ML081280633

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Annual Radioactive Effluent Release Report, (01/01/07 - 12/31/07)
ML081280633
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/28/2008
From:
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation
References
Download: ML081280633 (28)
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Text

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2007 TO DECEMBER 31, 2007)

PREPARED BY:

Uupervisor Radiological Analysis REVIEWED BY: :___

Supervisor 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 01,2007 TO DECEMBER 31, 2007 INDEX Section No. Subject Page 1 EXECUTIVE

SUMMARY

.................................. 1 -2 2 PURPOSE AND SCOPE ................................... 2 3 D ISC USSIO N................................................. 3 -'4 4 SUPPLEMENTAL INFORMATION ....................... 4 - Effluent Release Data ................................. 5 - Annual and Quarterly Doses ........................ 6 - Revisions to Offsite Dose Calculation Manual (O DCM ) ....................................... 7 - Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment System s ................................................ 8 - Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrum entation ...................................... 9 Unplanned Releases ................................ 10 Lower Limits of Detection (LLD) for Effluent Sample Analysis ........................... 11 - 12 Results of Ground Water Protection Initiative 13- 15 Sample Analysis

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 2007 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, 2007, 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 2007.

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 reporting criteria of the NEI Ground Water Protection Initiative.

Based on the 2007 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 6.22E-1 mrem, which is 1.04E+1 % of the dose limit and the critical organ dose due to liquid effluents was 8.36E-1 mrem, which is 4.18E+0% of the dose limit.
b. The air dose due to noble gases was 1.33E-3 mrad gamma, which is 6.65E- 3% of the annual gamma dose limit, and 2.76E-3 mrad beta, which is 6.91 E-3%-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 was 5.09E-2 mrem, which is 1.70E-1 % of the annual dose limit.

There were no major changes to radioactive liquid, gaseous, and solid waste treatment systems during this reporting period.

There were three revisions to the Offsite Dose Calculation Manual during this reporting period.

1

1.0 EXECUTIVE

SUMMARY

(cont.)

Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1, 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 Mayl st of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period, in Attachment 6.

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

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.7.2.a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluation are included. 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

3.0 DISCUSSION The basis for the calculation of the percent of Technical Specification for the critical organ in Table 1A of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-1 31 & 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 thyroid via the inhalation pathway.

The basis for the calculation of percent of Technical Specification for the total body and skin in Table 1A of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 gCi/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, 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 from radioactive materials in liquid effluents in unrestricted areas is defined as an adult. The total body dose was determined for this individual. The critical organ was determined to be the child liver.

As shown in Attachment 6 there were no unplanned releases meeting the requirements of 6.7.2.a.3 of the ODCM.

3

3.0 DISCUSSION (cont.)

The typical Lower Limit of Detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).

4.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is made to determine if new location(s) have been identified for the radiological environmental monitoring program pursuant to the ODCM. No changes were made.

Section 6.6.1 .b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples, as required by the ODCM, section 6.6.1, were collected from two stations during the period covered by this report. Milk samples from Station 27 could not be collected during 2007, due to the milch animal no longer being available. The leafy vegetation samples for Vegetation stations 14, 15, 16, 21, 23 and 26, as applicable, were not collected for the months of January, February, March, April, November and December 2007 due to seasonal unavailability. All other vegetation samples were obtained and analyzed as required during the time period covered by this report.

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 and soil samples from various locations on the site.

4

A'TACHMENT 1 EFFLUENT RELEASE DATA (01/07 - 12/07)

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 (01/07 - 12/07)

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

A. Fission and Activiation Gases:

1. Total Release Curies 9.40E+00 2.29E+00 1.80E+1
2. Average Release Rate For Period pCi/sec 1.21 E+00 2.91 E-01 B. lodines:
1. Total Iodine-131 Release Curies 5.79E-04 1.98E-05 2.80E+1
2. Average Release Rate For Period pCi/sec 7.44E-05 2.54E-06 C. Particulate (Tl/2 > 8 days):
1. Total Particulate (T1/2> 8 days) Release Curies 1.03E-02 8.91 E-06 2.80E+1
2. Average Release Rate For Period gCi/sec 1.32E-03 1.13E-06
3. Gross Alpha Radioactivity Release Curies 2.1OE-07 3.38E-07 D. Tritium:
1. Total Release Curies 7.28E+00 2.82E+01 3.10E+1
2. Average Release Rate For Period pCi/sec 9.36E-01 3.59E+00 E. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 5.91 E-04 2.49E-04
2. Skin Dose Rate  % 2.29E-04 7.24E-05
3. Critical Organ Dose Rate  % 1.32E-03 2.48E-03

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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

A. Fission and Activiation Gases:

1. Total Release Curies 4.78E+00 5.44E-01 1.80E+1
2. Average Release Rate For Period iiCi/sec 6.01 E-01 6.84E-02 B. Iodines:
1. Total Iodine-131 Release Curies 2.64E-04 4.74E-08 2.80E+1
2. Average Release Rate For Period pCi/sec 3.32E-05 5.96E-09 C. Particulate (Tl/2> 8 days):
1. Total Particulate (T1/2>8 days) Release Curies 1.16E-05 1.07E-05 2.80E+1
2. Average Release Rate For Period ACi/sec 1.46E-06 1.34E-06
3. Gross Alpha Radioactivity Release Curies 3.48E-07 1.02E-07 D. Tritium:
1. Total Release Curies 1.33E+01 6.45E+00 3.10E+1
2. Average Release Rate For Period jiCi/sec 1.67E+00 8.11 E-01 E. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 9.45E-05 1.48E-05
2. Skin Dose Rate  % 3.80E-05 6.19E-06
3. Critical Organ Dose Rate  % 1.45E-03 5.36E-04

TABLE 1 B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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

Krypton - 85 Ci N/D N/D 6.34E-02 1.11 E+00 Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D 2.57E-04 N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131 m Ci N/D N/D 7.99E-03 . 4.26E-02 Xenon - 133 Ci 2.66E+00 3.30E-01 1.14E+00 6.11E-01 Xenon - 133m Ci N/D N/D 1.42E-02 N/D Xenon - 135 Ci 1.19E-02 N/D 2.44E-03 3.89E-05 Xenon - 135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D 4.29E-04 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 4.89E-03 N/D 1.04E-04 6.15E-05 Total For Period Ci 2.68E+00 3.30E-01 1.23E+00 1.76E+00 lodines:

Iodine - 131 Ci 4.52E-07 6.54E-07 N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci 4.52E-07 6.54E-07 N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/Df 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 1.03E-02 N/D N/D N/D

TABLE 1 B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/07 -12/07)

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) Ci Total for Period (T1/2 > 8 days) Ci 1.03E-02 N/D N/D N/D Total for Period (Ti/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci 1.03E-02 N/D N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 9.88E-01 6.55E-01 1.13E-02 6.60E-04

TABLE 1 B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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 3.32E-01 7.61 E-02 Krypton - 85m Ci NID N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/DI Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131 m Ci N/D N/D 2.57E-02 1.12E-02 Xenon - 133 Ci 1.10E+00 1.08E-01 2.66E+00 2.08E-01 Xenon - 133m Ci N/D N/D 3.51 E-02 3.26E-03 Xenon - 135 Ci N/D N/D 4.06E-02 1.61 E-02 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 2.21 E-02 6.43E-03 N/D N/D Total For Period Ci 1.12E+00 1.14E-01 3.09E+00 3.15E-01 lodines:

Iodine- 131 Ci 3.33E-06 4.74E-08 N/D N/D Iodine - 133 Ci 1:35E-06 N/D N/D N/D Iodine- 135 Ci N/D N/D N/D N/D Total For Period Ci 4.68E-06 4.74E-08 N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 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 1.07E-08 1.29E-08 N/D N/D

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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 Other (Specify)

Total for Period (T1/2 > 8 days) Ci 1.07E-08 1.29E-08 N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci 1.07E-08 1.29E-08 N/D N/D GROSS ALPHA: Ci 8.93E-11 N/D N/D N/D TRITIUM: Ci 7.12E-01 4.OOE-01 9.51 E-03 5.09E-04

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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 2.41 E-02 4.26E-02 Krypton - 85m Ci N/D N/D 1.45E-05 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131 m Ci N/D N/D 4.60E-03 1.97E-04 Xenon - 133 Ci N/D N/D 4.99E+00 4.08E-02 Xenon - 133m Ci N/D N/D 3.56E-03 1.61 E-05 Xenon - 135 Ci N/D N/D 4.69E-01 1.40E-03 Xenon- 135m 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 1.13E-01 N/D 1.13E-06 Total For Period Ci N/D 1.13E-01 5.49E+00 8.50E-02 lodines:

Iodine - 131 Ci 5.78E-04 1.71 E-05 6.44E-08 2.OOE-06 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 5.78E-04 1.71 E-05 6.44E-08 2.0OE-06 Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D 1.15E-06 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D 8.43E-07 Zinc - 65 Ci N/D N/D N/D 1.46E-13 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

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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

Cesium - 137 Ci N/D N/D N/D 1.45E-06 Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify) Ci Chromium-51 (T1/2 > 8 days) Ci N/D N/D N/D 2.41 E-06 Zirconium-95 (T1/2 > 8 days) Ci N/D N/D N/D 6.85E-07 Niobium-95 (T1/2 > 8 days) Ci N/D N/D N/D 2.37E-06 Total for Period (T1/2 > 8 days) Ci N/D N/D N/D 8.91 E-06 Total for Period (Ti/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D 8.91 E-06 GROSS ALPHA: Ci 2.10E-07 3.38E-07 N/D N/D TRITIUM: Ci 3.60E+00 2.59E+01 2.68E+00 1.64E+00

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/07 - 12/07)

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 4.12E-02 2.18E-03 Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131 m Ci N/D N/D 7.99E-04 1.41 E-04 Xenon - 133 Ci N/D N/D 4.98E-01 1.07E-01 Xenon - 133m Ci N/D N/D 8.95E-05 1.14E-03 Xenon - 135 Ci N/D N/D 1.37E-03 4.38E-03 Xenon - 135m Ci N/D N/D 2.41E-02 N/D Xenon- 138 Ci N/D N/D N/D N/D Other (Specify) Ci Argon - 41 Ci N/D N/D N/D 3.87E-06 T*tal For Period Ci N/D N/D 5.66E-01 1.15E-01 lodines:

Iodine - 131 Ci 2.55E-04 N/D 5.44E-06 N/D Iodine - 132 Ci 7.48E-05 N/D 1.81 E-05 N/D Iodine - 133 Ci 5.89E-05 N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci 3.89E-04 N/D 2.35E-05 N/D Particulates:

Manganese - 54 Ci N/D N/D 2.65E-07 N/D Cobalt - 58 Ci N/D N/D 2.22E-06 N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D 2.25E-06 6.50E-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 (01/07 - 12/07)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Cesium - 137 Ci 1.64E-06 3.90E-06 6.19E-07 6.1OE-06 Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Chromium - 51 (T1/2 > 8 days) Ci N/D N/D 2.06E-06 N/D Zirconium-95 (T1/2 > 8 days) Ci N/D N/D 9.63E-07 N/D Niobium-95 (T1/2 > 8 days) Ci N/D N/D 1.59E-06 N/D Tellurium -131 m (T1/2 < 8 days) Ci N/D N/D 5.64E-07 N/D Total for Period (T1/2 > 8 days) Ci 1.64E-06 3.90E-06 9.97E-06 6.75E-06 Total for Period (T1/2 < 8 days) Ci N/D N/D 5.64E-07 N/D Total For Period Ci 1.64E-06 3.90E-06 1.05E-05 6.75E-06 GROSS ALPHA: Ci 3.48E-07 1.02E-07 N/D N/D TRITIUM: Ci 9.24E+00 5.70E+00 3.35E+00 3.49E-01

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT- SUMMATION OF ALL RELEASES FOR (01/07 - 12/07) 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 4.11 E-02 6.92E-02 2.OOE+01
2. Average diluted concentration during the period. [tCi/ml 1.37E-10 1.04E-10
3. Percent of applicable limit (T.S.)  % 2.35E-04 3.44E-04 B. Tritium:
1. Total release activity. Curies 5.87E+02 1.36E+01 2.OOE+01
2. Average diluted concentration during the period. liCi/ml 1.96E-06 2.05E-08
3. Percent of applicable limit (T.S.)  % 1.96E-02 2.05E-04 C. Dissolved and Entrained Gases:
1. Total release activity. Curies 6.55E-03 N/D 2.OOE+01
2. Average diluted concentration during the period. [tCi/m I 2.19E-11 N/D
3. Percent of applicable limit (T.S.)  % 1.09E-05 O.OOE+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies N/D N/D 2.OOE+01 E. Volume of waste released: (prior to dilution). Liters 1.36E+08 1.26E+08 3.OOE+00 F. Total volume of dilution water used during the period. Liters 2.99E+1 1 6.62E+1 1 3.OOE+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/07 - 12/07) 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 9.54E-02 5.02E-02 2.OOE+01
2. Average diluted concentration during the period. gCi/ml 1.25E-10 8.38E-11
3. Percent of applicable limit (T.S.)  % 5.39E-04 1.65E-04 B. Tritium:
1. Total release activity. Curies 4.77E+02 8.60E+01 2.OOE+01
2. Average diluted concentration during the period. ýtCi/ml 6.27E-07 1.44E-07
3. Percent of applicable limit (T.S.)  % 6.27E-03 1.44E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies 2.13E-04 N/D 2.OOE+01
2. Average diluted concentration during the period. gCi/ml 2.80E-13 N/D
3. Percent of applicable limit (T.S.)  % 1.40E-07 O.OOE+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies 5.69E-05 N/D 2.OOE+01 E. Volume of waste released: (prior to dilution). Liters 1.30E+08 1.37E+08 3.OOE+00 F. Total volume of dilution water used during the period. Liters 7.61 E+1 1 5.98E+1 1 3.O0E+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/07 - 12/07)

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 1.05E-04 7.59E-05 N/D N/A Iron - 55 Ci 5.79E-03 1.50E-02 N/D N/A Cobalt - 58 Ci 4.24E-03 4.13E-03 N/D N/A Cobalt - 60 Ci 1.53E-02 1.75E-02 N/D N/A Strontium - 89 Ci N/D 1.54E-03 N/D N/A Strontium - 90 Ci N/D N/D N/D N/A Niobium - 95 Ci 4.56E-05 1.58E-03 N/D N/A Ruthenium.- 106 Ci N/D N/D N/D N/A Silver - 110m Ci 6.92E-04 1.32E-03 N/D N/A Iodine - 131 Ci N/D 2.15E-04 N/D N/A Iodine - 133 Ci N/D N/D N/D N/A Cesium - 134 Ci 1.10E-04 3.62E-03 N/D N/A Cesium - 136 Ci N/D N/D N/D N/A Cesium - 137 Ci 9.24E-04 1.14E-02 N/D N/A Barium-Lathanum - 140 Ci N/D N/D N/D N/A Cerium - 141 Ci N/D N/D N/D N/A Antimony - 124 Ci 1.30E-04 1.41 E-03 N/D. N/A Antimony- 125 Ci 1.30E-02 7.07E-03 N/D N/A Other (Specify) Ci Sodium - 24 (T1/2 < 8 days) Ci N/D 7.15E-04 N/D N/A Chromium - 51 (T1/2 > 8 days) Ci 3.35E-04 2.90E-03 N/D N/A Niickel - 63 (T1/2 > 8 days) Ci N/D N/D N/A N/A Zirconium - 95 (T1/2 > 8 days) Ci N/D 5.09E-04 N/D N/A Silver-108m (T1/2 > 8 days) Ci 4.22E-04 1.15E-04 N/D N/A Antimony - 122 (T1/2 < 8 days) Ci N/D 8.40E-05 N/D N/A Antimony - 126 (T1/2 > 8 days) Ci N/D 3.20E-05 N/D N/A Total for Period Ci 4.11 E-02 6.92E-02 N/D N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/07 - 12/07)

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 6.55E-03 N/D N/D N/A Xenon - 133m Ci N/D N/D N/D N/A Xenon - 135 Ci N/D N/D N/D N/A Xenon - 135m Ci N/D N/D N/D N/A Other (Specify) Ci N/D N/D N/D N/A Kr-88 ( T1/2 < 8 days) Ci N/D N/D N/D N/A Kr-85 (T1/2 > 8 days) Ci N/D N/D N/D N/A Total for Period Ci 6.55E-03 N/D N/D N/A Tritium Ci 5.87E+02 1.36E+01 1.89E-08 N/A Gross Alpha Ci N/D N/D N/D N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/07 - 12/07)

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 6.91 E-04 3.24E-04 N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 9.99E-03 8.67E-03 N/A N/A Cobalt - 60 Ci 2.63E-02 1.63E-02 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 4.02E-03 1.40E-03 N/A N/A Ruthenium - 106 Ci N/D N/D N/A N/A Silver - 11 Om Ci 2.87E-03 2.48E-03 N/A N/A Iodine - 131 Ci 9.04E-05 6.77E-05 N/A N/A Iodine - 133 Ci N/D N/D N/A N/A Cesium - 134 Ci N/D 2.53E-04 N/A N/A Cesium - 137 Ci 6.20E-04 2.39E-03 N/A N/A Barium-Lathanum - 140 Ci N/D N/D N/A N/A Cerium - 141 Ci N/D N/D N/A N/A Antimony - 124 Ci 2.38E-03 1.28E-03 N/A N/A Antimony - 125 Ci 4.27E-02 1.51 E-02 N/A N/A Other (Specify)

Sodium - 24 (T1/2 < 8 days) Ci 2.10E-04 1.03E-04 N/A N/A Chromium - 51 (T1/2 > 8 days) Ci 2.69E-03 8.31 E-04 N/A N/A Iron - 59 (T1/2 > 8 days) Ci 3.96E-04 1.14E-04 N/A N/A Nickel -63 (YT1/2 > 8 days) Ci N/D N/D N/A N/A Zirconium - 95 (T1/2 > 8 days) Ci 1.65E-03 5.35E-04 N/A N/A Zirconium - 97 (T1/2 < 8 days) Ci 3.62E-04 N/D N/A N/A Silver-108m (Tl/2 > 8 days) Ci 2.39E-04 2.84E-04 N/A N/A Antimony-122 (T1/2 <8 days) Ci 1.36E-04 N/D N/A N/A Antimony-1 26 (Tl/2 > 8 days) Ci 3.60E-05 N/D N/A N/A Iodine - 132 (T1/2 < 8 days) Ci N/D 1.91 E-05 N/A N/A Total for Period Ci 9.54E-02 5.02E-02 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/07 - 12/07)

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 2.13E-04 N/D N/A N/A Xenon - 133m Ci N/D N/D N/A N/A Xenon - 135 Ci N/D N/D N/A N/A Xenon - 135m Ci N/D N/D N/A N/A Other (Specify)

Argon - 41 (T1/2 < 8 days) Ci N/D N/D N/A N/A Krypton - 85 (T1/2 > 8 days) Ci N/D N/D N/A N/A Total for Period Ci 2.13E-04 N/D N/A N/A Tritium Ci 4.77E+02 8.60E+01 N/A N/A Gross Alpha Ci 5.69E-05 N/D N/A N/A

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-07 THROUGH 12-31-07 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 3.06E+01" 2.50E+01 evaporator bottoms, etc., Ci 1.18E+02 2.50E+01
b. Dry compressible waste, contaminated m3 6.48E+02** 2.50E+01 equipment, etc., Ci 2.61 E+01 2.50E+01
c. Irradiated components, control rods, m3 0 2.50E+01 etc., Ci 0 2.50E+01
d. Other (describe)

Used Oil, Blast media, Sewage, m3 2.55E+00*** 2.50E+01 Gravel, Dessicant, Soil, Construction Ci 4.82E-04 2.50E+01 Debris

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Co-60 2.81 E+01 3.31 E+01 2.50E+01 Ni-63 2.55E+01 3.01 E+01 2.50E+01 Cs-1 37 2.25E+01 2.65E+01 2.50E+01 Co-58 9.05E+00 1.07E+01 2.50E+01 Cs-1 34 5.76E+00 6.77E+00 2.50E+01 Fe-55 4.53E+00 5.33E+00 2.50E+01 Mn-54 1.61 E+00 1.90E+00 2.50E+01 Sb-1 25 1.47E+00 1.73E+00 2.50E+01
b. Fe-55 2.62E+01 6.84E+00 2.50E+01 Cr-51 1.95E+01 5.08E+00 2.50E+01 Co-60 1.44E+01 3.76E+00 2.50E+01 Nb-95 1.33E+01 3.48E+00 2.50E+01 Zr-95 8.23E+00 2.15E+00 2.50E+01 Co-58 7.99E+00 2.09E+00 2.50E+01 Cs-1 37 3.14E+00 8.19E-01 2.50E+01 Ni-63 2.86E+00 7.46E-01 2.50E+01 Mn-54 1.22E+00 3.17E-01 2.50E+01 Fe-59 8.10E-01 2.11E-01 2.50E+01 Sb-1 25 5.51 E-01 1.44E-01 2.50E+01
c. No shipments
d. Co-60 8.53E+01 4.11E-04 2.50E+01 H-3 9.09E+00 4.38E-05 2.50E+01 Ni-63 3.73E+00 1.08E-05 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-07 THROUGH 12-31-07 Page 2 of 2

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Truck Barnwell,SC 17 Truck Oak Ridge,TN (Duratek)

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination N/A (4) shipments containing resins were shipped to a licensed waste processor for processing and/or volume reduction.

(3) shipments of resin/filters were shipped to licensed facility for disposal (13) shipments containing contaminated equipment, dry compressible waste / incinerable waste were shipped to a licensed waste processor for processing and/or volume reduction.

(2) shipments of dry compressible waste / incinerable waste was shipped to licensed facility for disposal (1) shipment containing oil/soil and other material was shipped to a licensed waste processor for volume reduction.

(Shipment also contained dry compressible waste accounted for above.)

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/07 - 12/07)

An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway will be made as required by ODCM Section 6.7.2.

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 1.73E-1 2.46E-1 1.38E-1 6.54E-2 6.22E-1 Critical Organ Dose (mrem) 2.31 E-1 3.32E-1 1.83E-1 9.01 E-2 8.36E-1 1st 2nd 3rd 4th Annual T^#ýl Noble Gas Gamma Dose (mrad) 8.40E-4 3.29E-4 1.39E-4 2.16E-5 1.33E-3 Noble Gas Beta Dose (mrad) 2.07E-3 2.70E-4 3.69E-4 5.94E-5 2.76E-3 Critical Organ Dose for 1-131, 1-133, H-3, 1.98E-2 1.43E-2 1.39E-2 3.03E-3 5.09E-2 Particulates with

""/2 > 8 days (mroem) 6

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/07 - 12/07)

As required by Technical Specification 6.15, 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 2007.

Revision 11, which was effective 03/15/07, included revisions to implement requirements for the NEI Ground Water Protection Initiative and changed the surveillance frequency requirements for the Condenser Air Ejector radiation monitors. Revision 12, which was effective 08/30/07, revised the definition of Source Check to address the MGPI gaseous effluent monitors. Finally, Revision 13, which was effective 10/08/07, revised the environmental program with the addition of an air sampling station at location 01 A, and added sample reporting requirements to the Annual Radioactive Effluent Report for the NEI Ground Water Protection Initiative.

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