ML11130A023

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Submittal of Annual Radioactive Effluent Release Report
ML11130A023
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/29/2011
From: Stanley B
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
11-219
Download: ML11130A023 (31)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 29, 2011 United States Nuclear Regulatory Commission Serial No.11-219 Attention: Document Control Desk SS&L/JSA RO Washington, DC 20555-0001 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2010 through December 31, 2010. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2010 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

If you have any further questions, please contact Paul Harris at 757-365-2692.

Sincerely, B. L. Stanley Director Safety & Licensing Surry Power Station Attachment 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

-- F-EýYpu NRC Senior Resident Inspector Surry Power Station C ý ý-o&ll

Serial No.11-219 SPS Annual Rad Effluent Report Docket Nos.: 50-280, 50-281 ATTACHMENT 1 2010 Annual Radioactive Effluent Release Report SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

Surry Power Station 2010 Annual Radioactive Effluent Release Report Dominion

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION January 1, 2010 through December 31, 2010

  • 2/CC-Prepared By: _

P. F. Blount Health Physicist Reviewed By:

P. R. Hanis Supervisor Radiological Analysis Reviewed By:

Supervisor Health Physics Technical Services Approved By:

a J.gW. Eggcalteo- a Manager Radiological Protection and Chemistry

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION January 1, 2010 through December 31, 2010 Index Section No. Subject Page 1 Executive Summary I 2 Purpose and Scope 2 3 Discussion 3 4 Supplemental Information 4 Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM)

Attachment 4 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Sample Analysis Attachment 8 Industry Ground Water Protection Initiative

FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-280, 50-281, Section 6.6.B.3.

EXECUTIVE

SUMMARY

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Annual Radioactive Effluent Release Report describes the radiological effluent control program conducted at Surry Power Station during the 2010 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Power Station in accordance with 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. The report also includes an assessment of radiation doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents.

During this reporting period, there were no unplanned liquid or gaseous effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual.

Based on the 2010 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

1. The total body dose due to liquid effluents was 2.25-04 mrem, which is 3.75E-03% of the 6 mrem dose limit. The critical organ doses due to liquid effluents, GI-LLI and Liver respectively, were 3.01E-04 mrem and 2.25E-04 mrem. These doses are 1.51 E-03% and 1.13E-03% of the respective 20 mrem dose limit.
2. The air dose due to noble gases in gaseous effluents was 2.25E-03 mrad gamma, which is 1.13E-02% of the 20 mrad gamma dose limit, and 1.03E-03 mrad beta, which is 2.58E-03% of the 40 mrad beta dose limit.
3. The critical organ dose from gaseous effluents due to 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days is 5.46E-01 mrem, which is 1.82E+00% of the 30 mrem dose limit.

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

There were no changes to VPAP-2103S, Offsite Dose Calculation Manual, during this reporting period.

In accordance with the Nuclear Energy Institute (NEI) Industry Ground Water Protection Initiative, analysis results of ground water monitoring locations not included in the Radiological Environmental Monitoring Program (REMP), will be included in this report. Ground water monitoring well sample results are provided in Attachment 8.

1

Based on the radioactivity measured and the dose calculations performed during this reporting period, the operation of Surry Power Station has resulted in negligible radiation dose consequences to the maximum exposed member of the public in unrestricted areas.

Purpose and Scope includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annual basis following the format of Tables 1,2 and 3 of Appendix B, thereof. Attachment 2 of this report 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 2010.

As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 10CFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.

As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. Additionally, a list of unplanned releases during the reporting period is included in . provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation.

As required by the ODCM, Section 6.7.5, a summary of on-site radioactive spills or leaks that were communicated in accordance with the Industry Ground Water Protection Initiative reporting protocol, and sample analyses from ground water wells that are not part of the Radiological Environmental Monitoring Program are provided in Attachment 8.

2

Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary.

The critical receptor is the child via the inhalation pathway.

The basis for the calculation of the 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 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 of Attachment I is the ODCM, Section 6.2.1, which states that the concentration of radioactive material releases in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 10CFR20, 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.OOE-04 microcuries/mL.

Percent of technical specification calculations are based on the total gaseous or liquid effluents released for the 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 the site boundary. The maximum exposed member of the public from the release of airborne iodine- 131, iodine- 133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was a child at 2.05 miles with the critical organ being the bone via the ingestion pathway. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas was an adult, exposed by either the invertebrate or fish pathway, with the critical organ typically being the gastrointestinal-lower large intestine. The total body dose was also determined for this individual.

Presented in Attachment 6 is a list of unplanned gaseous and liquid releases as required by the ODCM, Section 6.7.2.

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 volumes 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 the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower limit of detection, then the totals for this period will be designated as Not Applicable (N/A).

3

Supplemental Information Section 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk, or if required, leafy vegetation samples, and the identification for obtaining replacement samples.

As milk was available for collection during this reporting period, leafy vegetation sampling was not required.

As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program.

Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the Radiological Environmental Monitoring Program.

Beginning with the year 2010, the NRC recommended that U.S. nuclear power plants evaluate if carbon-14 is a principal radionuclide in gaseous effluents, and if so, report the quantity released in this report. Improvements in effluent management practices and fuel performance over the years have resulted in a decrease in the concentration, and a change in the distribution, of radionuclides released in gaseous effluents to the environment. At Surry Power Station, carbon-14 was determined to be a principal radionuclide in gaseous effluents. An assessment was performed using the technical guidance provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. This report includes the estimate of carbon-14 curies released from Surry Power Station in 2010. The public dose reported also includes the contribution of carbon-14.

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Attachment 1 EFFLUENT RELEASE DATA January 1, 2010 through December 31, 2010 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.

Attachment I TABLE 1A Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND  % EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 1.03E-03 8.30E-02 1.80E+01
2. AVE RELEASE RATE FOR PERIOD jiCi/sec 1.33E-04 1.06E-02 B. IODINE
1. TOTAL 1-131 Ci N/D N/D 2.80E+01
2. AVE RELEASE RATE FOR PERIOD gCi/sec N/A N/A C. PARTICULATE
1. HALF-LIFE >8 DAYS Ci N/D N/D 2.80E+01
2. AVE RELEASE RATE FOR PERIOD gCi/sec N/A N/A
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci 1.33E+01 1.21E+01 3.10E+01
2. AVE RELEASE RATE FOR PERIOD [tCi/sec 1.70E+00 1.53E+00 E. CARBON-14
1. TOTAL RELEASE Ci 2.86E-02 2.30E+00
2. AVE RELEASE RATE FOR PERIOD gCi/sec 3.67E-03 2.93E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 4.27E-04 4.17E-02 TOTAL BODY DOSE RATE  % 3.90E-06 9.59E-04 SKIN DOSE RATE  % 1.19E-06 2.38E-04

Attachment 1 TABLE 1A Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 3.36E-02 5.42E-01 1.80E+01
2. AVE RELEASE RATE FOR PERIOD gtCi/sec 4.23E-03 6.82E-02 B. IODINE
1. TOTAL 1-131 Ci N/D N/D 2.80E+01
2. AVE RELEASE RATE FOR PERIOD gtCi/sec N/A N/A C. PARTICULATE
1. HALF-LIFE >8 DAYS Ci 6.84E-07 1.94E-05 2.80E+01
2. AVE RELEASE RATE FOR PERIOD pCi/sec 8.61E-08 2.45E-06
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci 1.11E+01 9.61E+00 3.10E+01
2. AVE RELEASE RATE FOR PERIOD tCi/sec 1.40E+00 1.21E+00 E. CARBON-14
1. TOTAL RELEASE Ci 9.31E-01 1.50E+01
2. AVE RELEASE RATE FOR PERIOD [tCi/sec 1.17E-01 1.89E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 9.94E-03 6.64E-02 TOTAL BODY DOSE RATE  % 2.49E-04 4.83E-04 SKIN DOSE RATE  % 6.13E-05 1.27E-04

Attachment I TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D 1.97E-04 2.23E-04 Xe-135 Ci N/D N/D N/D 2.1OE-04 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131rm Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A 1.97E-04 4.33E-04
2. IODINES 1-131 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A
3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D 5.46E-03 1.20E-02 TOTAL FOR PERIOD Ci N/A N/A 5.46E-03 1.20E-02

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER I. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D 7.80E-04 Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D 2.72E-04 Xe-133 Ci N/D N/D 1.17E-02 3.52E-01 Xe-135 Ci 1.30E-04 N/D N/D 5.OOE-02 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D 3.OOE-03 Xe-133m Ci N/D N/D N/D 5.06E-03 Ar-41 Ci 1.98E-03 N/D N/D 9.04E-04 TOTAL FOR PERIOD Ci 2.11E-03 N/A 1.17E-02 4.12E-01

2. IODINES 1-131 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A
3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci 5.83E-02 N/D 3.23E-01 1.14E+01 TOTAL FOR PERIOD Ci 5.83E-02 N/A32E-1 3.23E-01 14+1 1.14E+01

Attachment 1 TABLE 1C Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D 2.40E-05 N/D 3.74E-03 Xe-135 Ci 1.34E-04 2.15E-04 5.58E-04 9.59E-03 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci 1.44E-04 1.22E-03 N/D 6.78E-02 TOTAL FOR PERIOD Ci 2.78E-04 1.46E-03 5.58E-04 8.11E-02
2. IODINES 1-131 Ci N/D N/D N/D N/D 1-132 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A
3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci 7.69E-03 4.04E-02 1.54E-02 2.25E+00 TOTAL FOR PERIOD Ci 7.69E-03 4.04E-02 1.4-2 1.54E-02 22E0 2.25E+00

TABLE 1C Attachment 1 Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci 1.50E-05 5.18E-05 N/D 9.10E-02 Xe-135 Ci 1.53E-04 9.84E-05 1.14E-03 7.73E-03 Xe-135m Ci 5.39E-05 4.96E-05 N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D 4.76E-05 Ar-41 Ci 1.11 E-03 6.72E-04 1.73E-02 3.08E-02 TOTAL FOR PERIOD Ci 1.33E-03 8.72E-04 1.84E-02 1.30E-01
2. IODINES 1-131 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A
3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba- 140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci 6.84E-07 1.94E-05 N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci 3.70E-02 2.41E-02 5.12E-01 3.59E+00 TOTAL FOR PERIOD Ci 3.70E-02 2.41E-02 5.12E-01 3.59E+00

Attachment 1 TABLE 2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND  % EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 4.72E-03 2.17E-03 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD gCi/mL 7.20E-12 3.07E-12
3. PERCENT OF APPLICABLE LIMIT  % 2.30E-05 1.53E-05 B. TRITIUM
1. TOTAL RELEASE Ci 1.04E+02 1. 14E+02 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD 1tCi/mL 1.58E-07 1.62E-07
3. PERCENT OF APPLICABLE LIMIT  % 1.58E-03 1.62E-03 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE Ci N/D N/D 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD tCi/mL N/A N/A
3. PERCENT OF APPLICABLE LIMIT  % N/A N/A D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE Ci N/D N/D 2.OOE+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 3.70E+07 4.21 E+07 3.OOE+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.56E+ 1I 7.06E+ 11 3.OOE+00

Attachment 1 TABLE 2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 1.81E-03 1.44E-03 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD gLCi/mL 2.47E-12 2.67E-12
3. PERCENT OF APPLICABLE LIMIT  % 9.61E-06 8.16E-06 B. TRITIUM
1. TOTAL RELEASE Ci 5.48E+02 2.20E+02 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD gCi/mL 7.46E-07 4.08E-07
3. PERCENT OF APPLICABLE LIMIT  % 7.46E-03 4.08E-03 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE Ci N/D N/D 2.OOE+01
2. AVE DIL. CONC. DURING PERIOD RiCi/mL N/A N/A
3. PERCENT OF APPLICABLE LIMIT  % N/A N/A D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE Ci N/D N/D 2.OOE+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 4.42E+07 5.03E+07 3.OOE+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.35E+11 5.38E+11 3.OOE+00

Attachment I TABLE 2B Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Fe-55 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci 5.62E-04 7.4 1E-04 N/D 5.21E-05 1-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 7.48E-04 2.13E-04 Co-60 Ci N/D 8.80E-06 2.65E-03 7.73E-04 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D 7.30E-05 1.45E-05 Cr-51 Ci N/D N/D 7.38E-05 N/D Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Tc-99m Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Ce- 141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Sb-124 Ci N/D N/D 1.91E-05 N/D Sb-125 Ci N/D N/D 5.55E-04 3.57E-04 Co-57 Ci N/D N/D 3.49E-05 6.25E-06 TOTAL FOR PERIOD Ci 5.62E-04 7.49E-04 4.16E-03 1.42E-03

Attachment 1 TABLE 2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/10 TO 12/31/10 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Fe-55 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci 6.38E-04 2.40E-04 9.48E-06 5.39E-05 1-131 Ci N/D N/D N/D 1.98E-05 Co-58 Ci N/D N/D 6.60E-05 2.39E-04 Co-60 Ci N/D N/D 6.30E-05 2.90E-04 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Cr-51 Ci N/D N/D N/D 9.92E-05 Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Tc-99m Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Ce- 141 Ci N/D N/D N/D N/D Ce- 144 Ci N/D N/D N/D N/D Sb- 124 Ci N/D N/D N/D 4.1 OE-06 Sb-125 Ci N/D N/D 1.04E-03 4.93E-04 Co-57 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci 6.38E-04 2.40E-04 1.18E-03 1.20E-03 Xe-133 Ci N/D N/D N/D N/D Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE 3 Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/10 - 12/31/10 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste 12 month Est. Total Period Error, %
a. Spent resins, filter sludges, evaporator m3 1.56E+01 Note 1 1.OOE+01 bottoms, etc. Ci 4.11E+02 3.OOE+01
b. Dry compressible waste, contaminated m3 2.92E+02 Note 2 1.00E+01 equip., etc. Ci 1.16E+00 3.OOE+01
c. Irradiated components, control m3 O.OOE+00 1.00E+01 rods, etc. Ci O.OOE+00 3.OOE+01
d. Other (Waste oil) m3 O.OOE+00 Note 3 1.00E+01 Ci 0.OOE+00 3.OOE+01
2. Estimate of major nuclide composition (by type of waste)
a. Ni-63 5.39E+01 Co-60 3.31E+01 Fe-55 5.1OE+00 Mn-54 3.30E+00 Co-58 1.71E+00 Cs-137 1.05E+00
b. Fe-55 2.71E+01 Co-58 2.58E+01 Co-60 1.86E+01 Ni-63 1.01E+01 Cs-137 7.10E+00 Cr-51 5.23E+00 Nb-95 1.1 6E+00 C.

d.

Attachment 1 TABLE 3 Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/10 - 12/31/10 CONTINUED SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 10 Truck Oak Ridge, TN (EnergySolutions) 4 Truck Erwin, TN (Studsvik)

B. IRRADIATED FUEL SHIPMENT (Disposition)

Number of Shipments Mode of Transportation Destination 0

NOTE 1: Some of this waste was shipped to licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 1.90E+01 Im3 .

NOTE 2: Some DAW was shipped to licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 1.1 OE+02 m3 .

NOTE 3: This waste was shipped to a licensed waste processor for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 9.50E-01 Im3 .

Attachment 2 Page 1 of 1 ANNUAL AND OUARTERLY DOSES 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 is made pursuant to the ODCM, Section 6.7.2, requirement.

LIQUID GASEOUS 2011 Total Body GI-LLI Liver Gamma Beta Bone (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 2.98E-05 8.46E-05 2.76E-05 5.07E-06 4.14E-06 1.72E-03 2nd Quarter 2.63E-05 3.84E-05 2.73E-05 1.26E-03 4.84E-04 1.67E-01 3rd Quarter 9.69E-05 9.66E-05 9.83E-05 3.32E-04 1.22E-04 4.25E-02 4th Quarter 7.16E-05 8.16E-05 7.19E-05 6.49E-04 4.21E-04 3.35E-01 Annual 2.25E-04 3.01E-04 2.25E-04 2.25E-03 1.03E-03 5.46E-01

Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are included with this attachment. There were no revisions to the ODCM implemented during this reporting period.

Attachment 4 Page 1 of 1 MAJOR CHANGES TO RADIOACTIVE LIQUID.

GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems for this reporting period.

Attachment 5 Page 1 of 1 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitoring instrumentation required by the ODCM Attachments 1 and 5, which were determined to be inoperable, were not returned to operable status within 30 days. Two components of the above referenced instrumentation were inoperable greater than 30 days during this reporting period.

The normal range noble gas radiation monitor, 1-VG-RM- 131 B, for the Ventilation Vent #2 stack and it's associated stack flow rate monitor, 1-VS-FT- 116, were out of service from 6/7/10 to 7/28/10. During the calibration of 1-VS-FT-1 16, the square root extractor failed rendering the stack flow rate monitor inoperable. Due to material obsolescence, Design Change SU-10-0 1092 was issued to obtain a replacement square root extractor. With 1-VS-FT- 116 electrically disconnected, a feedback loop from 1-VS-FT- 116 to the sample pump for 1-VG-RM-131B was not available. The unavailabilty of the feedback loop caused the sample pump to secure and this rendered the noble gas radiation monitor inoperable. In accordance with the ODCM, compensatory measures were instituted for Ventilation Vent #2 to provide for continuous particulate and iodine sampling, noble gas grab sampling and estimation of the of the Ventilation Vent #2 stack effluent exhaust rate. Design Change SU-10-01092 was completed on 7/27/10 and 1-VS-FT- 116 and 1-VG-RM-131B were returned to operable status on 7/28/10.

Attachment 6 Page 1 of 1 UNPLANNED RELEASES There were no unplanned liquid or unplanned gaseous releases during this reporting period.

Attachment 7 Page 1 of 1 LOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSIS GASEOUS: Isotope Required LLD Typical LLD Kr-87 1.OOE-04 2.24E 2.72E-06 Kr-88 1.OOE-04 1.98E 3.28E-06 Xe-133 1.OOE-04 8.65E 2.04E-06 Xe-133m 1.OOE-04 3.73E 8.37E-06 Xe-135 1.OOE-04 4.92E 1.06E-06 Xe-135m 1.OOE-04 2.93E 4.84E-06 Xe-138 1.OOE-04 6.04E 9.83E-06 1-131 1.OOE-12 5.99E 1.OIE-13 1-133 1.OOE-10 1.1OE-12 - 2.16E-12 Sr-89 1.OOE-1 1 1.28E-14 - 3.OOE-12 Sr-90 1.OOE-11 1.53E-15 - 3.90E-13 Cs-134 1.OOE-1 1 2.24E-14 - 4.01E-13 Cs-137 1.OOE- 11 6.90E-14 - 6.83E-13 Mn-54 1.OOE- 11 3.46E-14 - 4.44E-13 Fe-59 1.OOE-11 4.09E-14 - 1.04E-12 Co-58 1.OOE- 11 3.17E-14 - 5.45E-13 Co-60 1.OOE-11 5.59E-14 - 5.41E-13 Zn-65 1.OOE- 11 7.87E-14 - 9.91E-13 Mo-99 1.OOE-11 4.63E-13 - 4.OOE-12 Ce-141 1.OOE-1 1 4.36E-14 - 3.98E-13 Ce-144 1.OOE-11 1.59E-13 - 1.73E-12 Alpha 1.OOE-11 1.70E-14 - 1.71E-14 Tritium 1.OOE-06 6.38E-08 - 8.84E-08 LIQUID: Sr-89 5.OOE-08 1.78E-08 3.38E-08 Sr-90 5.OOE-08 3.63E-09 9.46E-08 Cs-134 5.OOE-07 5.36E-09 1.18E-08 Cs-137 5.OOE-07 1.40E-08 2.OOE-08 1-131 1.OOE-06 8.73E-09 2.08E-08 Co-58 5.OOE-07 6.23E-09 2.13E-08 Co-60 5.OOE-07 9.52E-09 2.39E-08 Fe-59 5.OOE-07 8.29E-09 3.40E-08 Zn-65 5.OOE-07 1.60E-08 3.42E-08 Mn-54 5.OOE-07 6.19E-09 1.42E-08 Mo-99 5.OOE-07 7.23E-08 2.73E-07 Ce-141 5.OOE-07 9.85E-09 1.76E-08 Ce-144 5.OOE-07 4.48E-08 7.70E-08 Fe-55 1.OOE-06 3.53E-07 8.83E-07 Alpha 1.OOE-07 2.89E-08 2.91E-08 Tritium 1.OOE-05 1.58E-06 2.20E-06 Xe-133 1.OOE-05 1.36E-08 2.98E-08 Xe-135 1.OOE-05 7.03E-09 1.30E-08 Xe-133m 1.OOE-05 5.35E-08 9.74E-08 Xe-135m 1.OOE-05 3.95E-07 7.38E-07 Xe-138 1.OOE-05 8.60E-07 2.11E-06 Kr-87 1.OOE-05 3.08E-08 4.94E-08 Kr-88 1.OOE-05 2.88E-08 4.96E-08

Attachment 8 Page 1 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE The following is a summary of 2010 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP). Analyses are performed by an independent laboratory.

Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-04 2/24/10 <776 ND NA NA NA NA 1-PL-Piez-06 2/24/10 1,780 ND <48.1 <15.4 <0.667 NA 1-PL-Piez-27 2/24/10 <756 ND NA NA NA NA 1-PL-Piez-29 2/24/10 11,200 ND <71.1 <16.6 <0.645 NA 1-PL-Piez-05 2/25/10 14,000 ND <130 <15.8 <0.834 NA 1-PL-Piez-07 2/25/10 <755 ND NA NA NA NA 1-PL-Piez-33 2/25/10 <769 ND NA NA NA NA 1-PL-Piez-34 2/25/10 <762 ND NA NA NA NA 1-PL-Piez-41 2/25/10 <768 ND NA NA NA NA 1-PL-Piez-42 2/25/10 <764 ND NA NA NA NA 1-PL-Piez-07 5/20/10 <1320 ND NA NA NA NA 1-PL-Piez-08 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-22 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-27 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-33 5/20/10 <1320 ND NA NA NA NA 1-PL-Piez-34 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-35 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-36 5/20/10 <1320 ND NA NA NA NA 1-PL-Piez-37 5/20/10 <1310 ND NA NA NA NA 1-PL-Piez-04 5/21/10 <1320 ND NA NA NA NA 1-PL-Piez-09 5/21/10 <1320 ND NA NA NA NA 1-PL-Piez-20 5/21/10 <1310 ND NA NA NA NA 1-PL-Piez-24 5/21/10 <1310 ND NA NA NA NA 1-PL-Piez-25 5/21/10 <1310 ND NA NA NA NA 1-PL-Piez-28 5/21/10 <1340 ND NA NA NA NA 1-PL-Piez-38 5/21/10 <1320 ND NA NA NA NA 1-PL-Piez-39 5/21/10 <1330 ND NA NA NA NA 1-PL-Piez-40 5/21/10 <1330 ND NA NA NA NA 1-PL-Piez-41 5/21/10 <1450 ND NA NA NA NA 1-PL-Piez-42 5/21/10 <1450 ND NA NA NA NA 1-PL-Piez-03 5/22/10 <1340 ND NA NA NA NA 1-PL-Piez-05 5/22/10 12,400 ND NA NA NA NA 1-PL-Piez-06 5/22/10 2,800 ND NA NA NA NA 1-PL-Piez-29 5/22/10 8,590 ND NA NA NA NA 1-PL-Piez-23 5/22/10 <1310 ND NA NA NA NA ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

NA = Analysis not required. TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

Attachment 8 Page 2 of 2 INDUSTRY GROUND WATER PROTECTION INITIATIVE The following is a summary of 2010 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP). Analyses are performed by an independent laboratory.

Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-04 8/11/10 <758 ND NA NA NA ND 1-PL-Piez-05 8/10/10 11800 ND NA NA NA ND 1-PL-Piez-06 8/10/10 3030 ND NA NA NA ND I -PL-Piez-07 8/11/10 <740 ND NA NA NA ND 1-PL-Piez-08 8/11/10 <726 ND NA NA NA ND 1-PL-Piez-25 8/10/10 <1150 ND NA NA NA ND 1-PL-Piez-27 8/11/10 <749 ND NA NA NA ND 1-PL-Piez-29 8/11/10 8910 ND NA NA NA ND 1-PL-Piez-33 8/10/10 <718 ND NA NA NA ND 1-PL-Piez-34 8/10/10 <717 ND NA NA NA ND 1-PL-Piez-40 8/11/10 <739 ND NA NA NA ND 1-PL-Piez-41 8/10/10 <749 ND NA NA NA ND 1-PL-Piez-42 8/11/10 <741 ND NA NA NA ND 1-PL-Piez-04 12/2/10 <1480 ND NA NA NA NA 1-PL-Piez-05 12/2/10 14,100 ND NA NA NA NA 1-PL-Piez-06 12/1/10 1,860 ND NA NA NA NA 1-PL-Piez-07 12/2/10 <1470 ND NA NA NA NA 1 -PL-Piez-24 12/2/10 <747 ND NA NA NA NA 1-PL-Piez-27 12/2/10 <758 ND NA NA NA NA 1-PL-Piez-29 12/1/10 9,240 ND NA NA NA NA 1-PL-Piez-33 12/2/10 <759 ND NA NA NA NA 1-PL-Piez-34 12/1/10 <765 ND NA NA NA NA 1-PL-Piez-41 12/1/10 <743 ND NA NA NA NA 1-PL-Piez-42 12/2/10 <738 ND NA NA NA NA ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

NA = Analysis not required. TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

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