ML061250328

Annual Radioactive Effluent Release Report

ML061250328
Person / Time
Site:	Surry
Issue date:	05/01/2006
From:	Jernigan D Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
06-359
Download: ML061250328 (101)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 1, 2006 United States Nuclear Regulatory Commission Serial No.06-359 Attention: Document Control Desk SS&L/TJN Washington, DC 20555-0001 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPF-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, 2005 through December 31, 2005. 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 ancI solid waste released during the 2005 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.

Surry Power Station Attachment Commitments made in this letter: None I f'L,8

Serial No.: 06-359 Docket Nos.: 50-280 50-281 cc: United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W., Suite 23T85 Atlanta, Georgia 30303-8931 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station American Nuclear Insurers Attn: Mr. Edward Everett 95 Glastonbury Blvd.

Glastonbury, CT 06033

Serial No.: 06-359 Docket Nos.: 50-280 50-:281 ATTACHMENT 1 2005 Annual Radioactive Effluent Release Report SURRY POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY

L Surry Power Station L

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2005 Annual Radlioactive.

Effluent Release Report iiDominnion 205AnaLaiatv

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION January 1, 2005 Through December 31, 2005 Prepared By: -

P. F. Blount Health Physicist Reviewed By:

P. R. Harris Supervisor Radiological Analysis Reviewed By:

D. K. Miller Approved By:

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION January 1, 2005 Through December 31, 2005 Index Section No. Subject Page 1 Executive Summary 1 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

FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Techni-al Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Compzny, 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 2005 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Pawer 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 2005 effluent release data, 10CFR50 Appendix I dose calculations were perfornmd in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

1. The total body dose due to liquid effluents was 2.37E-04 mrem, which is 3.95E-03% of the 6 mrem dose limit. The critical organ doses due to liquid effluents, GI-LUI and Liver respectively, were 9.07E-04 mrem and 2.38E-04 mrem. These doses are 4.54E-03% and 1.19E-03% of the respective 20 mnrem dose limit.

2. The air dose due to noble gases in gaseous effluents was 1.61E-03 mrad gamma, which is 8.05E-03% of the 20 mrad gamma dose limit, and 2.93E-03 mrad beta, which is 7.33E-03% of the 40 mrad beta dose limit.

3. The critical organ dose from gaseous effluents due to 1-131, I-133, H-3, and particulates with half-lives greater than 8 days is 1.50E-01 mrem, which is 5.00E-01 % of the 30 mrem dose limit.

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

There were two changes to VPAP-2103S, Offsite Dose Calculation Manual, during this reporting period. Attachment 3 provides the changes to VPAP-2103S.

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 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.

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 requaired 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.

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, [or 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 teen via the 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 mrem/yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 -s 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 arnual and quarterly doses, as reported in Attachment 2, were calculated according to the methocology 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 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). Aztual 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 (NJD) on 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.

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

4

Attachment 1 EFFLUENT RELEASE DATA January 1, 2005 Through December 31, 2005 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 1 U TABLE 1A Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1105 TO 12/31/05 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 1.33E-01 1.44E+00 1.80E+01

2. AVE RELEASE RATE FOR PERIOD ACi/sec 1.71E-02 1.83E-01 G B. IODINE

1. TOTAL I-131 Ci N/D 1.58E-08 2.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec N/A 1.94E-09 C. PARTICULATE

1. HALF-LIFE >8 DAYS Ci N/D 2.05E-05 2.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec N/A 2.60E-06

3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM U 1. TOTAL RELEASE

2. AVE RELEASE RATE FOR PERIOD Ci pCi/sec 1.86E+01 2.40E+00 1.65E+01

2. 1OE+00 3.10E+01 r PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 1.22E-02 1.07E-02 TOTAL BODY DOSE RATE  % 3.16E-04 1.09E-04 SKIN DOSE RATE  % 7.81E-05 4.03E-05

L TABLE IA Attachment 1 Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES L SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH %E.ST. ERROR A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 3.34E-02 1.60E+00 1.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec 4.21E-03 2.01E-01 UB. IODINE

1. TOTALI-131 Ci N/D N/D :2.80E+01

2. AVE RELEASE RATE FOR PERIOD pCi/sec N/A N/A C. PARTICULATE 1 1. HALF-LIFE >8 DAYS Ci N/ID N/ID 2.80E+01

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

3. GROSS ALP'HA RADIOACTIVITY Ci N/D N/D L D. TRITIUM

1. TOTAL RELEASE Ci 1.80E+01 8.91E+00 3.10E+01 G 2. AVE RELEASE RATE FOR PERIOD uCi/sec 2.26E+00 1.12E+00 L PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 1.15E-02 5.68E-03 TOTAL BODY DOSE RATE  % 5.87E-06 7.1OE-04 SKIN DOSE RATE  % 2.1OE-06 2.59E-04

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH M:ODE F SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER I i. FISSION &, ACTIVATION GASES Ai Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci NID NtD N/D '7.58E-04 Kr-87 Ci NID N/D N/D N/D L -Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D NID 1.07E-01 1t.27E+00 Xe-135 Ci N/D N/D N/D 4.84E-02 L Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci NID N/D N/D N/D Xe-131m Ci N/D N/D N/D 9.55E-03

-- Xe-133m Ci NID N/D N/D 1.43E-02 Ar-41 Ci N/D NID N/D .3.12E-03 TOTAL FOR PERIOD Ci N/A N/A 1 1.07E-01 .L.35E+00

2. IODINES 1 1-I-131 Ci NID N/D N/D NID j; I-133 Ci NID N/D N/D N/D I-135 Ci N/D N/D N/D N/D

TOTAL FOR PERIOD Ci N/A N/A N/A N/A Iv IJ 3. PARTICULATES Sr-89 Ci NID N/D N/D N/D L Sr-90 Cs-134 Cs-137 Ci Ci Ci N/D N/D N/D N/D NtD NtD NtD NtD NtD NtD NtD NtD Ba-140 Ci N/D NID N/D N/D La-140 Ci NtD NtD NtD N/D Co-58 Ci NID NtD N/D N/D Co-60 Ci NtD N/D NtD N/D l i Mn-54 Ci N/D N/D NID N/D L Fe-59 Ci NtD NtD NtD NtD Zn-65 Ci NtD N/D N/D NtD Mo-99 Ci NtD N/D N/D NtD h Ce-141 Ci N/D N/D N/D N/D Ce- 144 Ci N/D NtD N/D NtD Nb-95 Ci N/D N/D NtD NID L Cr-51 Ci N/D NID NtD N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE IB Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE fI SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH

,Ll QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES L Kr-85 Kr-85m Kr-87 Ci Ci Ci N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D 2.61E-04 N/D I' Kr-88 Ci N/D N/D N/D N/D L; Xe-133 Ci N/D N/D 3.04E-02 3.72E-01 Xe-135 Ci NID N/D N/D 2.59E-02

[" Xe-135m Ci N/D NID N/D N/D I 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 4.61E-03 b Ar-41 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A 3.04E-02 4.03E-01

2. IODINES Lm I-131 Ci N/D N/D N/D N/D L 1-133 Ci N/D NID N/D N/D I-135 Ci N/D N/D N/D N/D L TOTAL FOR PERIOD Ci N/A N/A N/A N/A i 3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D ir Sr-90 Ci N/D N/D N/D N/D L-, Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D 17 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 NID N/D N/D N/D z! Fe-59 Ci N/D NID N/D N/D Zn-65 Ci N/D N/D N/D N/D 1 Mo-99 Ci N/D N/D NID N/D Lz Ce-141 Ce-144 Ci Ci N/D N/D N/D N/D N/D N/D NID N/D Nb-95 Ci N/D N/D N/D N/D i, Cr-51 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE IC Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 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 i Kr-85 Ci N/D N/D NID NID Kr-85m Ci N/D NID N/D N/D Kr-87 Ci NID N/D N/D N/D

[i Kr-88 Ci N/D N/D NID N/D iI~ Xe-133 Ci 7.56E-04 NID 3.72E-04 6.OOE-02 Xe-135 Ci 1.60E-03 1.62E-02 6.52E-04 1.12E-02 J, Xe-135m Ci NID 2.03E-04 N/D N/D L Xe-138 Ci N/D NID N/D N/D Xe-131m Ci NID NID NID N/D I Xe-133m Ci NID N/D N/D N/D I, Ar-41 Ci 2.27E-02 NID N/D N/D TOTAL FOR PERIOD Ci 2.5 1E-02 1.64E-02 1.02E-03 7.12E-02

2. IODINES F' 1-131 Ci NID N/D NID 1.53E-08 L I-133 Ci N/D N/D NID N/D I-135 Ci N/D N/D NID N/D TOTAL FOR PERIOD ci N/A N/A N/A 1.53E-08 to 3. PARTICULATES Sr-89 Ci N/D NID NID N/D Sr-90 ci NID 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 I: Ba-140 Ci NID N/D NID N/D L La-140 Co-58 ci Ci N/D NID N/D 2.03E-05 N/D N/D N/D 1.36E-07 Co-60 ci N/D NID NID N/D Mn-54 ci NID 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 b Ce-141 Ci N/D N/D N/D N/D Ce-144 ci NID NID NID N/D Nb-95 ci NID NID N/D N/D il ' Cr-51 ci N/D NID N/D N/D TOTAL FOR PE RIOD Ci N/A 2.03E-05 N/A 1.36E-07

Attachment 1 TABLE 1C Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH b QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D NID N/D Kr-85m Ci NID N/D N/D N/D Kr-87 Ci N/D N/D N/D NID j ' Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci 8.16E-05 1.72E-03 1.13E-03 1.16E+00 Xe-135 Ci 4.13E-04 2.92E-03 1.34E-03 2.27E-02

.- Xe-135m Ci 8.91E-05 NID N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D NID N/D N/D Xe-133m Ci NID N/D N/D N/D tj Ar-41 Ci N/D 9.34E-03 N/D N/D TOTAL FOR P;_RIOD Ci 5.83E-04 1.40E-02 2.47E-03 1.18E+00

2. IODINES r- 1-131 Ci N/D NID N/D NtD I-133 Ci N/D N/D N/D N/D I-135 Ci N/D NID N/D NID TOTAL FOR P]_RIOD Ci N/A N/A N/A N/A W 3. PARTICULYATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D L Cs-134 Ci N/D N/D N/D NID Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D L La-140 Ci N/D NID 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 NID N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D 17 Mo-99 Ci N/D N/D N/D N/D w Ce-141 Ci N/D N/D N/D NID Ce-144 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D lI Cr-51 Ci N/D N/D N/D N/D TOTAL FOR PE-RIOD Ci N/A N/A N/A N/A

F1 Atiachment 1 TABLE 2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES L SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND  % EST. ERROR L A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING QUARTER QUARTER TRITIUM, GASES, ALPHA) Ci 8.74E-03 1.00E-02 O.OE+O 1 l 2. AVE DIL. CONC. DURING PERIOD pCi/mL 1.27E-11 1.50E-11

3. PERCENT OF APPLICABLE LIMIT  % 2.34E-05 2.96E-05 L B. TRITIUM

1. TOTAL RE LAEASE Ci 1.36E+02 3.69E+02 2.OOE+01 g 2. AVE DEL. CONC. DURING PERIOD pCi/mL 1.98E-07 5.54E-07

3. PERCENT OF APPLICABLE LIMIT  % 1.98E-03 5.54E-03 L C. DISSOLVEI) AND ENTRAINED GASES

1. TOTAL RELEASE Ci N/D N/D 2.00E+01

2. AVE DEL. CONC. DURING PERIOD pCi/mL N/A N/A U 3. PERCENT OF APPLICABLE LIMIT  % N/A N/A i~'

L D. GROSS ALP'HA RADIOACTIVITY

1. TOTAL RELEASE Ci N/D N/D .00E+01 l~E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 4.78E+07 3.42E+07 _,.OOE+00 L~ F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.86E+1 I 6.67E+I I .OOE+FlO

Attachment 1 TABLE 2A Page 8 of 12 L EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES U 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 3.37E-02 3.07E-02 ,!.OOE+01

2. AVE DIL. CONC. DURING PERIOD pCi/mL 4.22E-11 4.48E-1 I

3. PERCENT OF APPLICABLE LIMIT  % 3.23E-05 3.91E-05 I ~ B. TRITIUM

1. TOTAL RELEASE Ci 1.14E+02 2.23E+02 2.OOE+01 I 2. AVE DIL. C(ONC. DURING PERIOD

3. PERCENT OF APPLICABLE LIMIT uCi/mL 1.43E-07 1.43E-03 3.25E-07 3.25E-03 U1 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci N/D N/D '!.OOE+01

2. AVE DIL. CONC. DURING PERIOD uCi/mL N/A N/A

3. PERCENT OF APPLICABLE LIMIT  % N/A N/A

- D. GROSS AL1'HA RADIOACTIVITY

1. TOTAL RE:LEASE Ci N/D N/D 2.OOE+01 L; E. VOLUME OF WASTE RELEASED (PRIOR TO I)ILUTION) LITERS 3.22E+07 4.90E+07 3.00E+00 L F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.97E+l1 6.84E1+1 1 3.00E+0(

Attachment 1 TABLE12B Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111105 TO 12/31/05 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER tz 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 NID Cs-137 Ci 3.56E-04 2.98E-04 4.52E-05 2.05E-04 1-131 Ci N/D N/D NID N/D I~ Co-58 Ci N/D N/D 1.11E-03 3.50E-03 in Co-60 Ci N/D N/D 3.03E-03 3.68E-03 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D I" ~ Mn-54 Ci N/D N/D 2.76E-04 5.26E-04 UZr-95 Cr-51 Nb-95 Ci Ci Ci N/D N/D N/D N/D N/D N/D N/D N/D 1.24E-06 2.46E-04 4.13E-06 2.55E-05 Mo-99 Ci NID 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 LI 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 L Sb-124 Sb-125 Ci Ci N/D N/D N/D N/D N/D 3.91E-03 N/D 1.49E-03 Co-57 Ci N/D N/D 1.21E-05 2.53E-05 F1 Sr-92 Ci N/D N/D N/D NID TOTAL FOR PERIOD Ci 3.56E-04 2.98E-04 8.38E-03 9.70E-03 Xe-133 Ci N/D N/D NID N/D Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD N/A N/A N/A N/A

Attachment 1 TABLE 2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/05 TO 12/31/05 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 NID N/D NID N/D L Cs- 137 Ci 1.80E-04 3.39E-04 1.09E-04 3.93E-05 I-131 Ci NID N/D NID N/D Co-58 Ci N/D N/D 1.41E-02 1.87E-02

,U Co-60 Ci N/D N/D 3.17E-03 3.26E-03 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D j,, Mn-54 Ci N/D N/D 1.66E-03 6.32E-03 Cr-51 Ci NID N/D 5.08E-04 N/D I Zr-95 Ci N/D NID N/D N/D Nb-95 Ci N/D N/D 9.52E-06 1.77E-06 LI Mo-99 Ci NID 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 NID L 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 L Sb-124 Ci N/D N/D N/D N/D Sb-125 Ci N/D N/D 1.39E-02 1.90E-03 Co-57 Ci N/D N/D 4.80E-05 1.49E-04 l I Sr-92 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci 1.80E-04 3.39E-04 3.35E-02 3.03E-02 Xe-133 Ci N/D NID NJD N/D Xe-135 Ci N/D N/D NID N/D TOTAL FOR PERIOD 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: 1/1/05 - 12/31/05 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 1.42E+01* 1.00E+01 bottoms, etc. Ci 4.87E+02 3.OOE+01

b. Dry compressible waste, contaminated m3 5.32E+02** 1.00E+01 equip., etc. Ci 9.45E+00 3.OOE+01

c. Irradiated components, control m3 8.78E-02*** 1.00E+01 rods, etc. Ci 7.74E-01 3.OOE+01

d. Other (Waste oil) m3 0.OOE+00 1.00E+01 Ci 0.OOE+00 3.OOE+01

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

a. Co-58 3.74E+01 Ni-63 2.67E+01 Fe-55 1.94E+01 Co-60 1.32E+01 Mn-54 1.21E+00

b. Cs-137 3.57E+01 Fe-55 2.20E+01 Co-58 2.03E+01 Co-60 8.27E+00 Ni-63 7.94E+00 Cr-51 2.35E+00 Nb-95 1.45E+00

c. Fe-55 5.36E+01 Co-60 3.29E+01 Ni-63 6.38E+00 Co-58 4.18E+00 Mn-54 1.18E+00 Cr-51 1.17E+00 d.

Attachment 1 TABLE 3 Page 12 of 12

- EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/05 - 12/31/05 l CONTINUED L

Gil 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 8 Truck Barnwell, SC (WMF) 4 Truck Oak Ridge, IN (DGR) 5 Truck Oak Ridge, IN (DBC)

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 2.10E+01 in3 ,

including volume from three 2004 shipments.

• • 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 2.42E+01 m .

U *** 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 8.78E-02 m3 .

Attachment 2 Page 1 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.

LIQUID GASEOUS Total Body GI-LLI Liver Gamma Beta Lung (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 3.46E-05 1.04E-04 3.21E-05 4.1 1E-04 1.56E-04 4.50E-(12 2nd Quarter 9.23E-05 2.35E-04 8.85E-05 1.48E-04 2.66E-04 3.99E-02 3rd Quarter 3.79E-05 2.14E-04 3.40E-05 7.92E-06 1.1 1E-05 4.34E-02 4th Quarter 7.26E-05 3.54E-04 8.35E-05 1.04E-03 2.50E-03 2.15E-02 Annual 2.37E-04 9.07E-04 2.38E-04 1.61E-03 2.93E-03 1.50E-C1

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 two procedure revisions to the ODCM implemented during this reporting period. The revision summaries are as follows.

Revision 6:

1. Eliminated the review of ODCM changes as a function of the Management Safety and Review Committee.

2. Added the Quality Assurance manual of the environmental analysis laboratory to the References section of the ODCM.

3. Added a NOTE to Attachments 5 and 6 to clarify the intention and meaning of the mark numbers listed in the attachments.

4. Revi 3ed the distances to various Environmental sampling locations on Attachment 8. Distances were determined with GPS technology.

Revision 7:

1. Added two Health Physics technical procedures to the References section of the ODCM.

2. Dele:ed Action 3 statement from Attachment 1 because it was a duplicate of the Action 1 statement.

Renumbered the Minimum Operable Channels and Action columns due to the deletion of the action statement and to improve the readability of the Attachment. The Action 2 statement was expanded to include an instruction for initiating a procedurally controlled sampling schedule when the Action 2 statement is entered.

3. Renumbered the Minimum Operable Channels and Action columns and reformatted Attachrrient 5 to clarify and improve the readability of the Attachment. Provided numbers to the NOTE statements and included references to the NOTE statements within Attachment 5. The Action 1 statement was expanded to include an instruction for initiating a procedurally controlled sampling schedule when the Action 1 is entered.

Revisions 6 and 7 of the ODCM are included with this attachment.

Station bi Dominion Administrative Procedure

Title:

Offsite Dose Calculation Manual (Surry)

Process / Program Owner: Manager Radiological Protection (Surry)

Procedure Number Revision Number Effective Date VPAP-2103S 6 On File Revision Summary The following changes were made to delete the requirement for Management Safety and Review Committee (MSRC) review of this procedure:

• Deleted 3.2.1 - Quality Assurance Audit Report Number C 90-22, Management Safety Review Committee, Observation 03C, January 17, 1991.

• Deleted 6.7.4.d - "Submitted to the Management Safety Review Committee (MSRC)

Coordinator. [Commitment 3.2.1]".

The following change was made to' update references:

• Revised 3.1.21, as follows:

OLD, - Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361.

NEW - "Laboratory Quality Assurance Plan, Manual 100; Framatome Environmental Labcratory."

The following changes were made to for clarification:

• Revi:;ed Attachment 5, Radioactive Gaseous Effluent Monitoring Instrumentation, and Attachment 6, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements - added the following NOTE; "The mark numbers listed above in 1(b), 1(c), :3(b),

3(c), and 3(e) refer to the gaseous effluent radiation monitor with which the iodine and particulate samplers and the flow rate measuring devices are associated. The listed mark numbers do not refer to the particulate radiation monitor.".

The following change was made to update the environmental sampling location distances:

• Revised Attachment 8, Environmental Sampling Locations - updated mileage distances.

Approvals on File

(

Administrative Procedures Action Request (A-PAR) II solDominion- -

Instructions for competing this form are included in VPAP-0502.

II 41 __q= jju--gir g ~j- -MlT

..... 6r, aTTx~

1. Procedure Number 12. Revisro 3. Page 14. Effective Date VPAP-2103S I IOf Tit 6. Expiration Date N/A Oftsite ose Calculation Manual (Surry)

7. Type of Request

[]New Procedure [l- Procedure Revision U Procedure Deletion

8. Brief description of the modification See Revision Summary of affected procedure

9. Location [I SPS E NAPS E CORP Location E SPS El NAPS E CORP

10. Requested by (Printed Name) 11. Date i2 Phone 13. Requested by (Printed Name) 14. Date 15. Phone P. Blount 12/13/04 2467 N/A N/A N/A 1 .i*sa*I t Id*1 .o.]* _I - Age

16. Is this a new procedure or does procedure meet requirements of NOTE below? LIYes L No

17. Does this procedure require a Regulatory Evaluation? El Yes N3 No

18. Are there any new sections or steps designated North Anna or Surry? (SPS Only Procedure) E Yes [i No

19. Is the reason for the station-specific instructions due to differences in regulatory requirements?

20. Is the reason for the station -specific instructions due to differences in construction?

El Yes El E Yes El No No [

E N/A N/A K

El Yes El [X

21. Is the reason for the station -specific instructions due to station preferences?

If all answers are No or N/A, approval is required by PPOs as identified on the Procedure Cover Page. Check block 29.

No N/A L

If block 16 or 17 is Yes, approval is required by PPOs, SNSOCs, and/or Site Vice Presidents. Check blocks 29, 30, and 31, as appropriate.

NOTE: VPAP-2101 and VPAP-2201 require SNSOCs approvaL SPIPs, VPAP-2103N, VPAP-2103S, VPAP-2104, and VPAP-2401 require SNSOC(s) and Site Vice President(s) approval. L If block 18,19, or 20 is Yes with block 21 No, approval is required by PPOs and Site Vice Presidents. Check blocks 29 and 31.

If block 21 is Yes, approval is required by PPOs, Site Vice Presidents, and Vice President Corporate. Check blocks 29, 31, and 32.

22.Location [1 SPS El NAPS El CORP Location El SPS [E NAPS E CORP L

23. PPO (Printed Name) 24. Date 25. Phone 26. PPO (Printed Name) 27. Date 28. Phone L. B. Jones 12/13/04 12010 N/A N/A N/A i; DI A.. ,_,,, 3-. - .,. is*t; ~17 Fx 29. PPO(s) [E] 30. SNSOCs Fx3 31. Site Vice Presidents 1j] 32. Vice President (Corp)

33. PPO ( 34. Date 435. PPO (Signature) N/A 136. Date L U . _ +.I///Z.39. SNSOC Chairman (Si nature) 40. Date

+ -- q-----1--- +

43. Site Vice President (Signature)

N/A

-- J

44. Date 'I

_ _4 Ii Vice President Corporate (Signature) 46. Date I

in umlnl a1a ru F u.. U s 1ve .ILVu1

'S-North Anna Power Station; CORP. niOwner(s);

OC-Station Nuclear Safety and Oper an Implementing Procedures FormNo.720457(Ju2DO1)

L

DOMINION VPAP-2103S REVISION 6 PAGE 2 OF 71 TABLE OF CONTENTS Section Page 1.0 PURPOSE 4 2.0 SCOPE 4

3.0 REFERENCES

/COMMITMENT DOCUMENTS 5 4.0 DEFINITIONS 6 5.0 RESPONSIBILITIES 9 6.0 INSTRUCTIONS 11 6.1 Sampling and Monitoring Criteria 11 6.2 Liquid Radioactive Waste Effluents 11 6.2.1 Liquid Effluent Concentration Limitations 11 6.2.2 Liquid Monitoring Instrumentation 12 6.2.3 Liquid Effluent Dose Limit 15 6.2.4 Liquid Radwaste Treatment 18 6.2.5 Liquid Sampling 19 6.3 Gaseous Radioactive Waste Effluents 19 6.3.1 Gaseous Effluent Ddfse Rate Limitations 19 6.3.2 -Gaseous Monitoring Instrumentation 21 6.3.3 Noble Gas Effluent Air Dose Limit 24 6.3.4 I-13 1, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 26 6.3.5 Gaseous Radwaste Treatment 28 6.4 Radioactive Liquid and Gaseous Release Permits 29 6.4.1 Liquid Waste Batch Releases 29 6.4.2 Continuous Liquid Releases 29 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit 30 6.4.4 Reactor Containment Release Permits 30 6.4.5 Miscellaneous Gaseous Release Permit 30

DOMINION VPAP-2103S REVISION 6 PAGE 3 OF 71 TABLE OF CONTENTS (continued)

Section Page 6.4.6 Radioactive Liquid and Gaseous Release Controls 30 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 32 6.6 Radiological Environmental Monitoring 32 6.6.1 Monitoring Program 32 I.

6.6.2 Land Use Census 34 6.6.3 Interlaboratory Comparison Program 35 6.7 Reporting Requirements 36 6.7.1 Annual Radiological Environmental Operating Report 36 6.7.2 Annual Radioactive Effluent Release Report 37 6.7.3 Annual Meteorological Data 39 i 6.7.4 Changes to the ODCM 39 7.0 RECORDS 40 1

ATTACHMENTS Radioactive Liquid Effluent MonitoringInstrumentation 42 L

2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 43 L

3 Radioactive Liquid Waste Sampling and Analysis Program 44 4 Radioactive Gaseous Waste Sampling and Analysis Program 47 L 5 Radioactive Gaseous Effluent Monitoring Instrumentation 51 6 Radioactive Gaseous Effluent Monitoring Instrumentation 53 LT Surveillance Requirements 7 Radiological Environmental Monitoring Program 55 L 8 Environmental Sampling Locations 58 9 Detection Capabilities for Environmental Sample Analysis 61 L 10 Reporting Levels for Radioactivity Concentrations in Environmental 63 Samples Lo1 11 Meteorological, Liquid, and Gaseous Pathway Analysis 64 I

Li

DOMINION VPAP-2103S REVISION 6 PAGE 4 OF71 1.0 PURPOSE

'[he Offsite Dose Calculation Manual (ODCM) establishes requirements for the Radioactive Effluent and Radiological Environmental Monitoring Programs. Methodology and parameters are provided to calculate offsite doses resulting from radioactive gaseous and liquid effluents, to calculate gaseous and liquid effluent monitoring alarm/trip setpoints, and to conduct the Environmental Monitoring Program. Requirements are established for the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Station Technical Specifications. Calculation of offsite doses due to radioactive liquid and gaseous effluents are performed to assure that:

• Concentration of radioactive liquid effluents to the unrestricted area will be limited to ten times the effluent concentration values of 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases and 2E-4 [tCi/ml for dissol ved or entrained noble gases.

• Exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10 CFR 50, Appendix I

• Dose rate at and beyond the site boundary from radioactive gaseous effluents will be limited to:

Noble gases - less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin

• 131 j33, and H , and all radionuclides in particulate5form with half-lives greater than 8 days - less than or equal to a dose rate of 1500 mrem/yr to any organ

• Exposure from radioactive gaseous effluents to the maximum exposed member of the public in the unrestricted area will not result in doses greater than the gaseous dose limits of 10 CFR 50, Appendix I, and

• Exposure to a real individual will not exceed 40 CFR 190 dose limits 2.0 SCOPE This procedure applies to the Radioactive Effluent and Environmental Monitoring Programs at Surry Power Station.

DOMINION VPAP-2103S REVISION 6 PAGE 5 OF 71

3.0 REFERENCES

/COMMITMENT DOCUMENTS 3.1 References 3.1.1 10 CFR 20, Standards for Protection Against Radiation 3.1.2 10 CFR 50, Domestic Licensing of Production and Utilization Facilities 3.1.3 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites 3.1.5 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, Rev. 1, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I, Rev. 1, U.S. NRC, October 1977 3.1.7 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev. 1, U.S. NRC, July 1977  ; L 3.1.8 Surry Technical Specifications (Units 1 afid 2) --.

3.1.9 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine L Effluent Releases at Nuclear Power Stations, U.S..NRC, September 1977 3.1.10 NUREG/CR-1276, Users Manual for the LADTAP II Program, U.S. NRC, May, 1980 3.1.11 TID-4500, VCRL-50564, Rev. 1, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, October, 1972

/ 3.1.12 WASH 1258, Vol.2, July 1973, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Practicable" For Radioactive Material in Light Water-Cooled Nuclear Power Reactor Effluents 3.1.13 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June, 1980 L 3.1.14 Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Rev. I 3.1.15 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations, October, 1978 3.1.16 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.17 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, Draft, Rev. 3, March 1982 3.1.18 Environmental Measurements Laboratory, DOE HASL 300 Manual

DOMINION VPAP-2103S REVISION 6 PAGE 6 OF 71 3.1.19 NRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program 3.1.20 Surry UFSAR 3.1.21 Laboratory Quality Assurance Plan, Manual 100; Framatome Environmental Laboratory

.3.1.22 VPAP-2802, Notifications and Reports 3.2 Commitment Documents 3.2.1 Quality Assurance Audit Report Number 92-03, Observation 04NS (Item 2) 3.2.2 Deviation Report S-97-1281, Annual Radiological Effluent Release Report 3.2.3 Deviation S-2000-0235, Continuous Vent Stack Sampling 4.0 I)EFINITIONS 4.1 Channel Calibration

-Adjustment, as necessary, of the channel output so it responds with the necessary range and accuracy to known values of the parameter the channel monitors. It encompasses the entire channel, including the sensor and alarm and/or trip functions and the Channel Functional Test.

The Channel Calibration can be performed by any series of sequential, overlapping, or total channel steps so the entire channel is calibrated.

4.2 Channel Check A qualitative assessment, by observation, of channel behavior during operation. This assessment includes, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

4.3 Channel Functional Test There are two types of Channel Functional Tests.

4.3.1 Analog Channel Injection of a simulated signal into a channel, as close to the sensor as practicable, to verify Operability, including alarm and/or trip functions.

4.3.2 Bistable Channel Injection of a simulated signal into a sensor to verify Operability, including alarm and/or trip functions.

DOMINION VPAP-2103S REVISION 6 PAGE 7 OF 71 4.4 Critical Organ That organ, which has been determined to be the maximum exposed organ based on an effluent pathway analysis, thereby ensuring the dose and dose rate limitations to any organ will not be exceeded.

4.5 Dose Equivalent 1-131 I That concentration of I131 (pCilcc) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I131, I132, j133, i134, and 1135 actually present. Thyroid dose conversion factors for this calculation are listed in Table III of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used.

L.4 4.6 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.

• NOTATION FREQUENCY

. . ,I . ,

. a . - :

D - Daily At least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: L W - Weekly M - Monthly At least once per 7 days At least once per 31 days L

Q - Quarterly At least once per 92 days L

SA - Semi-annually At least once per 184 days R - Refueling S/U - Start-up

/ At least once per 18 months Prior to each reactor start-up L

P - Prior to release Completed prior to each release N.A. - Not applicable Not applicable I-DR - During the release At least once during each release 4.7 Gaseous Radwaste Treatment System A system that reduces radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing delay or holdup to reduce total radioactivity prior to release to the environment. The system comprises the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers and waste gas surge tanks.

j1

DOMINION VPAP-2103S REVISION 6 PAGE 8 OF 71 4.8 General Nomenclature x = Chi: concentration at a point at a given instant (curies per cubic meter)

D= Deposition: quantity of deposited radioactive material per unit area (curies per square meter)

Q = Source strength (instantaneous; grams, curies)

= Emission rate (continuous; grams per second, curies per second)

= Emission rate (continuous line source; grams per second per meter) 4.9 lower Limit of Detection (LLD)

The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that can be detected with 95 percent probability with only five percent probability of falsely concluding that a blank observation represents a "real" signal.

4.10 Members of the Public Individuals who, by virtue of their occupational status, have no formal association with the Station. This category includes non-employees of Dominion who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station

functions. This category does not include non-employees such as vending machine seivic emen

cr postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Dominion to protect individuals from exposure to radiation and radioactive materials.

4.11 Operable - Operability A system, subsystem, train, component, or device is operable or has operability when it is capable of performing its specified functions and all necessary, attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its functions are also capable of performing their related support functions.

4.12 Purge - Purging Controlled discharge of air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, so that replacement air or gas is required to purify the confinement.

DOMINION VPAP-2103S REVISION 6 PAGE 9 OF 71 4.13 Rated Thermal Power Total reactor core heat transfer rate to reactor coolant (i.e., 2546 Megawatts Thermal MWt).

4.14 Site Boundary The line beyond which Dominion does not own, lease, or otherwise control the land.

4.15 Source Check A qualitative assessment of channel response when a channel sensor is exposed to radiation.

This applies to installed radiation monitoring systems.

4.16 Special Report A report to NRC to comply with Subsections 6.2, 6.3, or 6.5 of this procedure. Also refer to VPAP-2802, Notifications and Reports.

4.17 Thermal Power X Total reactor core heat transfer rate to the reactor coolant. -

4.18 .: Unrestricted Area Any area at or beyond the site boundary, access to which is neither limited nor controlled by L Dominion for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional or recreational purposes.

4.19 Ventilation Exhaust Treatment System L A system that reduces gaseous radiyiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and High L Efficiency Particulate Air (HEPA) filters to remove iodines and particulates from a gaseous exhaust stream prior to release to the environment (such a system is not considered to have any i effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems X are not Ventilation Exhaust Treatment System components.

5.0 RESPONSIBILITIES 5.1 Manager Radiological Protection The Manager Radiological Protection is responsible for:

5.1.1 Establishing and maintaining procedures for surveying, sampling, and monitoring radioactive effluents and the environment.

L

DOMINION VPAP-2103S REVISION 6 PAGE IO 0F71 5.1.2 Surveying, sampling, and analyzing plant effluents and environmental monitori ng, and documenting these activities.

5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends.

5.1.4 Preparing Effluent and Environmental Monitoring Program records.

5.2 Manager Nuclear Operations -

The Manager Nuclear Operations is responsible for requesting samples, analyses, and authorization to release effluents.

f  :. , ,

. 7 ,

/

DOMINION VPAP-2103S REVISION 6 PAGE 11 OF 71 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Meteorological, Liquid, and Gaseous Pathway Analysis (Attachment 11).

6.1 Sampling and Monitoring Criteria 6.1.1 Surveys, sampling, and analyses shall use instruments calibrated for the type and range of radiation monitored and the type of discharge monitored.

6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation or parameter monitored. l 6.1.3 A sufficient number of survey points shall be used or samples taken to adequately assess the status of the discharge monitored.

6.1.4 Samples shall be representative of the volume and type of discharge monitored.

6.1.5 Surveys, sampling, analyses, and monitoring records shall be accurately and legibly  : X documented, and sufficiently detailed that the meaning and intent of the records are clear.  :'

6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness, and accuracy. X 6.2 Liquid Radioactive Waste Effluents '

6.2.1 Liquid Effluent Concentration Limitations/

a. Liquid waste concentrations discharged from the Station shall not exceed the following limits: L

1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent L concentrations released to unrestricted areas shall not exceed ten times the effluent concentration values specified in 10 CFR 20, Appendix B, Table 2, 1 Column 2. Li

2. For dissolved or entrained noble gases, concentrations shall not exceed 1 2E-4 jiCi/ml. I

b. If the concentration of liquid effluent exceeds the limits in 6.2.1 .a., promptly reduce concentrations to within limits.

DOMINION VPAP-2103S REVISION 6 PAGE 12 OF 71

c. Daily concentrations of radioactive materials in liquid waste released to unrestricted areas shall meet the following:

Volume of Waste Discharged + Volume of Dilution Water> (

• LCi/ml.

Volume of Waste Discharged x .

where:

[iCi0/ml = the concentration of nuclide i in the liquid effluent discharge ACWi = ten times the effluent concentration value in unrestricted areas of nuclide i, expressed as gCi/ml from 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases, and 2E-4 iCilml for dissolved or entrained noble gases 6.2.2 Liquid Monitoring Instrumentation

a. Radioactive Liquid Effluent Monitoring Instrumentation

- Radioactive liquid effluent monitoring instrumentation channels shown on Radioactive Liquid Effluent Monitoring Instrumentation (Attachment 1) shall be operable with their alarm/trip setpoints set to ensure that 6.2.1.a. limits are not exceeded.

1. Alarm/trip setpoints of these channels shall be determined and adjusted in accordance with 6.2.2.d., Setpoint Calculation.

2. If a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required by 6.2.2.a., perform one of the following:

• Promptly suspend release of radioactive liquid effluents monitored by the affected channel

• Declare the channel inoperable

• Change the setpoint to an acceptable, conservative value

DOMINION VPAP-2103S REVISION 6 PAGE 13 OF 71

b. Radioactive Liquid Effluent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be L, demonstrated operable by performing a Channel Check, Source Check, Channel Calibration, and Channel Functional Test at the frequencies shown in Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 2).

1. If the number of operable channels is less than the minimum required by the tables in Radioactive Liquid Effluent Monitoring Instrumentation (Attachment

1) perform the action shown in those tables.

2. Attempt to return the instruments to operable status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. Applicable Monitors Liquid effluent monitors for which alarm/trip setpoints shall be determined are:

Li Release Point - Instrument Number Service Water System Effluent Line 1-SW-RM-107 A, B, C, D L

Condenser Circulating Water Line 1-SW-RM-120 2-SW-RM-220 U Radwaste Facility Effluent Line 1-RM-RRM-131 L7 L

Li LiJ I

Li1

DOMINION VPAP-2103S REVISION 6 PAGE 14 OF 71

d. Setpoint Calculation N'OTE: This methodology does not preclude use of more conservative setpoints.

1. Maximum setpoint values shall be calculated by:

CF S = D (2)

FE where:

S = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution C = the effluent concentration limit for the monitor used to implement 10 C1R 20 for the Station, in jiCi/ml FE = maximum design pathway effluent flow rate FD = dilution water flow rate calculated as:

D - FE + (200,000 gpm x number of circ. pumps in service)

2. Each of the condenser circulating water channels (e.g., SW-120, SW-220) monitors the effluent (service water, including component cooling service water, circulating water, and liquid radwaste) in the circulating water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, Equation (2) becomes:

S = C (3)

The setpoint for Station monitors used to implement 10 CFR 20 for the site becomes the effluent concentration limit.

3. In addition, for added conservatism, setpoints shall be calculated for the service water system effluent line (i.e., SW-107 A, B, C, D), and the Radwaste Facility effluent line (i.e., RRM-131).

DOMINION VPAP-2103S REVISION 6 PAGE 15 OF 71

4. For the service water system effluent line, Equation (2) becomes:

S CFDKSW (4)

FE where:

Ksw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 for the Station, attributable to the service water effluent line pathway

5. For the Radwaste Facility effluent line, Equation (2) becomes:

= CFDKRW FE where:

KRW = The fraction of~the effluent concentration limit, used to implement 10 CFR 20 attributable to the Radwaste Facility effluent line pathway: -

6. The sum KSW + KRW shall not be greater than 1.0.

6.2.3 Liquid Effluent Dose Limit

a. Requirement At least once per 31 days, perform the dose calculations in 6.2.3.c. to ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials inliquid releases (from each reactor unit) to unrestricted areas h is limited to:

1. During any calendar quarter:

• Less than or equal to 1.5 mrem to the total body

• Less than or equal to 5 mrem to the critical organ

2. During any calendar year:

• Less than or equal to 3 mrem to the total body

• Less than or equal to 10 mrem to the critical organ L

DOMINION VPAP-2103S REVISION 6 PAGE 16 OF 71

b. Action If the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that identifies causes for exceeding limits and defines corrective actions taken to ieduce releases of radioactive materials in liquid effluents to ensure that subsequent:

releases will be in compliance with the above limits.

c. Dose Contribution Calculations NOTE: All critical organ doses for each age group are calculated to determine which is the limiting organ for the period being evaluated.

Dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on the equation:

.D tFM A j (6) where:

Subscripts = i, refers to individual radionuclide D = the cumulative dose commitment to the total body or critical organ from the liquid effluents for the period t, in mrem t = the period for which C; and F are averaged for all liquid releases, in hours M = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless, 0.2 from Appendix I IA, Surry UFSAR F = the near field average dilution factor for Ci during any liquid effluent release; the ratio of the average undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted areas C; = the average concentration of radionuclide, i, in undiluted liquid effluent during the period t, from all liquid releases, in 1iCi/ml

DOMINION VPAP-2103S REVISION 6 PAGE 17 OF 71 Ai = the site-related ingestion dose commitment factorto the total body orcritical organ for a particular age group for each identified principal gamma and L beta emitter in mrem-ml per hr-jiCi. Values for Ai are provided in the Canberra Source Code file.

A = 1.14 E+05(21BF +5BIY)DFi (7) for example:

1.14 E+05 = 1 E+06 pCi/fiCi x 1 E+03 ml/kg/(8760 hr/yr), units conversion factor 21 = adult fish consumption, kg/yr, from NUREG-0133 5 = adult invertebrate consumption, kg/yr, from NUREG-0133 Bli = the bioaccumulation factor for nuclide i, in invertebrates, pCi/kg per pCi/l BF1 = the bioaccumulation factor for nuclide i, in fish, pCi/kg per pCi/X DFi = the critical organ dose conversio'n factorjor nuclide i, for adults, in mrem/pCi -,

NOTE: The above parameters were obtained from R.G. 1.109, Rev. 1, LADTAP II, NUREG/CR-1276, and TID-4500, VCRL-50564, Rev. 1. LJ

d. Quarterly Composite Analyses For radionuclides not determined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative summation may be L approximated by assuming an average monthly concentration based on previous monthly or quarterly composite analyses. However, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses. Li

DOMINION VPAP-2103S REVISION 6 PAGE 103 OF 71 6.2.4 Liquid Radwaste Treatment Historical data pertaining to the volumes and radioactivity of liquid effluents r leased in connection with specific station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.

a. Requirement

1. The Surry Radwaste Facility Liquid Waste System shall be used to reduce the radioactive materials in liquid waste prior to discharge when projected dose due to liquid effluent, from each reactor unit, to unrestricted areas would exceed 0.06 mrem to total body or 0.2 mrem to the critical organ in a 31-day period.

2. Doses due to liquid releases shall be projected at least once per 31 days.

b. Action If radioactive liquid waste is discharged without treatment and in excess of the above limits, prepare and submit to the NRC, within 30 days, a special report in U.. accordance with VPAP-2802, Notifications and Reports, that includes the following: ,;

1. An explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-system, and the reason for the inoperability.

2. Actions taken to restore inoperable equipment to operable status.

/

3. Summary description of actions taken to prevent recurrence.

c. Projected Total Body and Critical Organ Dose Calculation

1. Determine DI, the sum of all liquid open and closed release points, in mrem, by the ith organ, for the quarter.

2. Determine P. the Projection Factor, which is result of 31 divided by the number of days from start of the quarter to the end of the release.

3. Determine Da, additional anticipated dose for liquid releases by the ith organ for the particular quarter of the release.

4. Determine Dp, the 31 day projected dose by the ith organ:

Dp=(DIxP)+Da

DOMINION VPAP-2103S REVISION 6 PAGE 19 OF 71 l 6.2.5 Liquid Sampling Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis requirements in Radioactive Liquid Waste Sampling and Analysis Program (Attachment 3).

6.3 Gaseous Radioactive Waste Effluents 6.3.1 Gaseous Effluent Dose Rate Limitations

a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to L.

areas at and beyond the site boundary shall be limited to:

1. The dose rate limit for noble gases shall be < 500 mrem/year to the total body and < 3000 mrem/year to the skin.

'1

2. The dose rate limit for 1131, 1133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be < 1500 mremlyear i ... i. h" . to the critical organ.

.I 1-7,

b. Action

.% t. I- . . , .

II

.  : . . .. i- 1. If dose rates exceed 6.3.1.a. limits, promptly decrease the release rate to within the above limits.

2. Dose rates due to noble gases in gaseous effluents shall be determined, L continuously, to be within 6.3.1.a. limits.

3. Dose rates due to 1131, 1133, tritium, and all radionuclides in particulate form LI with half-lives greater than 8 days, in gaseous effluents shall be determined to be within the above limits by obtaining representative samples and performing L analyses in accordance with the sampling and analysis program specified on Radioactive Gaseous Waste Sampling and Analysis Program (Attachment 4).

.I U-L

DOMINION VPAP-2103S REVIJION 6 PAGE 20 OF 71

c. Calculations of Gaseous Effluent Dose Rates NOTE: The dose factors used in the Gaseous Effluent Dose Rate calculations are included in the Canberra Source Code file. These dose factors, Ki, Li, Mi, and Pi for ventilation vent and process vent releases, DO NOT include the applicable X/Q value. Equations (8), (9), and (10) must be multiplied by the appropriate X/Q value for Gaseous Effluent Dose Rate calculations.

1. The dose rate limit for noble gases shall be determined to be within the li mit by limiting the release rate to the lesser of:

YKivvQivv + K p6Qipv] S500 mrem/yr to the total body (8)

.Oi OR

... .. I % . . v + l 1Miv + (Lipv + 1.lMjpv)0pv3000 mrenlyr to the skin (9) where:

Subscripts vv, refers to vent releases from the building ventilation vent, including Radwaste Facility Ventilation Vent; pv, refers to the vent releases from the process vent; i, refers to individual radionuclide /

Kivv, Kipv = The total body dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec Livv, Lipv = The skin dose factor for ventilation vents or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec

= The air dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per Curie/sec 1ivv.1pv = The release rate for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents in Curie/sec (per site) 1.1 = The unit conversion factor that converts air dose to skin dose, in mrem/mrad

DOMINION VPAP-2103S REVISION 6 PAGE 21 OF71

2. The dose rate limit for I131, I133, tritium, and for all radionuclides in particulate i I form with half-lives greater than 8 days, shall be determined to be within the limit by restricting the release rate to:

VPivvQivv + PipvQpv] <1 500 mremn/yr to the critical organ (10) i where:

P, Ppv = The critical organ dose factor for ventilation vents or process vent for 1131,1 33, H3 , and all radionuclides in particulate form with half-lives greater than 8 days, for the inhalation pathway, in mrem/yr per Curie/sec 0iVV.ipv = The release rate for ventilation vents or process vent of I131, I133, H3 , and all radionuclides i, in particulate form with half-lives greater than 8 days, in gaseous effluents in Curie/sec (per site)

3. All gaseous releases, not through the process vent, are considered ground level

.*-; ;:-. and shall be included in the determination of Q1 .,

6.3.2 Gaseous Monitoring Instrumentation .L

a. Requirement

1. The radioactive gaseous effluent monitoring instrumentation channels shown in Radioactive Gaseous Effluent Monitoring Instrumentation (Attachment 5) shall be operable with alarm/trip setpoints set to ensure that 6.3.1.a. noble gas limits F1 are not exceeded. Alarm/trip setpoints of these channels shall be determined and adjusted in accordance with 6.3.2.d.

2. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by Channel Checks, Source Checks, Channel Calibrations, and Channel Functional Tests at the frequencies shown in Li Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 6).

L

DOMINION VPAP-2103S REVISION 6 PAGE 22 OF 71

b. Action

1. If a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required by 6.3.2.a.1, promptly:

• Suspend the release of radioactive gaseous effluents monitored by the affected channel and declare the channel inoperable or

• Change the setpoint so it is acceptably conservative

2. If the number of operable channels is less than the minimum required by tables in Radioactive Gaseous Effluent Monitoring Instrumentation (Attachment 5),

take the action shown in those tables.

3. Return instruments to operable status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

.cApplicable Monitors Radioactive gaseous effluent monitors for which alarm/trip setpoints shall be determined are: I .

Release Point Instrument Number Process Vent 1-GW-RM-102 1-GW-RM-130-1 Condenser Air Ejector 1-SV-RM-111 2-SV-RM-211 Ventilation Vent No. 1 1-VG-RM-104 Ventilation Vent No. 2 1-VG-RM-110 1-VG-RM-131-1 Radwaste Facility Vent RRM-101

DOMINION VPAP-2103S REVISION 6 PAGE 23 OF 71

d. Setpoint Calculations

1. Setpoint calculations for each monitor listed in 6.3.2.c. shall maintain this relationship:

D>Dpv +Dcae +Dvv (1 1) where:

D = Step 6.3.1.a. dose limits that implement 10 CFR 20 for the Station, mrem/yr DPV = The noble gas site boundary dose rate from process vent gaseous effluent releases, mrem/yr Dcae = The noble gas site boundary dose rate from condenser air ejector gaseous effluent releases, mrem/yr DVV = The noble gas site boundary dose rate from summation of the Ventilation Vents 1, 2, and the Radwaste Facility vent gaseous effluent releases, mrem/yr

2. Setpoint values shall be determined by:

Cm =

Rm X 2.12 E-03 (12)

.1]

Fm where:

U m = The release pathway, process vent (pv), ventilation vent (vv) condenser air ejector (cae), or Radwaste Facility (rv) Li Cm = The effluent concentration limit implementing 6.3.1.a. for the Rm Station, ttCi/ml

= The release rate limit for pathway m determined from Li methodology in 6.3.1 .c., using XeI 33 as nuclide to be released, 2.12E-03 j1Ci/sec

= CFM per ml/sec Li Fm = The maximum flow rate for pathway m, CFM Li NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm/trip setpoints should be based on the radioactive noble gases. It is not practicable to apply instantaneous alarm/trip setpoints to integrating monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.

U1

DOMINION VPAP-2103S REVISION 6 PAGE 24 OF 71 6.3.3 Noble Gas Effluent Air Dose Limit NOTE: The dose factors used in the Noble Gas air dose calculations are included in tho Canberra Source Code file. These dose factors, Mi and Ni for ventilation vent and process vent releases, DO NOT include the applicable X/Q value. Equations (13) and (14) must be multiplied by the appropriate X/Q value for gamma and beta air dose calculations.

a. Requirement

1. The air dose in unrestricted areas due to noble gases released in gaseous effluents from each unit at or beyond the site boundary shall be limited to:

• During any calendar quarter: :5 mrads for gamma radiation and <10 mrads for beta radiation

• During any calendar year: <10 mrads for gamma radiation and '20 mrads for beta radiation

2. Cumulative close contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with 6.3.3.c. at least once per 31 days.

b. Action If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that identifies the causes for exceeding the limits and defines corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits in 6.3.3.a.

DOMINION VPAP-2103S ,

REVISION 6 PAGE 25 OF 71

c. Noble Gas Effluent Air Dose Calculation Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qivv The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following:

For gamma radiation:

Dg = 3.17E-08xMivvQivv + MipvQipv]

(13) i For beta radiation:

Db = 3.17E-08XNivvQivv +NipvQipv] (14)

'Where Subscripts vv,'iefers to vent releases from the building ventilation vents, [1

-including the Radwaste Facility Ventilation Vent and air ejectors pv, refers to the vent releases from the process vent i, refers to individual radionuclide Dg = the air dose for gamma radiation, in mrad Db = the air dose for beta radiation, in mrad MiVV MiPV = the air dose factors for ventilation vents or process v9 nt release L

due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per Curie/sec Nivv, Nipv - the air dose factor for ventilation vents or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per Curie/sec Qiws Qipv - the release for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site) 3.17 E-08 = the inverse of the number of seconds in a year I

U

DOMINION VPAP-2103S REVISION 6 PAGE 26 OF 71 6.3.4 1-131, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit

a. Requirement

1. Methods shall be implemented to ensure that the dose to any organ of a member of the public from 113, I"33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from the site to unrestricted areas from each reactor unit shall be:

• During any calendar quarter: < 7.5 mrem to the critical organ

• During any calendar year: < 15 mrem to the critical organ

2. Cumulative dose contributions to a member of the public from 131, 132, tritium, and radionuclides in particulate form with half-lives greater than 3 days, in gaseous effluents released to unrestricted areas for the current calendar quarter and current calendar year shall be determined at least once per 31 days in accordance with 6.3.4.c.

b. Action If the calculated dose from the release of j131, 1133, tritium, and radionuclid s in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, a sp cial report in accordance with VPAP-2802, Notifications and Reports, that contains the:

1. Causes for exceeding limits.

2. Corrective actions taken to reduce releases. /

3. Proposed corrective actions to be taken to assure that subsequent releases will be in compliance with limits stated in 6.3.4.a.

DOMINION VPAP-2103S REVISION 6 PAGE 27 OF 71

c. Dose Calculations NOTE: All critical organ doses for each age group are calculated to determine which is the limiting organ for the period being evaluated.

NOTE: The RM; and RI; dose factors DO NOT include the applicable D/Q and X/Q values respectively for Surry Power Station. Equation (15) must be multiplied by the applicable D/Q or X/Q, as appropriate, to calculate the critical organ dose.

Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of biv,. Historical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in the estimates, as appropriate.

1. The dose to the maximum exposed member of the public, attributable to gaseous effluents at and beyondthe site boundary that contain I131, j133, tritium, and particulate-form radiqnuclides with half-lives greater than 8 days, shall be determined by: I Dr = 3.17E-O8N(RMivvQivv + RMipvQipv) + (RtivvQivv + RlipvQipv)] (15) iJ1vV plV iVV p 1 I. For example:

Subscripts = vv, refers to vent releases from the building ventilation vents, including the Radwaste Facility Ventilation Vent and air Li ejectors; pv, refers to the vent releases from the process vent Dr = the dose to the critical organ of the maximum exposed member of the public in mrem RMim RM 1pv= the cow-milk pathway dose factor for ventilation vents or process vent release due to 1131, 1133, tritium, and from all particulate-form radionuclides with half-lives greater than eight days, in mrem/yr per jICi/m3 . Factors are included in the Canberra Source Code file.

L

DOMINION VPAP-2103S REVISION 6 PAGE 28 OF 71 Rijvv, RI 1pv = the inhalation pathway dose factor for ventilation vents or process vent release due to 1131, 1133, tritium, and from all particulate-form radionuclides with half-lives greater than eight days, in mrem/yr per pCi/m 3 . Factors are included in the Canberra Source Code file.

biVVipv = the release for ventilation vents or process vent of 1131, I133, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curies 3.17 E-08 = the inverse of the number of seconds in a year 6.3.5 Gaseous Radwaste Treatment Historical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection with specific Station functions, such as containment purges, shall be used to calculate projected doses, as appropriate.

a. Requirement

1. Appropriate portions of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, wh-n the projected gaseous effluent air doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, averaged over 31 days.

2. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when the projected doses due to gaseous effluent releases, from each unit to areas at and beyond the site /

boundary, would exceed 0.3 mrem to the critical organ, averaged over 31 days.

3. Doses due to gaseous releases from the site shall be projected at least once per 31 days, based on the calculations in 6.3.5.c.

b. Action If gaseous waste that exceeds the limits in 6.3.5.a. is discharged without treatment, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that includes:

1. An explanation why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason fbr the inoperability.

2. Actions taken to restore the inoperable equipment to operable status.

DOMINION VPAP-2103S REVISION 6 PAGE 29 OF 71

3. Summary description of actions taken to prevent recurrence.

c. Projected Dose Calculations

1. Determine Dg, the sum of all gaseous open and closed release points, in mrem, by the ith organ, for the quarter.

2. Determine P, the Projection Factor, which is result of 31 divided by the number of days from start of the quarter to the end of the release.

3. Determine Da, additional anticipated dose for gaseous releases by the ith organ for the particular quarter of the release.

4. Determine Dp, the 31 day projected dose by the ith organ.

Dp=(DgxP)+Da 6.4 Radioactive Liquid and Gaseous Release Permits RP shall maintain procedures for Liquid and Gaseous Release Permits to ensure effluent dose limits are not exceeded when making releases. As indicated on Attachment 3, Radioactive .

Liquid Waste Sampling and Analysis Program, prerelease assessments/permits are required fdr batch releases. Depending on the affected plant system, continuous releases may or may not L allow for a prerelease assessment and are evaluated on a-case by case basis.

6.4.1 Liquid Waste Batch Releases L

a. Operations shall obtain RP authorization before initiating batch releases of radioactive liquids.

b. Release of content~. from the following tanks/sumps other than transfers to the Radwaste Facility shall have a release permit before the discharge. Examples of il batch releases include:

• Turbine Building Sumps when RP determines that source activity requires placing pumps in manual mode L

• Condensate Polishing Building Sumps and Steam Generator secondary water when RP determines the presence of contamination from primary-to-secondary leakage

• Radwaste Facility release tanks (LWMT, LDMT) 6.4.2 Continuous Liquid Releases *'

a. Operations shall obtain RP authorization before initiating continuous releases of radioactive liquids.

DOMINION VPAP-2103S REVISION 6 PAGE 30 OF 71

b. Examples of continuous releases include:

• Steam generator blowdown

• Component Cooling Water (CCW) heat exchanger to service water leakage, if applicable

• Turbine building sumps and subsurface drains when pumps are in automatic mode or storm drains 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit Operations shall obtain RP authorization before initiating WGDT releases.

6.4.4 Reactor Containment Release Permits Operations shall obtain authorization from RP before initiating containment purges or containment hogging. Reactor Containment Release Permits shall be valid from start of purge/hog until:

• Routine termination

*

• Terminated for cause by RP - -

L Receipt of Radiation Monitoring S-ystem (RMS) Containment Gas Monitor high alarm i~ 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorization before initiating releases of noble gases that iLi ,may not be accounted for by routine sampling, or any planned release not being routed through the Process Vent or Ventilation Vents.

6.4.6 Radioactive Liquid and Gaseous Release Controls

a. Operations shall notify RP of pending releases and request RP to initiate the L appropriate release permit. Operations shall provide the necessary information to complete the required release permit.

b. A representative sample shall be obtained of the source to be released.

1. Operations shall provide RP with liquid samples and sample information (e.g.,

time of sample) for samples obtained outside the Primary Sample Room.

2. Chemistry shall provide RP with liquid samples and sample information for L L3.b samples obtained from inside the Primary Sample Room.

RPshall obtain gaseous samples.

DOMINION VPAP-2103S REVISION 6 PAGE 31 OF71

c. RP shall perform required sample analyses.

d. RP shall calculate and record the following information on a release permit:

• Maximum authorized release rate

• Applicable conditions or controls pertaining to the release

e. RP shall notify the Shift Supervisor if it is determined that a release may not be within the effluent dose limits.

f. Upon receipt of a release permit from RP, Operations shall:

1. Verify the correct source is authorized for release.

2. Note maximum authorized release rate.

3. Note and ensure compliance with any indicated controls or conditions applicable to the release.

g. When commencing release, Operations shall provide RP with required information.

As appropriate, required information shall include:

• Date and time release was started

• Starting tank/sump level L

• Beginning pressure

• Release flow rate L

• Dilution water flow rate

h. Upon terminating the release, Operations shall return the permit to RP and provide information necessary for completion of permit. As appropriate, required L

information shall include:

• Date and time release was stopped

• Tank/sump ending level

• Release flow rate just prior to termination

• Ending pressure

I

• Volume released

DOMINION VPAP-2103S REVISION 6 PAGE 32 OF 71 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 6.5.1 Requirement The annual (calendar year) dose or dose commitment to a real individual due to releases of radioactivity and radiation from uranium fuel cycle sources shall not exceed 25 mrem to the total body or the critical organ (except the thyroid, which shall not exceed 75 mrem).

6.5.2 Action

a. If the calculated doses from release of radioactive materials in liquid or gaseous effluents exceed twice the limits in 6.2.3.a., 6.3.3.a., or 6.3.4.a., calculate (including direct radiation contribution from the units and from outside storage tanks) whether limits in 6.5.1 have been exceeded.

b. If the limits in 6.5.1 have been exceeded, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that defines the corrective action to be taken to reduce subsequent releases L . and to prevent recurrence, and includes a schedule for achieving conformance with the limits. Special reports, as defined in 10 CFR 20.2203(a)(4),.shall include:

L 1. An analysis that estimates the radiation exposure (dose) to a real individual from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases covered by the report.

2. A description of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

3. If the estimated dose exceeds the limits in 6.5.1, and if the release condition that violates 40 CFR 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

6.6 IRadiological Environmental Monitoring 6.6.1 Monitoring Program

a. Requirement

1. The Radiological Environmental Monitoring Program shall be conducted as L specified in Radiological Environmental Monitoring Program (Attachment 7).

L

DOMINION VPAP-2103S REVISION 6 PAGE 33 OF 71

2. Samples shall be collected from specific locations specified in Environmental 1

Sampling Locations (Attachment 8). 4_-

3. Samples shall be analyzed in accordance with:

• Radiological Environmental Monitoring Program (Attachment 7) requirements -1

• Detection capabilities required by Detection Capabilities for Environmental Sample Analysis (Attachment 9)

• Guidance of the Radiological Assessment Branch Technical Position on

&-4 Environmental Monitoring dated November, 1979, Revision No. 1

b. Action

1. If the Radiological Environmental Monitoring Program is not being conducted as required in 6.6.1.a., report the situation in accordance with VPAP-2802, Notifications and Reports, by preparing and submitting to the NRC, in the

i. . . . . 7 .

j.

Annual Radiological Environmental Operating Report required by Technical 1'. . , '. . . -

I

.'(  ; ; . -

:-Specification (Surry Technical Specification 6.6.B.2), a description of the

. . , :. j  :.. . '. - . -m. reasons for not conducting the program as required, and the plan for precluding recurrence.

2. If, when averaged over any calendar quarter, radioactivity exceeds the reporting levels of Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 10), prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that: L

• Identifies the causes for exceeding the limits, and i.

• Defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of 6.2.3, 6.3.3, and 6.3.4 When more than one of the radionuclides listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 10) are detected in the sampling medium, the report shall be submitted if:

concentration (1) + concentration (2) +... > 1.0 (16) reporting level (1) reporting level (2)

DOMINION VPAP-2103S REVISION 6 PAGE 34 OF 71

3. When radionuclides'other than those listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 10) are detected and are the result of plant effluents, the report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of 6.2.3, 6.3.3, and 6.3.4. The report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, report and describe the condition in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.

4. If milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required by Radiological Environmental Monitoring Program (Attachment 7), identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify the cause of the unavailability of samples and iddntify the new locations for obtaining replacement samples in'the next Annual Radioactive Effluent Release Report in accordance with VPAP-2802, Notifications and Reports.

6.6.2 Land Use Census

a. Requirement A land use census shall be conducted and shall identify, within a distance of 8 km (5 miles), the location in each of the 16 meteorological sectors of the following:

• Nearest milk animal

• Nearest residence

• Nearest garden greater than 50 m2 (500 ft2 ) that produces broad leaf vegetation

1. The land use census shall be conducted during the growing season, at least once per 12 months, using methods that will provide the best results (e.g.,

door-to-door survey, aerial survey, local agriculture authorities). Land us-census results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.

DOMINION VPAP-2103S REVISION 6 PAGE 35 OF 71

2. In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted ground deposition (D/Qs). Specifications for broad leaf vegetation sampling in Radiological Environmental Monitoring Program (Attachment 7) shall be followed, including analysis of control samples.

b. Action

1. If a land use census identifies locations that yield a calculated dose or dose commitment greater than the values currently being calculated in 6.3.4.a.,

identify the new locations in the next Annual Radioactive Effluent Release Report in accordance with VPAP-2802, Notifications and Reports.

2. If a land use census identifies locations that yield a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained, add the new locations to the Radiological Environmental Monitoring Program within 30 days. Sampling locations, excluding the control station location, that have the lowest calculated dose or dose commitments (via the same exposure pathway) J may be deleted from the monitoring program. Identify new locations in the next Annual Radioactive Effluent Release Report and include in the report revised figures and tables reflecting the new locations in accordance with VPAP-2802, Notifications and Reports. [Commitment 3.2.1]

6.6.3 Interlaboratory Comparison Program

a. Requirement Radioactive materials (which contain nuclides produced at the Station), supplied as part of an Interlaboratory Comparison Program, shall be analyzed.

L

DOMINION VPAP-2103S REVISION 6 PAGE 36 OF 71

b. Action

1. Analyses shall be performed at least semiannually as follows:

Program Cross-Check of Milk I131, Gamma, Sr89 and Sr90 Water Gross Beta, Gamma, I131, H3 (Tritium), Sr89 and Sr90 (blind-any combinations of above radionuclides)

Air Filter Gross Beta, Gamma, Sr 90

2. If analyses are not performed as required by 6.6.3.b., report in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports, the corrective actions taken to prevent recurrence.

c. Results Results shall be reported in the Annual Radiological Environmental Monitoring Report in accordance with VPAP-2802, Notifications and Reports.'

6.7 Reporting Requirements 6.7.1 Annual Radiological Environmental Operating Report Routine Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year.

A single submittal may be made for the Station. Radiological Environmental Operating Reports shall include:

a. Summaries, interpretations, and analysis of trends of results of radiological environmental surveillance activities for the report period, including:

• A comparison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reports

• An assessment of the observed impacts of the plant operation on the environment

• Results of land use census per 6.6.2

b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per 6.6.1, Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.

DOMINION VPAP-2103S REVISION 6 PAGE 37 OF 71

1. If some individual results are not available for inclusion with the report, the report shall be submitted, noting and explaining reasons for missing results.

2. Missing data shall be submitted in a supplementary report as soon as possible.

c. A summary description of the radiological environmental monitoring program.

d. At least two legible maps covering sampling locations, keyed to a table giving distances and directions from the centerline of one reactor. One map shall cover stations near the site boundary; a second shall include more distant stations.

e. Results of Station participation in the Interlaboratory Comparison Program, per 6.6.3.

f. Discussion of deviations from the Station's environmental sampling schedule per Radiological Environmental Monitoring Program (Attachment 7).

g. Discussion of analyses in which the lower limit of detection (LLD) required by Detection Capabilities for Environmental Sample Analysis (Attachment 9) was not achievable.  :

LI NOTE: NUREG'0543 states: .There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40 CFR Part 190." L 6.7.2 Annual Radioactive Effluent Release Report L

a. Requirement - Station Radioactive Effluent Release Reports covering operation of the units during the L previous 12 months of operation shall be submitted before May 1 of each year. A single submittal may be made for the Station and should combine those sections that are common to both units. Radioactive Effluent Release Reports shall include:

I. A summary of quantities of radioactive liquid and gaseous effluents and solid waste released. Data shall be summarized on a quarterly basis following the format of Regulatory Guide 1.21, Appendix B, for liquid and gaseous effluents.

Data shall be summarized on an annual basis following the format of Regulatory Guide 1.21, Appendix B, for solid waste.

[Commitment 3.2.2]

DOMINION VPAP-2103S REVISION 6 PAGE 33 OF 71

2. An assessment of radiation doses to the maximum exposed members oi. the public due to the radioactive liquid and gaseous effluents released frorn the Station during the previous calendar year. This assessment shall be in accordance with 6.7.2.b.

3. A list and description of unplanned releases from the site to unrestricted areas, during the reporting period, which meet the following criteria:

• Unplanned releases that exceeded the limits in 6.2.1 and 6.3.1

• Unplanned releases which require a Plant Issue (Deviation) and involve the discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release tank W -* Unplanned releases from large leaks due to unexpected valve or pipe failures that result in a quantity of release such that a 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors or 10 CFR 50.73, Licensee Event Report System, report is required L Unplanned releases as determined by Radiation Protection Supervision,

• whichmay or may not require a Plant Issue (Deviation)

4. Major changes to radioactive liquid, gaseous, and solid waste treatment systems during the reporting period.

5. Changes to VPAP-2103S, Offsite Dose Calculation Manual (Surry) (See 6.7.4).

6. A listing of new locations for dose calculations or environmental monitoring hL' identified by the land use census (See 6.6.2).

b. Dose Assessment - Station

1. Radiation dose to individuals due to radioactive liquid and gaseous efflunts from the Station during the previous calendar year shall either be calculated in L accordance with this procedure or in accordance with Regulatory Guide 1.109.

.. Population doses shall not be included in dose assessments.

1 2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station and from the ISFSI shall be L incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits of 6.2.3.a.1, 6.2.3.a.2, 6.3.3.a.1, or 6.3.4.a.1, the dose assessment shall include the contribution from direct radiation.

L

DOMINION VPAP-2103S REVISION 6 PAGE 39 OF 71

3. Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine gaseous pathway doses.

NOTE: The Annual Radioactive Effluent Reports for Surry Station and Surry ISFSI are separate and not submitted as a combined report.

c. Requirement - ISFSI

1. Radioactive Effluent Release Report covering operation of the ISFSI during the previous 12 months of operation shall be submitted within 60 days after January 1.

2. The ISFSI Radioactive Effluent Release Report shall specify the quantities of each of the principal radionuclides released to the environment in liquid and in _

gaseous effluents.

3. Dose Assessment - ISF8I. .

Provide such information ;as may be required by the Commission to estimate potential radiation dose commitment to the public resulting from effluent L releases from the ISFSI.

6.7.3 Annual Meteorological Data L

a. Meteorological data collected during the previous year shall be in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

b. Meteorological data shall be retained in a file on site and shall be made available to NRC upon request. L 6.7.4 Changes to the ODCM Changes to the ODCM shall be:

a. Reviewed and approved by SNSOC and Site Vice President before implementation.

b. Documented. Records of reviews shall be retained as Station records.

Documentation shall include:

1. Sufficient information to support changes, together with appropriate analyses or evaluations justifying changes.

DOMINION VPAP-.2103S REVISION 6 PAGE 40 OF 71

2. A determination that a change will not adversely impact the accuracy or reliability of effluent doses or setpoint calculations, and will maintain the level of radioactive effluent control required by:

• 10 CFR 20 Subpart D

• 40 CFR 190

• 10 CFR 50.36a

• 10 CFR 50, Appendix I

c. Submitted to NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

d. Submitted to NRC in accordance with VPAP-2802, Notifications and Reports.

7.0 RECORDS 7.1 The following individual and packaged documents and. opies of any related correspondence completed as a result of the performance or implementation of this procedure are records. They shall be submitted to Records Management in accordance with VPAP-1701, Records Management. Prior to transmittal to Records Management, the sender shall assure that:

• Each record is packaged when applicable.

• QA program requirements have been fulfilled for Quality Assurance records.

• Each record is legible, completely filled out, and adequately identifiable to the item or activity involved.

• Each record is stamped, initialed, signed, or otherwise authenticated and dated, as required by this procedure.

7.1.1 Individual Records None

DOMINION VPAP-2103S REVISION 6 PAGE 41 OF 71 7.1.2 Record Packages

• Records of changes to the ODCM in accordance with 6.7.4

• Records of meteorological data in accordance with 6.7.3

• Records of sampling and analyses

• Records of radioactive materials and other effluents released to the environment

• Records of preventive maintenance, surveillances, and calibrations 7.2 The following documents completed as a result of the implementation of this procedure are not records and are not required to be transmitted to Records Management.

None

/

iDOMINION VPAP-2103S RE VISION 6 PAGE 42 OF 71 ATTACHMENT 1 (Page 1 of 1)

Radioactive Liquid Effluent Monitoring Instrumentation Instrument Minimum Action Operable Channels

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Radwaste Facility Liquid Effluent Line RM-RRM-131 1 I

2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: I-SW-RM-120 2 2 Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Effluent Line I-SW-RM-107A 4 2 I-SW-RM-107B I-SW-RM-107C I-SW-RM-107D

3. FLOW RATE MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 ACTION 1: If the number of operable channels is less than required, effluent releases shall be suspended.

ACTION4 2: If the number of operable channels is less than required, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters, as defined in Radioactive Liquid Waste Sampling and Analysis Program (Attachment 3).

ACTION 3: If the number of operable channels is less than required, effluent releases via this pathway shall be suspended.

L I

L

DOMINION VPAP-2103S REVISION 6 PAGE 43 OF 71 ATTACHMENT 2 (Page I of 1)

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel *1 Check Check Calibration Functional Test

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Radwaste Facility Liquid Effluent Line RM-RRM-131 D P R Q

2. GROSS BETA OR GAMMA RADIOACTIVI-TY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMI-NATION OF RELEASE I

-(a) Circulating Water Discharge Line Unit 1: I-SW-RM-120 D M R Q I.s . .

Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Efflu-ent Line I-SW-RM-107A D M R Q L I-SW-RM-107B I-SW-RM-107C I-SW-RM-107D U

3. FLOW RATE MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 DR N/A R N/A U?

I I -I LX

DOMITION VPAP .2103S REVISION 6 PAGE 44 OF 71 ATTACHMENT 3 (Page 1 of 3)

Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Fre- Minimum Analysis Type of Activity Lower Limit of Typequenque ncy uency Analysis (ICi/ml), (Note 1)

P P Principle Gamma 5 x 10; Emitters (Note 3)

(Each Batch) (Each Batch) 1131 1 x 10-,,

Dissolved and Batch Releases (One Batch/M) M Entrained Gases 1 x l0o-n a(Gamma Emitters)

(Note 2) P M Composite H3 1 x l0o-(Each Batch) (Note 4) Gross Alpha i 1 x 10-P Q Composite Sr89 and Sr 90 5 x 10-8 (Each Batch) (Note 4) Fe5 5 1 x 10-6 Continuous W Composite Principal Gamma 5 x 10-7 Emitters (Note 6)

/Note 6) (Note 6) I's' 1x10 6 Continuous . : M l Entrained DissolvedGases and 1 x 10-5 Releases Grab Sample (Gamm aE es (Gamma Emitters)

(Note 5) Continuous M Composite H3 1 x l0o-(Note 6) (Note 6) Gross Alpha 1 x 10-7 Continuous Q Composite Sr89 and Sr90 5 x 10-8 (Note 6) (Note 6) Fe 55 1 x 10-6

DOMINION VPAP-2103S REVISION 6 PAGE 45 OF 71 ATTACHMENT 3 (Page 2 of 3)

Radioactive Liquid Waste Sampling and Analysis Program NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD= b E

• V

• 2.22E+06

• Y

• e-(X~t)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection (as microcuries per unit mass or volume) (See 4.8)

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm)

E the counting efficiency (as counts per disintegration)

V = the sample size (in units of mass or volume) 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

X = the radioactive decay constant for the particular radionuclide At = the elapsed time between the midpoint of sample collection and time of counting Typical values of E, V,Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analyses, each batch shall be isolated, and appropriate methods will be used to obtain a representative sample for analysis.

DOMINION VPAP-2103S REVISION 6 PAGE 46 OF 71 ATTACHMENT 3 (Page 3 of 3)

Radioactive Liquid Waste Sampling and Analysis Program NOTE ': The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn5 4, Fe5 ?, Co 58, Cow, Zn65 , Mo??, Cs3 Cs137, Ce1'1 , and Ce 144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 4: A composite sample is one in which the quantity of liquid sampled is proportional lo the quantity of liquid waste discharged and for which the method of sampling employed -results in a specimen that is representative of the liquids released.

NOTE 5: A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquid effluents, composite sampling shall employ appropriate methods which will result in a specimen representative of the effluent release.

/

- I DOMINION VPAP-2103S REVISION 6 PAGE 47 OF 71

,I ATTACHMENT 4 (Page 1 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program

- Gaseous Release -Sampling Fre- -- Minimum Analysis -Type of-Activity- --Lower-Limit-of---- , 7.. 1 Type quency Frequency Analysis Detection (LLD)

([Ci/ml), (Note 1)

A. Waste Gas Prior to Release Prior to Release Principal Gamma Storage Tank (Grab Sample) (Each Tank) Emitters (Note 2) 1 X 10 Prior to Release Prior to Release Principle Gamma 1 x 104 B. Containment Emitters (Note 2)

Purge (Each PURGE) (Each PURGE) H3 1 x 1-6 (GrabSample)________ l C. Ventilation Weekly Weekly Principle Gamma 1 104 (I)Process Vent (Grab Sample) Emitters (Note 2)

.(2)Vent Vent4Al.fb-  ?. ..

(3)Vent Vent #2e (Note 3) (Note 3) H3 1x 10.6  :'-I, (4)SRF Vent . _  :

Continuous Weekly (Note 5) 1131 1 x 10.12 (Note 4) (Charcoal Sample) 1133 1 x 10-I Continuous Weekly (Note 5) Principal Gamma x lo-,,

All Release (Note 4) Particulate Sample Emitter (Note 2) L.

/ Continuous - Weekly Types as listed CotenuusComposite Gross Alpha 1 x 10-,1 Particulate Sample Li in A, B, and C Continuous Quarterly 8 CotenuusComposite Sr 9 and Sr 90 1 x 10-(Note 4) Particulate Continuous Noble Gases Gross 1 x 10-6 (Note 4) Beta and Gamma WeelyWeely Principle Gamma IX104 Condenser Air Weekly Weekly Emitters (Note 2)

Ejector Grab Sample (Note 3) H3 1 x 10-6 (N ote 3) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

L-

DOMINION' VPAP-2103S REVISION 6 PAGE 48 OF 71 ATTACHMENT 4 (Page 2 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Analysis Tlype of Activity Lower Limit of Type Frequency Frequency Analysis Detection (LLD)

(p.Ci/ml), (Note 1)

Prior to Release Prior to Release Principle Gamma 1 x 104 Emitters (Grab Sample) (Each Release) H3 I x 10-Continuous Charcoal Sample 131 1 x o-(Note 4) (Note 6) V133 1x Contlinment HogDeContinuous Particulate Sample Principal Gamma 1 10 (Note 4) (Note 6). Emitter (Note 2) I:

surization.. Composite Particu-Continuous late Sample Gross Alpha 1 x 10-(Note 4)(Note 6)

Composite Particu-Continuous late Sample Sr 89 and Sr 90 1 x lo'(

(Note 4) (Note 6)

DOMINION VPAP-2103S REVISION 6 PAGE 49 OF 71 ATTACHMENT 4 (Page 3 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program NOTE 1: For a particular measurement system (which may include radiochemical separation):

4.66 s LLD= (b E

• V

• 2.22E+06

• Y

• e((10-1)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above L (as microcuries per unit mass or volume) (See 4.8).

Sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute, cpm). [

E - the c6unting efficiency (as counts per disintegration).

V _ the saniple size (in units of mass or volume). L 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie. L Y = the fractional radiochemical yield (when applicable).

x = the radioactive decay constant for the particular radionuclide. L At = the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

DOMINION VPAP-2103S REVISION 6 PAGE 50 OF 71 ATTACHMENT 4 (Page 4 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: K87, jr88 Xe133 , Xel3 3 m Xe13 5 , Xe 3 ,mand Xe138 forgaseous 13 7 1 emissions and Mn 54 , Fe5 9 , Col 8 , Co60, Zn65 , Mo99 , Cs 134 , Cs , Ce and Ce 44 for 141 particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other nuclides with half lives greater than 8 days, that are measurable and identifiable at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 3: Sampling and analysis shall also be performed following shutdown, start-up, and whenever a thermal power change exceeding 15 percent of the rated thermal power occurs within any one-hour period, when:

a. Analysis shows that the dose equivalent j131 concentration in the primary coolant has increased more than a factor of 3; and

b. The noble gas activity m6nitor shows that effluent activity has increased by more than a factor of 3.

NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose ordose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4. I NOTE 5 Y Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven days following each shutdown, start-up, or thermal power change exceeding 15 percent of rated thermal power in one hour, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:

a. Analysis shows that the dose equivalent 1l31 concentration in the primary coolant has l bincreased by a factor of 3; and

b. Noble gas monitor shows that effluent activity has increased more than a factor (if 3.

NOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseous 1 effluents, composite sampling shall employ appropriate methods that will result in a specimen representative of the effluent release.

1

DOMINION VPAP-2103S REVISION 6 PAGE 51 OF 71 ATTACHMENT 5 (Page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION l1 CHANNELS

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1-GW-RM-102 1 1 1-GW-RM-130-1 (b) Iodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM-130-1 1 2 (c) Particulate Sampler Li Process Vent Continuous HP Sampler, or 1 2 I-GW-RM-130-1 . .

.ri (d) Process Vent Flow Rate Monitor ;

Li 1-GW-FT-100 . 1 3 (e) Sampler Flow Rate Measuring Device.

KAMAN Flow Rate Measuring Device (Parameter #19), or HP Sampler Rotometer 1 3 Li

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1-SV-RM-111 2-SV-RM-21 1 2 (one per unit) 1 L2 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-lA

. l1-VP-HI-LB Unit 2: 2-VP-FI-1A 2 (one per unit) 3 2-VP-FI-lB

3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 1 1 SPS: Vent #1, 1-VG-RM-104 1 1 Vent #2, 1-VG-RM -110, or 1 1 I, 1-VG-RM-131-1 L

U

DOMINION VPAP*-2103S REVISION 6 PAGE 52 OF 71 ATTACHMENT 5 (Page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS (b) Iodine Sampler SRF: RRM-101 1 2 SPS: Vent #1, 1-VG-RM-104 1 2 Vent #2, Continuous HP Sampler, or 1 2 1-VG-RM-131-1 (c) Particulate Sampler SRF: RRM-101 1 2 SPS: Vent #1, VG-RM-104 1 2 Vent #2, HP Continuous Sampler, or 1 2 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: o1-RHV-FT-156 1 3 SPS: Vent#1, 1-VS-FTr-i9 .*. 1 3 Vent #2, 1-VS-FIT-i16 1 3 (e) Sampler Flow Rate Measuning'Device.

SRF: RRM-101 1 3 SPS: Vent #1, 1-VG-RM-104 1 3 Vent #2, KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer NOTE: Vent #I1, 1-VG-RM-104, HPc*ontinuous samplerpump automatically maintains isokinetic sample flow when changes in stack flow are detected. Isokinetic sample flow adjustment can take 15 - 20 minutes.

[Commitment 3.2.3]

NOTE: The mark numbers listed above in l(b), 1(c), 3(b), 3(c), and 3(e) refer to the gaseous effluent radiation monitor with which the iodine and particulate samplers and the flow rate measuring devices are:

associated. The listed mark numbers do not refer to the particulate radiation monitor.

ACTION 1: If the number of operable channels is less than required, effluent releases via this path may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 2: If the number of operable channels is less than required, effluent releases via the effected path may continue provided samples are continuously collected within one hour with auxiliary sampling equipment as required in Radioactive Gaseous Waste Sampling and Analysis Program (Attachment 4).

ACTION 3: If the number of operable channels is less than required, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

DOMINION VPAP-2103S REVISION 6 PAGE 53 OF 71 ATTACHMENT 6 (Page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release 1-GW-RM-102 1-GW-RM-130-1 D M,

• R Q I (b) Iodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM- 130-1 W N/A N/A N/A (c) Particulate Sampler Process Vent Continuous HP L Sampler, or 1-GW-RM- 130-1 W N/A N/A N/A (d) Process Vent Flow Rate Monitor 1-GW-FI-100 (e) Sampler Flow Rate Measuring D N/A R N/A L

Device HP Sampler Rotometer, or D N/A SA N/A KAMAN Flow Rate Measuring Device (Parameter #19)

D N/A R N/A L

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor Unit 1: I -SV-RM- 11M Unit 2: 2-SV-RM-211 D M R Q (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-lA L

1-VP-FI- lB Unit 2: 2-VP-FI-lA D N/A R N/A 2-VP-FI-lB i I

3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 SPS: I-VG-RM -110 I-VG-RM -131-1 D M R Q I-VG-RM-104 L-

DOMINION VPAP-.2103S REVISION 6 PAGE 54 OF 71 ATTACHMENT 6

• (Page2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL

_ __ _ __ _ _ __ _ __ __ _ _T _ _ E ST (b) Iodine Sampler SRF: RRM-101 SPS: Vent #1, 1-VG-RM-104 Vent #2, Continuous HP W N/A N/A N/A Sampler or 1-VG-RM-131-1 (c) Particulate Sampler SRF: RRM-101 SPS: Vent #1, 1-VG-RM-104 Vent #2, Continuous BP W N/A N/A N/A Sampler or 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF:01-RHV-FT-156 SPS:Vent #1,I-VS-FT-11. D N/A R N/A Vent #2,1I-VS-FIr-i16 (e) Sampler Flow Rate Measuring Device SRF: RRM-101 D N/A R N/A SPS: Vent #1, 1-VG-RM-104 D N/A R N/A Vent #2, KAMAN Flow Rate D N/A R N/A Measuring Device (Parameter

1. 19), or HP Sampler Rotometer D N/A N/A S/A

• Prior to each Waste Gas Decay Tank release NOTE: The mark numbers listed above in 1(b), 1(c), 3(b), 3(c), and 3(e) refer to the gaseous effluent radiation monitor with which the iodine and particulate samplers and the flow rate measuring devices are associated. The listed mark numbers do not refer to the particulate radiation monitor.

DOMINION VPAP-2103S REVISION 6 PAGE 55 OF 71 ATTACHMENT 7 (Page I of 3)

L Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location Frequency Analysis

1. DIRECT RADIATION About 40 Routine Monitor-ing Stations to be placed as follows:

1) Inner Ring in general area of site boundary GAMMA DOSE with station in each sector

2) Outer Ring 6 to 8 km from the site with a Quarterly Quarterly I ,

station in each sector' L.J

3) The balance of the 8 dosimeters should be . 1-L placed in special interest areas such as population centers, nearby L residents, schools, and in 2 or 3 areas to serve as

2. AIRBORNE controls L

Samples from 7 locations:

a) 1 sample from close to the site boundary L

location of the highest Radioiodine Canister calculated annual 1131 Analysis Weekly ~I average ground level Continuous Radioiodines and D/Q Sampler IJ Particulates b) 5 sample locations 6-8 operation with articulate Sampler km distance located in a sample collection Gross beta radioactivity concentric ring around weekly analysis following filter the Station change; c) 1 sample from a control location loato 15-30 153 kmkm , Gamma isotopic of composite (by analysis hi1 distant, providing valid ocatiquarterly background data Li

DOMINION

• VPAP-2103S REVISION 6 PAGE 5(6 OF 71 ATTACHMENT 7 (Page 2 of 3)

Radiological Environmental Monitoring Program Expo:;ure Pathway Number of Sample and Collection Type and Frequency of andlor Sample Sample Location Frequency Analysis

3. WATERBORNE Gamma isotopic analysis a) Surface a) 1 sample upstream Monthly Sample monthly; b) 1 sample downstream Composite for tritium analysis J b) aground

___quarterly ____ ____

Sample from 1 or 2 sources Quarterly am isotopic and trilium analisoquanterly analysis quarterlyI c) sediment from a) 1 sample upstrSemi-Annually Gamma isotopic analysis semi-shoreline b) 1 sample downstream annually d) sit 1 sample upstream Semi-Annually Gamma isotopic analysis semi-d) Silt b) 1 sample downstream S annually

4. INGESTION a) Mkilk a) 2 samples from milking animals in the vicinity of the Station. NOTE I1311 Gamma isotopic and anal-b) 1 sample from milking Monthly animals at a control ysis monthly location (-15-30 km distant). NOTE 2l a) 2 samples of oysters in the Semi-Annually Gamma isotopic on edibles vicinity of the Station b) 4 samples of clams in the Semi-Annually Gamma isotopic on edibles b) Fish and vicinity of the Station Invertebrates c) 1 sampling of crabs from the vicinity of the Station Annually Gamma isotopic on edibles d) 1 sampling of 2 different species from the discharge Semi-Annually Gamma isotopic on edibles canal (catfish, white perch, eel) l NOTE I: If milk sampling cannot be performed, use item 4.c)d). Milk sampling cannot be performed when there are no milk sampling locations in the vicinity of the Station.

l NOTE 2: If milk sampling from a control location cannot be performed, use item 4.c)e). Milk sampling cannot be performed when there is no milk sampling location 30 km distant.

DOMINION VPAP-2103S REVISION 6 PAGE 57 OF 71 ATTACHMENT 7 (Page 3 of 3)

Radiological Environmental Monitoring Program I

Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location Frequency Analysis

4. INGESTION (Continued) a) 1 sample corn Gamma isotopic on edible b) 1 sample soybeans Annually ion c) sample peanuts d) 1 sample of a broadleaf vegetation grown nearest in each of two i different available offsite locations c) Food Products (sectors) with the highest annual average ground level D/Qs, if. Monthly, if Gamma isotopic and I131 L

milk sampling is not performed.

available, or at harvest analysis L e) 1 sample of a broadleaf vegetation grown 15 -

30 km distant in tje L available least prevalent wind direction, if milk sampling is not L

performed.

L7 I1 IS

N DOMINION VPAP--2103S REVISION 6 PAGE 58 OF 71 ATTACHMENT 8 (Page 1 of 3)

Environmental Sampling Locations SAMPLE LOCATION DISTANCE DIRECTION REMAR"S MEDIA (MILES)

Air Charcoal and Surry Station (SS) 0.3 NNE Particulate Hog Island Reserve (HIR) 2.0 NNE Bacons Castle (BC) 4.5 SSW Alliance (ALL) 5.1 WSW Colonial Parkway (CP) 3.8 NNW BASF (BASF) 5.1 ENE Fort Eustis (FE) 4.9 ESE Newport News (NN) 19.3 SE Control Location Environmental Control (00) Onsite ** .

TLDs West North West (02) 0.2 WNW Site Boundary Surry Station Discharge 0.4 NW Site Boundary (03);

North North West (04) 0.2 NNW Site Boundary L North (05) 0.3 N Site Boundary North North East (06) 0.3 NNE Site Boundary L North East East North East (07)

(08) 0.3 0.4 NE ENE Site Boundary Site Boundary 1i East (09) 0.3 E Exclusion Area Bouadary and Site Boundary West (10) 0.1 W Site Boundary West South West (11) 0.4 WSW Site Boundary South West (12) 0.3 SW Site Boundary L South South West South (13)

(14) 0.3 0.4 SSW S

Site Boundary Site Boundary South South East (15) 0.6 SSE Site Boundary L South East (16) 0.9 SE Site Boundary Station Intake (18) 1.6 ESE Site Boundary Hog Island Reserve (19) 2.0 NNE Near Resident L

DOMINION VPAP-2103S REVISION 6 PAGE 59 OF 71 ATTACHMENT 8 (Page 2 of 3)

Environmental Sampling Locations SAMPLE LOCATION DISTANCE DIRECTION REMARKS MEDIA (MILES) _

Environmental Bacon's Castle (20) 4.5 SSW Approx. 5 miles TLDs Route 633 (21) 4.9 SW Approx. 5 miles Alliance (22) 5.1 WSW Approx. 5 miles Surry (23) 7.7 WSW Population Center Route 636 and 637 (24) 4.0 W Approx. 5 miles Scotland Wharf (25) 5.0 WNW Approx. 5 miles Jamestown (26) 6.3 NW Approx. 5 miles Colonial Parkway (27) 3.8 NNW Approx. 5 miles

- Route 617 and618 (28) 4.9. . NNW Approx. S miles  ;

Kingsmill (29) 4.6 N Approx. 5 miles i

. Williamsburg (30) 7.8 N Population Center Kingsmill North (31) 5.5 NNE Approx. 5 miles l Budweiser (32) 5.8 NNE Population Center j u Water Plant (33) 5.0 NE Approx. 5 miles I BASF (34) 5.1 ENE Approx. 5 miles Lee Hall (35) 7.1 ENE Population Center Goose Island (36) 5.1 E Approx. 5 miles i [

Fort Eustis (37) 4.9 ESE Approx. 5 miles 1 Newport News (38) 19.3 SE Population Center 1 James River Bridge (39) 17.1 SE Control I U Benn's Church (40) 17.0 SSE Control 1 Smithfield (41) 13.4 SSE Control I Rushmere (42) 5.3 SSE Approx. 5 miles Route 628 (43) 5.1 S Approx. 5 miles Milk Epp's 4.8 SSW Colonial Parkway 3.7 NNW Williams 27.5 S Control Location

DOMINION VPAP-2103S REVISION 6 PAGE 60 OF 71 ATTACHMENT 8 (Page 3 of 3)

Environmental Sampling Locations SAMPLE LOCATION DISTANCE DIRECTION REMARKS M\EIDIA (MILES)

Well W'ater Surry Station Onsite***

Hog Island Reserve 2.0 NNE Crops (Corn, Slade's Farm 3.2 S I Peanuts, Soybeans) Brock's Farm 3.8 S River Water Surry Discharge 0.4 NW I (Monthly) Scotland Wharf 4.9 WNW Control Location I Sediment Chickahominy River 11.2 WNW Control Location (Silt) Surry Station Discharge 1.3 NNW Clams Chickahominy River- 11.2 WNW Control Location 1.3 NNW L . Surry Station Discharge Hog Island Point 2.4 NE Lawne's Creek 2.4 SE L Oysters Point of Shoals 6.4 4.9 SSE ESE Mulberry Point L Crabs Fish -

Surry Station Discharge Surry Station Discharge 1.3 1.3 NNW NNW 0.6 N Shoreline Sediment .

Hog Island Reserve I

Chickahominy River 11.2 WNW Control Location

• • Onsite Location - in Lead Shield L Onsite sample of Well Water-taken from tap-water at Surry Environmental Building L

L.

L L

DOMINION VPAP-2103S REVISION 6 PAGE 61 OF 71 ATTACHMENT 9 (Page 1 of 2) aI Detection Capabilities for Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD)

Analysis Water Airborne Fish Milk Food Sediment (NOTE 2) (pCi/I) Particulate (pCi/kg) (pCi/I) Products (pCi/kg) or Gases (wet) (pCi/kg) (dry)

(pCi/m3 ) (wet)

Gross beta 4 0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95: 30

.. I Nb-95 15 I-131 (NOQT3) 1 0.07- 1 60 L Cs-134 15 0.05 130 15 60 150 Cs-137 Ba-140 18 60 0.06 150 18 60 80 180 L

La-140 15 15 NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental L

measurements are given in Regulatory Guide 4.13. L[ I NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Otherpeaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

NOTE 3: LLD for the ground (drinking) water samples. The LLD for the surface (non-drinking) "I water samples is 10 pCi/l.

L DOMINION VPAI'-2103S REVISION 6 PAGE 62 OF 71 ATTACHMENT 9 L (Page 2 of 2)

Detection Capabilities for Environmental Sample Analysis L LOWER LIMIT OF DETECTION (LLD)

NOTE 1: For a particular measurement system (which may include radiochemical separation,):

4.66 sb LLD= E*

• 46 Sb(24-1) lE *V *2.22E+06 *Y *e-(0-) (4-1 Where:

LLD - the "a priori" (before the fact) LowerLimit of Detection as defined above L -(as microcuries per unit mass or volume) (See 4.8)

Sb = the standard.de'viation of the background counting rate or of the counting L rate of a blank sample as appropriate. (as counts per minute, cpm)

L E = the counting efficiency (as counts per disintegration)

V = the sample size (in units of mass or volume)

L 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie L Y = the fractional radiochemical yield (when applicable)

X = the radioactive decay constant for the particular radionuclide At = the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not L plant effluent samples)

.Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a L measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

L L

DOMINION VPAP-2103S REVISION 6 PAGE 63 OF 71 ATTACHMENT 10 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples Analysis Water Airborne Fish Milk Food Products (pCi/kg, wet) I (pCi/l) Particulate or (pCi/kg, wet) (pCi/i)

Gases (pCi/M3 )

H-3 30,000 h-A Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 (NOTE 1) 2 0.9. 7,..: .: 3 100 Cs-134 30 10 - 1,000 60 1,000 Cs-137 50 20 . 2,000 70 2,000 [1 L

Ba-La-140 200 300 NOTE 1: Reporting level for the ground (drinking) water samples required by Radiological L Environmental Monitoring Program (Attachment 7). The reporting level for the surface (non-drinking) water samples required by Attachment 7 is 20 pCi/A.  !

L i

DOMINION VPAP-2103S REVISION 6 PAGE 64 OF 71 ATTACHMENT 11 (Page 1 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis 1.0 M1ETEORLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the five (5) year average XVQ and D/Q values at critical locations around the Station for ventilation vent (ground level) and process vent (mixed mode) releases. The five year average XIQ and D/Q values are used in the dose pathway analysis to determine both the maximum exposed individual at site boundary and member of the public.

1.2 Meteorological Data, Parameters, and Methodology A five (5) year average of representative onsite meteorological data for the period January 1, 1.992 through December 31, 1996, is used in the gaseous effluent dose pathway calculations.

This data includes wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (i.e.,

ventilation vent), and those characterized as mixWd mode (i.e., process vent). The portions of release characterized as ground level were based on AT158.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on AT158.9ft-28.2ft and 158.9 ft wind data.

X/Qs and D/Qs were calculated using the PC version of NRC computer code "XOQDOQ -

Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", Version 2.0, provided in NUREG-0324. The code is based upon a straight lint airflow model implementing the assumptions outlined in Section C (excluding Cla and Clb) of Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."

The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide 1.111. The site region is characterized as flat terrain such that open terrain correction factors are considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area. The effective release height used in mixed mode release calculation, was based on a process vent release height of 131 ft. and plume rise due to momentum for a vent diameter of 3 in. with plume exit velocity of 100 ft/sec.

DOMINION VPAP-2103S _

REVISION 6 PAGE 65 OF 71 ATTACHMENT 11 (Page 2 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis Ventilation vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1.111 for release points less than the height of adjacent solid structures. Terrain elevations were obtained from Surry Power Station Units 1 and 2 Virginia Electric and Power Company Updated Final Safety Analysis Report Table 11A-8.

X/Q and D/Q values were calculated for the nearest site boundary, residence, milk-cow, discharge bank, and vegetable garden by sector for process vent and ventilation vent releases.

According to the definition for short term in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations," October, 1978, some gaseous releases may fit this category, primarily waste gas decay tank releases and containment purges.

However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release reports.

Therefore, the use of annual average ..

concentrations o.,n is:;.-appropriate p.codn.. rit according toNUREG-0133.

NRG-1 E

1.3 Results .

The X/Q value that would result in the maximum total body; skin, and inhalation exposure for ventilation vent releases was 6.OE-05 sec/m 3 at a site boundary location 532 meters NNE sector. For process vent releases, the site boundary XIQ value was 3.7E-07 sec/m 3 at a L location 565 meters WSW sector. The discharge canal bank X/Q value that would result in the maximum inhalation exposure for ventilation vent releases was 1.6E-04 sec/m 3 at a. L location 290 meters NW sector. The discharge canal $'ank XIQ value for process vent was 6.9E-07 sec/m 3 at a location 290 meters NW sector.

L

DOMINION VPAP-2103S REVISION 6 PAGE 66 OF 71 ATTACHMENT 11 (Page 3 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis The grass-cow-milk pathway analysis, which is performed to derive the maximum exposure from 1131,1133, and from all radionuclides in particulate form with half-lives greater than eight days, is based on the dairy location indicated by the 1996 Land Use Census. The D/Q value from ventilation vent releases that would result in the maximum exposure was 2.5E-10 per m2 at a location 5873 meters NNW sector. For process vent releases, the D/Q value was 1.4E-10 per m2 at a location 7788 meters SSW sector. For tritium, the X/Q value from ventilation vent ieleases that would result in the maximum exposure for the grass-cow-milk pathway was 1.5E-06 sec/m 3 at a locations 5873 meters NNW sector, and 7.OE-08 sec/m3 for process vent releases at a location 7788meters SSW sector. The inhalation pathway is the only other pathway existing at this location. Therefore, the XIQ values given for tritium also apply for the inhalation pathway.

2.0 LIQUID PATHWAY ANALYSIS.

2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum exposed member of the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysis included a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required for Subsection 6.2, Liquid Radioactive Waste Effluents. /

2.2 Data, Parameters, and Methodology Radioactive liquid effluent release data for the years 1976, 1977, 1978, 1979, 1980, and 1981 were compiled from the Surry Power Station effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.

DOMINION VPAP-2103S ,

REVISION 6 PAGE 67 OF 71 ATTACHMENT 11 (Page 4 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis Liquid radioactive effluents from both units are released to the James River via the discharge canal. Possible pathways of exposure for release from the Station include ingestion of fish and invertebrates and shoreline activities. The irrigated food pathway and potable water pathway do not exist at this location. Access to the discharge canal by the general public is gained two ways: bank fishing, controlled by the Station and limited to Dominion employees or guests of employees, and by boat as far upstream as the inshore end of the discharge canal groin. It has been estimated that boat sport fishing would be performed a maximum of 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year, and that bank fishing would be performed a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year.

For an individual fishing in the discharge canal, no river dilution was assumed for the fish pathway. For an individual located beyond the discharge canal groins, a river dilution factor of 5 (i.e. a mixing ratio of 0.2) was assumed as appropriate according to Regulatory Guide 1.109, Rev. 1, and the fish, invertebrate, and shoreline pathways were considered to exist. Dose L factors, bioaccumulation factors, shore width factors and usage terms for shoreline activities and ingestion of fish and invertebrates are included in the Canberra-Source Code file. Dose to an individual fishing on the discharge bank was determined by multiplying the annual dose calculated with LADTAP by the fractional year the individual spent fishing in the canal. L 2.3 Results Fortheyears 1976,1977,1979,1980,and 1981,theinvertebratepathwayresultedinthelargest dose. In 1978 the fish pathway resulted in the largest dose. The maximum exposed member of the public was determined to utilize the James River. The critical age group was the adult and L the critical organ was either the thyroid or GI-LLI. The ingestion dose factors, which include the fish and invertebrate pathways, are calculated for total body and various critical organs.

Validation of the limiting age group and critical organ is performed by Canberra's liquid effluent dose calculation program using the data, parameters, and methodology provided in the Canberra Source Code file.

DOMINION VPAP-2103S REVISION 6 PAGE 68 OF 71 ATTACHMENT 11 (Page 5 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis 3.0 GASEOUS PATHWAY ANALYSIS 3.1 'Purpose Gaseous effluent pathway analyses are performed to determine the location that would result in the maximum doses due to noble gases, for use in demonstrating compliance with 6.3.1.a.

Lo and 6.3.3.a. The analyses includes a determination of the location, pathway, and critical organ, of the maximum exposed member of the public, as a result of the release of 1131, 1133, tritium, L; and for all radionuclides in particulate form with half-lives greater than eight days for use in demonstrating compliance with 6.3.4.a. In addition, the analyses includes a determination of the critical organ, maximum age group, and sector location of an exposed individual th:rough the inhalation pathway from 1131, 1133, tritium, and particulates to demonstrate compliance I with 6.3.l.a.

3.2' I)at, Parameters, and Methodology  :  :

L Five year average XIQ values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each directional sector and at other critical locations accessible to.

L the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/m 3 at site boundary for ventilation vent releases at a location 532 meters NNE direction, and 3.7E-07 sec/m3 at site boundary for process vent releases at a location 565 meters VSW direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose.

6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and

%XQ values determined for maximum noble gas doses can be used to determine the maximum dose from 1131, 1133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.

DOMINION VPAP-2103S REVISION 6 PAGE 69 OF 71 ATTACHMENT 11 (Page 6 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis The maximum exposed individual for 10CFR50 Appendix I compliance could be at any of the following locations: site boundary, nearest resident, nearest milk-cow, or nearest vegetable garden, using the 1996 Land Use Census data. Therefore, ventilation vent and process vent X/Q and D/Q values for these selected receptors are included in the gaseous effluent dose pathway analyses. Ground plane, inhalation, cow-milk, and vegetable garden pathways are active with the exception of the infant age group, which is not active for the vegetable garden pathway. Otherwise, all age groups are evaluated at these locations. The data, parameters, and methodology of R. G. 1.109, Rev. 1, and NUREG-0133 are used in the gaseous effluent dose pathway analyses.

The gamma and beta dose factors Kivv, Livv, Mivv and Nivv for ground level releases and the gamma and beta dose factors Kipv Lipv, Mipv, and Nipv for mixed mode releases are included in the Canberra Source Code file.

Inhalation pathway dose factors P' and Pipv are calculated using the following equation:

Pi mrem/yr per Ci/m3 = K' (BR) DFAi (28-1) where:

K' = a constant of unit conversion, 1E+12 pCi/Ci BR = the breathing rate of the particular age group, m3 /yr, from Table E-5, Regulatory Guide L 1.109, Rev.I DFAi=the critical organ inhalation dose factor for particular age group for the ith radionuclide, L in mremlpCi Parameters used above were obtained from NUREG-0133, R.G. 1.109, Rev. 1, and LADTAP II, NUREG/CR-1276 It was determined that the member of the public within site boundary would be using the discharge canal bank for fishing a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year. The maximum five year average XIQ at this location was determined to be 1.6E-04 sec/m 3 at 290 meters NW direction.

Active pathways are ground plane and inhalation, and all age groups are evaluated for this pathway analysis.

Li

DOMINION VPAP--2103S REVISION 6 PAGE 70 OF 71 ATTACHMENT 11 (Page 7 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis The RMivv and RMipv dose factors, except for tritium, are calculated using the following tequation:

f fFI(Ufap) Cithi-~t

=K pSe RM ixw Fm (r)(DFLi)[ s+1

+

Y J itf (28-2) where:

K' = a constant of unit conversion, 1E+12 pCi/Ci OF = cow's consumption rate, 50, in Kg/day (wet weight)

Uap= infant milk consumption rate, 330, liters/yr agricultural

='p- productivity by unit area of pasture feed grass, 0.7 Kg/m 2  ;

I= agricultural productivity by unit area of stored feed, 2.0, in Kg/m 2 Fm = stable element transfer coefficients r = fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and. 0.2 for particulates DFLi=critical organ ingestion dose factor for the ith radionuclide for the particular age group, in mrem/pCi

= decay constant for the ith radionuclide, in sec-I A, = decay constant for removal of activity of leaf and plant surfaces by weathering, 5.73E-07 sec-1 (corresponding to a 14 day half-life) tf = transport time from pasture to cow, to milk, to receptor, 1.73+05, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+06, in seconds fp = fraction of year that cow is on pasture, 0.67 (dimensionless), 7.78E+06 in seconds fs = fraction of cow feed that is pasture grass while cow is on pasture, 1.0, dimensionless Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev. l, and LADTAP II, NUREG/CR-1276.

DOMINION VPAP-2103S REVISION 6 PAGE 71 OF 71 ATTACHMENT 11 (Page 8 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis Since the concentration of tritium in milk is based on the airborne concentration rather than the L deposition, the following equation is used:

R = K K FmQFUap(DFLH 3 ) [0.75(0.5/H)] (28-3) where:

K"'=a constant of unit conversion IE+03 gm/kg H = absolute humidity of the atmosphere, 8.0, gm/m3 0.75=the fraction of total feed that is water 0.5 = the ratio of the specific activity of the feed grass to the atmospheric water Other parameters have been previously-defined. - a.i L The inhalation pathway dose factors RIivv and Rispv were calculated using the following . .

equation: .

RI; mrem/yr per Ci/m 3 = K' (BR) DFAi (28-4) L where:

K'=a constant of unit conversion, IE+12 pCi/Ci / L BR=breathing rate of the particular age group, m3 /yr L DFAi=critical organ inhalation dose factor for particular age group for the ith radionuclide, in mrem/pCi l Parameters used above were obtained from NUREG-0133, R. G. 1.109, Rev. 1 and LI LAPTAP II, NUREG/CR-1276.

Attachment 5 Page 1 of 1 INOPERABILITY OF RADIOACTIVE LIOUID 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 Ihan 30 days during this reporting period.

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 l.OOE-04 1.95E 3.19E-06 Kr-88 l.OOE-04 2.06E 3.97E-06 Xe-133 l.OOE-04 1.04E 3.35E-06 Xe-133m L.OOE-04 3.49E 9.86E-06 Xe-135 l.OOE-04 5.17E 1.12E-06 Xe-135m l.OOE-04 2.02E 6.76E-06 Xe-138 l.OOE-04 6.78E 9.62E-06 1-131 1.OOE-12 5.06E 9.90E-14 1-133 l .OOE-10 1.25E-12 2.05E-12 Sr-89 l.OOE-l 1 2.OOE 5.20E-12 Sr-90 l.OOE-l 1 3.OOE 9.40E-13 Cs-134 l.OOE-l 1 3.99E 5.24E-13 Cs-137 l.OOE-1 1 4.68E 7.75E-13 Mn-54 l.OOE- 11 4.78E 5.35E-13 Fe-59 l.OOE-l 1 6.48E 1.16E-12 Co-58 l.OOE- Il 3.91E 5.09E-13 Co-60 l .OOE- 11 6.44E 6.42E-13 Zn-65 l.OOE- 11 9.70E 8.56E-13 Mo-99 l .OOE-l 1 4.21E 3.88E-12 Ce-141 l.OOE- Il 4.OOE 6.40E-13 Ce-144 l.OOE- 11 1.63E 2.20E-12 Alpha l.OOE-1 1 1.66E 1.66E-14 Tritium l.OOE-06 5.45E 5.72E-08 LIQUIp Sr-89 5.OOE-08 3.30E 4.40E-08 Sr-90 5.OOE-08 3.1OE 4.50E-08 Cs-134 5.OOE-07 7.03E 1.75E-08 Cs-137 5.OOE-07 8.32E 2.20E-08 1-131 1.OOE-06 5.91E 1.95E-08 Co-58 5.OOE-07 6.1 1E 1.58E-08 Co-60 5.OOE-07 7.79E 3.23E-08 Fe-59 5.OOE-07 1.25E 3.51E-08 Zn-65 5.OOE-07 l.lOE 3.53E-08 Mn-54 5.OOE-07 6.34E 1.55E-08 Mo-99 5.OOE-07 3.94E 2.65E-07 Ce-141 5.OOE-07 1.OOE 2.15E-08 Ce-144 5.OOE-07 3.57E 8.36E-08 Fe-55 1.OOE-06 2.60E 9.1OE-07 Alpha l.OOE-07 2.87E 2.94E-08 Tritium l.OOE-05 1.50E 1.58E-06 Xe-133 1.OOE-05 1.66E 3.88E-08 Xe-135 1.OOE-05 6.35E 1.16E-08 Xe-133m 1.OOE-05 4.92E 9.67E-08 Xe-135m l.OOE-05 2.08E 8.3 1E-07 Xe-138 l.OOE-05 8.07E 1.94E-06 Kr-87 1.OOE-05 2.36E 4.98E-08 Kr-88 l.OOE-05 2.61E 5.03E-08