ML17145A304: Difference between revisions

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| issue date = 04/27/2017
| issue date = 04/27/2017
| title = Independent Spent Fuel Storage Installation (Isfsi), Submittal of Annual Radioactive Effluent Release Report
| title = Independent Spent Fuel Storage Installation (Isfsi), Submittal of Annual Radioactive Effluent Release Report
| author name = Lane N L
| author name = Lane N
| author affiliation = Virginia Electric & Power Co (VEPCO)
| author affiliation = Virginia Electric & Power Co (VEPCO)
| addressee name =  
| addressee name =  

Revision as of 12:16, 19 June 2019

Independent Spent Fuel Storage Installation (Isfsi), Submittal of Annual Radioactive Effluent Release Report
ML17145A304
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/27/2017
From: Lane N
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
17-147
Download: ML17145A304 (43)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER C OMPANY RICHMOND, VIRG I NIA 23261 Apr i l 27 , 2017 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington , D. C. 20555 Serial No.17-147 NAPS/JHL Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2016 Annual Radioactive Effluent Release Report. This report i s provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Techn ic a l Specification 5.5.2c [10 CFR 72.44(d)(3)]. If you have any questions or require additional information, please contact Mr. Donald R. Tay l or at (540) 894-2100. Very tru l y yours , 0;2 N. Site Vice President Enclosure Commitments made i n this letter: None cc: U. S. Nuclear Regula t ory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta , Georgia 30303-1257 Director , Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U. S. Nuclea r Regulatory Commission Washington , D. C. 20555 NRC Senior Resident Inspector North Anna Power Station ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2016 TO DECEMBER 31, 2016) Barbara J. Thompson Super int endent Health Physics Technica l Services APPROVED BY George R. Simmons Manager Radiological Protection and Chemistry FORWARD This report is submitted in accordance with North Anna Unit 1and2 Technical Specification 5.6.3 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and 10CFR72.44(d)(3).

Section No. 1 2 3 4 Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Miscellaneous ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2016 TO DECEMBER 31, 2016 INDEX Subject EXECUTIVE

SUMMARY

....... '. .......................... . PURPOSE AND SCOPE .................................... . DISCUSSION

................................................. . SUPPLEMENTAL INFORMATION

...................... . Effluent Release Data ............................................. . Annual and Quarterly Doses ..................................... . Revisions to Offsite Dose Calculation Manual (ODCM) ....................................... . Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ................................................. . Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation

....................................... . Unplanned Releases ............................................ . Lower Limits of Detection (LLD) for Effluent Sample Analysis .......................... . Results of Ground Water Protection Initiative Sample Analysis .............

...................... . Carbon-14 Calculations

....................................... . Annual Effluent Release Report Log ........................ . 4 5 5-6 6-7 8 9 10 11 12 13 14-15 16-23 24 24 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 2016 calendar year. This document summarizes the quantities ofradioactive 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, 2016, and 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 2016. There were no tinplanned 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 2016 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 7.67E-1 mrem, which is 12.82% of the dose limit and the critical organ dose due to liquid effluents was 7.67E-1 mrem, which is 3.84% of the dose limit. b. The air dose due to noble gases was l.70E-4 mrad gamma, which is 8.50E-4% of the annual gamma dose limit, and l.07E-4 mrad beta, which is 2.68E-4% of the annual beta dose limit. c. The critical organ dose for I-131, I-133, H-3, and particulates with half-lives greaterthan8 days includingC-14 was 1.18 rniem, which is 3.93% of the annual dose limit. The bases ofC-14 calculations are described in Attachment
9. d. The critical organ dose for I-131, I-133, H-3, *and particulates with half-lives greater than 8 days not including C-14 was 3.09E-2 mrem, which is l.03E-l % 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 revisions 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 j )I 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 1and2 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 forthe 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 IA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-131 and iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary.

The critical organ is the child's bone ifC-14 is included and child's thyroid ifC-14 is not included both via the inhalation pathway. The basis for the calculation of percent of Technical Specification for the total body and skin in Table IA of Attachment 1 is the ODCM, section 6.3.1, which requires thatthe 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 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 umestricted 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. Percent of Technical Specification calculations are based on the total gaseous or liquid effluents released for that respective quarter. 5 The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at site boundary.

The maximum exposed member of the public from the releases of airborne iodine-131 and iodine-133, tritium and all radionuclides in 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 and 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 maximum exposed member of the public for calculation of total body from radioactive materials in liquid effluents released to unrestricted areas is defined as a child, and also as a child for the calculation of critical organ dose, which was determined to be Gastrointestinal-Lower Large Intestine ( GI-LLI). The age group is exposed via the drinking water and fish ingestion pathways.

As shown in Attachment 6, there was no unplanned releases meeting the requirements of6.7.2.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 analys_is

). 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 (NID) 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 seven (7) changes made to the land use census in 2016. The nearest garden location in the N sector changed from 1.76-miles to 1.56 miles. The nearest garden location in the NW sector changed from 1.96 miles to 1.28 miles. The nearest garden location in the NNW sector changed from 1.22 miles to 2.54 miles. Physical addresses for the nearest garden locations in the ESE and W sectors changed but distances from station were unchanged.

Also, the location of the nearest meat animal in the ENE sector changed from 2.65 miles to 2.49 miles. There are no longer meat animals in the W sector. Meat animals previously in W sector at 4.40 miles distance were no longer present and no other meat animals were found in the W sector within a five mile radius of the station. Finally, the physical address of the nearest resident in the ENE sector changed but the distance from the station was unchanged.

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. All milk samples were collected as required.

Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and 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 6 J 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. 7 J ATTACHMENT 1 EFFLUENT RELEASE DATA (01/16 -12/16) This attachment includes a summary of the quantities ofradioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, AppendixB, except that in accordance with Step 6.7.2.a.l of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis. 8 A. B. c. D. TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) 1 ST 2ND UNITS QUARTER QUARTER Fission and Activiation Gases 1. Total Release Curies 8.11 E-01 3.43E-02 2. Average Release Rate For Period µCi/sec 1.03E-01 4.37E-03 Iodines: 1. Total lodine-131 Release Curies 4.09E-05 O.OOE+OO 2. Average Release Rate For Period µCi/sec 5.20E-06 O.OOE+OO Particulate (T112 > 8 days): 1. Total Particulate (T112 > 8 days) Release Curies 1.36E-05 O.OOE-+:00

2. AveraQe Release Rate For Period uCi/sec 1.73E-06 O.OOE+OO 3. Gross Alpha Radioactivity Release Curies 1A4E-07 8.65E-08 Tritium: 1. Total Release Curies 5.19E+OO 6.11 E+OO 2. Average Release Rate For Period µCi/sec 6.59E-01 7.77E-01 E. Carbon-14
  • 1. Total Release Curies 2.48E+01 1.05E+OO 2. Average Release Rate For Period µCi/sec 3.15E+OO 1.34E-01 F. Percentage Of Technical SE!ecification Limits 1. Total Body Dose Rate % 6.41E-05 1.12E-07 2. Skin Dose Rate % 3.02E-05 1.23E-06 3. Critical Organ Dose Rate (with C-14) % 1.66E-02 9.24E-04 Critical Organ Dose Rate (without C-14) % 4.90E-04 5.39E-04 ... Page 1 of 2 ESTIMATED TOTAL PERCENT ERROR (%) 1.80E+1 2.80E+1 2.80E+1 3.10E+1 A. B. c. D. TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) 3RD 4TH UNITS QUARTER QUARTER Fission and Activiation Gases \ J 1. Total Release Curies 6.77E-02 2.28E-02 2. Average Release Rate For Period µCi/sec 8.52E-03 2.87E-03 Iodines: 1. Total lodine-131 Release Curies O.OOE+OO O.OOE+OO 2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO Particulate

{T112 > 8

1. Total Particulate (1112 > 8 davs) Release Curies 7.93E-07 3.25E-06 2. Averaqe Release Rate For Period uCi/sec 9.98E-08 4.09E-07 3. Gross Alpha Radioactivity Release Curies 2.11 E-07 3.10E-07 Tritium: 1. Total Release Curies 1.02E+01 1.96E+01 2. Average Release Rate For Period µCi/sec 1.28E+OO 2.47E+OO F. Carbon-14
1. Total Release Curies 2.08E+OO 7.01E-01 2. AveraQe Release Rate For Period uCi/sec 2.62E-01 8.82E-02 F. Percentage Of Technical Specification Limits 1. Total Bodv Dose Hate % 2.18E-06 1.10E-07 2. Skin Dose Rate . oia 1.54E-06 8.56E-07 3. Critical Organ Dose Rate {with C-14) % 2.10E-03 1.92E-03 Critical Organ Dose Rate {without C-14) % 8.76E-04 1.64E-03 Page 2 of 2 ESTIMATED TOTAL PERCENT ERROR (%) 1.80E+1 2.80E+1 2.80E+1 3.10E+1 TABLE 18 NORTH ANNA POWER STATION .. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) 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 2.43E-01 7.61E-03 1.92E-01 4.78E-03 Xenon -133m Ci N/D N/D 2.44E-03 N/D Xenon -135 Ci 4.10E-03 N/D 1.13E-01 5.76E-03 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 Other (Specify)

N/D. N/D N/D N/D Argon -41 Ci 7.77E-03 1.62E-02 1.55E-01 N/D Total For Period Ci 2.55E-01 2.38E-02 4.63E-01 1.05E-02 Iodines: Iodine -130 Ci N/D N/D N/D N/D Iodine -131 Ci 8.50E-09 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 Total For Period Ci 8.50E-09 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

-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 (01/16 -12/16) Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELj::ASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) Barium -Lanthanum

-140 Ci N/D N/D 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 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 (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 3.00E-01 9.33E-02 3.21E-02 1.16E-04 CARBON-14 Ci 7.82E+OO 7.30E-01 1.42E+01 3.22E

.. TABLE 18 NORTH ANNA POWER STATION .. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) 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 3.83E-06 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 9.47E-03 N/D 3.91 E-02 1.00E-02 -Xenon-133m Ci N/D N/D N/D N/D Xenon -135 Ci N/D N/D 1.22E-05 9.39E-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 1.44E-05 N/D Other (Specify)

N/D N/D N/D N/D Argon -41 Ci 1.09E-02 4.18E-05 2.03E-03 1.24E-02 Total For Period Ci 2.04E-02 4.18E-05 4.11E-02 2.25E-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 NID Iodine -134 Ci N/D N/D N/D *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 I N/D N/D lron-59. Ci N/D N/D N/D N/D Cobalt-6.0 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 NID 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 NID Cesium -134 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 (01/16 -12/16) Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.) Barium -Lanthanum

-140 Ci N/D N/D 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 Total for Period (T1/2 > 8 days) Ci N/D 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 N/D N/D N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 2.59E-01 1.09E+OO 2.96E-02 8.67E-05 CARBON-14 Ci 6.26E-01 1.28E-03 1.26E+OO 6.90E-01 NUCLIDES RELEASED Fission & Activation Gases: Krypton -85 Krypton -85m Krypton -87 Krypton -88 Xenon -131m Xenon -133 Xenon -133m Xenon -135 Xenon -135m Xenon -137 Xenon -138 Other (Specify)

Argon -41 Total For Period Iodines: Iodine -130 Iodine -131 Iodine -132 Iodine -133 Iodine -134 Iodine -135 Total For Period Particulates:

Manganese

-54 Cobalt -58 Iron -59 Cobalt-60 Zinc-65 Strontium

-89 Strontium

-90 Cesium -134 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE BATCH 1ST 2ND 1ST UNITS QUARTER QUARTER QUARTER Ci N/D N/D N/D Ci N/D N/D 1.49E-04 Ci N/D N/D 8.79E-05 Ci N/D N/D 2.04E-04 Ci N/D N/D N/D Ci N/D N/D 6.35E-02 Ci N/D N/D 4.50E-04 Ci N/D N/D 2.86E-03 Ci N/D N/D 6.96E-06 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D 2.56E-02 Ci N/D N/D 9.28E-02 Ci N/D N/D N/D Ci 4.09E-05 N/D N/D Ci 1.00E-04 N/D 2.19E-04 Ci N/D N/D N/D Ci N/D N/D N/D -Ci N/D N/D N/D Ci 1.41E-04 N/D 2.19E-04 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci 3.15E-06 N/D 3.27E-06 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Page 1 of 4 MODE 2ND QUARTER N/D N/D N/D N/D N/D 1.11E-05 N/D N/D N/D N/D N/D N/D 1.11 E-05 N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D NUCLIDES RELEASED Particulates: (cont.) Cesium-137 Barium -Lanthanum

-140 Ruthenium-103 (T1/2 > 8 days) Cerium-144 Niobium-95 Zirconium-95 Tellurium-131m (T1/2 < 8 days) Yttrium-91 m (T1/2 < 8 days) Chromium-51 Total for Period (T1/2 > 8 days) Total for Period (T1/2 < 8 days) Total For Period GROSS ALPHA: TRITIUM: CARBON-14 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND-LEVEL GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE BATCH 1ST 2ND 1ST UNITS QUARTER QUARTER QUARTER Ci N/D N/D N/D Ci N/D N/D N/D Ci 1.54E-06 N/D N/D Ci N/D N/D N/D Ci N/D N/D , N/D Ci N/D N/D N/D Ci N/D N/D 3.05E-05 Ci N/D N/D 1.87E-07 Ci N/D N/D 5.63E-06 Ci 4.?0E-06 N/D 8.89E-06 Ci N/D N/D 3.06E-05 Ci 4.?0E-06 O.OOE+OO 3.95E-05 Ci 1.44E-07 8.65E-08 N/D Ci 1.75E+OO 5.92E+OO 3.11E+OO Ci N/D N/D 2.85E+OO Page 2 of 4 MODE 2ND QUARTER N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D O.OOE+OO N/D 9.69E-02 3.41 E-04 NUCLIDES RELEASED Fission & Activation Gases: Krypton -85 Krypton -85m Krypton -87 Krypton -88 Xenon -131m Xenon -133 Xenon -133m Xenon -135 Xenon -135m Xenon-137 Xenon -138 Other (Specify)

Argon -41 Total For Period Iodines: Iodine -130 Iodine -131 Iodine -132 Iodine -133 Iodine -134 Iodine -135 Total For Period Particulates:

Manganese

-54 Cobalt -58 Iron -59 Cobalt-60 Zinc-65 Strontium

-89 Strontium

-90 Cesium -134 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/16 -12116) CONTINUOUS MODE BATCH 3RD 4TH 3RD UNITS QUARTER QUARTER QUARTER Ci N/D N/D N/D Ci N/D N/D 1.03E-05 Ci N/D N/D N/D Ci N/D N/D 1.74E-06 Ci N/D N/D N/D Ci N/D N/D 4.68E-03 Ci N/D N/D 1.35E-04 Ci N/D N/D 9.26E-04 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci Ci N/D N/D 4.91E-04

  • Ci N/D N/D 6.24E-03 Ci N/D N/D 5.71E-08 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D 5.71 E-08 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D. N/D 7.93E-07 Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D ,_ Page 3 of 4 MODE 4TH QUARTER N/D N/D N/D N/D N/D 2.95E-04 N/D N/D N/D N/D N/D N/D 2.95E-04 N/D N/D N/D N/D N/D N/D N/D N/D 7.75E-07 N/D 1.50E-06 N/D N/D N/D N/D NUCLIDES RELEASED Particulates: (cont.) Cesium-137 Barium -Lanthanum

-140 Cerium -141 Cerium -144 Other (Specify)

Strontium-91 (T1/2 < 8 days) Rubidium-88 (T1/2 < 8 days) Niobium-95 (T1/2 > 8 days) Ru-103 (T1/2 > 8 days) Rhodium-105 (T1/2 < 8 days) Ruthenium-105 (T1/2 < 8 days) Total for Period (T1/2 > 8 days) Total for Period (T1/2 < 8 days) ' Total For Period GROSS ALPHA: TRITIUM: CARBON-14 TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE BATCH 3RD 4TH 3RD UNITS QUARTER QUARTER QUARTER Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D 5.00E-07 Ci N/D N/D 2.77E-07 Ci N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D N/D Ci N/D N/D 7.93E-07 Ci N/D N/D 7.77E-07 Ci O.OOE+OO O.OOE+OO 1.57E-06 Ci 2.11E-07 3.10E-07 N/D Ci 6.72E+OO 1.78E+01 3.16E+OO Ci N/D N/D 1.91 E-01 Page 4 of 4 MODE 4TH QUARTER 1.42E-07 N/D N/D NID N/D N/D 8.32E-07 N/D 6.86E-11 4.89E-10 3.25E-06 5.58E-10 3.25E-06 N/D 7.0SE-01 9.0SE-03 TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/16 -12/16) Page 1of2 1 ST 2ND ESTIMATED TOTAL UNITS QUARTER QUARTER .PERCENT ERROR (%) A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 3.BOE-03 1.13E-02 2.00E+01 2. Average diluted concentration during the period. µCi/ml 1.36E-11 1.50E-11 3. Percent of applicable limit (T.S.} % 2.20E-05 2.18E-05 B. Tritium: 1. Total release activity.

Curies 9.78E+02 3.58E+02 2.00E+01 2. Average diluted concentration during the period. µCi/ml 3.49E-06 4.75E-07 3. Percent of applicable limit (T.S.) % 3.49E-02 4.75E-03 c. Dissolved and Entrained Gases: 1. Total release activity.

Curies O.OOE+OO O.OOE+OO 2.00E+01 2. Average diluted concentration during the period. µCi/ml O.OOE+OO O.OOE+OO 3. Percent of applicable limit (T.S.) % O.OOE+OO O.OOE+OO D. Gross Alpha Radioactivitv:

1. Total release activity.

Curies O.OOE+OO O.OOE+OO 2.00E+01 E. Volume of waste released: (prior to dilution).

Liters 9.79E+07 1.01 E+08 3.00E+OO F. Total volume of dilution water used during the period. Liters 2.80E+11 7.54E+11 3.00E+OO TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/16 -12/16) Page 2of2 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 Qross alpha). Curies 1.15E-02 7.58E-03 2.00E+01 -2. Average diluted concentration during the period. µCi/ml 1.47E-11
3. Percent of applicable limit (T.S.) % 1.99E-05 1.52E-05 B. Tritium: ' 1. Total release activity.

Curies 8.19E+02 1.42E+01 2.00E+01 2. Average diluted concentration during the period. µCi/ml 1.0SE-06 2.26E-08 3. Percent of applicable limit (T.S.) % 1.0SE-02 2.26E-04 c. Dissolved and Entrained Gases: 1. Total release activity.

Curies O.OOE+OO O.OOE+OO 2.00E+01 2. Average diluted concentration during the period. µCi/ml O.OOE+OO O.OOE+OO 3. Percent of applicable limit (T.S.) % O.OOE+OO O.OOE+OO D. Gross Alpha Radioactivity:

1. Total release activity. . Curies O.OOE+OO O.OOE+OO 2.00E+01 E. Volume of waste released: (prior to dilution).

Liters 9.08E+07 1.15E+08 3.00E+OO F. Total volume of dilution water used during the period. Liters 7.83E+11 6.28E+11 3.00E+OO NUCLIDES RELEASED Fission & Activation Products:

Manganese

-54 Iron -59 Cobalt-58 Cobalt-60

-89 Strontium

-90 Niobium -95 Antimony-124 Silver -11 Om Iodine -131 Iodine -133 Cesium -134 Cesium -137 Barium-Lathanum

-140 Cerium -141 Tellurium-125m Niickel -63 (T112 > 8 days) Antimony-125 Total for Period TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE 1ST 2ND UNITS QUARTER QUARTER Ci NID NID Ci NID 1.18E-04 Ci 2.35E-03 7.22E-03 Ci 1.42E-03 3.78E-03 Ci NID NID Ci NID NID Ci NID 8.24E-05 Ci NID NID Ci N/D 7.04E-05 Ci NID NID Ci NID NID Ci NID NID Ci 2.55E-05 NID Ci NID N/D Ci NID NID Ci NID NID Ci NID NID Ci NID NID Ci 3.80E-03 1.13E-02 Page 1 of 4 -BATCH MODE 1ST 2ND QUARTER QUARTER NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NUCLIDES RELEASED Dissolved

& Entrained Noble Gases: Xenon-133 Xenon-133m Xenon -135 Xenon-135m Other (Specify)

Krypton-88 ( T112 < 8 days) Krypton-85 (T112 > 8 days) Total for Period Tritium Gross Alpha TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE 1ST 2ND UNITS QUARTER QUARTER Ci N/D NID Ci NID NID Ci NID NID Ci NID NID Ci N/D NID Ci NID. NID Ci NID NID Ci NID NID Ci 9.78E+02 3.58E+02 Ci NID NID Page 2 of 4 BATCH MODE 1ST 2ND QUARTER QUARTER NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA '

NUCLIDES RELEASED Fission & Activation Products:

Manganese

-54 Iron -59 Cobalt-58 Cobalt-60 Strontium

-89 Strontium

-90 Niobium-95 Zirconium

-95 Silver-110m Iodine -131 Iodine -133 Cesium-134 Cesium-137 Barium-Lathanum

-140 Cerium -141 Chro!Jllum-51 Nickel -63 (T112 > 8 days) Antimony-122 (T112 < 8 days) Antimony-125 (T112 > 8 days) Antimony-124 (T112 > 8 days) Tellurium-125m (T112 > 8 days) Total for Period TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE -3RD 4TH UNITS QUARTER QUARTER Ci 1.34E-04 3.51E-05 Ci NID NID Ci 7.55E-03 5.47E-03 Ci 3.41 E-03 2.04E-03 Ci NID NID Ci NID NID Ci 8.57E-05 3.00E-05 Ci NID N/D Ci 4.63E-05 NID Ci NID NID Ci NID NID Ci NID NID Ci 1.98E-05 NID Ci NID N/D Ci NID NID Ci 2.23E-04 NID Ci NID NID Ci NID NID Ci NID Ci NID NID Ci NID Ci 1.15E-02 7.58E-03 Page 3 of 4 BATCH MODE 3RD 4TH QUARTER QUARTER NID NIA NID NIA 1.24E-06 NIA 2.36E-06 NIA NID NIA NID NIA 4.41E-07 NIA NID NIA NID NIA NID NIA NID NIA NID NIA 2.26E-06 NIA NID NIA NID NIA NID NIA NID NIA NID NIA 2.52E-05 NIA N/D NIA 5.81E-06 NIA 3.73E-05 NIA NUCLIDES RELEASED Dissolved

& Entrained Noble Gases: Xenon -133 Xenon-133m Xenon -135 Xenon -135m -Other (Specify)

Argon -41 (T1/2 < 8 days) Krypton -85 (T1/2 > 8 days) Total for Period Tritium Gross Alpha TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/16 -12/16) CONTINUOUS MODE 3RD 4TH UNITS QUARTER QUARTER Ci N/D N/D Ci N/D N/D Ci N/D N/D Ci N/D N/D Ci N/D N/D Ci N/D N/D Ci N/D N/D Ci 8.19E+02 1.42E+01 Ci N/D N/D Page 4 of 4 BATCH MODE 3RD 4TH QUARTER QUARTER N/D N/A N/D N/A N/D N/A N/D N/A N/D N/A N/D N/A N/D N/A 7.40E-03 N/A N/D N/A TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-16 THROUGH 12-31-16 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, mJ 1.80E+01

  • 2.50E+01 evaporator bottoms, etc., Ci 8.92E+01 2.50E+01 b. Dry compressible waste, contaminated mJ 8.31E+02 ** 2.50E+01 equipment, etc., Ci 1.73E+OO 2.50E+01 Irradiated components, control rods, mJ O.OOE+OO *** 2.50E+01 c. etc., Ci O.OOE+OO 2.50E+01 d. Other (describe)

Used oil/Blast media/Sewage/Gravel mJ 2.87E+OO **** 2.50E+01 Dessicant/Soil/Construction debris Ci 2.27E-05 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%) a. Co-60 4.44E+01 3.96E+01 2.50E+01 Fe-55 1.50E+01 1.34E+01 2.50E+01 Ni-63 1.17E+01 1.04E+01 2.50E+01 Cs-137 6.76E+OO 6.04E+OO 2.50E+01 Mn-54 5.55E+OO 4.96E+OO 2.50E+01 Co-58 5.41E+OO 4.83E+OO 2.50E+01 Cs-134 2;56E+OO 2.28E+OO 2.50E+01 Nb-95 2.03E+OO 1.82E+OO 2.50E+01 Zn-65 1.25E+OO 1.12E+OO 2.50E+01 Cr-51 1.11 E+OO 9.90E-01 2.50E+01 Zr-95 1.07E+OO 9.53E-01 2.50E+01 Be-7 7.10E-01 6.37E-01 2.50E+01 Eu-154 7.00E-01 6.24E-01 . 2.50E+01 Sb-125 6.40E-01 5.67E-01 2.50E+01 C-14 4.89E-01 2.50E+01 b. Co-60 2.61E+01 4.50E-01 2.50E+01 Cs-137 1.88E+01 3.24E-01 2.50E+01 Nb-95 1.63E+01 2.82E-01 2.50E+01 Zr-95 1.18E+01 2.03E-01 2.50E+01 Fe-55 8.14E+OO 1.41 E-01 2.50E+01 Cr-51 4.52E+OO 7.81E-02 2.50E+01 Ni-63 4.21E+OO 7.27E-02 2.50E+01 Co-58 3.62E+OO 6.25E-02 2.50E+01 H-3 2.04E+OO 3.53E-02 2.50E+01 Mn-54 1.52E+OO 2.62E-02 2.50E+01 Sb-125 4.50E-01 7.76E-03 2.50E+01 Zn-65 3.90E-01 6.65E-03 2.50E+01 C-14 3.80E-01 6.59E-03 2.50E+01 Sn-113 3.40E-01 5.87E-03 2.50E+01 Tc-99 3.40E-01 5.82E-03 2.50E+01 Ce-144 2.60E-01 4.51E-03 2.50E+01 c. NONE d. H-3 9.83E+01 4.63E-06 2.50E+01 Ce-144 8.10E-01 3.80E-08 2.50E+01 Cs-137 4.20E-01 1.99E-08 2.50E+01 Co-60 2.90E-01 .1.36E-08 2.50E+01 TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS
3. Solid Waste Disposition Number of Shipments 2 35 Mode of Transportation Truck Truck B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation 0 N/A Destination Clive, UT Oak Ridge, TN Destination N/A Page 2 of 2 (4) shipments containing resins were shipped to a licensed waste processor for final dewatering and disposal (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 processor for processing (31) shipments containing dry compactable waste were shipped to a licensed waste processor for processing (1) shipment containing dry compactable waste was shipped to a licensed waste facility for disposal None (1) shipment containing used oil was shipped to a licensed waste disposal facility for processing (1) shipment containing used blast media was shipped to a licensed waste disposal facility for disposal.

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01116 -12/16) An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway will be made as required by ODCM Section 6.7.2. 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem} 3.46E-1 1.27E-1 2.89E-1 5.12E-3 7.67E-1 Critical Organ Dose (mrem} 3.46E-1 1.27E-1 2.89E-1 5.22E-3 7.67E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad} 1.52E-4 6.31E-6 7.61E-6 4.56E-6 1.70E-4 Noble Gas Beta Dose (mrad) 9.60E-5 3.06E-6 6.22E-6 2.0SE-6 1.07E-4 Critical Organ (Child bone) Dose for 1-131, 1-133, H-3, Particulates with TYz > 8 days (including C-14} (mrem} 1.0SE+O 3.SOE-2 3.07E-2 3.41E-2 1.18E+O Critical Organ (Child thyroid) Dose for 1-131, 1-133, H-3, Particulates with TYz 0>8 days (excluding C-14} (inrem} 1.25E-2 3.25E-3 4.96E-3 1.02E-2 3.09E-2 9 ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM) (01/16 -12/16) 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 were no revisions to the ODCM during this reporting period. 10

_1. ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01116 -12/16) 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 2016. 11

  • ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING*INSTRUMENTATION (01/16 -12/16) As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability ofradioactive liquid and/or 'gaseous effluent monitoring instrumentation is provided in this attachment.

There was no liquid and/or gaseous effluent monitoring instrumentation inoperable for an extended period, greater than thirty consecutive days, during the reporting period. 12

... ATTACHMENT 6 UNPLANNED RELEASES (01116 -12/16) 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 2016 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. Elevated results indicated in Attachment 8 are from the on-going investigation/

mitigation for the voluntary communication made in 2010. The hydrological modeling indicates the horizontal groundwater movement around well #6 is < 1 inch per day. 13 i Gaseous Effluents:

-Radioisotope Krypton -87 Krypton-88 Xenon -133 Xenon-133m Xenon -135 Xenon -135m Xenon -138 Iodine -131 Iodine -133 Manganese

-54 Cobalt -58 Iron -59 Cobalt -60 Zinc -65 Strontium

-89 Strontium

-90 Molybdenum

-99 Cesium -134

  • Cesium -137 Cerium -141 Cerium -144 Gross Alpha Tritium ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/16 -12/16) Required L.L.D. Typical

µCi/mL µCi/mL 1.00E-4 2.50E-8 7.50E-8 1.00E-4 4.00E-8 2.50E-7 1.00E-4 2.00E-8 1.00E-7 1.00E-4 1.00E-7 4.00E-7 1.00E-4 1.00E-8 5.00E-8 1.00E-4* 5.00E-8 2.00E-7 1.00E-4 9.00E-8 4.00E-7 1.00E-12 3.00E-14 1.00E-13 1.00E-10 1.00E-14 7.00E-13 1.00E-11 2.00E-14 6.00E-14 1.00E-11 2.00E-14 6.00E-14 1.00E-11 6.00E-14 1.00E-13 1.00E-11 3.00E-14 1.00E-13

  • 1.00E-11 6.00E-14 2.00E-13 1.00E-11 3.00E-14 8.00E-12 1.00E-11 3.00E-15 9.00E-12 1.00E-11 2.00E-14 1.00E-13 1.00E-11 2.00E-14 8.00E-14 1.00E-11 3.00E-14 8.00E-14 1.00E-11 3.00E-14 1.00E-13 1.00E-11 1.50E-13 4.00E-13 1.00E-11 7.00E-15 2.00E-14 1.00E-6 4.00E-09 9.00E-09 14 Liguid Effluents:

Radioisotope Krypton-87 Krypton -88 Xenon-133 Xenon-133m Xenon -135 Xenon -135m Xenon -138 Iodine -131 Manganese

-54 Iron -55 Cobalt-58 Iron -59 Cobalt-60 Zinc-65 Strontium

-89 Strontium

-90 Molybdenum

-99 Cesium -134 Cesium -137 Cerium -141 Cerium -144 Gross Alpha Tritium ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01116 -12/16) Required L.L.D. Typical L.L.D. µCi/mL µCi/mL 1.00E-5 3.00E-8 1.00E-5 5.00E-8 1.00E-5 3.00E-8 1.00E-5 . 9.00E-8 1.00E-5 1.00E-8 1.00E-5 3.00E-8 1.00E-5 1.00E-7 1.00E-6 1.00E-8 5.00E-7 1.00E-8 1.00E-6 3.00E-7 5.00E-7 1.50E-8 5.00E-7 3.00E-8 5.00E-7 1.00E-8 5.00E-7 3.00E-8 5.00E-8 1.00E-8 5.00E-8 5.00E-9 5.00E-7 2.00E-8 5.00E-7 1.50E-8 5.00E-7 1.50E-8 5.00E-7 3.00E-8 5.00E-7 1.00E-7 1.00E-7 2.00E-8 1.00E-5 2.00E-6 15 1.00E-7 5.00E-7 1.00E-7 3.00E-7 5.00E-8 2.00E-7 1.00E-6 5.00E-8 5.00E-8 8.00E-7 6.00E-8 7.00E-8 5.50E-8 6.00E-8 4.00E-8 9.00E-9 6.00E-8 5.00E-8 6.00E-8 9.00E-8. 5.00E-7 7.00E-8 5.00E-6 ATTACHMENT 8 RESULTS OF GROUNDWATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/16 -12/16) 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 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 VP AP-2103N.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2016. 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. An N/D" indicates an analysis was performed but. the result was less than t}le 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.

16

,,, ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/16 -12/16) 1*t Quarter 2016 Sample Date Sample H-3<1> Gamma -Emitting 1-131(!) Sr-89190<1> Fe-ss<1> Ni-63<1> Alpha Pu-241<1)

Media Particulates<

1> TRU<1> PZ-3 01/15116 WATER 3227 NIA NIA NIA NIA NIA NIA NIA PZ-3 02123116 WATER 4112 NIA NIA NIA NIA NIA NIA NIA PZ-3 03119116 WATER 4064 NIA NIA NIA NIA NIA NIA NIA GWP-3 03118116 WATER <967 NIA NIA NIA NIA NIA NIA NIA GWP-4 03121116 WATER 1239 NIA NIA NIA NIA NIA NIA NIA GWP-5A 03/18116 WATER <804 NIA NIA NIA NIA NIA NIA NIA GWP-6 01115116 WATER 4320 NIA NIA NIA NIA NIA NIA NIA GWP-6 02123116 WATER 6347 NIA NIA NIA NIA NIA NIA GWP-6 02126116 WATER 8133 NIA NIA NIA NIA NIA NIA NIA GWP-6 03103116 WATER 7978 NIA NIA NIA NIA NIA NIA NIA GWP-6 03111116 WATER 6615 NIA NIA NIA NIA NIA NIA NIA GWP-6 03119116 WATER 4832 NIA NIA NIA NIA NIA NIA NIA GWP-6 03126116 WATER 5418 NIA NIA NIA NIA NIA NIA NIA GWP-6 03131/16 WATER 6587 NIA NIA NIA NIA NIA NIA NIA GWP-7 03119116 WATER <928 NIA NIA NIA NIA NIA NIA NIA GWP-8 03118116 WATER <851 NIA NIA NIA NIA NIA NIA NIA GWP-9 03118116 WATER <987 NIA NIA NIA NIA NIA NIA NIA GWP-13 03118116 WATER <1022 NIA NIA NIA NIA NIA NIA NIA GWP-14 03118116 WATER <813 NIA NIA NIA NIA NIA NIA NIA GWP-15 03130116 WATER <862 NIA NIA NIA NIA NIA NIA NIA GWP-16 03118116 WATER <812 NIA NIA NIA NIA NIA NIA NIA GWP-17 03/20116 WATER <770 NIA NIA' NIA NIA NIA NIA NIA GWP-18 01/15116 WATER 1931 NIA NIA NIA NIA NIA NIA NIA GWP18 02123116 WATER 880 NIA NIA NIA NIA NIA NIA NIA GWP18 03119116 WATER 2928 NIA NIA NIA NIA NIA NIA NIA GWP-19 03120116 WATER 3251 NIA NIA NIA NIA NIA NIA NIA GWP-20 03120116 WATER <767 NIA NIA NIA NIA NIA NIA NIA GWP-21 01/15116 WATER 1538 NIA NIA NIA NIA NIA NIA NIA GWP-21 02123116 WATER 1282 NIA NIA NIA NIA NIA NIA NIA GWP-21 03119116 WATER 1991 NIA NIA NIA

' NIA NIA NIA NIA GWP-22 03118116 WATER <952 NIA NIA NIA NIA NIA NIA NIA BTW-I 03125116 WATER <857 NIA NIA NIA NIA NIA NIA NIA BTW-2 03125116 WATER <870 NIA NIA NIA NIA NIA NIA NIA BTW-4 03/25116 WATER <872 NIA NIA NIA NIA NIA NIA NIA TTW-2 03125116 WATER <883 NIA NIA NIA NIA NIA NIA NIA TTW-3 03/25116 WATER <880 NIA NIA NIA NIA NIA NIA NIA TTW-5 03/25116 WATER <889 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 02123116 WATER 1334 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02117116 WATER 1515 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02117116 WATER 1538 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 02117116 WATER 1481 NIA NIA NIA NIA NIA NIA NIA 17

,, U-1 Mat Sump East. 03103116 WATER <1301 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 03123116 WATER <901 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 03103116 WATER <1355 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 03123116 WATER <907 NIA NIA NIA *NIA NIA NIA NIA U-2 Mat Sump Inside 03103116 WATER <1299 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 03123116 WATER <899 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 03103116 WATER <1322 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 03123/16 WATER <903 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 03103116 WATER <1307 NIA NIA NIA NIA NIA NIA NIA U-1 AB/FB GWMS 03123116 WATER <915 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 03103116 WATER <1307 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 03123116 WATER <903 NIA NIA NIA NIA NIA NIA NIA PZ-1 03118116 WATER Insufficient Volume to Sample PZ-2 03118116 WATER Insufficient Volume to Sample TTW-1 Well abandoned in place, pending decommissioning.

TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L 18

,, ATTACHMENT 8 RESULTS OF GROUNDWATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/16 -12/16) 2nd Quarter 2016 Sample Date Sample H-3<1> Gamma -Emitting 1-131<1> Sr-89190<1> Fe-55<1> Ni-63<1> Alpha Pu-241<1> Media Particulates<'>

TRU<1> PZ-3 04122116 WATER 4956 NIA NIA NIA NIA NIA NIA NIA PZ-3 06102116 WATER 5200 NIA NIA NIA NIA NIA NIA NIA PZ-3 06128116 WATER 1900 NIA NIA NIA NIA NIA NIA NIA pz_3<2 J 06128116 WATER 2710 NIA NIA NIA NIA NIA NIA NIA GWP-3(2) 06109116 WATER 1580 NIA NIA NIA NIA NIA NIA NIA GWP-4(2) 06109116 WATER 2780 NIA NIA NIA NIA NIA NIA NIA GWP-5A(2) 06109116 WATER <1050 NIA NIA NIA NIA NIA NIA NIA GWP-6 041091)6 WATER 4859 NIA NIA NIA NIA NIA NIA NIA GWP-6 04122116 WATER 6733 NIA NIA NIA NIA NIA NIA NIA GWP-6 05104116 WATER 3639 NIA NIA NIA NIA NIA NIA NIA GWP-6 06102116 WATER 7000 NIA NIA NIA NIA NIA NIA NIA GWP-6 06109116 WATER 5966 NIA NIA NIA NIA NIA NIA NIA GWP-6(2) 06109116 WATER 8250 NIA NIA NIA NIA NIA NIA NIA GWP-7(2) 06109116 WATER <1030 NIA NIA NIA NIA. NIA NIA NIA GWP-8(2) 06109116 WATER <1040 ND NIA NIA NIA NIA NIA NIA owP4 2 l 06109116 WATER, <1030 NIA NIA NIA NIA NIA NIA NIA GWP-13(2) 06128116 WATER 1870 NIA NIA NIA NIA NIA NIA NIA GwP-14(2) 06109116 WATER <1040 NIA NIA NIA NIA NIA NIA NIA GWP-15(2) 06128/16 WATER 1280 NIA NIA NIA NIA NIA NIA NIA GWP-16(2) 06128116 WATER 1260 NIA NIA NIA NIA NIA NIA NIA GWP-d 2 J 06128116 WATER 1650 NIA NIA NIA NIA NIA NIA NIA GWP-18 04122116 WATER 3381 NIA NIA NIA NIA NIA NIA NIA GWP-18 06102116 WATER 4133 NIA NIA NIA NIA NIA NIA NIA GWP-18 06128116 WATER 4271 NIA NIA NIA NIA NIA NIA NIA GWP-18(2) 06128116 WATER 2570 NIA NIA NIA NIA NIA NIA NIA GWP-19(2) 06122116 WATER 3800 NIA NIA NIA NIA NIA NIA NIA GWP-20<2 J 06122116 WATER 2910 NIA NIA NIA NIA NIA NIA NIA GWP-21 04122116 WATJ;:R 1136 NIA NIA NIA NIA NIA NIA NIA GWP-21 06102116 WATER 2153 NIA NIA NIA NIA NIA NIA NIA GWP-21 06128116 WATER* 1637 NIA NIA NIA NIA NIA NIA NIA GWP-21<2 l 06128116 WATER <1050 NIA NIA NIA NIA NIA NIA NIA GWP-22<2 J 06122116 WATER <1050 NIA NIA NIA NIA NIA NIA NIA BTW-1<2 J 06129116 WATER <1060 NIA NIA NIA NIA NIA NIA NIA BTW-z<2l 06129116 WATER <1040 NIA NIA NIA NIA NIA NIA NIA BTW-4(2) 06129116 WATER <1050 NIA NIA NIA NIA NIA NIA NIA TTW-2<2 J 06129116 WATER <1060 NIA NIA NIA NIA NIA NIA NIA TT\:V-3(2) 06129116 WATER <1030 NIA NIA NIA NIA NIA NIA NIA TTW-5(2) 06129116 WATER <1060 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05111116 WATER <1480 NIA NIA NIA NIA NIA NIA NIA 19

> ,Sample Date Sample H-3<1> Gamma -Emitting 1-131 (I) Sr-Fe-55<1> Ni-63<1> Alpha Pu-241<1l Media Particulates<

1> 89190(!) TRU<1> U-1 Intake Storm Drains 05/19116 WATER <1530 NIA NIA NIA NIA

  • NIA NIA NIA U-2 Intake Storm Drains 05119116 WATER <1530 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 05119116 WATER <1530 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 05112116 WATER <1468 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 05112116 WATER <1458 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 05112116 WATER <1462 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 05112116 WATER <1455 NIA NIA NIA NIA NIA NIA NIA U-1 AB/FB GWMS 05/12116 WATER <1460 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 05112116 WATER <1455 NIA NIA NIA NIA NIA NIA NIA PZ-1 06128116 WATER Insufficient Volume to Sample PZ-2 06128116 WATER Insufficient Volume to Sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 20

" .. ). ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01116 -12/16) 3rd Quarter 2016 Sample Date Sample H-3<1> Gamma -Emitting 1-131(!) Sr-Fe-55<1> Ni-63<1> Alpha Media Particulates<

1> 89190(!) TRU<1> PZ-3 07/12116 WATER 1443 NIA NIA NIA NIA NIA NIA PZ-3 08102116 WATER 2664 NIA NIA NIA NIA NIA NIA PZ-3 08110116 WATER 1771 NIA NIA NIA NIA NIA NIA PZ-3 09/12116 WATER 2062 NIA NIA NIA NIA NIA NIA GWP-3 09124116 WATER <824 NIA NIA NIA NIA NIA NIA GWP-4 09124116 WATER <840 NIA NIA NIA NIA NIA NIA GWP-5A 09124116 WATER <820 NIA NIA NIA NIA NIA NIA GwP-6 07/12116 WATER 7399 NIA NIA NIA NIA NIA NIA GWP-6 08102116 WATER 6674 NIA NIA NIA NIA NIA NIA GWP-6 08110116 WATER 4797 NIA NIA NIA NIA NIA NIA GWP-6 09112116 WATER 3322 NIA NIA NIA NIA NIA NIA GWP-7 09124116 WATER <856 NIA NIA NIA NIA NIA NIA GWP-8 09124116 WATER <856 NIA NIA NIA NIA NIA NIA GWP-9 09124116 WATER <849 NIA NIA NIA NIA NIA NIA GWP-13 09124116 WATER <854 NIA NIA NIA NIA NIA NIA GWP-14 09127116 WATER <940 NIA NIA NIA NIA NIA NIA GWP-15 09127116 WATER <929 NIA NIA NIA NIA NIA NIA GWP-16 09127116 WATER <912 NIA NIA NIA NIA NIA NIA GWP-17 09127116 WATER 1220 NIA NIA NIA NIA NIA NIA GWP-18 07112116 WATER 1459 NIA NIA NIA NIA NIA NIA GWP-18 09127116 WATER 1390 NIA NIA NIA NIA NIA NIA GWP-19 09127116 WATER 1310 NIA NIA NIA NIA NIA NIA GWP-20 09127116 WATER 1820 NIA NIA NIA NIA NIA NIA GWP-21 07112116 WATER <915 NIA NIA NIA NIA NIA NIA GWP-21 09127116 WATER <866 NIA NIA NIA NIA NIA NIA GWP-22 09124116 WATER <803 NIA NIA NIA NIA NIA NIA BTW-I 09127116 WATER <906 NIA NIA NIA NIA NIA NIA BTW-2 09127116 WATER <904 NIA NIA NIA NIA NIA NIA BTW-4 09127116 WATER <916 NIA NIA NIA NIA NIA NIA TTW-2 09127116 WATER <1070 NIA NIA NIA NIA NIA NIA TTW-3 09127116 WATER <912 NIA NIA NIA NIA NIA NIA TTW-5 09127116 WATER <940 NIA NIA NIA NIA NIA NIA Sub Surface Drains 08109116 WATER <1451 NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 08104116 WATER <1540 NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 08104116 -WATER <1530 NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 08104116 WATER <1440 NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 08110116 WATER , <1386 NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 09127116 WATER <960 NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 08/10116 WATER <1443 NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09127116 WATER <942 NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 08110116 WATER <1470 NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 09127116 WATER <951 NIA NIA NIA NIA NIA NIA 21 Pu-241<1> NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 08110116 WATER <1427 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09127116 WATER <957 NIA NIA 'NIA NIA NIA NIA NIA U-1 ABIFB GWMS 08110116 WATER <1424 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09127116 WATER <839 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 08110116 WATER <1440 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09127116 WATER <955 NIA NIA NIA NIA NIA NIA NIA PZ-1 09124116 WATER Insufficient volume to sample PZ-2 09124116 WATER Insufficient volume to sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L 22 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01116 -12/16) 4th Quarter 2016 Sample Date Sample H-3<1) Gamma -Emitting 1-131<1> Sr-89190<1> Fe-55<1> Ni-63<1> Alpha Pu-241<1> Media Particulates<

1> TRuu> PZ-3 10/12116 WATER 2438 NIA NIA NIA NIA NIA NIA NIA PZ-3 11109116 WATER 4764 NIA NIA NIA NIA NIA NIA NIA PZ-3 12121116 WATER 4933 NIA NIA NIA NIA NIA NIA NIA GWP-3 11122116 WATER <847 NIA -NIA NIA NIA NIA NIA NIA GWP-4 11122/16 WATER <847 NIA NIA NIA NIA NIA NIA NIA GWP-5A 11122116 WATER <907 NIA NIA NIA NIA NIA NIA NIA GWP-6 10112116 WATER 2099 NIA NIA NIA NIA NIA NIA NIA GWP-6 11109116 WATER 1655 NIA NIA NIA NIA NIA NIA NIA GWP-6 12121/16 WATER 1373 NIA NIA NIA NIA NIA NIA NIA GWP-7 11/22116 WATER <871 NIA NIA NIA NIA NIA NIA NIA GWP-8 11122116 WATER <936 NIA NIA NIA NIA NIA NIA NIA GWP-9 11122116 WATER <918 NIA NIA NIA NIA NIA NIA NIA GWP-13 11122116 WATER <887 NIA NIA NIA NIA NIA NIA NIA GWP-14 11/22116 WATER <869 ND ND NIA NIA NIA NIA NIA GWP-15 11122116 WATER <896 NIA NIA NIA NIA NIA NIA NIA GWP-16 11/22116 WATER <929 NIA NIA NIA NIA NIA NIA NIA GWP-17 11122116 WATER <887 NIA NIA NIA NIA NIA NIA NIA GWP-18 11/22116 WATER 3080 NIA NIA NIA NIA NIA NIA NIA GWP-19 11/22116 WATER 1250 NIA NIA NIA NIA NIA NIA NIA GWP-20 11122116 WATER 849 NIA NIA NIA NIA NIA NIA NIA GWP-21 11/22116 WATER <851 NIA NIA NIA NIA NIA NIA NIA GWP-22 11122116 WATER <904 NIA NIA NIA NIA NIA NIA NIA BTW-I 12109116 WATER <845 NIA NIA NIA NIA NIA NIA NIA BTW-2 12109116 WATER <817 NIA NIA NIA NIA NIA NIA NIA BTW-4 12109116 WATER <914 NIA NIA NIA NIA NIA NIA NIA TTW-2 12109116 WATER <789 NIA NIA NIA NIA NIA NIA NIA TTW-3 12109116 WATER <793 NIA NIA NIA NIA NIA NIA NIA TTW-5 12109116 WATER <886 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 11/04116 WA)'ER <1582 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11117116 WATER <1415 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 11/17116 WATER <1418 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 11117116 WATER <1413 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 10120116 WATER <819 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 10120116 WATER <840 ND NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 10120116 'WATER <823 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 10120116 WATER <838 NIA NIA NIA NIA NIA NIA NIA U-1 AB/FB GWMS 10120116 WATER <815 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 10120116 WATER <844 NIA NIA NIA NIA NIA NIA NIA PZ-1 11/22116 WATER Insufficient volume to sample PZ-2 11/22116 WATER Insufficient volume to sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L 23 I ATTACHMENT 9 CARBON-14 CALCULATIONS (01/16 -12/16). 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 ofC-14 in the atmosphere.

Due to the long half-life ofC-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 ofC-14 released.

At North Anna, improvements overthe years in fuel performance have resulted.in a decrease in the amount and distribution of radionuclides 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 of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-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 of C-14 in Nuclear Power Gaseous Effluents.

Based on this

  • document, at full capacity, North Anna would generate and release about 32.8 Ci ofC-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 28.7 Ci ofC-14 produced and released.

North Allna 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 of70% to 95% organic. North Anna used a value of70% organic and 30% C0 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 6.73E-2 rnrem from the inhalation pathway, or 4.49E-03%

TS of the 1500 rnrem/yr dose rate limit and l .09E+O rnrem from the ingestion pathway or 3.63E+OO%

TS of the 10CFR50, Appendix I, ALARA design objective of 15 rnrem/yr per unit. In both cases the critical organ was determined to be the child's bone. Miscellaneous There were no entries on the Annual Effluent Release Report Log for 2016. 24

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