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Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2 Independent Spent Fuel Storage Installation -Annual Radioactive Effluent Release Report
	ML16125A495
Person / Time
Site:	North Anna
Issue date:	04/26/2016
From:	Gerald Bichof; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML16125A506	List: ML16125A495; ML16125A497; ML16125A498; ML16125A499; ML16125A500;
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 2016 United States Nuclear Regulatory Commission Serial No.16-111 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. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2015 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, plei:ise contact Robin Klearman at (540) 894-2436.

Very truly yours, Gt~?c~-6 Site Vice President Enelosure Commitments made in this l~tter: None cc: U. S. Nuclear Regulatory Commission Region II *

Marquis One Tower 245 P,eachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nucl.ear rylateri~*I Safety and Safeguards U.S. Nuclear 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, 2015 TO DECEMBER 31, 2015)

PREPARED BY:.~-~-=-i\'r.i;.......i.__\lJ_\~'-1-\)-V..~~~~

-tld)0yf1;fa;ants, Jr.

Supervisor Radiological Analysis and Instrumentation REVIEWED BY: --------U. A~"- M ~

Aziz A. Maly Supervisor Health Physics Technica! Services APPROVED BY: ~ Robert B. Evans, Jr.

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, 2015 TO DECEMBER 31, 2015 IND EX Section No. Subject Page 1 EXECUTIVE

SUMMARY

................................... 1-2 2 PURPOSE AND SCOPE................................... 2 3 DISCUSSION.................................................. 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 Systems.................................................. 8 lnoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation........................................ 9 Unplanned Releases................................. 10 Lower Limits of Detection (LLD) for Effluent Sample Analysis........................... 11 - 12 Results of Ground Water Protection Initiative Sample Analysis..................................... 13 - 22 Carbon-14 Calculations............................. 23 - 24 Miscellaneous Annual Effluent Release Report Log............ 25

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 2015 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, 2015, 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 2015.

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 2015 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 2.38E-1 mrem, which is 3.97% of the dose limit and the critical organ dose due to liquid effluents was 2.39E-1 mrem, which is 1.20% of the dose limit.

b. The air dose due to noble gases was 4.22E-4 mrad gamma, which is 2.11 E-3% of the annual gamma dose limit, and 2.48E-4 mrad beta, which is 6.20E-4% 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 1.68 mrem, which is 5.60% 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 1.01 E-2 mrem, which is 3.37E-2% 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 four revisions to the Offsite Dose Calculation Manual during this reporting period.

1

1.0 EXECUTIVE

SUMMARY

(cont.)

Based on the levels of radi~activity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1and2 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 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) forthe 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 irioperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report.

2

<(' *.

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-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 if C-14 is included an~ 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 fo_r radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 µCi/ml.

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

The annual and quarterly dos*es, 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 particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131 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 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 Gastrointestinal- Lower Large Intestine ( Gl-LLI). 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 rad.ioactive 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 Attachme'nt 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 ODCM.

There were no new sampling locations added. There were five (5) changes made to the land use census in 2015. The nearest garden location in the N sector changed from 1. 78 miles to 1. 76 miles. The nearest ga'rden location in the S sector changed from 1.02 miles to 1.14 miles. Physical addresses for the nearest garden locations in the SSE and WNW sectors changed but distances from station were unchanged. Also, there are no longer meat animals in the WSW sector. Meat animals previously in WSW sector at 2.22 miles distance were no longer present and no other meat animals were found in the WSW sector within a five mile radius of the station.

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 148, 15, 16, 23 and 26 from January through April 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 optained 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 (01/15 - 12/15)

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 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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

A. Fission and Activiation Gases

1. Total Release Curies 2.38E-01 1.82E-01 1.80E+1

2. Average Release Rate For Period µCi/sec 3.03E-02 2.31E-02

8. Iodines:

1. Total lodine-131 Release Curies O.OOE+OO O.OOE+OO 2.80E+1

2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO

c. Particulate {T112 > 8 da)ls}:

1. Total Particulate (T112 > 8 days) Release Curies 7.56E-06 O.OOE+OO 2.80E+1

2. Averaqe Release Rate For Period µCi/sec 9.62E-07 O.OOE+OO

3. Gross Alpha Radioactivity Release Curies 6.38E-08 1.77E-07 D. Tritium:

1. Total Release Curies 3.64E+OO 2.13E+OO 3.10E+1

2. Average Release Rate For Period µCi/sec 4.68E-01 2.71E-01 E. Carbon-14

1. Total Release Curies 7.13E+OO 6.22E+OO

2. Average Release Rate For Periocl µCi/sec 9.0?E-01 7.91 E-01 F. Percentage Of Technical Specification Limits

1. Total Body Dose Rate % 2.79E-06 3.01E-04

2. Skin Dose Rate % 1.09E-06 7.36E-05

3. Critical Organ Dose Rate (with C-14) % 3.41 E-03 1.47E-02 Critical Organ Dose Rate (without C-14) % 2.64E-04 9.96E-05

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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

A. Fission and Activiation Gases

1. Total Release Curies 2.28E-01 1.64E-01 1.80E+1

2. Average Release Rate For Period µCi/sec 2.87E-02 2.06E-02 B. Iodines:

1. Total lodine-131 Release Curies O.OOE+OO O.OOE+OO 2.80E+1

2. Average Release Rate For Periocl µCi/sec O.OOE+OO O.OOE+OO

c. Particulate {T112 > 8 da~s}:

1. Total Particulate (Tt12 > 8 days) Release Curies O.OOE+OO O.OOE+OO 2.80E+1

2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO

3. Gross Alpha Radioactivity Release Curies 2.97E-07 5.39E-08 D. Tritium:

1. Total Release Curies 6.13E+OO 3.25E+OO 3.10E+1

2. Average Release Rate For Periocj µCi/sec 7.71E-01 4.09E-01 F. Carbon-14

1. Total Release Curies 7.80E+OO 5.62E+OO

2. Average Release Rate For Period µCi/sec 9.81E-01 7.0?E-01 F. Percentage Of Technical Specification Limits

1. Total Body Dose Rate % 1.46E-05 1.48E-06

2. Skin Dose Rate % 1.0BE-05 5.77E-07

3. Critical Organ Dose Rate (with C-14) % 1.53E-02 2.22E-03 Critical Organ Dose Rate (without C-14) % 4.72E-04 1.86E-04

TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/15 - 12115)

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 1.52E-01 3.05E-02 8.00E-02 N/D Xenon - 133m Ci N/D N/D N/D N/D Xenon -135 Ci N/D N/D 2.11 E-04 N/D Xenon -135m Ci N/D N/D N/D N/D 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 5.19E-03 N/D N/D Total For Period Ci 1.52E-01 3.57E-02 8.02E-02 N/D Iodines:

Iodine -131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine -133 Ci N/D N/D N/D N/D.

lodine-134 Ci N/D NID N/D NID Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D NID N/D Particulates:

Manganese - 54 Ci N/D ' NID N/D N/D Cobalt - 58 Ci N/D NID NID N/D Iron - 59 Ci N/D NID N/D N/D Cobalt-60 Ci NID N/D N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D NID N/D N/D Strontium - 90 Ci NID N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium-136 Ci NID N/D N/D N/D Cesium -137 Ci N/D NID N/D N/D

TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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-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 8.12E-01 1.16E+OO 7.84E-03 6.0SE-05 CARBON-14 Ci 5.20E+OO 1.22E+OO 1.72E+OO N/D

TABLE 18 NORTH ANNA POWER STATION ...

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci 8.39E-02 1.64E-01 N/D N/D Xenon -133m Ci N/D N/D N/D N/D Xenon -135 Ci N/D N/D N/D 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 N/D N/D Total For Period Ci 8.39E-02 1.64E-01 N/D N/D Iodines:

Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 N/D N/D N/D N/D Iodine - 133 Ci N/D 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 N/D Total For Period Ci N/D N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt- 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc- 65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver-110m Ci N/D N/D N/D N/D Cesium-134 Ci N/D N/D N/D N/D Cesium-137 Ci N/D N/D N/D N/D

TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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 1.03E-10 N/D N/D TRITIUM: . Ci 8.88E-01 1.31E+OO 3.51 E-04 N/D CARBON-14 Ci 2.87E+OO 5.62E+OO N/D N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01115- 12/15)

Page 1 of 4 CONTINUOUS MODE BATC!-f 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 5.59E-06 7.79E-05 Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon -133 Ci N/D N/D 5.32E-03 1.91 E-03 Xenon -133m Ci N/D N/D 6.81E-05 N/D Xenon -135 Ci N/D N/D 6.38E-04 6.85E-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 1.34E-05 1.43E-01 Total For Period Ci N/D N/D 6.05E-03 1.46E-01 Iodines:

Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D 1.42E-07 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 N/D 1.42E-07 N/D Particulates:

Manganese - 54 Ci - N/D N/D N/D N/D Cobalt -58 Ci 2.51 E-06 N/D 2.55E-07 N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D 2.47E-06 N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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 6.18E-07 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 Niobium-95 Ci N/D N/D 1.70E-06 N/D Zirconium-95 Ci N/D N/D N/D N/D Rubidium-88 (T1/2 < 8 days) Ci N/D N/D N/D N/D Cerium-143 (T1/2 < 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 (T1/2 > 8 days) Ci 2.51E-06 N/D 5.05E-06 N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci 2.51E-06 O.OOE+OO 5.05E-06 0.00E+OO GROSS ALPHA: Ci 6.38E-08 1.77E-07 N/D N/D TRITIUM: Ci 1.08E+OO . 9.66E-01 1.74E+OO 2.27E-03 CARBON-14 Ci N/D N/D 2.07E-01 5.00E+OO

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/15- 12/15)

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 1.34E-01 N/D Krypton - 85m Ci N/D N/D 1.92E-04 N/D Krypton - 87 Ci N/D N/D 1.49E-04 N/D Krypton - 88 Ci N/D N/D 3.31E-04 N/D Xenon -131m Ci N/D N/D N/D N/D Xenon -133 Ci N/D N/D 2.11 E-03 N/D Xenon -133m Ci N/D N/D 8.08E-05 N/D Xenon-135 Ci N/D N/D 2.28E-03 N/D Xenon -135m Ci N/D N/D 2.21E-04 N/D Xenon-137 Ci N/D N/D N/D N/D Xenon -138 Ci N/D N/D 4.37E-05 N/D Other (Specify) Ci Argon -41 Ci N/D N/D 5.11E-03 9.65E-06 Total For Period Ci N/D N/D 1.45E-01 9.65E-06 Iodines:

Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine -133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci

N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt -58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/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

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/15 - 12/15)

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 (T1/2 > 8 days) Ci N/D N/D N/D N/D Zirconium-95 (T1/2 > 8days) Ci N/D N/D N/D N/D Niobium-95 (T1/2 > 8days) Ci N/D N/D N/D N/D Ru-103 (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 (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period 'ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO GROSS ALPHA: Ci 2.97E-07 5.38E-08* - N/D N/D TRITIUM: Ci 5.06E+OO 1.94E+OO 2.06E+OO 9.09E-01 CARBON-14 Ci N/D N/D 4.93E+OO 3.30E-04

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT-SUMMATION OF ALL RELEASES FOR (01/15 - 12/15)

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 Qross alpha). Curies 1.25E-02 2.15E-03 2.00E+01

2. Average diluted concentration during the period. µCi/ml 4.25E-11 2.93E-12

3. Percent of applicable limit (T.S.) % 3.28E-05 2.52E-06 B. Tritium:

1. Total release activity. Curies 5.88E+02 4.30E+01 2.00E+01

2. Average diluted concentration during the period. µCi/ml 2.00E-06 5.84E-08

- 3. Percent of applicable limit (T.S.) % 2.00E-02 5.84E-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 1.02E+08 1.26E+08 3.00E+OO F. Total volume of dilution water used during the period. Liters 2.94E+11 7.36E+11 3.00E+OO

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/15 - 12/15)

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 gross alpha). Curies 1.27E-03 1.03E-03 2.00E+01

2. Average diluted concentration during the period. µCi/ml 1.45E-12 1.44E-12

3. Percent of applicable limit (T.S.) % 3.03E-06 3.34E-06 B. Tritium:

1. Total release activity. Curies 3.26E+01 1.30E+01 2.00E+01

2. Average diluted concentration during the period. µCi/ml 3.72E-08 1.82E-08

3. Percent of applicable limit (T.S.) % 3.72E-04 1.82E-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 aoolicable limit (T.S.) % O.OOE+OO O.OOE+OO D. Gross Al~ha Radioactiviw:

/

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

dilution). Liters 1.01 E+OS 1.22E+08 3.00E+OO F. Total volume of dilution water used during the period. Liters 8.75E+11 7.15E+11 3.00E+OO

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01115 - 12115)

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 NID NID NIA NIA Iron - 59 Ci NID NID NIA NIA Cobalt- 58 Ci 1.12E-02 1.88E-03 NIA NIA Cobalt- 60 Ci 1.19E-03 2.75E-04 NIA NIA Strontium - 89 Ci NID NID NIA NIA Strontium - 90 Ci NID NID NIA NIA Niobium - 95 Ci NID N/D NIA NIA Antimony-124 Ci 5.22E-05 N/D NIA NIA Silver-110m Ci NID NID NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine - 133 Ci NID NID NIA NIA Cesium -134 Ci NID N/D NIA NIA Cesium -137 Ci NID NID NIA NIA Barium-Lathanum - 140 Ci N/D NID NIA NIA Cerium -141 Ci NID NID NIA NIA Tellurium-125m Ci 4.57E-06 NID NIA NIA Niickel - 63 (T112 > 8.days) Ci NID NID NIA NIA Antimony-125 Ci 1.98E-05 NID NIA NIA Total for Period Ci 1.25E-02 2.16E-03 NIA NIA

TABLE 28 NORTH ANNA POWER STATION ..

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/15 12/15)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon-133 Ci NID NID NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon - 135 Ci NID NID NIA NIA Xenon-135m Ci NID NID NIA NIA Other (Specify) Ci N/D NID NIA NIA Krypton-88 ( T 112 < 8 days) Ci N/D NID NIA NIA Krypton-85 (T112 > 8 days) Ci NID NID NIA NIA Total for Period Ci NID NID NIA NIA Tritium Ci 5.88E+02 4.30E+01 NIA NIA

~

Gross Alpha Ci NID NID NIA NIA

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/15. - 12/15)

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 NID NID NID NIA Iron - 59 Ci NID NID NID NIA Cobalt- 58 Ci 4.05E-04

3.68E-04 NID NIA Cobalt-60 Ci 6.66E-04 6.62E-04 NID NIA Strontium - 89 Ci NID N/D NID NIA Strontium - 90 Ci NID NID NID NIA Niobium- 95 Ci 7.13E-05 NID NID NIA Zirconium - 95 Ci N/D NID NID NIA Silver-110m Ci 1.09E-05 NID NID NIA Iodine -131 Ci NID NID NID NIA Iodine - 133 Ci NID NID NID NIA Cesium-134 Ci NID NID NID NIA Cesium-137 Ci 1.53E-05 NID NID NIA Barium-Lathanum - 140 Ci NID N/D NID NIA Cerium - 141 Ci NID NID NID NIA

Chromium-51 Ci NID N/D NID NIA Nickel - 63 {T112 > 8 days) Ci NID NID NID NIA Antimony-122 {T112 < 8 days) Ci NID NID NID NIA Antimony-125 {T112 > 8 days) Ci 7.78E-05 N/D NID NIA Antimony-124 {T112 > 8 days) Ci NID NID NID NIA Tellurium-125m {T112 > 8 days) Ci 1.80E-05 NID NID NIA Total for Period Ci 1.26E-03 1.03E-03 NID NIA

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/15 - 12/15)

Page 4 of 4 CONTINU.OUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon - 133 Ci N/D N/D N/D N/A Xenon-133m Ci N/D N/D N/D NIA Xenon -135 Ci N/D N/D N/D N/A Xenon -135m Ci N/D N/D N/D N/A Other (Specify)

Argon - 41 (T1/2 < 8 days) Ci N/D N/D N/D N/A Krypton - 85 (T1/2 > 8 days) Ci N/D N/D N/D N/A Total for Period Ci N/D N/D N/D N/A Tritium Ci 3.26E+01 1.30E+01 4.36E-04 N/A Gross Alpha Ci N/D N/D N/D N/A

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-15 THROUGH 12-31-15 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 1.33E+01

2.50E+01 evaporator bottoms, etc., Ci 4.72E+01 2.50E+01

b. Dry compressible waste, contaminated mJ 3.66E+02 ** 2.50E+01 equipment, etc., Ci 1.32E+OO 2.50E+01

c. Irradiated components, control rods, m3 O.OOE+OO

.... 2.50E+01 etc., Ci O.OOE+OO 2.50E+01

d. Other (describe)

Used oil/Blast media/Sewage/Gravel mJ 3.60E+OO **** 2.50E+01 Dessicant/Soil/Construction debris Ci 4.66E+OO 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by tvpe of waste) (%) (Ci) Percent Error (%)

a. Ni-63 4.50E+01 2.13E+01 2.50E+01 Cs-137 1.73E+01 8.05E+OO 2.50E+01 Co-58 1.56E+01 7.38E+OO 2.50E+01 Co-60 1.03E+01 4.89E+OO 2.50E+01 Cs-134 6.07E+OO 2.87E+OO 2.50E+01 Fe-55 2.25E+OO 1.07E+OO 2.50E+01 Sb-125 6.30E-01 2.99E-01 2.50E+01 Mn-54 5.50E-01 2.59E-01 2.50E+01 Ni-59 5.50E-01 2.59E-01 2.50E+01 C-14 4.10E-01 1.95E-01 2.50E+01

b. Co-60 7.74E+01 1.02E+OO 2.50E+01 Fe-55 6.48E+OO 8.54E-02 2.50E+01 Cs-137 4.40E+OO 5.80E-02 2.50E+01 Nb-95 3.37E+OO 4.45E-02 2.50E+01 Mn-54 2.63E+OO 3.47E-02 2.50E+01 Zr-95 1.71E+OO 2.25E-02 2.50E+01 Sb-125 1.51E+OO 1.99E-02 2.50E+01 Ni-63 1.11E+OO 1.47E-02 2.50E+01 Co-58 6.60E-01 8.65E-03 2.50E+01 Te-125m 3.40E-01 3.91 E-03 2.50E+01 H-3 1.20E-01 1.54E-03 2.50E+01

c. NONE

d. Co-58 8.07E+01 3.80E+OO 2.50E+01 Co-60 1.17E+01 5.50E-01 2.50E+01 Ni-63 2.30E+OO 1.08E-01 2.50E+01 Nb-95 1.25E+OO 5.89E-02 2.50E+01 Fe-55 7.90E-01 3.67E-02 2.50E+01 Zr-95 7.30E-01 3.41E-02 2.50E+01 Ag-110m 5.50E-01 2.59E-02 2.50E+01 Cr-51 5.40E-01 2.55E-02 2.50E+01 Co-57 2.30E-01 1.09E-02 2.50E+01 Mn-54 2.30E-01 1.06E-02 2.50E+01 Sb-125 2.20E-01 1.05E-02 2.50E+01 H-3 2.10E-01 9.88E-03* 2.50E+01 Ce-144 1.80E-01 8.28E-03 2.50E+01 Sb-124 7.00E-02 3.49E-03 2.50E+01 Zn-65 4.00E-02 2.10E-03 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID. RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01-01-15 THROUGH 12-31-15 Page 2 of 2

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1 Truck Clive, UT 1 Truck Erwin, TN 14 Truck Oak Ridge, TN 4 Truck Barnwell, SC

8. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A (1) shipment containing resins was shipped to a licensed waste processor for processing (4) shipments containing resins were shipped to a licensed waste processor for disposal (1) shipment containing sludge was shipped to a licensed waste processor for processing (2) shipments containing mechanical filters were shipped to a licensed waste processor for processing (1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal (14) 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) shipments containing biological material was shipped to a licensed waste processor for processing (3) shipments containing charcoal were shipped to a licensed waste processor for disposal (1) shipment containing asbestos was shipped to a licensed waste processor for disposal.

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/15 - 12/15)

An assessment of radiation doses to the maximum exposed member of the public due tC?: 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} 2.07E-1 1.52E-2 1.16E-2 4.62E-3 2.38E-1 Critical Organ Dose {mrem} 2.07E-1 1.52E-2 1.19E-2 4.65E-3 2.39E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose {mrad} 4.09E-6 3.96E-4 1.95E-5 2.23E-6 4.22E-4 Noble Gas Beta Dose {mrad} 1.15E-5 1.42E-4 8.86E-5 6.56E-6 2.48E-4 Critical Organ

{Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T 1h > 8 days

{including C-14} {mrem} 2.54E-1 6.43E-1 5.98E-1 1.86E-1 1.68E+O Critical Organ

{Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T% > 8 days

{excluding C-14} {mrem} 1.79E-3 4.11E-3 2.95E-3 1.25E-3 1.01E-2 6

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCMl.

(01/15 - 12/15)

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 four revisions to the ODCM during this reporting period.

Revision 24 was effective on 01/07/15 and was initiated to incorporate the assignment from ACE019800/CA291380 by changing "radiation" to "a radioactive source" in step 4.15. Also, attachment 2, Section 2.a 1-SS-RM-125/ 2-SS-RM-225 source check column was changed to read D (NOTE) 7 to correct a wrong note

designation.

Revision 25 was effective on 01 /21 /15 and was initiated to correct a TLD location name to make it consistent with th~ location name in technical procedure HP-3051.010. Corrections were made to Attacment 10, pages 1 and 3.

Revision 26 was effective on 03/05/15 and was initiated to incorporate the assignment from CR558854/CA293145.

The reference section was updated with step 3.1.37- CR558854/293145. On Attachment 10, Page 2 of 5, an asterisk was placed beside 3 T~ermoluminescent Dosimeters (TLDs) which had been noted during a previous self assesment to be at a distance greater than 5 miles from the station. As discussed in the 2014 report, the locations.

of these TLDs were evaluated and determined to be acceptable.

Revision 27 was effective on 06/15/15 and was initiated to incorporate the _assign\llent from CA3.00793.

Accordingly, attachment 13, page 4 of 8 step 2.3 was changed by adding verbage " or equivalent software" to allow for more flexibility with the computer software methodology used to perform age group specific liquid total body and critical organ calculations. Previously the calculations could be completed by spreadsheet only. The reference section was updated to add "CR541897/CA300793, Revise section 2.3 in attachment 13 of the ODCM".

Also, a minor change was made to the table on attachment 10, page 3 of 5 to remove an improperly placed division line in the box below the "Sample Media" column.

7

ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID

\

WASTE TREATMENT SYSTEMS (01/15 - 12/15)

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 2015.

8

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/15 - 12/15)

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 liquid and/or gaseous effluent monitoring instrumentation inoperable for and extended period, greater than thirty consecutive days, during the reporting period.

9

ATTACHMENT 6 UNPLANNED RELEASES (01/15 - 12/15)

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 no unplanned releases during calendar year 2015 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.

10

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/15 - 12/15)

Gaseous Effluents:

Required LLD. Typical LLD.

Radioisotope µCi/ml µCi/ml Krypton - 87 1.00E-4 2.50E-8 7.50E-8 Krypton - 88 1.00E-4 4.00E.;8 2.50E-7 Xenon~ 133 1.00E-4 2.00E-8 1.00E-7 Xenon -133m 1.00E-4 1.00E-7 4.00E-7 Xenon -135 1.00E-4 1.00E-8 5.00E-8 Xenon -135m 1.00E-4 5.00E-8 2.00E-7 Xenon -138 1.00E-4 9.00E-8 4.00E-7 Iodine -131 1.00E-12 3.00E-14 1.00E-13 Iodine -133 1.00E-10 1.00E-14 7.00E-13 Manganese - 54 1.00E-11 2.00E-14 6.00E-14 Cobalt- 58 1.00E-11 2.00E-14 6.00E-14 Iron - 59 1.00E-11 6.00E-14 1.00E-13 Cobalt- 60 1.00E-11 3.00E-14 1.00E-13 Zinc - 65 1.00E-11 6.00E-14 2.00E-13 Strontium - 89 1.00E-11 3.00E-14 8.00E-12 Strontium - 90. 1.00E-11 3.00E-15 9.00E-12 Molybdenum - 99 1.00E-11 2.00E-14 1.00E-13 Cesium -134 1.00E-11 2.00E-14 8.00E-14 Cesium -137 1.00E-11 3.00E-14 8.00E-14 Cerium -141 1.00E-11 3.00E-14 1.00E-13 Cerium - 144 1.00E-11 1.50E-13 4.00E-13 Gross Alpha 1.00E-11 7.00E-15 2.00E-14 Tritium 1.00E-6 4.00E-09 9.00E-09 11

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/15 - 12/15)

Liguid Effluents:

Required LLD. Typical LLD.

Radioisotope µCi/ml uCi/ml Krypton - 87 1.00E-5 3.00E-8 1.00E-7 Krypton - 88 1.00E-5 5.00E-8 5.00E-7 Xenon -133 1.00E-5 3.00E-8 1.00E-7 Xenon -133m 1.00E-5 9.00E-8 3.00E-7 Xenon -135 1.00E-5 1.00E-8 5.00E-8 Xenon -135m 1.00E-5 3.00E-8 2.00E-7 Xenon -138. 1.00E-5 1.00E-7 1.00E-6 Iodine -131 1.00E-6 1.00E-8 5.00E-8 Manganese - 54 5.00E-7 1.00E-8 5.00E-8 Iron - 55 1.00E-6 3.00E-7 8.00E-7 Cobalt- 58 5.00E-7 1.50E-8 6.00E-8 Iron - 59 5.00E-7 3.00E-8 7.00E-8 Cobalt- 60 5.00E-7 1.00E-8 5.50E-8 Zinc - 65 5.00E-7 3.00E-8 6.00E-8 Strontium - 89 5.00E-8 1.00E-8

4.00E-8 Strontium - 90 5.00E-8 5.00E-9 9.00E-9 Molybdenum - 99 5.00E-7 2.00E-8 6.00E-8 Cesium -134 5.00E-7 1.50E-8 5.00E-8 Cesium -137 5.00E-7 1.50E-8 6.00E-8 Cerium -141 5.00E-7 3.00E-8 9.00E-8 Cerium -144 5.00E-7 1.00E-7 5.00E-7 Gross Alpha 1.00E-7 2.00E-8 7.00E-8 Tritium 1.00E-5 2.00E-6 5.00E-6 12

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/15 - 12/15)

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 buf 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 g~ound 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 onsite. Annually, during the second quarter, these samples are analyzed by Teledyne Brown Engineering Laboratories. Additional samples are obtained from wells located inside the restricted area on a quarterly basis and analyzed onsite. Annually, during the second quarter, these samples are analyzed by Teledyne Brown Engineering Laboratories. Samples are obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Finally, samples may be obt.ained 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 2015. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "NIA" indicates a sample analysis was not performed for that sample. An "N/D" indicates an analysis was pei-formed 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 (01/15 - 12/15) 1st Quarter 2015 Sample Gamma -Emitting Alpha Sample Date H-3< 11 1-131<11 Sr-89/90<11 Fe-55<11 Ni-63<11 TRU< 1l Pu-241<

11 Media Particulates<11 -

PZ-3 01115115 WATER 7275 NIA NIA NIA NIA NIA NIA NIA

,PZ-3 01121115 WATER 4280 NIA NIA NIA NIA NIA NIA NIA PZ-3 01129115 WATER 5550 NIA NIA NIA NIA NIA NIA NIA PZ-3 02104115 WATER 5042 NIA NIA NIA NIA NIA NIA NIA PZ-3 02110115 WATER 4026 NIA NIA NIA NIA NIA NIA NIA PZ-3 02111115 WATER 5717 NIA NIA NIA NIA NIA NIA NIA PZ-3 02112115 WATER 5607 NIA NIA NIA NIA NIA NIA NIA PZ-3 02118115 WATER 4826 NIA NIA NIA NIA NIA NIA NIA PZ-3 02124115 WATER 15373 NIA NIA NIA NIA NIA NIA NIA PZ-3 02125/15 WATER 5334 NIA NIA NIA NIA NIA NIA NIA PZ-3 02127115 WATER 4972 . NIA NIA NIA NIA NIA NIA NIA PZ-3 03102115 WATER 6757 NIA NIA NIA NIA NIA NIA NIA PZ-3 03104115 WATER 5626 NIA NIA NIA NIA NIA NIA NIA PZ-3 03110115 WATER 7749 NIA NIA NIA NIA NIA NIA NIA PZ-3 03113115 WATER 5113 NIA NIA NIA NIA NIA NIA NIA PZ-3 03120115 WATER 5607 NIA NIA NIA NIA NIA NIA NIA PZ-3 03124115 WATER 4994 NIA NIA NIA NIA NIA NIA NIA PZ-3 03131115 WATER 3690 NIA NIA NIA NIA NIA NIA NIA GWP-4 03114115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-5A 03116115 WATER <1530 NIA NIA NIA NIA NIA , NIA NIA GWP-6 01107115 WATER 5043 NIA NIA NIA NIA NIA NIA NIA GWP-6 01115115 WATER 17756 NIA NIA NIA NIA NIA NIA NIA GWP-6 01121115 WATER 18441 NIA NIA NIA NIA NIA NIA NIA GWP-6 01128115 WATER 2866 NIA . NIA NIA NIA NIA NIA NIA GWP-6 02104115 WATER 4217 NIA NIA NIA NIA NIA NIA NIA GWP-6 02110115 WATER 6029 NIA NIA NIA NIA NIA NIA NIA GWP-6 02111115 WATER 4145 NIA NIA NIA NIA NIA NIA NIA GWP-6 02112115 WATER 3403 NIA NIA NIA NIA NIA NIA NIA GWP-6 02118115 WATER 9522 NIA NIA NIA NIA NIA NIA NIA GWP-6 02124115 WATER 4649 NIA NIA NIA NIA NIA NIA NIA GWP-6 02127115 WATER 4121 NIA NIA NIA NIA NIA NIA NIA GWP-6 03102115 WATER 2875 NIA NIA NIA NIA NIA NIA NIA GWP-6 03104115 WATER 2516 NIA NIA NIA NIA NIA NIA NIA GWP-6 03110115 WATER 5617 NIA NIA NIA NIA NIA NIA NIA GWP-6 03113115 WATER 7021 NIA NIA NIA NIA NIA NIA NIA GWP-6 03120115 WATER 5487 NIA NIA NIA NIA NIA NIA NIA GWP-6 03124115 WATER 3556 NIA NIA NIA NIA NIA NIA NIA GWP-6 03131115 WATER 3273 NIA NIA NIA NIA NIA NIA NIA GWP-7 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA GWP-8 03116115 WATER <1530 . NIA NIA NIA NIA NIA NIA NIA GWP-9 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA 14

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/15 - 12/15) 1st Quarter 2015 Sample Gamma -Emitting Alpha Sample Date H-3 11 1 1-131 111 Sr-89/90 111 Fe-55111 Ni-63111 11 Media Particulatesl1l TRU 11 l Pu-2411 GWP-13 03/13115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-14 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA GWP-15 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA GWP-16 03116115 WATER <1530 NIA . NIA NIA -NIA NIA NIA NIA GWP-17 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA GWP-18 01107/15 WATER <1290 NIA NIA NIA NIA NIA NIA NIA GWP-18 01112115 WATER <1426 NIA NIA NIA NIA NIA NIA NIA GWP-1.8 03116115 WATER <1530 NIA NIA NIA NIA NIA NIA NIA GWP-19 . 01116115 WATER 2291 NIA NIA NIA NIA NIA NIA NIA GWP-19 01121/15 WATER 2324 NIA NIA NIA NIA NIA NIA NIA GWP-19 02103115 WATER 1660 NIA NIA NIA NIA NIA NIA NIA GWP-19 02110115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-19 02112115 WATER <1480 NIA NIA NIA NIA NIA NIA NIA GWP-19 02124115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA GWP-19 03113115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-20 01116115 WATER <1390 NIA NIA NIA NIA NIA NIA NIA GWP-20 02105115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA GWP-20 02112115 WATER <1480 NIA NIA NIA NIA NIA NIA NIA GWP-20 02124115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA GWP-20 03113115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-21 01129115 WATER <1400 NIA

NIA NIA NIA NIA NIA NIA GWP-21 02105115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA GWP-21 02112115 WATER <1480 NIA NIA NIA NIA NIA NIA NIA GWP-21 02124115 WATER <1450 NIA NIA NIA ,NIA NIA NIA NIA GWP-21 03113115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA GWP-22 01129115 WATER <1400 NIA NIA NIA NIA NIA NIA NIA GWP~22 02105115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA GWP-22 02112115 WATER <1480 NIA NIA NIA NIA NIA NIA NIA GWP-22 02124115 WATER <1450 NIA . NIA NIA NIA NIA NIA NIA GWP-22 03113115 WATER <1520 NIA NIA NIA NIA NIA NIA NIA TIW-2 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA TIW-3 03118115 WATER < 1430 NIA NIA NIA NIA NIA NIA NIA TIW-5 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA BTW-1

03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA BTW-2 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA BTW-4 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02109115 WATER <1730 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02109115 WATER <1730 NIA NIA NIA NIA NIA NIA NIA

. Disch Canal Storm Drains 02109115 WATER <1730 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 01130115 WATER <1400 NIA NIA NIA NIA NIA NIA NIA 15

U-1 Mat Sump East 03104115 WATER <1420 NIA . NIA NIA NIA NIA NIA NIA u~1 Mat Sump South 03104115 WATER <1420 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 03104/15 WATER <1420 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 03104115 WATER <1420 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 03104115 WATER <1420 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 03104115 WATER <1420 NIA NIA NIA NIA NIA NIA NIA U-2 AB/FB GWMS 03118115 WATER <1430 NIA NIA NIA NIA NIA NIA NIA PZ-1 03118/15 WATER Insufficient Volume to Sample PZ-2 03118115 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 16

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/15 - 12/15) 2"d Quarter 2015 Sample Gamma -Emitting Alpha Sample Date H-3 111 Particulates111 1-131 111 Sr-89/9011 1 Fe-55111 Ni-63 111 TRU 11 l Pu-241 111 Media GWP-3(2) 06/24115 WATER 1260 NIA NIA NIA NIA NIA NIA NIA GWP-3 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA PZ-3 04107115 WATER 6436 NIA NIA NIA NIA NIA NIA N/A PZ-3 04115/15 WATER 6158 NIA NIA NIA NIA NIA NIA NIA PZ-3 04116115 WATER 5569 NIA NIA NIA NIA NIA NIA NIA PZ-3 04121115 WATER 5022 NIA NIA NIA NIA NIA NIA NIA PZ-3 04129115 WATER 4232 NIA NIA NIA NIA NIA NIA NIA PZ-3 05106115 WATER 5645 NIA NIA NIA NIA NIA NIA NIA PZ-3 05114115 WATER 7270 NIA NIA NIA NIA NIA NIA NIA PZ-3 05121115 WATER 5008 NIA NIA NIA NIA NIA NIA NIA PZ-3 05128115 WATER 4768 NIA NIA NIA NIA NIA NIA NIA PZ-3 06111115 WATER 6637 NIA NIA NIA NIA NIA NIA NIA PZ-3 06124115 WATER 2899 NIA NIA NIA NIA NIA NIA NIA PZ-3 (2) 06124115 WATER 2910 NIA NIA NIA NIA NIA NIA NIA GWP-5A(2). 06125115 WATER <966 NIA NIA NIA NIA NIA NIA N/A GWP-5A 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-6 04107115 WATER 3498 ND

NIA NIA NIA NIA NIA NIA GWP-6 04115115 WATER *2444 NIA NIA NIA NIA NIA NIA NIA GWP-6 04121115 WATER 2339 NIA NIA NIA NIA NIA NIA NIA GWP-6 04130115 WATER 4203 NIA NIA NIA NIA NIA NIA NIA GWP-6 05106115 WATER 4313 NIA NIA NIA NIA NIA NIA NIA GWP-6 05114115 WATER 4395 NIA NIA NIA NIA NIA NIA NIA GWP-6 05121115 WATER 5717 NIA NIA NIA NIA NIA NIA NIA GWP-6 05128115 WATER 2698 *NIA NIA NIA NIA NIA NIA NIA GWP-6 06111115 WATER 4304 NIA NIA NIA NIA NIA NIA NIA GWP-6 06124115 WATER 2780 NIA NIA NIA NIA NIA NIA NIA GWP-6 (2) 06124115 WATER 3150 NIA NIA NIA NIA NIA NIA NIA GWP-7 (2) 06125/15 WATER <967 NIA NIA NIA NIA NIA NIA NIA GWP-7 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-8 (2) 06125115 WATER <949 NIA NIA NIA N/A NIA NIA NIA GWP-8 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-9 (2) 06124115 WATER <961 NIA NIA NIA NIA NIA NIA NIA GWP-9 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-13 (2) 06124115 WATER <964 NIA NIA NIA NIA NIA NIA NIA GWP-13 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA N/A GWP-14 (2) 06124115 WATER <1130 NIA NIA NIA NIA NIA NIA NIA GWP-14 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-15 (2) 06123115 WATER <1130 NIA NIA NIA NIA NIA NIA NIA GWP-15 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-16 (2) 06123115 WATER 1260 NIA NIA NIA NIA NIA NIA NIA GWP-16 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA 17

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/15 - 12/15) 2"d Quarter 2015 Sample H-3<1> Gamma -Emitting 1-131<1> Sr- Alpha Sample Date Fe-55<1> Ni-63<1> TRU111 Pu-241 11 >

Media Particulatesl1l 89190111 GWP-17 (2) 06123115 WATER 1470 NIA NIA NIA NIA NIA NIA NIA GWP-17 06130115 WATER <1410 NIA NIA NIA . NIA NIA NIA NIA GWP-18 (2) 06123115 WATER 4200 NIA NIA NIA 'NIA NIA NIA NIA GWP-18 06130115 WATER 3460 NIA NIA NIA NIA NIA NIA. NIA GWP-19 (2) 06124115 WATER 1320 NIA NIA NIA NIA NIA NIA NIA GWP-19 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-20 (2) 06124115 WATER <1140 NIA NIA NIA NIA NIA NIA NIA GWP-20 06130115 WATER <1390 NIA NIA NIA NIA NIA NIA NIA GWP-21 (2) 06125115 WATER 1710 NIA NIA NIA NIA NIA NIA NIA GWP-21 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA GWP-22 (2) 06125115 WATER 1690 NIA NIA NIA NIA NIA NIA NIA GWP-22 06130115 WATER <1390 NIA NIA NIA NIA NIA NIA NIA TIW-2 (2) 06126115 WATER <952 NIA NIA NIA NIA NIA NIA NIA TIW-2 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA TIW-3 (2) 06125115 WATER <953 NIA NIA NIA NIA NIA NIA NIA TIW-3 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA TIW-5 (2) 06126115 WATER <946 NIA NIA NIA NIA NIA NIA NIA TIW-5 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 06125115 WATER <962 NIA NIA NIA NIA NIA NIA NIA BTW-1 06130115 WATER <141.0 NIA NIA NIA NIA NIA NIA NIA BTW-2 (2) 06125115 WATER <967 NIA NIA NIA NIA NIA NIA NIA BTW-2 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA BTW-4 (2) 06126115 WATER <950 NIA NIA NIA NIA NIA NIA NIA BTW-4 06130115 WATER <1410 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 05121115 WATER <1790 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 05121115 WATER <1790 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 05121115 WATER <1790 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05121115 WATER <1790 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 06111115 . WATER <1450 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 06111115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 06111115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 06111115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 06111115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 06111115 WATER <1450 NIA NIA NIA NIA NIA NIA NIA PZ-1 06130115 WATER Insufficient Volume to Sample PZ-2 06130115 WATER Insufficient Volume to.Sample TIW-1 Well abandoned in place, pending decommissioning TIW-4 Well abandoned in place, pending decommissioning 18

(1) pCi/L (2) Vendor Analysis ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/15 - 12/15) 3rd Quarter 2015 Sample Gamma -Emitting Sr- Alpha Sample Date H-3< 1> 1-131< 1> Fe-55<1> Ni-63 11 > Pu-241<1>

Media Particulates<1> 89/90<1> TRU< 1>

PZ-3 07108115 WATER 4026 NIA NIA NIA NIA NIA NIA NIA PZ-3 07115115 WATER 3433 NIA NIA NIA NIA NIA NIA NIA PZ-3 07123115 WATER 3074 N/A NIA NIA NIA NIA NIA NIA PZ-3 07130115 WATER 4143 NIA NIA NIA NIA NIA NIA NIA PZ-3 08104115 WATER 4283 NIA NIA NIA NIA NIA NIA NIA PZ-3 08120115 WATER 3192 NIA NIA NIA NIA NIA NIA NIA.

PZ-3 09103115 WATER 5280 NIA NIA NIA NIA NIA NIA NIA PZ-3 09117115 WATER 3571 NIA NIA NIA NIA NIA NIA NIA GWP-4 (2) 07108115 WATER <797 NIA NIA NIA NIA NIA NIA NIA GWP-4 07108115 WATER <1390 NIA NIA NIA NIA NIA NIA NIA GWP-6. 07108115 WATER 6254 NIA NIA NIA NIA NIA NIA NIA GWP-6 07115115 WATER 5933 NIA NIA NIA NIA NIA NIA NIA GWP-6 07123115 WATER 5922 NIA NIA NIA NIA NIA NIA NIA GWP-6 07130115 WATER 6470 NIA NIA NIA NIA NIA NIA NIA GWP-6 08104115 WATER 4022 NIA NIA NIA NIA NIA NIA NIA GWP-6 08120115 WATER 3318 NIA NIA NIA NIA NIA NIA NIA GWP-6 09103115 WATER 4339 NIA NIA NIA NIA NIA NIA NIA GWP-6 09117115 WATER <1335 . NIA NIA NIA NIA NIA NIA NIA GWP-18 07130115, WATER 5326 NIA NIA NIA NIA NIA NIA NIA GWP-18 08104115 WATER 5617 NIA NIA NIA NIA NIA NIA NIA GWP-18 08113115 WATER 5060 NIA NIA NIA NIA NIA NIA NIA GWP-18 08120115 WATER 6129 NIA NIA NIA NIA NIA NIA NIA GWP-18 09103115 WATJ::R 6768 NIA NIA NIA NIA NIA NIA NIA GWP-18 09117115 WATER 3906 NIA NIA NIA NIA NIA NIA \

NIA GWP-19 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA GWP-20 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA GWP-22 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA TTW-2 10109115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA TTW-3 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA TTW-5 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA BTW-1 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA BTW-2 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA BTW-4 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 08120115 WATER <1638 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 08120115 WATER <1638 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 08120115 WATER <1625 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 08111115 WATER <1497 NIA NIA NIA NIA NIA NIA

NIA U-1 Mat Sump East 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA 19

ii M .f U-2 Mat Sump Inside 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09123115 WATER <1370 NIA NIA NIA NIA NIA NIA NIA PZ-1 10108115 WATER Insufficient volume to sample PZ-2 10108115 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 (01/15 - 12/15) 4th Quarter 2015 Sample Gamma -Emitting Alpha Sample Date H-3<1> 1-131<1> Sr-89/90<1> Fe-55< 1> Ni-63<1> Pu-241<1>

Media Particulates<11 TRU< 1>

PZ-3 10/01/15 WATER 3550 NIA NIA NIA NIA NIA NIA NIA PZ-3 10108115 WATER 4308 NIA NIA NIA NIA NIA NIA NIA PZ-3 10115115 WATER 2243 NIA NIA NIA NIA NIA NIA NIA PZ-3 10121115 WATER 4271 NIA NIA NIA NIA NIA NIA NIA PZ-3 10131115 WATER 2825 NIA NIA NIA NIA NIA NIA NIA PZ-3 11112115 WATER 4112 NIA NIA NIA NIA NIA NIA NIA PZ-3 11117115 WATER 3573 NIA NIA NIA NIA NIA NIA NIA

- PZ-3 12103115 WATER 3314 NIA NIA NIA NIA NIA NIA NIA PZ-3 12116115 WATER 4213 NIA NIA NIA NIA NIA NIA NIA PZ-3 12130115 WATER 3828 NIA NIA NIA NIA NIA NIA NIA GWP-6 10101115 WATER <954 NIA NIA NIA NIA NIA NIA NIA GWP-6 10108115 WATER <1310 NIA NIA NIA NIA NIA NIA NIA GWP-6 10115115 WATER 1450 NIA NIA NIA NIA NIA NIA NIA GWP-6 10122115 WATER 2404 ND ND NIA NIA NIA NIA NIA GWP-6 10131115 WATER <708 NIA NIA NIA NIA NIA NIA NIA GWP-6 11112115 WATER 2085 NIA NIA NIA NIA NIA NIA NIA GWP-6 11117115 WATER 1678 NIA NIA NIA NIA NIA NIA NIA GWP-6 12103115 WATER 2553 NIA NIA NIA NIA NIA NIA NIA GWP-6 12116115 WATER <900 NIA NIA NIA NIA NIA NIA NIA GWP-6 12130115 WATER 4110 NIA NIA NIA NIA N~A NIA ~IA GWP-7

12116115 WATER <890 NIA NIA NIA NIA NIA NIA NIA GWP-8 12116115 WATER <890 NIA NIA NIA NIA NIA NIA NIA GWP-9 12116115 WATER <844 NIA NIA NIA NIA NIA NIA NIA GWP-13 12117115 WATER <851 NIA NIA NIA NIA NIA NIA NIA GWP-14 12116115 WATER <895 NIA NIA NIA NIA NIA NIA NIA GVIJP-15 12116115 WATER <842 NIA NIA NIA NIA NIA NIA NIA GWP-16 12116115 WATER <846 NIA NIA NIA NIA NIA NIA 'NIA GWP-17 12117115 WATER <806 NIA NIA NIA NIA NIA NIA NIA GWP-18 10101115 WATER 2055 NIA NIA NIA NIA NIA NIA NIA GWP-18 10108115 WATER 2156 NIA NIA NIA NIA NIA NIA NIA GWP-18 10115115 WATER 1427 NIA NIA NIA NIA NIA NIA NIA GWP-18 10121115 WATER 1607 NIA NIA NIA NIA NIA NIA NIA GWP-18 10131115 WATER 3725 NIA

NIA NIA NIA NIA NIA NIA GWP-18 11112115 WATER 2641 ND NIA NIA NIA NIA NIA NIA GWP-18 11117115 WATER 2455 NIA NIA NIA NIA NIA NIA NIA GWP-18 12103115 WATER 3906 NIA NIA NIA NIA NIA NIA NIA GWP-18 12116115 WATER <900 NIA NIA NIA NIA NIA NIA NIA GWP-18 12130115 WATER 2427 NIA NIA NIA NIA NIA NIA NIA GWP-19 12116115 WATER <855 NIA NIA NIA NIA NIA NIA NIA GWP-20 12117115 WATER <863 NIA NIA NIA NIA NIA NIA NIA GWP-21 10109115 WATER 3810 NIA NIA NIA NIA NIA NIA NIA 21

GWP-21 10113115 WATER 1480 NIA NIA NIA NIA NIA NIA NIA GWP-21 10121115 WATER 4830 NIA NIA NIA NIA NIA NIA NIA GWP-21 10122115 WATER 2651 NIA NIA NIA NIA NIA NIA NIA GWP-21 10131115 WATER 2438 NIA NIA NIA NIA NIA NIA NIA GWP-21 11112115 WATER 3529 NIA NIA NIA NIA NIA NIA NIA GWP-21 11117115 WATER 2152 ND ND NIA NIA NIA NIA NIA GWP-21 12103115 WATER 3975 NIA NIA NIA NIA NIA NIA NIA GWP-21 12116115 WATER 2391 NIA NIA NIA NIA NIA NIA NIA GWP-21 12130115 WATER 1667 NIA NIA NIA NIA NIA NIA NIA GWP-22 12116115 WATER <863 NIA NIA NIA NIA NIA NIA NIA TTW-2 12117115 WATER <851 NIA NIA NIA NIA NIA NIA NIA TTW-3 12116115 WATER <844 NIA NIA NIA NIA NIA NIA NIA TTW-5 12117115 WATER <830 NIA NIA NIA NIA NIA NIA NIA BTW-1 12117115 WATER <855 NIA NIA *NIA NIA

NIA NIA NIA BTW-2 12117115 WATER <846 NIA NIA NIA NIA NIA NIA NIA BTW-4 12117115 WATER <851 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11117115 WATER <1540 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 11117115 WATER <1540 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 11117115 WATER <1540 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 11106115 WATER <1498 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 12116115 WATER <911 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 12116115 WATER <897 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 12116115 WATER <905 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 12116115 WATER <897 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 12/16115 WATER <892 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 12116115 WATER <894 NIA NIA NIA NIA NIA NIA NIA PZ-1 12117115 WATER Insufficient volume to sample PZ-2 .12117115 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 22

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/15 - 12/15)

Carbon-14, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere.

Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.

Due to the long half-life of C-14, 5730 years, a s*ignificant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution 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, Revis.ion 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 of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 26.8 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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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 effluen~s released at North Anna is estimated to be 1.30E-1 mrem from the inhalation pathway, or 8.66E-03% TS of the 1500 mrem/yr dose rate limit and 1.55E+O mrem from the ingestion pathway or 5.17E+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 were four entries on the Annual Effluent Release Report Log for 2015. All entries numbered 15-01 thru 15-04 were made to document revisions to VPAP-2103N, the North Anna Power Station Offsite Dose Calculation Manual (ODCM). ODCM revision numbers were 24 thru 27 respectively.

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 2016 United States Nuclear Regulatory Commission Serial No.16-111 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. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2015 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, plei:ise contact Robin Klearman at (540) 894-2436.

Very truly yours, Gt~?c~-6 Site Vice President Enelosure Commitments made in this l~tter: None cc: U. S. Nuclear Regulatory Commission Region II *

Marquis One Tower 245 P,eachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nucl.ear rylateri~*I Safety and Safeguards U.S. Nuclear Regulatory Commission