ML13141A414

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Independent Spent Fuel Storage Installation - 2012 Annual Radioactive Effluent Release Report
ML13141A414
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/22/2013
From: Gerald Bichof
Dominion, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
13-176
Download: ML13141A414 (50)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2013 United States Nuclear Regulatory Commission Serial No.13-176 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 2012 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, Gerald 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

r-I-a'* Dominion North Anna Power Station 2012 Annual Radioactive Effluent Release Report

,.*, r.4, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2012 TO DECEMBER 31, 2012)

PREPARED BY: t 6A Supervisor Radiological Analysis and Instrumentation REVIEWED BY: .

_upervisor Health Physics Technical Services APPROVED BY:_____ ____

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, 2012 TO DECEMBER 31, 2012 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 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 - 24 Carbon-14 Calculations ............................. 25-26 Miscellaneous Annual Effluent Release Report Log ............ 27

'A*.0 r-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 2012 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 R.G.

1.21 during the period January 1 through December 31, 2012, 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 2012.

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. Neither were there any spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6.

Based on the 2012 effluent release data, 10 CFR 50, Appendix I dose calculations were performed 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 2.68E-1 mrem, which is 4.46% of the dose limit and the critical organ dose due to liquid effluents was 2.78E-1 mrem, which is 1.39% of the dose limit.
b. The air doses due to noble gases was 1.37E-5 mrad gamma, which is 6.85E-5% of the annual gamma dose limit, and 3.52E-5 mrad beta, which is 8.80E-5% 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 1.02 mrem, which is 3.40% of the annual dose limit. The bases of these calculations are described in Attachment 9.
d. The critical organ dose for 1-131,1-133, H-3, and Particulates with half-lives greater than 8 days not including C-14 was 7.74E-4 mrem, which is 2.58-3% 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 three revisions to the Offsite Dose Calculation Manual during this reporting period.

I

I to F.-41 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 1st of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period, in Attachment 6.

As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.7.2.a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of FSAR updates.

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

' 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 & 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 2.0E-4 ý(Ci/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-1 31 & 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 & iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days, excluding carbon-14, 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 ODOM.

3

,i3.0 ,, 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 made to determine if new location(s) have been identified 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 2012. The nearest resident in the ENE sector changed from 2.2 miles out to 2.37 miles out. The meat animal in the ESE sector was removed. The garden in the SSW sector moved from 3.07 miles to 2.34 miles out. The nearest resident and garden in the SW have both moved to 1.65 miles out from 1.7 miles out and 2.64 miles respectively.

Section 6.6.1 .b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. All milk samples were collected as required. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and 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 (01112 - 12112)

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 (01111 - 12111)

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

A. Fission and Activiation Gases

1. Total Release Curies 2.14E-01 5.30E-03 1.80E+1
2. Average Release Rate For Period [tCi/sec 2.72E-02 6.74E-04 B. Iodines:
1. Total Iodine-131 Release Curies 1.69E-06 O.OOE+00 2.80E+1
2. Average Release Rate For Period 1 tCi/sec 2.15E-07 O.OOE+00 C. Particulate (T1/2 > 8 days):
1. Total Particulate (T1/2> 8 days) Release Curies 5.39E-05 2.41E-06 2.80E+1
2. Average Release Rate For Period piCi/sec 6.86E-06 3.07E-07
3. Gross Alpha Radioactivity Releas( Curies O.OOE+00 9.59E-08 D. Tritium:
1. Total Release Curies 7.30E+00 2.81E+00 3.10E+1
2. Average Release Rate For Period pCi/sec 9.29E-01 3.57E-01 E. Carbon-14
1. Total Release Curies 1.12E+01 2.76E-01
2. Average Release Rate For Period pCi/sec 1.42E+00 3.51 E-02 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 5.OOE-06 5.67E-08
2. Skin Dose Rate  % 2.04E-06 2.42E-08
3. Critical Organ Dose Rate (with C-14)  % 8.89E-03 1.26E-04 Critical Organ Dose Rate (without C-14)  % 6.24E-04 1.73E-04

TABLE JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/11 - 12/11)

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

A. Fission and Activiation Gases

1. Total Release Curies 4.96E-03 2.79E-01 1.80E+1
2. Average Release Rate For Period [iCi/sec 6.24E-04 3.51 E-02 B. lodines:
1. Total Iodine-131 Release Curies O.OOE+00 OOOE+00 2.80E+1
2. Average Release Rate For Period pCi/sec O.OOE+00 OOOE+00 C. Particulate (T112 > 8 days):
1. Total Particulate (T1/2> 8 days) Release Curies O.OOE+00 2.22E-08 2.80E+1
2. Average Release Rate For Period pCi/sec O.OOE+00 2.79E-09
3. Gross Alpha Radioactivity ReleasE Curies 3.54E-07 2.15E-07 D. Tritium:
1. Total Release Curies 7.93E+00 3.02E+00 3.10E+1
2. Average Release Rate For Period lCi/sec 9.98E-01 3.80E-01 F. Carbon-14
1. Total Release Curies 2.58E-01 1.45E+01
2. Average Release Rate For Period pCi/sec 3.25E-02 1.82E+00 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 8.77E-07 3.51 E-06
2. Skin Dose Rate  % 2.83E-07 1.30E-06
3. Critical Organ Dose Rate (with C-14)  % 7.23E-04 5.88E-03 Critical Organ Dose Rate (without C-14)  % 6.05E-04 2.05E-04

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

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 4.25E-05 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 6.46E-06 N/D Xenon - 133 Ci 1.58E-02 N/D 1.60E-01 5.11E-03 Xenon - 133m Ci N/D N/D 7.11E-04 N/D Xenon - 135 Ci N/D N/D N/D N/D Xenone- 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 PeCod Ci 1.58E-02 N/D 1.61 E-01 5.11E-03 Iodines:

Iodine - 131 Ci 5.97E-08 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 5.97E-08 N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobaft - 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 lCesium - 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 (01/12 - 12/12)

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 Other (Specify)

Total for Period (Tl/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (Tl/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D NID N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 3.73E-01 9.96E-01 1.80E-02 1.37E-04 CARBON-14 Ci 8.23E-01 N/D 8.39E+00 2.66E-01

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

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 N/D 1.71E-02 N/D 2.57E-01 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 NID N/D N/D N/D Total For Period Ci N/D 1.71E-02 N/D 2.57E-01 lodines:

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:

Sanganese - 54 Ci N/D N/D N/D N/D Sobant - 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 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 1.12E-08 N/D N/D

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/12 - 12112)

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 NID N/D N/D N/D Cerium - 144 Ci N/D NID N/D N/D Silver-110m Ci N/D 1.10E-08 N/D N/D Total for Period (Tl/2 > 8 days) Ci N/D 2.22E-08 N/D 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 1.24E+00 8.04E-01 2.16E-04 3,94E-04 CARBON-14 Ci N/D 8.91E-01 N/D 1.34E+01

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

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 1.31 E-03 3.17E-05 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 3.1OE-04 1.19E-05 Xenon - 133 Ci N/D N/D 3.26E-02 1.48E-04 Xenon - 133m Ci N/D N/D 6.85E-04 N/D Xenon - 135 Ci N/D N/D 2.55E-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)

Argon - 41 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 3.75E-02 1.92E-04 lodines:

Iodine - 131 Ci N/D N/D 1.63E-06 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 1.63E-06 N/D Particulates:

Manganese - 54 Ci N/D N/D 5.69E-07 N/D Cobalt - 58 Ci N/D N/D 5.51E-06 N/D Iron - 59 Ci N/D N/D N/D 1.12E-06 Cobalt - 60 Ci N/D N/D 1.22E-05 4.73E-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 (01/12 - 12112)

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

Cesium - 137 Ci NID N/D 7.93E-08 9.19E-08 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 9.92E-06 4.25E-07 Zirconium-95 Ci N/D N/D 7.33E-06 3.01 E-07 Rubidium-88 (Tl/2 < 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 1.83E-05 N/D Total for Period (Tl/2 > 8 days) Ci N/D N/D 5.39E-05 2.41 E-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 5.39E-05 2.41 E-06 GROSS ALPHA: Ci N/D 9.59E-08 N/D N/D TRITIUM: Ci 4.80E+00 1.29E+00 2.11 E+00 5.19E-01 CARBON-14 Ci N/D N/D 1.95E+00 1.00E-02

TABLE IC NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01112 - 12/12)

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 5.86E-06 Krypton - 85m Ci N/D N/D N/D 4.65E-06 Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D 3.16E-06 Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 4.30E-03 4.08E-03 Xenon - 133m Ci N/D N/D N/D 7.83E-05 Xenon - 135 Ci N/D N/D 4.83E-04 5.69E-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) Ci Argon - 41 Ci N/D N/D 1.81 E-04 2.53E-04 Total For Period Ci N/D N/D 4.96E-03 4.99E-03 lodines:

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 (01/12 - 12/12)

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 N/D N/D Zirconium-95 (Tl/2 > 8days) Ci N/D N/D N/D N/D Niobium-95 (Tl/2 > 8days) Ci N/D N/D N/D N/D Silver-1 1Om (Tl/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (Tl/2 > 8 days) Ci N/D N/D N/D N/D 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 0.OOE+00 GROSS ALPHA: Ci 3.54E-07 2.15E-07 N/D N/D

TRITIUM: Ci 6.69E+00 1.95E+00 2.41 E-05 2.67E-01 CAR BON- 14 Ci N/D N/D 2.58 E-01 2.60E-0 1

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/11 - 12/11)

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 4.75E-03 2.75E-03 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 1.63E-11 3.94E-12
3. Percent of applicable limit (T.S.)  % 5.44E-05 9.54E-06 B. Tritium:
1. Total release activity. Curies 2.39E+02 1.49E+02 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 8.21E-07 2.14E-07
3. Percent of applicable limit (T.S.)  % 8.21 E-03 2.14E-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. pCi/ml O.OOE+00 O.OOE+00
3. Percent of applicable limit (T.S.)  % 0.OOE+00 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 1.18E+08 1.51E+08 3.OOE+00 F. Total volume of dilution water used during the period. Liters 2.91E+11 6.96E+11 3.OOE+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/11 - 12111)

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 7.61 E-03 8.40E-04 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 8.70E-12 1.53E-12
3. Percent of applicable limit (T.S.)  % 2.69E-05 3.08E-06 B. Tritium:
1. Total release activity. Curies 3.89E+01 3.24E+02 2.OOE+01
2. Average diluted concentration during the period. pCi/ml 4.45E-08 5.90E-07
3. Percent of applicable limit (T.S.)  % 4.45E-04 5.90E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies O.OOE+00 O.OOE+00 2.O0E+01
2. Average diluted concentration during the period. pCi/ml O.OOE+00 O.OOE+00
3. Percent of applicable limit (T.S.)  % O.OOE+00 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 1.42E+08 1.46E+08 3.OOE+00 F. Total volume of dilution water used during the period. Liters 8.74E+11 5.49E+11 3.OOE+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01112 - 12112)

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 N/D N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 1.27E-04 8.88E-04 N/A N/A Cobalt - 60 Ci 4.57E-03 1.86E-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 - 110Om Ci N/D N/D 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 CesiumL-137 Ci 5.28E-05 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 Other (Specify) Ci Niickel - 63 (Tl/2 > 8 days) Ci N/D N/D N/A N/A Total for Period Ci 4.75E-03 2.75E-03 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01112 - 12/12)

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 Kr-88 (T1/2 < 8 days) Ci N/D N/D N/A N/A Kr-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 2.39E+02 1.49E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01112 - 12112)

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

Manganese - 54 Ci N/D N/D N/A N/A Iron - 55 Ci N/D N/D N/A N/A ICobalt - 58 Ci 1.36E-03 3.92E-04 N/A N/A Cobalt - 60 Ci 5.18E-03 4.48E-04 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 - 110Om Ci N/D N/D 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 6.30E-05 N/D N/A N/A Cesium - 137 Ci 4.60E-04 N/D N/A N/A 3arium-Lathanum - 140 Ci N/D N/D N/A N/A Cerium - 141 Ci N/D N/D N/A N/A Other (Specify)

Niickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A N/A A,.ntimony-122 (T1/2 < 8 days) Ci N/D N/D N/A N/A A.ntimony-125 (T1/2 > 8 days) Ci 3.89E-04 N/D N/A N/A A.ntimony-124 (T1/2 > 8 days) Ci 6.57E-05 N/D N/A N/A Tellurium-125m (T1/2 > 8 days) Ci 8.98E-05 Total for Period Ci 7.61 E-03 8.40E-04 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01112 - 12/12)

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 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)

Argon - 41 (TI/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 3.89E+01 3.24E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

I T- I "A TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-12 THROUGH 12-31-12 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 1.60E+01
  • 2.50E+01 evaporator bottoms, etc., Ci 1.59E+02 2.50E+01
b. Dry compressible waste, contaminated m3 2.88E+02 ** 2.50E+01 equipment, etc., Ci 3.14E-01 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 3.31E+00

  • 2.50E+01 DessicantJSoil/Construction debris Ci 2.43E-03 2.50E+01 Animal Carcasses
2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Co-60 0.OOE+00 5.96E+04 2.50E+01 Co-58 0.OOE+00 3.27E+04 2.50E+01 Fe-55 0.OOE+00 1.83E+04 2.50E+01 Cs-137 0.OOE+00 1.44E+04 2.50E+01 Cs-134 0.OOE+00 1.43E+04 2.50E+01 Ni-63 0.OOE+00 9.84E+03 2.50E+01 Mn-54 3.75E+01 6.93E+03 2.50E+01 H-3 2.06E+01 5.38E+02 2.50E+01 C-14 1.15E+01 4.52E+02 2.50E+01 Ni-59 9.04E+00 3.68E+02 2.50E+01
b. Co-60 3.01E+01 9.47E+01 2.50E+01 Cr-51 1.57E+01 4.93E+01 2.50E+01 Co-58 1.52E+01 4.77E+01 2.50E+01 Nb-95 1.33E+01 4.19E+01 2.50E+01 Zr-95 1.03E+01 3.25E+01 2.50E+01 Fe-55 5.05E+00 1.59E+01 2.50E+01 Cs-137 3.92E+00 1.23E+01 2.50E+01 Mn-54 2.46E+00 7.74E+00 2.50E+01 Ni-63 1.54E+00 4.85E+00 2.50E+01 H-3 9.82E-01 3.09E+00 2.50E+01 Fe-59 6.11E-01 1.92E+00 2.50E+01
c. NONE
d. H-3 3.48E+01 8.47E-01 2.50E+01 Co-60 3.13E+01 7.60E-01 2.50E+01 Co-58 7.82E+00 1.90E-01 2.50E+01 Cs-137 4.80E+00 1.17E-01 2.50E+01 Nb-95 3.96E+00 9.63E-02 2.50E+01 Zr-95 2.97E+00 7.23E-02 2.50E+01 Fe-55 2.50E+00 6.08E-02 2.50E+01 Cr-51 2.20E+00 5.35E-02 2.50E+01 C-14 1.46E+00 3.55E-02 2.50E+01 Mn-54 1.10E+00 2.67E-02 2.50E+01 Ni-63 1.00E+00 2.44E-02 2.50E+01 Zn-65 1.82E-01 4.41E-03 2.50E+01 Fe-59 8.40E-02 2.04E-03 2.50E+01 Co-57 5.45E-02 1.32E-03 2.50E+01 Cs-1 34 3.38E-02 8.22E-04 2.50E+01 Sb-125 1.86E-02 4.51 E-04 2.50E+01

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

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

Number of Shipments Mode of Transportatior Destination 0 N/A N/A (1) shipment containing resins was shipped to a licensed waste processor for processing.

(1) shipment of mechanical filters was shipped to a licensed disposal facility

- shipment included DAW, blast media, soil/gravel, sand, and charcoal (1) shipment of resin was shipped to a licensed waste processor for disposal.

(6) shipments of dry compactable waste were shipped to a licensed processor.

- 1 shipment contained resins.

- 3 shipments contained biological material

- 3 shipments contained mechanical filters (1) shipment of used oil was shipped to a licensed waste facility for disposal.

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01112 - 12/12)

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 Tntal Total Body Dose (mrem) 8.47E-2 5.26E-2 1.58E-2 1.14E-1 2.68E-1 Critical Organ Dose (mrem) 8.56E-2 5.26E-2 2.55E-2 1.14E-1 2.78E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 7.29E-6 8.45E-8 1.22E-6 5.14E-6 1.37E-5 Noble Gas Beta Dose (mrad) 2.02E-5 2.72E-7 1.86E-6 1.29E-5 3.25E-5 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T1 > 8 days (including C-14) (mrem) 5.06E-1 9.53E-3 2.84E-2 4.80E-1 1.02E+0 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with TI/ > 8 days (excluding C-14) (mrem) 2.98E-3 8.77E-4 2.95E-3 1.03E-3 7.83E-3 6

w ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/12 - 12/12)

As required by Technical Specification 5.5.1, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.

There were three revisions made to the ODCM in 2012.

Revision 19 was effective 01-25-2012, Revision 20 was effective 05-15-2012, and Revision 21 was effective 11-27-2012. Neither Revision 19, Revision 20, nor Revision 21 changed any sampling locations due to land use census dose calculations.

7

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

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 2012.

8

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01112- 12112)

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 days during 2012.

9

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

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 2012 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted area and 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 a result of 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 so plume mitigation will take several months.

10

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01112 - 12112)

Gaseous Effluents:

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

Radioisotope iiCi/mL aCi/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 5.00E-8 - 2.OOE-7 Xenon - 138 1.OOE-4 1.OOE-7 - 5.OOE-7 Iodine - 131 1.00E-12 6.OOE-14 - 1.00E-13 Iodine - 133 1.OOE-1 0 1.OOE-14 - 7.OOE-13 Manaanese - 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.OOE-11 3.OOE-15 - 9.OOE-12 Molybdenum - 99 1.OOE-11 7.OOE-14 - 2.OOE-13 Cesium - 134 1.00E-11 5.00E-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 - 5.00E-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 (01/12 - 12/12)

Liquid Effluents:

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

Radioisotope uCilmL uCi/mL Krypton - 87 1.OOE-5 4.OOE-8 - 1.OOE-7 Krypton - 88 1.OOE-5 I.OOE-7 - 1.OOE-6 Xenon - 133 1.00E-5 7.OOE-8 - 1.50E-7 Xenon - 133m 1.OOE-5 9.OOE-8 - 3.OOE-7 Xenon - 135 1.OOE-5 9.OOE-9 - 5.00E-8 Xenon - 135m 1.OOE-5 3.OOE-8 - 2.OOE-7 Xenon - 138 1.OOE-5 1.OOE-7 - 1.OOE-6 Iodine - 131 1.OOE-6 I.OOE-8 - 5.00E-8 Manganese - 54 5.OOE-7 2.OOE-8 - 5.00E-8 Iron - 55 1.OOE-6 3.OOE-7 - 8.OOE-7 Cobalt - 58 5.OOE-7 2.OOE-8 - 6.OOE-8 Iron - 59 5.OOE-7 3.OOE-8 - 7.OOE-8 Cobalt - 60 5.00E-7 1.OOE-8 - 5.50E-8 Zinc - 65 5.00E-7 3.OOE-8 - 6.OOE-8 Strontium - 89 5.OOE-8 I.OOE-8 - 4.OOE-8 Strontium - 90 5.00E-8 5.00E-9 - 9.OOE-9 Molybdenum - 99 5.00E-7 2.OOE-8 - 6.OOE-8 Cesium - 134 5.OOE-7 2.OOE-8 - 5.00E-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 I.OOE-7 - 5.00E-7 Gross Alpha I.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 (01112 - 12112)

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 Attachments1 1 & 12 to VPAP-2103N, which is attached to this document.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2012. 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

- .- - , 1- A ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01112 - 12/12) 1 st Quarter 2012 Sample Date Sample H-3 Gamma - Alpha Media (pCi/L) Emitting 1-131 Sr°89/90 Fe-55 Ni-63 TRU Pu-241 Particulates GWP-6 01/06/12 Water 44711 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/13/12 Water 41163 N/A N/A N/A N/A N/A N/A N/A PZ-2 01/19/12 INSUFFICIENT VOLUME TO SAMPLE PZ-1 01/19/12 INSUFFICIENT VOLUME TO SAMPLE GWP-3 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A PZ-3 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-4 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-5A 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/19/12 Water 54466 N/A N/A N/A N/A N/A N/A N/A GWP-7 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-8 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-9 01/19/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/25/12 Water 46372 N/A N/A N/A N/A N/A N/A N/A Discharge Canal 02/03/12 Water 3599 N/A N/A N/A N/A Storm Drain Outfall N/A N/A N/A Drain02/03/12 Water <1400 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm 02/03/12 Water < 1400 N/A N/A N/A N/A N/A N/A N/A Drain Outfall PZ-3 02/03/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-4 02/03/12 Water < 1380 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/03/12 Water 42851 N/A N/A N/A N/A N/A N/A N/A PZ-3 02/09/12 Water <1353 N/A N/A N/A N/A N/A N/A N/A GWP-4 02/09/12 Water < 1353 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/09/12 Water 48741 N/A N/A N/A N/A N/A N/A N/A PZ-3 02/17/12 Water <1342 N/A N/A N/A N/A N/A N/A N/A GWP-4 02/17/12 Water < 1342 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/17/12 Water 145169 N/A N/A N/A N/A N/A N/A N/A PZ-2 02/23/12 r 4 9 INSUFFICIENT VOLUMETO SAMPLE N / N PZ-1 02/23/12 INSUFFICIENT VOLUME TO SAMPLE GWP-3 02/23/12 Water <1364 N/A N/A N/A N/A N/A N/A N/A PZ-3 02/23/12 Water < 1364 N/A N/A N/A N/A N/A N/A N/A GWP-4 02/23/12 Water < 1364 N/A N/A N/A N/A N/A N/A N/A GWP-5A 02/23/12 Water < 1364 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/23/12 Water 48078 N/A N/A N/A N/A N/A N/A N/A GWP-7 02/23/12 Water <1364 N/A N/A N/A N/A N/A N/A N/A GWP-8 02/23/12 Water < 1364 N/A N/A N/A N/A N/A N/A N/A GWP-9 02/23/12 Water < 1364 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/27/12 Water 147538 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/01/12 Water <41388 N/A N/A N/A N/A N/A N/A N/A GWP-4 03/01/12 Water < 1388 N/A N/A N/A N/A N/A N/A N/A 14

, , _ L *r_,.

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12112) 1 st Quarter 2012 Gamma - Alpha Sample Date Media H-3 Emitting 1-131 Sr-89190 Fe-55 Ni-63 TRU Pu-241 Particulates GWP-6 03/01/12 Water 43948 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/05/12 Water 53703 N/A N/A N/A N/A N/A N/A N/A U-1 Auxiliary/Fuel Building Ground WaterMoni 03/07/12 Water <1362 N/A N/A N/A Water Monitoring N/A N/A N/A N/A Sump U-2 Auxiliary/Fuel Building Ground Waterouni 03/07/12 Water <1362 N/A N/A N/A Water Monitoring N/A N/A N/A N/A Sump U-2 Outside Mat 03/07/12 Water <1362 N/A N/A N/A N/A N/A N/A N/A Sump _____ _______ ___

U-2 Inside Mat 03/07/12 Water <1362 N/A N/A N/A N/A N/A N/A N/A Sump U-i Mat Sump 03/07/12 Water <1362 N/A N/A N/A N/A N/A N/A N/A South U-1 Mat Sump East 03/07/12 Water <1362 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/08/12 Water 57439 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/12/12 Water 1532 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/12/12 Water 63293 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/15/12 Water 1518 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/15/12 Water 69384 N/A N/A N/A N/A N/A N/A N/A GWP-3 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A GWP-4 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A GWP-5A 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/19/12 Water 3530 N/A N/A N/A N/A N/A N/A N/A GWP-8 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A AFW Tunnel Sump 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A

  1. 1 AFW Tunnel Sump 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A
  1. 1 AFW Tunnel Sump 03/19/12 Water < 1365 N/A N/A N/A N/A N/A N/A N/A PZ-2 03/22/12 Water < 1391 N/A N/A N/A N/A N/A N/A N/A PZ-1 03/22/12 INSUFFICIENT VOLUME TO SAMPLE GWP-3 03/22/12 Water < 1391 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/22/12 Water 12828 N/A N/A N/A N/A N/A N/A N/A GWP-7 03/22/12 Water < 1391 N/A N/A N/A N/A N/A N/A N/A GWP-9 03/22/12 Water < 1391 1 N/A N/A N/A N/A I N/A N/A N/A 15

,*- I-g ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12/12) 1 st Quarter 2012 Sample Gamma - Alpha Sampe Date SMedia H-3 Emitting Particulates 1-131 Sr-89/90 Fe-55 Ni-63 TRU I Pu-241 PZ-2(1" 03/22/12 Water < 1340 ND ND N/A N/A N/A N/A N/A GWP-61 11 03/25/12 Water 18800 ND ND N/A N/A N/A N/A N/A PZ-3(11 03/25/12 Water 11500 ND ND N/A N/A N/A N/A N/A PZ-3(21 03/25/12 Water 13400 N/A N/A N/A N/A N/A N/A N/A BTW-1 "' 03/25/12 Water < 1340 ND ND N/A N/A N/A N/A N/A BTW-2(I' 03/25/12 Water < 1330 ND ND N/A N/A N/A N/A N/A BTW-4(11 03/25/12 Water < 1300 ND ND N/A N/A N/A N/A N/A TTW-1(11 03/25/12 INSUFFICIENT VOLUME TO SAMPLE TTW-2(1" 03/25/12 Water < 1340 ND ND N/A N/A N/A N/A N/A TTW-3(1 ) 03/25/12 Water < 1300 ND ND N/A N/A N/A N/A N/A TTW-4'1" 03/25/12 Water < 1320 ND ND N/A N/A N/A N/A N/A TTW-51 ) 03/25/12 Water < 1330 ND ND N/A N/A N/A N/A N/A GWP-6 03/6/1 Water 383 N/A N/A N/A N/AN/A N/A N/A (1) Vendor Analyses (2) Vendor 2 nd analysis 16

-t,- i- ,

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01112 - 12112) 2"d Quarter 2012 Sample Date Sample H-3 Gamma -Emitting 1-131 Sr- Alpha Pu-241 Media Particulates 89/90 F5 N6 TRU GWP-6 04/02/2012 WATER 54704 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/05/2012 WATER 60252 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/09/2012 WATER 60471 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/12/2012 WATER 64047 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/16/2012 WATER 58642 N/A N/A N/A N/A N/A N/A N/A PZ-3 04/19/2012 WATER <1368 N/A N/A N/A N/A N/A N/A N/A GWP-4 04/19/2012 WATER < 1368 N/A N/A N/A N/A N/A N/A N/A GWP-5 04/19/2012 WATER < 1368 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/19/2012 WATER 42590 N/A N/A N/A N/A N/A N/A N/A GWP-7 04/19/2012 WATER <1368 N/A N/A N/A N/A N/A N/A N/A PZ-37" 04/19/2012 WATER 1360 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/23/2012 WATER 49207 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP EAST 04/23/2012 WATER <1370 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP SOUTH 04/23/2012 WATER < 1370 N/A N/A N/A N/A N/A N/A N/A U-1 ABGWMS 04/23/2012 WATER < 1370 N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 04/23/2012 WATER < 1370 N/A N/A N/A N/A N/A N/A N/A U-2 MAT SUMP INSIDE 04/23/2012 WATER < 1370 N/A N/A N/A N/A N/A N/A N/A U-2 MAT SUMP 04/23/2012 WATER < 1370 N/A N/A N/A N/A N/A N/A N/A OUTSIDESUMP GWP-6 04/26/2012 WATER 32500 N/A N/A N/A N/A N/A N/A N/A Co-58 1.99E+4 Co-60 6.39E+4 WATER FROM 1-QS-59 Ag-110M 5.53E+3 04/29/12 WATER 3.59E+7 Sb-124 7.53E+3 ND N/A N/A N/A N/A N/A CARBOy(2)

Nb-95 6.56E+3 Zr-95 2.77E+3

_Cs-137 4.15E+3 I PZ-3 04/30/2012 WATER < 1403 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/30/2012 WATER 50364 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/03/2012 WATER < 1397 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/03/2012 WATER 51380 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/07/2012 WATER < 1339 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/07/2012 WATER 43299 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/10/2012 WATER < 1411 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/10/2012 WATER 40120 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/14/2012 WATER <1419 N/A N/A N/A N/A N/A N/A N/A GWP-6 U-WQP-6OO 05/14/2012 05/14/2012 WATER WATER 39718

<1419 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A U-1 QSPH ROOF WATER < 1419 N/A N/A N/A N/A N/A N/A N/A DRAINS 05/14/2012 U-UTFDRAINS 05/14/2012 WATER <1419 N/A N/A N/A N/A N/A N/A N/A U-2 OUTFALL 05/14/2012 WATER U-1UTFLL 5/1/202 << 1419 WTER 119 N/A

/A N/A

/A N/A

/A N/A

/A N/A

/A N/A N/A N/A N/A L U-20OUTFALL 05/14/2012 WATER < 1419 N/A N/A IN/A N/A IN/A I/ I/

(1) Vendor Analysis (2) Results are not ground water results, but sample was from installed catch container.

17

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12112) 2nd Quarter 2012 Sample Date Sample Gamma -Emitting 1-131 Sr- Fe-56 Ni-63 Alpha Pu-241 Media Particulates 89190 TRU DISCHARGE CANAL 05/14/2012 WATER 2255 N/A N/A N/A N/A N/A N/A N/A OUTFALL ________________

PZ-3 05/17/2012 WATER < 1331 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/17/2012 WATER 55404 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/21/2012 WATER < 1353 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/21/2012 WATER 55852 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/24/2012 WATER < 1306 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/24/2012 WATER 53909 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/29/2012 WATER 45777 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/31/2012 WATER 45809 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/04/2012 WATER 46546 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/07/2012 WATER 42942 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP EAST 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP SOUTH 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A U-1 ABGWMS 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A U-2 MAT SUMP INSIDE 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A U-2 MAT SUMP 06/07/2012 WATER < 1362 N/A N/A N/A N/A N/A N/A N/A OUTSIDE PZ-2(1) 06/0712012 WATER < 805 N/A N/A N/A N/A N/A N/A N/A GWP-6() 06/07/2012 WATER 46100 ND ND N/A N/A N/A N/A N/A BTW-111) 06/10/2012 WATER < 831 ND ND N/A N/A N/A N/A N/A BTW-2(') 06/10/2012 WATER <805 ND ND N/A N/A N/A N/A N/A BTW-4(1) 06/10/2012 WATER < 823 ND ND N/A N/A N/A N/A N/A TTW-101 ) 06/10/2012 WATER Insufficient volume to sample TTW-2(1 ) 06/10/2012 WATER < 805 ND ND N/A N/A N/A N/A N/A TTW-3(1) 06/10/2012 WATER < 802 ND ND N/A N/A N/A N/A N/A TTW-4(1) 06/10/2012 WATER < 823 ND ND N/A N/A N/A N/A N/A TTW-5"') 06/10/2012 WATER < 812 ND ND N/A N/A N/A N/A N/A PZ-1i0 06/11/2012 WATER Insufficient volume to sample PZ-3(') 06/11/2012 WATER 1070 ND ND N/A N/A N/A N/A N/A PZ-2 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A PZ-3 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-3 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-4 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-5A 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/11/2012 WATER 50616 N/A N/A N/A N/A N/A N/A N/A GWP-7 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-8 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A GWP-9 06/11/2012 WATER < 1374 N/A N/A N/A N/A N/A N/A N/A (1) Vendor analyses 18

  • ~. " A ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12/12) 2 nd Quarter 2012 Sample Date Sample H-3 Gamma -Emitting Sr- Fe-56 Ni-63 Pu-241 Media Particulates 89/90 TRU GWP-6 06/14/2012 WATER 49678 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/18/2012 WATER 50464 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/21/2012 WATER 49527 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/25/2012 WATER 50648 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/28/2012 WATER 52180 N/A N/A N/A N/A N/A N/A N/A 19

& .. S.

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12112) 3rd Quarter 2012 Sample Date Sample Media H-3 Gamma -Emitting Particulates 1-131 Sr-89190 Fe-55 F5 Ni-63 Alpha TRU Pu-241 GWP-6 07/02/2012 WATER 52532 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/05/2012 WATER 46660 N/A N/A N/A N/A N/A N/A N/A WATER FROM RWST 07/05/2012 WATER < 1267 N/A N/A N/A N/A N/A N/A N/A BASE ___ _______ __ ______

I_____ I_______

GWP-6 07/09/2012 WATER 54306 N/A N/A N/A N/A N/A N/A N/A U-3 Well 81 07/11/12 WATER < 717 ND ND N/A N/A N/A N/A N/A U-3 Well 8 07/12/12 WATER < 1419 ND ND N/A N/A N/A N/A N/A GWP-6 07/12/2012 WATER 42073 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/16/2012 WATER 40313 N/A N/A N/A N/A N/A N/A N/A U-3 Well SS-1 USWITCHYARD) 07/18/2012 WATER < 993 ND ND N/A N/A N/A N/A N/A U-3 Well SS-1 USWITCHYARD) 07/18/2012 WATER < 1310 ND ND N/A N/A N/A N/A N/A GWP-6 07/19/2012 WATER 50145 N/A N/A N/A N/A N/A N/A N/A Sr-89/90:

ISFSI Well #1 07/19/25 WATER < 999 ND < 7.69 < 1.95 N/A N/A N/A N/A 0.707 Sr-89/90:

ISFSI Well #4(3) 07/19/25 WATER < 996 ND < 9.42 < 2.00 N/A N/A N/A N/A 0.639 GWP-6 07/23/2012 WATER 39741 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/26/2012 WATER 52912 N/A N/A N/A N/A N/A N/A N/A GWP-6 -5" 07/30/2012 WATER 35410 N/A N/A N/A N/A N/A N/A N/A GWP-6 -2.25' 07/30/2012 WATER 54055 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/30/2012 WATER 65136 N/A N/A N/A N/A N/A N/A N/A Condensation from 08/02/2012 WATER < 1411 N/A N/A N/A N/A N/A N/A N/A RWST HX GWP-6 -5" 08/02/2012 WATER 40601 N/A N/A N/A N/A N/A N/A N/A GWP-6 -2.25' 08/02/2012 WATER 57188 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/02/2012 WATER 65268 N/A N/A N/A N/A N/A N/A N/A GWP-6 (upper 5") 08/07/2012 WATER 86831 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/09/2012 WATER 61747 N/A N/A N/A N/A N/A N/A N/A U-1 INTAKE YARD 08/09/2012 WATER < 1288 N/A N/A N/A N/A N/A N/A N/A DRAIN OUTFALLR U-2 INTAKE YARD 08/09/2012 WATER < 1288 N/A N/A N/A N/A N/A N/A N/A DRAIN OUTFALL _____ _______ __ __

DISCHARGE CANAL YARD DRAIN OUTFALL 08/09/2012 WATER 1578 N/A N/A N/A N/A N/A N/A N/A SUBSURFACE DRAINS 08/09/2012 WATER < 1288 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/13/2012 WATER 60022 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/16/2012 WATER 57178 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/20/2012 WATER 50982 N/A N/A N/A N/A N/A N/A N/A VACUUM PRIMING 2 HOUSE DRAIN LINE 08/21/12 WATER < 3370 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/23/2012 WATER 54261 N/A N/A N/A N/A N/A N/A N/A 1-oS-35 Catch 08/23/2012 WATER 27768 N/A N/A N/A N/A N/A N/A N/A Container2______ _____ ___ ________ ___ ___ ___ ___

GWP-6 08/27/2012 WATER 53918 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/30/2012 WATER 44543 N/A N/A N/A N/A N/A N/A N/A (1) Vendor Analysis (2) Not a ground water sample (3) Sample taken as part of agreement with Louisa County, VA. Not a GWPP program sample 20

, '"* + .. 1, ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12/12) 3rd Quarter 2012 Sample Date Sample H-3 Gamma -Emitting 1-131 Sr- Fe-55 Ni-63 Pu-241 Media Particulates 89/90 TRU GWP-6 09/03/2012 WATER 55390 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/07/2012 WATER 60745 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/10/2012 WATER 65799 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/13/2012 WATER 67043 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/17/2012 WATER 70930 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP EAST 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A U-1 MAT SUMP SOUTH 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A U-2 MAT SUMP 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A OUTSIDE__ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ __ _ _ _ __ __ _ _

U-2 MAT SUMP INSIDE 09/17/2012 WATER < 1338 N/A N/A N/A N/A N/A N/A N/A 1

BTW-1 09/17/2012 WATER < 749 ND ND N/A N/A N/A N/A N/A BTW-2 1 09/17/2012 WATER < 788 ND ND N/A N/A N/A N/A N/A BTW-4 1 09/17/2012 WATER < 803 ND ND N/A N/A N/A N/A N/A 1

TTW-1 09/17/2012 WATER Insufficient volume to sample TTW-2' 09/17/2012 WATER < 787 ND ND N/A N/A N/A N/A N/A TT-'09/17/2012 WATER < 794 ND ND N/A jN/A jN/A N/A N/A PZ-2 09/20/12 WATER Insufficient volume to sample PZ-1 09/20/12 WATER Insufficient volume to sample GWP-3 09/20/12 WATER N/A ND N/A N/A N/A N/A N/A PZ-3 1 09/20/12 WATER < 1610 N/A N/A N/A N/A N/A N/A N/A PZ-3 1 09/20/12 WATER 1120 ND ND N/A N/A N/A N/A N/A PZ-3 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-4 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-5A 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/20/12 WATER 71387 N/A N/A N/A N/A N/A N/A N/A GWP-6 1 09/20/12 WATER 67000 ND ND ND ND ND ND ND GWP-7 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-8 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-9 09/20/12 WATER < 1327 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/24/12 WATER 59726 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/27/12 WATER 52120 N/A N/A N/A N/A N/A N/A N/A

__TTW_42 10/01/2012 WATER < 804 ND ND N/A N/A N/A N/A N/A TTW-5_2 10/01/2012 WATER < 802 ND ND N/A N/A N/A N/A N/A (1) Vendor analyses (2) 3rd Quarter sample. Scheduled for 15th September. Sample taken within grace period.

21

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ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01112 - 12112) 3rd Quarter 2012 Date Sample Boron Sample Media I.glL U-1 AB/FB GWMS 09/17/2012 Water 187 U-2 AB/FB GWMS 09/17/2012 Water 93.0 U-1 MAT SUMP EAST 09/17/2012 Water 196 U-1 MAT SUMP SOUTH 09/17/2012 Water 176 U-2 MAT SUMP INSIDE 09/17/2012 Water 114 U-2 MAT SUMP 09/17/2012 Water 101 OUTSIDE GWP-3 09/20/2012 Water 96.1 PZ-3 09/20/2012 Water 181 GWP-4 09/20/2012 Water 59.3 GWP-5A 09/20/2012 Water 61.9 GWP-6 09/20/2012 Water 8440 GWP-7 09/20/2012 Water 47.9 GWP-8 09/20/2012 Water 73.4 GWP-9 09/20/2012 Water 77.9 22

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ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/12 - 12/12) 4th Quarter 2012 Sample H-3~1~% Moisture Gamma -

Sample Date Media 1-141) Emitting 1-131 Sr-89/90 Fe-55 Ni-63 TRU Pu-241 Particulates GWP-6 10/01/12 WATER 56959 N/A N/A N/A N/A N/A N/A N/A N/A 1-4 10/03/12 SOIL(21 < 2.45 16.67 N/A N/A N/A N/A N/A N/A N/A 1-8 10/03/12 SOIL(2) < 4.11 15.71 N/A N/A N/A N/A N/A N/A N/A 3-3 10/03/12 SOIL(2) < 2.10 8.46 N/A N/A N/A N/A N/A N/A N/A 4-3 10/03/12 SOIL12) < 2.13 7.47 N/A N/A N/A N/A N/A N/A N/A 6-4 10/04/12 SOIL(2) 33.6 8.90 N/A N/A N/A N/A N/A N/A N/A 6-8 10/04/12 SOIL(2) < 4.10 9.88 N/A N/A N/A N/A N/A N/A N/A 7-4 10/04/12 SOIL(2) < 3.45 9.88 N/A N/A N/A N/A N/A N/A N/A 7-8 10/04/12 SOIL(2) < 2.96 9.98 N/A N/A N/A N/A N/A N/A N/A 9-4 10104112 SOILa) < 2.85 11.7 N/A N/A N/A N/A N/A N/A N/A 9-8 10/04/12 SOIL(2) < 2.82 9.14 N/A N/A N/A N/A N/A N/A N/A 10-4 10/04/12 SOIL(2) 36.3 11.86 N/A N/A N/A N/A N/A N/A N/A 10-8 10/04112 SOIL(2) < 2.55 8.81 N/A N/A N/A N/A N/A N/A N/A 11-4 10/04/12 SOIL(2) 17.8 12.89 N/A N/A N/A N/A N/A N/A N/A 11-8 10/04112 SOIL(2) < 2.51 8.13 N/A N/A N/A N/A N/A N/A N/A 12-4 10/04/12 SOIL(2) <3.38 13.31 N/A N/A N/A N/A N/A N/A N/A 12-8 10/04/12 SOIL(2) < 2.62 9.45 N/A N/A N/A N/A N/A N/A N/A 13-2 10/04/12 SOIL(2) <2.93 6.87 N/A N/A N/A N/A N/A N/A N/A 14-2 10/04/12 SOIL(2) < 2.21 12.51 N/A N/A N/A N/A N/A N/A N/A 15-2 10/04/12 SOIL12) < 2.10 13.92 N/A N/A N/A N/A N/A N/A N/A 16-2 10/04/12 SOIL() < 3.02 12.91 N/A N/A N/A N/A N/A N/A N/A GWP-6 10/04/12 WATER 63896 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/08/12 WATER 43582 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/11/12 WATER 41341 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/15/12 WATER 35785 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/18/12 WATER 32026 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/22/12 WATER 27590 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 10/25/12 WATER 28710 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 11/01/12 WATER 28043 N/A N/A N/A N/A N/A N/A N/A N/A PZ-3 11/01/12 WATER < 1363 N/A N/A N/A N/A N/A N/A N/A N/A U-1 INTAKE STORM 11/01/12 WATER < 1363 N/A N/A N/A N/A N/A N/A N/A N/A DRAINS U-2 INTAKE STORM 11/01/12 WATER < 1363 N/A N/A N/A N/A NJA N/A N/A N/A DRAINS DISCHARGE CANAL STORM 11/01/12 WATER 1784 N/A N/A N/A N/A N/A N/A N/A N/A DRAINS GWP-6 11/05/12 WATER 28774 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 11/08/12 WATER 40619 N/A N/A N/A N/A N/A N/A N/A N/A GWP-6 11/13/12 WATER 33567 N/A N/A N/A N/A N/A N/A N/A N/A (1) pCi/L for water samples, pCi/g for soil (2) Vendor Analysis 23

  • *-~) , ~. .~

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01112 - 12/12) 41h Quarter 2012 Sample Date Sample Gamma -Emitting 1-131 Sr- Fe-55 Ni-63 Pu-241 Media H-3 Particulates 89190 TRU GWP-6 11/15/12 WATER 35671 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 11/15/12 WATER <1350 N/A N/A N/A N/A N/A N/A N/A Subsurface drains 11/15/12 WATER 2296 N/A N/A N/A N/A N/A NIA N/A GWP-6 11/19/12 WATER 36366 N/A N/A N/A N/A N/A N/A N/A GWP-6 11/28/12 WATER 34573 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/04/12 WATER 28491 N/A N/A N/A N/A N/A N/A N/A 1

BTW-46 12/04/12 WATER <784 ND ND N/A N/A N/A N/A N/A BTW-4(1) 12/04/12 WATER < 833 ND ND N/A N/A N/A N/A N/A TTW-511) 12/04/12 WATER < 784 ND ND N/A N/A N/A N/A N/A BTW-1(1) 12/05/12 WATER < 788 ND ND N/A N/A N/A N/A N/A BTW-21() 12/05/12 WATER < 792 ND ND N/A N/A N/A N/A N/A TTW-10) 12/05/12 WATER Insufficient volume to sample TTW-13() 12/05/12 WATER <841 ND ND N/A N/A N/A N/A N/A 1

TTWV-2( ) 12/06/12 WATER < 782 ND ND N/A N/A N/A N/A N/A PZ-2(') 12/09/12 WATER Insufficient volume to sample PZ-1(1) 12/09/12 WATER Insufficient volume to sample GWP-3(") 12/09/12 WATER < 926 N/A N/A N/A N/A N/A N/A N/A PZ-3(1) 12/09/12 WATER < 928 ND ND N/A N/A N/A N/A N/A 1

GWP-4( ) 12/09/12 WATER < 842 N/A N/A N/A N/A N/A N/A N/A GWP-5A(1 ) 12/09/12 WATER < 830 N/A N/A N/A N/A N/A N/A N/A GWP-6(') 12/09/12 WATER 22900 ND ND N/A N/A N/A N/A N/A GWP-7(') 12/09/12 WATER < 836 N/A N/A N/A N/A N/A N/A N/A GWP-8(1 ) 12/09/12 WATER < 841 N/A N/A N/A N/A N/A N/A N/A GWP-9(1) 12/09/12 WATER < 925 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/09/12 WATER 17438 N/A N/A N/A N/A N/A N/A N/A GWP-3 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/09/12 WATER 1303 N/A N/A N/A N/A N/A N/A N/A GWP-4 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A GWP-5A 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A GWP-7 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A GWP-8 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A GWP-9 12/09/12 WATER < 1298 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/11/12 WATER 19655 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/20/12 WATER 13500 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/27/12 WATER 14040 N/A N/A N/A N/A N/A N/A N/A (1) Vendor Analyses 24

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/12 - 12112)

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

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution 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, Rev. 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 Ref. Reg. Guide 1.21, Rev. 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 23 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 16.1 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 PWR 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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P'Vjbl'c 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 2.34E-1 mrem from the inhalation pathway, or 1.56E-02%TS of the 1500 mrem/yr dose rate limit and 1.02 mrem from the ingestion pathway or 3.40% TS of the 1 0CFR50, 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.

26

Miscellaneous There were two entries on the Annual Effluent Release Report Log for 2012.12-001 there was a typographical error on the 2010 Annual Radioactive Effluent Report where "2009" vice "2010" was reported for the year of the Land Use Census.12-002 there was a footnote on Table 3 in the 2011 report that should have used (4) asterisks, when in fact it did not. This has been fixed for the 2012 Report.

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