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{{#Wiki_filter:ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT | {{#Wiki_filter:ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT | ||
NORTH ANNA POWER STATION | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2022 TO DECEMBER 31, 2022 INDEX Section No. | (JANUARY 01, 2022 TO DECEMBER 31, 2022) | ||
PREPARED BY: B,. J ~/M,,. ~, | |||
Supervisor Radiological Analysis and Instrumentation 0 | |||
APPROVED BY:_,£.....l,:.::..:...:..,,__R,c.... ~ (;)=..===-- | |||
J:i&.~ | |||
Manager Radiological Protection and Chemistry FORWARD | |||
This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 (10CFR50.36a) and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and I0CFR72.44(d)(3). | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT | |||
FOR THE | |||
NORTH ANNA POWER STATION | |||
JANUARY 01, 2022 TO DECEMBER 31, 2022 | |||
INDEX | |||
Section No. Subject | |||
EXECUTIVE | |||
==SUMMARY== | ==SUMMARY== | ||
................................... 4 | |||
2 PURPOSE AND SCOPE..................................... 5 | |||
3 DISCUSSION.................................................. 5-6 | |||
4 SUPPLEMENTAL INFORMATION....................... 6 Effluent Release Data.............................................. 7 Annual and Quarterly Doses...................................... 8 Revisions to Offsite Dose Calculation Manual (ODCM)........................................ 9 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems.................................................. | |||
In operability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation........................................ 11 Unplanned Releases............................................. 12 Lower Limits of Detection (LLD) for Effluent Sample Analysis........................... 13-14 Results of Ground Water Protection Initiative Sample Analysis..................................... 15-20 | |||
Carbon-14 Calculations........................................ 21 | |||
1.0 EXECUTIVE | Miscellaneous Annual Effluent Release Report Log........................ 22 1.0 EXECUTIVE | ||
==SUMMARY== | ==SUMMARY== | ||
The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2022 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2022 and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents. | The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2022 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2022 and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents. | ||
There were no releases from the ISFSI during 2022. | There were no releases from the ISFSI during 2022. | ||
There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also, there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6. | There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also, there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6. | ||
10 CFR 50, Appendix I dose calculations were performed on the 2022 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following: | 10 CFR 50, Appendix I dose calculations were performed on the 2022 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following: | ||
: a. | : a. The total body dose due to liquid effluents was 8.738E-01 mrem, which is 14.563% of the dose limit, and the critical organ dose due to liquid effluents was 8.790E-01 mrem, which is 4.395% of the dose limit. | ||
: b. | : b. The air dose due to noble gases was 6. 7 I IE-05 mrad gamma, which is 3.356E-04% of the annual gamma dose limit, and 3.790E-05 mrad beta, which is 9.475E-05% of the annual beta dose limit. | ||
: c. | : c. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days including C-14 was l.079E+0 mrem, which is 3.60% of the annual dose limit. The bases ofC-14 calculations are described in Attachment 9. | ||
: d. | : d. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days not including C-14 was 7.977E-03 mrem, which is 2.659E-02% of the annual dose limit. | ||
There were no major changes to either the radioactive liquid waste treatment system, or to the gaseous, and solid waste treatment systems during this reporting period. | There were no major changes to either the radioactive liquid waste treatment system, or to the gaseous, and solid waste treatment systems during this reporting period. | ||
There was no revision to the Offsite Dose Calculation Manual during this reporting period. | There was no revision to the Offsite Dose Calculation Manual during this reporting period. | ||
Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas. | Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas. | ||
2.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities | 4 2.0 PURPOSE AND SCOPE | ||
The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", | |||
Revision 1, June 1974, with data summarized on a quarterly basis for Table 1 and2 and on an annual basis on Table 3. The report submitted before May 1st of each year 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 the previous calendar year. The report also includes a list of unplanned releases during the reporting period in Attachment 6. | Revision 1, June 1974, with data summarized on a quarterly basis for Table 1 and2 and on an annual basis on Table 3. The report submitted before May 1st of each year 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 the previous calendar year. The report also includes a list of unplanned releases during the reporting period in Attachment 6. | ||
As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. | As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. | ||
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6. 7 .2 .a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50 .59 evaluation are included. | |||
As required by the ODCM, Sections 6.2.2.b.2 and 6.3 .2.b.3, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. | Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6. 7.2.a.4. Information to support the reason( s) for the change( s) and a summary of the 10 CFR 50.59 evaluation are included. | ||
3.0 DISCUSSION The basis for the calculation of 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, tritium, and all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to 15 00 mrem/yr to the critical organ at or beyond the site boundary. | |||
The basis for the calculation of percent of Technical' Specification for the total body and skin in Table lA of Attachment 1 is the ODCM, section 6.3 .1, which requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin. | As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. | ||
3.0 DISCUSSION The basis for the calculation of 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, tritium, and all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to 15 00 mrem/yr to the critical organ at or beyond the site boundary. | |||
The basis for the calculation of percent of Technical' Specification for the total body and skin in Table lA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin. | |||
The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases ofairbome iodine-13 I, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland. | The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases ofairbome iodine-13 I, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland. | ||
The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, 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 2.0E-4 uCi/ml. | 5 The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, 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 2.0E-4 uCi/ml. | ||
The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child. The critical organ dose calculation was determined to be the child liver. The age group is exposed via the drinking water and fish ingestion pathways. | The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child. The critical organ dose calculation was determined to be the child liver. The age group is exposed via the drinking water and fish ingestion pathways. | ||
As shown in Attachment 6, there were no unplanned releases meeting the requirements of 6. 7.2.a.3 of the ODCM. | As shown in Attachment 6, there were no unplanned releases meeting the requirements of 6. 7.2.a.3 of the ODCM. | ||
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 volume and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A). | 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 volume and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A). | ||
4.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is performed to identify ifnew location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM. There were no new sampling locations added. There were five (5) changes made from the land use census in 2022. The nearest resident location in the ESE sector changed from 1. 70 miles to 1.53 miles. The physical address of the nearest garden location in the ESE sector changed, however, the location remained at 1. 70 miles. The nearest garden location in the SE sector changed from 1.40 miles to 1.90 miles. The nearest resident in the SW sector changed from 1.65 miles to 1.56 miles. Finally, the nearest garden location in the W sector changed from 1.93 miles to 1.96 miles. | |||
4.0 SUPPLEMENTAL INFORMATION | |||
As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is performed to identify ifnew location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM. There were no new sampling locations added. There were five (5) changes made from the land use census in 2022. The nearest resident location in the ESE sector changed from 1. 70 miles to 1.53 miles. The physical address of the nearest garden location in the ESE sector changed, however, the location remained at 1. 70 miles. The nearest garden location in the SE sector changed from 1.40 miles to 1.90 miles. The nearest resident in the SW sector changed from 1.65 miles to 1.56 miles. Finally, the nearest garden location in the W sector changed from 1.93 miles to 1.96 miles. | |||
Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples were not collected in 2022 because the last of the operating dairies in the sampling area ceased operations at the start ofcalendar year 2018. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and November through December due to seasonal unavailability. All other vegetation samples were obtained. | Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples were not collected in 2022 because the last of the operating dairies in the sampling area ceased operations at the start ofcalendar year 2018. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and November through December due to seasonal unavailability. All other vegetation samples were obtained. | ||
Attachment 8 contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site. | Attachment 8 contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site. | ||
Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14. | Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14. | ||
Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values. | Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values. | ||
6 | 6 ATTACHMENT 1 EFFLUENT RELEASE DATA (01/22 - 12/22) | ||
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, except that in accordance with Step 6. 7.2.a. l of the O DCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis. | |||
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, except that in accordance with Step 6.7 .2 .a. l of the | |||
TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | 7 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page 1 of 2 1 ST | Page 1 of 2 | ||
1 ST 2ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%) | |||
A. Fission and Activiation Gases: | A. Fission and Activiation Gases: | ||
: 1. Total Release | : 1. Total Release Curies 1.17E--01 3.18E-02 1.80E+1 | ||
: 2. Average Release Rate For Period | : 2. Average Release Rate For Period µCi/sec 1.50E-02 4.04E-03 | ||
: 1. Total lodine-131 Release | |||
: 2. Average Release Rate For Period | B. Iodines: | ||
: 1. Total Particulate (T112 > 8 days) Release | : 1. Total lodine-131 Release Curies N/D N/D 2.80E+1 | ||
: 2. Average Release Rate For Period | : 2. Average Release Rate For Period µCi/sec N/D N/D | ||
: 3. Gross Alpha Radioactivity Release | |||
: 1. Total Release | C. Particulate {T112 > 8 da~s}: | ||
: 2. Average Release Rate For Period | : 1. Total Particulate (T112 > 8 days) Release Curies 2.56E-05 1.32E-06 2.80E+1 | ||
: 1. Total Release | : 2. Average Release Rate For Period µCi/sec 3.29E-06 1.68E--07 | ||
: 2. Average Release Rate For Period | : 3. Gross Alpha Radioactivity Release Curies N/D N/D | ||
D. Tritium: | |||
: 1. Total Release Curies 2.97E+0O 1.19E+00 3.10E+1 | |||
: 2. Average Release Rate For Period µCi/sec 3.82E-01 1.52E--01 | |||
E. Carbon-14 | |||
: 1. Total Release Curies 1.28E+01 3.47E+00 | |||
: 2. Average Release Rate For Period µCi/sec 1.65E+00 4.41E 0 01 | |||
F. Percentage Of Technical Specification Limits | F. Percentage Of Technical Specification Limits | ||
: 1. Total Body Dose Rate | : 1. Total Body Dose Rate % 2.56E--06 4.24E-05 | ||
: 2. Skin Dose Rate | : 2. Skin Dose Rate % 9.87E-07 1.03E-05 | ||
: 3. Critical Organ Dose Rate (with C-14) | : 3. Critical Organ Dose Rate (with C-14) % 8.11E-03 6.41E-03 Critical Organ Dose Rate (without C-14) % 2.55E-04 6.75E-05 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page 2 of 2 | |||
3RD 4TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%) | |||
A. Fission and Activiation Gases: | A. Fission and Activiation Gases: | ||
: 1. Total Release | : 1. Total Release Curies 8.22E-02 1.28E-02 1.80E+1 | ||
: 2. Average Release Rate For Period | : 2. Average Release Rate For Period µCi/sec 1.03E-02 1.61E-03 | ||
: 8. Iodines: | : 8. Iodines: | ||
: 1. Total lodine-131 Release | : 1. Total lodine-131 Release Curies N/D N/D 2.80E+1.,.,.. - | ||
: 2. Average Release Rate For Period | : 2. Average Release Rate For Period µCi/sec N/D N/D.. | ||
C. Particulate {T1I2 > 8 dall'.s}: | C. Particulate {T1I2 > 8 dall'.s}: | ||
: 1. Total Particulate (T112 > 8 days) Release | : 1. Total Particulate (T112 > 8 days) Release Curies 1.10E-05 0.00E+00 2.80E+1 | ||
: 2. Averaoe Release Rate For Period | : 2. Averaoe Release Rate For Period µCi/sec 1.38E-06 0.00E+00 | ||
: 3. Gross Alpha Radioactivity Release | : 3. Gross Alpha Radioactivity Release Curies N/D N/D | ||
: 1. Total Release | |||
* 3.10E+1 | D. Tritium: | ||
: 2. Average Release Rate For Period | : 1. Total Release Curies 1.25E+01 3.17E+00 | ||
: 1. Total Release | * 3.10E+1 ' | ||
: 2. Averaae Release Rate For Period | : 2. Average Release Rate For Period µCi/sec 1.58E+00 3.99E-01 | ||
: 1. Total Body Dose Rate | |||
: 2. Skin Dose Rate | F. Carbon-14 | ||
: 3. Critical Organ Dose Rate (with C-14) | : 1. Total Release Curies 8.98E+00 1.39E+00 | ||
: 2. Averaae Release Rate For Period µCi/sec 1.13E+00 1.75E-01 | |||
F. Percentage Of Technical Specification Limits | |||
: 1. Total Body Dose Rate % 5.16E-06 6.12E-07 | |||
: 2. Skin Dose Rate % 1.54E-06 1.65E-07 | |||
: 3. Critical Organ Dose Rate (with C-14) % 6.95E-03 5.12E-04 Critical Organ Dose Rate {without C-14) % 1.06E-03 2.70E-04 TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | |||
Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases: | |||
Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon-131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 9.62E-02 3.91 E-03 Xenon -133m Ci N/D N/D 5.39E-04 N/D Xenon -135 Ci N/D N/D 7.83E-03 4.82E-05 Xenon -135m Ci N/D N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon -41 Ci N/D 6.34E-03 N/D 2.35E-03 | |||
Total For Period Ci N/D 6.34E-03 1.05E-01 6.31 E-03 | |||
Iodines: | |||
Iodine -130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine -135 Ci N/D N/D N/D N/D Br-82 Ci 1.13E-07 1.84E-07 Total For Period Ci 1.13E-07 1.84E-07 N/D N/D | |||
Particulates: | |||
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium -136 Ci N/D N/D N/D N/D Cesium -137 Ci N/D N/D N/D N/D TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES. FOR {01/22 - 12/22) | |||
Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) | |||
As-76 Ci 2.16E-07 8.67E-07 N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Ag-110m Ci N/D 7.66E-09 N/D N/D | |||
Total for Period (T1/2 > 8 days) Ci N/D 7.66E-09 N/D N/D Total for Period (T1/2 < 8 days) Ci 2.16E-07 8.67E-07 N/D N/D | |||
Total For Period Ci 2.16E-07 8.75E-07 N/D N/D | |||
GROSS ALPHA: Ci N/D N/D N/D N/D | |||
TRITIUM: Ci 1.53E-01 5.01E-01 4.94E-03 5.57E-04 | |||
CARBON-14 Ci N/D 6.93E-01 1.15E+01 6.89E-01 TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | |||
Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases: | |||
Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon - 133 Ci 3.48E-02 N/D 2.11 E-02 1.08E-02 Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D 5.77E-04 4.25E-05.. | |||
Xenon -135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon-41 Ci 1.07E-02 N/D 1.11 E-03 1.92E-03 Total For Period Ci 4.55E-02 N/D 2.28E-02 1.28E-02 | |||
Iodines: | |||
Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Bromine-82 Ci 5.52E-08 N/D N/D N/D | |||
Total For Period Ci 5.52E-08 N/D N/D N/D | |||
Particulates: | |||
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver-11 Om Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium - 137 Ci N/D N/D N/D N/D TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MOOE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | |||
Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) | |||
Arsenic-76 Ci 1.10E-07 N/D N/D N/D Cerium -141 Ci NID NID N/D N/O Cerium 144 Ci N/O N/D N/D NID | |||
Total for Period (T1/2 > 8 days) Ci N/O N/D N/D.. NID Total for Period (T1/2 < 8 days) Ci 1.10E-07 N/D N/O N/O | |||
Total For Period Ci 1.10E-07 N/D N/D N/O | |||
GROSS ALPHA: Ci N/O N/D NID NID | |||
TRITIUM: Ci 5.48E-01 1.25E-01 3.47E-03 1.34E-03 | |||
TABLE | CARBON-14 Ci 4.97E+00 N/D 2.49E+00 1.39E+00 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page | Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases: | ||
Krypton 85 Ci N/0 N/D N/D N/D Krypton 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D. | |||
Xenon 133 Ci N/D N/D 1.13E-02 N/D Xenon 133m Ci N/D N/D 8.85E-05 N/D Xenon 135 Ci N/D N/D 1.02E-03 N/D Xenon -135m Ci N/D N/D N/0 NID Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon - 41 Ci N/D N/D 3.31E-06 1.91 E-02 Total For Period Ci N/D N/D 1.24E-02 1.91 E-02 | |||
Iodines: | |||
Iodine -130 Ci N/0 N/D N/D N/D Iodine - 131 Ci N/0 N/D N/D N/D Iodine 132 Ci N/D N/D N/D N/D Iodine 133 Ci N/0 N/D N/D N/D Iodine - 134 Ci N/D N/0 N/0 N/D Iodine 135 Ci N/D N/D N/D N/D | |||
Total For Period Ci N/D N/D N/0 N/D | |||
Iodine -130 | |||
TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 | Particulates: | ||
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci 9.81E-06 N/D N/D N/D Iron 59 Ci N/D N/D N/D N/D Cobalt-60 Ci 1.03E-05 1.31E-06 N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium 134 Ci N/D N/D N/D N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 | |||
* 12/22) | * 12/22) | ||
Page 2 of 4 CONTINUOUS MODE | Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) | ||
Cesium-137 | Cesium-137 Ci 1.97E-06 N/D N/D N/D Arsenic-76 ( T1/2 < 8 days J Ci N/D 4.73E-05 N/D N/D Rubidium-88 Ci N/D N/D N/D N/D. | ||
Cerium 144 | Cerium 144 Ci N/D N/D N/D N/D Niobium-95 Ci 3.55E-06 N/D N/O N/O Zirconium-95 Ci N/O N/D N/D N/D Tellurium-131m (T1/2 < 8 days) Ci N/D N/D N/D N/D Yttrium-91m (T1/2 < 8 days) Ci N/D N/D N/D N/D Chromium-51 Ci N/O N/D N/D N/D Total for Period (T1/2 > 8 days) Ci 2.56E-05 1.31E-06 N/D N/O Total for Period (T1/2 < 8 days) Ci N/D 4.73E-05 N/D N/O | ||
Total For Period Ci 2.56E-05 4.86E-05 N/D N/O | |||
GROSS ALPHA: Ci N/D N/D N/D N/D | |||
TRITIUM: Ci N/D N/D 2.81E+00 6.93E-01 | |||
CARBON-14 Ci N/O N/O 1.35E+00 2.09E+00 | |||
TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page 3 of 4 CONTINUOUS MODE | Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases: | ||
Krypton - 85 | Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D NID 3.37E-06 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon 133 Ci N/D N/D 1.25E-02 N/0 Xenon -133m Ci N/D N/D 2.90E-04 N/D Xenon - 135 Ci N/D N/D 1.09E-03 N/D Xenon -135m Ci N/D N/D N/D N/D Xenon-137 Ci N/D N/D N/D N/D | ||
. Xenon -138 | . Xenon -138 Ci N/D N/D N/D N/D | ||
!Argon - 41 | !Argon - 41 Ci N/D N/D 7.15E-05 N/D Total For Period Ci N/D N/D 1.39E-02 N/D | ||
Iodine - 130 | |||
Iodine 131 | Iodines: | ||
Iodine 132 | Iodine - 130 Ci N/D N/D N/D N/D. | ||
Iodine 131 Ci NID N/D NID N/D.. | |||
Iodine 132 Ci N/D N/D N!D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine 134 Ci N/D N/D NID N/D Iodine -135 Ci N/D N/D N/D N/D | |||
Total For Period Ci N/D N/D N/D N/D | |||
TABLE 1C NORTH ANNA POWER STATION ANNUAL | Particulates: | ||
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/0 Cobalt-60 Ci 1.10E-05 N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/0 Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL | |||
* RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | * RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page 4 of 4 CONTINUOUS MODE | Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) | ||
Cesium -137 | Cesium -137 Ci N/D N/D N/D N/D Niobium-95 (T1/2 > 8 days) Ci N/D N/D N/D N/D Ag-110m (T1/2 > 8 days) Ci N/D N/D N/D N/D Other (Specify) | ||
Total for Period (T1/2 > 8 days) | |||
Total for Period (T1/2 > 8 days) Ci 1.10E-05 N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D | |||
Total For Period Ci 1.10E-05 N/D N/D N/D | |||
GROSS ALPHA: Ci N/D N/D N/D N/D | |||
TRITIUM: Ci 1.04E+01 2.53E+00 1.55E+00 5.15E-01 | |||
TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF Ali.. 'RELEASES FOR (01/22 - 12/22) | CARBON-14 Ci N/D N/D 1.52E+00 3.91 E-03 TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF Ali.. 'RELEASES FOR (01/22 - 12/22) | ||
Page 1 of 2 1 ST | Page 1 of 2 1 ST 2 ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%) | ||
A. Fission and Activiation Products: | A. Fission and Activiation Products: | ||
: 1. Total Release (not including tritium, noble gas, and gross alpha). | : 1. Total Release (not including tritium, noble gas, and gross alpha). Curies 5.03E-03 3.21 E-03 2.00E+01 | ||
: 2. Average diluted concentration during the period. | : 2. Average diluted concentration during the period. µCi/ml 1.71E-11 4.33E-12 | ||
: 3. Percent of applicable limit (T.S.) | : 3. Percent of applicable limit (T.S.) % 2.39E-05 7.37E-06 | ||
TABLE. 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE .EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/22 - 12/22) | B. Tritium: | ||
Page 2 of2 3 RD | : 1. Total release activity. Curies 9.37E+02 5.87E+02 2.00E+01 | ||
: 2. Average diluted concentration during the period. µCi/ml 3.18E-06 7.92E-07 | |||
: 3. Percent of applicable limit (T.S.) % 3.18E-02 7.92E-03 | |||
C. Dissolved and Entrained Gases: | |||
: 1. Total release activity. Curies N/D N/D 2.00E+01 | |||
: 2. Average diluted concentration during the period. ~tCi/ml N/D N/D | |||
: 3. Percent of applicable limit (T.S.) % N/D N/D | |||
D. Gross Alpha Radioactivity: | |||
: 1. Total release activity. Curies N/D N/D 2.00E+01 | |||
E. Volume of waste released: (prior to dilution). Liters 9.90E+07 8.85E+07 3.00E+00 | |||
F. Total volume of dilution water used during the period. Liters 2.95E+11 7.42E+11 3.00E+00 TABLE. 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE.EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/22 - 12/22) | |||
Page 2 of2 3 RD 4 TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%) | |||
A. Fission and Activiation Products: | A. Fission and Activiation Products: | ||
: 1. Total Release (not including tritium, noble gas, and gross alpha). | : 1. Total Release (not including tritium, noble gas, and gross alpha). Curies 2.81 E-03 2.33E-03 2.00E+01 | ||
: 2. Average diluted concentration during the period. | : 2. Average diluted concentration during the period. µCi/ml 3.77E-12 4.04E-12 | ||
: 3. Percent of aoolicable limit (T.S.) | : 3. Percent of aoolicable limit (T.S.) % 7.01E-06 5.41E-06 B. Tritium: | ||
: 1. Total release activity. | : 1. Total release activity. Curies 6.95E+02 2.56E+02 2.00E+01 | ||
: 2. Average diluted concentration during the period. | : 2. Average diluted concentration during the period. µCi/ml 9.32E-07 4.43E-07 | ||
: 3. Percent of applicable limit (T.S.) | : 3. Percent of applicable limit (T.S.) % 9.32E-03 4.43E-03 C. Dissolved and Entrained Gases: | ||
: 1. Total release activity. | : 1. Total release activity. Curies N/D N/D 2.00E+01 | ||
: 2. Average diluted concentration during the period. | : 2. Average diluted concentration during the period. µCi/ml N/D N/D | ||
: 3. Percent of applicable limit (T.S.) | : 3. Percent of applicable limit (T.S.) % N/D N/D | ||
: 1. Total release activity. | |||
D. Gross Alpha Radioactivity: | |||
: 1. Total release activity. Curies N/D N/D 2.00E+01 | |||
E. Volume of waste released: {prior to dilution). Liters 8.20E+07 1.02E+08 3.00E+O0 | |||
F. Total volume of dilution water used durin~ the period. Liters 7.46E+11 5.78E+11 3.00E+00 TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22) | |||
Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCUDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products: ~*-, | |||
Manganese - 54 Ci 1.38E-04 N/D N/A N/A. | |||
Iron - 59 Ci N/D N/D N/A N/&,_, | |||
Cobalt - 58 Ci 3.26E-03 1.66E-03 N/A N/A Cobalt - 60 Ci 1.59E-03 8.99E-04 N/A NIA Strontium - 89 Ci N/D N/D NIA NIA Strontium - 90 Ci N/D N/D NIA N/A Tellurium-123m Ci N/D 1.47E-04 N/A NIA Tellurium-132 Ci 2.47E-05 NID N/A NIA Chromium-51 Ci N/D NID NIA NIA Iodine 131 Ci N/D NID N/A N/A Iodine - 133 Ci N/D N/D N/A NIA Cesium -134 Ci N/D N/D NIA N/A.. | |||
Cesium 137 Ci N/D 1.36E-04 N/A NIA Zirconium - 95 Ci N/D N/D NIA NIA Cerium - 141 Ci N/D N/D NIA N/A Silver-110m Ci 2.15E-05 NID N/A NIA Tellurium-125m Ci N/D 7.02E-05 N/A N/A Niickel - 63 (T1/2 > 8 days) Ci N/D N/D NIA N/A Antimony-125 Ci NID 3.04E-04 N/A NIA Total for Period Ci 5.03E-03 3.21E-03 N/A N/A | |||
TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22) | TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page | Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases: | ||
Manganese - 54 | Xenon -133 Ci NID NID NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA Xenon -135m Ci NID NID NIA N/A Other (Specify) Ci NID N/D N/A N/A Krypton-88 ( T1/2 < 8 days) Ci N/D N/D N/A N/A Krypton-85 (T1/2 > 8 days) Ci N/D N/D N/A N/A | ||
Iron | |||
Cobalt - 58 | Total for Period Ci N/D N/D N/A N/A | ||
Cesium | |||
Tritium Ci 9.37E+02 5.87E+02 N/A N/A | |||
Gross Alpha Ci N/D N/D N/A - NIA TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22) | |||
Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products: | |||
Manganese - 54 Ci N/D N/D N/A N/A Iron 59 Ci N/D N/D N/A N/A Cobalt-58 Ci 1.69E-03 1.52E-03 N/A N/A Cobalt-60 Ci 9.63E-04 6.60E-04 N/A NIA | |||
Strontium - 89 Ci N/D N/D NIA N/A Strontium - 90 Ci N/D N/D NIA N/A Niobium 95 Ci N/D N/D N/A N/A.. | |||
Zirconium 95 Ci N/D N/D N/A N/A Silver - 11 Om Ci N/D N/D N/A N/A Iodine -131 Ci N/D N/D N/A N/A lodine-133 Ci N/D N/0 N/A N/A Cesium -134 Ci N/D N/D NIA NIA Cesium-137 Ci 1.13E-04 1.12E-05 N/A N/A Tellurium-123m Ci 4.82E-05 N/0 N/A N/A Cerium - 141 Ci N/0 N/0 N/A N/A Chromium-51 Ci N/0 N/D NIA N/A Nickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A NIA | |||
-~., | |||
Ruthenium-105 {T1/2 < 8 days) Ci N/D N/0 NIA NIA Antimony-125 (T1/2 > 8 days) Ci N/D 1.12E-04 N/A N/A Antimony-122 (T1/2 > 8 days) Ci N/D N/D NIA NIA Tellurium-125m (T1/2 > 8 days) Ci N/D 2.58E-05 NIA NIA | |||
TABLE | Total for Period Ci 2.81E-03 2.33E-03 NIA NIA TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22) | ||
Page | Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases: | ||
Xenon -133 | Xenon -133 Ci NID NID NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA *- | ||
Xenon -135m Ci NID N/D NIA NIA Other (Specify) - | |||
Argon - 41 (T112 < 8 days) Ci NID NID NIA NIA **- | |||
Krypton - 85 (T112 > 8 days) Ci NID NID NIA NIA | |||
Total for Period Ci NID NID NIA NIA | |||
Tritium Ci 6.95E+02 2.56E+02 NIA NIA | |||
TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-22 THROUGH 12-31-22 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month | Gross Alpha Ci NID NID NIA NIA TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-22 THROUGH 12-31-22 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total | ||
: 1. Type of Waste | : 1. Type of Waste Unit Period Percent Error (%) | ||
: a. Spent resins, sludges, filters sludge, | : a. Spent resins, sludges, filters sludge, m3 1.17E+01 | ||
* 2.50E+01 evaporator bottoms, etc., | * 2.50E+01 evaporator bottoms, etc., Ci 1.53E+02 2.50E+01 | ||
: b. Dry compressible waste, contaminated | : b. Dry compressible waste, contaminated m3 2.05E+02 ** 2.50E+01 equipment, etc., Ci 1.78E-01 2.50E+01 C. Irradiated components, control rods, m3 0.00E+00... 2.50E+01 etc., Ci 0.0OE+0O 2.50E+01 | ||
equipment, etc., | |||
Irradiated components, control rods, | |||
: d. Other (describe) | : d. Other (describe) | ||
Used oil/Blast media/Sewage/Gravel | Used oil/Blast media/Sewage/Gravel m3 4.20E-01 **** 2.50E+01 Dessicant/Soil/Construction debris Ci 3.78E-03 2.50E+01 Animal Carcasses | ||
: 2. Estimate of major nuclide composition | : 2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%) | ||
: a. Co-60 | : a. Co-60 5.74E+01 8.75E+01 2.50E+01 Ni-63 2.42E+01 3.68E+01 2.50E+01 Fe-55 6.23E+00 9.50E+00 2.50E+01 Mn-54 3.70E+00 5.65E+00 2.50E+01 Co-58 3.35E+00 5.10E+00 2.50E+01 Sb-125 1.54E+00 2.35E+00 2.50E+01 Cs-137 1.07E+00 1.64E+00 2.50E+01 Zn-65 6.60E-01 1.01E+00 2.50E+01 Be-7 6.30E-01 9.61 E-01 2.50E+01 Aa-110m 2.36E-01 3.60E-01 2.50E+01 Ni-59 2.35E-01 3.59E-01 2.50E+01 H-3 1.67E-01 2.54E-01 2.50E+01 Nb-95 1.65E-01 2.52E-01 2.50E+01 | ||
: b. Co-60 | : b. Co-60 4.72E+01 8.45E-02 2.50E+01 Co-58 1.66E+01 2.96E-02 2.50E+01 Cr-51 8.20E+00 1.46E-02 2.50E+01 Nb-95 6.93E+00 1.24E-02 2.50E+01 Fe-55 6.49E+00 1.16E-02 2.50E+01 Ni-63 3.93E+00 7.01E-03 2.50E+01 Zr-95 3.88E+00 6.93E-03 2.50E+01 Cs-137 2.94E+00 5.25E-03 2.50E+01 Sb-125 1.62E+00 2.89E-03 2.50E+01 Mn-54 1.31E+00 2.33E-03 2.50E+01 Aa-110m 2.12E-01 3.78E-04 2.50E+01 Fe-59 1.26E-01 2.25E-04 2.50E+01 H-3 1.23E-01 2.19E-04 2.50E+01 Te-125m 9.84E-02 1.76E-04 2.50E+01 | ||
: c. NONE | : c. NONE | ||
: d. Co-60 | : d. Co-60 5.11 E+01 1.93E-03 2.50E+01 Ni-63 2.22E+01 8.40E-04 2.50E+01 Cs-137 1.61 E+01 6.10E-04 2.50E+01 H-3 8.70E+00 3.29E-04 2.50E+01 Sb-125 8.89E-01 3.36E-05 2.50E+01 Cs-134 1.83E-01 7.66E-06 2.50E+01 Mn-54 1.17E-01 6.91E-06 2.50E+01 TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01-01-22 THROUGH 12-31-22 Page 2 of 2 | ||
: 3. Solid Waste Disposition | |||
Number of Shipments Mode of Transportation Destination | |||
6 Truck Oak Ridge, TN 1 Truck Andrews, TX | |||
Note: Some of the 7 solid waste shipments contained multiple waste types and are therefore listed in more than one category below. | |||
B. Irradiated Fuel Shipments (Disposition) | B. Irradiated Fuel Shipments (Disposition) | ||
Number of Shipments | |||
Number of Shipments Mode of Transportation Destination | |||
0 N/A N/A | |||
* (2) shipments containing resins were shipped to a licensed waste processor for final dewatering and disposal. | |||
(1) shipment containing resins was shipped to a licensed waste facility for disposal. | (1) shipment containing resins was shipped to a licensed waste facility for disposal. | ||
(1) shipment containing mechanical filters was shipped to a licensed waste processor for processing. | (1) shipment containing mechanical filters was shipped to a licensed waste processor for processing. | ||
(1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal. | (1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal. | ||
** (4) shipments containing dry cornpactible waste were shipped to a licensed waste processor for processing. | |||
(1) shipment containing low activity calibration standards was shipped to a licensed waste facility for disposal. | (1) shipment containing low activity calibration standards was shipped to a licensed waste facility for disposal. | ||
*** None | |||
**** (1) shipment containing waste oil was shipped to a licensed waste processor for processing. | |||
(1) shipment containing sludge was shipped to a licensed waste processor for processing. | (1) shipment containing sludge was shipped to a licensed waste processor for processing. | ||
ATTACHMENT 2 ANNUAL AND OUARTERL Y DOSES (01/22 - 12/22) | |||
An assessment ofradiation 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 will be made as required by OD.CM Section 6.7.2. | An assessment ofradiation 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 will be made as required by OD.CM Section 6.7.2. | ||
ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM) | 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 3.305E-1 2.076E-1 2.454E-1 9.034E-2 8.738E-1 Critical Organ Dose (mrem) 3.306E-1 2.103E-1 2.475E-1 9.058E-2 8.790E-1 | ||
1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 3.639E-6 5.552E-5 7.120E-6 8.310E-7 6.711E-5 Noble Gas Beta Dose (mrad) 8.879E-6 l.972E-5 8.616E-6 6.846E-7 3.790E-5 Critical Organ (Child bone) | |||
Dose for 1-131, 1-133, H-3, Particulates with T1/2>8 days (including C-14) (mrem) 5.420E-1 2.970E-1 l.933E-l 4.624E-2 l.079E+0 | |||
Critical Organ (Child thyroid) | |||
Dose for 1-131, 1-133, H-3, Particulates with T1/2> 8 days (excluding C-14) (mrem) 1.222E-3 3.527E-4 5.109E-3 1.293E-3. 7.977E-3 | |||
8 ATTACHMENT 3 | |||
REVISIONS TO OFFSITE DOSE CALCULATION MANUAL | |||
(ODCM) | |||
(01/22 - 12/22) | (01/22 - 12/22) | ||
As required by Technical Specification 5.5.1.c, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment. | As required by Technical Specification 5.5.1.c, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment. | ||
There was no revision to the ODCM during this reporting period. | There was no revision to the ODCM during this reporting period. | ||
ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS (01122 - 12/22) | 9 ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS (01122 - 12/22) | ||
As required by the ODCM, Section 6.7 .2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable. | |||
As required by the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable. | |||
There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2022. | There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2022. | ||
ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01122 ~ 12/22) | 10 ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS | ||
As required by the ODCM, Sections 6.2.2.b.2 and 6.3 .2. b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment. | |||
EFFLUENT MONITORING INSTRUMENTATION | |||
(01122 ~ 12/22) | |||
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2. b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment. | |||
No liquid and/or gaseous effluent monitoring instrumentation was out of service for> 30 days during the reporting period. | No liquid and/or gaseous effluent monitoring instrumentation was out of service for> 30 days during the reporting period. | ||
ATTACHMENT 6 UNPLANNED RELEASES (01/22 - 12/22) | 11 ATTACHMENT 6 | ||
As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, ofradioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment. | |||
There were no unplanned releases during calendar year 2022 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground Water Protection Initiative, NEI 07-07. The current groundwater monitoring network provides adequate assurance that radiological contamination of groundwater will be detected in a timely manner. (i.e., prior to migration offsite). Both the historic and current tritium levels do not pose a risk to human health and the environment. The current tritium levels are well below the drinking water standard of 20,000 pCi/L. Furthermore, the impacted groundwater is controlled and discharged via a monitored discharge. | UNPLANNED RELEASES | ||
(01/22 - 12/22) | |||
As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, ofradioactive material in | |||
gaseous and liquid effluents occurring during the reporting period, is made in this attachment. | |||
There were no unplanned releases during calendar year 2022 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to | |||
unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground | |||
Water Protection Initiative, NEI 07-07. The current groundwater monitoring network provides adequate assurance that radiological | |||
contamination of groundwater will be detected in a timely manner. (i.e., prior to migration offsite ). Both the historic and current | |||
tritium levels do not pose a risk to human health and the environment. The current tritium levels are well below the drinking | |||
water standard of 20,000 pCi/L. Furthermore, the impacted groundwater is controlled and discharged via a monitored discharge. | |||
ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22) | 12 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22) | ||
Gaseous Effluents: | Gaseous Effluents: | ||
ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22) | Required L.L.D. Typical L.L.D. | ||
Radioisotope µCi/mL µCi/mL | |||
Krypton-87 1.00E-4 2.50E-8 7.50E-8 | |||
Krypton-88 1.00E-4 4.00E-8 2.50E-7 | |||
Xenon -133 1.00E-4 2.00E-8 1.00E-7 | |||
Xenon-133m 1.00E-4 1.00E-7 4.00E-7 | |||
Xenon -135 1.00E-4 1.00E-8 5.00E-8 | |||
Xenon-135m 1.00E-4 5.00E-8 2.00E-7 | |||
Xenon -138 1.00E-4 9.00E-8 4.00E-7 | |||
Iodine - 131 1.00E-12 3.00E-14 1.00E-13 | |||
Iodine -133 1.00E-10 1.00E-14 7.00E-13 | |||
Manganese - 54 1.00E-11 2.00E-14 6.00E-14 | |||
Cobalt-58 1.00E-11 2.00E-14 6.00E-14 | |||
Iron - 59 1.00E-11 6.00E-14 1.00E-13 | |||
Cobalt-60 1.00E-11 3.00E-14 1.00E-13 | |||
Zinc-65 1.00E-11 6.00E-14 2.00E-13 | |||
Strontium - 89 1.00E-11 3.00E-14 8.00E-12 | |||
Strontium - 90 1.00E-11 3.00E-15 9.00E-12 | |||
Molybdenum - 99 1.00E-11 2.00E-14 1.00E-13 | |||
Cesium -134 1.00E-11 2.00E-14 8.00E-14 | |||
Cesium -137 1.00E-11 3.00E-14 8.00E-14 | |||
Cerium - 141 1.00E-11 3.00E-14 1.00E-13 | |||
Cerium -144 1.00E-11 1.50E-13 4.00E-13 | |||
Gross Alpha 1.00E-11 7.00E-15 2.00E-14 | |||
Tritium 1.00E-6 4.00E-09 9.00E-09 | |||
13 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22) | |||
Liguid Effluents: | Liguid Effluents: | ||
ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS | Required L.L.D. Typical L.L.D. | ||
Radioisotope µCi/mL µCi/mL | |||
Krypton-87 1.00E-5 3.00E-8 1.00E-7 | |||
Krypton-88 1.00E-5 5.00E-8 5.00E-7 | |||
Xenon-133 1.00E-5 3.00E-8 1.00E-7 | |||
Xenon-133m 1.00E-5 9.00E-8 3.00E-7 | |||
Xenon-135 1.00E-5 1.00E-8 5.00E-8 | |||
Xenon-135m 1.00E-5 3.00E-8 2.00E-7 | |||
Xenon-138 1.00E-5 1.00E-7 '1.00E-6 | |||
Iodine - 131 1.00E-6 1.00E-8 5.00E-8 | |||
Manganese - 54 5.00E-7 1.00E-8 5.00E-8 | |||
Iron-55 1.00E-6 3.00E-7 8.00E-7 | |||
Cobalt-58 5.00E-7 1.50E-8 6.00E-8 | |||
Iron-59 5.00E-7 3.00E-8 7.00E-8 | |||
Cobalt-60 5.00E-7 1.00E-8 5.50E-8 | |||
Zinc - 65 5.00E-7 3.00E-8 6.00E-8 | |||
Strontium - 89 5.00E-8 1.00E-8 4.00E-8 | |||
Strontium - 90 5.00E-8 5.00E-9 9.00E-9 | |||
Molybdenum - 99 5.00E-7 2.00E-8 6.00E-8 | |||
Cesium -134 5.00E-7 1.50E-8 5.00E-8 | |||
Cesium -137 5.00E-7 1.50E-8 6.00E-8 | |||
Cerium -141 5.00E-7 3.00E-8 9.00E-8 | |||
Cerium-144 5.00E-7 1.00E-7 5.00E-7 | |||
Gross Alpha 1.00E-7 2.00E-8 7.00E-8 | |||
Tritium 1.00E-5 2.00E-6 5.00E-6 | |||
14 ATTACHMENT 8 | |||
RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS | |||
{01/22 - 12/22) | {01/22 - 12/22) | ||
The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water. | The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water. | ||
It complies with the requirements ofNEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials. | It complies with the requirements ofNEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials. | ||
Samples are obtained from monitoring wells installed both inside and outside the restricted area on a quarterly basis and analyzed onsite. | Samples are obtained from monitoring wells installed both inside and outside the restricted area on a quarterly basis and analyzed onsite. | ||
Annually, during the second quarter, these samples are analyzed by an Independent Lab. Samples are also obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Samples may be obtained more frequently than normal, if required and may be analyzed on-site or by an Independent Lab. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments 11 and 12 to VPAP-2103N. | Annually, during the second quarter, these samples are analyzed by an Independent Lab. Samples are also obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Samples may be obtained more frequently than normal, if required and may be analyzed on-site or by an Independent Lab. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments 11 and 12 to VPAP-2103N. | ||
ATTACHMENT 8 RES | On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2022. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "NI A" indicates a sample analysis was not performed for that sample. A"< value" indicates an analysis was performed but the result was less than the Minimum Detectable Activity, MDA, and the required LLD. If a result is greater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, due to the analysis software or interferences from naturally occurring radioactivity. In these cases, instead of the value, an explanatory footnote is provided. | ||
GWP-18 | 15 ATTACHMENT 8 RES UL TS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22) | ||
1st Quarter 2022 Sample Date Sample H.311> Gamma -Emitting 1-13111> Sr-89/90IMedia ParticulatesI1 > TRU 11 > 1> Fe-55I1 > Ni-63I1 > Alpha Pu-241I 1> | |||
GWP-18 01126122 WATER 3255 N/A N/A NIA NIA NIA NIA NIA PZ-1 02/13122 Insufficient volume PZ-2 02113122 Insufficient volume PZ-3 02/13/22 WATER <1133 NIA N/A NIA NIA NIA NIA N/A GWP-3 02113122 WATER <1133 NIA N/A NIA NIA NIA NIA NIA GWP-4 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-15R 03102122 WATER <1144 NIA NIA NIA NIA NIA NIA N/A GWP-17 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-18 02123122 WATER 4933 NIA NIA NIA NIA NIA NIA NIA GWP-19 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-20 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-6 02123122 WATER <1116 NIA NIA NIA NIA NIA NIA NIA GWP-18 03119122 WATER 4620 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 02123122 WATER <1385 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02123122 WATER <1142 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02123122 WATER <1142 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 03102122 WATER <1382 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 02123122 WATER 1418 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 02123122 WATER 1582 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 02123122 WATER 3329 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 02123122 WATER 2971 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 02123122 WATER 2456 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 02123122 WATER 3197 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 03119122 WATER 1364 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 03119122 WATER 1960 NIA NIA NIA NIA NIA NIA NIA | |||
(1) pCi/L | |||
16 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22) | |||
2nd Quarter 2022 | |||
Sample Date Sample H.3111 Gamma -Emitting 1-13111Media Particulatesl1l TRUl1l ) Sr-89/90 111 Fe-5511 l Ni-63111 Alpha Pu-241 111 | |||
GWP-18 04/04122 WATER 3966 NIA N/A NIA NIA NIA NIA NIA PZ-1 04111122 WATER <1287 NIA N/A NIA N/A NIA NIA NIA PZ-2 04/11122 WATER <1164 NIA N/A NIA N/A NIA NIA N/A PZ-3 04/06122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-3 04105122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-4 04106122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-5A 04108122 WATER <1164 NIA NIA N/A NIA NIA NIA NIA GWP-6 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-7 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-8 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-9 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-13 04111122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-16 04115122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA GWP-19 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-20 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-21 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-22 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-23 04111122 Insufficient volume GWP-14 04120122 WATER <1118 NIA NIA NIA NIA NIA NIA NIA GWP-15R 04115122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA GWP-17 04120122 WATER <1118 NIA NIA NIA NIA NIA N/A NIA GWP-18 05112122 WATER 3699 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05119122 WATER <1663 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 06106122 WATER 1990 NIA N/A NIA NIA NIA NIA NIA U-1 Mat Sump South 06106122 WATER 1410 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 06106122 WATER 1869 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 06106122 WATER 2026 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 06106122 WATER 2005 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 06106122 WATER 2724 NIA NIA NIA NIA NIA NIA NIA GWP-18 06120122 WATER 3616 N/A NIA NIA NIA NIA NIA NIA BTW-1 04112122 WATER <1126 N/A NIA NIA NIA NIA NIA NIA BTW-2 04114122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA BTW-4 04114122 WATER <1126 NIA NIA NIA NIA NIA N/A NIA TTW-2 04113122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA TTW-3 04112122 WATER <1126 NIA NIA NIA NIA N/A NIA NIA TTW-5 04114122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 04112122 WATER <948 NIA NIA NIA NIA NIA NIA NIA BTW-2 (2) 04114122 WATER <949 NIA NIA NIA NIA NIA NIA NIA BTW-4 (2) 04114122 WATER <950 NIA NIA NIA NIA NIA NIA NIA TTW-2 (2) 04113122 WATER <949 NIA NIA NIA NIA NIA NIA NIA | |||
17 TTW-3 (2) 04112122 WATER <949 NIA NIA NIA N/A NIA NIA NIA TTW-5 (2) 04/14/22 WATER <949 N/A N/A NIA NIA NIA NIA NIA PZ-3 (2) 04106/22 WATER 1100 NIA NIA NIA N/A N/A NIA NIA GWP-3 (2) 04/05/22 WATER <950 N/A N/A N/A NIA N/A NIA NIA GWP-4 (2) 04106/22 WATER <950 NIA N/A NIA NIA NIA NIA NIA GWP-5A(2) 04/08/22 WATER <949 NIA NIA N/A N/A NIA NIA N/A GWP-6 (2) 04/08/22 WATER <951 NIA N/A N/A NIA NIA N/A NIA GWP-7 (2) 04/08122 WATER <949 N/A NIA N/A NIA NIA N/A N/A GWP-8 (2) 04108122 WATER <952 NIA NIA NIA NIA NIA NIA N/A GWP-9 (2) 04108/22 WATER <949 NIA NIA NIA N/A NIA NIA NIA GWP-13 (2) 04111122 WATER <949 NIA NIA NIA N/A NIA NIA NIA GWP-14 (2) 04120122 WATER <949 N/A NIA NiA NIA NIA NIA N/A GWP-15R (2) 04/15/22 WATER <949 N/A NIA NIA N/A NIA N/A NIA GWP-16 (2) 04/15/22 WATER <950 N/A N/A NIA NIA N/A N/A NIA GWP-17 (2) 04120122 WATER 1230 NIA N/A NIA N/A N/A N/A NIA GWP-18 (2) 04/04122 WATER 4880 N/A N/A N/A NIA NIA NIA NIA GWP-19 (2) 04108122 WATER 1920 NIA NIA NIA N/A NIA N/A NIA GWP-20 (2) 04108122 WATER <949 N/A NIA NIA NIA NIA NIA NIA GWP-21 (2) 04108/22 WATER <950 N/A N/A N/A N/A NIA N/A NIA GWP-22 (2) 04108122 WATER 1260 NIA NIA N/A NIA NIA NIA N/A PZ-1 04/11/22 WATER 3300 NIA NIA N/A N/A NIA N/A NIA PZ-2 04/11/22 WATER 1400 NIA N/A NIA NIA N/A N/A NIA TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning | |||
(1) pCi/L (2) Vendor Analysis | |||
ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22) | 18 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22) | ||
ATTACHMENT 8 RES | 3 rd Quarter 2022 | ||
Sample Date Sample H-3<1> Gamma -Emitting 1-131<1> Sr-Fe-ss<1> Ni-63I1 > Alpha Media Particulates I1 > 8919011 > TRUl 1> Pu-241 I1 > | |||
GWP-18 07121122 WATER 3937 NIA NIA NIA NIA NIA NIA NIA GWP-3 08110122 WATER 1164 NIA NIA NIA NIA NIA NIA NIA PZ-3 08110122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-4 08110122 WATER 1095 NIA NIA NIA NIA NIA NIA NIA GWP-6 08110122 WATER 1285 NIA NIA NIA NIA NIA NIA NIA GWP-17 08112122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-15R 08112122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-18 08112122 WATER 3657 NIA NIA NIA NIA NIA NIA NIA GWP-19 08110122 WATER 1873 NIA NIA NIA NIA NIA NIA NIA GWP-20 08110122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-18 09115122 WATER 4042 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 08124122 WATER <1495 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA Drains NIA | |||
U-1 Mat Sump East 09107122 WATER 1330 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09107122 WATER <1150 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 09107122 WATER 1318 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09107122 WATER 2838 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09107122 WATER 1277 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09107122 WATER 2931 NIA NIA NIA NIA NIA NIA NIA | |||
(1} pCi/L | |||
19 ATTACHMENT 8 RES UL TS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22) | |||
4th Quarter 2022 Sample Date Sample H-3(11 Gamma -Emitting 1-131(1 l TRU 111 1) Sr-89/90111 Fe-55' 11 Ni-63111 Alpha Pu-2411 11 Media Particulates1 GWP-18 10/06/22 WATER 3638 NIA N/A NIA N/A N/A NIA NIA PZ-3 10110/22 WATER 921 NIA NIA NIA NIA NIA N/A NIA GWP-3 10110/22 WATER 1350 N/A NIA NIA NIA N/A N/A NIA GWP-4 10110122 WATER 1548 NIA NIA NIA NIA NIA NIA NIA GWP-6 10/10122 WATER 1261 NIA N/A N/A N/A NIA NIA N/A GWP-15R 10/09122 WATER 1352 NIA NIA NIA NIA N/A NIA N/A GWP-17 10/09122 WATER 1097 N/A NIA NIA NIA NIA NIA NIA GWP-19 10110122 WATER 1329 NIA NIA NIA NIA NIA NIA N/A GWP-20 10110122 WATER <854 N/A NIA N/A NIA NIA NIA NIA GWP-18 11/04122 WATER 4762 NIA NIA NIA NIA NIA NIA NIA GWP-18 12/02122 WATER 4979 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 11121122 WATER <1270 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11121122 WATER <1280 NIA NIA N/A NIA NIA N/A NIA U-2 Intake Storm Drains 11/21122 WATER <1380 NIA NIA N/A NIA NIA N/A NIA Disch Canal Storm Drains 11/21/22 WATER <1230 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 10105/22 WATER 1636 NIA NIA NIA NIA NIA N/A NIA U-1 Mat Sump South 10105/22 WATER 2726 NIA NIA NIA NIA N/A NIA N/A U-2 Mat Sump Inside 10/05122 WATER 2552 NIA NIA NIA N/A NIA NIA NIA U-2 Mat Sump Outside 10/05122 WATER 2397 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 10/05122 WATER 1081 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 10105122 WATER 2900 NIA NIA NIA N/A N/A NIA NIA U-1 Mat Sump East 11/09122 WATER <862 NIA NIA NIA NIA NIA N/A NIA U-1 Mat Sump South 11109122 WATER <893 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 11/09122 WATER <888 NIA N/A NIA NIA NIA NIA NIA U-2 Mat Sump Outside 11/09122 WATER <890 N/A N/A N/A NIA N/A N/A N/A U-1 AB/FB GWMS 11/09/22 WATER <846 N/A N/A N/A NIA N/A N/A N/A U-2 AB/FB GWMS 11109/22 WATER <827 NIA NIA NIA NIA NIA NIA NIA | |||
(1) pCi/L | |||
20 ATTACHMENT 9 CARBON-14 CALCULATIONS (01/22 - 12/22) | |||
Carbon-14, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Due to the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. | Carbon-14, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Due to the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing. | ||
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution ofradionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. | |||
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution ofradionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. Because the dose contribution ofC-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation ofC-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 2. | |||
The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 31.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 26.7 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter. | The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 31.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 26.7 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter. | ||
Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment, a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations. | Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment, a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations. | ||
Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 8.224E-02 mrem from the inhalation pathway, or 5.483E-03% TS of the 1500 mrem/yr dose rate limit and 9.963E-01 mrem from the ingestion pathway or | Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 8.224E-02 mrem from the inhalation pathway, or 5.483E-03% TS of the 1500 mrem/yr dose rate limit and 9.963E-01 mrem from the ingestion pathway or | ||
* 3.32E+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrern/yr per unit. In both cases the critical organ was determined to be the child's bone. | * 3.32E+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrern/yr per unit. In both cases the critical organ was determined to be the child's bone. | ||
Miscellaneous There was one entry on the 2022 Annual Effluent Release Report Log. Item 22-01 was entered to document that annual Meteorological data recovery was less than 90 percent on an annual basis. See Reg Guide 1.23, Revision 1, Page 10, Section 5, paragraph 1. | 21 Miscellaneous There was one entry on the 2022 Annual Effluent Release Report Log. Item 22-01 was entered to document that annual Meteorological data recovery was less than 90 percent on an annual basis. See Reg Guide 1.23, Revision 1, Page 10, Section 5, paragraph 1. | ||
22}} | 22}} | ||
Latest revision as of 16:34, 14 November 2024
| ML23130A147 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/19/2023 |
| From: | Glasco B Dominion Energy Virginia, Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| 23-083 | |
| Download: ML23130A147 (1) | |
Text
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
NORTH ANNA POWER STATION
(JANUARY 01, 2022 TO DECEMBER 31, 2022)
PREPARED BY: B,. J ~/M,,. ~,
Supervisor Radiological Analysis and Instrumentation 0
APPROVED BY:_,£.....l,:.::..:...:..,,__R,c.... ~ (;)=..===--
J:i&.~
Manager Radiological Protection and Chemistry FORWARD
This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 (10CFR50.36a) and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and I0CFR72.44(d)(3).
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
FOR THE
NORTH ANNA POWER STATION
JANUARY 01, 2022 TO DECEMBER 31, 2022
INDEX
Section No. Subject
EXECUTIVE
SUMMARY
................................... 4
2 PURPOSE AND SCOPE..................................... 5
3 DISCUSSION.................................................. 5-6
4 SUPPLEMENTAL INFORMATION....................... 6 Effluent Release Data.............................................. 7 Annual and Quarterly Doses...................................... 8 Revisions to Offsite Dose Calculation Manual (ODCM)........................................ 9 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems..................................................
In operability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation........................................ 11 Unplanned Releases............................................. 12 Lower Limits of Detection (LLD) for Effluent Sample Analysis........................... 13-14 Results of Ground Water Protection Initiative Sample Analysis..................................... 15-20
Carbon-14 Calculations........................................ 21
Miscellaneous Annual Effluent Release Report Log........................ 22 1.0 EXECUTIVE
SUMMARY
The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2022 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2022 and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.
There were no releases from the ISFSI during 2022.
There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also, there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6.
10 CFR 50, Appendix I dose calculations were performed on the 2022 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following:
- a. The total body dose due to liquid effluents was 8.738E-01 mrem, which is 14.563% of the dose limit, and the critical organ dose due to liquid effluents was 8.790E-01 mrem, which is 4.395% of the dose limit.
- b. The air dose due to noble gases was 6. 7 I IE-05 mrad gamma, which is 3.356E-04% of the annual gamma dose limit, and 3.790E-05 mrad beta, which is 9.475E-05% of the annual beta dose limit.
- c. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days including C-14 was l.079E+0 mrem, which is 3.60% of the annual dose limit. The bases ofC-14 calculations are described in Attachment 9.
- d. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days not including C-14 was 7.977E-03 mrem, which is 2.659E-02% of the annual dose limit.
There were no major changes to either the radioactive liquid waste treatment system, or to the gaseous, and solid waste treatment systems during this reporting period.
There was no revision to the Offsite Dose Calculation Manual during this reporting period.
Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas.
4 2.0 PURPOSE AND SCOPE
The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",
Revision 1, June 1974, with data summarized on a quarterly basis for Table 1 and2 and on an annual basis on Table 3. The report submitted before May 1st of each year 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 the previous calendar year. The report also includes a list of unplanned releases during the reporting period in Attachment 6.
As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.
Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6. 7.2.a.4. Information to support the reason( s) for the change( s) and a summary of the 10 CFR 50.59 evaluation are included.
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report.
3.0 DISCUSSION The basis for the calculation of 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, tritium, and all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to 15 00 mrem/yr to the critical organ at or beyond the site boundary.
The basis for the calculation of percent of Technical' Specification for the total body and skin in Table lA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.
The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases ofairbome iodine-13 I, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland.
5 The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, 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 2.0E-4 uCi/ml.
The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child. The critical organ dose calculation was determined to be the child liver. The age group is exposed via the drinking water and fish ingestion pathways.
As shown in Attachment 6, there were no unplanned releases meeting the requirements of 6. 7.2.a.3 of the ODCM.
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 volume and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).
4.0 SUPPLEMENTAL INFORMATION
As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is performed to identify ifnew location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM. There were no new sampling locations added. There were five (5) changes made from the land use census in 2022. The nearest resident location in the ESE sector changed from 1. 70 miles to 1.53 miles. The physical address of the nearest garden location in the ESE sector changed, however, the location remained at 1. 70 miles. The nearest garden location in the SE sector changed from 1.40 miles to 1.90 miles. The nearest resident in the SW sector changed from 1.65 miles to 1.56 miles. Finally, the nearest garden location in the W sector changed from 1.93 miles to 1.96 miles.
Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples were not collected in 2022 because the last of the operating dairies in the sampling area ceased operations at the start ofcalendar year 2018. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and November through December due to seasonal unavailability. All other vegetation samples were obtained.
Attachment 8 contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site.
Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14.
Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values.
6 ATTACHMENT 1 EFFLUENT RELEASE DATA (01/22 - 12/22)
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, except that in accordance with Step 6. 7.2.a. l of the O DCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.
7 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 1 of 2
1 ST 2ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activiation Gases:
- 1. Total Release Curies 1.17E--01 3.18E-02 1.80E+1
- 2. Average Release Rate For Period µCi/sec 1.50E-02 4.04E-03
B. Iodines:
- 1. Total lodine-131 Release Curies N/D N/D 2.80E+1
- 2. Average Release Rate For Period µCi/sec N/D N/D
C. Particulate {T112 > 8 da~s}:
- 1. Total Particulate (T112 > 8 days) Release Curies 2.56E-05 1.32E-06 2.80E+1
- 2. Average Release Rate For Period µCi/sec 3.29E-06 1.68E--07
- 3. Gross Alpha Radioactivity Release Curies N/D N/D
D. Tritium:
- 1. Total Release Curies 2.97E+0O 1.19E+00 3.10E+1
- 2. Average Release Rate For Period µCi/sec 3.82E-01 1.52E--01
E. Carbon-14
- 1. Total Release Curies 1.28E+01 3.47E+00
- 2. Average Release Rate For Period µCi/sec 1.65E+00 4.41E 0 01
F. Percentage Of Technical Specification Limits
- 1. Total Body Dose Rate % 2.56E--06 4.24E-05
- 2. Skin Dose Rate % 9.87E-07 1.03E-05
- 3. Critical Organ Dose Rate (with C-14) % 8.11E-03 6.41E-03 Critical Organ Dose Rate (without C-14) % 2.55E-04 6.75E-05 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 2 of 2
3RD 4TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activiation Gases:
- 1. Total Release Curies 8.22E-02 1.28E-02 1.80E+1
- 2. Average Release Rate For Period µCi/sec 1.03E-02 1.61E-03
- 8. Iodines:
- 1. Total lodine-131 Release Curies N/D N/D 2.80E+1.,.,.. -
- 2. Average Release Rate For Period µCi/sec N/D N/D..
C. Particulate {T1I2 > 8 dall'.s}:
- 1. Total Particulate (T112 > 8 days) Release Curies 1.10E-05 0.00E+00 2.80E+1
- 2. Averaoe Release Rate For Period µCi/sec 1.38E-06 0.00E+00
- 3. Gross Alpha Radioactivity Release Curies N/D N/D
D. Tritium:
- 1. Total Release Curies 1.25E+01 3.17E+00
- 3.10E+1 '
- 2. Average Release Rate For Period µCi/sec 1.58E+00 3.99E-01
F. Carbon-14
- 1. Total Release Curies 8.98E+00 1.39E+00
- 2. Averaae Release Rate For Period µCi/sec 1.13E+00 1.75E-01
F. Percentage Of Technical Specification Limits
- 1. Total Body Dose Rate % 5.16E-06 6.12E-07
- 2. Skin Dose Rate % 1.54E-06 1.65E-07
- 3. Critical Organ Dose Rate (with C-14) % 6.95E-03 5.12E-04 Critical Organ Dose Rate {without C-14) % 1.06E-03 2.70E-04 TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:
Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon-131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 9.62E-02 3.91 E-03 Xenon -133m Ci N/D N/D 5.39E-04 N/D Xenon -135 Ci N/D N/D 7.83E-03 4.82E-05 Xenon -135m Ci N/D N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon -41 Ci N/D 6.34E-03 N/D 2.35E-03
Total For Period Ci N/D 6.34E-03 1.05E-01 6.31 E-03
Iodine -130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine -135 Ci N/D N/D N/D N/D Br-82 Ci 1.13E-07 1.84E-07 Total For Period Ci 1.13E-07 1.84E-07 N/D N/D
Particulates:
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium -136 Ci N/D N/D N/D N/D Cesium -137 Ci N/D N/D N/D N/D TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES. FOR {01/22 - 12/22)
Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)
As-76 Ci 2.16E-07 8.67E-07 N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Ag-110m Ci N/D 7.66E-09 N/D N/D
Total for Period (T1/2 > 8 days) Ci N/D 7.66E-09 N/D N/D Total for Period (T1/2 < 8 days) Ci 2.16E-07 8.67E-07 N/D N/D
Total For Period Ci 2.16E-07 8.75E-07 N/D N/D
GROSS ALPHA: Ci N/D N/D N/D N/D
TRITIUM: Ci 1.53E-01 5.01E-01 4.94E-03 5.57E-04
CARBON-14 Ci N/D 6.93E-01 1.15E+01 6.89E-01 TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:
Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon - 133 Ci 3.48E-02 N/D 2.11 E-02 1.08E-02 Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D 5.77E-04 4.25E-05..
Xenon -135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon-41 Ci 1.07E-02 N/D 1.11 E-03 1.92E-03 Total For Period Ci 4.55E-02 N/D 2.28E-02 1.28E-02
Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Bromine-82 Ci 5.52E-08 N/D N/D N/D
Total For Period Ci 5.52E-08 N/D N/D N/D
Particulates:
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver-11 Om Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium - 137 Ci N/D N/D N/D N/D TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MOOE GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)
Arsenic-76 Ci 1.10E-07 N/D N/D N/D Cerium -141 Ci NID NID N/D N/O Cerium 144 Ci N/O N/D N/D NID
Total for Period (T1/2 > 8 days) Ci N/O N/D N/D.. NID Total for Period (T1/2 < 8 days) Ci 1.10E-07 N/D N/O N/O
Total For Period Ci 1.10E-07 N/D N/D N/O
GROSS ALPHA: Ci N/O N/D NID NID
TRITIUM: Ci 5.48E-01 1.25E-01 3.47E-03 1.34E-03
CARBON-14 Ci 4.97E+00 N/D 2.49E+00 1.39E+00 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:
Krypton 85 Ci N/0 N/D N/D N/D Krypton 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D.
Xenon 133 Ci N/D N/D 1.13E-02 N/D Xenon 133m Ci N/D N/D 8.85E-05 N/D Xenon 135 Ci N/D N/D 1.02E-03 N/D Xenon -135m Ci N/D N/D N/0 NID Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon - 41 Ci N/D N/D 3.31E-06 1.91 E-02 Total For Period Ci N/D N/D 1.24E-02 1.91 E-02
Iodine -130 Ci N/0 N/D N/D N/D Iodine - 131 Ci N/0 N/D N/D N/D Iodine 132 Ci N/D N/D N/D N/D Iodine 133 Ci N/0 N/D N/D N/D Iodine - 134 Ci N/D N/0 N/0 N/D Iodine 135 Ci N/D N/D N/D N/D
Total For Period Ci N/D N/D N/0 N/D
Particulates:
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci 9.81E-06 N/D N/D N/D Iron 59 Ci N/D N/D N/D N/D Cobalt-60 Ci 1.03E-05 1.31E-06 N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium 134 Ci N/D N/D N/D N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22
- 12/22)
Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)
Cesium-137 Ci 1.97E-06 N/D N/D N/D Arsenic-76 ( T1/2 < 8 days J Ci N/D 4.73E-05 N/D N/D Rubidium-88 Ci N/D N/D N/D N/D.
Cerium 144 Ci N/D N/D N/D N/D Niobium-95 Ci 3.55E-06 N/D N/O N/O Zirconium-95 Ci N/O N/D N/D N/D Tellurium-131m (T1/2 < 8 days) Ci N/D N/D N/D N/D Yttrium-91m (T1/2 < 8 days) Ci N/D N/D N/D N/D Chromium-51 Ci N/O N/D N/D N/D Total for Period (T1/2 > 8 days) Ci 2.56E-05 1.31E-06 N/D N/O Total for Period (T1/2 < 8 days) Ci N/D 4.73E-05 N/D N/O
Total For Period Ci 2.56E-05 4.86E-05 N/D N/O
GROSS ALPHA: Ci N/D N/D N/D N/D
TRITIUM: Ci N/D N/D 2.81E+00 6.93E-01
CARBON-14 Ci N/O N/O 1.35E+00 2.09E+00
TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:
Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D NID 3.37E-06 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon 133 Ci N/D N/D 1.25E-02 N/0 Xenon -133m Ci N/D N/D 2.90E-04 N/D Xenon - 135 Ci N/D N/D 1.09E-03 N/D Xenon -135m Ci N/D N/D N/D N/D Xenon-137 Ci N/D N/D N/D N/D
. Xenon -138 Ci N/D N/D N/D N/D
!Argon - 41 Ci N/D N/D 7.15E-05 N/D Total For Period Ci N/D N/D 1.39E-02 N/D
Iodine - 130 Ci N/D N/D N/D N/D.
Iodine 131 Ci NID N/D NID N/D..
Iodine 132 Ci N/D N/D N!D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine 134 Ci N/D N/D NID N/D Iodine -135 Ci N/D N/D N/D N/D
Total For Period Ci N/D N/D N/D N/D
Particulates:
Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/0 Cobalt-60 Ci 1.10E-05 N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/0 Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL
- RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)
Cesium -137 Ci N/D N/D N/D N/D Niobium-95 (T1/2 > 8 days) Ci N/D N/D N/D N/D Ag-110m (T1/2 > 8 days) Ci N/D N/D N/D N/D Other (Specify)
Total for Period (T1/2 > 8 days) Ci 1.10E-05 N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D
Total For Period Ci 1.10E-05 N/D N/D N/D
GROSS ALPHA: Ci N/D N/D N/D N/D
TRITIUM: Ci 1.04E+01 2.53E+00 1.55E+00 5.15E-01
CARBON-14 Ci N/D N/D 1.52E+00 3.91 E-03 TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF Ali.. 'RELEASES FOR (01/22 - 12/22)
Page 1 of 2 1 ST 2 ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activiation Products:
- 1. Total Release (not including tritium, noble gas, and gross alpha). Curies 5.03E-03 3.21 E-03 2.00E+01
- 2. Average diluted concentration during the period. µCi/ml 1.71E-11 4.33E-12
- 3. Percent of applicable limit (T.S.) % 2.39E-05 7.37E-06
B. Tritium:
- 1. Total release activity. Curies 9.37E+02 5.87E+02 2.00E+01
- 2. Average diluted concentration during the period. µCi/ml 3.18E-06 7.92E-07
- 3. Percent of applicable limit (T.S.) % 3.18E-02 7.92E-03
C. Dissolved and Entrained Gases:
- 1. Total release activity. Curies N/D N/D 2.00E+01
- 2. Average diluted concentration during the period. ~tCi/ml N/D N/D
- 3. Percent of applicable limit (T.S.) % N/D N/D
D. Gross Alpha Radioactivity:
- 1. Total release activity. Curies N/D N/D 2.00E+01
E. Volume of waste released: (prior to dilution). Liters 9.90E+07 8.85E+07 3.00E+00
F. Total volume of dilution water used during the period. Liters 2.95E+11 7.42E+11 3.00E+00 TABLE. 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE.EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/22 - 12/22)
Page 2 of2 3 RD 4 TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)
A. Fission and Activiation Products:
- 1. Total Release (not including tritium, noble gas, and gross alpha). Curies 2.81 E-03 2.33E-03 2.00E+01
- 2. Average diluted concentration during the period. µCi/ml 3.77E-12 4.04E-12
- 3. Percent of aoolicable limit (T.S.) % 7.01E-06 5.41E-06 B. Tritium:
- 1. Total release activity. Curies 6.95E+02 2.56E+02 2.00E+01
- 2. Average diluted concentration during the period. µCi/ml 9.32E-07 4.43E-07
- 3. Percent of applicable limit (T.S.) % 9.32E-03 4.43E-03 C. Dissolved and Entrained Gases:
- 1. Total release activity. Curies N/D N/D 2.00E+01
- 2. Average diluted concentration during the period. µCi/ml N/D N/D
- 3. Percent of applicable limit (T.S.) % N/D N/D
D. Gross Alpha Radioactivity:
- 1. Total release activity. Curies N/D N/D 2.00E+01
E. Volume of waste released: {prior to dilution). Liters 8.20E+07 1.02E+08 3.00E+O0
F. Total volume of dilution water used durin~ the period. Liters 7.46E+11 5.78E+11 3.00E+00 TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCUDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products: ~*-,
Manganese - 54 Ci 1.38E-04 N/D N/A N/A.
Iron - 59 Ci N/D N/D N/A N/&,_,
Cobalt - 58 Ci 3.26E-03 1.66E-03 N/A N/A Cobalt - 60 Ci 1.59E-03 8.99E-04 N/A NIA Strontium - 89 Ci N/D N/D NIA NIA Strontium - 90 Ci N/D N/D NIA N/A Tellurium-123m Ci N/D 1.47E-04 N/A NIA Tellurium-132 Ci 2.47E-05 NID N/A NIA Chromium-51 Ci N/D NID NIA NIA Iodine 131 Ci N/D NID N/A N/A Iodine - 133 Ci N/D N/D N/A NIA Cesium -134 Ci N/D N/D NIA N/A..
Cesium 137 Ci N/D 1.36E-04 N/A NIA Zirconium - 95 Ci N/D N/D NIA NIA Cerium - 141 Ci N/D N/D NIA N/A Silver-110m Ci 2.15E-05 NID N/A NIA Tellurium-125m Ci N/D 7.02E-05 N/A N/A Niickel - 63 (T1/2 > 8 days) Ci N/D N/D NIA N/A Antimony-125 Ci NID 3.04E-04 N/A NIA Total for Period Ci 5.03E-03 3.21E-03 N/A N/A
TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:
Xenon -133 Ci NID NID NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA Xenon -135m Ci NID NID NIA N/A Other (Specify) Ci NID N/D N/A N/A Krypton-88 ( T1/2 < 8 days) Ci N/D N/D N/A N/A Krypton-85 (T1/2 > 8 days) Ci N/D N/D N/A N/A
Total for Period Ci N/D N/D N/A N/A
Tritium Ci 9.37E+02 5.87E+02 N/A N/A
Gross Alpha Ci N/D N/D N/A - NIA TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:
Manganese - 54 Ci N/D N/D N/A N/A Iron 59 Ci N/D N/D N/A N/A Cobalt-58 Ci 1.69E-03 1.52E-03 N/A N/A Cobalt-60 Ci 9.63E-04 6.60E-04 N/A NIA
Strontium - 89 Ci N/D N/D NIA N/A Strontium - 90 Ci N/D N/D NIA N/A Niobium 95 Ci N/D N/D N/A N/A..
Zirconium 95 Ci N/D N/D N/A N/A Silver - 11 Om Ci N/D N/D N/A N/A Iodine -131 Ci N/D N/D N/A N/A lodine-133 Ci N/D N/0 N/A N/A Cesium -134 Ci N/D N/D NIA NIA Cesium-137 Ci 1.13E-04 1.12E-05 N/A N/A Tellurium-123m Ci 4.82E-05 N/0 N/A N/A Cerium - 141 Ci N/0 N/0 N/A N/A Chromium-51 Ci N/0 N/D NIA N/A Nickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A NIA
-~.,
Ruthenium-105 {T1/2 < 8 days) Ci N/D N/0 NIA NIA Antimony-125 (T1/2 > 8 days) Ci N/D 1.12E-04 N/A N/A Antimony-122 (T1/2 > 8 days) Ci N/D N/D NIA NIA Tellurium-125m (T1/2 > 8 days) Ci N/D 2.58E-05 NIA NIA
Total for Period Ci 2.81E-03 2.33E-03 NIA NIA TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/22 - 12/22)
Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:
Xenon -133 Ci NID NID NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA *-
Xenon -135m Ci NID N/D NIA NIA Other (Specify) -
Argon - 41 (T112 < 8 days) Ci NID NID NIA NIA **-
Krypton - 85 (T112 > 8 days) Ci NID NID NIA NIA
Total for Period Ci NID NID NIA NIA
Tritium Ci 6.95E+02 2.56E+02 NIA NIA
Gross Alpha Ci NID NID NIA NIA TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-22 THROUGH 12-31-22 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total
- 1. Type of Waste Unit Period Percent Error (%)
- a. Spent resins, sludges, filters sludge, m3 1.17E+01
- 2.50E+01 evaporator bottoms, etc., Ci 1.53E+02 2.50E+01
- b. Dry compressible waste, contaminated m3 2.05E+02 ** 2.50E+01 equipment, etc., Ci 1.78E-01 2.50E+01 C. Irradiated components, control rods, m3 0.00E+00... 2.50E+01 etc., Ci 0.0OE+0O 2.50E+01
- d. Other (describe)
Used oil/Blast media/Sewage/Gravel m3 4.20E-01 **** 2.50E+01 Dessicant/Soil/Construction debris Ci 3.78E-03 2.50E+01 Animal Carcasses
- 2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
- a. Co-60 5.74E+01 8.75E+01 2.50E+01 Ni-63 2.42E+01 3.68E+01 2.50E+01 Fe-55 6.23E+00 9.50E+00 2.50E+01 Mn-54 3.70E+00 5.65E+00 2.50E+01 Co-58 3.35E+00 5.10E+00 2.50E+01 Sb-125 1.54E+00 2.35E+00 2.50E+01 Cs-137 1.07E+00 1.64E+00 2.50E+01 Zn-65 6.60E-01 1.01E+00 2.50E+01 Be-7 6.30E-01 9.61 E-01 2.50E+01 Aa-110m 2.36E-01 3.60E-01 2.50E+01 Ni-59 2.35E-01 3.59E-01 2.50E+01 H-3 1.67E-01 2.54E-01 2.50E+01 Nb-95 1.65E-01 2.52E-01 2.50E+01
- b. Co-60 4.72E+01 8.45E-02 2.50E+01 Co-58 1.66E+01 2.96E-02 2.50E+01 Cr-51 8.20E+00 1.46E-02 2.50E+01 Nb-95 6.93E+00 1.24E-02 2.50E+01 Fe-55 6.49E+00 1.16E-02 2.50E+01 Ni-63 3.93E+00 7.01E-03 2.50E+01 Zr-95 3.88E+00 6.93E-03 2.50E+01 Cs-137 2.94E+00 5.25E-03 2.50E+01 Sb-125 1.62E+00 2.89E-03 2.50E+01 Mn-54 1.31E+00 2.33E-03 2.50E+01 Aa-110m 2.12E-01 3.78E-04 2.50E+01 Fe-59 1.26E-01 2.25E-04 2.50E+01 H-3 1.23E-01 2.19E-04 2.50E+01 Te-125m 9.84E-02 1.76E-04 2.50E+01
- c. NONE
- d. Co-60 5.11 E+01 1.93E-03 2.50E+01 Ni-63 2.22E+01 8.40E-04 2.50E+01 Cs-137 1.61 E+01 6.10E-04 2.50E+01 H-3 8.70E+00 3.29E-04 2.50E+01 Sb-125 8.89E-01 3.36E-05 2.50E+01 Cs-134 1.83E-01 7.66E-06 2.50E+01 Mn-54 1.17E-01 6.91E-06 2.50E+01 TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01-01-22 THROUGH 12-31-22 Page 2 of 2
- 3. Solid Waste Disposition
Number of Shipments Mode of Transportation Destination
6 Truck Oak Ridge, TN 1 Truck Andrews, TX
Note: Some of the 7 solid waste shipments contained multiple waste types and are therefore listed in more than one category below.
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination
0 N/A N/A
- (2) shipments containing resins were shipped to a licensed waste processor for final dewatering and disposal.
(1) shipment containing resins was shipped to a licensed waste facility for disposal.
(1) shipment containing mechanical filters was shipped to a licensed waste processor for processing.
(1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal.
- (4) shipments containing dry cornpactible waste were shipped to a licensed waste processor for processing.
(1) shipment containing low activity calibration standards was shipped to a licensed waste facility for disposal.
- None
- (1) shipment containing waste oil was shipped to a licensed waste processor for processing.
(1) shipment containing sludge was shipped to a licensed waste processor for processing.
ATTACHMENT 2 ANNUAL AND OUARTERL Y DOSES (01/22 - 12/22)
An assessment ofradiation 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 will be made as required by OD.CM Section 6.7.2.
1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 3.305E-1 2.076E-1 2.454E-1 9.034E-2 8.738E-1 Critical Organ Dose (mrem) 3.306E-1 2.103E-1 2.475E-1 9.058E-2 8.790E-1
1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 3.639E-6 5.552E-5 7.120E-6 8.310E-7 6.711E-5 Noble Gas Beta Dose (mrad) 8.879E-6 l.972E-5 8.616E-6 6.846E-7 3.790E-5 Critical Organ (Child bone)
Dose for 1-131, 1-133, H-3, Particulates with T1/2>8 days (including C-14) (mrem) 5.420E-1 2.970E-1 l.933E-l 4.624E-2 l.079E+0
Critical Organ (Child thyroid)
Dose for 1-131, 1-133, H-3, Particulates with T1/2> 8 days (excluding C-14) (mrem) 1.222E-3 3.527E-4 5.109E-3 1.293E-3. 7.977E-3
8 ATTACHMENT 3
REVISIONS TO OFFSITE DOSE CALCULATION MANUAL
(ODCM)
(01/22 - 12/22)
As required by Technical Specification 5.5.1.c, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.
There was no revision to the ODCM during this reporting period.
9 ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS (01122 - 12/22)
As required by the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable.
There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2022.
10 ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS
EFFLUENT MONITORING INSTRUMENTATION
(01122 ~ 12/22)
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2. b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment.
No liquid and/or gaseous effluent monitoring instrumentation was out of service for> 30 days during the reporting period.
11 ATTACHMENT 6
UNPLANNED RELEASES
(01/22 - 12/22)
As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, ofradioactive material in
gaseous and liquid effluents occurring during the reporting period, is made in this attachment.
There were no unplanned releases during calendar year 2022 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to
unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground
Water Protection Initiative, NEI 07-07. The current groundwater monitoring network provides adequate assurance that radiological
contamination of groundwater will be detected in a timely manner. (i.e., prior to migration offsite ). Both the historic and current
tritium levels do not pose a risk to human health and the environment. The current tritium levels are well below the drinking
water standard of 20,000 pCi/L. Furthermore, the impacted groundwater is controlled and discharged via a monitored discharge.
12 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22)
Gaseous Effluents:
Required L.L.D. Typical L.L.D.
Radioisotope µCi/mL µCi/mL
Krypton-87 1.00E-4 2.50E-8 7.50E-8
Krypton-88 1.00E-4 4.00E-8 2.50E-7
Xenon -133 1.00E-4 2.00E-8 1.00E-7
Xenon-133m 1.00E-4 1.00E-7 4.00E-7
Xenon -135 1.00E-4 1.00E-8 5.00E-8
Xenon-135m 1.00E-4 5.00E-8 2.00E-7
Xenon -138 1.00E-4 9.00E-8 4.00E-7
Iodine - 131 1.00E-12 3.00E-14 1.00E-13
Iodine -133 1.00E-10 1.00E-14 7.00E-13
Manganese - 54 1.00E-11 2.00E-14 6.00E-14
Cobalt-58 1.00E-11 2.00E-14 6.00E-14
Iron - 59 1.00E-11 6.00E-14 1.00E-13
Cobalt-60 1.00E-11 3.00E-14 1.00E-13
Zinc-65 1.00E-11 6.00E-14 2.00E-13
Strontium - 89 1.00E-11 3.00E-14 8.00E-12
Strontium - 90 1.00E-11 3.00E-15 9.00E-12
Molybdenum - 99 1.00E-11 2.00E-14 1.00E-13
Cesium -134 1.00E-11 2.00E-14 8.00E-14
Cesium -137 1.00E-11 3.00E-14 8.00E-14
Cerium - 141 1.00E-11 3.00E-14 1.00E-13
Cerium -144 1.00E-11 1.50E-13 4.00E-13
Gross Alpha 1.00E-11 7.00E-15 2.00E-14
Tritium 1.00E-6 4.00E-09 9.00E-09
13 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/22 - 12/22)
Liguid Effluents:
Required L.L.D. Typical L.L.D.
Radioisotope µCi/mL µCi/mL
Krypton-87 1.00E-5 3.00E-8 1.00E-7
Krypton-88 1.00E-5 5.00E-8 5.00E-7
Xenon-133 1.00E-5 3.00E-8 1.00E-7
Xenon-133m 1.00E-5 9.00E-8 3.00E-7
Xenon-135 1.00E-5 1.00E-8 5.00E-8
Xenon-135m 1.00E-5 3.00E-8 2.00E-7
Xenon-138 1.00E-5 1.00E-7 '1.00E-6
Iodine - 131 1.00E-6 1.00E-8 5.00E-8
Manganese - 54 5.00E-7 1.00E-8 5.00E-8
Iron-55 1.00E-6 3.00E-7 8.00E-7
Cobalt-58 5.00E-7 1.50E-8 6.00E-8
Iron-59 5.00E-7 3.00E-8 7.00E-8
Cobalt-60 5.00E-7 1.00E-8 5.50E-8
Zinc - 65 5.00E-7 3.00E-8 6.00E-8
Strontium - 89 5.00E-8 1.00E-8 4.00E-8
Strontium - 90 5.00E-8 5.00E-9 9.00E-9
Molybdenum - 99 5.00E-7 2.00E-8 6.00E-8
Cesium -134 5.00E-7 1.50E-8 5.00E-8
Cesium -137 5.00E-7 1.50E-8 6.00E-8
Cerium -141 5.00E-7 3.00E-8 9.00E-8
Cerium-144 5.00E-7 1.00E-7 5.00E-7
Gross Alpha 1.00E-7 2.00E-8 7.00E-8
Tritium 1.00E-5 2.00E-6 5.00E-6
14 ATTACHMENT 8
RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS
{01/22 - 12/22)
The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water.
It complies with the requirements ofNEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials.
Samples are obtained from monitoring wells installed both inside and outside the restricted area on a quarterly basis and analyzed onsite.
Annually, during the second quarter, these samples are analyzed by an Independent Lab. Samples are also obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Samples may be obtained more frequently than normal, if required and may be analyzed on-site or by an Independent Lab. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments 11 and 12 to VPAP-2103N.
On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2022. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "NI A" indicates a sample analysis was not performed for that sample. A"< value" indicates an analysis was performed but the result was less than the Minimum Detectable Activity, MDA, and the required LLD. If a result is greater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, due to the analysis software or interferences from naturally occurring radioactivity. In these cases, instead of the value, an explanatory footnote is provided.
15 ATTACHMENT 8 RES UL TS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22)
1st Quarter 2022 Sample Date Sample H.311> Gamma -Emitting 1-13111> Sr-89/90IMedia ParticulatesI1 > TRU 11 > 1> Fe-55I1 > Ni-63I1 > Alpha Pu-241I 1>
GWP-18 01126122 WATER 3255 N/A N/A NIA NIA NIA NIA NIA PZ-1 02/13122 Insufficient volume PZ-2 02113122 Insufficient volume PZ-3 02/13/22 WATER <1133 NIA N/A NIA NIA NIA NIA N/A GWP-3 02113122 WATER <1133 NIA N/A NIA NIA NIA NIA NIA GWP-4 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-15R 03102122 WATER <1144 NIA NIA NIA NIA NIA NIA N/A GWP-17 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-18 02123122 WATER 4933 NIA NIA NIA NIA NIA NIA NIA GWP-19 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-20 02113122 WATER <1133 NIA NIA NIA NIA NIA NIA NIA GWP-6 02123122 WATER <1116 NIA NIA NIA NIA NIA NIA NIA GWP-18 03119122 WATER 4620 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 02123122 WATER <1385 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02123122 WATER <1142 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02123122 WATER <1142 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 03102122 WATER <1382 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 02123122 WATER 1418 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 02123122 WATER 1582 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 02123122 WATER 3329 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 02123122 WATER 2971 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 02123122 WATER 2456 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 02123122 WATER 3197 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 03119122 WATER 1364 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 03119122 WATER <1227 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 03119122 WATER 1960 NIA NIA NIA NIA NIA NIA NIA
(1) pCi/L
16 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22)
2nd Quarter 2022
Sample Date Sample H.3111 Gamma -Emitting 1-13111Media Particulatesl1l TRUl1l ) Sr-89/90 111 Fe-5511 l Ni-63111 Alpha Pu-241 111
GWP-18 04/04122 WATER 3966 NIA N/A NIA NIA NIA NIA NIA PZ-1 04111122 WATER <1287 NIA N/A NIA N/A NIA NIA NIA PZ-2 04/11122 WATER <1164 NIA N/A NIA N/A NIA NIA N/A PZ-3 04/06122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-3 04105122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-4 04106122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-5A 04108122 WATER <1164 NIA NIA N/A NIA NIA NIA NIA GWP-6 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-7 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-8 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-9 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-13 04111122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-16 04115122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA GWP-19 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-20 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-21 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-22 04108122 WATER <1164 NIA NIA NIA NIA NIA NIA NIA GWP-23 04111122 Insufficient volume GWP-14 04120122 WATER <1118 NIA NIA NIA NIA NIA NIA NIA GWP-15R 04115122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA GWP-17 04120122 WATER <1118 NIA NIA NIA NIA NIA N/A NIA GWP-18 05112122 WATER 3699 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05119122 WATER <1663 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 06102122 WATER <1633 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 06106122 WATER 1990 NIA N/A NIA NIA NIA NIA NIA U-1 Mat Sump South 06106122 WATER 1410 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 06106122 WATER 1869 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 06106122 WATER 2026 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 06106122 WATER 2005 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 06106122 WATER 2724 NIA NIA NIA NIA NIA NIA NIA GWP-18 06120122 WATER 3616 N/A NIA NIA NIA NIA NIA NIA BTW-1 04112122 WATER <1126 N/A NIA NIA NIA NIA NIA NIA BTW-2 04114122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA BTW-4 04114122 WATER <1126 NIA NIA NIA NIA NIA N/A NIA TTW-2 04113122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA TTW-3 04112122 WATER <1126 NIA NIA NIA NIA N/A NIA NIA TTW-5 04114122 WATER <1126 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 04112122 WATER <948 NIA NIA NIA NIA NIA NIA NIA BTW-2 (2) 04114122 WATER <949 NIA NIA NIA NIA NIA NIA NIA BTW-4 (2) 04114122 WATER <950 NIA NIA NIA NIA NIA NIA NIA TTW-2 (2) 04113122 WATER <949 NIA NIA NIA NIA NIA NIA NIA
17 TTW-3 (2) 04112122 WATER <949 NIA NIA NIA N/A NIA NIA NIA TTW-5 (2) 04/14/22 WATER <949 N/A N/A NIA NIA NIA NIA NIA PZ-3 (2) 04106/22 WATER 1100 NIA NIA NIA N/A N/A NIA NIA GWP-3 (2) 04/05/22 WATER <950 N/A N/A N/A NIA N/A NIA NIA GWP-4 (2) 04106/22 WATER <950 NIA N/A NIA NIA NIA NIA NIA GWP-5A(2) 04/08/22 WATER <949 NIA NIA N/A N/A NIA NIA N/A GWP-6 (2) 04/08/22 WATER <951 NIA N/A N/A NIA NIA N/A NIA GWP-7 (2) 04/08122 WATER <949 N/A NIA N/A NIA NIA N/A N/A GWP-8 (2) 04108122 WATER <952 NIA NIA NIA NIA NIA NIA N/A GWP-9 (2) 04108/22 WATER <949 NIA NIA NIA N/A NIA NIA NIA GWP-13 (2) 04111122 WATER <949 NIA NIA NIA N/A NIA NIA NIA GWP-14 (2) 04120122 WATER <949 N/A NIA NiA NIA NIA NIA N/A GWP-15R (2) 04/15/22 WATER <949 N/A NIA NIA N/A NIA N/A NIA GWP-16 (2) 04/15/22 WATER <950 N/A N/A NIA NIA N/A N/A NIA GWP-17 (2) 04120122 WATER 1230 NIA N/A NIA N/A N/A N/A NIA GWP-18 (2) 04/04122 WATER 4880 N/A N/A N/A NIA NIA NIA NIA GWP-19 (2) 04108122 WATER 1920 NIA NIA NIA N/A NIA N/A NIA GWP-20 (2) 04108122 WATER <949 N/A NIA NIA NIA NIA NIA NIA GWP-21 (2) 04108/22 WATER <950 N/A N/A N/A N/A NIA N/A NIA GWP-22 (2) 04108122 WATER 1260 NIA NIA N/A NIA NIA NIA N/A PZ-1 04/11/22 WATER 3300 NIA NIA N/A N/A NIA N/A NIA PZ-2 04/11/22 WATER 1400 NIA N/A NIA NIA N/A N/A NIA TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning
(1) pCi/L (2) Vendor Analysis
18 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22)
3 rd Quarter 2022
Sample Date Sample H-3<1> Gamma -Emitting 1-131<1> Sr-Fe-ss<1> Ni-63I1 > Alpha Media Particulates I1 > 8919011 > TRUl 1> Pu-241 I1 >
GWP-18 07121122 WATER 3937 NIA NIA NIA NIA NIA NIA NIA GWP-3 08110122 WATER 1164 NIA NIA NIA NIA NIA NIA NIA PZ-3 08110122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-4 08110122 WATER 1095 NIA NIA NIA NIA NIA NIA NIA GWP-6 08110122 WATER 1285 NIA NIA NIA NIA NIA NIA NIA GWP-17 08112122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-15R 08112122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-18 08112122 WATER 3657 NIA NIA NIA NIA NIA NIA NIA GWP-19 08110122 WATER 1873 NIA NIA NIA NIA NIA NIA NIA GWP-20 08110122 WATER <1086 NIA NIA NIA NIA NIA NIA NIA GWP-18 09115122 WATER 4042 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 08124122 WATER <1495 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm 08129122 WATER <1508 NIA NIA NIA NIA NIA NIA Drains NIA
U-1 Mat Sump East 09107122 WATER 1330 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09107122 WATER <1150 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 09107122 WATER 1318 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09107122 WATER 2838 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09107122 WATER 1277 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09107122 WATER 2931 NIA NIA NIA NIA NIA NIA NIA
(1} pCi/L
19 ATTACHMENT 8 RES UL TS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/22 - 12/22)
4th Quarter 2022 Sample Date Sample H-3(11 Gamma -Emitting 1-131(1 l TRU 111 1) Sr-89/90111 Fe-55' 11 Ni-63111 Alpha Pu-2411 11 Media Particulates1 GWP-18 10/06/22 WATER 3638 NIA N/A NIA N/A N/A NIA NIA PZ-3 10110/22 WATER 921 NIA NIA NIA NIA NIA N/A NIA GWP-3 10110/22 WATER 1350 N/A NIA NIA NIA N/A N/A NIA GWP-4 10110122 WATER 1548 NIA NIA NIA NIA NIA NIA NIA GWP-6 10/10122 WATER 1261 NIA N/A N/A N/A NIA NIA N/A GWP-15R 10/09122 WATER 1352 NIA NIA NIA NIA N/A NIA N/A GWP-17 10/09122 WATER 1097 N/A NIA NIA NIA NIA NIA NIA GWP-19 10110122 WATER 1329 NIA NIA NIA NIA NIA NIA N/A GWP-20 10110122 WATER <854 N/A NIA N/A NIA NIA NIA NIA GWP-18 11/04122 WATER 4762 NIA NIA NIA NIA NIA NIA NIA GWP-18 12/02122 WATER 4979 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 11121122 WATER <1270 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11121122 WATER <1280 NIA NIA N/A NIA NIA N/A NIA U-2 Intake Storm Drains 11/21122 WATER <1380 NIA NIA N/A NIA NIA N/A NIA Disch Canal Storm Drains 11/21/22 WATER <1230 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 10105/22 WATER 1636 NIA NIA NIA NIA NIA N/A NIA U-1 Mat Sump South 10105/22 WATER 2726 NIA NIA NIA NIA N/A NIA N/A U-2 Mat Sump Inside 10/05122 WATER 2552 NIA NIA NIA N/A NIA NIA NIA U-2 Mat Sump Outside 10/05122 WATER 2397 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 10/05122 WATER 1081 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 10105122 WATER 2900 NIA NIA NIA N/A N/A NIA NIA U-1 Mat Sump East 11/09122 WATER <862 NIA NIA NIA NIA NIA N/A NIA U-1 Mat Sump South 11109122 WATER <893 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 11/09122 WATER <888 NIA N/A NIA NIA NIA NIA NIA U-2 Mat Sump Outside 11/09122 WATER <890 N/A N/A N/A NIA N/A N/A N/A U-1 AB/FB GWMS 11/09/22 WATER <846 N/A N/A N/A NIA N/A N/A N/A U-2 AB/FB GWMS 11109/22 WATER <827 NIA NIA NIA NIA NIA NIA NIA
(1) pCi/L
20 ATTACHMENT 9 CARBON-14 CALCULATIONS (01/22 - 12/22)
Carbon-14, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Due to the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution ofradionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. Because the dose contribution ofC-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation ofC-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 2.
The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 31.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 26.7 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter.
Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment, a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations.
Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 8.224E-02 mrem from the inhalation pathway, or 5.483E-03% TS of the 1500 mrem/yr dose rate limit and 9.963E-01 mrem from the ingestion pathway or
- 3.32E+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrern/yr per unit. In both cases the critical organ was determined to be the child's bone.
21 Miscellaneous There was one entry on the 2022 Annual Effluent Release Report Log. Item 22-01 was entered to document that annual Meteorological data recovery was less than 90 percent on an annual basis. See Reg Guide 1.23, Revision 1, Page 10, Section 5, paragraph 1.
22