ML14118A042

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Independent Spent Fuel Storage Installation (Isfsi), Submittal of 2013 Annual Radioactive Effluent Release Report
ML14118A042
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/22/2014
From: Gerald Bichof
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML14118A042 (47)
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Text

4 . I VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2014 United States Nuclear Regulatory Commission Serial No.14-130 Attention: Document Control Desk NAPS/JHL Washington, D. C. 20555 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. I AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2013 Annual Radioactive Effluent Release Report. This report is 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 Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].

If you have any questions or require additional information, please contact Page Kemp at (540) 894-2295.

Very truly yours, ia id T.-Bischof Site Vice President Enclosure Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station

iDommnno North Anna Power Station 2013 Annual Radioactive Effluent Release Report

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2013 TO DECEMBER 31, 2013)

PREPARED BY SuAarvisor Raadiological Analysis and Instrumentation REVIEWED BY:

Health Physics Technical Services APPROVEDBY Manager Radiological Protection and Chemistry

FORWARD This report is submitted in accordance with North Anna Unit 1 and 2 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).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2013 TO DECEMBER 31, 2013 INDEX Section No. Subject Page 1 EXECUTIVE

SUMMARY

................................... 1-2 2 PURPOSE AND SCOPE ................................... 2 3 D IS C US S IO N .................................................. 3-4 4 SUPPLEMENTAL INFORMATION ....................... 4 - Effluent Release Data ................................. 5 - Annual and Quarterly Doses ........................ 6 - Revisions to Offsite Dose Calculation Manual (ODCM) ........................................ 7 - Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment S yste m s .................................................. 8 - Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrum entation ........................................ 9 - Unplanned Releases ................................. 10 - Lower Limits of Detection (LLD) for Effluent Sample Analysis ........................... 11 -12 - Results of Ground Water Protection Initiative Sample Analysis ..................................... 13-21 - Carbon-14 Calculations ............................. 22-23 Miscellaneous - Annual Effluent Release Report Log ............ 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 Independent Spent Fuel Storage Installation (ISFSI) during the 2013 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 January 1 through December 31, 2013, 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 2013.

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 2013 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 4.53E-1 mrem, which is 7.54% of the dose limit and the critical organ dose due to liquid effluents was 4.55E-1 mrem, which is 2.28% of the dose limit.
b. The air dose due to noble gases was 8.30E-3 mrad gamma, which is 4.15E-2% of the annual gamma dose limit, and 5.50E-3 mrad beta, which is 1.38E-2% 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 0.921 mrem, which is 3.07% of the annual dose limit. The bases of C-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 1.1 2E-1 mrem, which is 3.73E-1 % 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.

1

1.0 EXECUTIVE

SUMMARY

(cont.)

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 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 and 2 and on an annual basis on Table 3. The report submitted before May 1 st 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 of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report.

2

j 3.0 DISCUSSION The basis for the calculation of the percent of Technical Specification for the critical organ in Table 1A of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-1 31 and iodine-1 33, 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 if C-14 is included and child's thyroid if C-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 1A 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 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.OE-4 pCi/ml.

Percent of Technical Specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases of airborne iodine-131 and iodine-1 33, 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-1 31 and iodine-1 33, 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 dose 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 the 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.

3

3.0 DISCUSSION (cont.)

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 if new location(s) need be added for the radiological environmental monitoring program pursuant to the ODOM.

There were no new sampling locations added. There were two (2) changes made to the land use census in 2013. The nearest garden in the N sector changed from 1.72 miles out to 1.78 miles out. The nearest garden in the SSW sector moved from 2.34 miles out to 1.33 miles out.

Section 6.6.1 .b.4 of the ODOM 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 from 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.

4

ATTACHMENT 1 EFFLUENT RELEASE DATA (01/13 - 12/13)

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.1 of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.

5

TABLE JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01113 - 12/13)

Page 1 of 2 1 ST 2 ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 6.54E-01 3.15E+00 1.80E+1
2. Average Release Rate For Period iiCi/sec 8.41 E-02 4.01 E-01 B. Iodines:
1. Total Iodine-131 Release Curies 0.OOE+00 1.28E-06 2.80E+1
2. Average Release Rate For Period iiCi/sec 0.OOE+00 1.63E-07 C. Particulate (Tl/2 > 8 days):
1. Total Particulate (T1/2 > 8 days) Release Curies 0.OOE+00 4.11 E-06 2.80E+1
2. Average Release Rate For Period VCi/sec 0.OOE+00 5.23E-07
3. Gross Alpha Radioactivity Release Curies 3.18E-07 2.30E-07 D. Tritium:
1. Total Release Curies 1.02E+01 9.67E-01 3.10E+1
2. Average Release Rate For Period pCi/sec 1.31E+00 1.23E-01 E. Carbon-14
1. Total Release Curies 8.26E-01 3.99E+00
2. Average Release Rate For Period l.Ci/sec 1.05E-01 5.07E-01 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 2.60E-06 3.56E-05
2. Skin Dose Rate  % 3.48E-05 8.88E-05
3. Critical Organ Dose Rate(with C-14)  % 3.10E-03 6.69E-03 Critical Organ Dose Rate (without C-14)  % 7.80E-04 3.13E-05

TABLE JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/13 - 12/13)

Page 2 of 2 3 RD 4TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 1.65E+01 2.83E+00 1.80E+1
2. Average Release Rate For Period giCi/sec 2.07E+00 3.56E-01 B. lodines:
1. Total Iodine-131 Release Curies 4.02E-03 3.95E-06 2.80E+1
2. Average Release Rate For Period pCi/sec 5.06E-04 4.97E-07 C. Particulate (T1/2 > 8 days):
1. Total Particulate (T1/2 > 8 days) Release Curies 1.20E-05 1.31 E-06 2.80E+1
2. Average Release Rate For Period pCi/sec 1.51 E-06 1.65E-07
3. Gross Alpha Radioactivity Release Curies 4.04E-07 2.27E-07 D. Tritium:
1. Total Release Curies 1.10E+01 3.12E+00 3.10E+1
2. Average Release Rate For Period pCi/sec 1.38E+00 3.93E-01 F. Carbon-14
1. Total Release Curies 2.08E+01 6.58E-02
2. Average Release Rate For Period pCi/sec 2.62E+00 8.28E-03 F. Percentane Of Technical Specification Limits
1. Total Body Dose Rate  % 3.52E-05 5.86E-03
2. Skin Dose Rate  % 8.78E-05 1.42E-03
3. Critical Organ Dose Rate (with C-1 4)  % 1.49E-02 3.83E-04 Critical Organ Dose Rate (without C-14)  % 3.09E-05 1.99E-04

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/13 - 12/13)

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 3.05E-01 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 4.78E-03 Xenon - 133 Ci 1.52E-02 4.17E-01 N/D 7.47E-01 Xenon - 133m Ci NID N/D N/D 5.12E-03 Xenon - 135 Ci N/D N/D N/D N/D Xenon - 135m Ci N/D N/D N/D 4.70E-03 Xenon - 137 Ci NID 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 N/D N/D N/D N/D Total For Period Ci 1.52E-02 4.17E-01 N/D 1.07E+00 lodines:

Iodine - 131 Ci N/D 2.38E-08 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 N/D 2.38E-08 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 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01113 - 12113)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND 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 Ag-1 10m Ci N/D 1.61E-08 N/D N/D Total for Period (T112 > 8 days) Ci N/D 1.61E-08 N/D N/D Total for Period (Tll2 < 8 days) Ci NID NID NID NID Total For Period Ci N/D 1.61E-08 N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUMK Ci 1.71E+00 7.15E-01 2.44E-05 1.12E-02 CARBON-14 Ci 169E-02 4.63E-01 N/D 1.19E+00

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01113 - 12113)

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 2.18E+00 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 1.08E-01 N/D Xenon - 133 Ci 3.41E+00 N/D 8.32E+00 N/D Xenon - 133m Ci N/D N/D 5.26E-02 N/D Xenon - 135 Ci 1.47E-03 N/D 9.09E-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 Other (Specify) N/D N/D N/D N/D Argon - 41 Ci N/D N/D 2.50E-03 N/D Total For Period Ci 3.41 E+00 N/D 1.07E+01 N/D lodines:

Iodine - 131 Ci 2.63E-06 5.13E-08 N/D N/D Iodine- 132 N/D N/D N/D N/D Iodine - 133 Ci 1.20E-07 N/D N/D N/D Iodine - 134 N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D NID Total For Period Ci 2.75E-06 5.13E-08 N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D 1.32E-06 N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci NID N/D 5.14E-06 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 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 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01113 - 12/13)

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 Silver-110m Ci N/D N/D N/D N/D Total for Period (Tl/2 > 8 days) Ci N/D N/D 6.46E-06 N/D Total for Period (Tl/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 4.06E-01 1.05E+00 5.05E-02 N/D CARBON-14 Ci 3.79E+00 N/D 1.19E+01 N/D

TABLE IC NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01113- 12/13)

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 6.39E-01 1.39E+00 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 - 131 m Ci N/D N/D N/D 4.57E-03 Xenon - 133 Ci N/D N/D N/D 2.72E-01 Xenon- 133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D 3.15E-04 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)

Argon - 41 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 6.39E-01 1.67E+00 lodines:

Iodine- 131 Ci N/D 1.26E-06 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 N/D 1.26E-06 N/D N/D Particulates:

Manganese - 54 Ci NID 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 9.79E-07 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 (01113 - 12/13)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Cesium - 137 Ci N/D N/D N/D 3.11E-06 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 NID N/D N/D Niobium-95 Ci N/D N/D N/D N/D Zirconium-95 Ci N/D N/D N/D N/D Rubidium-88 (T112 < 8 days) Ci N/D N/D N/D N/D Cerium-143 (Tl/2 < 8 days) Ci N/D N/D N/D N/D Chromium-51 Ci N/D N/D N/D N/D Total for Period (Tl/2 > 8 days) Ci N/D N/D N/D 4.09E-06 Total for Period (Tl/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci 0.OOE+00 0.OOE+00 0.OOE+00 4.09E-06 GROSS ALPHA: Ci 3.18E-07 2.30E-07 N/D N/D TRITIUM: Ci 8.43E+00 N/D 9.68E-03 2.40E-01 CARBON-14 Ci N/D N/D 7.10E-01 1.85E+00

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/13 - 12/13)

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 9.84E-02 6.19E-04 Krypton - 85m Ci N/D N/D 4.41E-04 6.80E-05 Krypton - 87 Ci N/ID N/D 2.61 E-05 3.85E-05 Krypton - 88 Ci N/D N/D 1.73E-04 1.26E-04 Xenon - 131m Ci N/D N/D 1.82E-02 1.68E-04 Xenon - 133 Ci N/D N/D 2.17E+00 8.49E-04 Xenon - 133m Ci N/D N/D 1.70E-02 N/D Xenon - 135 Ci N/D N/D 4.02E-02 6.95E-04 Xenon - 135m Ci N/D N/D 2.83E-04 4.80E-05 Xenon-137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify) Ci Argon - 41 Ci N/D 2.78E+00 3.44E-02 4.95E-02 Total For Period Ci N/D 2.78E+00 2.38E+00 5.21E-02 lodines:

Iodine - 131 Ci 3.94E-03 3.90E-06 7.79E-05 N/D Iodine- 132 Ci 3.26E-05 N/D 3.75E-05 N/D Iodine- 133 Ci 1.93E-05 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 3.99E-03 3.90E-06 1.15E-04 N/D Particulates:

Manganese - 54 Ci N/D N/D N/D 1.66E-07 Cobalt - 58 Ci N/D N/D 1.32E-06 5.55E-07 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D 5.14E-06 5.85E-07 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 (01/13 - 12/13)

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 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 Other (Specify)

Chromium-51 (Tl/2 > 8 days) Ci N/D N/D 1.45E-06 N/D Zirconium-95(T1/2 > 8days) Ci N/D N/D 1.011E-06 N/D Niobium-95 (Tl/2 > 8days) Ci N/D N/D 3.08E-06 N/D Silver-110m (Tl/2 > 8days) Ci N/D N/D N/D N/D Total for Period (Tl/2 > 8 days) Ci N/D N/D N/D NID Total for Period (Tl/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 GROSS ALPHA: Ci 4.04E-07 2.27E-07 N/D N/D TRITIUM: Ci 6.62E+00 2.06E+00 3.91E+00 1.07E-03 CARBON-14 Ci N/D 3.09E+00 2.64E+00 5.79E-02

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/13 - 12/13)

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 1.84E-03 4.85E-03 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 5.61E-12 8.34E-12
3. Percent of applicable limit (T.S.)  % 5.44E-05 9.54E-06 B. Tritium:
1. Total release activity. Curies 4.08E+02 2.65E+02 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 1.24E-06 4.55E-07
3. Percent of applicable limit (T.S.)  % 1.24E-02 4.55E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies O.OOE+00 O.OOE+00 2.OOE+01
2. Average diluted concentration during the period. 1Ci/ml O.OOE+00 O.OOE+00
3. Percent of applicable limit (T.S.)  % O.OOE+00 O.OE+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies O.OOE+00 O.OOE+00 2.OOE+01 E. Volume of waste released: (prior to dilution). Liters 1.1 8E+08 8. 52E+07 3.OOE+00 F. Total volume of dilution water used during the period. Liters 3.28E+11 5.82E+11 3.OOE+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/13 - 12113)

Page 2 of 2 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 7.21 E-03 6.87E-03 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 9.43E-12 9.50E-12
3. Percent of applicable limit (T.S.)  % 2.69E-05 3.08E-06 B. Tritium:
1. Total release activity. Curies 4.69E+02 1.38E+02 2.OOE+01
2. Average diluted concentration during the period. ltCi/ml 6.13E-07 1.91 E-07
3. Percent of applicable limit (T.S.)  % 6.13E-03 1.91 E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies 7.14E-04 O.OOE+00 2.OOE+01
2. Average diluted concentration during the period. laCi/ml 9.34E-13 O.OOE+00
3. Percent of applicable limit (T.S.)  % 4.67E-07 O.OOE+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies O.OOE+00 O.OOE+00 2.OOE+01 E. Volume of waste released: (prior to dilution). Liters 9.65E+07 1.03E+08 3.OOE+00 F. Total volume of dilution water used during the period. Liters 7.65E+11 7.23E+11 3.OOE+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/13 - 12/13)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci N/D 3.46E-05 N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 8.37E-05 2.94E-03 N/A N/A Cobalt - 60 Ci 8.30E-04 1.82E-03 N/A N/A Strontium - 89 Ci N/D N/D N/A N/A Strontium - 90 Ci N/D N/D N/A N/A Niobium - 95 Ci N/D N/D N/A N/A Ruthenium - 106 Ci N/D N/D N/A N/A Silver - 110m Ci 8.59E-04 3.72E-05 N/A N/A Iodine- 131 Ci N/D N/D N/A N/A Iodine - 133 Ci N/D N/D N/A N/A Cesium - 134 Ci N/D N/D N/A N/A Cesium- 137 Ci N/D N/D N/A N/A Barium-Lathanum - 140 Ci N/D N/D N/A N/A Cerium - 141 Ci N/D N/D N/A N/A Antimony-124 Ci N/D 1.35E-05 N/D N/A Niickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A N/A Antimony-125 Ci 6.66E-05 N/D N/A N/A Total for Period Ci 1.84E-03 4.85E-03 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/13 - 12113)

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 N/D N/D N/A N/A Xenon - 133m Ci N/D N/D N/A N/A Xenon - 135 Ci N/D N/D N/A N/A Xenon- 135m Ci N/D N/D N/A N/A Other (Specify) Ci N/D N/D N/A N/A Krypton-88 ( T1/2 < 8 days) Ci N/D N/D N/A N/A Krypton-85 (Tl/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 4.08E+02 2.65E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

M--.

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01113 - 12113)

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 1.26E-04 1.59E-05 N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 3.62E-03 5.42E-03 N/A N/A Cobalt - 60 Ci 2.90E-03 1.23E-03 N/A N/A Strontium - 89 Ci N/D NID N/A N/A Strontium - 90 Ci N/D N/D N/A N/A Niobium - 95 Ci 1.88E-04 N/D N/A N/A Ruthenium- 106 Ci N/D N/D N/A N/A Silver - 110m Ci 2.09E-04 8.58E-05 N/A N/A Iodine - 131 Ci N/D N/D N/A N/A Iodine - 133 Ci NID N/D N/A N/A Cesium - 134 Ci 3.84E-05 N/D N/A N/A Cesium- 137 Ci 1.30E-04 N/D N/A N/A Barium-Lathanum - 140 Ci N/D N/D N/A N/A Cerium - 141 Ci N/D N/D N/A N/A Chromium-51 Ci N/D 1.25E-04 N/A N/A Nickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A N/A Antimony-122 (T1/2 < 8 days) Ci N/D N/D N/A N/A Antimony-125 (T1/2 > 8 days) Ci N/D N/D N/A N/A Antimony-124 (Tl/2 > 8 days) Ci N/D N/D N/A N/A Tellurium-125m (T1/2 > 8 days) Ci N/D Total for Period Ci 7.21E-03 6.88E-03 N/A N/A

v TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01113 - 12/13)

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 7.14E-04 N/D N/A N/A Xenon- 133m Ci N/D N/D N/A N/A Xenon- 135 Ci N/D N/D N/A N/A Xenon - 135m Ci N/D N/D N/A N/A Other (Specify)

Argon - 41 (Tl/2 < 8 days) Ci N/D N/D N/A N/A Krypton - 85 (Tl/2 > 8 days) Ci N/D N/D N/A N/A Total for Period Ci 7.14E-04 N/D N/A N/A Tritium Ci 4.69E+02 1.38E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-13 THROUGH 12-31-13 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 1.68E+01 2.50E+01 evaporator bottoms, etc., Ci 5.96E+01 2.50E+01
b. Dry compressible waste, contaminated m3 3.83E+02 ** 2.50E+01 equipment, etc., Ci 2.64E+00 2.50E+01
c. Irradiated components, control rods, m3 0.OOE+00 2.50E+01 etc., Ci 0.OOE+00 2.50E+01
d. Other (describe)

Used oil/Blast media/Sewage/Gravel m3 7.90E-01

  • 2.50E+01 Dessicant/Soil/Construction debris Ci 1.17E-03 2.50E+01 Animal Carcasses
2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Ni-63 4.70E+01 2.80E+01 2.50E+01 Co-60 2.25E+01 1.34E+01 2.50E+01 Cs-137 2.03E+01 1.21E+01 2.50E+01 Cs-134 4.01E+00 2.39E+00 2.50E+01 Co-58 1.1OE+00 6.54E-01 2.50E+01 Fe-55 8.54E-01 5.09E-01 2.50E+01 Ni-59 7.22E-01 4.30E-01 2.50E+01 Mn-54 6.94E-01 4.14E-01 2.50E+01 C-14 5.41E-01 3.22E-01 2.50E+01 Cr-51 4.55E-01 2.71E-01 2.50E+01
b. Co-60 4.14E+01 1.09E+00 2.50E+01 Cr-51 1.17E+01 3.09E-01 2.50E+01 Fe-55 1.07E+01 2.82E-01 2.50E+01 Co-58 1.06E+01 2.80E-01 2.50E+01 Nb-95 8.28E+00 2.18E-01 2.50E+01 Zr-95 5.OOE+00 1.32E-01 2.50E+01 Cs-137 4.94E+00 1.30E-01 2.50E+01 Mn-54 4.67E+00 1.23E-01 2.50E+01 Ni-63 1.43E+00 3.77E-02 2.50E+01 Fe-59 6.81E-01 1.80E-02 2.50E+01 Zn-65 3.14E-01 8.27E-03 2.50E+01
c. NONE
d. H-3 5.41E+01 6.32E-04 2.50E+01 Fe-55 2.40E+01 2.80E-04 2.50E+01 Co-60 1.27E+01 1.48E-04 2.50E+01 C-14 2.37E+00 2.76E-05 2.50E+01 Co-58 1.75E+00 2.04E-05 2.50E+01 Cr-51 1.31 E+00 1.53E-05 2.50E+01 Nb-95 1.06E+00 1.24E-05 2.50E+01 Mn-54 7.87E-01 9.18E-06 2.50E+01 Ni-63 7.38E-01 8.61E-06 2.50E+01 Zr-95 7.18E-01 8.38E-06 2.50E+01 Cs-137 2.32E-01 2.71E-06 2.50E+01 Fe-59 9.51 E-02 1.11E-06 2.50E+01 Zn-65 6.77E-02 7.90E-07 2.50E+01 Co-57 1.01E-02 1.18E-07 2.50E+01 Ce-144 3.79E-03 4.42E-09 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01-01-13 THROUGH 12-31-13 Page 2 of 2

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1 Truck Clive, UT 1 Truck Erwin, TN 8 Truck Oak Ridge, TN 3 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A (3) shipments containing resins were shipped to a licensed waste processor for processing (1) shipment containing resins was shipped to a licensed waste processor for disposal (1) shipment containing sludge was shipped to a licensed waste processor for processing (4) shipments containing mechanical filters were shipped to a licensed waste processor for processing (8) 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 disposal (2) shipments containing biological material were shipped to a licensed waste processor for processing (1) shipment containing charcoal was shipped to a licensed waste facility for disposal (1) shipment containing. asbestos was shipped to a licensed waste facility for disposal

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/13- 12/13)

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 4

r%. rn A. *r+ ft.* . rf ft. .ý .- r T~nfa Total Body Dose (mrem) 1.44E-1 9.35E-2 1.67E-1 4.88E-2 4.53E-1 Critical Organ Dose (mrem) 1.44E-1 9.34E-2 1.69E-1 4.88E-2 4.55E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 3.44E-6 5.23E-5 5.08E-4 7.74E-3 8.30E-3 Noble Gas Beta Dose (mrad) 3.67E-4 9.54E-4 1.44E-3 2.74E-3 5.50E-3 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T% > 8 days (including C-14) (mrem) 8.99E-2 2.78E-1 4.47E-1 3.80E-1 1.20E+0 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T%/ > 8 days (excluding C-14) (mrem) 3.74E-3 2.21 E-4 1.07E-1 1.09E-3 1.12E-1 6

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/13 - 12/13)

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 made to the ODCM in 2013.

7

ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01/13 - 12/13)

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 2013.

8

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/13 - 12/13)

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.

There was no radioactive liquid and/or gaseous effluent monitoring instrumentation out-of-service for more than 30 consecutive days during 2013.

9

ATTACHMENT 6 UNPLANNED RELEASES (01/13 - 12/13)

As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

There were neither any unplanned releases during 2013 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted areas nor were there any spills or leaks that required voluntary communication under the criteria of the NEI Ground Water Protection Initiative, NEI 07-07. Elevated results indicated in 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.

10

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/13 - 12/13)

Gaseous Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope aCi/mL- Ci/mL Krypton - 87 1.OOE-4 2.50E-8 7.50E-8 Krypton - 88 1.OOE-4 1.OOE-7 4.50E-7 Xenon - 133 1.OOE-4 5.OOE-8 1.OOE-7 Xenon - 133m 1.OOE-4 2.OOE-7 4.OOE-7 Xenon - 135 1.OOE-4 2.OOE-8 5.OOE-8 Xenon - 135m 1.OOE-4 5.OOE-8 2.OOE-7 Xenon - 138 1.OOE-4 1.OOE-7 5.OOE-7 Iodine - 131 1.OOE-12 6.OOE-14 - 1.OOE-13 Iodine - 133 1.OOE-10 1.OOE-14 - 7.OOE-13 Manganese - 54 1.OOE-11 6.OOE-14 - 8.OOE-14 Cobalt - 58 1.OOE-11 5.OOE-14 - 8.OOE-14 Iron - 59 1.OOE-11 9.OOE-14 - 2.OOE-13 Cobalt - 60 1.OOE-11 5.OOE-14 - 2.OOE-13 Zinc - 65 1.OOE-11 9.OOE-14 - 3.OOE-13 Strontium - 89 1.OOE-11 3.OOE-14 - 8.OOE-12 Strontium - 90 1.00E-11 3.OOE-15 - 9.OOE-12 Molybdenum - 99 1.00E-11 7.OOE-14 - 2.OOE-13 Cesium - 134 1.OOE-11 5.OOE-14 - 1.OOE-13 Cesium - 137 1.OOE-11 5.OOE-14 - 8.OOE-14 Cerium - 141 1.OOE-11 5.OOE-14 - 2.OOE-13 Cerium - 144 1.OOE-11 2.OOE-13 - 5.OOE-13 Gross Alpha 1.OOE-11 7.OOE-15 - 2.OOE-14 Tritium 1.OOE-6 4.OOE-09 - 9.OOE-09 11

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/13 - 12/13)

Liquid Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope aCi/mL-iCi/mL Krypton - 87 1.OOE-5 4.OOE-8 - 1.OOE-7 Krypton - 88 1.OOE-5 1.OOE-7 - 1.00E-6 Xenon - 133 1.OOE-5 7.OOE-8 - 1.50E-7 Xenon - 133m 1.OOE-5 9.OOE-8 - 3.OOE-7 Xenon - 135 1.00E-5 9.OOE-9 5.OOE-8 Xenon - 135m 1.OOE-5 3.00E-8 2.OOE-7 Xenon - 138 1.OOE-5 1.OOE-7 - 1.OOE-6 Iodine - 131 1.00E-6 1.OOE-8 - 5.OOE-8 Manganese - 54 5.00E-7 2.00E-8 - 5.OOE-8 Iron - 55 1.00E-6 3.OOE-7 - 8.OOE-7 Cobalt - 58 5.OOE-7 2.OOE-8 6.OOE-8 Iron - 59 5.00E-7 3.00E-8 - 7.OOE-8 Cobalt - 60 5.OOE-7 1.OOE-8 - 5.50E-8 Zinc - 65 5.OOE-7 3.00E-8 - 6.00E-8 Strontium - 89 5.OOE-8 1.OOE-8 - 4.OOE-8 Strontium - 90 5.OOE-8 5.OOE-9 - 9.OOE-9 Molybdenum - 99 5.OOE-7 2.00E-8 - 6.OOE-8 Cesium - 134 5.OOE-7 2.OOE-8 - 5.OOE-8 Cesium - 137 5.OOE-7 3.OOE-8 - 6.OOE-8 Cerium - 141 5.OOE-7 3.OOE-8 - 9.OOE-8 Cerium - 144 5.OOE-7 1.OOE-7 - 5.OOE-7 Gross Alpha 1.OOE-7 2.OOE-8 - 7.OOE-8 Tritium 1.OOE-5 2.OOE-6 5.OOE-6 12

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13)

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 of NEI 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 outside the restricted area on a quarterly basis and analyzed by Teledyne Brown Engineering Laboratories. Additional samples are obtained from wells located inside the restricted area and analyzed by Teledyne Brown. Samples are obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Finally, samples may be obtained more frequently than normal, if required. These samples may be analyzed on-site or by a vendor such as Teledyne Brown. 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 2013. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "N/A" indicates a sample analysis was not performed for that sample. An "ND" 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.

13

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13)

Ist Quarter 2013 Fe.55 1 Ni.63(1 ) Aa 1

Sample H3') Gamma -Emitting 1131(1) SrA89190( RU-h Sample Date Media Particulates -(1)

GWP-6 01/03/13 WATER 12540 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/09/13 WATER 12410 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/17/13 WATER 17680 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/24/13 WATER 33896 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/30/13 WATER 41117 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/06/13 WATER 43077 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/14/13 WATER 40495 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Yard Drains 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Yard drains 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A Discharge Canal Yard 02/15/13 WATER 3162 N/A N/A N/A N/A N/A N/A N/A Drains Subsurface drains 02/15/13 WATER < 1297 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/21/13 WATER 41126 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/28/13 WATER 39986 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/07/13 WATER 27410 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/14/13 WATER 38635 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/20/13 WATER 44356 N/A N/A N/A N/A N/A N/A N/A GWP-6 2 03/20/13 WATER 41,900 ND ND N/A N/A N/A N/A N/A PZ-2 03/20/13 WATER Insufficient volume to sample PZ-1 03/20/13 WATER Insufficient volume to sample GWP-3 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/20/13 WATER <1284 N/A N/A N/A N/A N/A N/A N/A 2

PZ-3 03/20/13 WATER <944 ND ND N/A N/A N/A N/A N/A GWP-4 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A GWP-5A 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A GWP-7 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A GWP-8 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A GWP-9 03/20/13 WATER < 1284 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/27/13 WATER 42559 N/A N/A N/A N/A N/A N/A N/A BTW-1(2) 03/28/13 WATER <817 N/A N/A N/A N/A N/A N/A N/A BTW-2(2) 03/28/13 WATER <821 N/A N/A N/A N/A N/A N/A N/A BTW-4(21 03/28/13 WATER <823 N/A N/A N/A N/A N/A N/A N/A TT'W-1 Well abandoned in place, pending decommissioning 14

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 1 st Quarter 2013 1

Sample Date Sample H-3(1) Gamma -Emitting 1-131 (') Sr-Particulates*1 ) 89/90(0) Fe-55( 1 ) Ni-63 1 )

-Alpha Media TRU(A) Pu'241(1)

TTW-2(2) 03/28/13 WATER <824 N/A N/A N/A N/A N/A N/A N/A IfW-3(2) 03/28/13 WATER <822 N/A N/A N/A N/A N/A N/A N/A TTW-4 Well abandoned in place, pending decommissioning TTW-5 (2) 03/28/13 WATER <821 N/A N/A IN/A I N/A I N/A I N/A N/A (1) pCi/L (2) Vendor Analysis 15

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 2 nd Quarter 2013 1

Sample H.3) Gamma -Emitting 1131(1) Sr.89/90lph Fe.55a, Ni.63(, AhU41 Sample Date Media Particulates() -/ TRUt1 (

GWP-6 04/03/13 WATER 40,991 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 04/03/13 WATER < 1287 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/11/13 WATER 38,392 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/18/13 WATER 39,491 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/24/13 WATER 37,523 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 04/24/13 WATER <1373 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/01/13 WATER 47,342 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/09/13 WATER 43,604 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/16/13 WATER 40,113 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Yard Drains 05/16/13 WATER <1360 ND N/A N/A N/A N/A N/A N/A U-2 Intake Yard drains 05/16/13 WATER <1360 N/A N/A N/A N/A N/A N/A N/A Discharge Canal Yard Drana 05/16/13 WATER 3865 N/A N/A N/A N/A N/A N/A N/A Drains _________

Subsurface drains 05/21/13 WATER <1376 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/22/13 WATER 46,495 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 05/22/13 WATER <1301 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/30/13 WATER 46,126 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/06/13 WATER 46,338 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/12/13 WATER 43,108 N/A N/A N/A N/A N/A N/A N/A 2

GWP-6 06/12/13 WATER 36,400 ND ND N/A N/A N/A N/A N/A PZ-2 06/12/13 WATER Insufficient volume to sample PZ-1 06/12/13 WATER Insufficient volume to sample GWP-3 06/12/13 WATER < 1343 N/A N/A N/A N/A N/A N/A N/A GWP-3(2) 06/12/13 WATER <1870 N/A N/A N/A N/A N/A N/A N/A PZ-3 06/12/13 WATER < 1343 N/A N/A N/A N/A N/A N/A N/A PZ-3 2 06/12/13 WATER 1410 ND ND N/A N/A N/A N/A N/A GWP-4 06/12/13 WATER < 1343 N/A N/A N/A N/A N/A N/A N/A GWP-4(2) 06/12/13 WATER <827 N/A N/A N/A N/A N/A N/A N/A 16

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01113 - 12/13) 2 nd Quarter 2013 Sample Date Sample H.3(1 ) Gamma -Emitting 1.131) Sr- AlTRUpha Media Particulates() 1 89/90(,) Fe-55(1 ) Ni-63( Alpha Pu-241()

GWP-5A 06/12/13 WATER < 1343 N/A N/A N/A N/A N/A N/A N/A 2

GWp_5A( ) 06/12/13 WATER <816 N/A N/A N/A N/A N/A N/A N/A GWP-7 06/12/13 WATER <1343 N/A N/A N/A N/A N/A N/A N/A GWP-7(2 ) 06/12/13 WATER <826 N/A N/A N/A N/A N/A N/A N/A GWP-8 06/12/13 WATER <1343 N/A N/A N/A N/A N/A N/A N/A 2

GWP-8( ) 06/12/13 WATER <819 N/A N/A N/A N/A N/A N/A N/A GWP-9 06/12/13 WATER <1343 N/A N/A N/A N/A N/A N/A N/A GWP-9(2 ) 06/12/13 WATER <824 N/A N/A N/A N/A N/A N/A N/A BTW-19(2) 6/19/13 WATER <798 ND ND N/A N/A N/A N/A N/A BTW-1(2) 6/19/13 WATER <804 ND ND N/A N/A N/A N/A N/A BTW-4(2) 6/19/13 WATER <800 ND ND N/A N/A N/A N/A N/A TTW_1 Well abandoned in place, pending decommissioning TTW-1(2) 6/19/13 WATER [ ND ND iN/A dN/A N/A N/A N/A TTW-3 (2) 6/19/13 WATER <786 ND ND N/A N/A N/A N/A N/A TTW-4 Well abandoned in place, pending decommissioning TTW-5(2) 6/19/13 WATER <792 ND ND N/A N/A N/A N/A N/A GWP-6 06/20/13 WATER 50,833 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/27/13 WATER 49,333 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L (2) Vendor Analysis 17

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 3rd Quarter 2013 Sample Date Sample 1

H.3 ) Gamma -Emitting 1.131(1) Sr-89/90O) Fe-55(1 ) Ni-63(1) Alpha Pu-241()

Media 1

Particulates( ) TRU(1 )

GWP-6 07/03/13 WATER 54,541 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/10/13 WATER 48,977 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/18/13 WATER 53,887 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/25/13 WATER 57,185 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/01/13 WATER 57,626 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/08/13 WATER 79,559 N/A N/A N/A N/A N/A N/A N/A GWP-5A 08/09/13 WATER <1355 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/09/13 WATER 73,252 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Yard Drains 08/15/13 WATER <1650 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Yard drains 08/15/13 WATER <1650 N/A N/A N/A N/A N/A N/A N/A Discharge Canal Yard 08/15/13 WATER <1650 N/A N/A N/A N/A N/A N/A N/A Drains Subsurface drains 08/14/13 WATER <1630 N/A N/A N/A N/A N/A N/A N/A GWP-4 08/15/13 WATER <1370 N/A N/A N/A N/A N/A N/A N/A PZ-3 08/15/13 WATER <1370 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/15/13 WATER 39,856 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 08/21/13 WATER <1338 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 08/21/13 WATER <1338 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 08/21/13 WATER <1338 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 08/21/13 WATER <1338 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 08/21/13 WATER <1338 ND N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 08/21/13 WATER <1338 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/22/13 WATER 39,113 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/29/13 WATER 63,874 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/05/13 WATER 76,059 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/12/13 WATER 51,532 N/A N/A N/A N/A N/A N/A N/A PZ-3(1) 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A PZ-3(2) 09/17/13 WATER 1990 N/A N/A N/A N/A N/A N/A N/A GWP-3 09/18/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A GWP-4 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A GWP-5A 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A 1

GWP-6( ) 09/17/13 WATER 47,356 N/A N/A N/A N/A N/A N/A N/A GWP-6(2) 09/17/13 WATER 49,100 N/A N/A N/A N/A N/A N/A N/A GWP-7 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A GWP-8 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A GWP-9 09/17/13 WATER <1331 N/A N/A N/A N/A N/A N/A N/A PZ-1 09/18/13 WATER Insufficient volume to sample PZ-2 09/18/13 WATER Insufficient volume to sample 18

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 3 rd Quarter 2013 1

Sample Date Sample H-3( ) Gamma -Emitting 1.131(l) Sr- Alpha Pu-241()

Media Particulates(1 ) 89190(1) Fe'55°' Ni'63°) Ap P 1)

BTW-1(2) 09/16/13 WATER <980 ND ND N/A N/A N/A N/A N/A BTW-2(2) 09/17/13 WATER <984 ND ND N/A N/A N/A N/A N/A BTW-4(2) 09/16/13 WATER <982 ND ND N/A N/A N/A N/A N/A T-W-1 09/16/13 Well abandoned in place, pending decommissioning TTW.2(2) 09/16/13 WATER <962 ND ND N/A N/A N/A N/A N/A TTW3 2

() 09/16/13 WATER [<969 J ND ND jN/A JN/A JN/A JN/A IN/A "I-/W-4 09/16/13 Well abandoned in place, pending decommissioning TTW.5(2 ) 09/16/13 WATER <953 ND ND N/A N/A N/A N/A N/A GWP-6 09/26/13 WATER 31,923 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 09/27/13 WATER <1410 N/A N/A N/A N/A N/A N/A N/A ISFSIWELL#1( 2 ) IND08/01/13 WATER <776 ND ND ND ND ND ND ISFSI WELL #2(2) 08/01/13 WATER <776 ND ND ND ND ND ND ND (1) pCi/L (2) Vendor Analysis 19

q ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 4 th Quarter 2013 Gamma -

Sample Date Sample H131) Emitting 1-131 Sr-89/90 Fe-55 Ni-63 TRA Pu-241 Particulates GWP-6 10/03/13 WATER 26982 N/A N/A N/A N/A N/A N/A N/A GWP-6 10/09/13 WATER 18459 N/A N/A N/A N/A N/A N/A N/A GWP-6 10/17/13 WATER 10878 N/A N/A N/A N/A N/A N/A N/A GWP-6 10/24/13 WATER 5180 N/A N/A N/A N/A N/A N/A N/A GWP-6 10/31/13 WATER 3986 N/A N/A N/A N/A N/A N/A N/A GWP-6 11/07/13 WATER 2964 N/A N/A N/A N/A N/A N/A N/A GWP-6 11/14/13 WATER 1991 N/A N/A N/A N/A N/A N/A N/A U-1 INTAKE STORM 11/14/13 WATER < 1670 N/A N/A N/A N/A N/A N/A N/A DRAINS U-2 INTAKE STORM 11/14/13 WATER < 1670 N/A N/A N/A N/A N/A N/A N/A DRAINS DISCHARGE CANAL STORM 11/14/13 WATER < 1670 N/A N/A N/A N/A N/A N/A N/A STORM DRAINS I SUBSURFACE 11/14/13 WATER < 1670 N/A N/A N/A N/A N/A N/A N/A DRAINS U-1 Mat Sump 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A East U-1 Mat Sump 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A South U-2 Inside Mat 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A U-2 Outside 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A Mat AB/FBd U-i Sump U-M 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A U-2AB/FB 11/15/13 WATER <1299 N/A N/A N/A N/A N/A N/A N/A GWMS GWP-6 11/21/13 WATER 1410' N/A N/A N/A N/A N/A N/A N/A GWP-6 11/27/13 WATER <1319 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/05/13 WATER <1297 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/12/13 WATER 2860 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/13/13 WATER 7333 N/A N/A N/A N/A N/A N/A N/A TTW-1 12/16/13 WATER Insufficient volume tosample NA /

TTW-2 (2) 12/16/13 WATER <847 ND <MDA N/A N/A N/A N/A N/A TTW-3 (2) 12/16/13 WATER <7845 ND ND N/A N/A N/A N/A N/A TTW-4 12/16/13 WATER Insufficient volume to sample TTW-3(2) 12/16/13 WATER < 861 ND ND N/A N/A N/A N/A N/A BTW-1 (2) 12/16/13 WATER <856 ND <MDA N/A N/A N/A N/A N/A BTW-2 (2) 12/16/13 WATER < 847 ND ND N/A N/A N/A N/A N/A BTW-4 (2) 12/16/13 WATER <843 ND <MDA N/A N/A N/A N/A N/A (2) 12/16/13 WATER <1843 ND NDA N/A N/A N/A N/A N/A 12/17/13 WATER <1361 ND N/A N/A N/A N/A N/A N/A P- 12/17/13 WATER <1361 ND N/A N/A N/A N/A N/A N/A

- 12/17/13 WATER <1361 ND N/A N/A N/A N/A N/A N/A 12/17/13 12/17/13 WATER WATER <1361

<1361 ND ND N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 20

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/13 - 12/13) 4 th Quarter 2013 Gamma - Alph Sample Date Sample H-3 Emitting 1-131 Sr-89/90 Fe-55 Ni-63 a Pu-241 Particulates TRU GWP-18 12/17/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-18(2) 12/17/13 WATER 2210 N/A N/A N/A N/A N/A N/A N/A PZ-1 12/18/13 WATER Insufficient Volume to sample PZ-2 12/18/13 WATER Insufficient Volume to sample PZ-3 12/18/13 WATER 2824 N/A N/A N/A N/A N/A N/A N/A PZ-3(2) 12/18/13 WATER 3730 ND ND ND ND ND N/A ND GWP-4 12/18/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-5A 12/18/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/18/13 WATER 23243 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/18/13 WATER 20900 ND <MDA <MDA <MDA <MDA N/A <MDA GWP-3 12/19/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/19/13 WATER 37252 N/A N/A N/A N/A N/A N/A N/A GWP-7 12/19/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-8 12/19/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-9 12/19/13 WATER <1361 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/30/13 WATER 51441 N/A N/A N/A N/A N/A N/A N/A (1) Sample results in pCi/L (2) Vendor Analysis 21

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/13 - 12/13)

Carbon-1 4, 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 ifso, 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 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 29.2 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 25.7 Ci of C-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 of 70% organic and 30% C02 in its calculations.

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,A V 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 1.1 2E-1 mrem from the inhalation pathway, or 7.48E-03% TS of the 1500 mrem/yr dose rate limit and 9.72E-1 mrem from the ingestion pathway or 3.24E+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yr per unit. In both cases the critical organ was determined to be the child's bone.

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Miscellaneous There was one entry,13-001, on the Annual Effluent Release Report Log for 2013. There were typographical errors where incorrect dates, 01/11-12/11 versus 01/12-12/12 were entered on gaseous and liquid effluent summary tables 1A and 2A of the 2012 Annual Effluent Release Report.

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