1 2 7 34 3.5-7.5 0 3 1 1 1 0 2 3 5 6 0 3 2 0 0 0 27 7.5-12.5 0 0 0 0 0 0 0 0 0 6 1 0 0 0 0 0 7 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 8 I89 2 3 i0 2 3 5 112 1I 3 I2 1I 68 Class C Freq 0.055 raph I [ NNE N ENEI E EE SE SSE S I SSW IWsW l 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 3 6 9 3 4 1 2 0 0 1 1 1 2 4 4 8 49 3.5-7.5 0 2 0 3 2 1 0 1 10 23 5 2 3 1 2 1 56 7.5-12.5 0 0 0 0 0 0 0 0 1 14 1 0 0 0 0 0 16 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 3 I8 I I 6 2 2 1 11 38 7 3 5 1 5 6 9 121 Class D 0.377 Mph.I INNNE1 NE [ENEI E IEESEIS I SSEI S ISSW ISW IWSwl W IWNWI NW INNW[ 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 23 45 45 34 23 19 12 10 7 8 11 2 9 7 18 18 291 3.5-7.5 6 32 9 1 3 17 21 3 64 245 49 16 9 7 3 3 488 7.5-12.5 0 0 0 0 0 0 0 0 1 47 3 0 0 1 0 0 52 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 1 29 77 54 35 26 36 34 13 72 300 63 18 I 18 15] 21 1 I 832 Page 53 Table A-1 (continued)

Jul-Sep 2014 Class E Freq 0.294 mph IN INNEI NE IENEI EIESEI SE ISSE S ISSWl SW Iwsw_ W IWNWINW I Nvvl TOTAL Calm-0.95 0 0 0 0 0 1 2 3 3 4 3 3 3 0 0 5 27 0.95-3.5 17 22 19 20 21 15 19 23 40 27 14 35 27 18 17 13 347 3.5-7.5 4 3 0 0 0 5 1 3 15 119 62 29 10 2 5 1 259 7.5-12.5 0 0 0 0 0 0 0 0 0 12 5 0 0 0 0 0 17 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 21 25 19 1 20 1 21 21 22 29 58 1162 1 84 [ 67 1 40 2O[ 22 1 19 650 Class F Fre: 0.127 mph ININNE INE I ENE I E ESE SE SSE [S Isvl SSW IVsW v IW W WNW[ NW INNWI TOTAL Calm-0.95 0 0 1 0 0 0 0 1 1 1 3 1 0 1 1 0 10 0.95-3.5 1 0 0 4 1 2 1 4 22 40 42 46 13 1 2 1 180 3.5-7.5 0 0 0 0 0 0 0 0 1 21 67 1 0 0 0 0 90 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 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 1 0 1 4 1 2 1 5 24 62 1113 148 13 1 2 -1 1 281 Class G Frec 0.042 mph IN'INNE NEIENE EIESEI SE ISSEI S ISSWI SW IWSWI W IWNWI NW INNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 2 0.95-3.5 0 0 0 0 0 0 0 0 0 5 25 27 2 1 0 0 60 3.5-7.5 0 0 0 0 0 0 0 0 0 1 29 0 0 0 0 0 30 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 ' 1 0 0 0 0 0 0 0 6 154 2 7 1 3 I2 0 0 92 Class All Fre: 1.000 mph IN INNE I N IENEIEIE ESEI SSE IS I S I SSW ISW SWIV W IVNWIVlW INNWvI TOTAL Calm-0.95 0 0 1 0 0 1 3 4 4 5 6 4 4 2 1 5 40 0.95-3.5 64 94 99 66 59 37 34 37 69 81 93 111 54 38 49 51 1036 3.5-7.5 18 67 24 12 16 23 24 10 98 418 213 53 31 10 10 8 1035 7.5-12.5 0 0 0 0 0 0 0 0 2 82 12 0 0 1 0 0 97 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 I82 161 I124 78 75 I61 61 51 173 1 586 1 324 1 168 1 89 I51 60 1 64 1 2208 Page 54 Table A-1 (continued)

Oct-Dec 2014 Class A Freq: 0.026_L _ph I N I IE NE IENEI E ESE I SSEI S [SSW ISW IWSwl W IWNWl 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 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 1 4 3.5-7.5 4 3 4 2 0 0 0 0 0 0 0 3 6 8 7 5 42 7.5-12.5 0 3 1 0 1 2 0 1 0 0 0 0 2 0 1 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 17 16 121 1 2 0 11 0 01 0 3 1 181 [6 16 57 Class B Fre: 0.031 L.np I N INNNEI NE IENE I E IESE SE ISSE I S ISSW SW IWSW] W IWNW]NW W [NNW TTOTAL 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 1 0 0 0 0 0 0 1 0 0 0 0 3 3.5-7.5 1 9 1 1 1 2 0 0 1 1 3 3 11 4 5 2 45 7.5-12.5 1 6 7 1 2 2 0 0 0 2 0 0 0 0 0 0 21 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 12 115 19 2 14 10 0 1 13 13 14 1 11 4 15 12 69 Class C Freq 0.054 mph N NNE I NE ENE E ESE SE SSE I S I SW Iwswl W IwNwl 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 1 1 0 1 1 2 0 0 0 0 0 0 2 2 0 10 3.5-7.5 0 14 12 4 0 0 1 1 0 1 6 11 10 8 8 5 81 7.5-12.5 1 10 3 6 0 0 0 1 0 0 0 0 0 4 0 1 26 12.5-18.5 0 2 0 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 I [1 27 16 10 1 1 3 2 I0 1 1 6 1 11 I10 14 1 10 6 119 Class D Fre: 0.542 mph I N [NNEI NE IENEI E IESEI SE SSEI S I SSW WSWI W IWNwNWINNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0.95-3.5 12 9 9 11 8 4 18 10 16 9 4 11 9 7 11 7 155 3.5-7.5 27 71 37 21 27 9 20 22 51 93 58 82 139 90 63 12 822 7.5-12.5 6 41 10 6 5 8 0 0 11 51 24 3 11 18 8 2 204 12.5-18.5 0 0 0 2 0 0 0 3 1 8 0 0 0 0 0 0 14 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 45 1121 56 1 40 1 40 1 21 1 38 35 79 161 86 1 96 11591115 1 82 1 22 1196 Page 55 Table A-1 (continued)

Oct-Dec 2014 Class E F 0.284 mph IN INNEI NE IENEI E IESEI SE ISSEI S ISSW IWSW I W IWNWI NW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 0.95-3.5 3 9 4 5 3 3 12 23 20 25 31 29 10 18 8 6 209 3.5-7.5 0 5 2 7 4 6 7 25 57 46 51 94 55 20 3 1 383 7.5-12.5 0 0 3 2 1 1 0 1 2 14 2 0 2 0 0 0 28 12.5-18.5 0 0 0 2 0 0 0 0 3 1 0 0 0 0 0 0 6 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 14 9 16 8 10 19 50 82 86 84 1123 67 38 1 7 627 Class F Fr 0.055 mph IN INNE N ENEI E 1 ESE SE I SS Is SW sw I W IwNwI NW INNw[ TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 2 0.95-3.5 0 1 1 1 0 1 1 10 6 11 12 17 8 2 0 0 71 3.5-7.5 0 0 0 0 0 0 0 1 1 3 38 4 1 0 0 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 0 1 1 1 0 1 1 1 1 7 15 1 50 1 22 1 2 1 0 1 0 1 121 Class G Fr. 0.009 mph I N E INEI IESE SE SSEI S ISSWI SW IWSWI W IwNwI NWINNwlTOTAL 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 4 6 1 0 0 0 11 3,5-7.5 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 0 8 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 10 0 0 10 0 0 0 0 0 0 112 16 1 1 10 0 I0 19 Class All Fre 1.000 mph N NNE NE ENEI IESEI SE ISSE S ISSWl SW IwswI W IwNwl NW INNwl TOTAL Calm-0.95 0 0 0 0 0 0 0 1 0 1 0 1 0 0 0 1 4 0.95-3.5 16 21 17 17 13 9 33 43 42 45 51 64 28 29 21 14 463 3,5-7.5 32 102 56 35 32 17 28 49 110 144 164 197 222 130 86 25 1429 7.5-12.5 8 60 24 15 9 13 0 3 13 67 26 3 15 22 9 3 290 12,5-18.5 0 2 0 4 0 0 0 3 4 9 0 0 0 0 0 0 22 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 56 1185 97 71 54 3 61 99 169 266 241 265 265 181 116 43 2208 Page 56 Table A-1 (continued)

Jan-Dec 2014 Class A Freq 0.071 mph N NNE NE ENE E [ESE SE SSE S JsS SWV I I W W IWV NWI 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 23 29 25 8 16 0 0 0 0 0 0 0 1 8 8 9 127 3.5-7.5 34 71 65 32 30 8 13 1 5 9 5 8 27 57 34 30 429 7.5-12.5 4 5 15 0 2 2 0 5 3 6 1 0 6 9 8 2 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 I61 105 1051 40 148 [10 [13 I6L 8 15 6 1 8 1 34 74 50 I411 624 Class B Freq 0.030 mph. I INNE] NE ENEI E ESE SE ISSEI S Is v SSW I SW IWSW W IWNWv NWv 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 8 8 12 2 6 0 0 0 0 0 0 1 2 3 4 9 55 3.5-7.5 4 17 13 10 9 4 5 3 12 9 10 9 22 9 9 4 149 7.5-12.5 2 9 10 2 2 2 0 1 2 17 1 0 4 5 1 4 62 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 114 134 135 14 117 5 4 114 27111 10 1 28 17 14 117 267 Class C Fre 0 0.050 mph N NNE NE IENE[ E ESEI SE ISSEI S SSW SW IWSW [ W IWV[ N W 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 9 9 16 7 10 4 6 1 0 3 1 3 2 9 10 11 101 3.5-7.5 1 22 25 15 8 6 4 6 12 29 18 19 28 17 13 12 235 7.5-12.5 5 15 15 9 0 0 0 1 8 23 5 3 3 6 3 4 100 12.5-18.5 0 2 0 0 0 0 0 0 2 1 0 0 0 0 0 0 5 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 115 48 56 31 18 110 10 8 122 56 124 125 133 [32 ]26 127I 441 Class D Fre1 0.443 mph I N INNENE1 E I E ESE SE I SSW SW IWSWv W IVWNWv NW vNNW TOTAL Calm-0.95 0 0 0 1 0 0 1 0 0 0 0 0 0 0 0 1 3 0.95-3.5 55 82 85 72 62 58 57 37 43 28 39 40 34 30 44 38 804 3.5-7.5 69 152 90 51 58 56 83 55 187 481 194 211 301 166 124 33 2311 7.5-12.5 31 92 22 11 8 10 2 1 57 232 52 15 84 52 39 8 716 12.5-18.5 5 9 2 2 0 0 0 3 7 16 4 0 0 0 1 2 51 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 1160 335 199 137] 128 124 143 96 294 757 289 266 419 248 208 82 3885 Page 57 Table A-1 (continued)

Jan-Dec 2014 Class E Freq 0.298 mph I E I NEE IEI I E IESE I SE I S s s III v vWNW I NW I NNWv TOTAL Calm-0.95 0 3 0 2 1 1 2 5 4 4 4 3 4 1 0 5 39 0.95-3.5 33 45 35 53 43 33 60 96 96 85 85 119 69 73 55 38 1018 3.5-7.5 21 29 7 15 29 28 23 63 99 264 217 277 164 60 39 16 1351 7.5-12.5 2 8 5 5 1 1 9 11 15 69 39 3 5 8 6 1 188 12.5-18.5 0 0 0 2 0 0 0 0 11 4 0 0 0 0 0 0 17 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 1 56 1 85 ]47 I 7L 4 I463 1 94 1 175 12251 426 1 345 1 402 12421 142 11001 60 1 2613 Class F Fre : 0.083 mph__ N ILNNE]NEIENEI E IESEJ SE ISSE IS I SSW SW IWSW IWIWNWINWINNWJ TOTAL Calm-0.95 0 0 1 0 1 1 0 1 1 2 3 3 0 1 1 0 15 0.95-3.5 1 3 2 8 1 8 6 25 34 59 85 126 44 11 6 3 422 3.5-7.5 0 2 7 2 1 0 4 8 6 35 165 30 2 1 3 2 268 7.5-12.5 0 0 0 0 0 0 0 0 1 7 14 1 0 0 0 0 23 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 5 10 I 10 i3 I9 10 34 ]42 ]103 267 160 146 13 110 15 728 Class G gre: 0.023 mph N INNE NE ENE I E LESEISE ISSEJ S ]SSW ISWIWSWIWIWNWINWINNWI TOTAL_Ca1m-0.95 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 2 0.95-3.5 0 0 0 1 0 0 1 0 3 11 41 54 8 2 0 0 121 3.5-7.5 0 0 0 2 1 0 1 0 0 2 57 2 0 0 0 0 65 7.5-12.5 0 0 0 0 0 0 0 0 0 0 14 0 0 0 0 0 14 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 I0 10 3 11 0 I2 0[313 112 56 9W 3 0 oT 202 Class All Fre: 1.000 mph__ N N EE E E S ESE S SW S S WWN IN TOTAL_Calm-0.95 0 3 1 3 2 2 3 6 5 6 7 6 5 3 1 6 59 0.95-3.5 129 176 175 151 138 103 130 159 176 186 251 343 160 136 127 108 2648 3.5-7.5 129 293 207 127 136 102 133 136 321 829 666 556 544 310 222 97 4808 7.5-12.5 44 129 67 27 13 15 11 19 86 354 126 22 102 80 57 19 1171 12.5-18.5 5 11 2 4 0 0 0 3 20 22 4 0 0 0 1 2 74 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 307 6 612 1452 312 1289 1 222 1277 1 323 16081 1397 1 10541 927 1811 1 529 14081 232 1 8760 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 2014 Class A Freq 0.070 mr h INNNE NE ENEI E I ESE SE [SSEI S ISSW] SW IVWSWv VW IVN NW INNWv TOTAL Caim-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 3 0 0 0 0 0 0 0 0 0 0 4 1 4 14 7.5-12.5 5 5 3 0 3 1 0 0 0 1 1 0 3 14 7 4 47 12,5-18.5 3 2 0 1 1 3 0 0 0 0 0 0 6 19 6 4 45 18.5-24 6 0 0 0 0 0 0 0 0 0 0 0 7 14 5 3 35>24 1 0 0 0 0 0 0 0 0 0 0 0 0 5 4 0 10 TOTAL 171 7 1 6 1 4 4 0 0 0 1 1 0 11r.6 561523115 1 151 Class B Freq 0.023 mph N NNEI NE IE E ESE I SE ISSE I S ISSWvl SW IWSWv W IWVvl NW IWNW- 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 0 2 1 0 0 0 0 0 0 0 0 1 2 0 0 7 7.5-12.5 1 1 1 1 1 0 0 0 0 0 1 1 2 0 1 1 11 12,5-18.5 1 0 0 0 0 1 0 0 0 0 0 0 5 0 2 0 9 18.5-24 1 0 0 0 0 0 0 2 0 0 0 0 3 0 1 2 9>24 3 0 1 1 0 0 0 0 0 0 0 0 0 5 2 2 14 TOTAL I7 I1 4 3 1 1 0I 2 0 0I 1 1 117 7 [ 6 5 1 0 Class C Freq 0.040 p h INNNENE ENE E I E SE I SSE I SSWISW I WSW I W IWNWv NWINNWv 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 1 0 1 0 0 0 1 0 0 1 0 1 2 1 10 7.5-12.5 0 0 0 1 0 0 0 0 0 0 0 5 1 4 0 0 11 12,5-18.5 2 0 0 0 0 0 0 1 2 2 2 3 7 3 0 3 25 18.5-24 2 0 0 0 0 0 0 1 0 1 2 0 2 3 0 2 13>24 7 0 1 5 0 0 0 0 0 1 0 1 3 3 1 5 27 TOTAL 12 1 1 2 6 1 0 0 12 3 4 1 4 10113 1 [14 [3 1 866 Class D Freq 0.491 mh N NNE [E I EN[ E I....E.. ESE] SE JSSE I S ~ ~~ I S WISI W IWNW [ NW [ 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 1 1 2 0 1 1 1 0 1 0 0 3 0 0 1 2 14 3,5-7.5 4 6 3 0 4 3 2 0 1 4 3 9 13 3 2 1 58 7.5-12.5 5 7 8 4 5 4 5 4 18 39 44 33 22 7 9 0 214 12,5-18.5 4 5 6 3 2 4 4 5 19 63 38 59 76 45 21 12 366 18.5-24 25 5 2 5 1 2 5 3 2 22 12 9 43 28 30 9 203>24 49 11 9 3 4 0 0 0 3 5 4 1 19 37 28 32 205 TOTAL 88 35 30 1 15 14 [ 17J 12 44 133 1011 114 173 1120 [ 91 56I 1060 Page 59 Table A-2 (continued)

Jan-Mar 2014 Class E Freq 0.320 mph I N I NNE INE IENEI E I ESE I SE I SSE I S I SSVW ISVV WSW I WV .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 3 0 0 0 0 1 0 0 0 1 1 1 0 0 1 1 9 3.5-7.5 3 2 2 1 4 5 6 3 8 6 6 3 8 11 5 8 81 7.5-12.5 0 6 1 1 8 3 7 7 20 16 18 27 33 12 5 4 168 12.5-18.5 7 2 1 6 5 8 9 10 19 17 38 55 71 20 17 10 295 18.5-24 6 2 0 0 5 0 7 12 11 15 8 9 9 11 4 1 100>24 11 0 1 3 1 0 0 0 5 2 1 0 3 8 2 1 38 TOTAL I 30 1 12 1L5 11 1231 17 1 291 32 163 1 57 1 72 95 112 62 34 I2 691 Class F Freq 0.050 mph I N I NNE INE I ENE I E ESE SE I SSE I S I SSW I SW s I W I W WNW I NNWI TOTAL Calm-0.95 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 3 2 0 0 1 2 1 0 1 1 2 0 1 1 1 0 16 3.5-7.5 1 0 0 0 0 2 3 5 1 2 4 0 5 6 3 2 34 7.5-12.5 0 0 0 0 0 0 1 1 8 3 2 5 5 2 2 2 31 12.5-18.5 0 0 0 0 0 0 2 3 4 1 5 2 4 0 0 0 21 18.5-24 0 0 0 0 0 0 4 1 1 0 0 0 0 0 0 0 6>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 4I 2 0 12 I4 ll 110 1 7 113 I7 1 9 6 I I 109 Class G Fre: 0.006 raph N NNE N NE I ENE E ESE SE SSE I SSW I SW I WSW IW WNW 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 1 0 0 1 2 0 0 0 0 0 0 4 3.5-7.5 0 1 0 0 0 0 0 0 0 0 1 0 2 0 0 0 4 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 2 12.5-18.5 0 0 0 0 0 0 0 1 1 0 1 0 0 0 0 0 3 18.5-24 0 0 0 0 O 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 0oI 1 0 0 1 0 110 2 2 2 2 2 0 101 13 Class All Frec 1.000 aph I N INNEINE I ENE E I ESE ISEI SSE IS IS SW I SW I WSW I WI WNW NW I I TOTAL Calm-0.95 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 7 3 2 0 2 5 2 0 3 4 3 4 1 1 3 3 43 3.5-7.5 12 10 11 2 9 10 11 8 11 12 14 13 29 27 13 16 208 7.5-12.5 11 19 13 7 17 8 13 12 46 59 66 73 66 39 24 11 484 12.5-18.5 17 9 7 10 8 16 15 20 45 83 84 119 169 87 46 29 764 18.5-24 40 7 2 5 6 2 16 19 14 38 22 18 64 56 40 17 366>24 71 11 12125 0 0 0 8 8 5 2 25 58 37 40 294 TOTAL I158 1 59 1471 36 1481 41 157 1 59 11271 204 11941 229 13541 268 11631116I 2160 Page 60 Table A-2 (continued)

Apr-Jun 2014 Class A Fre 0.115 mph N N NE NE IENEI E IESEI SSEI S IT vv SW IWSW WVV I 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 1 7 8 3 2 1 0 0 0 0 0 0 0 0 0 2 24 7.5-12.5 11 4 14 6 18 4 0 1 1 1 2 2 0 4 2 8 78 12.5-18.5 16 10 20 4 4 10 13 0 5 1 1 0 8 6 3 7 108 18.5-24 4 4 7 0 0 0 2 5 2 3 0 0 0 0 0 3 30>24 5 0 0 0 0 0 0 0 0 0 0 0 0 0 5 2 12 TOTAL 37 125 149 113 24 15 15 6 8 5 3 2 I8 ] 110 122 252 Class B Fr 0 0.037 mphLI N ]NNEI NE IENEI E ESE I SE I SSE I S SSW SW [WSWI W VWNWI NW I NNWv 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 3 0 3 0 0 0 0 0 0 0 1 2 0 0 11 7.5-12.5 1 1 3 0 2 7 0 0 3 0 3 1 1 1 0 2 25 12.5-18.5 0 0 3 0 2 1 4 0 5 1 5 0 2 2 2 0 27 18.5-24 1 0 3 1 0 0 0 0 0 4 1 0 1 0 0 0 11>24 1 0 0 0 0 0 0 0 0 4 0 0 0 0 1 0 6 TOTAL 4 2 12 1 7 8 4 0 8 9 9 i1 I5 I5 31 2I 80 Class C Fre 0.053 mph IN INNE NE ENE E ESE SE LSSE S I SSW I vSW[WSWlWIvWNWv 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 1 2 5 1 3 1 0 0 0 0 0 1 0 0 0 1 15 7.5-12.5 1 1 2 2 3 4 7 1 1 3 1 2 0 1 1 4 34 12.5-18.5 2 0 14 3 3 2 1 0 5 5 6 1 1 0 2 0 45 18.5-24 0 0 5 2 2 0 0 2 1 2 0 0 0 0 1 1 16>24 0 0 0 0 0 0 0 0 2 0 0 0 0 0 3 0 5 TOTAL I4 I3 26 8 7 8 3 9 10 7 4 1 [1 7 I6 115 Class D FrO 0.365 aph IN NNE N NE lESEl SE ISSE IS ISSW IVWWSWlW IWNWv NW INNWv TOTAL Caim-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 2 1 1 2 0 1 2 0 1 0 0 0 0 1 12 3.5-7.5 11 1 15 6 12 27 11 8 4 5 3 0 2 4 9 7 125 7.5-12.5 6 9 20 11 5 21 20 13 17 23 19 5 2 5 3 7 186 12.5-18.5 1 11 18 13 6 15 23 13 28 58 19 6 10 14 5 2 242 18.5-24 10 6 2 7 7 2 4 17 12 68 10 3 4 10 7 5 174>24 12 0 1 0 0 0 0 0 4 14 2 0 4 5 16 0 58 TOTAL 140 28 58] 38 31 67 [58 52 67 168 1 5 1 14 [ 22 38 40I 22 797 Page 61 Table A-2 (continued)

Apr-Jun 2014 Class E Freq 0.295 mph N N] NNE NE ENE I E I ESE I SE SSE I S I S SW I SW I WSW I WNW I NW I 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 1 1 4 3 5 3 2 2 2 2 1 1 1 1 0 0 29 3.5-7.5 5 5 10 2 6 16 8 4 9 8 3 2 2 5 6 3 94 7.5-12.5 8 4 5 1 4 15 13 14 10 17 4 3 4 8 9 7 126 12.5-18.5 11 4 1 0 0 5 6 12 12 33 16 17 22 46 22 11 218 18.5-24 6 0 0 0 0 0 2 5 4 32 31 3 5 13 14 7 122>24 1 0 0 0 0 0 4 0 5 15 9 0 0 5 11 5 55 TOTAL I 32 14 120 6 1151 39 136 1 37 142 1 107 164 1 26 134 7I 8 162 I 33 I 645 Class F Freq 0.099 mph N N NE I E I Es I ES I SSE I ssW I sW I WSW W I WNW NW 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 1 1 0 1 3 0 0 1 0 0 1 0 0 8 3.5-7.5 3 4 2 2 0 1 2 2 1 2 3 0 1 4 1 1 29 7.5-12.5 1 2 1 0 0 1 4 1 3 6 7 4 7 11 9 2 59 12.5-18.5 2 1 0 0 0 0 0 2 3 3 6 11 16 17 11 5 77 18.5-24 1 0 0 0 0 0 0 0 0 6 8 7 7 0 2 1 32>24 0 0 0 0 0 0 0 0 0 2 8 0 0 0 0 2 12 TOA 7 7 3 I3 1 [1 2 7 I 7 19 133 122 131 1 33 23 11 217 Class G Freq 0.036 mph N ~NNE NE1 ENE [SESEISSE SISSW ISW]WSW IW IWNW INW jNNWI 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 2 1 1 0 0 0 0 1 0 1 0 1 0 3 11 3.5-7.5 1 2 1 1 0 1 1 1 1 2 0 4 0 1 3 1 20 7.5-12.5 0 0 0 0 0 0 0 1 0 1 1 4 6 3 0 0 16 12.5-18.5 0 0 0 0 0 0 0 0 0 0 2 6 3 0 1 1 13 18.5-24 0 0 0 0 0 0 0 0 0 2 10 4 0 0 0 1 17>24 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOT I 1 313 123 111 1 1 2 111 6 114 1 19I9 1 5 4 6I 78 Class All Freq 1.000 mph N NN[ NE ENEIE[SE SsEISS S ]SSW SW WS NWIN N 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 1 3 8 6 8 5 3 6 4 3 3 2 1 3 0 4 60 3.5-7.5 23 22 44 15 26 47 22 15 15 17 9 7 6 16 19 15 318 7.5-12.5 28 21 45 20 32 52 44 31 35 51 37 21 20 33 24 30 524 12.5-18.5 32 26 56 20 15 33 47 27 58 101 55 41 62 85 46 26 730 18.5-24 22 10 17 10 9 2 8 29 19 117 60 17 17 23 24 18 402>24 19 0 1 0 0 0 4 0 11 35 20 0 4 10 36 9 149 TOTAL 1125 [ 82 711111 1901 1396 1 1421 324 I111 8 11101 170 11491 102 2184 Page 62 Table A-2 (continued)

Jul-Sep 2014 Class A Freq: 0.074 mp.h N .INNEI NE IENEJ E IJESE SE ISSE S [SSW] SW IWSWv W IVVV[ NW N INW 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 5 8 5 6 2 0 0 0 0 0 1 0 0 4 3 3 37 7.5-12.5 13 12 6 6 2 0 0 0 1 0 0 0 6 3 0 2 51 12.5-18.5 17 9 3 7 10 0 0 1 3 2 0 0 3 1 1 0 57 18.5-24 6 1 0 0 1 0 0 0 1 1 1 0 1 1 0 6 19>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL I41 30 14 19 15 I0 I0 I1 5 3 I 2 0 10 I9 4 I l 164 Class B Freq 0.031 CaLm-.g5 N I NNE NE ENE 0EESEI SE SSE 0S ISSWISWJWSW WIWNW 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 8 3 3 1 0 0 0 0 0 0 0 0 0 0 2 1 18 7.5-12.5 3 0 2 1 0 1 1 1 2 1 0 1 0 1 0 5 19 12.5-18.5 2 1 1 2 1 0 2 0 8 2 0 1 2 1 0 1 24 18.5-24 0 1 0 0 0 0 0 1 0 3 2 0 0 0 0 0 7>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 113 5 6 4 1 I1 3 2 110 6 2 2 2 1 2 12 71 68 Class C Freq 0.055_mh. N NNE I NE I ENE E ESE SE SSE S I SSW VSW IWSWv I W IVNWI 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 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 2 4 5 2 0 0 1 0 0 0 2 0 0 3 2 4 25 7.5-12.5 1 1 4 3 3 1 2 1 3 5 1 1 2 4 0 4 36 12.5-18.5 1 1 0 1 0 0 1 1 13 17 3 2 1 2 1 2 46 18.5-24 0 0 0 1 0 0 0 0 2 7 1 0 0 0 0 0 11>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 2 TOTAL 4 71 9 I 3 1 4 2 18 29 7 3 3 9 4 11 121 Class D Fre_ 0.377_____l N INNE INE IENE I __IES_ SE ISSE I SI SSW ILSW IWSWJIW IWNWI NW [NNWj TOTAL_Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 5 3 1 4 2 1 0 0 0 0 1 0 0 0 0 1 18 3.5-7.5 13 16 17 9 11 12 3 1 3 9 11 2 1 2 7 3 120 7.5-12.5 5 13 23 8 6 9 19 11 15 39 26 7 1 4 3 10 199 12.5-18.5 10 12 9 16 4 3 11 1 41 170 31 10 10 3 4 10 345 18.5-24 17 9 0 0 9 3 6 0 4 71 5 0 1 7 4 3 139>24 4 0 0 0 0 1 0 0 0 0 0 0 0 5 0 1 11 T9OTA 154] 53150137132 39 13 63 1289 74 I 19 13 1 21 1 1 1 2 32 TOTAL 4ý5 --3 3 3 Page 63 Table A-2 (continued)

Jul-Sep 2014 Class E Freq 0.294 ph I N INEI I ENE E I ESE I SE I SSE I N SSN WS I WSv I v I WNW NW I NNW I TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0.95-3,5 2 0 2 2 2 2 1 1 0 0 2 0 1 1 1 0 17 3.5-7.5 3 4 7 6 7 23 10 4 1 2 2 3 3 0 2 3 80 7.5-12,5 12 11 10 12 14 7 9 7 14 22 3 8 10 11 13 8 171 12.5-18.5 10 0 2 2 9 2 3 20 8 60 46 17 23 25 12 7 246 18.5-24 3 0 0 0 3 1 1 0 1 54 30 6 1 7 3 7 117>24 5 0 0 0 0 0 0 0 0 6 4 0 0 0 0 3 18 TOTAL 35 j 15 121 1 22 1351 35 1241 3 2 1 2 4 1 4 4 188 1 34 138 1 44 31 1 28 1 650 Class F Freq 0.127 N ph N NE NE E I ESE ISES I s SE ISSW SW WSW W WNW I N]NWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3,5 2 0 1 0 1 0 3 0 2 0 0 0 0 0 0 1 10 3.5-7.5 2 0 1 1 1 7 5 6 1 5 0 1 2 0 1 0 33 7.5-12,5 1 1 0 0 1 4 7 9 12 10 5 4 6 8 15 5 88 12.5-18.5 0 0 0 0 0 0 5 12 9 23 29 15 6 27 5 0 131 18.5-24 0 0 0 0 0 0 0 0 0 2 14 1 0 0 0 2 19>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 5 1 12 I1 3 11 120 27 24 40 48 21 14 35 21 8 281 Class G Freq 0.042... NhI N NNE NE ENE E ESE SE SSE S SSW SW WSW I Wv 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 1 0 0 2 0 1 0 0 1 1 0 0 1 0 0 1 8 3.5-7.5 0 0 0 0 1 0 1 0 3 4 3 5 2 1 1 0 21 7.5-12,5 0 0 0 0 0 0 1 2 1 1 7 11 14 5 2 0 44 12.5-18.5 0 0 0 0 0 0 0 1 2 2 3 2 4 3 2 0 19 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 1 I 0 0 2I0 LLL 1213 7 8 1 31 18 121 1 9 I 1 92 Class All Freq 1.000 n .I NNI NIIE NEIE ESE I SSE S S IsW I WSW IW IWNW INW INNWI TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0.95-3.5 10 4 4 8 5 4 4 1 3 1 3 0 2 1 1 3 54 3.5-7.5 33 35 38 25 22 42 20 11 8 20 19 11 8 10 18 14 334 7.5-12.5 35 38 45 30 26 22 39 31 48 78 42 32 39 36 33 34 608 12.5-18.5 40 23 15 28 24 5 22 36 84 276 112 47 49 62 25 20 868 18.5-24 26 11 0 1 13 4 7 1 8 138 53 7 3 15 7 18 312>24 9 0 0 0 0 1 0 0 0 6 4 0 0 5 1 5 31 TOTAL 1153 1 111 11021 92 1901 78 j 921 80 1151 1 519 12341 97 11011 129 1 85 ] 94 1 2208 Page 64 Table A-2 (continued)

Oct-Dec 2014 Class A Freq 0.026 Nph I N I N E [ENE E EIsE s S IssSW I SW Ivswl W IvvWI Nv 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 1 0 0 0 0 0 0 0 0 0 0 1 1 0 3 7.5-12.5 3 0 1 0 0 0 0 0 0 0 0 1 1 6 1 2 15 12.5-18.5 3 0 2 1 0 0 0 0 0 0 0 0 4 4 5 3 22 18.5-24 1 0 0 2 0 1 0 1 0 0 0 0 2 0 2 0 9>24 1 2 1 0 2 0 0 0 0 0 0 0 0 1 1 0 8 TOTAL I8 2 5 3 2 1 0 1 0 0 0 1 1 7 112 110 1 5 57 Class B 0.031 mph IN INNNE NE IENEl E IESEI SE ISSEI S ISSWI SW IWSWI W IWNWI NW INNWI TOTAL Caim-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 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 7.5-12.5 0 0 1 1 2 2 0 0 0 0 0 5 5 1 1 0 18 12.5-18.5 3 1 1 0 0 0 0 0 1 1 3 0 5 2 1 0 18 18.5-24 0 5 4 1 0 1 0 0 0 0 0 0 0 1 3 1 16'24 2 6 1 0 2 1 0 0 0 0 0 0 0 1 1 2 16 TOTAL 15f 112 18 12 14 14 l0 l0 1 1 13 15 10 15 16 13 I 69 Class C 0.054 mph NNE I NEI ENEI E EISE SEI SSE SSSW Is SWl Iwsw W INW NNw IN.wlTOTAL 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 1 0 1 0 0 0 0 0 0 0 0 1 1 0 0 4 7.5-12.5 0 0 3 1 2 1 3 0 0 1 1 8 6 2 6 1 35 12.5-18.5 2 3 5 2 0 0 0 0 0 0 2 4 4 3 5 0 30 18.5-24 0 7 4 8 0 0 1 1 0 0 0 0 1 0 4 1 27>24 6 10 0 0 0 0 0 0 0 0 0 0 0 5 0 2 23 TOTAL I 8 21 I12 I [12I 1 I I2 1 4 1. 0 11 3112[1I15 I 119 Class D Freq 0.542 mph I N INNE NE ENE E ESE SE SSE S ISSW SW Iwswl W IwNwl NW I 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 2 1 0 0 0 0 0 0 1 0 0 0 0 0 0 0 4 3.5-7.5 4 3 3 12 6 6 5 4 4 3 5 5 1 1 5 3 70 7.5-12.5 5 8 12 6 8 4 14 6 19 24 29 23 17 16 6 6 203 12.5-18.5 12 22 10 9 8 6 17 14 23 87 64 32 79 80 40 9 512 18.5-24 13 21 11 21 6 10 5 5 3 32 19 2 24 37 29 14 252>24 41 19 10 8 6 0 0 4 0 8 0 0 1 21 20 17 155 TOTAL 177 74 46 6 34 26 41 I33 I5 154 117 62 122 155 100 49 1196 Page 65 Table A-2 (continued)

Oct-Dec 2014 Class E Freq 0.284 mph IN INNE NE I ENEI ESE SEI SSE I S ISSW I SW IWSWv W I[WNW NW INNWvI 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 1 1 1 2 0 1 0 1 1 0 0 2 0 0 12 3.5-7.5 5 4 9 2 1 1 4 4 6 12 4 7 2 7 6 3 77 7.5-12.5 1 4 1 3 4 7 7 13 9 25 28 13 14 23 5 5 162 12.5-18.5 1 1 0 4 4 3 5 41 25 32 29 52 59 34 12 3 305 18.5-24 2 2 1 2 1 0 0 1 2 20 4 5 10 8 1 0 59>24 0 0 2 5 2 0 0 0 1 1 0 0 0 1 0 0 12 TOTAL I 9 1 13 14 1 7 13 13 1616 0 43 91 668 7 I 85 75 I24 I 11 I 627 Class F Fre( 0.055 mph [N NNE I __ ENE E ESE SE SSE I SSW I SW IVsv VVIW J IwNW 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 1 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 3 3.5-7.5 3 2 0 0 1 0 0 2 1 3 1 3 2 1 0 3 22 7.5-12.5 0 0 0 0 0 2 3 4 0 2 4 1 5 12 2 2 37 12.5-18.5 0 0 0 0 0 0 3 10 3 2 8 15 15 3 0 0 59 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 14 12 10 11 2 16 117 1 4 1 7 13 119 122 1 12 61 121 Class G F 1 eq 0.009 mph N NNEI NE ENE E ESE SE ISS S I I SW Ivsv 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 1 0 0 1 0 0 0 0 0 2 3.5-7.5 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 4 6 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 1 4 12.5-18.5 0 0 0 0 0 0 0 0 1 0 5 1 0 0 0 0 7 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 0101010101010 11 21017121210 0151 19 Class All Freq 1.000 mp I N INNEI NE ENEI E ESEI SE I SSE S ISSWvl SW IWSWv IV IW NwI NW I NNWl 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 1 1 2 0 3 1 1 2 0 0 2 0 1 21 3.5-7.5 12 10 14 15 8 7 9 10 12 18 10 15 7 11 12 13 183 7.5-12.5 9 12 18 11 16 16 27 23 28 52 63 52 49 60 21 17 474 12.5-18.5 21 27 18 16 12 9 25 65 53 122 111 104 166 126 63 15 953 18.5-24 16 35 20 34 7 12 6 8 5 52 23 7 37 46 39 16 363>24 50 37 14 13 12 1 0 4 1 9 0 0 1 29 22 21 214 TOTAL I 111 124 85 90 56 I47 67 I113 100 I 254 209 178 260 274 157 I83I 2208 Page 66 Table A-2 (continued)

Jan-Dec 2014 Class A Freq 0.071 mph I N NNE NE ENE E IESE SE SSE S NSS SN I I I W IWvWv 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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 8 15 17 9 4 1 0 0 0 0 1 0 0 9 5 9 78 7.5-12.5 32 21 24 12 23 5 0 1 2 2 3 3 10 27 10 16 191 12.5-18.5 39 21 25 13 15 13 13 1 8 3 1 0 21 30 15 14 232 18.5-24 17 5 7 2 1 1 2 6 3 4 1 0 10 15 7 12 93>24 7 2 1 0 2 0 0 0 0 0 0 0 0 6 10 2 30 TOTAL 103 64 74 36 45 2 15 8 13 9 I 6 3 I41 87 47 1 53 I 624 Class B Freq 0.030 mph N NNE NE ENE I E ;ESEl SE ISSE S I SSW SW IjWSW WNWJ 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 10 4 9 2 3 0 0 0 0 0 0 0 2 4 2 1 37 7.5-12.5 5 2 7 3 5 10 1 1 5 1 4 8 8 3 2 8 73 12.5-18.5 6 2 5 2 3 2 6 0 14 4 8 1 14 5 5 1 78 18.5-24 2 6 7 2 0 1 0 3 0 7 3 0 4 1 4 3 43>24 6 6 2 1 2 1 0 0 0 4 0 0 0 6 4 4 36 TOTAL 129 20 30] 10 13 14 7 4 19] 16 15 9 [28 19 17 17I 267j Class C Freq 0.050 ph N [NNE IEENE E ESESEI s SSEI S sswI sWvvW IvWsw [W Iv NW 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 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 4 8 11 4 4 1 1 0 1 0 2 2 1 5 4 6 54 7.5-12.5 2 2 9 7 8 6 12 2 4 9 3 16 9 11 7 9 116 12.5-18.5 7 4 19 6 3 2 2 2 20 24 13 10 13 8 8 5 146 18.5-24 2 7 9 11 2 0 1 4 3 10 3 0 3 3 5 4 67>24 13 10 1 5 0 0 0 0 2 1 0 1 3 8 5 8 57 TOTAL 128 32 49 33 ]17 9 16 I8 .30 1I44 T21 J 29 [ 29 [ 35 129 32 441 Class D Freq 0.443 mph I N [NNE NE IENE] I ESE SE I SSE S IssW I SW IWSW I [vWNWI NWv 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 8 6 5 5 4 4 1 1 4 0 2 3 0 0 1 4 48 3.5-7.5 32 26 38 27 33 48 21 13 12 21 22 16 17 10 23 14 373 7.5-12.5 21 37 63 29 24 38 58 34 69 125 118 68 42 32 21 23 802 12.5-18.5 27 50 43 41 20 28 55 33 111 378 152 107 175 142 70 33 1465 18.5-24 65 41 15 33 23 17 20 25 21 193 46 14 72 82 70 31 768>24 106 30 20 11 10 1 0 4 7 27 6 1 24 68 64 50 429 TOTAL I259 190 184 146 114 1 136 155 1 110 224 744] 346 1 209 1 330 [ 334 1 249] 155I 3885 Page 67 Table A-2 (continued)

Jan-Dec 2014 Class E Fre: 0.298 mph N I NNE INEIENEI E[ I SE I SE I SSE I S I SSW I SW I WSW_ I W I VWNW I I VNNW I TOTAL Calm-0.95 0 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 2 0.95-3.5 6 3 7 6 8 8 3 4 2 4 5 2 2 4 2 1 67 3.5-7.5 16 15 28 11 18 45 28 15 24 28 15 15 15 23 19 17 332 7.5-12.5 21 25 17 17 30 32 36 41 53 80 53 51 61 54 32 24 627 12.5-18.5 29 7 4 12 18 18 23 83 64 142 129 141 175 125 63 31 1064 18.5-24 17 4 1 2 9 1 10 18 18 121 73 23 25 39 22 15 398>24 17 0 3 8 3 0 4 0 11 24 14 0 3 14 13 9 123 TOTAL J106 I 5 160 56 1 86 1 104 1105 161 1172 1 399 12901 232 1281 [ 259 1151 ] 97 2613 Class F Freq 0.083 mh N NNE_ NE_ EN E_ ES-EISEIS-SIW WS IWIWWIN N TOTAL Calm-0.95 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 6 2 1 1 3 2 5 4 3 1 3 0 1 2 1 2 37 3.5-7.5 9 6 3 3 2 10 10 15 4 12 8 4 10 11 5 6 118 7.5-12.5 2 3 1 0 1 7 15 15 23 21 18 14 23 33 28 11 215 12.5-18.5 2 1 0 0 0 0 10 27 19 29 48 43 41 47 16 5 288 18.5-24 1 0 0 0 0 0 4 1 1 8 22 8 7 0 2 3 57>24 0 0 0 0 0 0 0 0 0 2 8 0 0 0 0 2 12 TOAL 20 112 15 14 7I 19 44 J 62 150 1 73 11071 69 182 1 93 152 I 29 1 728 Class G Freq 0.023 N [ N NNE INE IENE IE IESE ISE SSE IS I SW SWI WSW W I WNW ]NWI 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 1 1 2 3 1 2 0 1 2 4 1 1 1 1 0 4 25 3.5-7.5 1 3 1 1 1 1 2 1 5 6 4 9 5 2 4 5 51 7.5-12.5 0 0 0 0 0 0 1 3 1 2 9 18 21 8 2 1 66 12.5-18.5 0 0 0 0 0 0 0 2 4 2 11 9 7 3 3 1 42 18.5-24 0 0 0 0 0 0 0 0 0 2 10 4 0 0 0 1 17>24 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTAL I2 4 I3 4 I2 3I3 7 112 I1 36 41 134 114 9 1 121 202 Class All Freq: 1.000 m h N [NNEINE IENE I EESEI SE] SSE I S ISSW [SWIWSWIW IWNW INW INNWI TOTAL Calm-0.95 0 0 0 0 1 0 1 0 0 0 1 0 0 0 0 0 3 0.95-3.5 21 13 15 15 16 16 9 10 11 9 11 6 4 7 4 11 178 3.5-7.5 80 77 107 57 65 106 62 44 46 67 52 46 50 64 62 58 1043 7.5-12.5 83 90 121 68 91 98 123 97 157 240 208 178 174 168 102 92 2090 12.5-18.5 110 85 96 74 59 63 109 148 240 582 362 311 446 360 180 90 3315 18.5-24 104 63 39 50 35 20 37 57 46 345 158 49 121 140 110 69 1443>24 149 48 27 25 17 2 4 4 20 58 29 2 30 102 96 75 688 TOTAL I 547 1 376 14051 289 12841 305 13451 360 1520 I 1301 1821 I 592 18251 841 15541 395 1 8760 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 inside the protected area fence during the fourth quarter of 2007. The first samples were collected in November 2007. 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. Two pre-existing wells were incorporated into the groundwater monitoring program in early 2008. Additional wells were added to the program in 2010 (12 wells), 2011 (2 wells), 2012 (1 well), 2013 (3 wells), and 2014 (1 well). A total of 23 wells are being sampled on a routine basis.In addition to sampling the onsite monitoring wells, samples of surface water are collected from two locations in the PNPS Intake Canal. These locations are along the shoreline in the same direction as the groundwater flow gradient.All samples collected are analyzed for tritium, a radioactive isotope of hydrogen, and also for gamma emitting radionuclides.

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.

Low levels of tritium were detected in the many of the onsite wells. Although gamma spectroscopy 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 groundwater samples, other than tritium. 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 demonstrates the ability of the gamma spectroscopy analyses to detect radioactivity in groundwater.

Analyses are also performed for hard-to-detect radionuclides, including Iron-55, Nickel-63, Strontium-89, and Strontium-90 on a less frequent basis. These hard-to-detect radionuclides were also non-detectable in all of the wells sampled and analyzed during 2014.A summary of the results of the tritium analyses conducted in 2014 are presented in the following table. In this table, 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 13-Jan-2014 contained no detectable tritium, and a minimum detectable concentration of 389 pCi/L was achieved on that sample. The achieved sensitivity of 389 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.

No plant-related radioactivity (other than tritium) was detected in any of the monitoring wells, and no tritium or plant-related radioactivity was detected in surface water samples collected from the intake canal.Page 69 Number of Minimum Maximum Monitoring Well ID Date Samples Positive Concentration Concentration Results pCiIL pCi/L MW201 Nov-2007 27 1 NDA < 311 396 MW202 Nov-2007 5 0 NDA < 353 NDA < 387 MW202-1 Apr-2010 5 3 NDA < 405 1740 MW203 Nov-2007 Well decommissioned in 2013 during construction of ISFSI pad MW204 Nov-2007 4 0 NDA < 366 NDA < 406 MW205 Apr-2010 50 23 NDA < 349 1520 MW206 Apr-2010 27 6 NDA < 339 1080 MW207 Apr-2010 4 0 NDA < 365 NDA < 399 MW208-S Apr-2010 4 0 NDA < 364 NDA < 394 MW208-1 Apr-2010 4 0 NDA < 365 NDA < 387 MW209 Aug-2010 52 52 380 1610 MW210 Aug-2010 4 0 NDA < 371 NDA < 406 MW211 Aug-2010 52 52 616 1440 MW212 Aug-2010 4 3 NDA < 368 624 MW213 Aug-2010 4 0 NDA < 366 NDA < 393 MW214 Aug-2010 4 0 NDA < 338 NDA < 401 MW215 Dec-2011 27 27 667 1280 MW216 Sep-2012 52 52 1050 6610 MW217 Dec-2011 4 0 NDA < 362 NDA < 391 MW218 Nov-2013 52 52 1070 4730 MW219 Dec-2013 53 53 591 20000 MW220 Dec-2014 Well installed late Dec-2014; first sample collected 15-Jan-2015 MW3 Jul-1987 4 0 1 NDA < 358 1 NDA < 395 MW4 Jul-1997 Well decommissioned in 2013 during installation of MW4R MW4-R Nov-2013 14 7 NDA < 339 581 All Wells -- 456 331 NDA < 311 20000 Intake Canal West -- 51 0 NDA < 311 NDA < 416 Intake Canal East -- 4 0 NDA < 368 NDA < 427 Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 311 pCi/L, up to a maximum concentration of 20,000 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 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 MW219 (average concentration

= 4314 pCi/L) was consumed as drnking 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.Page 70 Although there are no indications that the groundwater containing detectable 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 2014, 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 potential 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 430 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.00538 Curies. This activity represents less than 0.006% 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 0.00538 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 2014 was 614 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.0088 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 0.0000000050 millirem, resulting from ingestion of 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 71 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 9.61E+01 2.06E+02 1.51E+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 3.81 E+02 5.08E+02 5.85E+02 3.74E+02 Annual Segment Tritium Discharge

-Ci/yr 6.13E-04 1.10E-03 1.11E-03 2.56E-03 Total Volumetric Discharge

-L/yr 1.25E+07 Total H-3 Discharge

-Ci/yr 5.38E-03 Annual Circulating Water Flow -Liter/yr 6.14E+11 Discharge Canal H-3 Concentration

-Ci/L 8.75E-15 Discharge Canal H-3 Concentration

-pCi/L 8.75E-03 Max. Indiv. Dose Factor -mrem/yr per Ci/L 5.73E+05 Maximum Individual Dose -mrem/yr 5.01 E-09 In April 2013, an internal inspection of the neutralizing sump discharge line identified a separation in the line approximately 5-feet below the ground surface where the line exits the foundation of the building.

The inspection also identified two additional anomalies in the line closer to where it terminates in Catch Basin #10. The locations of the line separation and the two anomalies were excavated in July 2013 to inspect the condition of the line and collect soil samples for radioactivity analyses.

The line was found to be intact at the two anomalies, and soil samples collected in the vicinity of these anomalies was non-detectable for plant-related radioactivity, including tritium, gamma emitters, and hard-to-detect radionuclides.

However, in the soil immediately adjacent to the line separation, low levels of plant-related gamma activity were identified in the soil. Tritium was also detected in the water contained in the soil at this location, at concentrations lower than that assumed to have leaked from the line during the March discharge.

All of the radiological survey information was entered into Pilgrim Station's 10CFR50.75(g) decommissioning database, and another voluntary notification was made to the NRC and interested stakeholders.

Because the neutralizing sump discharge line was still intact at the location of the separation, it was determined that most of the volume discharged during the four permitted releases in March 2013 would have continued to flow down the line to Catch Basin #10, as originally intended.

The original bounding calculation assuming over 38,000 gallons of contaminated water entering the groundwater was very conservative, as the actual volume entering the soil at the line separation was much smaller, most likely less than a few hundred gallons. Increased well sampling throughout 2013 at monitoring wells downgradient of the line separation have not identified any increased concentrations of tritium, and no gamma activity has been identified in any well samples. The gamma nuclides identified tend to chemically bind to the soil particles, and likely moved only a few inches from the location of the separation.

This would explain why the activity would not reach the groundwater at a depth of about 18-feet below the ground surface, or 13-feet below the line separation.

Since there is no evidence of this gamma activity having entered the groundwater, no ingestion exposure pathways exist for this radioactivity.

Page 72 Additional excavations were performed during 2014 in the vicinity of neutralizing sump discharge line separation, and confirmed that the highest concentrations were immediately adjacent to the separation, and had migrated only a few feet horizontally or vertically from the separation.

The additional soil survey results were entered into the 10CFR50.75(g) decommissioning database.Based on the lower concentrations observed during the 2014 soil sampling efforts, it was determined that the assessments and bounding calculations performed during 2013 were conservative, and the actual impact would have been less than that assessed in 2013.Due to these events involving the neutralizing sump discharge line, two new wells were installed in November and December of 2013 to further characterize the movement of tritiated water along the west side of the building.

MW218 was installed downgradient of the line separation to monitor for radioactivity entering the groundwater from this location.

MW219 was installed immediately adjacent to Catch Basin #10 to monitor for any potential leakage from this catch basin. Tritium results from these wells are listed in the earlier table. In the case of MW218 downgradient of the neutralizing sump discharge line separation, the tritium concentrations during 2014 ranged from 1070 pCi/L to 4730 pCi/L. The concentrations in this well immediately downgradient of the line separation are significantly less than the concentration of tritium contained in the permitted discharges during 2013. Based on these results, it does not appear that any significant fraction of the discharges actually made it to the groundwater.

In October 2013, a temporary discharge hose was put into place to facilitate continued permitted discharges from the neutralizing sump, since the original discharge line was isolated in March-2013. One such discharge was made in October, and three discharges occurred in December, the latest on 20-Dec-2013, about 9-days after MW219 was installed.

The sample collected on 30-Dec from MW219, approximately 10-days following the permitted discharge into Catch Basin #10, indicated a tritium concentration of 69,000 pCi/L. The time delay between the permitted discharge and the elevated tritium result is consistent with the groundwater moving about 4-feet from the catch basin to the well at a rate of about 6-inches/day.

The information surrounding this event was entered into Pilgrim Station's 10CFR50.75(g) decommissioning database, and another voluntary notification was made to the NRC and interested stakeholders.

No elevated tritium concentrations have been detected at additional wells downgradient of MW219, indicating that the concentration of 69,000 pCi/L is very localized in the vicinity of MW219, and becomes diluted within a short distance of Catch Basin #10. The first sample collected from MW219 during 2014 yielded a concentration of 20,000 pCi/L, indicating the very localized nature of this event and the rapid reduction in concentrations through time. By the fourth quarter of 2014, tritium concentrations in MW219 were ranging between 591 and 1240 pCi/L.An internal inspection of Catch Basin #10 was performed in 2014 and determined that there was some degradation in the grout seal around the invert pipes entering and exiting the catch basin.An inspection was also performed of Catch Basin #11, which receives the discharge from Catch Basin #11 before ultimately entering the PNPS Discharge Canal. Similar degradation was found in the grout at this catch basin, and the degraded grout in each catch basin was repaired in 2014. As a follow-up activity related to the degraded grout, additional soil excavations were performed in the vicinity of both catch basins to determine if any residual plant-related activity existed. Five excavations were performed at each of the two catch basins. Although several soil samples collected near Catch Basin #10 indicated some low-level Cs-1 37 and tritium, none of the samples collected near Catch Basin #11 indicated the presence of plant-related radioactivity.

The concentrations of tritium in the soil samples at Catch Basin #10 ranged from non-detectable at less than 540 pCi/L, up to a maximum concentration of 2460 pCi/L. Such concentrations are consistent with the tritium concentrations detected in MW219 immediately adjacent to Catch Basin #10. An evaluation of the soil radioactivity determined that there was no need for immediate remediation of the area around Catch Basin #10, and all of the soil analyses were entered into Pilgrim Station's 10CFR50.75(g) decommissioning database.Page 73 A bounding calculation was performed in 2014 to assess the potential dose impact from leakage occurring from Catch Basin #10. It is assumed that 280 gallons of water containing tritium at a concentration of 550,000 pCi/L leaked from the catch basin from the discharges that occurred in Dec-2013.

Based on groundwater flow rates, it would take approximately 18-months for this tritium to reach the saltwater environment at the Pilgrims Station Intake Canal. Over that time period, the tritium would be diluted by the groundwater flowing through the area, resulting in a maximum diluted concentration of about 170 pCi/L upon entry into the seawater.

Since there are no drinking water wells affected by the presumed leak of this wastewater to the groundwater, the dose impact was determined from ingestion of contaminated fish and shellfish that accumulated tritium from the seawater after it had passed through the circulating pumps. Using such worst-case assumptions, the calculated dose from this event was estimated at 0.0000000050 mrem/yr.In conclusion, the only radionuclide detected in groundwater during the 2014 monitoring effort that is attributable to Pilgrim Station operations is tritium. Although some soil samples near the separation in the underground discharge line from the neutralizing sump indicated the presence of low-level gamma radioactivity, such activity has not been detected in the groundwater and indicates the radioactivity is immobile and confined to the soil. Even in the case of the three reportable events that occurred in 2013 and subsequent sample results in 2014, the total dose impact to a maximally-exposed member of the public would have been much less than 1 mrem/yr.Page 74 APPENDIX C CORRECTIONS TO PREVIOUS EFFLUENT REPORTS Table 3.1-2 of the PNPS ODCM requires that if any of the gaseous effluent monitors are inoperable for more than 30-days, such events are to be reported in the Annual Radioactive Effluent Release Report (ARERR), with an explanation of why the affected monitor was not returned to operable status in a timely manner. During a review of the ARERRs for 2012 and 2013, it was identified that such instances were not included in the annual reports.During 2012 the Turbine Building Gaseous Effluent Monitoring System (GEMS, unit C-3003) was inoperable from 27-Feb-2012 through 06-Apr-2012 (40 days). During 2012, the Feed Pump Gaseous Effluent Monitoring System (GEMS, unit C-3004) was inoperable from 14-May-2012 through 24-Jun-2012 (42 days), and again from 16-Aug-2012 through 31-Dec-2012 (138 days).During each of these periods of inoperability, compensatory sampling activities were performed during the duration of the inoperability, including manually sampling the effluent release points twice per week for noble gases, and continuous sampling of the effluent release points twice per week for particulates and radioiodines.

In both of these situations, repairs to each of the monitors were delayed due to difficulty in obtaining replacement components necessary to fix the monitor.During 2013 the Turbine Building GEMS, unit C-3003, was inoperable from 22-Jan-2012 through 31-Dec-2013 (344 days). Also during 2012, the Feed Pump GEMS, unit C-3004, was inoperable for the entire year from 01-Jan-2013 through 31-Dec-2013 (365 days). During each of these periods of inoperability, compensatory sampling activities were performed during the duration of the inoperability, including manually sampling the effluent release points twice per week for noble gases, and continuous sampling of the effluent release points twice per week for particulates and radioiodines.

In both of these situations, repairs to each of the monitors were delayed due to difficulty in obtaining replacement components necessary to fix the monitor, and issues related to scheduling the repairs in the station work plan due to higher priority tasks.Page 75 APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2014.Page 76