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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY \ RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1AND2 ANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT Serial No. S&LfTSC Docket Nos. License Nos. 17-117 RO 50-280 50-281 DPR-32 OPR-37 Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2016 through December 31, 2016. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.8.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2016 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974. If you have any further questions, please contact Lee Ragland at 757-365-2010. Douglas . awrence Director S fety & Licensing Surry Power Station Attachment Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station ATTACHMENT Serial No. 17-117 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 Annual Radioactive Effluent Release Report Surry Power Station January 1, 2016 through December.31, 2016 SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station 2016 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE' REPORT SURRY POWER STATION January 1, 2016 through December 31, 2016
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY \ RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1AND2 ANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT Serial No. S&LfTSC Docket Nos. License Nos. 17-117 RO 50-280 50-281 DPR-32 OPR-37 Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2016 through December 31, 2016. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.8.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2016 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974. If you have any further questions, please contact Lee Ragland at 757-365-2010. Douglas . awrence Director S fety & Licensing Surry Power Station Attachment Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station ATTACHMENT Serial No. 17-117 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 Annual Radioactive Effluent Release Report Surry Power Station January 1, 2016 through December.31, 2016 SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station 2016 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE' REPORT SURRY POWER STATION January 1, 2016 through December 31, 2016
* Prepared # -. __,_____ __ P. F. Blount Health Physicist Reviewed By: __ __ '&deg;_...< __ Approved By: P.R. Harris Superintendent Health P 7cal Services T. L. Ragland Manager Radiological Protection and Chemistry ANNUAL R.4.DIOACTIVE EFFLUENT RELEASE REPORT Section No. 1 2 3 4 FOR THE SURRY POWER STATION January 1, 2016 through December 31, 2016 Subject Executive Summary Purpose and Scope Discussion Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual {ODCM) Attachment 4 Major Changes to Radioactive Liql.Jid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Sample Analysis 1 2 3 4 Attachment 8 Industry Ground Water Protection Initiative I I -FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-280, 50-281, Section 6.6.B.3.
* Prepared #-1--. __,_____ __ P. F. Blount Health Physicist Reviewed By: __ __ '&deg;_...< __ Approved By: P.R. Harris Superintendent Health P 7cal Services T. L. Ragland Manager Radiological Protection and Chemistry ANNUAL R.4.DIOACTIVE EFFLUENT RELEASE REPORT Section No. 1 2 3 4 FOR THE SURRY POWER STATION January 1, 2016 through December 31, 2016 Subject Executive Summary Purpose and Scope Discussion Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual {ODCM) Attachment 4 Major Changes to Radioactive Liql.Jid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Sample Analysis 1 2 3 4 Attachment 8 Industry Ground Water Protection Initiative I I -FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-280, 50-281, Section 6.6.B.3.
EXECUTIVESUMlVIARY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Annual Radioactive Effluent Release Report describes the radiological effluent control program conducted at Surry Power Station during the 2016 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Power Station in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Power Plants", Revision 1, June 1974. The report also includes an assessment of radiation .doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents. During this reporting period, there were no unplanned liquid or gaseous effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual. Based on the 2016 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows: 1. The total body dose due to liquid effluents was l.34E-04 mrem, which is 2.23E-03% of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 1. 72E-04 mrem to the GI-LLI, which is 8.70E-04% of the 20 mrem dose limit. 2. The air dose due to noble gases in gaseous effluents was 2.22E-05 mrad gamma, which is l.1 lE-04% of the 20 mrad gamma dose limit, and 4.68E-05 mrad beta, which is l.17E-04% of the 40 mrad beta dose limit. 3. The critical organ dose from gaseous effluents due to I-131, I-133, H-3, and particulates with half-lives greater than 8 days is 9.00E-02 mrem, which is 3.00E-01 % of the 30 mrem dose limit. There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during this reporting period. There were no changes made to VPAP-2103S, Offsite Dose Calculation Manual, during this reporting period. In accordance with the Nuclear Energy Institute (NEI) Industry Ground Water Protection Initiative, analysis results of ground water monitoring locations not included in the Radiological Environmental Monitoring Program (REMP), will be included in this report. Ground water monitoring well sample results are provided in Attachment 8. 1 Based on the radioactivity measured_ and the dose calculations performed dming this reporting period, the operation of Surry Power Station has resulted in negligible radiation dose consequences to the maxi?Jlum exposed member of the public in unrestricted areas. Purpose and Scope Attachment 1 includes a summary of the quantities of radioactive liquid and gaseous effluents and .solid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annual basis following the format of Tables 1, 2 and 3 of Appendix B, thereof Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during 2016. As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to th*se systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radi0active waste treatment systems may be submitted as part of the annual FSAR update. As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6. Attachment 7 provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation. As required by the ODCM, 'Section 6. 7 .5, a summary of on-site radioactive spills or leaks that were communicated in accordance with the Industry Ground Water Protection Initiative reporting protocol, and sample analyses from ground water wells that are not part of the Environmental Monitoring Program are provided in Attachment 8. In 2016, no on-site radioactive spills or leaks were communicated in accordance with the Industry Ground Water Protection Initiative. Attachment 9 provides a redetermination of the gaseous effluent doses reported for 2015. In November of 2016, it was discovered that atmospheric dispersion and deposition factors were determined using meteorological data that was processed as delta-degrees Celsius vice degrees Fahrenheit. Dispersion and deposition factors were updated based on delta-degrees Fahrenheit and the revised doses are provided. The revised doses represent a 4% to 5% increase in the noble gas air doses originally reported. No gaseous effluent dose limits were challenged due to the misprocessed meteorological data. 2 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM; Section 6.3.1, which requires that the dose rate for iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary. The critical receptor was modeled as a teenage individual via the inhalation pathway._-_--__ The basis for the calculation of the percent of technical specification for the total body and skin in Table IA of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal te 500 mrem/yr to the total body and iess than or equal to 3 000 mrem/yr to the skin. The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 is the ODCM, Section 6.2.1, which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 1 OCFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/mL. Percent of technical specification calculations are based on the total gaseous or liquid effluents released for the respective quarter.
EXECUTIVESUMlVIARY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Annual Radioactive Effluent Release Report describes the radiological effluent control program conducted at Surry Power Station during the 2016 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Power Station in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Power Plants", Revision 1, June 1974. The report also includes an assessment of radiation .doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents. During this reporting period, there were no unplanned liquid or gaseous effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual. Based on the 2016 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows: 1. The total body dose due to liquid effluents was l.34E-04 mrem, which is 2.23E-03% of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 1. 72E-04 mrem to the GI-LLI, which is 8.70E-04% of the 20 mrem dose limit. 2. The air dose due to noble gases in gaseous effluents was 2.22E-05 mrad gamma, which is l.1 lE-04% of the 20 mrad gamma dose limit, and 4.68E-05 mrad beta, which is l.17E-04% of the 40 mrad beta dose limit. 3. The critical organ dose from gaseous effluents due to I-131, I-133, H-3, and particulates with half-lives greater than 8 days is 9.00E-02 mrem, which is 3.00E-01 % of the 30 mrem dose limit. There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during this reporting period. There were no changes made to VPAP-2103S, Offsite Dose Calculation Manual, during this reporting period. In accordance with the Nuclear Energy Institute (NEI) Industry Ground Water Protection Initiative, analysis results of ground water monitoring locations not included in the Radiological Environmental Monitoring Program (REMP), will be included in this report. Ground water monitoring well sample results are provided in Attachment 8. 1 Based on the radioactivity measured_ and the dose calculations performed dming this reporting period, the operation of Surry Power Station has resulted in negligible radiation dose consequences to the maxi?Jlum exposed member of the public in unrestricted areas. Purpose and Scope Attachment 1 includes a summary of the quantities of radioactive liquid and gaseous effluents and .solid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annual basis following the format of Tables 1, 2 and 3 of Appendix B, thereof Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during 2016. As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to th*se systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radi0active waste treatment systems may be submitted as part of the annual FSAR update. As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6. Attachment 7 provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation. As required by the ODCM, 'Section 6. 7 .5, a summary of on-site radioactive spills or leaks that were communicated in accordance with the Industry Ground Water Protection Initiative reporting protocol, and sample analyses from ground water wells that are not part of the Environmental Monitoring Program are provided in Attachment 8. In 2016, no on-site radioactive spills or leaks were communicated in accordance with the Industry Ground Water Protection Initiative. Attachment 9 provides a redetermination of the gaseous effluent doses reported for 2015. In November of 2016, it was discovered that atmospheric dispersion and deposition factors were determined using meteorological data that was processed as delta-degrees Celsius vice degrees Fahrenheit. Dispersion and deposition factors were updated based on delta-degrees Fahrenheit and the revised doses are provided. The revised doses represent a 4% to 5% increase in the noble gas air doses originally reported. No gaseous effluent dose limits were challenged due to the misprocessed meteorological data. 2 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM; Section 6.3.1, which requires that the dose rate for iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary. The critical receptor was modeled as a teenage individual via the inhalation pathway._-_--__ The basis for the calculation of the percent of technical specification for the total body and skin in Table IA of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal te 500 mrem/yr to the total body and iess than or equal to 3 000 mrem/yr to the skin. The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 is the ODCM, Section 6.2.1, which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 1 OCFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/mL. Percent of technical specification calculations are based on the total gaseous or liquid effluents released for the respective quarter.
* The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was modeled as a child at 2.05 miles with the critical organ being the bone via the ingestion pathway. ,The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas was modeled as an adult, exposed by either the invertebrate or fish pathway, with the critical organ typically being the lower large intestine. The total body dose was also determined for this individual. Attachment 5 provides a discussion on the gaseous effluent monitoring instrumentation that was inoperable for greater than 30 days. As presented in the discussion, the instrumentation remained inoperable at the end of2016. It should be noted, however, that the instrumentation was returned to operable status ill February of 2017. There were no unplanned gaseous or liquid releases in 2016 to describe in Attachment 6 as required by the ODCM, Section 6.7.2. The typical lower limit of detection (LLD) capabilities of the radioactive-effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, 3 then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower limit of detection, then the totals for this period will be designated as Not Applicable (NIA). Supplemental Information Section 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk, or if required, leafy vegetation samples, and the identification for obtaining replacement samples. As milk was available for collection during this reporting period, leafy vegetation sampling was not required. In April 2016, the control milk sample was not obtained because the dairy closed its operation. A new control milk sample location. was added to the RadioJogi.cal Environmental Monitoring Program and sampling commenced inMay 2016. As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program. Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the Radiological Environmental Monitoring Program. 4    EFFLUENT RELEASE DATA January 1, 2016 through December 31, 2016 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.
* The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was modeled as a child at 2.05 miles with the critical organ being the bone via the ingestion pathway. ,The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas was modeled as an adult, exposed by either the invertebrate or fish pathway, with the critical organ typically being the lower large intestine. The total body dose was also determined for this individual. Attachment 5 provides a discussion on the gaseous effluent monitoring instrumentation that was inoperable for greater than 30 days. As presented in the discussion, the instrumentation remained inoperable at the end of2016. It should be noted, however, that the instrumentation was returned to operable status ill February of 2017. There were no unplanned gaseous or liquid releases in 2016 to describe in Attachment 6 as required by the ODCM, Section 6.7.2. The typical lower limit of detection (LLD) capabilities of the radioactive-effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, 3 then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower limit of detection, then the totals for this period will be designated as Not Applicable (NIA). Supplemental Information Section 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk, or if required, leafy vegetation samples, and the identification for obtaining replacement samples. As milk was available for collection during this reporting period, leafy vegetation sampling was not required. In April 2016, the control milk sample was not obtained because the dairy closed its operation. A new control milk sample location. was added to the RadioJogi.cal Environmental Monitoring Program and sampling commenced inMay 2016. As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program. Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the Radiological Environmental Monitoring Program. 4    EFFLUENT RELEASE DATA January 1, 2016 through December 31, 2016 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.
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UNPLANNED RELEASES There were no unplanned liquid or unplanned gaseous releases during this reporting period. Attachment 6 Page 1 ofl LOWER LIMIT OF DETECTION (LL-U) FOR EFFLUENT SAJVIPLE ANALYSIS GASEOUS: Isotope Reguired LLD Typical LLD Kr-87 l.OOE-04 l.97E-06 -4.78E-05 Kr-88 1.00E-04 1.71E-06 -2.l3E-05 Xe-133 1.00E-04 l.05E-06 -l.68E-05 Xe-133m l.OOE-04 3.61E-06 -4.06E-05 Xe-135 l.OOE-04 4.59E-07 -l.23E-05 Xe-135m l.OOE-04 l.35E-05 -8.36E-05 Xe-138 l.OOE-04 2.32E-05 -9.90E-05 I-131 l.OOE-12 4.06E-13 -4.06E-13 I-133 l.OOE-10 4.06E-11 -4.06E-11 Sr-89 l.OOE-11 l.38E-14 -9.34E-13 Sr-90 l.OOE-11 l.77E-15 -l.14E-13 Cs-134 l.OOE-11 l.29E-13 -2.50E-13 Cs-137 l.OOE-11 1.81E-13 -3.64E-13 Mn-54 l.OOE-11 2.50E-14 -2.70E-13 Fe-59 l.OOE-11 3.41E-13 -8.38E-13 Co-58 l.OOE-11 1.72E-14 -2.86E-13 Co-60 l.OOE-11 2.58E-14 -4.79E-13 l.OOE-11 3.l3E-13 -6.99E-13 Mo-99 l.OOE-11 4.06E-12 -4.06E-12 Ce-141 l.OOE-11 2.06E-13. -2.98E-13 Ce-144 l.OOE-11 7.84E-13 -l.34E-12 Alpha l.OOE-11 l.69E-14 -2.21E-14 Tritium l.OOE-06 4.94E-08 6.82E-08 LIQUID: Sr-89 5.00E-08 2.78E-08 -4.54E-08 *sr-90 5.00E-08 6.46E-09 -9.49E-09 *Cs-134 5:00E-07 l.77E-08 -5.46E-08 Cs-137 5.00E-07 2.45E-08 -8.33E-08 I-131 1.00E-06 2.61E-08 -6.48E-08 Co-58 5.00E-07 2.18E-09 -5.99E-08 Co-60 5.00E-07 2.77E-09 -8.82E-08 Fe-59 5.00E-07 3.25E-08 -1.48E-07 Zn-65 5:00E-07 3.64E-08 -l.37E-07 Mn-54 5.00E-07 3.19E-09 -5.70E-08 Mo-99 5.00E-07 2.20E-07 4.95E-07 Ce-141 5.00E-07 3.13E-08 -9.27E-08 Ce-144 5.00E-07 l.32E-07 -3.47E-07 Fe-55 l.OOE-06 4.27E-07 -9.70E-07. Alpha l.OOE-07 2.70E-08 -2.73E-08 Tritium 1.00E-05 l.22E-06 -l.69E-06 *xe-133 1.00E-05 8.90E-08 l.73E-07 Xe-135 l.OOE-05 2.78E-08 -l.18E-07 Xe-133m l.OOE-05 2.27E-07 -3.71E-07 Xe-135m l.OOE-05 l.59E-06 -2.81E-06 Xe-138 1.00E-05 2.38E-06 -8.93E-06 Kr-87 l.OOE-05 . l.30E-07 -2.22E-07 Kr-88 l.OOE-05 l.59E-08 -7.85E-07 Attachment 7 Page 1of1    Page 1 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE -The following is a .summary of 2016 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP). Analyses are performed by an
UNPLANNED RELEASES There were no unplanned liquid or unplanned gaseous releases during this reporting period. Attachment 6 Page 1 ofl LOWER LIMIT OF DETECTION (LL-U) FOR EFFLUENT SAJVIPLE ANALYSIS GASEOUS: Isotope Reguired LLD Typical LLD Kr-87 l.OOE-04 l.97E-06 -4.78E-05 Kr-88 1.00E-04 1.71E-06 -2.l3E-05 Xe-133 1.00E-04 l.05E-06 -l.68E-05 Xe-133m l.OOE-04 3.61E-06 -4.06E-05 Xe-135 l.OOE-04 4.59E-07 -l.23E-05 Xe-135m l.OOE-04 l.35E-05 -8.36E-05 Xe-138 l.OOE-04 2.32E-05 -9.90E-05 I-131 l.OOE-12 4.06E-13 -4.06E-13 I-133 l.OOE-10 4.06E-11 -4.06E-11 Sr-89 l.OOE-11 l.38E-14 -9.34E-13 Sr-90 l.OOE-11 l.77E-15 -l.14E-13 Cs-134 l.OOE-11 l.29E-13 -2.50E-13 Cs-137 l.OOE-11 1.81E-13 -3.64E-13 Mn-54 l.OOE-11 2.50E-14 -2.70E-13 Fe-59 l.OOE-11 3.41E-13 -8.38E-13 Co-58 l.OOE-11 1.72E-14 -2.86E-13 Co-60 l.OOE-11 2.58E-14 -4.79E-13 l.OOE-11 3.l3E-13 -6.99E-13 Mo-99 l.OOE-11 4.06E-12 -4.06E-12 Ce-141 l.OOE-11 2.06E-13. -2.98E-13 Ce-144 l.OOE-11 7.84E-13 -l.34E-12 Alpha l.OOE-11 l.69E-14 -2.21E-14 Tritium l.OOE-06 4.94E-08 6.82E-08 LIQUID: Sr-89 5.00E-08 2.78E-08 -4.54E-08 *sr-90 5.00E-08 6.46E-09 -9.49E-09 *Cs-134 5:00E-07 l.77E-08 -5.46E-08 Cs-137 5.00E-07 2.45E-08 -8.33E-08 I-131 1.00E-06 2.61E-08 -6.48E-08 Co-58 5.00E-07 2.18E-09 -5.99E-08 Co-60 5.00E-07 2.77E-09 -8.82E-08 Fe-59 5.00E-07 3.25E-08 -1.48E-07 Zn-65 5:00E-07 3.64E-08 -l.37E-07 Mn-54 5.00E-07 3.19E-09 -5.70E-08 Mo-99 5.00E-07 2.20E-07 4.95E-07 Ce-141 5.00E-07 3.13E-08 -9.27E-08 Ce-144 5.00E-07 l.32E-07 -3.47E-07 Fe-55 l.OOE-06 4.27E-07 -9.70E-07. Alpha l.OOE-07 2.70E-08 -2.73E-08 Tritium 1.00E-05 l.22E-06 -l.69E-06 *xe-133 1.00E-05 8.90E-08 l.73E-07 Xe-135 l.OOE-05 2.78E-08 -l.18E-07 Xe-133m l.OOE-05 2.27E-07 -3.71E-07 Xe-135m l.OOE-05 l.59E-06 -2.81E-06 Xe-138 1.00E-05 2.38E-06 -8.93E-06 Kr-87 l.OOE-05 . l.30E-07 -2.22E-07 Kr-88 l.OOE-05 l.59E-08 -7.85E-07 Attachment 7 Page 1of1    Page 1 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE -The following is a .summary of 2016 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP). Analyses are performed by an
* independent laboratory. Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter. pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-04 3/9/16 <1,400 ND NA NA NA NA 1-PL-Piez-05 3/9/16 6,160 ND <119 <4.43 <0.461 ND 1-PL-Piez-06 3/9/16 2,580 ND <87.1 <4.44 <0.355 ND 1-PL-Piez-07 3/9/16 <1,410 ND NA NA NA .. NA 3/9/16 <1,410 ND NA NA NA . -* NA 1-PL-Piez-33 319116 <1,420 ND NA NA NA NA 1-PL-Piez-3A 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez-41 3/9/16 <1,430. ND NA NA NA NA 1-PL-Piez-42 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez.-29 3/9/16 8,340 ND <83.4-<4.62 . <0.433 ND 1-PL-Piez-04 5/11/16 <947 ND NA NA NA NA 1-PL-Piez-05 5/11/16 5,380 ND NA. NA NA NA 1-PL-Piez-06 5/11/16 2,750 ND NA NA NA NA 1-PL-Piez-07 5/11/16 <971 ND NA NA NA NA . l -PL-Piez-08 5/11/16 <958 ND NA NA NA NA 1-PL-Piez-09 5/11116 <956 NA NA NA NA NA 1-PL-Piez-20 5111116 <946 ND NA* NA NA NA 1-PL-Piez-22 5/11116 <968 ND NA NA NA NA 1-PL-Piez-24 5/11/16 <950 ND NA NA NA NA 1-PL-Piez-25 5/11116 <942 ND NA NA NA NA 1-PL-Piez-27 5/11/16 <970 ND NA NA NA NA 1-PL-Piez-28 5/11/16 <952 ND NA .. NA NA NA 1-PL-Piez-29 5/1.1/16 7,780 ND NA NA NA NA 1-PL-Piez-33 5/11/16 <953 .ND NA NA NA NA 1-PL-Piez-03 5/12/16 <964 NA NA NA NA NA 1-PL-Piez-23 5/12/16 <9.51 ND NA NA NA NA 1-PL-Piez-34 5/12/16 <954 ND NA NA NA NA 1-PL-Piez-35 5/12/16 <973 NA NA NA NA NA 1-PL-Piez-36 5/12/16 <965 NA NA NA NA NA 1-PL-Piez-37 5/12/16 <958 NA NA NA NA NA 1-PL-Piez-38 5/12/16 <967 NA NA NA .NA* NA 1-PL-Piez-39 5/12/16 <963 NA NA NA NA NA 1-PL-Piez-40 5/12/16 <963 ND NA NA NA NA 1-PL-Piez-41 5/12/16 <960 ND NA NA NA NA 1-PL-Piez-42 5/12/16 <951 ND NA NA NA NA    Page 2 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE Well Sample Tritium Gamma Fe-55
* independent laboratory. Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter. pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-04 3/9/16 <1,400 ND NA NA NA NA 1-PL-Piez-05 3/9/16 6,160 ND <119 <4.43 <0.461 ND 1-PL-Piez-06 3/9/16 2,580 ND <87.1 <4.44 <0.355 ND 1-PL-Piez-07 3/9/16 <1,410 ND NA NA NA .. NA 3/9/16 <1,410 ND NA NA NA . -* NA 1-PL-Piez-33 319116 <1,420 ND NA NA NA NA 1-PL-Piez-3A 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez-41 3/9/16 <1,430. ND NA NA NA NA 1-PL-Piez-42 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez.-29 3/9/16 8,340 ND <83.4-<4.62 . <0.433 ND 1-PL-Piez-04 5/11/16 <947 ND NA NA NA NA 1-PL-Piez-05 5/11/16 5,380 ND NA. NA NA NA 1-PL-Piez-06 5/11/16 2,750 ND NA NA NA NA 1-PL-Piez-07 5/11/16 <971 ND NA NA NA NA . l -PL-Piez-08 5/11/16 <958 ND NA NA NA NA 1-PL-Piez-09 5/11116 <956 NA NA NA NA NA 1-PL-Piez-20 5111116 <946 ND NA* NA NA NA 1-PL-Piez-22 5/11116 <968 ND NA NA NA NA 1-PL-Piez-24 5/11/16 <950 ND NA NA NA NA 1-PL-Piez-25 5/11116 <942 ND NA NA NA NA 1-PL-Piez-27 5/11/16 <970 ND NA NA NA NA 1-PL-Piez-28 5/11/16 <952 ND NA .. NA NA NA 1-PL-Piez-29 5/1.1/16 7,780 ND NA NA NA NA 1-PL-Piez-33 5/11/16 <953 .ND NA NA NA NA 1-PL-Piez-03 5/12/16 <964 NA NA NA NA NA 1-PL-Piez-23 5/12/16 <9.51 ND NA NA NA NA 1-PL-Piez-34 5/12/16 <954 ND NA NA NA NA 1-PL-Piez-35 5/12/16 <973 NA NA NA NA NA 1-PL-Piez-36 5/12/16 <965 NA NA NA NA NA 1-PL-Piez-37 5/12/16 <958 NA NA NA NA NA 1-PL-Piez-38 5/12/16 <967 NA NA NA .NA* NA 1-PL-Piez-39 5/12/16 <963 NA NA NA NA NA 1-PL-Piez-40 5/12/16 <963 ND NA NA NA NA 1-PL-Piez-41 5/12/16 <960 ND NA NA NA NA 1-PL-Piez-42 5/12/16 <951 ND NA NA NA NA    Page 2 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE Well Sample Tritium Gamma Fe-55
* Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-05 8/2/16 4,950 ND NA NA NA NA 1-PL-Piez-06 8/2/16 1,880 ND NA NA NA NA 1-PL-Piez-07 8/2/16 <931 ND NA NA NA NA 1-PL-Piez-27 8/2/16 <945 ND NA NA NA NA 1-PL-Piez-04 8/3/16 <937 ND NA NA NA NA 1-PL-Piez-29 8/3/16. -7,640 ND NA -NA NA NA l-PL-Piez-33 8/3/16 <928 ND** NA NA NA NA l-PL-Piez-34 8/3/16 <942 ND NA NA NA NA 1-PL-Piez-41 8/3/16 <934 ND NA NA NA NA 1-PL-Piez-42 8/3/16 <921 ND NA NA NA NA 1-P'L-Piez-04 12/5/16 <951 ND NA NA NA NA l -PL-Piez-05 12/5/16 . 4,840 . ND NA NA NA NA 1-PL-Piez-06 12/5/16 1,330 ND NA NA *NA NA 1-PL-Piez-07 12/5/16 <951 ND NA NA NA NA l-PL-Piez-08 12/5/16 <970 ND NA NA NA NA 1-PL-Piez-24 12/5/16 <965. ND NA NA NA NA 1-PL-Piez-25 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-27 12/5/16 <950 ND NA NA NA NA 1-PL-Piez-33 12/5/16 <952 ND NA NA NA NA 1-PL-Piez-34 12/5/16 <942 ND NA NA NA NA 1-PL-Piez-40 12/5/16 <953 ND _r NA .NA NA NA
* Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-05 8/2/16 4,950 ND NA NA NA NA 1-PL-Piez-06 8/2/16 1,880 ND NA NA NA NA 1-PL-Piez-07 8/2/16 <931 ND NA NA NA NA 1-PL-Piez-27 8/2/16 <945 ND NA NA NA NA 1-PL-Piez-04 8/3/16 <937 ND NA NA NA NA 1-PL-Piez-29 8/3/16. -7,640 ND NA -NA NA NA l-PL-Piez-33 8/3/16 <928 ND** NA NA NA NA l-PL-Piez-34 8/3/16 <942 ND NA NA NA NA 1-PL-Piez-41 8/3/16 <934 ND NA NA NA NA 1-PL-Piez-42 8/3/16 <921 ND NA NA NA NA 1-P'L-Piez-04 12/5/16 <951 ND NA NA NA NA l -PL-Piez-05 12/5/16 . 4,840 . ND NA NA NA NA 1-PL-Piez-06 12/5/16 1,330 ND NA NA *NA NA 1-PL-Piez-07 12/5/16 <951 ND NA NA NA NA l-PL-Piez-08 12/5/16 <970 ND NA NA NA NA 1-PL-Piez-24 12/5/16 <965. ND NA NA NA NA 1-PL-Piez-25 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-27 12/5/16 <950 ND NA NA NA NA 1-PL-Piez-33 12/5/16 <952 ND NA NA NA NA 1-PL-Piez-34 12/5/16 <942 ND NA NA NA NA 1-PL-Piez-40 12/5/16 <953 ND _r NA .NA NA NA *-1-PL-Piez-41 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-42 12/5/16 <944 ND NA NA NA NA Well Sample Tritium Co-58 . Ee-55 Ni-:63 . Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-29 12/5/16 6,700 16.3 NA NA NA NA 12/15/16 6,210 11.6 <67.2 <3.73 -<0.637 ND NA= Analysis not required. ND =No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs. TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241), ND = not detected ERRATA/CORRECTIONS TO PREVIOUS REPORTS Attachment 9
* PL-Piez-41 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-42 12/5/16 <944 ND NA NA NA NA Well Sample Tritium Co-58 . Ee-55 Ni-:63 . Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-29 12/5/16 6,700 16.3 NA NA NA NA 12/15/16 6,210 11.6 <67.2 <3.73 -<0.637 ND NA= Analysis not required. ND =No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs. TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241), ND = not detected ERRATA/CORRECTIONS TO PREVIOUS REPORTS Attachment 9
* Page 1 ofl 1bis section contains revised gaseous effluent doses and associated release data for 2015. In November 2016, it was determined that delta-temperature data transmitted in delta-degrees Celsius from the Surry Power Station meteorological tower was erroneously processed and used as delta-degrees Fahrenheit data. This had the potential to impact the gaseous effluent doses reported for 2015 because the dispersion ___ _ used in the calcuations where based on a joint frequency distribution determined with delta-degrees Celsius vice Fahrenheit. The delta-degrees data was converted to Fahrenheit, processed as a new joint frequency distribution, and doses for 2015 were determined using dispersion and deposition factors based on the new joint frequency distribution. The revised doses indicate minimal change to the originally reported doses. The gamma and beta air doses increased by 4% to 5% while the critical organ dose decreased 14%.
* Page 1 ofl 1bis section contains revised gaseous effluent doses and associated release data for 2015. In November 2016, it was determined that delta-temperature data transmitted in delta-degrees Celsius from the Surry Power Station meteorological tower was erroneously processed and used as delta-degrees Fahrenheit data. This had the potential to impact the gaseous effluent doses reported for 2015 because the dispersion ___ _ used in the calcuations where based on a joint frequency distribution determined with delta-degrees Celsius vice Fahrenheit. The delta-degrees data was converted to Fahrenheit, processed as a new joint frequency distribution, and doses for 2015 were determined using dispersion and deposition factors based on the new joint frequency distribution. The revised doses indicate minimal change to the originally reported doses. The gamma and beta air doses increased by 4% to 5% while the critical organ dose decreased 14%.
ANNUAL AND QUARTEHLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the .. _ calendar year of this along with an annual tota] of each effluent pathway is made _ pursuant to the ODCM, Section 6. 7 .2, -_ _ . __ . ___ _ LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 l.44E-04 6.76E-05 3.62E-08 1.08E-07 7.90E-04 2nd Quarter 8.50E-05 2.2JE-04 7.63E-05 4.49E-05 1.28E-04 6.26E-02 3rd Quarter 6.62E-05 l.61E-04 6.03E-05 l.73E-06 2.43E-06 1.43E-02 4th Quarter _ l.20E-04 5.56E-04 9.16E-05 3.76E-06 4.75E-06 3.06E-02 Annual 3.43E-04 1.08E-03 2.96E-04 5.05E-05 1.33E-04 -l.08E-01 Revised LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem)_ (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 1.44E-04 6.76E-05 3.35E-08 9.95E-08 6.42E-04 2nd Quarter 8.50E-05 2.23E-04 7.63E-05 4.60E-05 l.30E-04 5.56E-02 3rd Quarter 6.62E-05 1.61E-04 -6.03E-05 2.28E-06 2.61E-06 1.16E-02 4th Quarter 1.20E-04 5.56E-04 9.16E-05 4.71E-06 5.55E-06 2.48E-02 Annual 3.43E-04 _ 1.08E-03 2.96E-04 5.30E-05 1.38E-04 9.26E-02 -
ANNUAL AND QUARTEHLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the .. _ calendar year of this along with an annual tota] of each effluent pathway is made _ pursuant to the ODCM, Section 6. 7 .2, -_ _ . __ . ___ _ LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 l.44E-04 6.76E-05 3.62E-08 1.08E-07 7.90E-04 2nd Quarter 8.50E-05 2.2JE-04 7.63E-05 4.49E-05 1.28E-04 6.26E-02 3rd Quarter 6.62E-05 l.61E-04 6.03E-05 l.73E-06 2.43E-06 1.43E-02 4th Quarter _ l.20E-04 5.56E-04 9.16E-05 3.76E-06 4.75E-06 3.06E-02 Annual 3.43E-04 1.08E-03 2.96E-04 5.05E-05 1.33E-04 -l.08E-01 Revised LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem)_ (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 1.44E-04 6.76E-05 3.35E-08 9.95E-08 6.42E-04 2nd Quarter 8.50E-05 2.23E-04 7.63E-05 4.60E-05 l.30E-04 5.56E-02 3rd Quarter 6.62E-05 1.61E-04 -6.03E-05 2.28E-06 2.61E-06 1.16E-02 4th Quarter 1.20E-04 5.56E-04 9.16E-05 4.71E-06 5.55E-06 2.48E-02 Annual 3.43E-04 _ 1.08E-03 2.96E-04 5.30E-05 1.38E-04 9.26E-02 -
TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND QUARTER QUARTER A. FISSION & ACTIVATION GASES l. TOTAL RELEASE Ci l.25E-02 6.49E-01 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.60E-03* 8.25E-02 B. IODINE l. TOTALI-131 Ci N/D N/D 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec NIA NIA C. PARTICULATE l. HALF-LIFE>8 DAYS Ci N/D. 2.65E-05 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec NIA 3.37E-06 3. GROSS ALPHA RADIOACTMTY Ci N/D. N/D D. TRITIUM 1. TOTAL RELEASE Ci 8.34E+OO l.04E+Ol 2.. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.07E+OO l.32E+OO E. CARBON-14 l. TOT AL RELEASE Ci l.42E-01 7.39E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.83E-02 9.40E-Ol PERCENTAGE *oF T.S. LIMITS CRITICAL ORGAN DOSE RATE % l.62E-03 l.33E-02 TOTAL BODY DOSE RATE % 2.27E-08 3.IOE-05 SKIN DOSE RATE % 8.92E-09 l.19E-05 %EST.ERROR l.80E+Ol 2.80E+OI 2.80E+Ol 3.lOE+Ol TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH QUARTER QUARTER A. FISSION & ACTIVATION GASES 1. TOT AL RELEASE Ci 2.24E-Ol 4.80E-Ol 2. A VE RELEASE RATE FOR PERIOD _&#xb5;Ci/sec 2.82E-02 6.04E-02 B. IODINE l. TOTAL I-131 Ci NID NID 2. A VE RELEASE RATE FORPERIOD &#xb5;Ci/sec NIA. NIA C. PARTICULATE l. HALF-LIFE >8 DAYS Ci 4.93E-06 7.15E-06 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 6.20E-07 9.00E-07 3. GROSS ALPHA RADIOACTIVITY Ci NID NID D. TRITIUM l. TOTAL RELEASE Ci 4.42E+OO 8.43E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 5.55E-Ol l.06E+OO E. CARBON-14 1. TOTAL RELEASE Ci 2.56E+OO 5.47E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 3.22E-01 6.96E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE % 8.51E-04 l.67E-03 TOTAL BODY DOSE RATE % l.67E-06 3.43E-06 SKIN DOSE RATE % 5.05E-07 l.OIE-06 %EST.ERROR l.80E+Ol 2.80E+Ol 2.80E+Ol 3.IOE+Ol TABLElB EFFLUENT AND WASTE DISPOSAL ANNUAL REJ>ORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER l. FISSION & ACTIVATION GASES Kr-85 Ci NID N/D N/D *NID Kr-85m Ci N/D N/D N/D l.30E-03 Kr-87 Ci NID NID N/D NID Kr-88 Ci N/D NID NID NID Xe-i33 Ci l.03E-02 N/D 2.16E-03 3.69E-Ol Xe-135 Ci NID NID N/D 6.21E-02 Xe-135m Ci NID NID N/D N/D Xe-138 Ci NID NID N/D N/D Xe-13lm Ci N/D NID N/D. .N/D Xe-133m Ci N/D NID N/D 4.39E-03 Ar-41 Ci NID NID NID 3.45E-03 TOTAL FOR PERIOD Ci l.03E-02 NIA 2.16E-03 4.40E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D NID N/D N/D I-135 Ci NID NID N/D NID TOTAL FOR PERIOD Ci . -NIA NIA -NIA NIA 3. PARTICULATES Sr-89 Ci NID NID N/D NID Sr-90 Ci N/D NID N/D NID Cs-134 Ci NID NID N/D NID
TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND QUARTER QUARTER A. FISSION & ACTIVATION GASES l. TOTAL RELEASE Ci l.25E-02 6.49E-01 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.60E-03* 8.25E-02 B. IODINE l. TOTALI-131 Ci N/D N/D 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec NIA NIA C. PARTICULATE l. HALF-LIFE>8 DAYS Ci N/D. 2.65E-05 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec NIA 3.37E-06 3. GROSS ALPHA RADIOACTMTY Ci N/D. N/D D. TRITIUM 1. TOTAL RELEASE Ci 8.34E+OO l.04E+Ol 2.. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.07E+OO l.32E+OO E. CARBON-14 l. TOT AL RELEASE Ci l.42E-01 7.39E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec l.83E-02 9.40E-Ol PERCENTAGE *oF T.S. LIMITS CRITICAL ORGAN DOSE RATE % l.62E-03 l.33E-02 TOTAL BODY DOSE RATE % 2.27E-08 3.IOE-05 SKIN DOSE RATE % 8.92E-09 l.19E-05 %EST.ERROR l.80E+Ol 2.80E+OI 2.80E+Ol 3.lOE+Ol TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH QUARTER QUARTER A. FISSION & ACTIVATION GASES 1. TOT AL RELEASE Ci 2.24E-Ol 4.80E-Ol 2. A VE RELEASE RATE FOR PERIOD _&#xb5;Ci/sec 2.82E-02 6.04E-02 B. IODINE l. TOTAL I-131 Ci NID NID 2. A VE RELEASE RATE FORPERIOD &#xb5;Ci/sec NIA. NIA C. PARTICULATE l. HALF-LIFE >8 DAYS Ci 4.93E-06 7.15E-06 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 6.20E-07 9.00E-07 3. GROSS ALPHA RADIOACTIVITY Ci NID NID D. TRITIUM l. TOTAL RELEASE Ci 4.42E+OO 8.43E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 5.55E-Ol l.06E+OO E. CARBON-14 1. TOTAL RELEASE Ci 2.56E+OO 5.47E+OO 2. A VE RELEASE RATE FOR PERIOD &#xb5;Ci/sec 3.22E-01 6.96E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE % 8.51E-04 l.67E-03 TOTAL BODY DOSE RATE % l.67E-06 3.43E-06 SKIN DOSE RATE % 5.05E-07 l.OIE-06 %EST.ERROR l.80E+Ol 2.80E+Ol 2.80E+Ol 3.IOE+Ol TABLElB EFFLUENT AND WASTE DISPOSAL ANNUAL REJ>ORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER l. FISSION & ACTIVATION GASES Kr-85 Ci NID N/D N/D *NID Kr-85m Ci N/D N/D N/D l.30E-03 Kr-87 Ci NID NID N/D NID Kr-88 Ci N/D NID NID NID Xe-i33 Ci l.03E-02 N/D 2.16E-03 3.69E-Ol Xe-135 Ci NID NID N/D 6.21E-02 Xe-135m Ci NID NID N/D N/D Xe-138 Ci NID NID N/D N/D Xe-13lm Ci N/D NID N/D. .N/D Xe-133m Ci N/D NID N/D 4.39E-03 Ar-41 Ci NID NID NID 3.45E-03 TOTAL FOR PERIOD Ci l.03E-02 NIA 2.16E-03 4.40E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D NID N/D N/D I-135 Ci NID NID N/D NID TOTAL FOR PERIOD Ci . -NIA NIA -NIA NIA 3. PARTICULATES Sr-89 Ci NID NID N/D NID Sr-90 Ci N/D NID N/D NID Cs-134 Ci NID NID N/D NID
* Cs-137 Ci NID NID N/D NID Ba-140 Ci N/D NID N/D NIP La-140 Ci NID NID N/D N/D Co-58 Ci NID N/D N/D NID Co-60 Ci NID NID NID N!D Mn-54 Ci N/D NID N/D* N/D Fe-59 Ci N!D NID N/D N!D Zn-65 Ci NID NID N/D NID Mo-99 Ci N/D N/D N/D NID Ce-141
* Cs-137 Ci NID NID N/D NID Ba-140 Ci N/D NID N/D NIP La-140 Ci NID NID N/D N/D Co-58 Ci NID N/D N/D NID Co-60 Ci NID NID NID N!D Mn-54 Ci N/D NID N/D* N/D Fe-59 Ci N!D NID N/D N!D Zn-65 Ci NID NID N/D NID Mo-99 Ci N/D N/D N/D NID Ce-141
* Ci NID N/D N/D NID Ce-144 Ci NID N/D N/D NID C-14 Ci l.17E-Ol NID 2.46E-02 5.02E+OO TOTAL FOR PERIOD Ci l.17E-Ol NIA 2.46E-02 5.02E+OO TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131115 EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Ci N/D N/D 5.81E-04 6.44E-04 Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D l.84E-01 4.38E-Ol Xe-135 Ci N/D N/D 3.50E-02 2.83E-02 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-13lm Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D 2.93E-03 7.66E-03 Ar-41 Ci N/D N/D 9.00E-04 4.16E-03 TOT AL FOR PERIOD Ci NIA NIA 2.24E-01 4.79E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89. Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci NID N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D 2.55E+OO 5.46E+OO TOTAL FOR PERIOD Ci NIA NIA . 2.55E+OO 5.46E+OO TABLElC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT -__ -:eERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D NID NID N/D Kr-85m Ci NID N/D N/D N/D Kr-87 Ci NID NID NID N/D Kr-88 Ci N/D N/D NID N/D Xe-133 Ci .. N/D N/D NID 2.08E-Ol Xe-135 Ci N/D N/D NID-N/D* Xe-l35m Ci N/D N/D NID N/D Xe-138 Ci NID NID NID N/D Xe-13lm Ci NID NID NID N/D Xe-133m Ci NID NID NID N/D Ar-41 Ci NID 3.61E-04 NID N/D TOT AL FOR PERIOD Ci NIA 3.61E-04 N/A* 2.08E-Ol 2. IODINES I 31 Ci NID NID NID N/D I-133 Ci NID NID NID N/D I-135 Ci NID NID NID N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci N/D NID NID N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D NID N/D Cs-137 Ci N/D 2.43E-05 N/D N/D Ba-140 Ci N/D NID N/D N/D La-140 Ci NID NID N/D N/D Co-58 Ci NID 2.12E-06 N/D N/D Co-60 Ci NtD NID N/D N/D Mn-54 Ci NID NID N/D N/D Fe-59 Ci N/D NID N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci NID NID N/D N/D Ce-141 Ci N/D NID N/D N/D Ce-144 Ci NID NID N/D N/D C-14 Ci N/D 4.llE-03 N/D 2.37E+OO TOTAL FOR PERIOD Ci NIA 4.14E-03 NA 2.37E+OO TABLElC EFFLuENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOUR.TH THIRD FOURTH QUARTER* QUARTER QUARTER ----QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D 1.76E-06 Nin N/D Kr-87 Ci N/D l.66E-06 NID NID Kr-88 Ci N/D 3.14E-06 N/D N/D Xe-133 Ci N/D
* Ci NID N/D N/D NID Ce-144 Ci NID N/D N/D NID C-14 Ci l.17E-Ol NID 2.46E-02 5.02E+OO TOTAL FOR PERIOD Ci l.17E-Ol NIA 2.46E-02 5.02E+OO TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131115 EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Ci N/D N/D 5.81E-04 6.44E-04 Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D l.84E-01 4.38E-Ol Xe-135 Ci N/D N/D 3.50E-02 2.83E-02 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-13lm Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D 2.93E-03 7.66E-03 Ar-41 Ci N/D N/D 9.00E-04 4.16E-03 TOT AL FOR PERIOD Ci NIA NIA 2.24E-01 4.79E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89. Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci NID N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D 2.55E+OO 5.46E+OO TOTAL FOR PERIOD Ci NIA NIA . 2.55E+OO 5.46E+OO TABLElC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT -__ -:eERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D NID NID N/D Kr-85m Ci NID N/D N/D N/D Kr-87 Ci NID NID NID N/D Kr-88 Ci N/D N/D NID N/D Xe-133 Ci .. N/D N/D NID 2.08E-Ol Xe-135 Ci N/D N/D NID-N/D* Xe-l35m Ci N/D N/D NID N/D Xe-138 Ci NID NID NID N/D Xe-13lm Ci NID NID NID N/D Xe-133m Ci NID NID NID N/D Ar-41 Ci NID 3.61E-04 NID N/D TOT AL FOR PERIOD Ci NIA 3.61E-04 N/A* 2.08E-Ol 2. IODINES I-1-31 Ci NID NID NID N/D I-133 Ci NID NID NID N/D I-135 Ci NID NID NID N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci N/D NID NID N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D NID N/D Cs-137 Ci N/D 2.43E-05 N/D N/D Ba-140 Ci N/D NID N/D N/D La-140 Ci NID NID N/D N/D Co-58 Ci NID 2.12E-06 N/D N/D Co-60 Ci NtD NID N/D N/D Mn-54 Ci NID NID N/D N/D Fe-59 Ci N/D NID N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci NID NID N/D N/D Ce-141 Ci N/D NID N/D N/D Ce-144 Ci NID NID N/D N/D C-14 Ci N/D 4.llE-03 N/D 2.37E+OO TOTAL FOR PERIOD Ci NIA 4.14E-03 NA 2.37E+OO TABLElC EFFLuENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOUR.TH THIRD FOURTH QUARTER* QUARTER QUARTER ----QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D 1.76E-06 Nin N/D Kr-87 Ci N/D l.66E-06 NID NID Kr-88 Ci N/D 3.14E-06 N/D N/D Xe-133 Ci N/D
* l.25E-05 N/D 5.66E-04 Xe-135 Ci N/D 2.28E-05 N/D N/D Xe-135m Ci N/D 4.26E-06 N/D NID Xe-138 Ci N/D N/D N/D N/D Xe-131m *ci N/D N/D N/D N/D Xe-l33m Ci N/D N/D N/D N/D Ar=41. Ci 2.25E-04 4.93E-04 N/D N/D TOTAL FOR PERIOD Ci 2.25E-04 5.40E-04 NIA 5.66E-04 2. IODINES 1-13-1 Ci N/D N/D N/D N/D 1-132 Ci NID l.31E-03 N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci NIA l.31E-03 NIA NIA 3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D NID Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D .NID* NID N/D Co-58 Ci 4:93E-06 6.89E-06 N/D 2.12E-07 Co-60 Ci N/D N/D N/D 5.03E-08 Mn-54 Ci
* l.25E-05 N/D 5.66E-04 Xe-135 Ci N/D 2.28E-05 N/D N/D Xe-135m Ci N/D 4.26E-06 N/D NID Xe-138 Ci N/D N/D N/D N/D Xe-131m *ci N/D N/D N/D N/D Xe-l33m Ci N/D N/D N/D N/D Ar=41. Ci 2.25E-04 4.93E-04 N/D N/D TOTAL FOR PERIOD Ci 2.25E-04 5.40E-04 NIA 5.66E-04 2. IODINES 1-13-1 Ci N/D N/D N/D N/D 1-132 Ci NID l.31E-03 N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci NIA l.31E-03 NIA NIA 3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D NID Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D .NID* NID N/D Co-58 Ci 4:93E-06 6.89E-06 N/D 2.12E-07 Co-60 Ci N/D N/D N/D 5.03E-08 Mn-54 Ci
* N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D NID N/D N/D. Ce-144 Ci NIP N/D N/D N/D C-14 Ci 2.56E-03 6.15E-03 N/D 6.45E-03 TOTAL FOR PERIOD Ci 2.56E-03 6.16E-03 NA 6.45E-03   
* N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D NID N/D N/D. Ce-144 Ci NIP N/D N/D N/D C-14 Ci 2.56E-03 6.15E-03 N/D 6.45E-03 TOTAL FOR PERIOD Ci 2.56E-03 6.16E-03 NA 6.45E-03   
}}
}}

Revision as of 05:05, 2 May 2018

Surry Power Station Units 1 and 2, Annual Radioactive Effluent Release Report for 2016
ML17124A374
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/27/2017
From: Lawrence D C
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17124A374 (39)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY \ RICHMOND, VIRGINIA 23261 April 27, 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1AND2 ANNUAL RADIOACTIVE. EFFLUENT RELEASE REPORT Serial No. S&LfTSC Docket Nos. License Nos.17-117 RO 50-280 50-281 DPR-32 OPR-37 Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2016 through December 31, 2016. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.8.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2016 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974. If you have any further questions, please contact Lee Ragland at 757-365-2010. Douglas . awrence Director S fety & Licensing Surry Power Station Attachment Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station ATTACHMENT Serial No.17-117 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 Annual Radioactive Effluent Release Report Surry Power Station January 1, 2016 through December.31, 2016 SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station 2016 Annual Radioactive Effluent Release Report ANNUAL RADIOACTIVE EFFLUENT RELEASE' REPORT SURRY POWER STATION January 1, 2016 through December 31, 2016

  • Prepared #-1--. __,_____ __ P. F. Blount Health Physicist Reviewed By: __ __ '°_...< __ Approved By: P.R. Harris Superintendent Health P 7cal Services T. L. Ragland Manager Radiological Protection and Chemistry ANNUAL R.4.DIOACTIVE EFFLUENT RELEASE REPORT Section No. 1 2 3 4 FOR THE SURRY POWER STATION January 1, 2016 through December 31, 2016 Subject Executive Summary Purpose and Scope Discussion Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual {ODCM) Attachment 4 Major Changes to Radioactive Liql.Jid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Sample Analysis 1 2 3 4 Attachment 8 Industry Ground Water Protection Initiative I I -FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-280, 50-281, Section 6.6.B.3.

EXECUTIVESUMlVIARY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Annual Radioactive Effluent Release Report describes the radiological effluent control program conducted at Surry Power Station during the 2016 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Power Station in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Power Plants", Revision 1, June 1974. The report also includes an assessment of radiation .doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents. During this reporting period, there were no unplanned liquid or gaseous effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual. Based on the 2016 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows: 1. The total body dose due to liquid effluents was l.34E-04 mrem, which is 2.23E-03% of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 1. 72E-04 mrem to the GI-LLI, which is 8.70E-04% of the 20 mrem dose limit. 2. The air dose due to noble gases in gaseous effluents was 2.22E-05 mrad gamma, which is l.1 lE-04% of the 20 mrad gamma dose limit, and 4.68E-05 mrad beta, which is l.17E-04% of the 40 mrad beta dose limit. 3. The critical organ dose from gaseous effluents due to I-131, I-133, H-3, and particulates with half-lives greater than 8 days is 9.00E-02 mrem, which is 3.00E-01 % of the 30 mrem dose limit. There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during this reporting period. There were no changes made to VPAP-2103S, Offsite Dose Calculation Manual, during this reporting period. In accordance with the Nuclear Energy Institute (NEI) Industry Ground Water Protection Initiative, analysis results of ground water monitoring locations not included in the Radiological Environmental Monitoring Program (REMP), will be included in this report. Ground water monitoring well sample results are provided in Attachment 8. 1 Based on the radioactivity measured_ and the dose calculations performed dming this reporting period, the operation of Surry Power Station has resulted in negligible radiation dose consequences to the maxi?Jlum exposed member of the public in unrestricted areas. Purpose and Scope Attachment 1 includes a summary of the quantities of radioactive liquid and gaseous effluents and .solid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annual basis following the format of Tables 1, 2 and 3 of Appendix B, thereof Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during 2016. As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to th*se systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radi0active waste treatment systems may be submitted as part of the annual FSAR update. As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6. Attachment 7 provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation. As required by the ODCM, 'Section 6. 7 .5, a summary of on-site radioactive spills or leaks that were communicated in accordance with the Industry Ground Water Protection Initiative reporting protocol, and sample analyses from ground water wells that are not part of the Environmental Monitoring Program are provided in Attachment 8. In 2016, no on-site radioactive spills or leaks were communicated in accordance with the Industry Ground Water Protection Initiative. Attachment 9 provides a redetermination of the gaseous effluent doses reported for 2015. In November of 2016, it was discovered that atmospheric dispersion and deposition factors were determined using meteorological data that was processed as delta-degrees Celsius vice degrees Fahrenheit. Dispersion and deposition factors were updated based on delta-degrees Fahrenheit and the revised doses are provided. The revised doses represent a 4% to 5% increase in the noble gas air doses originally reported. No gaseous effluent dose limits were challenged due to the misprocessed meteorological data. 2 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM; Section 6.3.1, which requires that the dose rate for iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary. The critical receptor was modeled as a teenage individual via the inhalation pathway._-_--__ The basis for the calculation of the percent of technical specification for the total body and skin in Table IA of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal te 500 mrem/yr to the total body and iess than or equal to 3 000 mrem/yr to the skin. The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 is the ODCM, Section 6.2.1, which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 1 OCFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/mL. Percent of technical specification calculations are based on the total gaseous or liquid effluents released for the respective quarter.

  • The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was modeled as a child at 2.05 miles with the critical organ being the bone via the ingestion pathway. ,The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas was modeled as an adult, exposed by either the invertebrate or fish pathway, with the critical organ typically being the lower large intestine. The total body dose was also determined for this individual. Attachment 5 provides a discussion on the gaseous effluent monitoring instrumentation that was inoperable for greater than 30 days. As presented in the discussion, the instrumentation remained inoperable at the end of2016. It should be noted, however, that the instrumentation was returned to operable status ill February of 2017. There were no unplanned gaseous or liquid releases in 2016 to describe in Attachment 6 as required by the ODCM, Section 6.7.2. The typical lower limit of detection (LLD) capabilities of the radioactive-effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, 3 then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower limit of detection, then the totals for this period will be designated as Not Applicable (NIA). Supplemental Information Section 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk, or if required, leafy vegetation samples, and the identification for obtaining replacement samples. As milk was available for collection during this reporting period, leafy vegetation sampling was not required. In April 2016, the control milk sample was not obtained because the dairy closed its operation. A new control milk sample location. was added to the RadioJogi.cal Environmental Monitoring Program and sampling commenced inMay 2016. As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program. Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the Radiological Environmental Monitoring Program. 4 EFFLUENT RELEASE DATA January 1, 2016 through December 31, 2016 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.

TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111/16 TO 12/31/16 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND QUARTER QUARTER A. FISSION & ACTIVATION GASES 1. TOTALRELEASE Ci l.28E-03 2.64E-03 2. A VE RELEASE RATE FOR PERIOD µCi/sec l.63E-04 3.36E-04 B. IODINE 1. TOTALI-131 Ci N/D N/D 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA NIA C. PARTICULATE 1. HALF-LIFE >8 DAYS Ci N/D N/D 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA NIA 3, GROSS ALPHA RADIOACTIVITY Ci N/D NID D. TRITIUM 1. TOTAL RELEASE Ci 5.69E+OO 5.61E+OO 2. A VE RELEASE RATE FOR PERIOD µCi/sec 7.24E-01 7.14E-Ol E. CARBON-14 1. TOT AL RELEASE Ci 8.94E-03 l.84E-02 2. A VE RELEASE RATE FOR PERIOD µCi/sec l.14E-03 2.34E-03 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE % l.lOE-03 l.lOE-03 TOTAL BODY DOSE RATE % . 2.31E-09 l.72E-06 SKIN DOSE RATE % 9.06E-10 4.76E-07 Attachment 1 Page 1of12 %EST.ERROR l.80E+Ol 2.80E+Ol. 2.80E+01 . 3.lOE+Ol TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/16 TO 12/31/16 GASEOUS EFFLUENT-SUlVIMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH QUARTER QUARTER A. FISSION & ACTIVATION GASES l. TOTAL RELEASE Ci N/D 2.80E+OO 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA 3.56E-01 B. IODINE 1. TOTALI-131 Ci N/D l.17E-04 2. A VE RELEASE RATE FOR PERIOD_ µCi/sec NIA l.49E-05 C. PARTICULATE 1. HALF-LIFE >8 DAYS Ci 3.41E-06 1.19E-05 2. J\. VE RELEASE RATE FOR PERIOD µCi/sec 4.34E-07 l.51E-06 3. GROSS ALPHA RADIOACTIVITY Ci NID N/D D. TRITIUM 1. TOT AL RELEASE Ci 2.96E+OO l.47E+Ol 2. A VE RELEASE RATE FOR PERIOD µCi/sec 3.76E-Ol l.87E+OO E. CARBON-14 1. TOTAL RELEASE Ci N/D l.96E+Ol 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA 2.49E+OO PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE % 5.66E-04 3.29E-03 TOTAL BODY DOSE RATE % O.OOE+OO l.42E-05 SKJN DOSE RATE % O.OOE+OO 5.70E-06 Attachment 1 Page 2of12 %EST.ERROR l.80E+Ol 2.80E+Ol 2.80E+Ol 3.lOE+Ol TABLElB Page 3of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/16 TO 12/31/16 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FlRST SECOND QUARTER QUARTER QUARTER QUARTER --1. FISSION & ACTIVATION GASES Kr-85 Ci NID NID N/D NID Kr-85m Ci NID NID N/D NID Kr-87 Ci NID NID N/D NID Kr-88 Ci NID NID NID NID Xe-133 Ci NID NID l.28E-03 N/D Xe-135 Ci N/D NID NID NID Xe-l35m Ci NID NID N/D NID Xe-138 Ci NID NID NID N/D Xe-l3lm Ci N/D NID NID N/D Xe-l33m Ci NID NID NID N/D Ar-41 Ci NID N/D NID NID TOTAL FOR PERIOD Ci NIA NIA l.28E-03 NIA 2. IODINES I-131 Ci NID N/D NID NID I-133 Ci NID N/D N/D N/D I-135 Ci N/D NID NID NID TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID N/D Cs-134 Ci NID NID NID NID Cs-137 Ci NID. NID NID N/D Ba-140 Ci NID N/D N/D NID La-140 Ci NID NID N/D N/D Co-58 Ci N/D NID N/D NID Co-60 Ci NID N/D NID N/D Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID N/D NID Zn-65 Ci NID N/D NID NID Mo-99 Ci NID NID N/D NID Ce-141 Ci N/D N/D NID NID Ce-144 Ci, NID NID NID NID C-14 Ci NID N/D 8.94E-03 N/D TOTAL FOR PERIOD Ci NIA NIA 8.94E-03 NIA TABLE 1B Page 4of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111i16 TO 12131116 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci NID NID NID 5.77E-Ol Kr-85m Ci NID NID NID 8.79E-03 Kr-87 Ci NID NID NID NID Kr-88 Ci NID NID NID 4.14-E-03 Xe-133 Ci NID 5.41E-Ol NID l.16E-:J-00 Xe-135 Ci NID 8.55E-03 NID 4.06E-Ol Xe-l35m Ci NID NID NID NID Xe-138 Ci NID NID NID NID Xe-l3lm Ci NID N/D NID l.28E-02 Xe-133m Ci NID NID NID 2.31E-02 Ar-41 Ci NID NID NID 3.97E-02 TOTAL FOR PERIOD Ci NIA 5.50E-01 NIA 2.23E+OO 2. IODINES I-131 Ci NID N/D NID NID I-133 Ci NID N/D NID NID I-135 Ci NID NID NID NID TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci NID N/D NID NID Cs-137 Ci NID NID NID NID Ba-140 Ci NID NID NID NID La-140 Ci NID NID NID NID* Co-58 Ci NID NID NID NID Co-60 Ci NID NID NID NID Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID NID NID Zn-65 Ci NID NID NID NID Mo-99 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ci NID NID NID NID C-14 Ci NID 3.84E+OO NID l.56E+Ol TOTAL FOR PERIOD Ci NIA 3.84E+OO NIA 1.56E+Ol TABLElC Attachment 1 Page 5of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111116 TO 12131/16 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci NID NID NID N/D Kr-85m Ci NID 2.48E-05 NID N/D Kr-87 Ci NID 5.27E-06 NID N/D Kr-88 Ci NID 2.75E-05 NID N/D Xe-133 Ci NID 2.17E-03 NID N/D Xe-135 Ci NID 8.87E-05 NID N/D Xe-135m Ci NID 2.30E-06 NID N/D Xe-138 Ci NID N/D N/D N/D Xe-13lm Ci NID l.43E-05 NID N/D Xe-133m Ci NID 3.16E-05 NID N/D Ar-41 Cr NID 2.80E-04 N/D* N/D TOTAL FOR PERIOD Ci NIA 2.64E-03 NIA NIA 2. IODINES I-131 Ci NID N/D NID N/D I-133 Ci NID N/D NID N/D I-135 Ci NID N/D NID N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci NID N/D N/D N/D Sr-90 Ci NID N/D NID N/D Cs-134 Ci NID N/D NID N/D Cs-137 Ci NID N/D NID N/D Ba-140 Ci NID N/D NID N/D La-140 Ci NID N/D NID NID Co-58 Ci NID N/D NID N/D Co-60 Ci NID N/D* NID N/D Mn-54 Ci NID N/D NID N/D Fe-59 Ci NID N/D N/D N/D Zn-65 Ci NID. N/D NID N/D Mo-99 Ci NID N/D N/D N/D Ce-141 Ci NID N/D NID N/D Ce-144 Ci NID N/D N/D N/D C-14 Ci NID l.84E-02 NID N/D TOTAL FOR PERIOD Ci NIA l.84E-02 NA NA TABLElC Attachment 1 Page 6of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111116 TO 12131116 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci *N/D N/D N/D N/D Xe-133 Ci *N/D 2.22E-03 N!D l.84E-02 Xe-135 Ci N/D N/D N/D 8.94E-06 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D NID N/D N/D Xe-13lm Ci N/D N/D NID NID Xe-133m Ci N/D N/D N/D 3.18E-04 Ar-41 Ci N/D 2.90E-04 N/D N/D TOTAL FOR PERIOD Ci NIA 2.51.E-03 NIA l.87E-02 2. IODINES I-131 Ci N/D 9.27E-05 N/D N/D I-133 Ci N/D 2.43E-05 N/D N/D I-135 Ci

  • NID N/D N/D N/D TOTAL FOR PERIOD Ci NIA 1.17E-04 NIA NIA 3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci 3AlE-06 l.19E-05 N/D 3.65E-08 Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D NID N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D l.75E-02 N/D l.31E-Ol TOTAL FOR PERIOD Ci 3.41E-06 l.75E-02 NA l.31E-01 I l __ TABLE2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111116 TO 12131/16 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND . QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) -.... -. Ci 2.00E-03 6.99E-03 2. A VE DIL. CONC. DURING PERIOD µCi/mL 3.0SE-12 l.02E-1 l 3. PERCENT OF APPLICABLE LIMLT % 5.37E-06 1.12E-05 B. TRITIUM l. TOTAL RELEASE Ci 3.74E+Ol _ 2.43E+Ol 2. A VE DIL. CONC. DURING PERIOD µCi/mL 5.71E-08 3.56E-08 3. PERCENT OF APPLICABLE LIMIT % 5.71E-04 3.56E-04 C. DISSOLVED AND ENTRAINED GASES 1. TOTAL RELEASE Ci NID NID 2. A VE DIL. CONC. DURING PERIOD µCi/mL NIA NIA 3. PERCENT OF APPLICABLE LIMIT % NIA NIA D. GROSS ALPHA RADIOACTIVITY 1. TOTAL RELEASE Ci NID N/D E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 5.49E+07 5.28E+07 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.54E+ll 6.82E+ll Attachment 1 Page 7-of 12 %EST.ERROR 2.00E+Ol 2.00E+Ol 2.00E+Ol 2.00E+Ol 3.00E+OO 3.00E+OO TABLE2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/16 TO 12/31/16 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRYPOWERSTATIONUNITS 1&2
  • UNIT THIRD FOURTH QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 1.55E-03 9.22E-04 2. A VE DIL. CONC. DURING PERIOD µCi/mL 1.95E-12 l.37E-12 3. PERCENT OF APPLICABLE LIMIT % 7.05E-06 5.29E-06 B. TRITIUM 1. TOTAL RELEASE Ci 1.71E+02 4.47E+02 ..
  • 2. A VE DIL. CONC. DURING PERIOD µCi/mL 2.16E-07 6.62E-07 3. PERCENT OF APPLICABLE LIMIT % 2.16E-03 6.62E-03 C. DISSOLVED AND ENTRAINED GASES l. TOTAL RELEASE Ci NID 6.66E-03 2. A VE DIL. CONC .. DURING PERIOD µCi/rnL NIA 9.86E-12 3. PERCENT OF APPLICABLE LIMIT % NIA 4.93E-06 D. GROSS ALPHA RADIOACTIVITY* 1. TOTAL RELEASE Ci N/D NID E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 5.35E+07 5.40E+07 F. VOLUME OF DILUTION WATER USED DURING PERIOD *LITERS 7.93E+ll 6.75E+ll Attachment 1 Page 8 ofl2 %EST.ERROR 2.00E+Ol . 2.00E+Ol 2.00E+Ol 2.00E+CH 3.00E+OO 3.00E+OO TABLE2B P.age-9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/16 TO 12/31/16 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER.STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Fe-55 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci 2.24E-04 2.17E-04 2.14E-05 4.3GE-05 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 2.03E-04 8.93E-04 Co-60 Ci N/D. N/D l.44E-04 8.78E-04 Fe-59 Ci N/D N/D. N/D N/D Zn-65 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Cr-51 Ci N/D N/D N/D 4.92E-05 Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Tc-99m Ci N/D N/D N/D NID Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D NID N/D Ce-141 Ci NfD NID N/D N/D Ce-144 Ci N/D N/D N/D N/D Sb-124 Ci N/D N/D 9.20E-06 NID. Sb-125 Ci N/D N/D l.39E-03 4.9IE-03 Co-57 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci 2.24E-04 2.17E-04 l.77E-03 6.77E-03 Xe-133 Ci N/D N/D N/D N/D Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA TABLE2B Page 10of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111116 TO 12131/16 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT TIIlRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER .QUARTER Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Fe-55 Ci NID NID NID NID Cs-134 Ci NID NID NID l.34E-05 Cs-137 Ci 4.23E-04 2.74E-04 l.03E-05 I-131 Ci N/D NID NID NID Co-58 Ci NID 2.00E-07 3:08E-05 9.27E-05 Co-60 Ci NID l.76E-06 2.40E-04 l.17E-04 I Fe-59 Ci NID NID NID NID I Zn-65 Ci NID NID NID NID Mn-54 Ci NID NID NID NID Cr-51 Ci NID NID NID NID Zr-95 Ci NID NID NID NID Nb-95 Ci NID NID NID. NID Mo-99 Ci NID NID NID NID Tc-99m. Ci N/D NID N!D* NID Ba-140 Ci NID NID NID NID La-140 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ce-144 Ci NID N/D NID NID Sb-124 Ci NID NID 4.27E-06 NID Sb-125 Ci N/D 7.14E-07 8.26E-04 4.12E-04 Co-57 Ci NID N/D NID NID TOTAL FOR PERIOD Ci 4.23E-04 2.77E-04 l.13E-03 6.45E-04 Xe-133 Ci NID NID NID 6.66E-03 Xe-135 Ci NID NID NID NID TOTAL FOR PERIOD Ci NIA NIA NIA 6.66E-03 TABLE3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SIDPMENTS PERIOD: 1/1/16 -12/31/16 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1. Type of waste a. Spent resins, filter sludges, evaporator bottoms, etc. b. Dry compressible waste, contaminated equip., etc. c. Irradiated components, control rods, etc. d. Other (Waste oil) 2. Estimate of major nuclide composition (by type of waste) a. Co-60 Ni-63 Fe-55 Co-58 Mn-54 b. Co-60 Ni-63 Cs-137 Fe-55 c. d. C-14 H-3 I-129 Tc-99 m3 Ci m3 Ci m3 Ci 3 m Ci % % % % % % % % % % % % % % 12 month Period 2.26E+OO 8.20E+Ol 5.14E+02 l.74E+OO O.OOE+OO O.OOE+OO 3.13E+OO 5.40E-08 5.57E+Ol 2.92E+Ol 7.50E+OO 2.78E+OO l.37E+OO 6.67E+Ol 1.50E+Ol 9.35E+OO 4.72E+OO 3.92E+Ol 3.13E+Ol l.56E+Ol l.32E+Ol Note 1 Note2 Note3 Attachment 1 Page 11of12 Est. Total Error,% l.OOE+Ol 3.00E+Ol l.OOE+Ol 3.00E+Ol 1-.00E+Ol 3.00E+Ol TABLE3 EFFI:,UENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/16 -12/31/16 CONTJNUED SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 3. Solid Waste Disposition Number of Shipments 19 1 B. IRRADIATED FUEL SHiPMENT (Disposition) Number of Shipments 0 Mode of Transportation Truck Truck Mode of Transportation Destination Attachment 1 Page 12of12 Oak Ridge, TN (EnergySolutions) Erwin, TN (EnergySolutions) Destination NOTE 1: Some of this waste was shipped to licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is l. l 6E+OO m3* Burial volume by Erwin Resin Solutions is indeterminable due to mixing of Surry waste with other generators waste. NOTE 2: Some DAW was shipped to licensed waste processors for processing volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is l.81E+02 m3. NOTE 3: This waste was shipped to a licensed waste processor for. processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is O.OOE+OO m3*

ANNUAL AND QUARTERLY DOSES Attachment 2 Page 1 ofl An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total _of each effluent pathway is made pursuant to the ODCl\11, S_ection 6.7.2, requirement. -LIQUID GASEOUS 2016 Total Body GI-LLI Liver Gamma -Beta Bone (mrem) (mrem) (mrem) (mrad) (mrad) (mrem). 1st Quarter 8.84E-06 l.36E-05 9.19E-06 3.43E-09 l.02E-08 4.04E-05 2nd Quarter 8.71E-06 3.64E-05 7.66E-06 2.30E-06 2.09E-06 2.56E-04 3rd Quarter 2.%E-05 3.26E-05 . 3.03E-05 O.OOE+OO Q.OOE+OO 2.91E-08 4th Quarter 8.70E-05 8.89E-05 8.76E-05 1.99E-05 4.47E-05 8.97E-02 Annual l.34E-04 l.72E-04 l.35E-04 2.22E-05 4.68E-05 9.00E-02 L ___ --REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM) Attachment 3 Page I .of 1 As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period .covered by this report, are included with this attachment. There were no revisions to the ODCM implemented during this reporting period.

  • .MAJOR CHANGES. TO RADIOACTIVE LIQUID,
  • GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems for this reporting period. Attachment 4 Page 1 ofl INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION Attachment 5 Pclge i of 1 The Annual Radioactive Effluent Release Report shall explain why monitoring instrumentation required by the ODCM Attachments 1 and 5, which were determined to be inoperable, were not returned to operable status within 30 days. Two of the above referenced instrumentation were inoperable greater than 30 days during this reporting period. On 05/06/2015, the Surry Radwaste Facility (SRF) Ventilation Stack Noble Gas Monitor selector switch was determined inoperable. The selector switch provides the capability to toggle through various monitor parameters and perform selected functions. Two instruments required to monitor the SRF stack pathway, in accordance with Attachment 5 of the ODCM, were rendered inoperable with the loss of the selector switch. The instruments lost were the noble gas activity radiation monitor and the flow .rate measuring device for the stack continuous particulate and iodine sampler. Additionally, although not required by Attachment 5, the capability to source check the noble gas activity radiation monitor was rendered inoperable. Compensatory measures for the loss of the instruments were initiated in accordance with the ODCM. For the loss of the noble gas activity radiation monitor, grab samples of the SRF stack exhaust are taken and analyzed at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. No activity has been detected in any of these samples. For the loss of the sampler flow rate measuring device, an estimate of the sampler flow rate is made at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and documented in the Station logs. At this time, these instruments remain inoperable with compensatory measures in place. A similar radiation monitor skid was obtained to replace the current skid, but it could not be made functional. Design Change 15-01054 was initiated to obtain a new radiation monitoring system for the SRF -ventillation. In 2016, the new radiation monitoring skid was manufactured and delivered to the station. Installation of and return to operational status with the new noble gas radiation monitor will occur in 2017.

UNPLANNED RELEASES There were no unplanned liquid or unplanned gaseous releases during this reporting period. Attachment 6 Page 1 ofl LOWER LIMIT OF DETECTION (LL-U) FOR EFFLUENT SAJVIPLE ANALYSIS GASEOUS: Isotope Reguired LLD Typical LLD Kr-87 l.OOE-04 l.97E-06 -4.78E-05 Kr-88 1.00E-04 1.71E-06 -2.l3E-05 Xe-133 1.00E-04 l.05E-06 -l.68E-05 Xe-133m l.OOE-04 3.61E-06 -4.06E-05 Xe-135 l.OOE-04 4.59E-07 -l.23E-05 Xe-135m l.OOE-04 l.35E-05 -8.36E-05 Xe-138 l.OOE-04 2.32E-05 -9.90E-05 I-131 l.OOE-12 4.06E-13 -4.06E-13 I-133 l.OOE-10 4.06E-11 -4.06E-11 Sr-89 l.OOE-11 l.38E-14 -9.34E-13 Sr-90 l.OOE-11 l.77E-15 -l.14E-13 Cs-134 l.OOE-11 l.29E-13 -2.50E-13 Cs-137 l.OOE-11 1.81E-13 -3.64E-13 Mn-54 l.OOE-11 2.50E-14 -2.70E-13 Fe-59 l.OOE-11 3.41E-13 -8.38E-13 Co-58 l.OOE-11 1.72E-14 -2.86E-13 Co-60 l.OOE-11 2.58E-14 -4.79E-13 l.OOE-11 3.l3E-13 -6.99E-13 Mo-99 l.OOE-11 4.06E-12 -4.06E-12 Ce-141 l.OOE-11 2.06E-13. -2.98E-13 Ce-144 l.OOE-11 7.84E-13 -l.34E-12 Alpha l.OOE-11 l.69E-14 -2.21E-14 Tritium l.OOE-06 4.94E-08 6.82E-08 LIQUID: Sr-89 5.00E-08 2.78E-08 -4.54E-08 *sr-90 5.00E-08 6.46E-09 -9.49E-09 *Cs-134 5:00E-07 l.77E-08 -5.46E-08 Cs-137 5.00E-07 2.45E-08 -8.33E-08 I-131 1.00E-06 2.61E-08 -6.48E-08 Co-58 5.00E-07 2.18E-09 -5.99E-08 Co-60 5.00E-07 2.77E-09 -8.82E-08 Fe-59 5.00E-07 3.25E-08 -1.48E-07 Zn-65 5:00E-07 3.64E-08 -l.37E-07 Mn-54 5.00E-07 3.19E-09 -5.70E-08 Mo-99 5.00E-07 2.20E-07 4.95E-07 Ce-141 5.00E-07 3.13E-08 -9.27E-08 Ce-144 5.00E-07 l.32E-07 -3.47E-07 Fe-55 l.OOE-06 4.27E-07 -9.70E-07. Alpha l.OOE-07 2.70E-08 -2.73E-08 Tritium 1.00E-05 l.22E-06 -l.69E-06 *xe-133 1.00E-05 8.90E-08 l.73E-07 Xe-135 l.OOE-05 2.78E-08 -l.18E-07 Xe-133m l.OOE-05 2.27E-07 -3.71E-07 Xe-135m l.OOE-05 l.59E-06 -2.81E-06 Xe-138 1.00E-05 2.38E-06 -8.93E-06 Kr-87 l.OOE-05 . l.30E-07 -2.22E-07 Kr-88 l.OOE-05 l.59E-08 -7.85E-07 Attachment 7 Page 1of1 Page 1 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE -The following is a .summary of 2016 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP). Analyses are performed by an

  • independent laboratory. Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter. pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-04 3/9/16 <1,400 ND NA NA NA NA 1-PL-Piez-05 3/9/16 6,160 ND <119 <4.43 <0.461 ND 1-PL-Piez-06 3/9/16 2,580 ND <87.1 <4.44 <0.355 ND 1-PL-Piez-07 3/9/16 <1,410 ND NA NA NA .. NA 3/9/16 <1,410 ND NA NA NA . -* NA 1-PL-Piez-33 319116 <1,420 ND NA NA NA NA 1-PL-Piez-3A 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez-41 3/9/16 <1,430. ND NA NA NA NA 1-PL-Piez-42 3/9/16 <1,420 ND NA NA NA NA 1-PL-Piez.-29 3/9/16 8,340 ND <83.4-<4.62 . <0.433 ND 1-PL-Piez-04 5/11/16 <947 ND NA NA NA NA 1-PL-Piez-05 5/11/16 5,380 ND NA. NA NA NA 1-PL-Piez-06 5/11/16 2,750 ND NA NA NA NA 1-PL-Piez-07 5/11/16 <971 ND NA NA NA NA . l -PL-Piez-08 5/11/16 <958 ND NA NA NA NA 1-PL-Piez-09 5/11116 <956 NA NA NA NA NA 1-PL-Piez-20 5111116 <946 ND NA* NA NA NA 1-PL-Piez-22 5/11116 <968 ND NA NA NA NA 1-PL-Piez-24 5/11/16 <950 ND NA NA NA NA 1-PL-Piez-25 5/11116 <942 ND NA NA NA NA 1-PL-Piez-27 5/11/16 <970 ND NA NA NA NA 1-PL-Piez-28 5/11/16 <952 ND NA .. NA NA NA 1-PL-Piez-29 5/1.1/16 7,780 ND NA NA NA NA 1-PL-Piez-33 5/11/16 <953 .ND NA NA NA NA 1-PL-Piez-03 5/12/16 <964 NA NA NA NA NA 1-PL-Piez-23 5/12/16 <9.51 ND NA NA NA NA 1-PL-Piez-34 5/12/16 <954 ND NA NA NA NA 1-PL-Piez-35 5/12/16 <973 NA NA NA NA NA 1-PL-Piez-36 5/12/16 <965 NA NA NA NA NA 1-PL-Piez-37 5/12/16 <958 NA NA NA NA NA 1-PL-Piez-38 5/12/16 <967 NA NA NA .NA* NA 1-PL-Piez-39 5/12/16 <963 NA NA NA NA NA 1-PL-Piez-40 5/12/16 <963 ND NA NA NA NA 1-PL-Piez-41 5/12/16 <960 ND NA NA NA NA 1-PL-Piez-42 5/12/16 <951 ND NA NA NA NA Page 2 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE Well Sample Tritium Gamma Fe-55
  • Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-05 8/2/16 4,950 ND NA NA NA NA 1-PL-Piez-06 8/2/16 1,880 ND NA NA NA NA 1-PL-Piez-07 8/2/16 <931 ND NA NA NA NA 1-PL-Piez-27 8/2/16 <945 ND NA NA NA NA 1-PL-Piez-04 8/3/16 <937 ND NA NA NA NA 1-PL-Piez-29 8/3/16. -7,640 ND NA -NA NA NA l-PL-Piez-33 8/3/16 <928 ND** NA NA NA NA l-PL-Piez-34 8/3/16 <942 ND NA NA NA NA 1-PL-Piez-41 8/3/16 <934 ND NA NA NA NA 1-PL-Piez-42 8/3/16 <921 ND NA NA NA NA 1-P'L-Piez-04 12/5/16 <951 ND NA NA NA NA l -PL-Piez-05 12/5/16 . 4,840 . ND NA NA NA NA 1-PL-Piez-06 12/5/16 1,330 ND NA NA *NA NA 1-PL-Piez-07 12/5/16 <951 ND NA NA NA NA l-PL-Piez-08 12/5/16 <970 ND NA NA NA NA 1-PL-Piez-24 12/5/16 <965. ND NA NA NA NA 1-PL-Piez-25 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-27 12/5/16 <950 ND NA NA NA NA 1-PL-Piez-33 12/5/16 <952 ND NA NA NA NA 1-PL-Piez-34 12/5/16 <942 ND NA NA NA NA 1-PL-Piez-40 12/5/16 <953 ND _r NA .NA NA NA *-1-PL-Piez-41 12/5/16 <953 ND NA NA NA NA 1-PL-Piez-42 12/5/16 <944 ND NA NA NA NA Well Sample Tritium Co-58 . Ee-55 Ni-:63 . Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-29 12/5/16 6,700 16.3 NA NA NA NA 12/15/16 6,210 11.6 <67.2 <3.73 -<0.637 ND NA= Analysis not required. ND =No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs. TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241), ND = not detected ERRATA/CORRECTIONS TO PREVIOUS REPORTS Attachment 9
  • Page 1 ofl 1bis section contains revised gaseous effluent doses and associated release data for 2015. In November 2016, it was determined that delta-temperature data transmitted in delta-degrees Celsius from the Surry Power Station meteorological tower was erroneously processed and used as delta-degrees Fahrenheit data. This had the potential to impact the gaseous effluent doses reported for 2015 because the dispersion ___ _ used in the calcuations where based on a joint frequency distribution determined with delta-degrees Celsius vice Fahrenheit. The delta-degrees data was converted to Fahrenheit, processed as a new joint frequency distribution, and doses for 2015 were determined using dispersion and deposition factors based on the new joint frequency distribution. The revised doses indicate minimal change to the originally reported doses. The gamma and beta air doses increased by 4% to 5% while the critical organ dose decreased 14%.

ANNUAL AND QUARTEHLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the .. _ calendar year of this along with an annual tota] of each effluent pathway is made _ pursuant to the ODCM, Section 6. 7 .2, -_ _ . __ . ___ _ LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 l.44E-04 6.76E-05 3.62E-08 1.08E-07 7.90E-04 2nd Quarter 8.50E-05 2.2JE-04 7.63E-05 4.49E-05 1.28E-04 6.26E-02 3rd Quarter 6.62E-05 l.61E-04 6.03E-05 l.73E-06 2.43E-06 1.43E-02 4th Quarter _ l.20E-04 5.56E-04 9.16E-05 3.76E-06 4.75E-06 3.06E-02 Annual 3.43E-04 1.08E-03 2.96E-04 5.05E-05 1.33E-04 -l.08E-01 Revised LIQUID GASEOUS 2015 Total Body GI-LLI Liver Gamma Beta Bone (mrem)_ (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.18E-05 1.44E-04 6.76E-05 3.35E-08 9.95E-08 6.42E-04 2nd Quarter 8.50E-05 2.23E-04 7.63E-05 4.60E-05 l.30E-04 5.56E-02 3rd Quarter 6.62E-05 1.61E-04 -6.03E-05 2.28E-06 2.61E-06 1.16E-02 4th Quarter 1.20E-04 5.56E-04 9.16E-05 4.71E-06 5.55E-06 2.48E-02 Annual 3.43E-04 _ 1.08E-03 2.96E-04 5.30E-05 1.38E-04 9.26E-02 -

TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND QUARTER QUARTER A. FISSION & ACTIVATION GASES l. TOTAL RELEASE Ci l.25E-02 6.49E-01 2. A VE RELEASE RATE FOR PERIOD µCi/sec l.60E-03* 8.25E-02 B. IODINE l. TOTALI-131 Ci N/D N/D 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA NIA C. PARTICULATE l. HALF-LIFE>8 DAYS Ci N/D. 2.65E-05 2. A VE RELEASE RATE FOR PERIOD µCi/sec NIA 3.37E-06 3. GROSS ALPHA RADIOACTMTY Ci N/D. N/D D. TRITIUM 1. TOTAL RELEASE Ci 8.34E+OO l.04E+Ol 2.. A VE RELEASE RATE FOR PERIOD µCi/sec l.07E+OO l.32E+OO E. CARBON-14 l. TOT AL RELEASE Ci l.42E-01 7.39E+OO 2. A VE RELEASE RATE FOR PERIOD µCi/sec l.83E-02 9.40E-Ol PERCENTAGE *oF T.S. LIMITS CRITICAL ORGAN DOSE RATE % l.62E-03 l.33E-02 TOTAL BODY DOSE RATE % 2.27E-08 3.IOE-05 SKIN DOSE RATE % 8.92E-09 l.19E-05 %EST.ERROR l.80E+Ol 2.80E+OI 2.80E+Ol 3.lOE+Ol TABLE lA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131/15 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH QUARTER QUARTER A. FISSION & ACTIVATION GASES 1. TOT AL RELEASE Ci 2.24E-Ol 4.80E-Ol 2. A VE RELEASE RATE FOR PERIOD _µCi/sec 2.82E-02 6.04E-02 B. IODINE l. TOTAL I-131 Ci NID NID 2. A VE RELEASE RATE FORPERIOD µCi/sec NIA. NIA C. PARTICULATE l. HALF-LIFE >8 DAYS Ci 4.93E-06 7.15E-06 2. A VE RELEASE RATE FOR PERIOD µCi/sec 6.20E-07 9.00E-07 3. GROSS ALPHA RADIOACTIVITY Ci NID NID D. TRITIUM l. TOTAL RELEASE Ci 4.42E+OO 8.43E+OO 2. A VE RELEASE RATE FOR PERIOD µCi/sec 5.55E-Ol l.06E+OO E. CARBON-14 1. TOTAL RELEASE Ci 2.56E+OO 5.47E+OO 2. A VE RELEASE RATE FOR PERIOD µCi/sec 3.22E-01 6.96E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE % 8.51E-04 l.67E-03 TOTAL BODY DOSE RATE % l.67E-06 3.43E-06 SKIN DOSE RATE % 5.05E-07 l.OIE-06 %EST.ERROR l.80E+Ol 2.80E+Ol 2.80E+Ol 3.IOE+Ol TABLElB EFFLUENT AND WASTE DISPOSAL ANNUAL REJ>ORT PERIOD: 1/1/15 TO 12131/15 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER l. FISSION & ACTIVATION GASES Kr-85 Ci NID N/D N/D *NID Kr-85m Ci N/D N/D N/D l.30E-03 Kr-87 Ci NID NID N/D NID Kr-88 Ci N/D NID NID NID Xe-i33 Ci l.03E-02 N/D 2.16E-03 3.69E-Ol Xe-135 Ci NID NID N/D 6.21E-02 Xe-135m Ci NID NID N/D N/D Xe-138 Ci NID NID N/D N/D Xe-13lm Ci N/D NID N/D. .N/D Xe-133m Ci N/D NID N/D 4.39E-03 Ar-41 Ci NID NID NID 3.45E-03 TOTAL FOR PERIOD Ci l.03E-02 NIA 2.16E-03 4.40E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D NID N/D N/D I-135 Ci NID NID N/D NID TOTAL FOR PERIOD Ci . -NIA NIA -NIA NIA 3. PARTICULATES Sr-89 Ci NID NID N/D NID Sr-90 Ci N/D NID N/D NID Cs-134 Ci NID NID N/D NID

  • Cs-137 Ci NID NID N/D NID Ba-140 Ci N/D NID N/D NIP La-140 Ci NID NID N/D N/D Co-58 Ci NID N/D N/D NID Co-60 Ci NID NID NID N!D Mn-54 Ci N/D NID N/D* N/D Fe-59 Ci N!D NID N/D N!D Zn-65 Ci NID NID N/D NID Mo-99 Ci N/D N/D N/D NID Ce-141
  • Ci NID N/D N/D NID Ce-144 Ci NID N/D N/D NID C-14 Ci l.17E-Ol NID 2.46E-02 5.02E+OO TOTAL FOR PERIOD Ci l.17E-Ol NIA 2.46E-02 5.02E+OO TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111115 TO 12131115 EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Ci N/D N/D 5.81E-04 6.44E-04 Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D l.84E-01 4.38E-Ol Xe-135 Ci N/D N/D 3.50E-02 2.83E-02 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-13lm Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D 2.93E-03 7.66E-03 Ar-41 Ci N/D N/D 9.00E-04 4.16E-03 TOT AL FOR PERIOD Ci NIA NIA 2.24E-01 4.79E-01 2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89. Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci NID N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D 2.55E+OO 5.46E+OO TOTAL FOR PERIOD Ci NIA NIA . 2.55E+OO 5.46E+OO TABLElC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT -__ -:eERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRYPOWERSTATIONUNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D NID NID N/D Kr-85m Ci NID N/D N/D N/D Kr-87 Ci NID NID NID N/D Kr-88 Ci N/D N/D NID N/D Xe-133 Ci .. N/D N/D NID 2.08E-Ol Xe-135 Ci N/D N/D NID-N/D* Xe-l35m Ci N/D N/D NID N/D Xe-138 Ci NID NID NID N/D Xe-13lm Ci NID NID NID N/D Xe-133m Ci NID NID NID N/D Ar-41 Ci NID 3.61E-04 NID N/D TOT AL FOR PERIOD Ci NIA 3.61E-04 N/A* 2.08E-Ol 2. IODINES I-1-31 Ci NID NID NID N/D I-133 Ci NID NID NID N/D I-135 Ci NID NID NID N/D TOTAL FOR PERIOD Ci NIA NIA NIA NIA 3. PARTICULATES Sr-89 Ci N/D NID NID N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D NID N/D Cs-137 Ci N/D 2.43E-05 N/D N/D Ba-140 Ci N/D NID N/D N/D La-140 Ci NID NID N/D N/D Co-58 Ci NID 2.12E-06 N/D N/D Co-60 Ci NtD NID N/D N/D Mn-54 Ci NID NID N/D N/D Fe-59 Ci N/D NID N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci NID NID N/D N/D Ce-141 Ci N/D NID N/D N/D Ce-144 Ci NID NID N/D N/D C-14 Ci N/D 4.llE-03 N/D 2.37E+OO TOTAL FOR PERIOD Ci NIA 4.14E-03 NA 2.37E+OO TABLElC EFFLuENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/15 TO 12/31/15 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOUR.TH THIRD FOURTH QUARTER* QUARTER QUARTER ----QUARTER 1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D 1.76E-06 Nin N/D Kr-87 Ci N/D l.66E-06 NID NID Kr-88 Ci N/D 3.14E-06 N/D N/D Xe-133 Ci N/D
  • l.25E-05 N/D 5.66E-04 Xe-135 Ci N/D 2.28E-05 N/D N/D Xe-135m Ci N/D 4.26E-06 N/D NID Xe-138 Ci N/D N/D N/D N/D Xe-131m *ci N/D N/D N/D N/D Xe-l33m Ci N/D N/D N/D N/D Ar=41. Ci 2.25E-04 4.93E-04 N/D N/D TOTAL FOR PERIOD Ci 2.25E-04 5.40E-04 NIA 5.66E-04 2. IODINES 1-13-1 Ci N/D N/D N/D N/D 1-132 Ci NID l.31E-03 N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci NIA l.31E-03 NIA NIA 3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D NID Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D .NID* NID N/D Co-58 Ci 4:93E-06 6.89E-06 N/D 2.12E-07 Co-60 Ci N/D N/D N/D 5.03E-08 Mn-54 Ci
  • N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D NID N/D N/D. Ce-144 Ci NIP N/D N/D N/D C-14 Ci 2.56E-03 6.15E-03 N/D 6.45E-03 TOTAL FOR PERIOD Ci 2.56E-03 6.16E-03 NA 6.45E-03
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