ML17142A066: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:* May 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 | {{#Wiki_filter:* | ||
May 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Annual Radioactive Effluent Release Report for January 1 through December 31, 2016 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.17.033 | Annual Radioactive Effluent Release Report for January 1 through December 31, 2016 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.17.033 | ||
Line 25: | Line 27: | ||
==Attachment:== | ==Attachment:== | ||
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Senior Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8 B1A Washington, DC 20555 Mr. John Giarrusso, Jr. Planning, Preparedness & Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.17.033 Page 2 of 2 Attachment Letter Number 2.17.033 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, 2016 * | |||
* PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 Prepared by: K.J. Sejkora Senior HP/Chemistry Specialist Reviewed by: 2B--&ftl'1/-;(CJl7 G. . Blankenbiller Chemistry Manager Reviewed by: _Z_o_f_l_ Radiation Protection Manager Page2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2016 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 EXECUTIVE SUMMARY 5 2.0 RADIOACTIVE EFFLUENT DATA 8 2.1 Supplemental Effluent Release Data 8 2.2 Gaseous Effluent Data 8 2.3 Liquid Effluent Data 9 3.0 METEOROLOGICAL DATA 19 4.0 MAXIMUM INDIVIDUAL DOSES 20 4.1 Doses From Noble Gas Releases 20 4.2 Doses From Gaseous Effluent Releases 22 4.3 Doses From Liquid Effluent Releases 28 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS 34 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS 37 6.1 Gaseous Effluent Releases 37 6.2 Liquid Effluent Releases 40 7.0 RADIOACTIVE WASTE DISPOSAL DATA 43 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS 45 9.0 PROCESS CONTROL PROGRAM REVISIONS 46 | Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Senior Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8 B1A Washington, DC 20555 Mr. John Giarrusso, Jr. Planning, Preparedness | ||
& Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.17.033 Page 2 of 2 Attachment Letter Number 2.17.033 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, 2016 * | |||
* PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 Prepared by: | |||
K.J. Sejkora Senior HP/Chemistry Specialist Reviewed by: 2B--&ftl'1/-;(CJl7 G. . Blankenbiller Chemistry Manager Reviewed by: | |||
_Z_o_f_l_ Radiation Protection Manager Page2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2016 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 EXECUTIVE SUMMARY 5 2.0 RADIOACTIVE EFFLUENT DATA 8 2.1 Supplemental Effluent Release Data 8 2.2 Gaseous Effluent Data 8 2.3 Liquid Effluent Data 9 3.0 METEOROLOGICAL DATA 19 4.0 MAXIMUM INDIVIDUAL DOSES 20 4.1 Doses From Noble Gas Releases 20 4.2 Doses From Gaseous Effluent Releases 22 4.3 Doses From Liquid Effluent Releases 28 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS 34 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS 37 6.1 Gaseous Effluent Releases 37 6.2 Liquid Effluent Releases 40 7.0 RADIOACTIVE WASTE DISPOSAL DATA 43 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS 45 9.0 PROCESS CONTROL PROGRAM REVISIONS 46 | |||
==10.0 REFERENCES== | ==10.0 REFERENCES== | ||
48 APPENDIX A Meteorological Joint Frequency Distributions 49 APPENDIX B Onsite Groundwater Monitoring Program 70 APPENDIX C Corrections to Previous Effluent Reports 74 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual 75 Page 3 TABLE 2.1 2.2-A 2.2-B 2.2-C 2.3-A 2.3-B 4.1 4.2-A 4.2-B 4.2-C 4.2-D 4.2-E 4.3-A 4.3-B 4.3-C 4.3-D 4.3-E 5.0 6.1 6.2 7.0 A-1 A-2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2016 LIST OF TABLES TABLE TITLE Supplemental Information Gaseous Effluents -Summation of All Releases Gaseous Effluents -Elevated Releases Gaseous Effluents -Ground Level Releases Liquid Effluents -Summation of All Releases Liquid Effluents Maximum Doses from Noble Gas Releases During 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Gaseous Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Gaseous Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Gaseous Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Liquid Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Liquid Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Liquid Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Dec 2016 Average TLD Exposures by Distance Zone During 2016 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 Solid Waste and Irradiated Fuel Shipments Joint Frequency Distribution of Wind Directions and Speeds for the 33-ft Level of the 220-ft Tower Joint Frequency Distribution of Wind Directions and Speeds for the 220-ft Level of the 220-ft Tower Page4 PAGE 10 11 12 14 16 17 21 23 24 25 26 27 29 30 31 32 33 36 38 41 44 50 60 INTRODUCTION EXECUTIVE SUMMARY PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 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, 2016. 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 be.en prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3. The quantity of radioactive material released from PNPS was determined from sample analyses and continuous on-line monitoring of gaseous releases from the main stack, reactor building vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal. The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation. The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station. GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 0.20 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0020 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 7.8 Curies. No gross alpha radioactivity was detected in gaseous effluents. Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.00000093 mrem, with a corresponding skin dose of 0.0000023 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 0.017 mrem. The maximum hypothetical dose to any organ from radioactive particulates, iodines, tritium, and carbon-14 was about 0.077 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.017 mrem. The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 0.000014% of the corresponding 1 OCFR50 dose objectives. Maximum doses resulting from releases of particulates, iodines, tritium, and carbon-14 in gaseous effluents were less than 0.52% of corresponding 1 OCFR50 objectives. Page 5 LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B. Two discharges of liquid containing radioactivity occurred during the reporting period. These discharges contained 0.0015 Curies of tritium, and 0.0000081 Curies of fission and activation products. The resulting maximum total body dose was 0.00000026 mrem, with a corresponding organ dose of 0.00000046 mrem. All doses from liquid discharges were less than 0.000014% of corresponding 1 OCFR50 objectives. METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 96% for the 33-ft and 96% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 14% of the time during the reporting period. The predominant stability class was Class D, which occurred about 41 % 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 1.6 mrem during 2016. There was no measurable increase during 2016 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 2016 was calculated as being about 0.77 mrem. This amount is about 0.12% of the typical dose of 620 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 427 cubic meters of solid waste, containing 1040 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 2016, 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 related radioactivity was detected in the groundwater samples. The average concentration of tritium detected in these onsite monitoring wells during 2016 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 0.0000000055 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 2016, 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, 18, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference 1) format. 2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1. 2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities. Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows: | |||
48 APPENDIX A Meteorological Joint Frequency Distributions 49 APPENDIX B Onsite Groundwater Monitoring Program 70 APPENDIX C Corrections to Previous Effluent Reports 74 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual 75 Page 3 TABLE 2.1 2.2-A 2.2-B 2.2-C 2.3-A 2.3-B 4.1 4.2-A 4.2-B 4.2-C 4.2-D 4.2-E 4.3-A 4.3-B 4.3-C 4.3-D 4.3-E 5.0 6.1 6.2 7.0 A-1 A-2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2016 LIST OF TABLES TABLE TITLE Supplemental Information Gaseous Effluents | |||
-Summation of All Releases Gaseous Effluents | |||
-Elevated Releases Gaseous Effluents | |||
-Ground Level Releases Liquid Effluents | |||
-Summation of All Releases Liquid Effluents Maximum Doses from Noble Gas Releases During 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Gaseous Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Gaseous Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Gaseous Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Liquid Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Liquid Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Liquid Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Dec 2016 Average TLD Exposures by Distance Zone During 2016 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 Solid Waste and Irradiated Fuel Shipments Joint Frequency Distribution of Wind Directions and Speeds for the 33-ft Level of the 220-ft Tower Joint Frequency Distribution of Wind Directions and Speeds for the 220-ft Level of the 220-ft Tower Page4 PAGE 10 11 12 14 16 17 21 23 24 25 26 27 29 30 31 32 33 36 38 41 44 50 60 INTRODUCTION EXECUTIVE SUMMARY PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 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, 2016. 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 be.en prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3. The quantity of radioactive material released from PNPS was determined from sample analyses and continuous on-line monitoring of gaseous releases from the main stack, reactor building vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal. The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation. | |||
The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station. | |||
GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 0.20 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0020 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 7.8 Curies. No gross alpha radioactivity was detected in gaseous effluents. | |||
Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.00000093 mrem, with a corresponding skin dose of 0.0000023 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 0.017 mrem. The maximum hypothetical dose to any organ from radioactive particulates, | |||
: iodines, tritium, and carbon-14 was about 0.077 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.017 mrem. The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 0.000014% | |||
of the corresponding 1 OCFR50 dose objectives. | |||
Maximum doses resulting from releases of particulates, | |||
: iodines, tritium, and carbon-14 in gaseous effluents were less than 0.52% of corresponding 1 OCFR50 objectives. | |||
Page 5 LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B. Two discharges of liquid containing radioactivity occurred during the reporting period. These discharges contained 0.0015 Curies of tritium, and 0.0000081 Curies of fission and activation products. | |||
The resulting maximum total body dose was 0.00000026 mrem, with a corresponding organ dose of 0.00000046 mrem. All doses from liquid discharges were less than 0.000014% | |||
of corresponding 1 OCFR50 objectives. | |||
METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 96% for the 33-ft and 96% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 14% of the time during the reporting period. The predominant stability class was Class D, which occurred about 41 % 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 1.6 mrem during 2016. There was no measurable increase during 2016 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 2016 was calculated as being about 0.77 mrem. This amount is about 0.12% of the typical dose of 620 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 427 cubic meters of solid waste, containing 1040 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 2016, 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 related radioactivity was detected in the groundwater samples. | |||
The average concentration of tritium detected in these onsite monitoring wells during 2016 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 0.0000000055 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 2016, 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, 18, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference | |||
: 1) format. 2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1. 2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities. | |||
Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows: | |||
* Noble gases: 0.195 Ci, 0.00617 µCi/sec | * Noble gases: 0.195 Ci, 0.00617 µCi/sec | ||
* Iodines and particulates with 0.0020 Ci, 0.0000633 µCi/sec half-life greater than 8 days | * Iodines and particulates with 0.0020 Ci, 0.0000633 | ||
* Tritium: 66.9 Ci, 2.12 µCi/sec | µCi/sec half-life greater than 8 days | ||
* Carbon-14: 7.82 Ci, 0.248 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 1 OCFR50 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 2016 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 2016, the Turbine Building Gaseous Effluent Monitor (C-3003) was out of service for 42-days from 12-Feb-2016 to 25-Mar-2016 due to a failure of the sample pump and flow controller circuitry. The Feed Pump Gaseous Effluent Monitor (C-3004) was out of service for 238-days from 07-May-2016 to 31-Dec-2016 due to a failure of the detector and flow controller circuitry. Both of these monitors are subject to obsolescence issues and it was difficult to obtain replacement parts necessary to perform repairs. In both of these situations compensatory sampling was performed by collecting noble gas samples twice per week. There were no instances in 2016 when both channels of a dual-channel effluent monitor (Main Stack, Reactor Building Vent) were out of service at the same time during a 30 consecutive day period. 2.3 Liquid Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building. Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were two discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows: | * Tritium: | ||
66.9 Ci, 2.12 µCi/sec | |||
* Carbon-14: | |||
7.82 Ci, 0.248 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 1 OCFR50 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 2016 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 2016, the Turbine Building Gaseous Effluent Monitor (C-3003) was out of service for 42-days from 12-Feb-2016 to 25-Mar-2016 due to a failure of the sample pump and flow controller circuitry. | |||
The Feed Pump Gaseous Effluent Monitor (C-3004) was out of service for 238-days from 07-May-2016 to 31-Dec-2016 due to a failure of the detector and flow controller circuitry. | |||
Both of these monitors are subject to obsolescence issues and it was difficult to obtain replacement parts necessary to perform repairs. | |||
In both of these situations compensatory sampling was performed by collecting noble gas samples twice per week. There were no instances in 2016 when both channels of a dual-channel effluent monitor (Main Stack, Reactor Building Vent) were out of service at the same time during a 30 consecutive day period. 2.3 Liquid Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building. | |||
Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were two discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows: | |||
* Total Effluent Volume: 73,600 Liters | * Total Effluent Volume: 73,600 Liters | ||
* Total Dilution Volume: 612 billion Liters | * Total Dilution Volume: 612 billion Liters | ||
* Fission/Activation products: 0.00000806 Ci, 0.0000000000000132 µCi/ml | * Fission/Activation products: | ||
* Tritium: 0.00147 Ci, 0.00000000000240 µCi/ml | 0.00000806 Ci, 0.0000000000000132 | ||
* Dissolved/entrained noble gases: 0.00 Ci, 0.00 µCi/ml Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2016 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. Iodines, particulates with half-life: 1500 mrem/yr to any organ at site boundary >8 davs, 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 Aooendix B Table II b. Iodines: 10CFR20 Aooendix B Table II c. Particulates with half-life > 8 davs: 10CFR20 Aooendix B Table II d. Liquid effluents: 2E-04 µCi/ml for entrained noble gases; 10CFR20 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. Iodines: 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 2016 2016 2016 2016 2016 a. Liquid Effluents 1. Total number of releases: N/A 1.00E+OO 1.00E+OO N/A 2.00E+OO 2. Total time period (minutes): N/A 8.70E+02 9.60E+02 N/A 1.83E+03 3. Maximum time period N/A 8.70E+02 9.60E+02 N/A 9.60E+02 (minutes): 4. Average time period (minutes): N/A 8.70E+02 9.60E+02 N/A 9.15E+02 5. Minimum time period (minutes): N/A 8.70E+02 9.60E+02 N/A 8.70E+02 6. Average stream flow during periods of release of N/A 1.19E+06 1.19E+06 N/A 1.19E+06 effluents into a flowing stream (Liters/min): b. Gaseous Effluents None None None None None 6. ABNORMAL RELEASES a. Liquid Effluents None None None None None b. Gaseous Effluents None None None None None Page 10 Table 2.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents -Summation of All Releases January-December 2016 RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATION GASES Total Release: Ci O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Average Release Rate: µCi/sec O.OOE+OO 5.02E-03 8.85E-03 1.08E-02 Percent of Effluent Control Limit* * * * | µCi/ml | ||
* B. IODINE-131 Total lodine-131 Release: Ci 1.04E-04 1.06E-04 9.75E-05 1.01E-04 Averaqe Release Rate: µCi/sec 1.32E-05 1.34E-05 1.24E-05 1.28E-05 Percent of Effluent Control Limit* * * * | * Tritium: | ||
* C. PARTICULATES WITH HALF-LIVES > 8 DAYS Total Release: Ci 7.19E-06 3.51E-05 5.88E-05 5.46E-05 Averaqe Release Rate: µCi/sec 9.12E-07 4.45E-06 7.45E-06 6.92E-06 Percent of Effluent Control Limit* * * * | 0.00147 Ci, 0.00000000000240 | ||
* Gross Aloha Radioactivity: Ci NDA NOA NDA NOA D. TRITIUM Total Release: Ci 1.62E+01 1.76E+01 1.52E+01 1.51 E+01 Average Release Rate: µCi/sec 2.06E+OO 2.23E+OO 1.92E+OO 1.91E+OO Percent of Effluent Control Limit* * * * | µCi/ml | ||
* E. CARBON-14 Total Release: Ci 2.03E+OO 2.11E+OO 1.73E+OO 1.95E+OO Average Release Rate: µCi/sec 2.58E-01 2.68E-01 2.20E-01 2.47E-01 Percent of Effluent Control Limit* * * * | * Dissolved/entrained noble gases: 0.00 Ci, 0.00 µCi/ml Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2016 FACILITY: | ||
* Notes for Table 2.2-A: Est. Jan-Dec Total 2016 Error 1.95E-01 6.17E-03 +/-22% | PILGRIM NUCLEAR POWER STATION LICENSE: | ||
* 4.09E-04 1.30E-05 +/-20% | 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. Iodines, particulates with half-life: | ||
* 1.56E-04 4.94E-06 +/-21% | 1500 mrem/yr to any organ at site boundary | ||
* NOA 6.41E+01 2.03E+OO +/-20% | >8 davs, 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 Aooendix B Table II b. Iodines: | |||
10CFR20 Aooendix B Table II c. Particulates with half-life > 8 davs: 10CFR20 Aooendix B Table II d. Liquid effluents: | |||
2E-04 µCi/ml for entrained noble gases; 10CFR20 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. Iodines: | |||
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 2016 2016 2016 2016 2016 a. Liquid Effluents | |||
: 1. Total number of releases: | |||
N/A 1.00E+OO 1.00E+OO N/A 2.00E+OO | |||
: 2. Total time period (minutes): | |||
N/A 8.70E+02 9.60E+02 N/A 1.83E+03 | |||
: 3. Maximum time period N/A 8.70E+02 9.60E+02 N/A 9.60E+02 (minutes): | |||
: 4. Average time period (minutes): | |||
N/A 8.70E+02 9.60E+02 N/A 9.15E+02 | |||
: 5. Minimum time period (minutes): | |||
N/A 8.70E+02 9.60E+02 N/A 8.70E+02 | |||
: 6. Average stream flow during periods of release of N/A 1.19E+06 1.19E+06 N/A 1.19E+06 effluents into a flowing stream (Liters/min): | |||
: b. Gaseous Effluents None None None None None 6. ABNORMAL RELEASES | |||
: a. Liquid Effluents None None None None None | |||
: b. Gaseous Effluents None None None None None Page 10 Table 2.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents | |||
-Summation of All Releases January-December 2016 RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATION GASES Total Release: | |||
Ci O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Average Release Rate: µCi/sec O.OOE+OO 5.02E-03 8.85E-03 1.08E-02 Percent of Effluent Control Limit* * * * | |||
* B. IODINE-131 Total lodine-131 Release: | |||
Ci 1.04E-04 1.06E-04 9.75E-05 1.01E-04 Averaqe Release Rate: µCi/sec 1.32E-05 1.34E-05 1.24E-05 1.28E-05 Percent of Effluent Control Limit* * * * | |||
* C. PARTICULATES WITH HALF-LIVES | |||
> 8 DAYS Total Release: | |||
Ci 7.19E-06 3.51E-05 5.88E-05 5.46E-05 Averaqe Release Rate: µCi/sec 9.12E-07 4.45E-06 7.45E-06 6.92E-06 Percent of Effluent Control Limit* * * * | |||
* Gross Aloha Radioactivity: | |||
Ci NDA NOA NDA NOA D. TRITIUM Total Release: | |||
Ci 1.62E+01 1.76E+01 1.52E+01 1.51 E+01 Average Release Rate: µCi/sec 2.06E+OO 2.23E+OO 1.92E+OO 1.91E+OO Percent of Effluent Control Limit* * * * | |||
* E. CARBON-14 Total Release: | |||
Ci 2.03E+OO 2.11E+OO 1.73E+OO 1.95E+OO Average Release Rate: µCi/sec 2.58E-01 2.68E-01 2.20E-01 2.47E-01 Percent of Effluent Control Limit* * * * | |||
* Notes for Table 2.2-A: Est. Jan-Dec Total 2016 Error 1.95E-01 6.17E-03 | |||
+/-22% | |||
* 4.09E-04 1.30E-05 | |||
+/-20% | |||
* 1.56E-04 4.94E-06 | |||
+/-21% | |||
* NOA 6.41E+01 2.03E+OO | |||
+/-20% | |||
* 7.82E+OO 2.48E-01 N/A * | * 7.82E+OO 2.48E-01 N/A * | ||
* Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report. 1. NOA stands for No Detectable Activity. 2. LLD for airborne gross alpha activity listed as NDA is 1 E-11 µCi/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 2016 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE:roo O.OOE+OO O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 2. IODINES: Ci 1-131 1.29E-06 2.99E-07 6.05E-06 1.29E-06 1-133 1.63E-06 O.OOE+OO 6.24E-06 O.OOE+OO Total for Period 2.92E-06 2.99E-07 1.23E-05 1.29E-06 3. PARTICULATES WITH HALF-LIVES> 8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 O.OOE+OO O.OOE+OO 7.08E-07 O.OOE+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 O.OOE+OO O.OOE+OO 1.81 E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO 1.06E-06 O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO O.OOE+OO 3.58E-06 O.OOE+OO 4. TRITIUM: Ci H-3 2.52E-02 5.02E-02 6.16E-02 4.91E-02 5. CARBON-14: Ci C-14 1.97E+OO 2.05E+OO 1.68E+OO 1.89E+OO Notes for Table 2.2-B: 1. N/A stands for not applicable. 2. NOA stands for No Detectable Activity. 3. LLDs for airborne radionuclides listed as NOA are as follows: Fission Gases: 1 E-04 µCi/cc Iodines: 1 E-12 Particulates: 1 E-11 µCi/cc Page 12 Jan-Dec 2016 O.OOE+OO O.OOE+OO 1.95E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-01 8.93E-06 7.87E-06 1.68E-05 O.OOE+OO 7.08E-07 O.OOE+OO O.OOE+OO 1.81 E-06 1.06E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.58E-06 1.86E-01 7.58E+OO Table 2.2-B (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents -Elevated Release January-December 2016 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES: Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period 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 Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM: Ci H-3 N/A N/A N/A N/A 5. CARBON-14: Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-B: 1. N/A stands for not applicable. 2. NOA stands for No Detectable Activity. 3. LLDs for airborne radionuclides listed as NOA are as follows: Fission Gases: 1 E-04 µCi/cc Iodines: 1 E-12 µCi/cc Particulates: 1 E-11 µCi/cc Page 13 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents -Ground-Level Release January-December 2016 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE+OO O.OOE+OO . O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. IODINES: Ci 1-131 1.03E-04 1.06E-04 9.15E-05 9.99E-05 1-133 3.24E-04 3.77E-04 3.52E-04 3.51 E-04 Total for period 4.27E-04 4.83E-04 4.43E-04 4.51E-04 3. PARTICULATES WITH HALF-LIVES> 8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 4.23E-06 O.OOE+OO 2.02E-05 4.13E-05 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 2.96E-06 O.OOE+OO 8.53E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO 1.41E-05 1.33E-05 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO 3.51E-05 1.24E-05 O.OOE+OO Total for period 7.19E-06 3.51E-05 5.52E-05 5.46E-05 4. TRITIUM: Ci H-3 1.62E+01 1.76E+01 1.51 E+01 1.50E+01 5. CARBON-14: Ci C-14 6.09E-02 6.33E-02 5.20E-02 5.83E-02 Notes for Table 2.2-C: 1. N/A stands for not applicable. 2. NOA stands for No Detectable Activity. 3. LLDs for airborne radionuclides listed as NOA are as follows: Fission Gases: 1 E-04 µCi/cc Iodines: 1E-12 µCi/cc Particulates: 1 E-11 µCi/cc Page 14 Jan-Dec 2016 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-04 1.40E-03 1.BOE-03 O.OOE+OO 6.57E-05 O.OOE+OO O.OOE+OO 1.15E-05 O.OOE+OO 2.73E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.75E-05 1.52E-04 6.39E+01 2.34E-01 Table 2.2-C (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents -Ground-Level Release January-December 2016 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES: Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 3. PARTICULATES WITH HALF-LIVES> B DAYS: Ci Cr-51 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM: Ci H-3 N/A N/A N/A N/A 5. CARBON-14: Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-C: 1. N/A stands for not applicable. 2. NOA stands for No Detectable Activity. 3. LLDs for airborne radionuclides listed as NOA are as follows: Fission Gases: 1 E-04 µCi/cc Iodines: Particulates: 1 E-11 µCi/cc Page 15 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents -Summation of All Releases January-December 2016 | * Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report. 1. NOA stands for No Detectable Activity. | ||
* RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATIOl'J PRODUCTS Total Release (not including N/A 6.23E-06 1.83E-06 N/A tritium, Qases, alpha): Ci Average Diluted Concentration N/A 4.10E-14 1.19E-14 N/A During Period: µCi/ml Percent of Effluent N/A 4.10E-06% 1.19E-06% N/A Concentration Limit* B. TRITIUM Total Release: Ci N/A 4.96E-04 9.71E-04 N/A Average Diluted Concentration N/A 3.26E-12 6.30E-12 N/A DurinQ Period: µCi/ml Percent of Effluent N/A 3.26E-07% 6.30E-07% N/A Concentration Limit* C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A NDA NDA N/A Average Diluted Concentration N/A NDA NDA N/A DurinQ Period: uCi/mL Percent of Effluent N/A 0.00E+OO% O.OOE+OO% N/A . Concentration Limit* D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A NDA NDA N/A E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters O.OOE+OO 3.54E+04 3.82E+04 O.OOE+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 1.52E+11 1.54E+11 1.54E+11 Notes for Table 2.3-A: Est. Jan-Dec Total 2016 Error 8.06E-06 1.32E-14 +/-12% 1.32E-06% 1.47E-03 2.40E-12 +/-9.4% 2.40E-07% NDA NDA +/-16% O.OOE+OO% NDA +/-34% 7.36E+04 +/-5.7% 6.12E+11 +/-10% | : 2. LLD for airborne gross alpha activity listed as NDA is 1 E-11 µCi/cc. 3. N/A stands for not applicable. | ||
* 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 1 E-05 µCi/ml. 4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 µCi/ml. Page 16 Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A N/A Mn-54 N/A N/A Fe-55 N/A N/A Fe-59 N/A N/A Co-58 N/A N/A Co-60 N/A N/A Zn-65 N/A N/A Zn-69m N/A N/A Sr-89 N/A N/A Sr-90 N/A N/A Zr/Nb-95 N/A N/A Mo/Tc-99 N/A N/A Aq-110m N/A N/A Sb-124 N/A N/A 1-131 N/A N/A 1-133 N/A N/A Cs-134 N/A N/A Cs-137 N/A N/A Ba/la-140 N/A N/A Ce-141 N/A N/A Total for period N/A N/A 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A Xe-135 N/A N/A Total for period N/A N/A Notes for Table 2.3-8: 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 µCi/ml Iodines: 1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 17 Jul-Sep 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Oct-Dec 2016 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-8 (continued) Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 BATCH MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 1. FISSION AND ACTIVATION PRODUCTS: Ci Na-24 N/A O.OOE+OO O.OOE+OO Cr-51 N/A O.OOE+OO O.OOE+OO Mn-54 N/A O.OOE+OO O.OOE+OO Fe-55 N/A O.OOE+OO O.OOE+OO Fe-59 N/A O.OOE+OO O.OOE+OO Co-58 N/A O.OOE+OO O.OOE+OO Co-60 N/A O.OOE+OO O.OOE+OO Zn-65 N/A O.OOE+OO O.OOE+OO Zn-69m N/A O.OOE+OO O.OOE+OO Sr-89 N/A O.OOE+OO O.OOE+OO Sr-90 N/A O.OOE+OO O.OOE+OO Zr/Nb-95 N/A O.OOE+OO O.OOE+OO Mo/Tc-99 N/A O.OOE+OO O.OOE+OO Ag-110m N/A O.OOE+OO O.OOE+OO Sb-124 N/A O.OOE+OO O.OOE+OO 1-131 N/A O.OOE+OO O.OOE+OO 1-133 N/A O.OOE+OO O.OOE+OO Cs-134 N/A O.OOE+OO O.OOE+OO Cs-137 N/A 6.23E-06 1.83E-06 8a/la-140 N/A O.OOE+OO O.OOE+OO Ce-141 N/A O.OOE+OO O.OOE+OO Ce-144 N/A O.OOE+OO O.OOE+OO Total for period N/A 6.23E-06 1.83E-06 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A NOA NOA Xe-135 N/A NOA NOA Total for period N/A NOA NOA Notes for Table 2.3-8: 1. N/A stands for not applicable. 2. NDA stands for No Detectable Activity. 3. llDs for liquid radionuclides listed as NOA are as follows: Strontium: 5E-08 µCi/ml Iodines: 1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 18 Oct-Dec 2016 Jan-Dec 2016 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A NOA N/A NOA N/A NOA 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: | Page 11 Table 2.2-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents | ||
-Elevated Release January-December 2016 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE:roo O.OOE+OO O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 | |||
: 2. IODINES: | |||
Ci 1-131 1.29E-06 2.99E-07 6.05E-06 1.29E-06 1-133 1.63E-06 O.OOE+OO 6.24E-06 O.OOE+OO Total for Period 2.92E-06 2.99E-07 1.23E-05 1.29E-06 | |||
: 3. PARTICULATES WITH HALF-LIVES> | |||
8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 O.OOE+OO O.OOE+OO 7.08E-07 O.OOE+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 O.OOE+OO O.OOE+OO 1.81 E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO 1.06E-06 O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO O.OOE+OO 3.58E-06 O.OOE+OO | |||
: 4. TRITIUM: | |||
Ci H-3 2.52E-02 5.02E-02 6.16E-02 4.91E-02 | |||
: 5. CARBON-14: | |||
Ci C-14 1.97E+OO 2.05E+OO 1.68E+OO 1.89E+OO Notes for Table 2.2-B: 1. N/A stands for not applicable. | |||
: 2. NOA stands for No Detectable Activity. | |||
: 3. LLDs for airborne radionuclides listed as NOA are as follows: | |||
Fission Gases: 1 E-04 µCi/cc Iodines: | |||
1 E-12 Particulates: | |||
1 E-11 µCi/cc Page 12 Jan-Dec 2016 O.OOE+OO O.OOE+OO 1.95E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-01 8.93E-06 7.87E-06 1.68E-05 O.OOE+OO 7.08E-07 O.OOE+OO O.OOE+OO 1.81 E-06 1.06E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.58E-06 1.86E-01 7.58E+OO Table 2.2-B (continued) | |||
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents | |||
-Elevated Release January-December 2016 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES: | |||
Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period 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 Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM: | |||
Ci H-3 N/A N/A N/A N/A 5. CARBON-14: | |||
Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-B: 1. N/A stands for not applicable. | |||
: 2. NOA stands for No Detectable Activity. | |||
: 3. LLDs for airborne radionuclides listed as NOA are as follows: | |||
Fission Gases: 1 E-04 µCi/cc Iodines: | |||
1 E-12 µCi/cc Particulates: | |||
1 E-11 µCi/cc Page 13 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents | |||
-Ground-Level Release January-December 2016 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE+OO O.OOE+OO | |||
. O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO | |||
: 2. IODINES: | |||
Ci 1-131 1.03E-04 1.06E-04 9.15E-05 9.99E-05 1-133 3.24E-04 3.77E-04 3.52E-04 3.51 E-04 Total for period 4.27E-04 4.83E-04 4.43E-04 4.51E-04 | |||
: 3. PARTICULATES WITH HALF-LIVES> | |||
8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 4.23E-06 O.OOE+OO 2.02E-05 4.13E-05 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 2.96E-06 O.OOE+OO 8.53E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO 1.41E-05 1.33E-05 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO 3.51E-05 1.24E-05 O.OOE+OO Total for period 7.19E-06 3.51E-05 5.52E-05 5.46E-05 | |||
: 4. TRITIUM: | |||
Ci H-3 1.62E+01 1.76E+01 1.51 E+01 1.50E+01 | |||
: 5. CARBON-14: | |||
Ci C-14 6.09E-02 6.33E-02 5.20E-02 5.83E-02 Notes for Table 2.2-C: 1. N/A stands for not applicable. | |||
: 2. NOA stands for No Detectable Activity. | |||
: 3. LLDs for airborne radionuclides listed as NOA are as follows: | |||
Fission Gases: 1 E-04 µCi/cc Iodines: | |||
1E-12 µCi/cc Particulates: | |||
1 E-11 µCi/cc Page 14 Jan-Dec 2016 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-04 1.40E-03 1.BOE-03 O.OOE+OO 6.57E-05 O.OOE+OO O.OOE+OO 1.15E-05 O.OOE+OO 2.73E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.75E-05 1.52E-04 6.39E+01 2.34E-01 Table 2.2-C (continued) | |||
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents | |||
-Ground-Level Release January-December 2016 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES: | |||
Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 3. PARTICULATES WITH HALF-LIVES> | |||
B DAYS: Ci Cr-51 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM: | |||
Ci H-3 N/A N/A N/A N/A 5. CARBON-14: | |||
Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-C: 1. N/A stands for not applicable. | |||
: 2. NOA stands for No Detectable Activity. | |||
: 3. LLDs for airborne radionuclides listed as NOA are as follows: | |||
Fission Gases: 1 E-04 µCi/cc Iodines: | |||
Particulates: | |||
1 E-11 µCi/cc Page 15 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents | |||
-Summation of All Releases January-December 2016 | |||
* RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATIOl'J PRODUCTS Total Release (not including N/A 6.23E-06 1.83E-06 N/A tritium, Qases, alpha): Ci Average Diluted Concentration N/A 4.10E-14 1.19E-14 N/A During Period: µCi/ml Percent of Effluent N/A 4.10E-06% | |||
1.19E-06% | |||
N/A Concentration Limit* B. TRITIUM Total Release: | |||
Ci N/A 4.96E-04 9.71E-04 N/A Average Diluted Concentration N/A 3.26E-12 6.30E-12 N/A DurinQ Period: µCi/ml Percent of Effluent N/A 3.26E-07% | |||
6.30E-07% | |||
N/A Concentration Limit* C. DISSOLVED AND ENTRAINED GASES Total Release: | |||
Ci N/A NDA NDA N/A Average Diluted Concentration N/A NDA NDA N/A DurinQ Period: uCi/mL Percent of Effluent N/A 0.00E+OO% | |||
O.OOE+OO% | |||
N/A . Concentration Limit* D. GROSS ALPHA RADIOACTIVITY Total Release: | |||
Ci N/A NDA NDA N/A E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters O.OOE+OO 3.54E+04 3.82E+04 O.OOE+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 1.52E+11 1.54E+11 1.54E+11 Notes for Table 2.3-A: Est. Jan-Dec Total 2016 Error 8.06E-06 1.32E-14 | |||
+/-12% 1.32E-06% | |||
1.47E-03 2.40E-12 | |||
+/-9.4% 2.40E-07% | |||
NDA NDA +/-16% O.OOE+OO% | |||
NDA +/-34% 7.36E+04 | |||
+/-5.7% 6.12E+11 | |||
+/-10% | |||
* 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 1 E-05 µCi/ml. 4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 µCi/ml. Page 16 Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 1. FISSION AND ACTIVATION PRODUCTS: | |||
Ci Cr-51 N/A N/A Mn-54 N/A N/A Fe-55 N/A N/A Fe-59 N/A N/A Co-58 N/A N/A Co-60 N/A N/A Zn-65 N/A N/A Zn-69m N/A N/A Sr-89 N/A N/A Sr-90 N/A N/A Zr/Nb-95 N/A N/A Mo/Tc-99 N/A N/A Aq-110m N/A N/A Sb-124 N/A N/A 1-131 N/A N/A 1-133 N/A N/A Cs-134 N/A N/A Cs-137 N/A N/A Ba/la-140 N/A N/A Ce-141 N/A N/A Total for period N/A N/A 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A Xe-135 N/A N/A Total for period N/A N/A Notes for Table 2.3-8: 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 µCi/ml Iodines: | |||
1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 17 Jul-Sep 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Oct-Dec 2016 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-8 (continued) | |||
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 BATCH MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 1. FISSION AND ACTIVATION PRODUCTS: | |||
Ci Na-24 N/A O.OOE+OO O.OOE+OO Cr-51 N/A O.OOE+OO O.OOE+OO Mn-54 N/A O.OOE+OO O.OOE+OO Fe-55 N/A O.OOE+OO O.OOE+OO Fe-59 N/A O.OOE+OO O.OOE+OO Co-58 N/A O.OOE+OO O.OOE+OO Co-60 N/A O.OOE+OO O.OOE+OO Zn-65 N/A O.OOE+OO O.OOE+OO Zn-69m N/A O.OOE+OO O.OOE+OO Sr-89 N/A O.OOE+OO O.OOE+OO Sr-90 N/A O.OOE+OO O.OOE+OO Zr/Nb-95 N/A O.OOE+OO O.OOE+OO Mo/Tc-99 N/A O.OOE+OO O.OOE+OO Ag-110m N/A O.OOE+OO O.OOE+OO Sb-124 N/A O.OOE+OO O.OOE+OO 1-131 N/A O.OOE+OO O.OOE+OO 1-133 N/A O.OOE+OO O.OOE+OO Cs-134 N/A O.OOE+OO O.OOE+OO Cs-137 N/A 6.23E-06 1.83E-06 8a/la-140 N/A O.OOE+OO O.OOE+OO Ce-141 N/A O.OOE+OO O.OOE+OO Ce-144 N/A O.OOE+OO O.OOE+OO Total for period N/A 6.23E-06 1.83E-06 | |||
: 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A NOA NOA Xe-135 N/A NOA NOA Total for period N/A NOA NOA Notes for Table 2.3-8: 1. N/A stands for not applicable. | |||
: 2. NDA stands for No Detectable Activity. | |||
: 3. llDs for liquid radionuclides listed as NOA are as follows: | |||
Strontium: | |||
5E-08 µCi/ml Iodines: | |||
1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 18 Oct-Dec 2016 Jan-Dec 2016 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A NOA N/A NOA N/A NOA 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, 41 % | * Stability Class: Class D, 41 % | ||
* 33-ft Wind Direction (from): South-southwest, 14% | * 33-ft Wind Direction (from): South-southwest, 14% | ||
* 33-ft Wind Speed: 3.5-7.5 mph, 56% | * 33-ft Wind Speed: 3.5-7.5 mph, 56% | ||
* 220-ft Wind Direction (from): Southwest, 13% | * 220-ft Wind Direction (from): Southwest, 13% | ||
* 220-ft Wind Speed: 12.5-18.5 mph, 34% Joint data recovery for the 33-ft level was 96.3% and for the 220-ft level of the tower was 96.3%, both of which meet the 90% annual data recovery goal specified by the NRC. Problems were encountered in December 2015 when the main power supply for the | |||
* Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidnev N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A | * Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidnev N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A | ||
* 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 Organ Bone Gl-LLI Kidney Liver LunQ Table 4.3-B Maximum Individual Organ Doses --mrem From Liquid Release Period: Apr-Jun 2016 Age Class Organ Dose -mrem Adult Teen Child 1.95E-07 2.97E-07 2.59E-07 2.58E-08 1.19E-07 2.58E-08 1.02E-07 1.98E-07 9.78E-08 2.59E-07 3.57E-07 2.49E-07 4.80E-08 1.48E-07 5.08E-08 Thyroid 2.11E-08 1.16E-07 2.44E-08 T.Body 1.77E-07 2.00E-07 5.76E-08 Page 30 Organ Bone Gl-LLI Kidney Liver Lung Table 4.3-C Maximum Individual Organ Doses --mrem From Liquid Release Period: Jul-Sep 2016 Age Class Organ Dose -mrem Adult Teen Child 5.64E-08 8.60E-08 7.52E-08 8.24E-09 3.51E-08 7.98E-09 3.03E-08 5.79E-08 2.88E-08 7.59E-08 1.04E-07 7.28E-08 1.47E-08 4.34E-08 1.52E-08 Thyroid 6.90E-09 3.41 E-08 7.57E-09 T.Body 5.21 E-08 5.85E-08 1.72E-08 Page 31 Table 4.3-D Maximum Individual Organ Doses --mrem From Liquid Release Period: Oct-Dec 2016 Age Class Organ Dose -mrem | * 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 Organ Bone Gl-LLI Kidney Liver LunQ Table 4.3-B Maximum Individual Organ Doses --mrem From Liquid Release Period: Apr-Jun 2016 Age Class Organ Dose -mrem Adult Teen Child 1.95E-07 2.97E-07 2.59E-07 2.58E-08 1.19E-07 2.58E-08 1.02E-07 1.98E-07 9.78E-08 2.59E-07 3.57E-07 2.49E-07 4.80E-08 1.48E-07 5.08E-08 Thyroid 2.11E-08 1.16E-07 2.44E-08 T.Body 1.77E-07 2.00E-07 5.76E-08 Page 30 Organ Bone Gl-LLI Kidney Liver Lung Table 4.3-C Maximum Individual Organ Doses --mrem From Liquid Release Period: Jul-Sep 2016 Age Class Organ Dose -mrem Adult Teen Child 5.64E-08 8.60E-08 7.52E-08 8.24E-09 3.51E-08 7.98E-09 3.03E-08 5.79E-08 2.88E-08 7.59E-08 1.04E-07 7.28E-08 1.47E-08 4.34E-08 1.52E-08 Thyroid 6.90E-09 3.41 E-08 7.57E-09 T.Body 5.21 E-08 5.85E-08 1.72E-08 Page 31 Table 4.3-D Maximum Individual Organ Doses --mrem From Liquid Release Period: Oct-Dec 2016 Age Class Organ Dose -mrem | |||
* Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidney N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A | * Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidney N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A | ||
* 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 2016 Age Class Organ Dose -mrem | * 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 2016 Age Class Organ Dose -mrem | |||
* Organ Adult Teen Child Bone 2.50E-07 3.81E-07 3.33E-07 Gl-LLI 3.39E-08 1.54E-07 3.37E-08 Kidney 1.32E-07 2.55E-07 1.26E-07 Liver 3.34E-07 4.60E-07 3.21E-07 Lu no 6.25E-08 1.90E-07 6.58E-08 Thyroid 2.BOE-08 1.49E-07 3.19E-08 T.Bodv 2.28E-07 2.57E-07 7.46E-08 | * Organ Adult Teen Child Bone 2.50E-07 3.81E-07 3.33E-07 Gl-LLI 3.39E-08 1.54E-07 3.37E-08 Kidney 1.32E-07 2.55E-07 1.26E-07 Liver 3.34E-07 4.60E-07 3.21E-07 Lu no 6.25E-08 1.90E-07 6.58E-08 Thyroid 2.BOE-08 1.49E-07 3.19E-08 T.Bodv 2.28E-07 2.57E-07 7.46E-08 | ||
* These doses are conservative since the same usage factor was applied for each quarter. In reality, it is unlikely that anyone would be swimming or boating during the entire year. However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose. Page 33 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure. However, Regulatory Guide 1.21 (Reference 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man. Thermoluminescent dosimeters (TLDs) are located at 86 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 c;tt 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 (l&S Building), was 204 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 74.8 +/- 26.2 mR/yr to 62.6 +/- 8.0 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.1 +/- 8.3 mR/yr, and is indicative of natural background radiation. Although the annual exposure at TLD location OA was 144 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 0.66 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 61.6 +/- 3.6 mR (based on continuous occupancy at this location), which compares quite well to the Zone 4 annual average background radiation level of 60.1 +/- 8.3 mR. Statistically, there is no difference between these two values. Page 34 Pilgrim Station began moving spent fuel to the Independent Spent Fuel Storage Installation (ISFSI) located within the protected area immediately west of the PNPS Reactor Building. Three new TLDs were installed at the beginning of 2016 to monitor any incremental dose from this facility. TLD ISF-1 was located on Rocky Hill Road 0.35 km (0.21 mi) southwest of the reactor building. The annual exposure at this location was calculated as being 76. 7 +/- 4.0 mR (based on continuous occupancy at this location), or 16.6 mR above the Zone 4 average of 60.1 mR. However, the area is not continuously occupied, and when corrected for an exposure time of 365 hours/year, the estimated exposure to a person walking along this section of Rocky Hill Road would be 0.69 mR/year. It must be emphasized that the projected ambient exposures discussed above and 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 1 OCFR20.1301, 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 (l&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 2016 is estimated as being about 1.6 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 2016. 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 0.0016 mrem, resulting from inhalation. Agairi, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy. Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR190. This regulation explicitly 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 0. 7 mrem/year. Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2016 AveraQe Exposure +/- Standard Deviation: mR/ Jeriod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 18.2 +/- 6.7 14.2 +/- 2.0 13.6 +/- 1.6 14.3 +/- 2.3 Apr-Jun 19.6 +/- 7.0 15.0 +/- 2.0 14.5+/-1.5 15.7+/-2.0 Jul-Sep 19.3+/-6.1 15.0 +/- 1.9 14.7+/-1.6 15.7 +/- 1.9 Oct-Dec 17.6 +/- 6.3 13.3 +/- 1.8 13.2 +/- 1.4 14.3 +/- 2.1 Jan-Dec 74.8 +/- 26.2** 57.6 +/- 8.0 55.9 +/- 6.3 60.1+/-8.3 | * These doses are conservative since the same usage factor was applied for each quarter. | ||
* 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 62.6 +/- 8.0 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 2016 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 2016 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 9.26E-07 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 2.31E-06 C. Instantaneous Dose Rate Limit -Particulates, Iodines, & Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 D. Quarterly Dose Objective -Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective: 5 mrad Gamma Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value-mrad O.OOE+OO 2.83E-07 4.99E-07 6.09E-07 E. Annual Dose Objective -Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: 10 mrad Gamma Air Dose Period Jan-Dec Value -mrad/yr 1.39E-06 Page 38 Fraction of Limit 1.85E-07% Fraction of Limit 7.71E-08% Fraction of Limit 5.16E-03% Fraction of Limit O.OOE+OO% 5.66E-06% 9.98E-06% 1.22E-05% Fraction of Limit 1.39E-05% | 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. | ||
Table 6.1 (continued) Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 F. Quarterly Dose Objective -Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: 10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrad O.OOE+OO 3.38E-07 5.96E-07 7.28E-07 G. Annual Dose Objective -Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: 20 mrad Beta Air Dose Period Jan-Dec Value -mrad/yr 1.66E-06 Fraction of Limit O.OOE+OO% 3.38E-06% 5.96E-06% 7.28E-06% Fraction of Limit 8.31E-06% H. Quarterly Dose Objective -Particulates, Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective: 7 .5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.01 E-02 2.09E-02 1.71 E-02 1.93E-02 Fraction of Limit 2.68E-01% 2.78E-01% 2.29E-01% 2.57E-01% I. Annual Dose Objective -Particulates, Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: 15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 Page 39 Fraction of Limit 5.16E-01% | : However, Regulatory Guide 1.21 (Reference | ||
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 2016 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1 OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 4.10E-14 1.19E-14 N/A 1.32E-14 B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.0E-03 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 3.26E-12 6.30E-12 N/A 2.40E-12 C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.0E-04 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO Page 41 Fraction of Limit N/A 4.10E-06% 1.19E-06% N/A 1.32E-06% Fraction of Limit N/A 3.26E-07% 6.30E-07% N/A 2.40E-07% Fraction of Limit N/A O.OOE+00% O.OOE+00% N/A O.OOE+00% | : 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man. Thermoluminescent dosimeters (TLDs) are located at 86 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. | ||
Table 6.2 (continued) Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: 1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec E. Annual Total Body Dose Objective Value -mrem N/A 2.00E-07 5.85E-08 N/A PNPS ODCM Control 3.2.2.b Objective: 3 mrem Total Body Dose Period Jan-Dec F. Quarterly Organ Dose Objective Value -mrem 2.57E-07 PNPS ODCM Control 3.2.2.a Objective: 5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec G. Annual Organ Dose Objective Value -mrem N/A 3.57E-07 1.04E-07 N/A PNPS ODCM Control 3.2.2.b Objective: 10 mrem Organ Dose Period Jan-Dec Value -mrem 4.60E-07 Page 42 Fraction of Limit N/A 1.33E-05% 3.90E-06% N/A Fraction of Limit 8.58E-06% Fraction of Limit N/A 7.14E-06% 2.08E-06% N/A Fraction of Limit 4.60E-06% | 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 | ||
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, | : exposure, TLDs will also record radiation resulting from noble gases (plume and immersion exposure), | ||
* Other. During the reporting period approximately 83.7 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 1040 Curies were shipped from PNPS for processing and disposal. Dry activated wastes and contaminated equipment shipped during the period totaled 343 cubic meters and contained 0.427 Curies of radioactivity. There were no shipments of irradiated components during the reporting period. There were no shipments of "Other wastes" during the reporting period. 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 21 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 2 shipments to Energy Solutions Erwin Resin Solutions' Facility in Erwin, TN.; and 2 shipments to Alaron Nuclear Services, Wampum, PA. Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2016 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 2016 Type of waste Volume-Curies a. Spent resins, filters, filter sludges, 8.37E+01 1.04E+03 evaporator bottoms, etc. b. Dry activated waste, contaminated 3.43E+02 4.27E-01 equipment, etc. c. Irradiated components, control rods, etc. O.OOE+OO O.OOE+OO d. Other (describe): O.OOE+OO O.OOE+OO 2. Estimate of major nuclide composition by type of waste 1 Tvoe of waste Radionuclide Abundance a. Spent resins, filters, filter sludge's, Mn-54 12.02% evaporator bottoms, etc. Fe-55 55.12% Co-60 23.82% Zn-65 5.16% Cs-137 1.97% b. Dry activated waste, contaminated Mn-54 2.36% equipment, etc. Fe-55 80.07% Co-60 14.65% Ni-63 1.87% c. Irradiated components, control rods, etc. N/A N/A d. Other (describe): Contaminated oil and water N/A N/A 7 " ,,. . . 0 . . Ma1or 1s defined as any radionuclide compnsmg > 1 % of the total activity m the waste category. 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Total Error +/-25% +/-25% N/A N/A | 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. | ||
* Total Error +/-25% +/-25% .+/-25% +/-25% +/-25% +/-25% +/-25% +/-25% +/-25% N/A N/A 21 Tractor-trailer Energy Solutions, Bear Creek Facility"' (Hittman Transport) Oak Ridge, TN 2 Tractor-trailer Energy Solutions, Erwin Resin Solutions"' (Hittman Transport) Erwin, TN 2 Tractor-trailer Alaron Nuclear Services"' (Hittman Transport) Wampum, PA L This processor provides volume reduction services for dry compressible waste, contaminated eqwpment, etc. Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal. 8. 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 2016. 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 2016 to various procedures related to the Process Control Program (PCP): EN-RW-102. "Radioactive Shipping Procedure". Rev.14: The primary purpose of this revision is to update the procedure to ensure compliance with current and upcoming changes to 49 CFR, especially those changes stemming from HM-215M and HM-250 (changes are as recommended by review of EN-RW-102 by WMG). Additionally, the issue identified in NIOS audit QA-14/15-2015-IP-01 regarding retention of DOT Spec 7A test and engineering evaluation is addressed. | 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 c;tt 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 (l&S Building), | |||
was 204 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 74.8 +/- 26.2 mR/yr to 62.6 +/- 8.0 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.1 +/- 8.3 mR/yr, and is indicative of natural background radiation. | |||
Although the annual exposure at TLD location OA was 144 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 0.66 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 61.6 +/- 3.6 mR (based on continuous occupancy at this location), | |||
which compares quite well to the Zone 4 annual average background radiation level of 60.1 +/- 8.3 mR. Statistically, there is no difference between these two values. Page 34 Pilgrim Station began moving spent fuel to the Independent Spent Fuel Storage Installation (ISFSI) located within the protected area immediately west of the PNPS Reactor Building. | |||
Three new TLDs were installed at the beginning of 2016 to monitor any incremental dose from this facility. | |||
TLD ISF-1 was located on Rocky Hill Road 0.35 km (0.21 mi) southwest of the reactor building. | |||
The annual exposure at this location was calculated as being 76. 7 +/- 4.0 mR (based on continuous occupancy at this location), | |||
or 16.6 mR above the Zone 4 average of 60.1 mR. However, the area is not continuously | |||
: occupied, and when corrected for an exposure time of 365 hours/year, the estimated exposure to a person walking along this section of Rocky Hill Road would be 0.69 mR/year. | |||
It must be emphasized that the projected ambient exposures discussed above and 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 1 OCFR20.1301, 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 (l&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 2016 is estimated as being about 1.6 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 2016. 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 0.0016 mrem, resulting from inhalation. | |||
Agairi, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy. | |||
Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR190. | |||
This regulation explicitly 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 0. 7 mrem/year. | |||
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2016 AveraQe Exposure | |||
+/- Standard Deviation: | |||
mR/ Jeriod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 18.2 +/- 6.7 14.2 +/- 2.0 13.6 +/- 1.6 14.3 +/- 2.3 Apr-Jun 19.6 +/- 7.0 15.0 +/- 2.0 14.5+/-1.5 15.7+/-2.0 Jul-Sep 19.3+/-6.1 15.0 +/- 1.9 14.7+/-1.6 15.7 +/- 1.9 Oct-Dec 17.6 +/- 6.3 13.3 +/- 1.8 13.2 +/- 1.4 14.3 +/- 2.1 Jan-Dec 74.8 +/- 26.2** 57.6 +/- 8.0 55.9 +/- 6.3 60.1+/-8.3 | |||
* Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary. | |||
** When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated. | |||
to be 62.6 +/- 8.0 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 2016 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 2016 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 9.26E-07 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 2.31E-06 C. Instantaneous Dose Rate Limit -Particulates, | |||
: Iodines, | |||
& Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 D. Quarterly Dose Objective | |||
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective: | |||
5 mrad Gamma Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value-mrad O.OOE+OO 2.83E-07 4.99E-07 6.09E-07 E. Annual Dose Objective | |||
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective: | |||
10 mrad Gamma Air Dose Period Jan-Dec Value -mrad/yr 1.39E-06 Page 38 Fraction of Limit 1.85E-07% | |||
Fraction of Limit 7.71E-08% | |||
Fraction of Limit 5.16E-03% | |||
Fraction of Limit O.OOE+OO% | |||
5.66E-06% | |||
9.98E-06% | |||
1.22E-05% | |||
Fraction of Limit 1.39E-05% | |||
Table 6.1 (continued) | |||
Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 F. Quarterly Dose Objective | |||
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective: | |||
10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrad O.OOE+OO 3.38E-07 5.96E-07 7.28E-07 G. Annual Dose Objective | |||
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective: | |||
20 mrad Beta Air Dose Period Jan-Dec Value -mrad/yr 1.66E-06 Fraction of Limit O.OOE+OO% | |||
3.38E-06% | |||
5.96E-06% | |||
7.28E-06% | |||
Fraction of Limit 8.31E-06% | |||
H. Quarterly Dose Objective | |||
-Particulates, | |||
: Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.a Objective: | |||
7 .5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.01 E-02 2.09E-02 1.71 E-02 1.93E-02 Fraction of Limit 2.68E-01% | |||
2.78E-01% | |||
2.29E-01% | |||
2.57E-01% | |||
I. Annual Dose Objective | |||
-Particulates, | |||
: Iodines, Tritium, and Carbon-14 PNPS ODCM Control 3.3.3.b Objective: | |||
15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 Page 39 Fraction of Limit 5.16E-01% | |||
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 2016 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1 OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 4.10E-14 1.19E-14 N/A 1.32E-14 B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.0E-03 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 3.26E-12 6.30E-12 N/A 2.40E-12 C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.0E-04 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO Page 41 Fraction of Limit N/A 4.10E-06% | |||
1.19E-06% | |||
N/A 1.32E-06% | |||
Fraction of Limit N/A 3.26E-07% | |||
6.30E-07% | |||
N/A 2.40E-07% | |||
Fraction of Limit N/A O.OOE+00% | |||
O.OOE+00% | |||
N/A O.OOE+00% | |||
Table 6.2 (continued) | |||
Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective: | |||
1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec E. Annual Total Body Dose Objective Value -mrem N/A 2.00E-07 5.85E-08 N/A PNPS ODCM Control 3.2.2.b Objective: | |||
3 mrem Total Body Dose Period Jan-Dec F. Quarterly Organ Dose Objective Value -mrem 2.57E-07 PNPS ODCM Control 3.2.2.a Objective: | |||
5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec G. Annual Organ Dose Objective Value -mrem N/A 3.57E-07 1.04E-07 N/A PNPS ODCM Control 3.2.2.b Objective: | |||
10 mrem Organ Dose Period Jan-Dec Value -mrem 4.60E-07 Page 42 Fraction of Limit N/A 1.33E-05% | |||
3.90E-06% | |||
N/A Fraction of Limit 8.58E-06% | |||
Fraction of Limit N/A 7.14E-06% | |||
2.08E-06% | |||
N/A Fraction of Limit 4.60E-06% | |||
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 83.7 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 1040 Curies were shipped from PNPS for processing and disposal. | |||
Dry activated wastes and contaminated equipment shipped during the period totaled 343 cubic meters and contained 0.427 Curies of radioactivity. | |||
There were no shipments of irradiated components during the reporting period. There were no shipments of "Other wastes" during the reporting period. 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 21 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 2 shipments to Energy Solutions Erwin Resin Solutions' Facility in Erwin, TN.; and 2 shipments to Alaron Nuclear Services, Wampum, PA. Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2016 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 2016 Type of waste Volume-Curies a. Spent resins, filters, filter sludges, 8.37E+01 1.04E+03 evaporator | |||
: bottoms, etc. b. Dry activated waste, contaminated 3.43E+02 4.27E-01 equipment, etc. c. Irradiated components, control rods, etc. O.OOE+OO O.OOE+OO | |||
: d. Other (describe): | |||
O.OOE+OO O.OOE+OO | |||
: 2. Estimate of major nuclide composition by type of waste 1 Tvoe of waste Radionuclide Abundance | |||
: a. Spent resins, filters, filter sludge's, Mn-54 12.02% evaporator | |||
: bottoms, etc. Fe-55 55.12% Co-60 23.82% Zn-65 5.16% Cs-137 1.97% b. Dry activated waste, contaminated Mn-54 2.36% equipment, etc. Fe-55 80.07% Co-60 14.65% Ni-63 1.87% c. Irradiated components, control rods, etc. N/A N/A d. Other (describe): | |||
Contaminated oil and water N/A N/A 7 " ,,. . . 0 . . Ma1or 1s defined as any radionuclide compnsmg | |||
> 1 % of the total activity m the waste category. | |||
: 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Total Error +/-25% +/-25% N/A N/A | |||
* Total Error +/-25% +/-25% .+/-25% +/-25% +/-25% +/-25% +/-25% +/-25% +/-25% N/A N/A 21 Tractor-trailer Energy Solutions, Bear Creek Facility"' | |||
(Hittman Transport) | |||
Oak Ridge, TN 2 Tractor-trailer Energy Solutions, Erwin Resin Solutions"' | |||
(Hittman Transport) | |||
Erwin, TN 2 Tractor-trailer Alaron Nuclear Services"' | |||
(Hittman Transport) | |||
Wampum, PA L This processor provides volume reduction services for dry compressible waste, contaminated | |||
: eqwpment, etc. Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal. | |||
: 8. 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 2016. 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 2016 to various procedures related to the Process Control Program (PCP): EN-RW-102. | |||
"Radioactive Shipping Procedure". | |||
Rev.14: The primary purpose of this revision is to update the procedure to ensure compliance with current and upcoming changes to 49 CFR, especially those changes stemming from HM-215M and HM-250 (changes are as recommended by review of EN-RW-102 by WMG). Additionally, the issue identified in NIOS audit QA-14/15-2015-IP-01 regarding retention of DOT Spec 7A test and engineering evaluation is addressed. | |||
* Added a bullet item to step 7.0[2] specifying that shipment records are to include documentation of tests and engineering evaluations for DOT Spec 7 A packages it Step 2.0[1 O]: Corrected reference to WMG software packages | * Added a bullet item to step 7.0[2] specifying that shipment records are to include documentation of tests and engineering evaluations for DOT Spec 7 A packages it Step 2.0[1 O]: Corrected reference to WMG software packages | ||
* Step 5.1 [12]: replaced specific shipping names with generic statement regarding Marking and Labeling | * Step 5.1 [12]: replaced specific shipping names with generic statement regarding Marking and Labeling | ||
* Step 5.2[11](c), Attachment 9.10: Updated terminology for Industrial Package | * Step 5.2[11](c), | ||
* Step 5.2[11](c): Added requirement to cover Specification Marking | Attachment 9.10: Updated terminology for Industrial Package | ||
* Step 5.2[16]: Added reference for requirements for multiple hazard radioactive material | * Step 5.2[11](c): | ||
* Step 5.2[19]: Revised step to indicate that the survey only releases the vehicle back to exclusive use service * | Added requirement to cover Specification Marking | ||
* Step 5.2[16]: | |||
Added reference for requirements for multiple hazard radioactive material | |||
* Step 5.2[19]: | |||
Revised step to indicate that the survey only releases the vehicle back to exclusive use service * | |||
* Added step 5.2[20] for unconditional release of formerly exclusive use vehicle. | * Added step 5.2[20] for unconditional release of formerly exclusive use vehicle. | ||
* Step 7.0[1]: Added an additional reference for record retention | * Step 7.0[1]: Added an additional reference for record retention | ||
Line 100: | Line 481: | ||
* Add a requirement for contacting ANI | * Add a requirement for contacting ANI | ||
* Added step 2.0[20] for reference to NUREG-2155 (which is the basis for preplanning documentation requirements) | * Added step 2.0[20] for reference to NUREG-2155 (which is the basis for preplanning documentation requirements) | ||
* Step 3.0[1] added: ANI (American Nuclear Insurers), MCC-Movement Control Center, SAS -Secondary Alarm Station | * Step 3.0[1] added: ANI (American Nuclear Insurers), | ||
MCC-Movement Control Center, SAS -Secondary Alarm Station | |||
* Step 5.3[4]: corrected step reference | * Step 5.3[4]: corrected step reference | ||
* Step 5.7.4.1[3]: corrected the NRC email address | * Step 5.7.4.1[3]: | ||
* Added steps 5.7.5.2[8] and 5.7.5.3[7] for ANI notification in the event of an accident. | corrected the NRC email address | ||
* Added steps 5.7.5.2[8] | |||
and 5.7.5.3[7] | |||
for ANI notification in the event of an accident. | |||
* Step 5. 7 .6.1 [2]: expanded requirements for documentation of preplanning activities | * Step 5. 7 .6.1 [2]: expanded requirements for documentation of preplanning activities | ||
* Step 5.8[2] is reworded for clarity EN-RW-108, "Radioactive Shipment Accident Response". Rev.2: The primary purpose of this revision is to add instruction for contacting ANI in the event of an accident covered by this procedure. Specifically: | * Step 5.8[2] is reworded for clarity EN-RW-108, "Radioactive Shipment Accident Response". | ||
* ANI is added to the definitions section, section 3.0 | Rev.2: The primary purpose of this revision is to add instruction for contacting ANI in the event of an accident covered by this procedure. | ||
* Step 5.4[1] is expanded to address contacting ANI This is a complete rewrite of the procedure in order to align the procedure format with EN-AD-101-01. Content changes are made only to correct grammatical errors or to change step levels to correct formatting and are editorial. No change bars are used to reflect the changes made due to the rewrite. Changes worth noting are: | Specifically: | ||
* ANI is added to the definitions | |||
: section, section 3.0 | |||
* Step 5.4[1] is expanded to address contacting ANI This is a complete rewrite of the procedure in order to align the procedure format with EN-AD-101- | |||
: 01. Content changes are made only to correct grammatical errors or to change step levels to correct formatting and are editorial. | |||
No change bars are used to reflect the changes made due to the rewrite. | |||
Changes worth noting are: | |||
* Sections 5.1 and 5.2 are reversed in order for alignment with EN-AD-101-01 | * Sections 5.1 and 5.2 are reversed in order for alignment with EN-AD-101-01 | ||
* Section 5.3.2: "CAUTION" is changed to "NOTE" in the box associated with ion chambers versus GM instruments as the associated statement does not qualify as a caution statement. | * Section 5.3.2: "CAUTION" is changed to "NOTE" in the box associated with ion chambers versus GM instruments as the associated statement does not qualify as a caution statement. | ||
Line 116: | Line 507: | ||
==10.0 REFERENCES== | ==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", | |||
* Page 75}} | * Page 75}} |
Revision as of 20:13, 29 June 2018
ML17142A066 | |
Person / Time | |
---|---|
Site: | Pilgrim |
Issue date: | 05/12/2017 |
From: | Perkins E P, Sejkora K J Entergy Nuclear Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
2.17.033 | |
Download: ML17142A066 (78) | |
Text
May 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360
SUBJECT:
Annual Radioactive Effluent Release Report for January 1 through December 31, 2016 Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.17.033
Dear Sir or Madam:
In accordance with Pilgrim Nuclear Power Station Technical Specification 5.6.3, Entergy Nuclear Operations, Inc. submits the attached Annual Radioactive Effluent Release Report for January 1 through December 31, 2016. If you have any questions or require additional information, please contact me at (508) 830-8323. There are no regulatory commitments contained in this letter. Sincerely, k, Everett P. Perkins, Jr. Manager, Regulatory Assuranc EPP/rb
Attachment:
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Mr. John Lamb, Senior Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 8 B1A Washington, DC 20555 Mr. John Giarrusso, Jr. Planning, Preparedness
& Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Letter No. 2.17.033 Page 2 of 2 Attachment Letter Number 2.17.033 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, 2016 *
- PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 Prepared by:
K.J. Sejkora Senior HP/Chemistry Specialist Reviewed by: 2B--&ftl'1/-;(CJl7 G. . Blankenbiller Chemistry Manager Reviewed by:
_Z_o_f_l_ Radiation Protection Manager Page2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report January-December 2016 TABLE OF CONTENTS SECTION SECTION TITLE PAGE 1.0 EXECUTIVE SUMMARY 5 2.0 RADIOACTIVE EFFLUENT DATA 8 2.1 Supplemental Effluent Release Data 8 2.2 Gaseous Effluent Data 8 2.3 Liquid Effluent Data 9 3.0 METEOROLOGICAL DATA 19 4.0 MAXIMUM INDIVIDUAL DOSES 20 4.1 Doses From Noble Gas Releases 20 4.2 Doses From Gaseous Effluent Releases 22 4.3 Doses From Liquid Effluent Releases 28 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS 34 6.0 PERCENT OF ODCM EFFLUENT CONTROL LIMITS 37 6.1 Gaseous Effluent Releases 37 6.2 Liquid Effluent Releases 40 7.0 RADIOACTIVE WASTE DISPOSAL DATA 43 8.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS 45 9.0 PROCESS CONTROL PROGRAM REVISIONS 46
10.0 REFERENCES
48 APPENDIX A Meteorological Joint Frequency Distributions 49 APPENDIX B Onsite Groundwater Monitoring Program 70 APPENDIX C Corrections to Previous Effluent Reports 74 APPENDIX D Changes to PNPS Offsite Dose Calculation Manual 75 Page 3 TABLE 2.1 2.2-A 2.2-B 2.2-C 2.3-A 2.3-B 4.1 4.2-A 4.2-B 4.2-C 4.2-D 4.2-E 4.3-A 4.3-B 4.3-C 4.3-D 4.3-E 5.0 6.1 6.2 7.0 A-1 A-2 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Jan-Dec 2016 LIST OF TABLES TABLE TITLE Supplemental Information Gaseous Effluents
-Summation of All Releases Gaseous Effluents
-Elevated Releases Gaseous Effluents
-Ground Level Releases Liquid Effluents
-Summation of All Releases Liquid Effluents Maximum Doses from Noble Gas Releases During 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Gaseous Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Gaseous Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Gaseous Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Gaseous Effluents Jan-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Mar 2016 Maximum Individual Organ Doses from Liquid Effluents Apr-Jun 2016 Maximum Individual Organ Doses from Liquid Effluents Jul-Sep 2016 Maximum Individual Organ Doses from Liquid Effluents Oct-Dec 2016 Maximum Individual Organ Doses from Liquid Effluents Jan-Dec 2016 Average TLD Exposures by Distance Zone During 2016 Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 Solid Waste and Irradiated Fuel Shipments Joint Frequency Distribution of Wind Directions and Speeds for the 33-ft Level of the 220-ft Tower Joint Frequency Distribution of Wind Directions and Speeds for the 220-ft Level of the 220-ft Tower Page4 PAGE 10 11 12 14 16 17 21 23 24 25 26 27 29 30 31 32 33 36 38 41 44 50 60 INTRODUCTION EXECUTIVE SUMMARY PILGRIM NUCLEAR POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 01 THROUGH DECEMBER 31, 2016 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, 2016. 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 be.en prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.3. The quantity of radioactive material released from PNPS was determined from sample analyses and continuous on-line monitoring of gaseous releases from the main stack, reactor building vent, turbine building, and various decontamination facilities, and liquid releases into the discharge canal. The quantity and volume of radioactive waste shipped offsite from PNPS for processing and burial were determined from data contained on the radwaste shipping documentation.
The meteorological data were obtained from monitoring instruments located on the 220-foot meteorological tower located at Pilgrim Station.
GASEOUS EFFLUENTS Gaseous radioactive releases for the reporting period are quantified in Tables 2.2-A, 2.2-B, and 2.2-C. Radioactive noble gases released during the period totaled 0.20 Curies. Releases of radioactive iodines and particulates with half-life of greater than 8 days totaled 0.0020 Curies, tritium releases totaled 64 Curies, and carbon-14 totaled 7.8 Curies. No gross alpha radioactivity was detected in gaseous effluents.
Noble gases released in gaseous effluents resulted in a maximum total body dose of 0.00000093 mrem, with a corresponding skin dose of 0.0000023 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 0.017 mrem. The maximum hypothetical dose to any organ from radioactive particulates,
- iodines, tritium, and carbon-14 was about 0.077 mrem. The maximum, hypothetical total body dose from the combined release of all airborne radioactivity in gaseous effluents was 0.017 mrem. The maximum individual doses from gaseous radioactive effluents were compared to the applicable ODCM dose limits. Noble gas doses were less than 0.000014%
of the corresponding 1 OCFR50 dose objectives.
Maximum doses resulting from releases of particulates,
- iodines, tritium, and carbon-14 in gaseous effluents were less than 0.52% of corresponding 1 OCFR50 objectives.
Page 5 LIQUID EFFLUENTS Liquid radioactive releases for the reporting period are quantified in Tables 2.3-A and 2.3-B. Two discharges of liquid containing radioactivity occurred during the reporting period. These discharges contained 0.0015 Curies of tritium, and 0.0000081 Curies of fission and activation products.
The resulting maximum total body dose was 0.00000026 mrem, with a corresponding organ dose of 0.00000046 mrem. All doses from liquid discharges were less than 0.000014%
of corresponding 1 OCFR50 objectives.
METEOROLOGICAL DATA Meteorological joint frequency distributions are listed in Appendix A. Data recovery for the entire annual period was 96% for the 33-ft and 96% for the 220-ft levels of the tower. The predominant wind direction was from the south-southwest, which occurred approximately 14% of the time during the reporting period. The predominant stability class was Class D, which occurred about 41 % 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 1.6 mrem during 2016. There was no measurable increase during 2016 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 2016 was calculated as being about 0.77 mrem. This amount is about 0.12% of the typical dose of 620 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 427 cubic meters of solid waste, containing 1040 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 2016, 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 related radioactivity was detected in the groundwater samples.
The average concentration of tritium detected in these onsite monitoring wells during 2016 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 0.0000000055 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 2016, 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, 18, 1C, 2A, 2B, and Supplemental Information table from NRC Regulatory Guide 1.21 (Reference
- 1) format. 2.1 Supplemental Effluent Release Data Supplemental information related to radioactive gaseous and liquid releases for the reporting period are given in the standard NRC Regulatory Guide 1.21 format in Table 2.1. 2.2 Gaseous Effluent Data Gaseous radioactivity is released from Pilgrim Station to the atmosphere from the main stack, reactor building vent, turbine building, and various decontamination facilities.
Combined gaseous effluent releases from all release points are summarized in Table 2.2-A. No alpha activity was detected on any of the particulate filters collected during the reporting period. The total gaseous releases for various categories of radionuclides, as well as the corresponding average release rates, can be summarized as follows:
- Noble gases: 0.195 Ci, 0.00617 µCi/sec
- Iodines and particulates with 0.0020 Ci, 0.0000633
µCi/sec half-life greater than 8 days
- Tritium:
66.9 Ci, 2.12 µCi/sec
- Carbon-14:
7.82 Ci, 0.248 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 1 OCFR50 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 2016 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 2016, the Turbine Building Gaseous Effluent Monitor (C-3003) was out of service for 42-days from 12-Feb-2016 to 25-Mar-2016 due to a failure of the sample pump and flow controller circuitry.
The Feed Pump Gaseous Effluent Monitor (C-3004) was out of service for 238-days from 07-May-2016 to 31-Dec-2016 due to a failure of the detector and flow controller circuitry.
Both of these monitors are subject to obsolescence issues and it was difficult to obtain replacement parts necessary to perform repairs.
In both of these situations compensatory sampling was performed by collecting noble gas samples twice per week. There were no instances in 2016 when both channels of a dual-channel effluent monitor (Main Stack, Reactor Building Vent) were out of service at the same time during a 30 consecutive day period. 2.3 Liquid Effluent Data Liquid radioactivity is released from PNPS to Cape Cod Bay via the circulating water discharge canal. These effluents enter Cape Cod Bay at the outfall of the canal, which is located about 1100 feet north of the reactor building.
Liquid effluent releases are summarized in Table 2.3-A. Detailed breakdowns for individual radionuclides are listed in Table 2.3-B. There were two discharges of liquid effluents containing radioactivity during the reporting period. Total releases for the various categories of radionuclides, as well as their corresponding mean concentrations, can be summarized as follows:
- Total Effluent Volume: 73,600 Liters
- Total Dilution Volume: 612 billion Liters
- Fission/Activation products:
0.00000806 Ci, 0.0000000000000132
µCi/ml
- Tritium:
0.00147 Ci, 0.00000000000240
µCi/ml
- Dissolved/entrained noble gases: 0.00 Ci, 0.00 µCi/ml Page 9 Table 2.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2016 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. Iodines, particulates with half-life:
1500 mrem/yr to any organ at site boundary
>8 davs, 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 Aooendix B Table II b. Iodines:
10CFR20 Aooendix B Table II c. Particulates with half-life > 8 davs: 10CFR20 Aooendix B Table II d. Liquid effluents:
2E-04 µCi/ml for entrained noble gases; 10CFR20 Appendix B Table II values for all other radionuclides
- 3. AVERAGE ENERGY Not Applicable
- 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY
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 2016 2016 2016 2016 2016 a. Liquid Effluents
- 1. Total number of releases:
N/A 1.00E+OO 1.00E+OO N/A 2.00E+OO
- 2. Total time period (minutes):
N/A 8.70E+02 9.60E+02 N/A 1.83E+03
- 3. Maximum time period N/A 8.70E+02 9.60E+02 N/A 9.60E+02 (minutes):
- 4. Average time period (minutes):
N/A 8.70E+02 9.60E+02 N/A 9.15E+02
- 5. Minimum time period (minutes):
N/A 8.70E+02 9.60E+02 N/A 8.70E+02
- 6. Average stream flow during periods of release of N/A 1.19E+06 1.19E+06 N/A 1.19E+06 effluents into a flowing stream (Liters/min):
- 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 2016 RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATION GASES Total Release:
Ci O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Average Release Rate: µCi/sec O.OOE+OO 5.02E-03 8.85E-03 1.08E-02 Percent of Effluent Control Limit* * * *
- B. IODINE-131 Total lodine-131 Release:
Ci 1.04E-04 1.06E-04 9.75E-05 1.01E-04 Averaqe Release Rate: µCi/sec 1.32E-05 1.34E-05 1.24E-05 1.28E-05 Percent of Effluent Control Limit* * * *
- C. PARTICULATES WITH HALF-LIVES
> 8 DAYS Total Release:
Ci 7.19E-06 3.51E-05 5.88E-05 5.46E-05 Averaqe Release Rate: µCi/sec 9.12E-07 4.45E-06 7.45E-06 6.92E-06 Percent of Effluent Control Limit* * * *
- Gross Aloha Radioactivity:
Ci NDA NOA NDA NOA D. TRITIUM Total Release:
Ci 1.62E+01 1.76E+01 1.52E+01 1.51 E+01 Average Release Rate: µCi/sec 2.06E+OO 2.23E+OO 1.92E+OO 1.91E+OO Percent of Effluent Control Limit* * * *
- E. CARBON-14 Total Release:
Ci 2.03E+OO 2.11E+OO 1.73E+OO 1.95E+OO Average Release Rate: µCi/sec 2.58E-01 2.68E-01 2.20E-01 2.47E-01 Percent of Effluent Control Limit* * * *
- Notes for Table 2.2-A: Est. Jan-Dec Total 2016 Error 1.95E-01 6.17E-03
+/-22%
- 4.09E-04 1.30E-05
+/-20%
- 1.56E-04 4.94E-06
+/-21%
- NOA 6.41E+01 2.03E+OO
+/-20%
- 7.82E+OO 2.48E-01 N/A *
- Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report. 1. NOA stands for No Detectable Activity.
- 2. LLD for airborne gross alpha activity listed as NDA is 1 E-11 µCi/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 2016 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO 3.96E-02 6.98E-02 8.52E-02 Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE:roo O.OOE+OO O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO 3.96E-02 6.98E-02 8.52E-02
- 2. IODINES:
Ci 1-131 1.29E-06 2.99E-07 6.05E-06 1.29E-06 1-133 1.63E-06 O.OOE+OO 6.24E-06 O.OOE+OO Total for Period 2.92E-06 2.99E-07 1.23E-05 1.29E-06
- 3. PARTICULATES WITH HALF-LIVES>
8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 O.OOE+OO O.OOE+OO 7.08E-07 O.OOE+OO Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 O.OOE+OO O.OOE+OO 1.81 E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO 1.06E-06 O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for Period O.OOE+OO O.OOE+OO 3.58E-06 O.OOE+OO
- 4. TRITIUM:
Ci H-3 2.52E-02 5.02E-02 6.16E-02 4.91E-02
- 5. CARBON-14:
Ci C-14 1.97E+OO 2.05E+OO 1.68E+OO 1.89E+OO Notes for Table 2.2-B: 1. N/A stands for not applicable.
- 2. NOA stands for No Detectable Activity.
Fission Gases: 1 E-04 µCi/cc Iodines:
1 E-12 Particulates:
1 E-11 µCi/cc Page 12 Jan-Dec 2016 O.OOE+OO O.OOE+OO 1.95E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.95E-01 8.93E-06 7.87E-06 1.68E-05 O.OOE+OO 7.08E-07 O.OOE+OO O.OOE+OO 1.81 E-06 1.06E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.58E-06 1.86E-01 7.58E+OO Table 2.2-B (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Elevated Release January-December 2016 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES:
Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period 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 Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM:
Ci H-3 N/A N/A N/A N/A 5. CARBON-14:
Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-B: 1. N/A stands for not applicable.
- 2. NOA stands for No Detectable Activity.
Fission Gases: 1 E-04 µCi/cc Iodines:
1 E-12 µCi/cc Particulates:
1 E-11 µCi/cc Page 13 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Ground-Level Release January-December 2016 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-85m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-87 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Kr-88 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-131m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-133 O.OOE+OO O.OOE+OO O.OOE+OO
. O.OOE+OO Xe-133m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-135m O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Xe-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2. IODINES:
Ci 1-131 1.03E-04 1.06E-04 9.15E-05 9.99E-05 1-133 3.24E-04 3.77E-04 3.52E-04 3.51 E-04 Total for period 4.27E-04 4.83E-04 4.43E-04 4.51E-04
- 3. PARTICULATES WITH HALF-LIVES>
8 DAYS: Ci Cr-51 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Mn-54 4.23E-06 O.OOE+OO 2.02E-05 4.13E-05 Fe-59 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-58 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Co-60 2.96E-06 O.OOE+OO 8.53E-06 O.OOE+OO Zn-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 O.OOE+OO O.OOE+OO 1.41E-05 1.33E-05 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cs-137 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba/La-140 O.OOE+OO 3.51E-05 1.24E-05 O.OOE+OO Total for period 7.19E-06 3.51E-05 5.52E-05 5.46E-05
- 4. TRITIUM:
Ci H-3 1.62E+01 1.76E+01 1.51 E+01 1.50E+01
- 5. CARBON-14:
Ci C-14 6.09E-02 6.33E-02 5.20E-02 5.83E-02 Notes for Table 2.2-C: 1. N/A stands for not applicable.
- 2. NOA stands for No Detectable Activity.
Fission Gases: 1 E-04 µCi/cc Iodines:
1E-12 µCi/cc Particulates:
1 E-11 µCi/cc Page 14 Jan-Dec 2016 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-04 1.40E-03 1.BOE-03 O.OOE+OO 6.57E-05 O.OOE+OO O.OOE+OO 1.15E-05 O.OOE+OO 2.73E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.75E-05 1.52E-04 6.39E+01 2.34E-01 Table 2.2-C (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents
-Ground-Level Release January-December 2016 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 Oct-Dec 2016 1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 2. IODINES:
Ci 1-131 N/A N/A N/A N/A 1-133 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 3. PARTICULATES WITH HALF-LIVES>
B DAYS: Ci Cr-51 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A Total for period N/A N/A N/A N/A 4. TRITIUM:
Ci H-3 N/A N/A N/A N/A 5. CARBON-14:
Ci C-14 N/A N/A N/A N/A Notes for Table 2.2-C: 1. N/A stands for not applicable.
- 2. NOA stands for No Detectable Activity.
Fission Gases: 1 E-04 µCi/cc Iodines:
Particulates:
1 E-11 µCi/cc Page 15 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents
-Summation of All Releases January-December 2016
- RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec 2016 2016 2016 2016 A. FISSION AND ACTIVATIOl'J PRODUCTS Total Release (not including N/A 6.23E-06 1.83E-06 N/A tritium, Qases, alpha): Ci Average Diluted Concentration N/A 4.10E-14 1.19E-14 N/A During Period: µCi/ml Percent of Effluent N/A 4.10E-06%
1.19E-06%
N/A Concentration Limit* B. TRITIUM Total Release:
Ci N/A 4.96E-04 9.71E-04 N/A Average Diluted Concentration N/A 3.26E-12 6.30E-12 N/A DurinQ Period: µCi/ml Percent of Effluent N/A 3.26E-07%
6.30E-07%
N/A Concentration Limit* C. DISSOLVED AND ENTRAINED GASES Total Release:
Ci N/A NDA NDA N/A Average Diluted Concentration N/A NDA NDA N/A DurinQ Period: uCi/mL Percent of Effluent N/A 0.00E+OO%
O.OOE+OO%
N/A . Concentration Limit* D. GROSS ALPHA RADIOACTIVITY Total Release:
Ci N/A NDA NDA N/A E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters O.OOE+OO 3.54E+04 3.82E+04 O.OOE+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 1.52E+11 1.54E+11 1.54E+11 Notes for Table 2.3-A: Est. Jan-Dec Total 2016 Error 8.06E-06 1.32E-14
+/-12% 1.32E-06%
1.47E-03 2.40E-12
+/-9.4% 2.40E-07%
NDA NDA +/-16% O.OOE+OO%
NDA +/-34% 7.36E+04
+/-5.7% 6.12E+11
+/-10%
- 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 1 E-05 µCi/ml. 4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 µCi/ml. Page 16 Table 2.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 1. FISSION AND ACTIVATION PRODUCTS:
Ci Cr-51 N/A N/A Mn-54 N/A N/A Fe-55 N/A N/A Fe-59 N/A N/A Co-58 N/A N/A Co-60 N/A N/A Zn-65 N/A N/A Zn-69m N/A N/A Sr-89 N/A N/A Sr-90 N/A N/A Zr/Nb-95 N/A N/A Mo/Tc-99 N/A N/A Aq-110m N/A N/A Sb-124 N/A N/A 1-131 N/A N/A 1-133 N/A N/A Cs-134 N/A N/A Cs-137 N/A N/A Ba/la-140 N/A N/A Ce-141 N/A N/A Total for period N/A N/A 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A N/A Xe-135 N/A N/A Total for period N/A N/A Notes for Table 2.3-8: 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:
1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 17 Jul-Sep 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Oct-Dec 2016 Jan-Dec 2016 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Table 2.3-8 (continued)
Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2016 BATCH MODE RELEASES Nuclide Released Jan-Mar 2016 Apr-Jun 2016 Jul-Sep 2016 1. FISSION AND ACTIVATION PRODUCTS:
Ci Na-24 N/A O.OOE+OO O.OOE+OO Cr-51 N/A O.OOE+OO O.OOE+OO Mn-54 N/A O.OOE+OO O.OOE+OO Fe-55 N/A O.OOE+OO O.OOE+OO Fe-59 N/A O.OOE+OO O.OOE+OO Co-58 N/A O.OOE+OO O.OOE+OO Co-60 N/A O.OOE+OO O.OOE+OO Zn-65 N/A O.OOE+OO O.OOE+OO Zn-69m N/A O.OOE+OO O.OOE+OO Sr-89 N/A O.OOE+OO O.OOE+OO Sr-90 N/A O.OOE+OO O.OOE+OO Zr/Nb-95 N/A O.OOE+OO O.OOE+OO Mo/Tc-99 N/A O.OOE+OO O.OOE+OO Ag-110m N/A O.OOE+OO O.OOE+OO Sb-124 N/A O.OOE+OO O.OOE+OO 1-131 N/A O.OOE+OO O.OOE+OO 1-133 N/A O.OOE+OO O.OOE+OO Cs-134 N/A O.OOE+OO O.OOE+OO Cs-137 N/A 6.23E-06 1.83E-06 8a/la-140 N/A O.OOE+OO O.OOE+OO Ce-141 N/A O.OOE+OO O.OOE+OO Ce-144 N/A O.OOE+OO O.OOE+OO Total for period N/A 6.23E-06 1.83E-06
- 2. DISSOLVED AND ENTRAINED GASES: Ci Xe-133 N/A NOA NOA Xe-135 N/A NOA NOA Total for period N/A NOA NOA Notes for Table 2.3-8: 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
- 3. llDs for liquid radionuclides listed as NOA are as follows:
Strontium:
1 E-06 µCi/ml Noble Gases: 1 E-05 µCi/ml All Others: 5E-07 µCi/ml Page 18 Oct-Dec 2016 Jan-Dec 2016 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A O.OOE+OO N/A O.OOE+OO N/A O.OOE+OO N/A 8.06E-06 N/A NOA N/A NOA N/A NOA 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, 41 %
- 33-ft Wind Direction (from): South-southwest, 14%
- 33-ft Wind Speed: 3.5-7.5 mph, 56%
- 220-ft Wind Direction (from): Southwest, 13%
- 220-ft Wind Speed: 12.5-18.5 mph, 34% Joint data recovery for the 33-ft level was 96.3% and for the 220-ft level of the tower was 96.3%, both of which meet the 90% annual data recovery goal specified by the NRC. Problems were encountered in December 2015 when the main power supply for the 220-ft tower meteorological dataloggers failed, resulting in the loss of two weeks of data at the beginning of 2016. Although a new backup 160-ft tower was constructed in late October-2015, it was not put into service until January 2016. In addition, beginning in late September 2016 and continuing through the end of the year, some anomalous delta-T readings were observed on the 220-ft tower. Wind speed and wind direction values from the 220-ft tower were not affected.
To maintain consistency with readings collected from the 220-ft tower during the remainder of the year, delta-T readings from the 160-ft tower were scaled by a factor of 1.47 to account for the difference in tower heights, and these scaled delta-T values from the 160-ft tower were substituted for the anomalous 220-ft tower readings for the affected period. 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,
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 2016 resulted in a maximum total body dose of 0.000000926 mrem. The maximum skin dose was 0.00000231 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 (0.63 km SSW of the Reactor Building).
For the more "realistic" individuals at offsite locations, the maximum total body dose was 0.000000859 mrem (nearest residence, 0.86 kilometers WNW from the Reactor Building),
while the maximum skin 'dose was 0.00000134 mrem (nearest residence, 2.39 kilometers SSW from the Reactor Building).
Page 20 Table 4.1 Maximum Doses From Noble Gas Releases During 2016(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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (0.52 km SSE) (0.64 km ESE) (0.52 km SSE) (0.54 km NW) Apr-Jun 2.83E-07 3.38E-07 1.88E-07 4.71 E-07 (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) Jul-Sep 4.99E-07 5.96E-07 3.32E-07 8.30E-07 (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) (0.64 km ESE) Oct-Dec 6.09E-07 7.28E-07 4.05E-07 1.01 E-06 (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) (0.63 km SSW) Jan-Dec 1.39E-06 1.66E-06 2.31 E-06 (0.63 km SSW) (0.64 km ESE) (0.63 km SSW) (0.63 km SSW) (al 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 2005 through 2014 were used as input to the NRC XOQDOQ computer program (Reference 7). 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 addre*ssed 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 2016 resulted in a maximum total body dose of 0.0167 mrem (child age class at nearest meat animal, 3.82 kilometers S from the Reactor Building),
while the maximum organ dose was 0.0774 mrem (child bone at nearest meat animal, 3.82 kilometers S from the Reactor Building).
Carbon-14 contributed 93% of the child total body dose and >99% of the child bone dose at the location of the nearest meat animal. Page 22 Table 4.2-A Maximum Individual Organ Dose at Receptor Location
--mrem From Gaseous Release Period: Jan-Mar 2016 Receptor:
Bound Resident Garden Cow/Goat Direction:
WNW s s w Distance1: 0.24km 2.22 km 3.44 km 3.75 km Pathwav2:
DI DI DIV3 DIVCG3 Age Class: Adult Bone 6.29E-05 1.45E-04 4.56E-03 2.64E-03 Gl-LLI 1.00E-04 9.56E-05 1.11 E-03 8.03E-04 Kidney 1.01 E-04 9.57E-05 1.11 E-03 8.04E-04 Liver 1.00E-04 9.56E-05 1.11 E-03 8.03E-04 Lung 1.01 E-04 9.57E-05 1.11 E-03 8.03E-04 Thyroid 1.14E-04 1.07E-04 1.15E-03 1.01 E-03 T.Body 1.00E-04 9.56E-05 1.11 E-03 8.03E-04 Age Class: Teen Bone 9.00E-05 2.07E-04 7.37E-03 4.45E-03 Gl-LLI 1.06E-04 1.08E-04 1.69E-03 1.20E-03 Kidney 1.06E-04 1.08E-04 1.69E-03 1.21 E-03 Liver 1.06E-04 1.08E-04 1.69E-03 1.21 E-03 LunQ 1.07E-04 1.08E-04 1.69E-03 1.20E-03 Thyroid 1.24E-04 1.22E-04 1.73E-03 1.50E-03 T.Body 1.06E-04 1.08E-04 1.69E-03 1.20E-03 Age Class: Child Bone 1.24E-04 2.86E-04 1.76E-02 1.07E-02 Gl-LLI 1.02E-04 1.15E-04 3.82E-03 2.60E-03 Kidney 1.02E-04 1.15E-04 3.82E-03 2.60E-03 Liver 1.02E-04 1.15E-04 3.82E-03 2.60E-03 Lung 1.02E-04 1.15E-04 3.82E-03 2.60E-03 Thyroid 1.24E-04 1.31E:.04 3.88E-03 3.17E-03 T.Body 1.02E-04 1.15E-04 3.82E-03 2.60E-03 Age Class: Infant Bone 9.16E-05 2.11 E-04 1.39E-04 6.73E-03 Gl-LLI 6.38E-05 7.73E-05 5.63E-05 1.66E-03 Kidney 6.39E-05 7.74E-05 5.63E-05 1.67E-03 Liver 6.39E-05 7.74E-05 5.63E-05 1.67E-03 Lung 6.39E-05 7.74E-05 5.64E-05 1.66E-03 Thyroid 8.34E-05 9.28E-05 6.85E-05 2.94E-03 T.Body 6.38E-05 7.73E-05 5.63E-05 1.66E-03 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:
Cow/Meat w 5.17 km DIVCM3 2.33E-03 6.50E-04 6.50E-04 6.50E-04 6.49E-04 7.67E-04 6.50E-04*
3.52E-03
9.06E-04 9.06E-04 9.06E-04 9.05E-04 1.07E-03 9.06E-04 8.27E-03 1.94E-03 1.94E-03 1.94E-03 1.94E-03 2.26E-03 1.94E-03 4.71E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.84E-03
1.13E-03 Meat s 3.82 km DIVM3 6.16E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.50E-03 1.45E-03 8.70E-03 1.96E-03 1.96E-03 1.96E-03 1.96E-03 2.01E-03 1.96E-03 2.01E-02 4.33E-03
. 4.33E-03 4.33E-03 4.33E-03 4.39E-03 4.33E-03 1.38E-04 5.56E-05 5.57E-05 5.57E-05 5.57E-05 6.77E-05 5.56E-05 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 2016 Receptor:
Bound Resident Garden Cow/Goat Direction:
WNW s s w Distance1: 0.24km 2.22 km 3.44 km 3.75 km Pathwav2:
DI DI DIV3 DIVCG3 Age Class: Adult Bone 6.53E-05 1.50E-04 5.31E-03 2.75E-03 Gl-LLI 1 .. 08E-04 1.02E-04 1.31 E-03 8.47E-04 Kidney 1.08E-04 1.02E-04 1.31 E-03 8.47E-04 Liver 1.08E-04 1.02E-04 1.31 E-03 8.47E-04 Lunq 1.08E-04 1.03E-04 1.31 E-03 8.46E-04 Thyroid 1.23E-04 1.14E-04 1.36E-03 1.05E-03 T.Body 1.08E-04 1.02E-04 1.31 E-03 8.47E-04 Aqe Class: Teen Bone 9.35E-05 2.15E-04 8.59E-03 4.62E-03 Gl-LLI 1.15E-04 1.15E-04 1.99E-03 1.27E-03 Kidney 1.15E-04 1.15E-04 1.99E-03 1.27E-03 Liver 1.14E-04 1.15E-04 1.99E-03 1.27E-03 Lung 1.15E-04 1.15E-04 1.99E-03 1.27E-03 Thyroid 1.34E-04 1.30E-04 2.04E-03 1.57E-03 T.Body 1.14E-04 1.15E-04 1.99E-03 1.27E-03 Aqe Class: Child Bone 1.29E-04 2.97E-04 2.05E-02 1.11 E-02 Gl-LLI 1.10E-04 1.22E-04 4.48E-03 2.72E-03 Kidney 1.10E-04 1.22E-04 4.48E-03 2.72E-03 Liver 1.10E-04 1.22E-04 4.48E-03 2.72E-03 Lung 1.10E-04 1.22E-04 4.48E-03 2.72E-03 Thyroid 1.33E-04 1.40E-04 4.55E-03 3.30E-03 T.Body 1.10E-04 1.22E-04 4.48E-03 2.72E-03 Age Class: Infant Bone 9.52E-05 2.19E-04 1.62E-04 6.99E-03 Gl-LLI 6.83E-05 8.19E-05 6.79E-05 1.74E-03 Kidney 6.84E-05 8.20E-05 6.80E-05 1.74E-03 Liver 6.84E-05 8.20E-05 6.80E-05 1.74E-03 Lung 6.85E-05 8.21E-05 6.81 E-05 1.74E-03 Thyroid 8.95E-05 9.86E-05 8.33E-05 3.05E-03 T.Body 6.83E-05 8.19E-05 6.80E-05 1.74E-03 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:
Cow/Meat w 5.17 km DIVCM3 2.42E-03 6.83E-04 6.83E-04 6.83E-04 6.83E-04 8.03E-04 6.83E-04 3.66E-03 9.50E-04 9.50E-04 9.50E-04 9.49E-04 1.12E-03 9.50E-04 8.59E-03 2.03E-03 2.03E-03 2.03E-03 2.03E-03 2.36E-03 2.03E-03 4.89E-03 1.18E-03 1.18E-03 1.18E-03 1.18E-03 1.91 E-03 1.18E-03 Meat s 3.82 km DIVM3 6.40E-03 1.51 E-03 1.51 E-03 1.51 E-03 1.51 E-03 1.56E-03 1.51 E-03 9.04E-03 2.05E-03 2.05E-03 2.05E-03 2.05E-03 2.10E-03 2.05E-03 2.09E-02 4.51E-03 4.51E-03 4.51E-03 4.51E-03 4.57E-03 4.51E-03 1.43E-04 5.91E-05 5.91E-05
5.91E-05 5.92E-05 7.21E-05 5.91E-05 D =Deposition (Ground Plane) I =Inhalation V =Vegetable Garden C = Cow Milk G = Goat Milk M = Meat Page 24 Table 4.2-C Maximum Individual Organ Dose at Receptor Location
--mrem From Gaseous Release Period: Jul-Sep 2016 Receptor:
Bound Resident Garden Cow/Goat Direction:
WNW s s w Distance1: 0.24km 2.22 km 3.44 km 3.75 km Pathwal:
DI DI DIV3 DIVCG3 AQe Class: Adult Bone 5.37E-05 1.23E-04 4.36E-03 2.26E-03 Gl-LLI 9.28E-05 8.71 E-05 1.08E-03 7.08E-04 Kidney 9.28E-05 8.71 E-05 1.08E-03 7.08E-04 Liver 9.27E-05 8.7.0E-05 1.08E-03 7.07E-04 LunQ 9.35E-05 8.77E-05 1.08E-03 7.07E-04 Thyroid 1.06E-04 9.79E-05 1.13E-03 8.94E-04 T.Body 9.27E-05 8.70E-05 1.08E-03 7.07E-04 AQe Class: Teen Bone 7.69E-05 1.77E-04 7.06E-03 3.80E-03 Gl-LLI 9.78E-05 9.76E-05 1.64E-03 1.05E-03 Kidney 9.79E-05 9.76E-05 1.64E-03 1.05E-03 Liver 9.78E-05 9.76E-05 1.64E-03 1.05E-03 LunQ 9.89E-05 9.85E-05 1.64E-03 1.05E-03 Thyroid 1.15E-04 1.11 E-04 1.69E-03 1.33E-03 T.Bodv 9.77E-05 9.75E-05 1.64E-03 1.05E-03 AQe Class: Child Bone 1.06E-04 2.44E-04 1.69E-02 9.16E-03 Gl-LLI 9.35E-05 1.03E-04 3.70E-03 2.25E-03 Kidney 9.36E-05 1.03E-04 3.69E-03 2.25E-03 Liver 9.36E-05 1.03E-04 3.69E-03 2.25E-03 LunQ 9.45E-05 1.03E-04 3.69E-03 2.25E-03 Thyroid 1.14E-04 1.19E-04 3.76E-03 2.78E-03 T.Body 9.35E-05 1.03E-04 3.69E-03 2.25E-03 AQe Class: Infant Bone 7.82E-05 1.80E-04 1.33E-04 5.75E-03 Gl-LLI 5.80E-05 6.88E-05 5.72E-05 1.44E-03
- Kidney 5.81E-05 6.88E-05 5.72E-05 1.44E-03 Liver 5.81E-05 6.88E-05 5.72E-05 1.44E-03 LunQ 5.87E-05 6.93E-05 5.77E-05 1.44E-03 Thyroid 7.72E-05 8.41 E-05 7.13E-05 2.62E-03 T.Body 5.80E-05 6.88E-05 5.72E-05 1.44E-03 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:
Cow/Meat w 5.17 km DIVCM3 1.99E-03 5.69E-04 5.69E-04 5.69E-04 5.69E-04 6.77E-04 5.69E-04 3.00E-03 7.89E-04 7.89E-04 7.89E-04 7.89E-04 9.44E-04 7.89E-04 7.06E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.98E-03 1.68E-03 4.02E-03 9.72E-04 9.75E-04 9.74E-04 9.72E-04 1.63E-03 9.73E-04 Meat s 3.82 km DIVM3 5.26E-03 1.25E-03 1.25E-03 1.25E-03 1.25E-03 1.30E-03 1.25E-03 7.42E-03 1.70E-03 1.69E-03 1.69E-03 1.69E-03 1.74E-03 1.69E-03 1.71E-02 3.72E-03 3.72E-03 3.72E-03 3.72E-03 3.78E-03 3.72E-03 1.17E-04 4.97E-05
4.97E-05 4.97E-05 5.01E-05 6.16E-05 4.97E-05 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 2016 Receptor:
Bound Resident Garden Cow/Goat Direction:
WNW s s ' w Distance 1: 0.24km 2.22 km 3.44 km 3.75 km Pathwav2:
DI DI DIV3 DIVCG3 Age Class: Adult Bone 6.03E-05 1.39E-04 4.37E-03 2.54E-03 Gl-LLI 9.35E-05 8.96E-05 1.06E-03 7.62E-04 Kidney 9.36E-05 8.96E-05 1.06E-03 7.62E-04 Liver 9.35E-05 8.96E-05 1.06E-03 7.61E-04 Lung 9.40E-05 8.99E-05 1.06E-03 7.61 E-04 Thyroid 1.0BE-04 1.01 E-04 1.10E-03 9.58E-04 T.Bodv 9.35E-05 8.95E-05 1.06E-03 7.61 E-04 Age Class: Teen Bone 8.63E-05 1.98E-04 7.07E-03 4.26E-03 Gl-LLI 9.91 E-05 1.01 E-04 1.61 E-03 1.15E-03 Kidney 9.92E-05 1.01 E-04 1.61 E-03 1.15E-03 Liver 9.92E-05 1.01 E-04 1.61 E-03 1.15E-03 Lung 9.99E-05 1.02E-04 1.61 E-03 1.14E-03 Thyroid 1.17E-04 1.16E-04 1.65E-03 1.43E-03 T.Body 9.91E-05 1.01 E-04 1.61 E-03 1.14E-03 Age Class: Child Bone 1.19E-04 2.74E-04 1.69E-02 1.03E-02 Gl-LLI 9.56E-05 1.0BE-04 3.66E-03 2.47E-03 Kidney 9.57E-05 1.0BE-04 3.66E-03 2.48E-03 Liver 9.56E-05 1.0BE-04 3.66E-03 2.48E-03 Lung 9.62E-05 1.0BE-04 3.66E-03 2.47E-03 Thyroid 1.17E-04 1.25E-04 3.71E-03 3.03E-03 T.Body 9.56E-05 1.0BE-04 3.66E-03 2.47E-03 Age Class: Infant Bone 8.78E-05 2.02E-04 1.33E-04 6.45E-03 Gl-LLI 5.97E-05 7.30E-05 5.31 E-05 1.59E-03 Kidney 5.98E-05 7.31E-05 5.31 E-05 1.59E-03 Liver 5.98E-05 7.31 E-05 5.31 E-05 1.59E-03 Lung 6.02E-05 7.34E-05 5.34E-05 1.59E-03 Thyroid 7.96E-05 8.87E-05 6.55E-05 2.83E-03 T.Body 5.97E-05 7.30E-05 5.31E-05 1.59E-03 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:
Cow/Meat w 5.17 km DIVCM3 2.24E-03 6.17E-04 6.17E-04 6.17E-04 6.17E-04 7.31 E-04 6.17E-04 3.37E-03 8.62E-04 8.62E-04 8.62E-04
8.61E-04 1.03E-03 8.61E-04 7.93E-03 1.85E-03 1.85E-03 1.85E-03 1.85E-03 2.16E-03 1.85E-03 4.51E-03 1.08E-03 1.08E-03 1.0BE-03 1.08E-03 1.77E-03 1.08E-03 Meat s 3.82 km DIVM3 5.91E-03 1.38E-03 1.38E-03 1.38E-03 1.38E-03 1.43E-03 1.38E-03 8.34E-03 1.88E-03 1.88E-03 1.88E-03 1.88E-03 1.92E-03 1.88E-03 1.93E-02 4.14E-03 4.14E-03 4.14E-03 4.14E-03 4.20E-03 4.14E-03 1.32E-04 5.24E-05
5.25E-05 5.25E-05 5.27E-05 6.47E-05 5.25E-05 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 26 Table 4.2-E Maximum Individual Organ Dose at Receptor Location
--mrem From Gaseous Release Period: Jan-Dec 2016 Receptor:
Bound Resident Garden Cow/Goat Direction:
WNW s s w Distance1: 0.24km 2.22 km 3.44 km 3.75 km Pathwav2:
DI DI DIV3 DIVCG3 Age Class: Adult Bone 2.42E-04 5.56E-04 1.76E-02 1.02E-02 Gl-LLI 3.95E-04 3.75E-04 4.29E-03 3.12E-03 Kidney 3.95E-04 3.75E-04 4.28E-03 3.12E-03 Liver 3.95E-04 3.75E-04 4.28E-03
. 3.12E-03 Lung 3.97E-04 3.76E-04 4.28E-03 3.12E-03
. Thyroid 4.52E-04 4.20E-04 4.46E-03 3.91E-03 T.Body 3.95E-04 3.75E-04 4.28E-03 3.12E-03 Aoe Class: Teen Bone 3.47E-04 7.97E-04 2.84E-02 1.71 E-02 Gl-LLI 4.18E-04 4.22E-04 6.53E-03 4.67E-03 Kidney 4.18E-04 4.22E-04 6.53E-03 4.67E-03 Liver 4.18E-04 4.22E-04 6.53E-03 4.67E-03 Lung 4.20E-04 4.24E-04 6.53E-03 4.67E-03 Thyroid 4.90E-04 4.79E-04 6.69E-03 5.83E-03 T.Body 4.18E-04 4.22E-04 6.53E-03 4.67E-03 Aoe Class: Child Bone 4.79E-04 1.10E-03 6.79E-02 4.13E-02 Gl-LLI 4.01E-04 4.47E-04 1.48E-02 1.00E-02 Kidney 4.02E-04 4.47E-04 1.48E-02 1.00E-02 Liver 4.01E-04 4.47E-04 1.48E-02 1.00E-02 Lunq 4.03E-04 4.49E-04 1.48E-02 1.00E-02 Thvroid 4.BBE-04 5.16E-04 1.50E-02 1.23E-02 T.Body 4.01E-04 4.47E-04 1.48E-02 1.00E-02 Age Class: Infant Bone 3.53E-04 8.11 E-04 5.34E-04 2.59E-02 Gl-LLI 2.50E-04 3.01E-04 2.19E-04 6.42E-03 Kidney 2.50E-04 3.01E-04 2.20E-04 6.44E-03 Liver 2.50E-04 3.01E-04 2.20E-04 6.43E-03 Lung 2.51E-04 3.02E-04 2.20E-04 6.42E-03 Thyroid 3.30E-04 3.64E-04 2.69E-04 1.14E-02 T.Body 2.50E-04 3.01E-04 2.19E-04 6.42E-03 1 Distances are measured with respect to the reactor building vent. 2 Pathway designations are as follows:
Cow/Meat w 5.17 km DIVCM3 8.98E-03 2.52E-03 2.52E-03 2.52E-03 2.52E-03 2.98E-03 2.52E-03 1.36E-02 3.51E-03 3.51E-03 3.51E-03 3.50E-03 4.17E-03 3.51E-03 3.19E-02 7.50E-03 7.50E-03 7.50E-03 7.50E-03 8.76E-03 7.50E-03 1.81 E-02 4.36E-03
4.37E-03 4.36E-03 4.36E-03 7.16E-03 4.36E-03 Meat s 3.82 km DIVM3 2.37E-02 5.59E-03 5.59E-03 5.59E-03 5.59E-03 5.78E-03 5.59E-03 3.35E-02 7.59E-03 7.59E-03 7.59E-03 7.59E-03 7.76E-03 7.59E-03 7.74E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.69E-02 1.67E-02 5.29E-04 2.17E-04 2.17E-04 2.17E-04 2.18E-04 2.66E-04 2.17E-04 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 27 4.3 Doses From Liquid Effluent Releases Liquid effluent release data presented in Tables 2.3-A and 2.3-B were used as input to the dose assessment computer program to calculate radiation doses. The maximum individual doses resulting from radionuclides released in liquid effluents are presented in Tables 4.3-A through 4.3-E. These tables cover the individual calendar quarters and the total calendar year, respectively.
Tables 4.3-A through 4.3-E summarize the maximum total body and organ doses for the adult, teen, and child age classes resulting from the major liquid exposure pathways.
NRC Regulatory Guide 1.109 does not recognize the infant age class as being exposed to the liquid effluent pathways.
Therefore, doses for this age class are not included in any of the tables. It should be noted that doses calculated for the entire year might not equal the sum of the doses for the individual quarters.
Doses from liquid effluents are based on the concentration (activity divided by volume) of radionuclides released in the effluent, as prescribed by the NRC in Regulatory Guide 1.109. If a larger proportion of activity is released with a relatively smaller volume of dilution water during a given quarter, the resulting concentration for that quarter will be higher than concentrations from other quarters.
This will result in a proportionally higher dose for that quarter.
- However, when that quarter's activity values are included in the annual sum, and divided by the total annual dilution flow, the resulting dose contribution will be smaller.
In such a situation, the annual dose will actually be less than the sum of the individual quarterly doses. Radioactivity released in liquid effluents from PNPS during the reporting period resulted in a maximum total body dose (teen age class) of 0.000000257 mrem. The maximum organ dose (teen age class, Liver) was 0.000000460 mrem. Page 28 Table 4.3-A Maximum Individual Organ Doses --mrem From Liquid Release Period: Jan-Mar 2016 Age Class Organ Dose -mrem
- Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidnev N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A
- 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 Organ Bone Gl-LLI Kidney Liver LunQ Table 4.3-B Maximum Individual Organ Doses --mrem From Liquid Release Period: Apr-Jun 2016 Age Class Organ Dose -mrem Adult Teen Child 1.95E-07 2.97E-07 2.59E-07 2.58E-08 1.19E-07 2.58E-08 1.02E-07 1.98E-07 9.78E-08 2.59E-07 3.57E-07 2.49E-07 4.80E-08 1.48E-07 5.08E-08 Thyroid 2.11E-08 1.16E-07 2.44E-08 T.Body 1.77E-07 2.00E-07 5.76E-08 Page 30 Organ Bone Gl-LLI Kidney Liver Lung Table 4.3-C Maximum Individual Organ Doses --mrem From Liquid Release Period: Jul-Sep 2016 Age Class Organ Dose -mrem Adult Teen Child 5.64E-08 8.60E-08 7.52E-08 8.24E-09 3.51E-08 7.98E-09 3.03E-08 5.79E-08 2.88E-08 7.59E-08 1.04E-07 7.28E-08 1.47E-08 4.34E-08 1.52E-08 Thyroid 6.90E-09 3.41 E-08 7.57E-09 T.Body 5.21 E-08 5.85E-08 1.72E-08 Page 31 Table 4.3-D Maximum Individual Organ Doses --mrem From Liquid Release Period: Oct-Dec 2016 Age Class Organ Dose -mrem
- Organ Adult Teen Child Bone N/A N/A N/A Gl-LLI N/A N/A N/A Kidney N/A N/A N/A Liver N/A N/A N/A Lung N/A N/A N/A Thyroid N/A N/A N/A T.Bodv N/A N/A N/A
- 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 2016 Age Class Organ Dose -mrem
- Organ Adult Teen Child Bone 2.50E-07 3.81E-07 3.33E-07 Gl-LLI 3.39E-08 1.54E-07 3.37E-08 Kidney 1.32E-07 2.55E-07 1.26E-07 Liver 3.34E-07 4.60E-07 3.21E-07 Lu no 6.25E-08 1.90E-07 6.58E-08 Thyroid 2.BOE-08 1.49E-07 3.19E-08 T.Bodv 2.28E-07 2.57E-07 7.46E-08
- These doses are conservative since the same usage factor was applied for each quarter.
In reality, it is unlikely that anyone would be swimming or boating during the entire year. However, the resulting dose is considerably lower than those from other pathways and does not contribute much to the total dose. Page 33 5.0 OFFSITE AMBIENT RADIATION MEASUREMENTS The PNPS ODCM does not contain control limits related specifically to offsite ambient radiation exposure.
- However, Regulatory Guide 1.21 (Reference
- 1) recommends calculation of ambient radiation exposure as part of the overall assessment of radiological impact on man. Thermoluminescent dosimeters (TLDs) are located at 86 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 c;tt 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 (l&S Building),
was 204 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 74.8 +/- 26.2 mR/yr to 62.6 +/- 8.0 mR/yr. Such a corrected dose is not statistically different from the Zone 4 average of 60.1 +/- 8.3 mR/yr, and is indicative of natural background radiation.
Although the annual exposure at TLD location OA was 144 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 0.66 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 61.6 +/- 3.6 mR (based on continuous occupancy at this location),
which compares quite well to the Zone 4 annual average background radiation level of 60.1 +/- 8.3 mR. Statistically, there is no difference between these two values. Page 34 Pilgrim Station began moving spent fuel to the Independent Spent Fuel Storage Installation (ISFSI) located within the protected area immediately west of the PNPS Reactor Building.
Three new TLDs were installed at the beginning of 2016 to monitor any incremental dose from this facility.
TLD ISF-1 was located on Rocky Hill Road 0.35 km (0.21 mi) southwest of the reactor building.
The annual exposure at this location was calculated as being 76. 7 +/- 4.0 mR (based on continuous occupancy at this location),
or 16.6 mR above the Zone 4 average of 60.1 mR. However, the area is not continuously
- occupied, and when corrected for an exposure time of 365 hour0.00422 days <br />0.101 hours <br />6.035053e-4 weeks <br />1.388825e-4 months <br />s/year, the estimated exposure to a person walking along this section of Rocky Hill Road would be 0.69 mR/year.
It must be emphasized that the projected ambient exposures discussed above and 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 1 OCFR20.1301, 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 (l&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 2016 is estimated as being about 1.6 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 2016. 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 0.0016 mrem, resulting from inhalation.
Agairi, it must be emphasized that the above-described exposures were received by personnel who are employees or contractors of Entergy, accessing areas or facilities on property under the ownership and control of Entergy.
Since this exposure was received within the owner-controlled area, it is not used for comparison to the annual dose limit of 25 mrem/yr specified in 40CFR190.
This regulation explicitly 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 0. 7 mrem/year.
Page 35 Table 5.0 Average TLD Exposures By Distance Zone During 2016 AveraQe Exposure
+/- Standard Deviation:
mR/ Jeriod Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 18.2 +/- 6.7 14.2 +/- 2.0 13.6 +/- 1.6 14.3 +/- 2.3 Apr-Jun 19.6 +/- 7.0 15.0 +/- 2.0 14.5+/-1.5 15.7+/-2.0 Jul-Sep 19.3+/-6.1 15.0 +/- 1.9 14.7+/-1.6 15.7 +/- 1.9 Oct-Dec 17.6 +/- 6.3 13.3 +/- 1.8 13.2 +/- 1.4 14.3 +/- 2.1 Jan-Dec 74.8 +/- 26.2** 57.6 +/- 8.0 55.9 +/- 6.3 60.1+/-8.3
- Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.
- When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated.
to be 62.6 +/- 8.0 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 2016 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 2016 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 9.26E-07 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 2.31E-06 C. Instantaneous Dose Rate Limit -Particulates,
& Tritium PNPS ODCM Control 3.3.1.b Limit: 1500 mrem/yr Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 D. Quarterly Dose Objective
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.a Objective:
5 mrad Gamma Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value-mrad O.OOE+OO 2.83E-07 4.99E-07 6.09E-07 E. Annual Dose Objective
-Noble Gas Gamma Air Dose PNPS ODCM Control 3.3.2.b Objective:
10 mrad Gamma Air Dose Period Jan-Dec Value -mrad/yr 1.39E-06 Page 38 Fraction of Limit 1.85E-07%
Fraction of Limit 7.71E-08%
Fraction of Limit 5.16E-03%
Fraction of Limit O.OOE+OO%
5.66E-06%
9.98E-06%
1.22E-05%
Fraction of Limit 1.39E-05%
Table 6.1 (continued)
Percent of ODCM Effluent Control Limits for Gaseous Effluent Releases During 2016 F. Quarterly Dose Objective
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.a Objective:
10 mrad Beta Air Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrad O.OOE+OO 3.38E-07 5.96E-07 7.28E-07 G. Annual Dose Objective
-Noble Gas Beta Air Dose PNPS ODCM Control 3.3.2.b Objective:
20 mrad Beta Air Dose Period Jan-Dec Value -mrad/yr 1.66E-06 Fraction of Limit O.OOE+OO%
3.38E-06%
5.96E-06%
7.28E-06%
Fraction of Limit 8.31E-06%
H. Quarterly Dose Objective
-Particulates,
7 .5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Value -mrem 2.01 E-02 2.09E-02 1.71 E-02 1.93E-02 Fraction of Limit 2.68E-01%
2.78E-01%
2.29E-01%
2.57E-01%
I. Annual Dose Objective
-Particulates,
15 mrem Organ Dose Period Jan-Dec Value -mrem/yr 7.74E-02 Page 39 Fraction of Limit 5.16E-01%
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 2016 A. Fission and Activation Product Effluent Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1 OCFR20 Appendix B, Table 2, Column 2 Value Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 4.10E-14 1.19E-14 N/A 1.32E-14 B. Tritium Average Concentration Limit PNPS ODCM Control 3.2.1 Limit: 1.0E-03 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A 3.26E-12 6.30E-12 N/A 2.40E-12 C. Dissolved and Entrained Noble Gases Concentration Limit PNPS ODCM Control 3.2.1 Limit: 2.0E-04 µCi/ml Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Value -uCi/ml N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO Page 41 Fraction of Limit N/A 4.10E-06%
1.19E-06%
N/A 1.32E-06%
Fraction of Limit N/A 3.26E-07%
6.30E-07%
N/A 2.40E-07%
Fraction of Limit N/A O.OOE+00%
O.OOE+00%
N/A O.OOE+00%
Table 6.2 (continued)
Percent of ODCM Effluent Control Limits for Liquid Effluent Releases During 2016 D. Quarterly Total Body Dose Objective PNPS ODCM Control 3.2.2.a Objective:
1.5 mrem Total Body Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec E. Annual Total Body Dose Objective Value -mrem N/A 2.00E-07 5.85E-08 N/A PNPS ODCM Control 3.2.2.b Objective:
3 mrem Total Body Dose Period Jan-Dec F. Quarterly Organ Dose Objective Value -mrem 2.57E-07 PNPS ODCM Control 3.2.2.a Objective:
5 mrem Organ Dose Period Jan-Mar Apr-Jun Jul-Sep Oct-Dec G. Annual Organ Dose Objective Value -mrem N/A 3.57E-07 1.04E-07 N/A PNPS ODCM Control 3.2.2.b Objective:
10 mrem Organ Dose Period Jan-Dec Value -mrem 4.60E-07 Page 42 Fraction of Limit N/A 1.33E-05%
3.90E-06%
N/A Fraction of Limit 8.58E-06%
Fraction of Limit N/A 7.14E-06%
2.08E-06%
N/A Fraction of Limit 4.60E-06%
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 83.7 cubic meters of spent resins, filter sludges, etc., containing a total activity of about 1040 Curies were shipped from PNPS for processing and disposal.
Dry activated wastes and contaminated equipment shipped during the period totaled 343 cubic meters and contained 0.427 Curies of radioactivity.
There were no shipments of irradiated components during the reporting period. There were no shipments of "Other wastes" during the reporting period. 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 21 shipments to Energy Solutions' Bear Creek Facility in Oak Ridge, TN; 2 shipments to Energy Solutions Erwin Resin Solutions' Facility in Erwin, TN.; and 2 shipments to Alaron Nuclear Services, Wampum, PA. Page 43 Table 7.0 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments January-December 2016 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 2016 Type of waste Volume-Curies a. Spent resins, filters, filter sludges, 8.37E+01 1.04E+03 evaporator
- bottoms, etc. b. Dry activated waste, contaminated 3.43E+02 4.27E-01 equipment, etc. c. Irradiated components, control rods, etc. O.OOE+OO O.OOE+OO
- d. Other (describe):
O.OOE+OO O.OOE+OO
- 2. Estimate of major nuclide composition by type of waste 1 Tvoe of waste Radionuclide Abundance
- a. Spent resins, filters, filter sludge's, Mn-54 12.02% evaporator
- bottoms, etc. Fe-55 55.12% Co-60 23.82% Zn-65 5.16% Cs-137 1.97% b. Dry activated waste, contaminated Mn-54 2.36% equipment, etc. Fe-55 80.07% Co-60 14.65% Ni-63 1.87% c. Irradiated components, control rods, etc. N/A N/A d. Other (describe):
Contaminated oil and water N/A N/A 7 " ,,. . . 0 . . Ma1or 1s defined as any radionuclide compnsmg
> 1 % of the total activity m the waste category.
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Total Error +/-25% +/-25% N/A N/A
- Total Error +/-25% +/-25% .+/-25% +/-25% +/-25% +/-25% +/-25% +/-25% +/-25% N/A N/A 21 Tractor-trailer Energy Solutions, Bear Creek Facility"'
(Hittman Transport)
Oak Ridge, TN 2 Tractor-trailer Energy Solutions, Erwin Resin Solutions"'
(Hittman Transport)
Erwin, TN 2 Tractor-trailer Alaron Nuclear Services"'
(Hittman Transport)
Wampum, PA L This processor provides volume reduction services for dry compressible waste, contaminated
- eqwpment, etc. Remaining radioactive wastes will be shipped to Envirocare, Inc. in Clive, UT for final disposal.
- 8. 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 2016. 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 2016 to various procedures related to the Process Control Program (PCP): EN-RW-102.
"Radioactive Shipping Procedure".
Rev.14: The primary purpose of this revision is to update the procedure to ensure compliance with current and upcoming changes to 49 CFR, especially those changes stemming from HM-215M and HM-250 (changes are as recommended by review of EN-RW-102 by WMG). Additionally, the issue identified in NIOS audit QA-14/15-2015-IP-01 regarding retention of DOT Spec 7A test and engineering evaluation is addressed.
- Added a bullet item to step 7.0[2] specifying that shipment records are to include documentation of tests and engineering evaluations for DOT Spec 7 A packages it Step 2.0[1 O]: Corrected reference to WMG software packages
- Step 5.1 [12]: replaced specific shipping names with generic statement regarding Marking and Labeling
- Step 5.2[11](c),
Attachment 9.10: Updated terminology for Industrial Package
- Step 5.2[11](c):
Added requirement to cover Specification Marking
- Step 5.2[16]:
Added reference for requirements for multiple hazard radioactive material
- Step 5.2[19]:
Revised step to indicate that the survey only releases the vehicle back to exclusive use service *
- Added step 5.2[20] for unconditional release of formerly exclusive use vehicle.
- Step 7.0[1]: Added an additional reference for record retention
- Step 7.0[2]: Added bullet item requiring that documentation of. tests and engineering evaluations be kept for records
- Attachment 9.1: replaced RAMSHP with RADMAN and replaced obsolete reference to Studsvik with Erwin Resin Solutions
- Attachment 9.2, step 21: replaced Studsvik with Erwin Resin Solutions
- Attachment 9.3, step 12: combined sub-step "a" with step 12 as there is no step "b"
- Attachment 9.3, step 13: replaced Studsvik with Erwin Resin Solutions
- Attachment 9.3, step 24: added requirement for DOT 7 A test and engineering documentation
- Attachment 9.4, step 14: replaced Studsvik with Erwin Resin Solutions
- Attachment 9.4: Added a new step #5 for verifying the licensee is a registered user of Type B package
- Attachment 9.5, step #9: added reference to requirements of 49CFR173.422
- Attachment 9.6, step #8: added reference to requirements of 49CFR 173.422
- Attachment 9.7, step #10: added reference to requirements of 49CFR173.422
- Attachment 9.8, step #7: added reference to requirements of 49CFR 173.422
- Attachment 9.9, step #6: added reference to requirements of 49CFR173.422
- Attachment 9.10: updated references for Industrial Package (I, II, and Ill changed to Type 1,2,3)
- Attachment 9.11, sheet 2: updated contamination limits to reflect latest regulations
- Attachment 9.14: updated definition of Exclusive Use according to WMG recommendation
- Updated section 8.0 and related procedure steps per GGNS Commitment Review Page 46 EN-RW-106, "Integrated Transportation Security Plan, Rev.5: The purpose of this revision is to address:
- A QA-identified issue regarding documentation of preplanning activities
- Correct the NRC email address
- Add a requirement for contacting ANI
- Added step 2.0[20] for reference to NUREG-2155 (which is the basis for preplanning documentation requirements)
- Step 3.0[1] added: ANI (American Nuclear Insurers),
MCC-Movement Control Center, SAS -Secondary Alarm Station
- Step 5.3[4]: corrected step reference
- Step 5.7.4.1[3]:
corrected the NRC email address
- Added steps 5.7.5.2[8]
and 5.7.5.3[7]
for ANI notification in the event of an accident.
- Step 5. 7 .6.1 [2]: expanded requirements for documentation of preplanning activities
- Step 5.8[2] is reworded for clarity EN-RW-108, "Radioactive Shipment Accident Response".
Rev.2: The primary purpose of this revision is to add instruction for contacting ANI in the event of an accident covered by this procedure.
Specifically:
- ANI is added to the definitions
- section, section 3.0
- Step 5.4[1] is expanded to address contacting ANI This is a complete rewrite of the procedure in order to align the procedure format with EN-AD-101-
- 01. Content changes are made only to correct grammatical errors or to change step levels to correct formatting and are editorial.
No change bars are used to reflect the changes made due to the rewrite.
Changes worth noting are:
- Sections 5.1 and 5.2 are reversed in order for alignment with EN-AD-101-01
- Section 5.3.2: "CAUTION" is changed to "NOTE" in the box associated with ion chambers versus GM instruments as the associated statement does not qualify as a caution statement.
- The Note statement in section 5.4[3] (of Rev. 1) regarding evaluation for fatigue is changed to an instructional step as the statement is not appropriate for a Note statement.
- The statement in section 5.4[3] (of Rev: 1) regarding the reference to EN-OM-123 is changed to an instructional step as the statement is not appropriate for a Note statement or a Caution statement.
- The last Note statement in section 5.0 regarding disposition of documents is changed to a step as the contents are not appropriate for a Note statement
- Attachment 9.1: changed note on page one to a step because the content is inappropriate for a Note. Page 47
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 1 OCFR50 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., P1OO-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".
- 7. U.S. Nuclear Regulatory Commission, "XOQDOQ:
Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",
NUREG/CR2919, September 1982. Page 48 TABLE A-1 A-2 APPENDIX A Meteorological Joint Frequency Distributions TABLE TITLE Joint Frequency Distribution of Wind Directions and Speeds for the 33-ft Level of the 220-ft Tower Joint Frequency Distribution of Wind Directions and Speeds for the 220-ft Level of the 220-ft Tower Page 49 PAGE 50 60 Jan-Mar 2016 ------mph N NNE Calm-0.95 0 0 0.95-3.5 0 0 3.5-7.5 12 16 7.5-12.5 4 2 12.5-18.5 0 0 18.5-24 0 0 >24 0 0 TOTAL 16 18 Class B Frea: 0.024 mph N NNE Calm-0.95 0 0 0.95-3.5 1 1 3.5-7.5 1 1 7.5-12.5 1 0 12.5-18.5 0 0 18.5-24 0 0 >24 0 0 TOTAL 3 2 0.044 mph N NNE Calm-0.95 0 0 0.95-3.5 2 0 3.5-7.5 4 3 7.5-12.5 2 2 12.5-18.5 0 0 18.5-24 0 0 >24 0 0 TOTAL 8 5 mph N NNE Calm-0.95 0 0 0.95-3.5 4 6 3.5-7.5 27 22 7.5-12.5 12 10 12.5-18.5 2 7 18.5-24 0 3 >24 0 0 TOTAL 45 48 Table A-1 Joint Frequency Distribution of Wind Directions and Speeds For the 33-ft level of the 220-ft Tower NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 15 8 6 3 1 0 0 1 0 2 8 6 1 2 0 1 0 0 0 2 1 0 9 11 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 16 11 6 4 1 0 0 3 1 2 17 17 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 3 1 6 2 0 0 0 0 0 1 2 1 0 3 1 0 2 0 2 2 2 0 2 1 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 4 8 2 2 1 2 2 2 1 4 2 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 2 3 3 1 0 0 0 0 0 0 1 1 2 3 1 0 4 0 4 12 3 0 5 1 0 0 0 0 2 0 0 6 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 6 4 1 6 0 4 18 4 0 6 2 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 6 7 3 1 0 1 0 2 3 2. 2 5 18 20 21 17 13 3 5 25 20 9 13 25 5 10 7 4 3 0 9 63 9 4 13 64 3 7 0 0 1 4 1 8 6 0 0 41 1 1 0 0 0 3 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 33 46 31 22 17 11 15 98 38 15 28 135 Page 50 NW NNW TOTAL 0 0 0 0 0 1 6 3. 87 0 2 35 0 0 0 0 0 0 0 0 0 6 5 123 NW NNW TOTAL 0 0 0 1 0 4 2 0 20 1 2 19 0 0 1 0 0 0 0 0 0 4 2 44 NW NNW TOTAL 0 0 0 0 0 3 3 1 22 4 2 45 2 0 11 0 0 0 0 0 0 9 3 81 NW NNW TOTAL 0 0 0 7 5 54 34 16 288 37 10 260 34 1 115 0 0 8 0 0 1 112 32 726 Table A-1 (continued}
Jan-Mar 2016 ------------moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 4 3 4 6 3 6 4 14 11 8 14 11 9 6 3 110 3.5-7.5 13 4 3 7 24 7 15 15 28 24 30 41 59 43 19 18 350 7.5-12.5 5 8 0 3 6 1 5 8 15 55 47 9 10 25 16 5 218 12.5-18.5 3 11 1 2 0 0 2 7 21 20 1 0 0 0 2 5 75 18.5-24 2 8 3 3 0 0 0 3 7 0 0 0 0 0 0 0 26 >24 0 *o 6 1 0 0 0 0 1 0 0 0 0 0 0 0 8 TOTAL 27 35 16 20 36 11 28 37 86 110 86 64 80 77 43 31 787 F moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 0 1 0 1 0 0 2 3 1 3 1 1 0 3 18 3.5-7.5 0 0 1 1 0 0 0 3 8 6 22 14 7 2 1 1 66 7.5-12.5 0 0 0 0 0 0 0 4 2 0 3 0 1 0 0 0 10 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 2 1 2 0 1 0 7 12 9 26 17 9 3 1 4 94 -------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 1 0 2 0 0 0 0 3 7.5-12.5 0 0 0 0 0 0 0 1 0 0 2 1 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 0 0 0 0 0 0 0 1 0 1 2 3 0 0 0 0 7 Cl ------... F . . --.-1.0 . ----mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 11 13 10 13 10 5 6 5 16 16 12 19 14 15 14 11 190 3.5-7.5 57 46 42 40 60 30 29 21 41 57 72 69 90 78 65 39 836 7.5-12.5 24 22 8 21 15 6 14 13 32 134 67 14 40 102 58 21 591 12.5-18.5 5 18 4 9 0 0 5 12 22 34 8 0 0 41 38 6 202 18.5-24 2 11 4 4 0 0 0 6 7 0 0 0 0 0 0 0 34 >24 0 0 6 2 0 0 0 0 1 0 .o 0 0 0 0 0 9 TOTAL 99 110 74 89 85 41 54 57 119 241 159 102 144 236 175 77 1862 Page 51 Table A-1 (continued)
Apr-Jun 2016 -*---.. . . --.* -* *--mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 4 0 1 0 1 0 0 0 0 0 0 0 0 0 2 1 9 3.5-7.5 32 47 20 32 14 3 1 1 1 1 0 0 15 12 10 12 201 7.5-12.5 3 17 0 0 0 0 1 0 6 5 0 1 16 4 0 0 53 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 39 64 21 32 15 3 2 1 7 6 0 1 31 16 12 13 263 -------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 1 0 0 0 0 0 0 1 1 1 4 3.5-7.5 1 8 6 10 8 4 2 0 0 0 2 3 7 3 2 0 56 7.5-12.5 0 0 0 0 0 0 1 1 10 8 1 0 1 1 0 0 23 12.5-18.5 0 0 0 0 0 0 0 0 0 4 0 0 0 0 0 0 4 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 8 6 10 8 4 4 1 10 12 3 3 8 5 3 1 87 mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 3 2 1 0 3 0 0 0 1 0 0 0 1 1 2 1 15 3.5-7.5 0 11 7 9 12 5 5 0 1 5 5 5 7 1 2 3 78 7.5-12.5 0 5 1 0 0 0 2 0 23 16 2 0 2 0 0 0 51 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 3 18 9 9 15 5 7 0 25 22 7 5 10 2 4 4 145 -*----. *--* -* *--mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 26 15 20 21 26 6 6 5 9 6 4 3 10 10 12 13 192 3.5-7.5 18 28 39 49 33 29 23 12 73 59 31 19 35 12 8 5 473 7.5-12.5 3 35 2 0 1 0 12 11 50 72 6 5 10 0 2 0 209 12.5-18.5 0 0 0 0 0 0 0 10 6 1 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 47 78 61 70 60 35 41 38 138 138 41 27 55 22 22 18 891 Page 52 Table A-1 (continued)
Apr-Jun 2016 Class E Frea: 0.248 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 7 5 8 9 15 6 9 15 12 6 6 11 16 16 11 4 156 3.5-7.5 13 16 1 12 5 5 12 17 20 39 41 65 25 14 9 14 308 7.5-12.5 0 0 0 0 0 0 1 1 3 51 15 3 1 0 0 0 75 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 20 21 9 21 20 11 22 33 37 96 62 79 42 30 20 18 541 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 1 1 0 2 3 2 5 3 3 4 13 14 23 5 4 0 83 3.5-7.5 0 0 0 3 4 1 1 4 1 14 30 21 6 2 0 1 88 7.5-12.5 0 0 0 0 0 0 0 0 0 15 15 0 0 0 0 0 30 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 1 0 5 7 4 6 7 4 33 58 35 29 7 4 1 202 Class G Frea: 0.025 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 1 0 0 0 1 0 4 7 3 0 0 1 17 3.5-7.5 0 0 0 2 0 0 0 0 0 1 21 2 0 0 0 0 26 7.5-12.5 0 0 0 0 0 0 0 0 0 4 8 0 0 0 0 0 12 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 2 1 0 0 0 1 5 33 9 3 0 0 1 55 Class All Frea: 1.000 ---------------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 0.95-3.5 41 23 30 32 49 14 21 23 26 16 27 35 53 33 32 21 476 3.5-7.5 64 110 73 117 76 47 44 34 96 119 130 115 95 44 31 35 1230 7.5-12.5 6 57 3 0 1 0 17 13 92 171 47 9 30 5 2 0 453 12.5-18.5 0 0 0 0 0 0 0 10 8 6 0 0 0 0 0 0 24 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 111 190 106 149 126 62 82 80 222 312 204 159 178 82 65 56 2184 Page 53 Table A-1 (continued)
Jul-Sep 2016 ....................
. , .... _ ..............
mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 10 6 10 2 0 2 0 0 0 0 0 0 0 3 0 4 37 3.5-7.5 12 27 32 19 12 13 5 0 1 0 3 0 10 16 11 2 163 7.5-12.5 0 4 0 0 0 0 6 0 7 8 1 0 0 0 0 0 26 12.5-18.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 22 37 42 21 12 15 11 0 9 8 4 0 10 19 11 6 227 -*----. *--* -*---mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 2 1 3 0 0 0 0 0 0 0 1 0 6 5 20 3.5-7.5 1 10 1 12 6 9 1 1 0 2 20 3 6 1 1 3 77 7.5-12.5 0 0 0 0 0 0 0 0 10 8 6 0 0 0 0 0 24 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 12 3 13 9 9 1 1 10 10 26 3 7 1 7 8 121 ----------,-----. mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 1 3 2 1 4 0 0 0 1 1 1 0 1 6 4 27 3.5-7.5 0 8 6 6 5 6 6 1 6 4 17 3 7 4 3 0 82 7.5-12.5 0 2 0 0 0 0 0 0 9 12 2 0 0 0 0 0 25 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 11 9 8 6 10 6 1 15 17 20 4 7 5 9 4 134 ...................
-........................
mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 16 23 23 31 21 13 9 2 6 4 8 5 12 9 8 9 199 3.5-7.5 5 64 39 40 21 16 28 13 60 152 46 18 12 8 4 9 535 7.5-12.5 0 8 1 0 0 0 1 1 22 68 2 0 0 0 0 0 103 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 95 63 71 42 29 38 16 88 224 56 23 24 17 12 18 837 Page 54 Table A-1 (continued)
Jul-Sep 2016 ------------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW 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 5 17 10 13 18 15 10 10 10 15 16 17 21 16 22 11 226 3.5-7.5 8 4 2 8 3 2 6 21 33 132 62 28 12 2 8 5 336 7.5-12.5 0 0 0 0 0 0 0 0 1 20 4 0 0 0 0 0 25 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 13 21 12 21 21 17 17 31 44 167 82 45 33 18 30 16 588 Class F F mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 0 0 1 0 1 0 0 3 0.95-3.5 2 0 2 3 0 1 2 7 7 6 25 39 27 10 7 2 140 3.5-7.5 1 0 0 0 0 0 1 2 2 17 55 8 1 0 0 1 88 7.5-12.5 0 0 0 0 0 0 0 0 0 2 14 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 TOTAL 3 0 2 3 0 1 3 9 10 25 94 48 28 11 7 3 247 Class G -------F --0.024 ----mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 2 0.95-3.5 0 0 1 0 0 0 0 0 1 0 4 13 0 1 0 1 21 3.5-7.5 0 0 0 1 0 0 0 0 0 4 22 0 0. 0 0 1 28 7.5-12.5 0 0 0 0 0 0 0 0 0 1 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 cl 0 0 TOTAL 0 0 1 2 0 0 0 1 1 5 26 13 0 1 0 2 52 mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW . TOTAL Calm-0.95 0 0 0 1 0 0 1 1 1 0 0 1 0 1 0 0 6 0.95-3.5 35 49 51 52 43 35 21 19 24 26 54 75 61 40 49 36 670 3.5-7.5 27 113 80 86 47 46 47 38 102 311 225 60 48 31 27 21 1309 7.5-12.5 0 14 1 0 0 0 7 1 49 119 29 0 0 0 0 0 220 12.5-18.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 62 176 132 139 90 81 76 59 177 456 308 136 109 72 76 57 2206 Page 55 Table A-1 (continued)
Oct-Dec 2016 c lass A Freq: 0.043 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 3 6 2 3 0 0 0 0 0 0 0 0 0 0 0 15 3.5-7.5 12 10 7 10 17 3 0 0 0 0 0 0 0 2 2 16 79 7.5-12.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 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 13 13 13 12 20 3 0 0 0 0 0 0 0 2 2 17 95 Class B Freq: 0.023 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 2 1 3 3 0 0 0 0 0 0 0 0 0 0 11 3.5-7.5 3 8 1 0 0 0 0 0 0 1 0 0 1 12 5 5 36 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 0 0 2 0 1 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 3 10 3 1 3 3 0 0 0 1 1 0 1 14 5 6 51 Cl C F 0 034 ass req: mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 0 3 1 0 1 0 0 0 0 0 0 2 0 0 8 3.5-7.5 0 5 2 1 1 1 1 0 0 1 0 6 8 21 6 2 55 7.5-12.5 0 0 0 0 0 0 0 0 1 0 3 2 1 4 0 0 11 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 5 2 4 2 1 2 0 1 1 3 8 9 27 6 2 74 Cl D F 0 446 ass rea: mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 16 14 8 8 8 1 5 1 2 4* 4 2 12 10 20 21 136 3.5-7.5 23 55 29 14 16 13 26 10 19 25 39 76 109 106 77 35 672 7.5-12.5 2 7 0 0 1 1 14 4 9 7 14 35 41 16 12 8 171 12.5-18.5 0 0 0 0 0 0 4 0 0 0 1 0 1 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 41 76 37 22 25 15 49 15 30 36 58 113 163 132 109 64 985 Page 56 Table A-1 (continued)
Oct-Dec 2016 ------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 5 7 4 6 5 8 10 8 17 16 15 42 26 26 14 6 215 3.5-7.5 8 4 1 1 4 11 25 43 24 38 85 126 43 23 29 5 470 7.5-12.5 3 8 0 0 1 9 18 9 6 40 14 10 2 2 0 0 122 12.5-18.5 0 0 0 0 0 0 1 3 0 2 3 0 0 0 0 0 9 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 16 19 5 7 10 28 54 63 47 96 117 178 71 51 43 11 816 -*---. . ---.------moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 1 0 1 0 1 0 3 0.95-3.5 2 1 0 0 0 0 0 3 9 6 11 35 10 4 3 1 85 3.5-7.5 0 0 0 0 0 0 0 3 10 7 30 5 2 0 0 0 57 7.5-12.5 0 0 0 0 0 0 0 0 0 0 7 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 2 1 0 0 0 0 0 6 19 13 49 40 13 4 4 1 152 -----mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 1 0 0 1 8 5 2 0 1 18 3.5-7.5 0 0 0 0 0 0 0 0 0 0 7 4 0 0 0 0 11 7.5-12.5 0 0 0 0 0 0 0 0 0 0 5 0 0 0 0 0 5 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 1 0 0 13 12 5 2 0 1 34 -*---.... . ---.------moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 1 0 1 0 1 0 3 0.95-3.5 25 27 20 20 20 12 16 13 28 26 31 87 53 44 37 29 488 3.5-7.5 46 82 40 26 38 28 52 56 53 72 161 217 163 164 119 63 1380 7.5-12.5 5 15 0 0 2 10 32 13 16 47 44 47 44 24 12 10 321 12.5-18.5 0 0 0 0 0 0 5 3 0 2 4 0 1 0 0 0 15 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 76 124 60 46 60 50 105 85 97 147 241 351 262 232 169 102 2207 Page 57 Table A-1 (continued)
Jan-Dec 2016 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 15 9 17 5 4 2 0 0 0 0 0 0 0 3 2 5 62 3.5-7.5 68 100 74 69 49 22 7 1 2 2 3 2 33 36 29 33 530 7.5-12.5 7 23 1 2 0 1 7 0 13 15 2 1 25 15 0 3 115 12.5-18.5 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 90 132 92 76 53 25 14 1 16 17 5 3 58 54 31 41 708 Class B Frea: 0.036 -----------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 5 4 2 7 3 1 0 0 0 0 0 1 1 8 6 39 3.5-7.5 6 27 11 23 20 15 3 1 0 3 22 7 16 17 10 8 189 7.5-12.5 1 0 0 3 1 0 3 1 22 18 10 0 3 4 1 3 70 12.5-18.5 0 0 0 0 0 0 0 1 0 4 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 8 32 15 28 28 18 7 3 22 25 32 7 20 22 19 17 303 Class C Frea: 0.051 --------------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 8 3 5 5 5 4 1 0 1 1 1 1 1 4 8 5 53 3.5-7.5 4 27 17 19 21 13 12 1 7 10 22 14 23 27 14 6 237 7.5-12.5 2 9 3 3 1 0 6 0 37 40 10 2 8 5 4 2 132 12.5-18.5 0 0 0 0 0 0 2 0 0 7 1 0 0 0 2 0 12 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 14 39 25 27 27 17 21 1 45 58 34 17 32 36 28 13 434 Cl ----. *--.* -* *-* mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 62 58 57 67 58 21 20 9 17 16 19 12 36 34 47 48 581 3.5-7.5 73 169 125 123 91 75 90 38 157 261 136 122 169 151 123 65 1968 7.5-12.5 17 60 8 10 9 5 30 16 90 210 31 44 64 80 51 18 743 12.5-18.5 2 7 3 7 0 0 5 14 7 9 7 0 1 41 34 1 138 18.5-24 0 3 1 1 0 0 0 3 0 0 0 0 0 0 0 0 8 >24 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 .0 1 TOTAL 154 297 194 209 158 101 145 80 271 496 193 178 270 306 255 132 3439 Page 58 Table A-1 (continued)
Jan-Dec 2016 Class E Frea: 0.323 ' mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW 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 21 33 25 32 44 32 35 37 53 48 45 84 74 67 53 24 707 3.5-7.5 42 28 7 28 36 25 58 96 105 233 218 260 139 82 65 42 1464 7.5-12.5 8 16 0 3 7 10 24 18 25 166 80 22 13 27 16 5 440 12.5-18.5 3 11 1 2 0 0 3 10 23 22 4 0 0 0 2 5 86 18.5-24 2 8 3 3 0 0 0 3 7 0 0 0 0 0 0 0 26 >24 0 0 6 1 0 0 0 0 1 0 0 0 0 0 0 0 8 TOTAL 76 96 42 69 87 67 121 164 214 469 347 366 226 176 136 76 2732 Cl F ass F req: 0 082 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 1 0 0 1 0 1 1 1 1 1 0 7 0.95-3.5 5 4 2 6 3 4 7 13 21 19 50 91 61 20 14 6 326 3.5-7.5 1 0 1 4 4 1 2 12 21 44 137 48 16 4 1 3 299 7.5-12.5 0 0 0 0 0 0 0 4 2 17 39 0 1 0 0 0 63 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 6 4 3 10 7 6 9 29 45 80 227 140 79 25 16 9 695 Class G Frea: 0.017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 2 0.95-3.5 0 0 1 0 1 0 0 1 2 0 9 28 8 3 0 3 56 3.5-7.5 0 0 0 3 0 0 0 0 0 6 50 8 *o 0 0 1 68 7.5-12.5 0 0 0 0 0 0 0 1 0 5 15 1 0 0 0 0 22 12.5-18.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18.5-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 1 4 1 0 0 3 2 11 74 37 8 3 0 4 148 Cl All ass F rea: 1 000 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 1 0 1 1 1 1 0 1 1 1 1 1 0 10 0.95-3.5 112 112 111 117 122 66 64 60 94 84 124 216 181 132 132 97 1824 3.5-7.5 194 351 235 269 221 151 172 149 292 559 588 461 396 317 242 158 4755 7.5-12.5 35 108 12 21 18 16 70 40 189 471 187 70 114 131 72 31 1585 12.5-18.5 5 18 4 9 0 0 10 25 31 42 12 0 1 41 38 6 242 18.5-24 2 11 4 4 0 0 0 6 7 0 0 0 0 0 0 0 34 >24 0 0 6 2 0 0 0 0 1 0 0 0 0 0 0 0 9 TOTAL 348 600 372 423 361 234 317 281 615 1156 912 748 693 622 485 292 8459 Page 59
Jan-Mar 2016 Class A Frea: 0.066 mph N NNE Calm-0.95 0 0 0.95-3.5 0 0 3.5-7.5 0 3 7.5-12.5 6 6 12.5-18.5 2 4 18.5-24 3 1 >24 4 0 TOTAL 15 14 Class B Freq: 0.024 mph N NNE Calm-0.95 0 0 0.95-3.5 0 0 3.5-7.5 0 1 7.5-12.5 2 0 12.5-18.5 0 0 18.5-24 0 0 >24 1 0 TOTAL 3 1 Cl C F 0 044 ass req: mph N NNE Calm-0.95 0 0 0.95-3.5 0 0 3.5-7.5 2 1 7.5-12.5 1 2 12.5-18.5 1 0 18.5-24 1 0 >24 1 2 TOTAL 6 5 Class D Freq: 0.390 mph N NNE Calm-0.95 0 0 0.95-3.5 1 1 3.5-7.5 3 4 7.5-12.5 4 7 12.5-18.5 4 8 18.5-24 14 5 >24 18 6 TOTAL 44 31 Table A-2 Joint Frequency Distribution of Wind Directions and Speeds For the 220-ft level of the 220-ft Tower NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 1 0 0 0 0 0 0 0 1 2 7 1 10 2 1 0 0 0 0 1 2 1 6 0 0 3 0 0 0 2 2 0 4 5 0 2 0 0 0 0 0 0 0 0 7 1 0 0 0 0 0 0 0 0 0 0 0 14 14 5 11 5 1 0 0 2 2 1 14 23 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 1 2 0 1 0 0 0 0 0 1 0 2 0 0 1 2 0 0 1 2 2 0 0 1 0 2 4 0 2 0 0 1 0 0 1 0 0 1 0 0 0 1 0 0 0 0 0 2 1 5 7 3 2 1 1 3 2 1 1 5 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0 0 0 0 0 0 1 1 0 1 3 0 0 0 1 0 0 0 0 1 1 0 0 3 0 1 8 5 0 2 2 0 3 2 0 2 0 0 5 0 0 3 1 0 0 1 0 1 0 0 4 2 0 0 1 4 5 4 3 6 0 1 18 7 0 5 5 NE ENE E ESE SE SSE s SSW SW WSW w WNW 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 1 6 6 2 6 2 1 0 4 5 4 4 1 3 9 10 10 6 4 5 11 7 3 11 11 10 12 4 9 3 0 1 39 26 9 12 42 9 7 12 2 1 5 0 25 18 3 19 34 3 15 2 0 0 2 1 3 3 0 5 38 32 49 30 27 13 12 7 82 59 19 51 127 Page 60 NW NNW TOTAL 0 0 0 0 0 0 0 1 11 4 3 44 0 4 32 0 4 18 0 0 18 4 12 123 NW NNW TOTAL 0 0 0 0 0 0 0 2 5 1 1 11 1 1 11 1 1 12 0 0 5 3 5 44 NW NNW TOTAL 0 0 0 0 0 0 1 0 8 1 0 10 3 1 28 3 1 21 1 1 14 9 3 81 NW NNW TOTAL 0 0 0 1 1 7 7 7 62 13 3 117 14 6 199 35 15 204 24 17 137 94 49 726 Table A-2 (continued)
Jan-Mar 2016 ------.. --.* -----moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 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 1 0 2 2 1 1 1 2 0 2 1 1 0 0 2 1 17 3.5-7.5 5 2 1 1 4 7 9 7 3 1 3 7 9 5 1 3 68 7.5-12.5 8 3 4 8 3 8 10 14 12 12 11 11 37 31 15 8 195 12.5-18.5 8 3 1 8 5 5 5 7 15 29 49 21 21 47 14 16 254 18.5-24 4 6 0 3 6 1 4 5 13 45 42 6 8 8 11 6 168 >24 13 10 10 7 4 0 0 3 11 5 2 0 0 2 11 6 84 TOTAL 39 24 18 29 24 22 29 38 54 94 108 46 75 93 54 40 787 -*---* . *--* -*---mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 1 0 0 0 0 0 0 0 1 0 1 0 0 0 0 4 3.5-7.5 1 1 0 1 0 0 1 0 0 1 2 2 0 0 2 0 11 7.5-12.5 1 2 0 0 0 0 0 2 4 4 3 1 8 5 2 3 35 12.5-18.5 0 0 0 1 0 0 0 2 7 0 10 12 2 6 0 0 40 18.5-24 0 0 0 0 0 0 0 0 0 0 3 1 0 0 0 0 4 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 4 0 2 0 0 1 4 11 6 18 17 10 11 4 3 94 -----mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.5-12.5 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 0 3 12.5-18.5 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 2 18.5-24 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 2 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 0 1 0 3 2 1 0 0 0 7 -*---.... . ---------moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 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 3 2 1 1 2 2 0 3 1 2 0 1 3 2 28 3.5-7.5 11 12 10 11 9 13 12 8 3 6 10 13 14 9 11 13 165 7.5-12.5 22 20 16 20 24 24 17 20 21 28 22 18 59 50 36 18 415 12.5-18.5 15 15 18 22 10 19 11 9 26 80 95 42 41 103 32 28 566 18.5-24 22 12 9 17 24 3 9 10 13 76 64 11 38 44 50 27 429 >24 37 18 13 23 7 0 1 6 12 12 7 0 5 57 36 24 258 TOTAL 110 79 69 95 76 60 52 55 75 205 199 86 157 264 168 112 1862 Page 61 Table A-2 (continued)
Apr-Jun 2016 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 4 9 5 0 1 0 0 0 0 0 0 0 0 2 0 1 22 7.5-12.5 13 10 5 7 17 4 0 2 1 1 0 0 2 5 5 8 80 12.5-18.5 24 8 6 7 9 2 1 0 4 5 0 1 6 3 3 9 88 18.5-24 8 7 0 0 0 0 0 0 0 2 0 0 9 5 5 5 41 >24 13 4 0 0 0 0 0 0 0 0 0 0 7 6 1 1 32 TOTAL 62 38 16 14 27 6 1 2 5 8 0 1 24 21 14 24 263 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 3.5-7.5 0 3 1 4 1 0 0 0 0 0 0 0 1 0 3 0 13 7.5-12.5 2 1 0 3 4 7 1 0 2 0 1 1 1 0 0 1 24 12.5-18.5 1 1 3 1 1 2 2 1 6 10 2 1 2 2 0 0 35 18.5-24 0 1 1 0 0 0 0 0 0 4 0 0 4 1 1 0 12 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 TOTAL 3 6 5 8 6 9 3 2 8 14 3 2 8 5 4 1 87 Class C Frea: 0.066 -------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 1 4 6 4 5 1 0 0 1 0 1 1 2 1 2 2 31 7.5-12.5 2 7 0 2 2 7 4 0 3 7 1 4 1 1 2 3 46 12.5-18.5 1 1 2 1 3 3 2 0 16 13 5 1 3 0 0 0 51 18.5-24 1 0 0 0 0 0 0 0 1 5 0 0 1 1 1 0 10 . >24 1 4 0 0 0 0 0 0 0 0 0 0 0 2 0 0 7 TOTAL 6 16 8 7 10 11 6 0 21 25 7 6 7 5 5 5 145 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 3 3 3 1 2 1 0 1 1 0 0 0 0 0 0 17 3.5-7.5 9 11 22 16 27 15 5 6 7 2 4 1 2 3 8 6 144 7.5-12.5 15 15 17 14 22 26 21 10 36 47 14 8 7 3 6 15 276 12.5-18.5 5 5 9 6 8 5 17 5 30 87 34 11 14 3 3 9 251 18.5-24 10 7 4 7 4 0 0 7 5 42 6 5 16 6 5 4 128 >24 17 22 0 0 0 0 0 4 1 4 0 0 5 14 5 3 75 TOTAL 58 63 55 46 62 48 44 32 80 183 58 25 44 29 27 37 891 Page 62 Table A-2 (continued}
Apr-Jun 2016 -------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 .o 0 0 0 0 0 0.95-3.5 2 2 5 3 4 0 1 0 0 1 1 0 0 0 1 3 23 3.5-7.5 3 5 1 4 6 7 6 10 8 7 3 1 1 1 2 3 68 7.5-12.5 4 7 1 0 6 9 8 13 13 12 7 10 13 6 11 5 125 12.5-18.5 6 4 2 1 2 2 4 6 6 30 22 27 34 9 12 9 176 18.5-24 10 2 0 0 0 0 0 0 2 34 26 7 9 12 6 14 122 >24 1 0 0 0 0 0 0 0 0 14 5 0 0 5 1 1 27 TOTAL 26 20 9 8 18 18 19 29 29 98 64 45 57 33 33 35 541 mch N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 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 0 1 0 0 1 0 2 0 3 0 0 1 0 0 0 1 9 3.5-7.5 1 1 2 0 4 3 3 2 3 4 3 3 1 3 5 0 38 7.5-12.5 2 1 0 0 1 3 5 2 6 4 3 6 8 6 9 3 59 12.5-18.5 1 0 0 0 0 0 1 1 0 5 6 6 16 7 5 3 51 18.5-24 0 0 0 0 0 0 0 0 0 17 10 6 3 0 1 1 38 >24 0 0 0 0 0 0 0 0 0 0 6 0 0 0 0 0 6 TOTAL 4 3 2 0 6 6 11 5 12 30 28 22 28 16 20 9 202 -----mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 0 0 0 0 0 1 0 0 0 0 0 1 1 0 4 3.5-7.5 0 0 0 0 1 0 1 0 0 1 0 0 4 1 1 0 9 7.5-12.5 0 0 0 0 0 1 0 0 1 1 2 4 3 1 2 0 15 12.5-18.5 0 1 0 0 0 0 0 0 0 2 4 5 3 1 1 0 17 18.5-24 0 0 0 0 0 0 0 0 0 1 6 1 2 0 0 0 10 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 1 0 0 1 1 1 1 1 5 12 10 12 4 5 0 55 Cl ---.... F -. --.-1.000 -----mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 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 5 6 8 6 6 2 4 2 4 2 1 1 0 1 2 4 54 3.5-7.5 18 33 37 28 45 26 15 18 19 14 11 6 11 11 21 12 325 7.5-12.5 38 41 23 26 52 57 39 27 62 72 28 33 35 22 35 35 625 12.5-18.5 38 20 22 16 23 14 27 13 62 152 73 52 78 25 24 30 669 18.5-24 29 17 5 7 4 0 0 7 8 105 48 19 44 25 19 24 361 >24 32 30 0 0 0 0 0 4 1 18 11 0 12 29 7 5 149 TOTAL 160 147 95 83 130 99 85 71 156 363 172 111 180 113 108 111 2184 Page 63 Table A-2 (continued)
Jul-Sep 2016 Class A Frea: 0.103 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 3 6 13 2 2 0 0 1 1 0 0 0 0 2 3 3 36 7.5-12.5 15 6 5 9 10 16 3 0 0 0 1 1 6 10 2 3 87 12.5-18.5 7 11 14 1 3 7 5 0 5 8 2 1 4 7 1 2 78 18.5-24 4 1 2 3 1 0 0 0 0 2 0 0 2 2 1 1 19 >24 0 5 0 1 0 0 0 0 0 0 0 0 0 0 0 1 7 TOTAL 29 29 34 16 16 23 8 1 6 10 3 2 12 21 7 10 227 Cl B F 0 055 ass rea: mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 2 3 3 2 4 0 0 0 0 0 0 1 1 1 2 4 23 7.5-12.5 2 2 0 4 2 11 0 1 0 2 7 5 4 2 1 5 48 12.5-18.5 2 1 4 1 1 2 2 0 7 8 14 3 0 2 0 0 47 18.5-24 0 0 1 0 0 0 0 0 0 1 1 0 0 0 0 0 3 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 6 6 8 7 7 13 2 1 7 11 22 9 5 5 3 9 121 Cl C F 0 061 ass rea: mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 3 1 4 4 0 2 1 0 1 2 1 1 1 1 4 4 30 7.5-12.5 0 0 0 0 2 11 6 1 2 4 8 5 1 3 0 2 45 12.5-18.5 0 0 7 0 0 1 1 0 5 13 9 0 3 4 2 1 46 18.5-24 0 1 2 1 0 0 0 0 0 3 1 0 0 1 0 0 9 >24 1 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 TOTAL 4 4 13 6 2 14 8 1 8 22 19 6 5 9 6 7 134 Class D Frea: 0.380 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0.95-3.5 1 3 7 2 2 1 0 2 0 0 1 0 0 0 0 1 20 3.5-7.5 12 10 17 14 13 14 4 6 3 5 8 4 2 6 1 6 125 7.5-12.5 13 8 7 6 24 30 16 12 13 33 28 10 6 3 6 13 228 12.5-18.5 3 10 38 11 4 4 2 1 12 169 55 7 8 7 1 4 336 18.5-24 0 14 12 15 3 0 0 0 0 28 12 1 2 6 3 3 99 >24 2 11 0 13 1 0 0 0 0 0 0 0 0 0 0 2 29 TOTAL 31 56 81 61 47 49 22 21 29 235 104 22 18 22 11 29 838 Page 64 Table A-2 (continued)
Jul-Sep 2016 Cl ass E F req: 0267 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 2 1 5 0 4 0 1 0 0 1 0 1 0 0 0 15 3.5-7.5 4 4 6 7 6 7 4 4 9 1 3 3 2 3 5 8 76 7.5-12.5 3 4 9 7 11 7 14 11 7 11 14 11 12 9 8 9 147 12.5-18.5 9 2 2 8 2 0 6 4 5 84 58 21 19 11 13 12 256 18.5-24 3 1 0 0 0 0 0 0 0 48 23 0 0 2 5 6 88 >24 3 0 0 1 0 0 0 0 0 0 0 0 0 0 0 3 7 TOTAL 22 13 18 28 19 18 24 20 21 144 99 35 34 25 31 38 589 Class F F req: 0. 12 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 1 1 2 0 1 0 1 0 0 0 0 1 1 1 0 9 3.5-7.5 1 0 1 0 2 3 0 6 1 5 2 3 0 2 4 4 34 7.5-12.5 2 0 0 0 0 0 8 4 10 3 2 6 10 11 11 10 77 12.5-18.5 1 0 0 0 0 0 0 1 5 8 19 15 10 16 12 9 96 18.5-24 0 0 0 0 0 0 0 0 0 2 20 2 0 0 0 4 28 >24 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 3 TOTAL 5 1 2 2 2 4 8 12 16 18 43 26 21 30 28 29 247 Class G Freq: 0.024 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 0 1 1 0 1 0 0 1 2 0 1 0 1 0 9 3.5-7.5 0 0 0 0 0 0 0 1 3 0 2 0 2 0 0 1 9 7.5-12.5 0 0 0 0 0 0 0 0 1 0 2 8 8 1 1 1 22 12.5-18.5 0 0 0 0 0 0 0 0 0 1 6 2 1 1 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 1 1 TOTAL 1 0 0 1 1 0 1 1 4 2 12 10 12 2 2 3 52 Class All Freq: 1.000 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0.95-3.5 2 6 9 11 3 6 1 4 0 1 4 0 3 1 2 1 54 3.5-7.5 25 24 44 29 27 26 9 18 18 13 16 12 8 15 19 30 333 7.5-12.5 35 20 21 26 49 75 47 29 33 53 62 46 47 39 29 43 654 12.5-18.5 22 24 65 21 10 14 16 6 39 291 163 49 45 48 29 28 870 18.5-24 7 17 17 19 4 0 0 0 0 84 57 3 4 11 9 14 246 >24 7 18 0 15 1 0 0 0 0 0 0 0 0 0 0 9 50 TOTAL 98 109 156 121 94 121 73 57 91 442 302 110 107 114 88 125 2208 Page 65 Table A-2 (continued)
Oct-Dec 2016 Frea: 0.04 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 8 6 3 3 3 0 0 0 0 0 0 0 0 0 0 23 7.5-12.5 2 3 2 1 7 10 0 0 0 0 0 0 0 0 0 1 26 12.5-18.5 7 1 3 0 7 0 0 0 0 0 0 0 0 1 1 7 27 18.5-24 1 1 0 0 0 0 0 0 0 0 0 0 0 1 1 9 13 >24 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 6 TOTAL 12 13 11 4 17 13 0 0 0 0 0 0 0 2 2 21 95 -------mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 7 7.5-12.5 0 1 2 0 1 1 1 0 0 0 1 0 0 4 1 1 13 12.5-18.5 4 2 0 0 0 0 0 0 0 0 1 0 0 6 2 1 16 18.5-24 1 2 0 0 0 0 0 0 0 0 0 0 0 3 2 4 12 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 1 3 TOTAL 6 6 3 1 2 2 2 0 0 0 2 0 0 15 5 7 51 F mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 0 0 0 2 0 0 1 0 0 0 0 1 0 0 2 0 6 7.5-12.5 0 1 1 0 1 2 1 0 0 0 1 3 4 8 4 0 26 12.5-18.5 0 2 1 1 1 0 0 0 1 0 3 0 2 5 2 0 18 18.5-24 0 2 0 0 0 0 0 0 0 0 0 0 3 7 2 2 16 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 5 3 0 8 TOTAL 0 5 2 3 2 2 2 0 1 0 4 4 9 25 13 2 74 Cl ----F .. --0.447 -* . mph N NNE NE ENE E ESE SE SSE S. SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 6 3 1 1 0 0 0 0 0 0 0 0 0 0 1 1 13 3.5-7.5 3 8 9 4 3 5 4 3 0 2 4 2 7 8 13 14 89 7.5-12.5 9 2 14 6 7 7 16 12 8 17 23 16 20 10 12 5 184 12.5-18.5 2 14 14 12 13 5 13 3 3 19 17 47 59 30 32 24 307 18.5-24 7 18 2 5 3 2 1 7 0 5 6 27 41 60 60 26 270 >24 22 7 0 5 0 0 0 0 0 0 3 0 6 21 37 21 122 TOTAL 49 52 40 33 26 19 34 25 11 43 53 92 133 129 155 91 985 Page 66 Table A-2 (continued)
Oct-Dec 2016 Class E mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 1 0 3 0 1 1 2 2 2 1 0 0 0 1 0 2 16 3.5-7.5 3 1 2 4 5 3 10 2 6 3 1 4 7 4 10 5 70 7.5-12.5 3 5 1 3 2 6 19 17 8 10 22 10 27 26 12 6 177 12.5-18.5 3 5 1 4 3 4 19 23 20 12 47 60 56 29 32 16 334 18.5-24 6 0 0 0 4 5 6 4 1 18 54 24 24 15 11 6 178 >24 9 3 0 0 4 5 2 0 0 3 5 0 1 1 5 1 39 TOTAL 25 14 7 11 19 24 58 48 37 47 129 98 115 76 70 36 814 moh N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 . 0 0 0 0 1 0 0 0 0 1 0.95-3.5 0 0 0 0 1 1 0 1 1 3 0 0 1 0 2 0 10 3.5-7.5 2 1 3 1 2 3 4 3 4 1 0 2 1 2 2 0 31 7.5-12.5 0 0 0 0 0 0 1 5 7 8 1 2 9 12 10 3 58 12.5-18.5 0 2 0 0 0 0 1 2 5 6 8 12 4 1 3 0 44 18.5-24 0 0 0 0 0 0 0 0 0 0 4 4 0 0 0 0 8 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 2 3 3 1 3 4 6 11 17 18 13 21 15 15 17 3 152 Class G mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 3.5-7.5 1 3 1 0 1 0 0 0 0 1 0 1 2 0 1 1 12 7.5-12.5 2 1 0 0 0 0 0 0 1 0 1 1 4 3 0 0 13 12.5-18.5 0 0 0 0 0 0 0 0 0 0 3 2 2 0 0 0 7 18.5-24 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3 4 1 0 1 0 0 0 1 1 6 4 8 3 1 1 34 Class All --------. *--.-**---mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 1 0.95-3.5 7 3 4 1 2 2 2 3 3 4 1 0 1 1 3 3 40 3.5-7.5 10 22 22 15 15 15 20 8 10 7 5 10 17 14 28 20 238 7.5-12.5 16 13 20 10 18 26 38 34 24 35 49 32 64 63 39 16 497 12.5-18.5 16 26 19 17 24 9 33 28 29 37 79 121 123 72 72 48 753 18.5-24 15 23 2 5 7 7 7 11 1 23 65 55 68 86 76 47 498 >24 33 10 0 5 4 5 2 0 0 3 8 0 7 29 45 27 178 TOTAL 97 97 67 53 70 64 102 84 67 109 207 219 280 265 263 161 2205 Page 67 Table A-2 (continued)
Jan-Dec 2016 Class A Frea: 0.084 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.5-7.5 7 26 25 7 7 3 0 1 1 0 0 0 1 6 3 5 92 7.5-12.5 36 25 19 18 44 32 4 2 1 1 1 2 10 16 11 15 237 12.5-18.5 40 24 29 8 19 12 6 0 9 15 4 2 14 16 5 22 225 18.5-24 16 10 2 5 1 0 0 0 0 4 0 0 18 9 7 19 91 >24 19 9 0 1 0 0 0 0 0 0 0 0 7 20 1 6 63 TOTAL 118 94 75 39 71 47 10 3 11 20 5 4 50 67 27 67 708 Class B Frea: 0.036 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 3.5-7.5 3 8 5 7 8 1 1 0 0 0 0 1 2 1 5 6 48 7.5-12.5 6 4 3 9 7 20 2 1 2 2 9 7 5 8 3 8 96 12.5-18.5 7 4 7 2 3 6 4 1 14 20 19 4 2 11 3 2 109 18.5-24 1 3 2 2 4 0 2 0 0 6 1 0 5 4 4 5 39 >24 1 0 0 1 0 *o 0 1 0 0 0 0 0 6 0 1 10 TOTAL 18 19 17 21 22 27 9 4 16 28 29 12 14 30 15 22 303 Cl C F 0 051 ass rea: mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 3.5-7.5 6 6 12 11 5 3 2 0 2 2 2 3 3 3 9 6 75 7.5-12.5 3 10 2 2 6 23 11 1 5 12 10 12 6 12 7 5 127 12.5-18.5 2 3 11 3 4 4 6 0 23 34 22 1 10 11 7 2 143 18.5-24 2 3 2 4 2 0 2 0 1 13 1 0 7 10 6 3 56 >24 3 8 0 0 1 0 1 0 0 4 2 0 0 8 4 1 32 TOTAL 16 30 27 21 18 30 22 1 31 65 37 16 26 44 33 17 434 Class D Frea: 0.407 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0.95-3.5 10 10 12 6 3 3 2 2 1 1 1 0 0 1 2 3 57 3.5-7.5 27 33 54 40 45 40 15 16 10 13 21 11 15 18 29 33 420 7.5-12.5 41 32 41 35 63 73 59 38 62 108 72 37 44 27 37 36 805 12.5-18.5 14 37 71 41 29 23 35 9 46 314 132 74 93 82 50 43 1093 18.5-24 31 44 27 34 22 4 2 19 5 100 42 36 78 106 103 48 701 >24 59 46 3 33 3 0 0 6 2 7 6 0 16 73 66 43 363 TOTAL 182 202 208 189 165 143 113 90 127 543 274 158 246 307 287 206 3440 Page 68
Table A-2 (continued)
Jan-Dec 2016 Cl E ass F rea: 0 323 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 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 4 4 11 10 6 6 4 5 2 4 3 1 1 1 3 6 71 3.5-7.5 15 12 10 16 21 24 29 23 26 12 10 15 19 13 18 19 282 7.5-12.5 18 19 15 18 22 30 51 55 40 45 54 42 89 72 46 28 644 12.5-18.5 26 14 6 21 12 11 34 40 46 155 176 129 130 96 71 53 1020 18.5-24 23 9 0 3 10 6 10 9 16 145 145 37 41 37 33 32 556 >24 26 13 10 8 8 5 2 3 11 22 12 0 1 8 17 11 157 TOTAL 112 71 52 76 80 82 130 135 141 383 400 224 281 227 188 149 2731 Cl F ass F req: 0 082 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 2 0.95-3.5 1 3 1 2 2 2 2 2 4 4 0 2 2 1 3 1 32 3.5-7.5 5 3 6 2 8 9 8 11 8 11 7 10 2 7 13 4 114 7.5-12.5 5 3 0 0 1 3 14 13 27 19 9 15 35 34 32 19 229 12.5-18.5 2 2 0 1 0 0 2 6 17 19 43 45 32 30 20 12 231 18.5-24 0 0 0 0 0 0 0 0 0 19 37 13 3 0 1 5 78 >24 1 0 0 0 0 0 0 0 0 0 6 0 0 0 0 2 9 TOTAL 14 11 7 5 11 14 26 32 56 72 102 86 74 72 69 44 695 Class G Freq: 0.017 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.95-3.5 2 0 0 1 1 0 1 1 0 1 3 0 1 1 2 0 14 3.5-7.5 1 3 1 0 2 0 1 1 3 2 2 1 8 1 2 2 30 7.5-12.5 2 1 0 0 0 1 0 0 3 1 6 14 16 5 3 1 53 12.5-18.5 0 1 0 0 0 0 0 0 1 3 14 9 6 2 1 0 37 18.5-24 0 0 0 0 0 0 0 0 0 1 8 2 2 0 0 0 13 >24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 TOTAL 5 5 1 1 3 1 2 2 7 8 33 26 33 9 8 4 148 Class All Freq: 1.000 mph N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TOTAL Calm-0.95 0 0 0 0 1 0 0 0 1 0 0 1 0 0 0 1 4 0.95-3.5 17 17 24 20 12 11 9 11 7 10 7 3 4 4 10 10 176 3.5-7.5 64 91 113 83 96 80 56 52 50 40 42 41 50 49 79 75 1061 7.5-12.5 111 94 80 82 143 182 141 110 140 188 161 129 205 174 139 112 2191 12.5-18.5 91 85 124 76 67 56 87 56 156 560 410 264 287 248 157 134 2858 18.5-24 73 69 33 48 39 10 16 28 22 288 234 88 154 166 154 112 1534 >24 109 76 13 43 12 5 3 10 13 33 26 0 24 115 88 65 635 TOTAL 465 432 387 352 370 344 312 267 389 1119 880 526 724 756 627 509 8459 Page 69 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 many of the onsite wells. Although gamma spectroscopy indicated the presence of 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 lron-55, Nickel-63, Strontium-89, and Strontium-90 on a less frequent basis. These to-detect radionuclides were also non-detectable in all of the wells sampled and analyzed during 2016. A summary of the results of the tritium analyses conducted in 2016 are presented in the following table. In this table, a value of "NOA< 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 16-Jan-2016 contained no detectable
- tritium, and a minimum detectable concentration of 369 pCi/L was achieved on that sample. The achieved sensitivity of 369 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 70 Installation Number of Number of Minimum Maximum Monitoring Well ID Date Samples Positive Concentration Concentration Results pCi/L pCi/L MW201 Nov-2007 4 3 NOA< 317 556 MW202 Nov-2007 4 2 NOA< 322 873 MW202-I Apr-2010 4 1 NOA< 323 345 MW203 Nov-2007 Well decommissioned in 2013 during construction of ISFSI pad MW204 Nov-2007 4 1 NOA< 333 555 MW205 Apr-2010 4 4 500 877 MW206 Apr-2010 45 8 NOA< 265 1028 MW207 Apr-2010 4 2 NOA< 265 624 MW208-S Apr-2010 4 0 NOA< 272 NOA< 336 MW208-I Apr-2010 4 0 NOA< 326 NOA< 344 MW209 Aug-2010 24 24 453 1060 MW210 Aug-2010 4 4 690 1180 MW211 Aug-2010 34 34 1050 2080 MW212 Aug-2010 4 4 580 815 MW213 Aug-2010 4 0 NOA< 269 NOA< 330 MW214 Aug-2010 4 0 NOA< 324 NOA< 344 MW215 Dec-2011 32 32 589 1260 MW216 Sep-2012 45 45 903 5430 MW217 Dec-2011 4 2 NOA< 330 438 MW218 Nov-2013 45 45 1640 6070 MW219 Dec-2013 11 11 754 1370 MW220 Dec-2014 4 4 450 718 MW3 Jul-1987 4 0 NOA< 315 NOA< 337 MW4 Jul-1997 Well decommissioned in 2013 during installation of MW4R MW4-R Nov-2013 4 0 NOA< 269 NOA< 321 All Wells --300 226 NOA< 265 6070 Intake Canal West --52 0 NOA< 174 NOA< 348 Intake Canal East --3 0 NOA< 305 NOA< 337 Concentrations of tritium detected in the onsite wells ranged from non-detectable at less than 17 4 pCi/L, up to a maximum concentration of 6070 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 MW218 (average concentration
= 3545 pCi/L) was consumed as drinking water for an entire year, the maximum dose consequence would be less than 0.31 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 71 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 2016, 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 468 pCi/L, the annual discharge of tritium into the intake bay under this hypothetical scenario would be 0.00585 Curies. This activity represents less than 0.009% 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 0.00585 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 2016 was 612 billion Liters, yielding an effective concentration of tritium in the intake bay of about 0.0096 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 0.0000000055
- 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. Page 72 Shoreline Segment Number . 1 2 3 4 Monitoring Well Number MW204 MW205 MW202 MW201 Hydraulic Conductivity
-cm/sec 1.99E-03 4.27E-03 3.13E-03 5.64E-03 Hydraulic Slope 0.014 0.014 0.014 0.014 Porosity 0.300 0.300 0.300 0.300 Flow Velocity
-m/day 8.02E-02 1.72E-01 1.26E-01 2.27E-01 Flow Velocity
-fUyr 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 Laver -m 3.0 3.0 3.0 3.0 Volumetric Discharge -m3/dav 4.40E+OO 5.90E+OO 5.19E+OO 1.87E+01 Volumetric Discharge
-Liter/vr 1.61E+06 2.16E+06 1.90E+06 6.84E+06 Annual Average H-3 Concentration
-pCi/L 3.95E+02 6.47E+02 5.12E+02 4.17E+02 Annual Segment Tritium Discharge
-Ci/yr 6.34E-04 1.40E-03 9.71E-04 2.85E-03 Total Volumetric Discharge
-Uyr 1.25E+07 Total H-3 Discharge
-Ci/yr 5.85E-03 Annual Circulating Water Flow -Liter/yr 6.12E+11 Discharge Canal H-3 Concentration
-Ci/L 9.56E-15 Discharge Canal H-3 Concentration
-pCi/L 9.56E-03 Max. lndiv. Dose Factor -mrem/yr per Ci/L 5.73E+05 Maximum Individual Dose -mrem/yr 5.47E-09 In conclusion, the only radionuclide detected in groundwater during the 2016 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 2016, the total dose impact to a maximally-exposed member of the public would have been much less than 1 mrem/yr.
Page 73 APPENDIXC CORRECTIONS TO PREVIOUS EFFLUENT REPORTS There were no corrections made to previous effluent reports during calendar-year 2016. Page 74 APPENDIX D CHANGES TO PNPS OFFSITE DOSE CALCULATION MANUAL No revisions were made to the PNPS Offsite Dose Calculation Manual (ODCM) during calendar year 2016. *
- Page 75