ML031250340

Annual Radioactive Effluent Release Report

ML031250340
Person / Time
Site:	Surry
Issue date:	04/22/2003
From:	Blount R Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
03-307, RG-1.021, Rev 1, SS&L/BAG
Download: ML031250340 (31)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Serial No.

SS&LJBAG 03-307 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2002 through December 31, 2002. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.8.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2002 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

If you have any questions or require additional information, please contact us.

Very truly yours,

i
7 Richard H. Blount, Site Vice President Richard H. Blount, Site Vice President Surry Power Station Attachment Commitments made in this letter: None

, 9

>0

cc:

United States Nuclear Reguiatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W., Suite 23T85 Atlanta, Georgia 30303-8931 R. A. Musser NRC Senior Resident Inspector Surry Power Station American Nuclear Insurers Aftn: Mr. Tom Wolff 29 South Main Street Town Center Suite 300S West Hartford, CT 06107-2430

ATTACHMENT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37

Surry Power Station I

2002 Annual Radioactive Effluent Release Report Dominiw

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION January 1, 2002 Through December 31, 2002 Prepared By: _

Reviewed By:

Reviewed By:

Approved By:

,,D74 4 -c P. F. Blount Health Physicist B. A. Hilt Supervisor Radiological Analysis and Material Control D. K. Miller Supervisor Health Physics Technical Services T. F. Steed Manager Radiological Protection

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION January 1, 2002 Through December 31, 2002 Index Section No.

1 2

3 4

Subject Executive Summary Purpose and Scope Discussion Supplemental Information Effluent Release Data Annual and Quarterly Doses Revisions to Offsite Dose Calculation Manual (ODCM) Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Unplanned Releases Lower Limit of Detection (LLD) for Effluent Sample Analysis Page 1

2 3

4

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, 50-28 1, 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 the Surry Power Station during the 2002 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the 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 2002 effluent release data, 1 OCFR50 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 1.86E-04 mrem, which is 3.10E-03% of the 6 mrem dose limit. The critical organ doses due to liquid effluents, GI-LLI and Thyroid respectively, were 8.85E-04 mrem and 9.71E-05 mrem.

These doses are 4.43E-03% and 4.86E-04% of the respective 20 mrem dose limit.

2. The air dose due to noble gases in gaseous effluents was 2.06E-04 mrad gamma, which is 1.03E-03% of the 20 mrad gamma dose limit, and 4.74E-04 mrad beta, which is 1.19E-03% of the 40 mrad beta dose limit.

3. The critical organ dose from gaseous effluents due to I-131, 1-133, H-3, and particulates with half-lives greater than 8 days is 9.53E-02 mrem, which is 3.18E-0I% 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.

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.

1

Purpose and Scope The Annual Radioactive Effluent Release Report, Attachment 1, 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 the previous calendar year. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6.

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, 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.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 of this report. provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation.

2

Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table IA 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 organ is the teen's lung, inhalation pathway.

The basis for the calculation of the percent of technical specification for the total body and skin in Table IA 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 mnRem/yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 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 2.00E-04 microcuries/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 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 teen at the site boundary with the critical organ being the lung. 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 being either the thyroid gland or 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 level of detection, then the totals for this period will be designated as Not Applicable (N/A).

3

Supplemental Information Section 6.6.1.b.4 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.

4

ATTACHMENT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 EFFLUENT RELEASE DATA January 1, 2002 Through December 31, 2002 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 I of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/02 TO 12/31/02 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 7.64E-01 4.17E-01 1.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 9.82E-02 5.3 1E-02 B. IODINE

1. TOTAL I-131 Ci N/D 1.75E-06 2.80E+O1

2. AVE RELEASE RATE FOR PERIOD pCi/sec N/A 2.22E-07 C. PARTICULATE

1. HALF-LIFE >8 DAYS Ci 3.19E-06 1.93E-05 2.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 4.10E-07 2.45E-06

3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM

1. TOTAL RELEASE Ci 5.12E+00 7.OOE+00 3.10E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 6.58E-01 8.90E-01 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE 3.32E-03 4.52E-03 TOTAL BODY DOSE RATE 1.08E-04 4.14E-06 SKIN DOSE RATE 4.23E-05 1.40E-06

Attachment I TABLE IA Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/02 TO 12/31/02 GASEOUS EFFLUENT-SUMMIATION OF ALL RELEASES SURRY POWER STATION UNITS 1 &2 UNIT THIRD FOURTH

% EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 1.18E-01 7.29E-02 1.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 1.49E-02 9.17E-03 B. IODINE

1. TOTAL I-131 Ci 5.98E-07 7.3 1E-07 2.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 7.52E-08 9.20E-08 C. PARTICULATE

1. HALF-LIFE >8 DAYS Ci N/D N/D 2.80E+01

2. AVE RELEASE RATE FOR PERIOD plCi/sec N/A N/A

3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM

1. TOTAL RELEASE Ci 1.16E+01 1.58E+01 3.10E+01

2. AVE RELEASE RATE FOR PERIOD gCi/sec 1.46E+00 1.98E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE 7.36E-03 1.01E-02 L

TOTAL BODY DOSE RATE 2.22E-05 9.28E-06 SKIN DOSE RATE 5.63E-06 2.63E-06 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 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 1.26E-03 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 8.98E-03 N/D 4.76E-01 4.13E-01 Xe-135 Ci N/D N/D 5.20E-02 1.11E-03 Xe-135m Ci N/D NID N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D 3.60E-03 2.31E-04 Xe-133m Ci N/D N/D 5.75E-03 1.93E-03 Ar-41 Ci N/D N/D 3.05E-03 N/D TOTAL FOR PERIOD Ci 8.98E-03 N/A 5.42E-01 4.16E-01

2. IODINES I-131 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D I-135 Ci N/D NID NID 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 3.69E-09 7.44E-09 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 TOTAL FOR PERIOD Ci 3.69E-09 7.44E-09 N/A N/A Page 4 of 12 TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2

1. FISSION & ACTIVATION GASES Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Xe-13 lm Xe-133m Ar-41 TOTAL FOR PERIOD UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/A N/D N/D N/D N/D 1.16E-01 N/D N/D N/D N/D N/D N/D 1.16E-01 N/D N/D N/D N/D 7.1IE-02 N/D N/D N/D N/D N/D N/D 7.1 1E-02 Ci N/A

2. IODINES 1-131 1-133 L

1-135 ci ci ci N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D L

TOTAL FOR PERIOD

3. PARTICULATES Sr-89 Sr-90 Cs-134

-I Cs-137 Ba-140 La-140 Co-58 Co-60 Mn-54 Fe-59 Zn-65 Mo-99 Ce-141 Ce-144 Ci N/A Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/A N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/A N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/A N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment I TALE1CPage 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD:1/1/02 TO 12/31/02 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 NID 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 3.88E-05 2.09E-01 6.16E-05 Xe-135 Ci N/D 5.88E-04 3.95E-03 4.91E-05 Xe-135m Ci N/D l.91E-04 N/D 5.21E-05 Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D NID N/D N/D Xe-133m Ci N/D N/D 1.21E-04 N/D Ar-41 Ci N/D N/D N/D N/D TOTALFORPERIOD Ci N/A 8.18E-04 2.13E-01 1.63E-04

2. IODINES I-131 Ci N/D 1.75E-06 N/D N/D I-133 Ci N/D N/D NID N/D 1-135 Ci N/D N/D N/D N/D L

TOTAL FOR PERIOD Ci N/A 1.75E-06 N/A N/A

3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D 2.25E-06 N/D NID 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 3.19E-06 1.35E-05 N/D N/D Co-60 Ci N/D 3.57E-06 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 NID 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 TOTAL FOR PERIOD Ci 3.19E-06 1.93E-05 N/A N/A

T L

TABLE1C Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD:1/1/02 TO 12/31/02 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 NID N/D N/D N/D L

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 NID N/D N/D Xe-133 Ci 2.99E-05 NID 1.33E-05 N/D Xe-135 Ci 5.07E-04 7.82E-04 2.21E-05 2.69E-04 Xe-135m Ci 3.29E-04 3.45E-04 1.64E-05 N/D Xe-138 Ci N/D N/D N/D NID Xe-131m Ci NID NID NlD N/D Xe-133m Cl N/D NID N/D N/D L

Ar-41 Ci 1.41E-03 9.76E-06 NID 3.34E-04 TOTAL FOR PERIOD Ci 2.28E-03 1.14E-03 5.18E-05 6.04E-04

2. IODINES I-131 Ci 5.98E-07 7.3 1E-07 NID NID 1-133 Ci N/D NID NID NID I-135 Ci NID NID NID NID L

TOTAL FOR PERIOD Ci 5.98E-07 7.31E-07 N/A N/A

!L

3. PARTICULATES Sr-89 Ci N/D N/D NID N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D NID 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 NID 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 NID N/D N/D N/D Zn-65 Ci NID N/D NID N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci NID NID N/D N/D Ce-144 Ci NID N/D N/D N/D Cr-51 Ci N/D N/D N/D N/D Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A NIA N/A N/A

Attachment I TABLE2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 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 3.02E-02 3.55E-02 2.OOE+O1

2. AVE DIL. CONC. DURING PERIOD itCi/ml 4.62E-1 1 5.31E-1l

3. PERCENT OF APPLICABLE LIMIT 5.22E-05 6.14E-05 B. TRITIUM

1. TOTAL RELEASE Ci 1.28E+02 8.43E+01 2.OOE+01

2. AVE DIL. CONC. DURING PERIOD iLCi/ml 1.97E-07 1.26E-07

3. PERCENT OF APPLICABLE LIMIT 1.97E-03 1.26E-03 C. DISSOLVED AND ENTRAINED GASES L

1. TOTAL RELEASE Ci N/D N/D 2.OOE+O1

2. AVE DIL. CONC. DURING PERIOD pCi/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 K

(PRIOR TO DILUTION)

LITERS 4.57E+07 6.82E+07 3.OOE+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.53E+l I 6.69E+ 1I 3.OOE+00

IE

!TABLE2A Page 8of12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 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 5.20E-03 1.17E-02 2.OOE+O1

2. AVE DIL. CONC. DURING PERIOD piCi/ml 6.59E-12 1.66E-11

3. PERCENT OF APPLICABLE LIMIT 1.49E-05 3.55E-05 B. TRITIUM

1. TOTAL RELEASE Ci 1.33E+01 2.89E+02 2.00E+01

2. AVE DIL. CONC. DURING PERIOD RCi/ml 1.68E-08 4.09E-07

3. PERCENT OF APPLICABLE LIMIT 1.68E-04 4.09E-03 C. DISSOLVED AND ENTRAINED GASES I

1. TOTAL RELEASE Ci N/D N/D 2.OOE+01

2. AVE DIL. CONC. DURING PERIOD pCi/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 2.00E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

LITERS 5.21E+07 7.52E+07 3.OOE+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.89E+l 1 7.06E+1 1 3.OOE+00

TABLE 2B Attachment I Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 LIQUID EFFLUENTS SURRY POWER STATION UNITS 1 &2 CONTINUOUS MODE UNIT FIRST SECOND QUARTER QUARTER BATCH MODE FIRST SECOND QUARTER QUARTER Sr-89 L

Sr-90 Fe-55 I

Cs-134 L

Cs-137 1-131 I

Co-58 L

Co-60 Fe-59 I

Zn-65 Mn-54 Cr-51 Zr-95 i

Nb-95 Mo-99 Tc-99m I

Ba-140 La-140 Ce-141 Ce-144 i

Sb-124 Sb-125 Co-57 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci N/D N/D N/D N/D 2.04E-04 N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D NID N/D N/D N/D N/D N/D N/D 2.89E-04 N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D 2.48E-06 7.26E-04 N/D 8.52E-03 4.52E-03 N/D N/D 1.18E-03 6.82E-04 N/D 1.59E-05 N/D 2.74E-05 N/D N/D N/D N/D 2.6 1E-04 1.40E-02 2.88E-05 N/D N/D N/D N/D 6.94E-04 1.89E-05 1.43E-02 6.05E-03 N/D N/D 1.07E-03 3.64E-03 N/D 5.14E-05 N/D 4.15E-05 N/D N/D N/D N/D 1.96E-04 9.1 lE-03 9.41E-05 TOTAL FOR PERIOD Ci 2.04E-04 2.89E-04 N/D N/D 3.001E-02 N/D N/D 3.53E-02 N/D N/D Xe-133 Xe-135 Ci Ci N/D N/D TOTAL FOR PERIOD NIA N/A N/A N/A

Attachment I Page 10 of 12 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/02 TO 12/31/02 LIQUID EFFLUENTS SURRY POWER STATION UNITS 1 &2 CONTINUOUS MODE UNIT THIRD FOURTH QUARTER QUARTER BATCH MODE THIRD FOURTH QUARTER QUARTER Sr-89 Sr-90 Fe-55 Cs-134 Cs-137 1-131 i

Co-58 Co-60 Fe-59 Zn-65 Mn-54 L

Cr-51 Zr-95 Nb-95 Mo-99 Tc-99m Ba-140 i

La-140 Ce-141 Ce-144 Sb-124 Sb-125 Co-57 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci N/D N/D N/D N/D 3.5 1E-04 N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D 7.0 1E-04 N/D NID N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D 7.54E-08 1.04E-04 N/D 1.87E-03 1.77E-03 N/D N/D 5.73E-04 N/D N/D 5.05E-06 N/D N/D N/D N/D N/D N/D N/D 4.93E-04 3.70E-05 N/D N/D N/D N/D 1.22E-04 N/D 2.61E-03 4.27E-03 N/D N/D 7.53E-04 N/D N/D 2.88E-06 N/D N/D N/D N/D N/D N/D N/D 3.18E-03 7.55E-05 TOTAL FOR PERIOD Ci 3.5 1E-04 7.01E-04 N/D N/D 4.85E-03 N/D N/D 1.10E-02 N/D N/D Xe-133 Xe-135 Ci Ci N/D N/D TOTAL FOR PERIOD N/A N/A N/A N/A

Attachment I Page 11 of 12 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/02 - 12/31/02 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste 12 month Period Est. Total Error, %

a. Spent resins, filter sludges, evaporator m3 2.43E+01*

1.OOE+01 bottoms, etc.

Ci 1.43E+02 3.OOE+01

b. Dry compressible waste, contaminated m3 2.84E+02**

1.00E+01 equip., etc.

Ci 2.60E+00 3.OOE+01

c. Irradiated components, control m3 0.OOE+00***

1.00E+0I rods, etc.

Ci O.OOE+00 3.OOE+O I

d. Other (Waste Oil) m3 O.OOE+00****

1.00E+01 Ci 0.00E+00 3.OOE+01

2. Estimate of major nuclide composition (by type of waste)

a. Ni-63 Co-60 Co-58 Fe-55 Cs-137 Mn-54

b. Co-58 Cs-137 Co-60 Fe-55 Ni-63 Cr-51 Nb-95 3.48E+01 2.39E+0 1 1.99E+01 1.31E+01 3.25E+00 1.09E+00 3.02E+01 2.47E+01 2.4 1E+01 7.78E+oo 6.55E+00 2.43E+00 1.77E+00 c.

d.

Attachment I Page 12 of 12 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/02 -12/31/02 CONT'D SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

3. Solid Waste Disposition Number of Shipments 3

7 3

Mode of Transportation Truck Truck Truck Destination Barnwell, SC (WMF)

Oak Ridge, TN (D-BCI)

Erwin, TN (SPF)

B. IRRADIATED FUEL SHIPMENT (Disposition)

Number of Shipments 0

Mode of Transportation Destination

• 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 9.04E+00 m3.

• • 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 2.35E+01 m3.

NOTE 3: In previous years, irradiated components have been shipped to licensed waste processors for processing and/or volume reduction. Previous years burial volumes have been reported in previous years reports. The total volume buried for this reporting period is O.OOE+00 m3.

L

• • • • NOTE 4: Waste oil is shipped to a 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 0.OOE+00 m3.

Page I of 1 ANNUAL AND QUARTERLY 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.

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual LIQUID GASEOUS Total Body Thyroid GI-LLI Gamma Beta Lung (mrem)

(mrem)

(mrem)

(mrad)

(mrad)

(mrem) 4.98E-05 2.42E-05 2.45E-04 1.58E-04 4.43E-04 1.23E-02 5.81E-05 1.98E-05 4.06E-04 5.69E-06 8.68E-06 1.70E-02 9.76E-06 2.1 lE-06 5.89E-05 2.97E-05 1.33E-05 2.79E-02

• 6.82E-05 5.10E-05 1.75E-04 1.24E-05 8.43E-06 3.8 1E-02 1.86E-04 9.7 1E-05 8.85E-04 2.06E-04 4.74E-04 9.53E-02 Page I 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 to be included in this report. There were no procedure revisions to the ODCM implemented during this reporting period.

Page I of I 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.

Page I of 1 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitors required by the ODCM Attachments 1 and 5, which were determined to be inoperable, were not returned to operable status within 30 days. None of the above referenced monitors were inoperable greater than 30 days during this reporting period.

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

Page I of 1 LOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSIS GASEOUS:

Isotope Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 I-131 I-133 Sr-89 Sr-90 Cs-134 Cs-137 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Ce-141 Ce-144 Alpha Tritium Required LLD l.OOE-04 l.OOE-04 1.OOE-04 l.OOE-04 l.OOE-04 1.00E-04 l.OOE-04 1.OOE-12 l.OOE-10 1.OOE-0 1

l.OOE-1 1 1.OOE-0 1

l.OOE-1 1 l.OOE-1 1 l.OOE-1 1 1.OOE-1 1 1.OOE-11 l.OOE-1 1 l.OOE-l 1 l.OOE-1 1 l.OOE-1 1 l.OOE-1 1 l.OOE-06 Typical LLD 2.41E 5.25E-06 2.65E 7.96E-06 1.09E 6.91E-06 4.11E 1.8313-05 5.02E 2.37E-06 2.69E 9.23E-06 7.28E 1.82E-05 3.68E 3.34E-13 9.60E-13 7.50E-12 1.20E 5.20E-12 2.80E 9.30E-13 4.40E 4.47E-13 4.24E 6.36E-13 4.00E 6.27E-13 l.OlE 1.06E-12 4.14E 5.75E-13 8.05E 8.58E-13 7.98E 1.63E-12 4.50E 3.66E-12 4.7613 4.87E-13 1.8213 2.16E-12 1.6613 2.18E-14 4.56E 4.85E-08 LIQUID Sr-89 Sr-90 Cs-134 Cs-137 1-131 Co-58 Co-60 Fe-59 Zn-65 Mn-54 Mo-99 Ce-141 Ce-144 Fe-55 Alpha Tritium Xe-133 Xe-135 Xe-133m Xe-135m Xe-138 Kr-87 Kr-88 5.0013-08 5.0013-08 5.0013-07 5.00E-07 1.OOE-06 5.00E-07 5.00E-07 5.00E-07 5.0013-07 5.0013-07 5.00E-07 5.0013-07 5.0013-07 1.0013-06 l.OOE-07 1.OOE-05 1.001-05 1.0013-05 l.OOE-05 1.0013-05 1.OOE-05 l.OOE-05 1.0013-05 3.60E 2.2013 8.22E 7.78E 8.4613 7.1 lE 1.34E 1.04E 1.22E 6.85E 6.4813 1.1013 4.8513 2.00E 7.85E 1.26E 1.44E 6.91E 5.14E 3.52E 1.OOE 3.20E 3.3 1E 4.6013-08 4.2013-08 1.4513-08 1.8813-08 1.72E-08 2.09E-08 2.44E-08 3.14E-08 4.67E-08 1.80E-08 2.78E-07 1.75E-08 7.45E-08 3.80E-07 7.97E-08 1.34E-06 3.47E-08 1.28E-08 9.26E-08 6.92E-07 1.72E-06 4.53E-08 5.08E-08