ML18151A212

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Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998.
ML18151A212
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/31/1998
From: Blount P, Keithley J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18151A214 List:
References
NUDOCS 9905040140
Download: ML18151A212 (316)
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Text

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (January 1, 1998 Through December 31, 1998)

Prepared By: i-ru/ZL-t Staff Health Physicist Supervisor Health Physics Technical Services Approved By: _ _ -~-0-U=--.c__-------"'""--'=--=-

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Superintendent Radiological Protection 9905040140 -990423 PDR ADOC~ 05000280 R PDR

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (January 1, 1998 Through December 31, 1998)

Index Section No. Subject 1 Executive Summary 1 2 Purpose and Scope 2 3 Discussion 3&4 4 Supplemental Information 5 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 lnoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Analysis

  • FORWARD This report is submitted as required by Appendix A to Operating License No.'s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.8.3 .

EXECUTIVE

SUMMARY

ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT The Annual Radiological Effluent Release Report describes the radiological effluent control program conducted at the Surry Power Station during the 1998 calendar year.

This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the Surry Power Station in accordance with R. G. 1.21 and includes an assessment of radiation doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents.

There were no unplanned liquid or gaseous effluent releases classified according to the criteria in the Offsite Dose Calculation Manual during this reporting period.

Based on the 1998 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

1. The total body dose due to liquid effluents was 5.14-04 mrem, which is 8.57-03% of the 6 mrem dose limit. The critical organ doses due to liquid effluents, GI-LU and Thyroid respectively, were 1.77-03 mrem and 2.09E-04 mrem. These doses are 8.85E-03% and 1.05E-03% of the respective 20
  • mrem dose limit.
2. The air dose due to noble gases in gaseous effluents was 8.98-02 mrad gamma, which is 4.49-01 % of the 20 mrad gamma dose limit, and 2.64-01 mrad beta, which is 6.60E-01 % of the 40 mrad beta dose limit.
3. The critical organ dose from gaseous effluents due to 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days is 2.54E-02 mrem, which is 8.1 ?E-02% of the 30 mrem dose limit.

There were no major changes to the radioactive gaseous and solid waste treatment systems during this reporting period. Changes were made to the liquid radwaste treatment system at the Surry Radwaste Facility. The changes are discussed in Attachment 4.

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

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

1

  • Purpose and Scope The Radioactive Effluent Release Report, Attachment 1, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly or annual basis following the format of Tables 1, 2 and 3 of Appendix B thereof. Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. Additionally, a list of unplanned releases during the reporting period is included in Attachment 6.

As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.

Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 10CFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report.

2

Discussion

  • The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1 is the ODCM section, 6.3.1, which requires that the dose rate for iodine - 131, iodine - 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mRem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid, inhalation pathway.
  • The basis for the calculation of the percent of technical specification for the total body and skin in Table 1A of Attachment 1, is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mRem/yr to the total body and less than or equal to 3000 mRem/yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is the ODCM, section 6.2.1, which states that the concentration of radioactive material releases in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/ml.

Percent of technical specification. calculations are based on the total gaseous or liquid

  • effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being either the thyroid gland or gastrointestinal-lower large intestine. The total body dose was also determined for this individual.

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

  • 3

The typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis

  • instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower level of detection, then the totals for this period will be designated as Not Applicable (N/A) .

4

Supplemental Information

  • Section 6.6.1.b.4 of the ODCM requires the identification of the cause(s) for the unavailability of milk samples and the identification for obtaining replacement samples.

During this reporting period, one indicator milk sample location, Judkins Dairy, was deleted from the sampling program. This deletion resulted from the dairy going out of business. No replacement sample location was identified for this dairy within 5 km of Surrry Power Station. Additionally, a change was made to the control milk sample location. The control sample location, Williams Dairy, was replaced with Pivarnic Dairy as Williams Dairy went out of business also.

As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program. Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the radiological environmental monitoring program .

5

  • EFFLUENT RELEASE DATA Attachment 1 (January 1, 1998 Through December 31, 1998)

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 .

l Attachment 1 TABLE lA Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 12/31/98 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 l.22E+02 6.07E+Ol l.80E+Ol
2. A VE RELEASE RA TE FOR PERIOD µCi/sec l.57E+Ol 7.7IE+OO B. IODINE
1. TOTAL I-131 Ci 4.68E-04 3.38E-04 2.80E+Ol
2. A VE RELEASE RA TE FOR PERIOD µCi/sec 6.02E-05 4.30E-05 C. PARTICULATE
1. HALF-LIFE >8 DAYS Ci 9.98E-07 7.74E-07 2.80E+Ol
2. AVE RELEASE RA TE FOR PERIOD µCi/sec l.28E-07 9.84E-08
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci l.03E+Ol 8.44E+OO 3.IOE+Ol
2. AVE RELEASE RA TE FOR PERIOD µCi/sec l.32E+OO l.07E+OO PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RA TE  % l.OOE-02 7.73E-03 TOTAL BODY DOSE RATE  % 4.18E-02 5.IOE-03 SKIN DOSE RA TE  % l.69E-02 2.0IE-03

Attachment I TABLE IA Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 12/31/98 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH %EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES I. TOTAL RELEASE Ci l.31E+OI 4.19E+OI l.80E+OI

2. A VE RELEASE RA TE FOR PERIOD µCi/sec l.65E+OO 5.27E+OO B. IODINE I. TOTAL 1-131 Ci 3.92E-05 9.72E-04 2.80E+OI
2. A VE RELEASE RA TE FOR PERIOD µCi/sec 4.93E-06 l.22E-04 C. PARTICULATE I. HALF-LIFE >8 DAYS Ci I.OSE-07 2.88E-05 2.80E+OI
2. A VE RELEASE RA TE FOR PERIOD µCi/sec l.32E-08 3.62E-06
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM I. TOTAL RELEASE Ci 8.42E+OO 1.14E+OI 3.IOE+OI

. A VE RELEASE RA TE FOR PERIOD µCi/sec l.06E+OO l.44E+OO PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RA TE  % 5.08E-03 l.45E-02 TOTAL BODY DOSE RATE  % 3.95E-03 9.39E-03 SKIN DOSE RA TE  % l.55E-03 3.72E-03 I~

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12/31/98 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci 9.06E-04 NID 6.58E-01 3.90E-Ol Kr-85m Ci l.59E-04 NID 5.58E-04 5. l lE-04 Kr-87 Ci N/D NID N/D NID Kr-88 Ci l.59E-05 N/D NID NID Xe-133 Ci 8.48E+OO l.15E-01 2.50E+Ol 4.83E+Ol Xe-135 Ci l.92E-02 l.43E-03 5.77E-02 2.59E-02 Xe-135m Ci N/D NID N/D NID Xe-138 . Ci N/D NID N/D NID Xe-131m Ci 6.60E-02 NID 5.28E-01 7.56E-01 Xe-133m Ci l.16E-01 NID l.38E-01 2.81E-01 Ar-41 Ci l.ISE-05 NID NID NID TOTAL FOR PERIOD Ci 8.68E+OO 1.17E-Ol 2.63E+OI 4.98E+Ol
2. IODINES 1-131 Ci N/D 3.39E-07 N/D NID I-133 Ci N/D NID N/D NID 1-135 Ci N/D NID N/D NID TOTAL FOR PERIOD Ci NIA 3.39E-07 NIA NIA
3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci N/D NID N/D NID Cs-137 Ci l.19E-09 2.23E-09 N/D NID Ba-140 Ci NID NID N/D NID La-140 Ci NID N/D NID NID Co-58 Ci NID NID N/D NID Co-60 Ci 4.45E-09 2.64E-09 NID NID Mn-54 Ci NID NID N/D NID Fe-59 Ci N/D NID NID NID Zn-65 Ci N/D NID NID NID Mo-99 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ce-144 Ci NID NID NID NID TOTAL FOR PERIOD Ci 5.64E-09 4.87E-09 NIA NIA

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12/31/98 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D NID 4.29E-Ol 7.50E-01 Kr-85m Ci NID NID NID NID Kr-87 Ci N/D NID NID NID Kr-88 Ci NID NID NID NID Xe-133 Ci 3.14E-02 2.13E+OO 3.80E+OO l.72E+Ol Xe-135 Ci 4.75E-03 2.73E-03 9.81E-04 4.69E-02 Xe-135m Ci NID NID NID NID Xe-138 Ci. NID NID NID NID Xe-131m Ci NID l.77E-02 l.92E-01 7.82E-01 Xe-133m Ci NID 1.81E-02 5.98E-03 7.0lE-02 Ar-41 Ci NID NID NID NID TOTAL FOR PERIOD Ci 3.62E-02 2.17E+OO 4.43E+OO l.89E+Ol
2. IODINES
  • I-131 I-133 I-135 TOTAL FOR PERIOD Ci Ci Ci Ci 5.98E-I0 NID NID NIA 1.48E-07 NID NID 1.48E-07 NID NID NID NIA NID NID NID NIA
3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci NID NID NID NID Cs-137 Ci 2.08E-09 4.04E-09 NID NID Ba-140 Ci NID NID NID NID La-140 Ci NID NID NID NID Co-58 Ci NID 2.33E-09 NID NID Co-60 Ci NID NID NID NID Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID NID NID Zn-65 Ci NID NID NID NID Mo-99 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ce-144 Ci NID NID NID NID
  • TOTALFORPERIOD Ci 2.08E-09 6.37E-09 NIA NIA

Attachment 1 TABLElC Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD:1/1/98 TO 12/31/98 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci NID N/D 8.76E-Ol N/D Kr-85m Ci 2.58E-04 3.15E-04 2.85E-02 NID Kr-87 Ci 9.29E-05 2.31E-04 NID NID Kr-88 Ci NID NID NID NID Xe-133 Ci 6.96E+OO l.45E-02 7.66E+Ol l.07E+Ol Xe-135 Ci 2.44E-03 7.25E-03 l.20E+OO 4.33E-02 Xe-135m Ci 7.65E-04 l.20E-03 NID NID Xe-138 Ci NID NID NID NID Xe-13lm Ci NID NID 8.67E-Ol l.28E-02 Xe-133m Ci NID NID 8.18E-01 6.52E-03 Ar-41 Ci NID 1.32E-03 NID NID TOTAL FOR PERIOD Ci 6.97E+OO 2.48E-02 8.03E+Ol l.07E+Ol
2. IODINES 1-131 Ci 4.04E-04 3.12E-04 6.40E-05 2.59E-05 1-133 Ci 8.95E-05 5.75E-05 l.20E-05 6.0SE-06 1-135 Ci NID NID NID NID TOTAL FOR PERIOD Ci 4.94E-04 3.69E-04 7.60E-05 3.20E-05
3. PARTICULATES Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Cs-134 Ci NID NID NID NID Cs-137 Ci NID NID NID NID Ba-140 Ci NID NID NID NID La-140 Ci NID NID NID NID Co-58 Ci 9.92E-07 7.69E-07 NID NID Co-60 Ci NID NID NID NID Mn-54 Ci NID NID NID NID Fe-59 Ci NID NID NID NID Zn-65 Ci NID NID NID NID Mo-99 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ce-144 Ci NID NID NID NID Rb-88 Ci NID l.03E-03 NID NID Te-132 Ci NID 2.46E-07 NID NID Cs-138 Ci NID 4.39E-04 NID NID TOTAL FOR PERIOD Ci 9.92E-07 1.47E-03 NIA NIA

Attachment 1 TABLElC Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD:1/1/98 TO 12/31/98 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D NID l.33E-03 Kr-85m Ci l.13E-03 l.40E-04 N/D N/D Kr-87 Ci l.29E-03 l.69E-04 NID NID Kr-88 Ci NID NID N/D NID Xe-133 Ci 8.65E+OO 2.02E+Ol N/D 2.99E-Ol Xe-135 Ci 8.52E-03 7.49E-02 N/D NID Xe-135m Ci 3.63E-03 4.29E-04 NID NID Xe-138 Ci l .5 lE-03 2.67E-04 NID NID Xe-13lm Ci NID 2.35E-Ol N/D l.24E-02 Xe-133m Ci NID N/D NID 2.66E-03 Ar-41 Ci 2.72E-03 6.65E-04 N/D NID TOTAL FOR PERIOD Ci 8.67E+OO 2.05E+Ol NIA 3.16E-Ol

.2mrs1-133 Ci Ci Ci 3.92E-05 N/D 3.35E-06 9.71E-04 2.86E-04 5.2IE-05 NID NID NID 6.94E-07 NID NID 1-135 Ci N/D N/D NID NID TOTAL FOR PERIOD Ci 4.25E-05 l.3 IE-03 NIA 6.94E-07

3. PARTICULATES Sr-89 Ci N/D N/D N/D NID Sr-90 Ci N/D N/D NID N/D Cs-134 Ci N/D N/D NID N/D Cs-137 Ci N/D 3.81E-06 NID NID Ba-140 Ci NID NID N/D N/D La-140 Ci NID N/D N/D N/D Co-58 Ci N/D I.30E-05 N/D l.07E-08 Co-60 Ci NID. 9.92E-08 N/D NID Mn-54 Ci N/D NID N/D NID Fe-59 Ci N/D NID N/D NID Zn-65 Ci N/D NID N/D NID Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci NID N/D NID N/D Ce-144 Ci NID NID N/D N/D Cr-51 Ci NID l.19E-05 N/D NID Co-57 Ci l.03E-07 NID N/D N/D TOTAL FOR PERIOD Ci l.03E-07 2.88E-05 NIA l.07E-08 I_

Attachment 1 TABLE2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12/31/98 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND %EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 2.43E-02 7.03E-02 2.00E+Ol
2. A VE DIL. CONC. DURING PERIOD µCi/ml 3.64E-11 9.69E-11
3. PERCENT OF APPLICABLE LIMIT  % 1.28E-04 2.53E-04 B. TRITIUM
1. TOTAL RELEASE Ci l.36E+02 3.95E+02 2.00E+Ol
2. A VE DIL. CONC. DURING PERIOD µCi/ml 2.04E-07 5.45E-07
3. PERCENT OF APPLICABLE LIMIT  % 2.04E-03 5.45E-03 C. DISSOLVED AND ENTRAINED GASES
l. TOTAL RELEASE Ci 9.83E-05 9.61E-05 2.00E+Ol
2. AVE DIL. CONC. DURING PERIOD µCi/ml 1.47E-13 l.33E-13
3. PERCENT OF APPLICABLE LIMIT  % 7.36E-08 6.63E-08

. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci N/D N/D 2.00E+Ol E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 1.42E+08 1.67E+08 3.00E+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.68E+ 11 7.25E+ll 3.00E+OO

Attachment I TABLE2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12/31/98 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH %EST.ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS I. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 3.46E-02 2.98E-02 2.00E+Ol

2. A VE DIL. CONC. DURING PERIOD µCi/ml 4.59E-l 1 4.85E-l 1
3. PERCENT OF APPLICABLE LIMIT  % 2.71E-04 2.04E-04 B. TRITIUM I. TOTAL RELEASE Ci 2.49E+02 l.29E+02 2.00E+OI
2. A VE DIL. CONC. DURING PERIOD µCi/ml 3.31E-07 2.1 lE-07
3. PERCENT OF APPLICABLE LIMIT  % 3.31E-03 2.lOE-03 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE Ci l.19E-02 l.96E-03 2.00E+OI
2. A VE DIL. CONC. DURING PERIOD µCi/ml l.58E-11 3.19E-12
3. PERCENT OF APPLICABLE LIMIT  % 7.88E-06 l.60E-06 D. GROSS ALPHA RADIOACTIVITY I. TOTAL RELEASE Ci N/D N/D 2.00E+Ol E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS l.34E+08 9.31E+07 3.00E+OO F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.53E+II 6.14E+ 11 3.00E+OO I_

Attachment 1 Page 9 of 12 TABLE2B

  • EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12131/98 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci NID NID NID NID Sr-90 Ci N/D NID NID NID Fe-55 Ci NID NID NID NID Cs-134 Ci 7.02E-05 l.20E-03 l .79E-04 3.76E-04 Cs-137 Ci 6.28E-03 9.70E-03 5.57E-04 l.30E-03 I-131 Ci NID NID 2.67E-05 l.90E-05 Co-58 Ci N/D 2.35E-02 7.49E-03 4.26E-03 Co-60 Ci 8.98E-04 l.OOE-02 l .30E-03 6.84E-04 Fe-59 Ci N/D N/D 5.24E-06 N/D Zn-65 Ci NID N/D NID NID Mn-54 Ci N/D 2.27E-04 2.37E-05 l.46E-05 Cr-51 Ci NID 4.59E-03 l.69E-04 2.15E-04 Zr-95 Ci NID N/D l.l lE-06 7.52E-06 Nb-95 Ci N/D 5.41E-04 l.40E-05 l.52E-05 Mo-99 Ci N/D NID 2.15E-05 NID Tc-99m Ci NID 3.89E-04 l.33E-06 N/D Ba-140 Ci N/D NID NID 3.45E-06 La-140 Ci N/D NID NID N/D Ce-141 Ci N/D NID N/D N/D Ce-144 Ci N/D NID 5.65E-06 l.42E-05 Sb-122 Ci N/D NID 4.46E-06 2.37E-06 Sb-124 Ci NID NID 2.29E-04 5.89E-04 Sb-125 Ci N/D NID 6.92E-03 l.25E-02 Co-57 Ci NID 4.43E-05 2.77E-05 2.89E-06 Sr-92 Ci NID NID NID 3.18E-06 Ag-llOm Ci NID NID 2.81E-05 l.85E-06 Te-132 Ci NID N/D 6.14E-06 N/D Te-127m Ci N/D NID NID 9.58E-05 Ru-106 Ci NID NID 2.47E-05 NID Np-239 Ci NID NID l.64E-05 2.24E-05 TOTAL FOR PERIOD Ci 7.25E-03 5.02E-02 l.71E-02 2.0lE-02 Xe-133 Ci NID NID 9.75E-05 9.34E-05 Xe-135 Ci NID NID 8.04E-07 2.70E-06 TOTAL FOR PERIOD NIA NIA 9.83E-05 9.61E-05 I_

Attachment 1 TABLE2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/98 TO 12/31/98 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 NID NID Fe-55 Ci N/D N/D NID NID Cs-134 Ci N/D N/D 4.4IE-03 3.25E-04 Cs-137 Ci 5.88E-03 6.7IE-03 8.24E-03 3.05E-03 1-131 Ci N/D 9.83E-07 5.4IE-04 l.61E-04 Co-58 Ci N/D l.70E-04 4.37E-03 4.98E-03 Co-60 Ci 2.2IE-04 l.82E-03 6.79E-04 3.43E-03 Fe-59 Ci N/D NID N/D l.30E-05 Zn-65 Ci N/D N/D NID N/D Mn-54 Ci NID N/D l.07E-04 1.13E-04 Cr-51 Ci N/D N/D l.OIE-04 l.72E-03 Zr-95 Ci N/D NID NID 5.26E-05 Nb-95 Ci NID NID N/D l.79E-04 Mo-99 Ci NID N/D NID NID Tc-99m Ci NID N/D NID N/D Ba-140 Ci N/D NID NID N/D La-140 Ci N/D N/D NID 4.96E-06 Ce-141 Ci N/D NID NID NID Ce-144 Ci N/D NID l.22E-05 N/D Sb-122 Ci N/D NID 6.85E-06 N/D Sb-124 Ci N/D NID 5.49E-05 N/D Sb-125 Ci NID NID 9.69E-03 7.0IE-03 Co-57 Ci N/D NID NID l.95E-05 Sn-113 Ci N/D N/D NID 4.69E-06 Te-132 Ci N/D N/D 3.02E-06 N/D Te-125m Ci N/D N/D l.99E-04 N/D Np-239 Ci N/D N/D 5.90E-06 N/D Na-22 Ci N/D N/D l.53E-06 N/D TOTAL FOR PERIOD Ci 6.lOE-03 8.70E-03 2.84E-02 2.1 IE-02 Xe-133 Ci N/D N/D l.18E-02 l.9IE-03 Xe-135 Ci NID N/D 3.35E-06 8.0IE-06 Xe-131m Ci N/D N/D 6.82E-05 4.52E-05 TOTAL FOR PERIOD NIA NIA 1.19E-02 l.96E-03

TABLE3 Attachment I Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/98 - 12/31/98 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 8.85E+Ol
  • l.OOE+Ol bottoms, etc. Ci l.59E+02 3.00E+Ol
b. Dry compressible waste, contaminated m3 8.90E+Ol ** l.OOE+Ol equip., etc. Ci l.14E-Ol 3.00E+Ol
c. Irradiated components, control m3 O.OOE+OO l.OOE+Ol rods, etc. Ci O.OOE+OO 3.00E+Ol
d. Other (Waste Oil) m3 3.03E+OO*** l.OOE+Ol Ci l.95E-04 3.00E+Ol
2. Estimate of major nuclide composition (by type of waste)
a. Co-60  % 2.53E+Ol Ni-63  % 2.12E+Ol Fe-55  % l.39E+Ol Co-58  % I.30E+Ol Cs-137  % l.25E+Ol Cs-134  % 9.65E+OO H-3  % 2.04E+OO Sb-125  % l.OIE+OO
b. Co-60  % 4.89E+Ol Ni-63  % 2.09E+Ol Fe-55  % l.92E+Ol Cs-137  % 5.15E+OO (

Co-58  % 3.52E+OO Cs-134  % l.75E+OO C.  %

TABLE3 Attachment I Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/98 - 12/31/98 CONT'D SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

2. Estimate of major nuclide composition (by type of waste)
d. Ce-144  % 8.l 7E+Ol Cs-137  % l.60E+Ol Fe-55  % l.27E+OO Co-60  % l.02E+OO
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 14 Truck Barnwell, SC 3 Truck Oak Ridge, TN DIATED FUEL SHIPMENT (Disposition)

Number of Shipments Mode of Transportation Destination 0

  • NOTE I: l.29E +O I m3 of this was liquid and 1.5 IE+O I m3 of this was filters shipped to a licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 2.80E+OI m3.
    • NOTE 2: The 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 7.34E+Ol m3.
      • NOTE 3: Waste oil was shipped to a licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is O.OOE+OO 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 Thyroid GI-LLI Gamma Beta Thyroid (mrem) (mrem) (mrem) (mrad) (mrad) (mrem) 1st Quarter 7.46E-05 2.70E-05 l.72E-04 6.l 7E-02 l.SIE-01 9.63E-03 2nd Quarter l.87E-04 6.97E-05 l.06E-03 7.96E-03 2.33E-02 6.97E-03 3rd Quarter 1.46E-04 7.36E-05 l.06E-04 6.00E-03 l.76E-02 l.02E-03 4th Quarter l.07E-04 3.86E-05 4.29E-04 l.42E-02 4.21E-02 7.74E-03 Annual 5.14E-04 2.09E-04 l.77E-03 8.98E-02 2.64E-01 2.54E-02

Attachment 3 Page 1 of 1

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 the period January 1 through December 31, 1998. Revision summaries associated with Surry Power Station are as follows.

Revision 9:

1. X/Q and D/Q values were redetermined for the gaseous effluent pathways based upon the 1992 through 1996 five year average of site meteorological data. Values will be reassessed based on a rolling five year average of site meteorological data.
2. Revised dose projection methodology.
3. Removed effluent dose factor tables from the ODCM.
4. Clarified the different effluent and ISFSI reporting requirements between Surry and North Anna power stations.
5. Added an "upstream" shoreline sediment sample to the Radiological Environmental Monitoring Program (REMP).
6. Reduced the REMP silt sampling locations to two.

Changed the REMP control milk sampling location as the dairy went out of business .

. Revised distances and directions to various REMP sampling locations.

Revision 10:

1. Deleted one indicator milk sampling location as the dairy went out of business.

Revisions 9 and 10 of the ODCM are included with this attachment.

VIRGINIA POWER Administrative Procedures Action Request (A-PAR)

VPAP-0502 - Attachment 22

4. Effective Date VPAP-2103 9 2 5:'2/-9g
5. Procedure Title 6. Expiration Date NJA Offsite Dose Calculation Manual
7. Type of Request D New Procedure !Xl Procedure Revision D Procedure Deletion
8. Brief description of the modification
  • (See page 2 of 2) 9* Location ~ SPS D NAPS D CORP IX) NAPS D CORP Is this a new procedure or does procedure meet requirements of NOTE below ?

Does this procedure require a Safety Evaluation?

re there any new sections or steps designated North Anna or Surry?

s the reason for the station-specific instructions due to differences in regulatory requirements? ON/A

20. Is the reason for the station-specific instructions due to differences in construction? ON/A ON/A If all answers are No or NIA, approval is required by PPOs as identified on the Procedure Cover Page. Check block 29.

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

NOTE: VPAP-2101 and VPAP-2201 require SNSOC approval.

VPAP-2103, VPAP-2104, and VPAP-2401 require SNSOC and Station Manager approval.

If block 18, 19, or 20 is Yes with block 21 No, approval is required by PPOs and Station Managers. Check blocks 29 and 31.

If block 21 is Yes, approval is required by PPOs,Station ManageFS, and Vice President. Check blocks 29, 31'; and 32.

22. Location IX] SPS D NAPS D CORP Location D SPS !X l NAPS CORP
23. PPO Name (Please Print) 25. Phone 26. PPO Name (Please Print)

W. A. Thornton A.H. Stafford

40. Date 5-!c).- C/f'
44. Date 5'-1,) -9
46. Date Key: A-Par - Administrative Procedures Action Request; SPS - Surry Power Station; NAPS* North Anna Power Station; CORP
  • Corporate; PPO(s) - Process Program OWnar(s); SNSOC
  • Station Nuclear Safety Operating Commltaa Form No. 720457(0ct 96)

VIRGIMIA POWER Revision 9

Page 2 of 2 Administrative Procedures Action Request (A-PAR)

Additional information for block 8 (Brief description of the modification)

The following changes were made due to the implementation of 5 year meteorological data average:

Revised 6.2.3.c, Surry Dose Contribution Calculations - reworded Revised 6.2.4.c, Projected Total Body Dose Calculation - deleted reference to Equation (7) and Surry Revised 6.2.4.d, Projected Critical Organ Dose Calculation - became North Anna only Added 6.2.4.e, Projected Dose Calculations (Surry)

Revised 6.3.1.c, Calculations of Gaseous Effluent Dose Rates - added Surry only NOTE; calculations are for North Anna Revised 6.3.3, Noble Gas Effluent Air Dose Limit- added Surry only NOTE Revised 6.3.3.c - calculations are for North Anna Revised 6.3.4.c, Surry Dose Calculations - added note referring to RMi and Rii dose factors Revised 6.3.4.c. 1 - deleted reference to Attachment 16, Critical Organ and Inhalation Dose Factors for Surry; added reference to Canberra Source Code file Revised 6.3.5.c, d, & e - became North Anna only Added 6.3.5.f-Projected Dose Calculations (Surry)

Deleted Attachment 5, Liquid Ingestion Pathway Dose Factors for Surry Station Units 1 and 2 Deleted Attachment 10, Gaseous Effluent Dose Factors for Surry Revised renumbered Attachment 23, Surry Meteorological, Liquid, and Gaseous Pathway Analysis -

changed to reflect implementation of new program The following miscellaneous changes were made for clarification:

Added 3.1.11 - TID-4500, VCRL-50564, Rev. 1, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, October, 1972 Revised 6.0 NOTE - added "for Surry and North Anna respectively" evised Attachment 15, Surry Radiological Environmental Monitoring Program (3.c) - changed "1 sample downstream area with existing potential recreational value" to "a) 1 sample upstream, & b) 1 sample tream" evised Attachment 17, Surry Environmental Sampling Locations - Environmental TLDs: changed East (Exclusion) Remarks from "Onsite" to "Exclusion Area Boundary", 3.5 to 5.0 for Route 633 Distance, and 5.2 to 4.7 for Route 617 and 618 Distance; Sediment (Silt): changed NNW to NW for Surry Station Discharge Direction and NE to NNE for Hog Island Point Direction; Clams: changed NNW to NW for Surry Station Discharge Direction and NE NNE for Hog Island Point Direction; Oysters: changed NE to NNE for Kingsmill Direction and EESE to SE for Mulberry Point Direction; Shoreline Sediment: added Chickahominy River; changed milk sample media control location (Williams) to (Pivamik) with revised distance direction

  • The following changes were made in response to NAPS internal audit:

Revised 6.2.4 - moved text concerning historical data pertaining to the volumes and radioactivity of liquid effluents released from 6.2.4.d Revised 6.7.2.c. NOTE - Annual Radioacttve*Effluent Report for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Report (6.7.2.c became Surry only)

Revised Attachment 2, North Anna Radioactive Liquid Effluent Monitoring Instrumentation [l(c)] and Attachment 4, North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements [l(c)] - changed "Sampler Flow Monitor to "solenoid valve" Revised Attachment 6, North Anna Radioactive Liquid Waste Sampling and Analysis Program - added Note references to table; added NOTE 8 concerning gamma emitters for which the LLD specification applies exclusively Revised Attachment 11, Surry Radiological Environmental Monitoring Program - added Note references to table; added NOTE 3 defining what a "channel" shall consist of Revised Attachment 9, Gaseous Effluent Dose Factors for North Anna - deleted Kr-83m and Kr-90 from Dose Factors for Ventilation Vent table and Dose Factors for Process Vent table Revised 6.7 .2 NOTE - added "The Annual Radioactive Effluent Report for the North Anna ISFSI is ded as part of the North Anna Station Annual Radioactive Effluent Report" e the following change to update position title:

~ anged 6.7.4.a (Station Manager) to (Site Vice President)

Station Administrative

  • VIRGINIA POWER

Title:

Offsite Dose Calculation Manual Procedure

@ 1998 by Virginia Power. All Rights Reserved Process I Program Owner:Superintendent - Radiological Protection Procedure Number Revision Number Effective Date VPAP-2103 9 s-~1-qz Revision Summary The following changes were made due to the implementation of 5 year meteorological data average:

  • Revised 6.2.3.c, Surry Dose Contribution Calculations - reworded
  • Revised 6.2.4.c, Projected Total Body Dose Calculation - deleted reference to Equation (7) and Surry
  • Revised 6.2.4.d, Projected Critical Organ Dose Calculation - became North Anna only
  • Added 6.2.4.e, Projected Dose Calculations (Surry)
  • Revised 6.3.1.c, Calculations of Gaseous Effluent Dose Rates - added Surry only NOTE; calculations are for North Anna
  • Revised 6.3.3, Noble Gas Effluent Air Dose Limit - added Surry only NOTE
  • Revised 6.3.3.c - calculations are for North Anna
  • Revised 6.3.4.c, Surry Dose Calculations - added note referring to RMi and Rii dose factors
  • Revised 6.3.4.c. 1 - deleted reference to Attachment 16, Critical Organ and Inhalation Dose Factors for Surry; added reference to Canberra Source Code file
  • Revised 6.3.5.c, d, & e - became North Anna only
  • Added 6.3.5.f - Projected Dose Calculations (Surry)
  • Deleted Attachment 5, Liquid Ingestion Pathway Dose Factors for Surry Station Units 1 and 2
  • Deleted Attachment 10, Gaseous Effluent Dose Factors for Surry
  • Revised renumbered Attachment 23, Surry Meteorological, Liquid, and Gaseous Pathway Analysis - changed to reflect implementation of new program Revision Summary continued on Page 2 Approvals on File l__

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE2 OF 140 Revision Summary continued The following changes were made for clarification and to update requirements:

  • Added 3.1.11 - TID-4500, VCRL-50564, Rev. 1, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, October, 1972
  • Revised 6.0 NOTE - added "for Surry and North Anna respectively"
  • Deleted from renumbered Attachment 13, North Anna Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements, "(NOTE 5)" from La) - l-RM-GW-102 source check to update surveillance requirements .
  • Revised renumbered Attachment 15, Surry Radiological Environmental Monitoring Program:

3.c) - changed "1 sample from downstream area with existing .potential recreational value" to "a) 1 sample upstream, & b) 1 sample downstream";

3.d) - changed number of samples from 5 to 2 4.a) - added to Ingestion - Milk: "Composite for Sr89/Sr90 analysis quarterly"

  • Revised renumbered Attachment 17, Surry Environmental Sampling Locations - Environmental TLDs: changed East (Exclusion) Remarks from "Onsite" to "Exclusion Area Boundary", 3.5 to 5.0 for Route 633 Distance, and 5.2 to 4.7 for Route 617 and 618 Distance; Sediment (Silt): changed NNW to NW for Surry Station Discharge Direction, deleted Surry Station Intake, Hog Island Point, and Point of Shoals; Clams: changed NNW to NW for Surry Station Discharge Direction and NE NNE for Hog Island Point Direction; Oysters: changed NE to NNE for Kingsmill Direction and EESE to SE for Mulberry Point Direction; Shoreline Sediment: added Chickahominy River; changed milk sample media control location (Williams) to (Pivarnik) _with revised distance and direction The following changes were made in response to NAPS internal audit:
  • Revised 6.2.4 - moved text concerning historical.data pertaining to the volumes and radioactivity of liquid effluents released from 6.2.4.d *
  • Revised 6.7.2.c. NOTE -Annual Radioactive Effluent.Report fot the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Report (6.7 .2.c became Surry only)
  • Revised Attachment 2, North Anna Radioactive Liquid Effluent Monitoring Instrumentation [1 (c )]

and Attachment 4, North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements [l(c)] - changed "Sampler Flow Monitor" to "solenoid valve"

  • Revised Attachment 6, North Anna Radioactive Liquid Waste Sampling and Analysis Program -

added Note references to table; added NOTE 8 concerning gamma emitters for which the LLD specification applies exclusively

  • Revised Attachment 11, Surry Radiological Environmental Monitoring Program - added Note references to table; added NOTE 3 defining what a "channel" shall consist of
  • Revised Attachment 9, Gaseous Effluent Dose Factors for North Anna - deleted Kr-83m and Kr-90 from Dose Factors for Ventilation Vent table and Dose Factors for Process Vent table
  • Revised 6.7 .2 NOTE - added "The Annual Radioactive Effluent Report for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Report" Made the following change to update position title:
  • Changed 6.7.4.a (Station Manager) to (Site Vice President)

J

VIRGINIA VPAP-2103 POWER REVIS10N9, PAGE3 OF 140

  • Section TABLE OF CONTENTS Page 1.0 PURPOSE 7 2.0 SCQPE 7

3.0 REFERENCES

/COMMITMENT DOCUMENTS 8 4.0 DEFINITIONS 9 5.0 RESPONSIBILITIES 13 6.0 INSTRUCTIONS 15 6.1 Sampling and Monitoring Criteria 15 6.2 Liquid Radioactive W~te Effluents 15 6.2.1 Liquid Effluent Concentration Limitations 15 6.2.2 Liquid Monitoring Instrumentation 16 6.2.3 Liquid Effluent Dose Limit 20 6.2.4 Liquid Radwaste Treatment 23 6.2.5 Liquid S,~mpling 25 6.3 Gas~ous Radioactive W~te Effluents 25 6.3.1 Gaseous Efflu~nt Dose Rate Limitation 25 6.3.2 Gaseous Monitoring Instrumentation 27 6.3.3 Noble Gas Effluent Air Dose Limit

  • 30 6.3.4 1-131, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 32 6.3.5 Gaseous Radwaste Treatment 36 6.4 Radioactive Liquid and Gaseous Release Pernnts 38 6.4.1 Liquid Waste Batch Release Permits 38 6.4.2 Continuous Release Permit 39 6.4.3 Waste Gas Decay Taruc (WGDT) Release Permit 40 6.4.4 Reactor Containment Release Permits 40 6.4.5 Miscellaneous Gaseous Release Permit 40

VIRGINIA VPAP-2103 POWER REV1SI0N9

  • PAGE40F 140 TABLE OF CONTENTS (continued)

Section Page 6.4.6 Radioactive Liquid and Gaseous Release Controls 41 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 42 6.6 Radiological Environmental Monitoring 43 6.6.1 Monitoring Program 43 6.6.2 Land Use Census 45 6.6.3 Interlaboratory Comparison Program 46 6.7 Reporting Requirements 47 6.7.1 Annual Radiological Environmental Operating Report 47 6.7.2 Annual Radioactive Effluent Release Report 48 6.7.3 Annual Meteorological Data 50 6.7.4 Changes to the ODCM 50 7.0 RECORDS 52 ATTACHMENTS

  • 1 Surry Radioactive Liquid Effluent Monitoring Instrumentation 53 2 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 55 3 Surry Radioactive Liquid Effluent Monitoring Instrumentation 57 Surveillance Requirements **

4 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 59 Surveillance Requirements 5 Surry Radioactive Liquid Waste Sampling and Analysis Program 61 6 North Anna Radioactive Liquid Waste Sampling and Analysis Program 65 7 Surry Radioactive Gaseous Waste Sampling and Analysis Program 69 8 North Anna Radioactive Gaseous Waste Sampling and Analysis Program 75 9 Gaseous Effluent Dose Factors for North Anna 79

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGES OF 140

  • Section TABLE OF CONTENTS (continued) 10 Surry Radioactive Gaseous Effluent M(,nitoring Instrumentation Page 83 11 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 87 12 Surry Radioactive Gaseous Effluent Mo~itoring Instrumentation 91 Surveillance Requirements 13 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 93 Surveillance Req1d.rements .

14 Criti~l Organ Dose Factors for North Anna 97 15 Surry Radiologi~l Environme11tal Monitoring Progrim 99 16 North Anna Radiological 'Environme11tal Monitoring Program 103 17 Surry Environmental Sampling Locations 109 18 North Anna Environmental Sampling Locations 1)3 19 Detection Capabiliti~ for Surry Environmental Sample Analysis 117 20 Detection Capabilities for North Anna E11vironmental Sample Analysis 119 21 Reporting Levels for Radioactivity Concentrations in Enviro~mental 121 Samples at Surry 22 Reporting Levels (or RadiQijctivity Concentratio~s in Environmental 123 Samples at North Anna 23 Surry Meteorologi~l, Liquid, and Gaseous Pathway Analysis 1'.25 24 North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 133

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE6 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION9 PAGE70F 140

  • 1.0 PURPOSE The 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 µCi/ml for dissolved 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
    • 1131 , 1133 , and H 3 , and all radionuclides in particulate form 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 and North Anna Stations.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 8 OF 140

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 3.1.8 Surry and North Anna Technical Specifications (Units 1 and 2)

3. 1.9 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine 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 3.1.14 Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Rev. 1 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, Rev. 3, March 1982 3.1.18 Environmental Measurements Laboratory, DOE HASL 300 Manual

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE90F 140

  • 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 Calcul~tion Manual or to the Process Control Program 3.1.20 UFSAR (Surry and North Anna) 3.1.21 Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361 3.1.22 VPAP-2802, Notifications and Reports 3.1.23 NAPS Circulating Water System Modifications
a. DC-85-37-1 Unit 1
b. DC-85-38-2 Unit 2 3.1.24 Deviation Report N94-1137, Improper Placement of Emergency TLDs 3.2 Commitment Documents 3.2.1 Quality Assurance Audit Report Number C 90-22, Management Safety Review Committee, Observation 03C, January 17, 1991 3.2.2 Quality Assurance Audit Report Number 91-03, Observation 08N 3.2.3 Quality Assurance Audit Report Number 92-03, Observation 02N 3.2.4 Quality Assurance Audit Report Number 92-03, Observation 04NS (Item 2) 3.2.5 North Anna DR N-97-0926, Annual Radiological Effluent Release Report 3.2.6 Surry DR S-97-1281, Annual Radiological Effluent Release Report 4.0 DEFINITIONS 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 cfoµmel indication and/or status with

  • other indications and/or status derived from independent instrumentation channels measuring the same parameter.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 10 OF 140 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.

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 That concentration of 1131 (µCi/cc) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131 , I 132, I 133 , I 134, and I 135 actually present. Thyroid dose conversion factors for this calculation are listed in Table Ill 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 (Surry).

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 11 OF 140

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

NOTATION FREQUENCY D -Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W-Weekly At least once per 7 days M-Monthly At least once per 31 days Q - Quarterly At least once per 92 days SA - Semi-annually At least once per 184 days R - Refueling At least once per 18 months SIU - Start-up Prior to each reactor start-up P - Prior to release Completed prior to each release N.A. - Not applicable Not applicable DR - During the release At least once during each release

  • 4.7 Gaseous Radwaste Treatment System A system that redt1ces radioactive gaseous effluents by collecting primary coolant system offgases from the primary system a~d 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, waste gas surge tanks, and waste gas diaphragm compressor (North Anna).

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 (ins_tantaneous; 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 12 OF 140 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 Virginia Power 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 servicemen or postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Virginia Power 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, 4.13 humidity, concentration, or other operating condition, so that replacement air or gas is required to purify the confinement.

Rated Thermal Power Total reactor core heat transfer rate to reactor coolant.

  • Surry - 2546 Megawatts Thermal (MWt)
  • North Anna- 2893 MWt 4.14 Site Boundary The line beyond which Virginia Power 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 13 OF 140

  • 4.17 4.18 Thermal Power Total reactor core heat transfer rate to the reactor coolant.

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

4.19 Ventilation Exhaust Treatment System A system that reduces gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and High 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 effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not Ventilation Exhaust Treatment System components.

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

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

5.1.2 Surveying, sampling, and analyzing plant effluents and environmental monitoring, 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 Superintendent Operations The Superintendent Operations is responsibl~ for requesting sampl~s, analyses, and authorization to release effluents.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 14 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 15 OF 140 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Attachments 23 and 24, Meteorological, Liquid, and Gaseous Pathway Analysis for Surry and North Anna, respectively.

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

6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation or parameter monitored.

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 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.

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:
1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to unrestricted areas shall not exceed ten times the effluent cpncentration values specified in 10 CFR 20, Appendix B, Table 2, Column 2.
2. For dissolved or entrained noble gases, concentrations shall not exceed 2E-4 µCi/ml .
  • b. If the concentration of liquid effluent exceeds the limits in 6.2.1.a., promptly reduce concentrations to within limits.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 16 OF 140

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> (l) 1

µCi/ml.1 -

Volume of Waste Discharged x L i ACW.

1 where:

µCi/m4 =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 µCi/ml from 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases, and 2E-4 µCi/ml 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 Attachments 1 and 2, Radioactive Liquid Effluent Monitoring Instrumentation, 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
  • Change the setpoint to an acceptable, conservative value

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 17 OF 140

b. Radioactive Liquid Effluent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performjng a Channel Check, Source Check, Channel Calibration, and Channel Functional Test at the*frequencies shown in Attachments 3 and 4, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.
1. If the number of operable channels is less than the minimum required by the tables in Attachment 1 or 2, perform the action shown in those tables.
2. Attempt to return the instruments to operable status within 30 days. If un*successful, explain in the next Annual R~dioactive 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:

Release Point Instrument Number NorthAnna Surry Liquid Radwaste Effluent Line 1-LW-RM-111 NIA Service Water System Effluent Line 1-SW-RM-108 1-SW-RM-107 A, B,C,D Condenser Circulating Water Line 1-SW-RM-130 1-SW-RM-120 2-SW-RM-230 2-SW-RM-220 Radwaste Facility Effluent Line *

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 18 OF 140 6.2.2 Liquid Monitoring Instrumentation (continued)

d. Setpoint Calculation NOTE: This methodology does not preclude use of more conservative setpoints.
1. Maximum setpoint values shall be calculated by:

s = (2) where:

S = the setpoint, in µCi/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 CFR 20 for the Station, in µCi/ml FE = maximum design pathway effluent flow rate Fo = dilution water flow rate calculated as:

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

(N. Anna) D =FE+ (218,000 gpm x number of circ. pumps in service)

2. Each of the condenser circulating water channels (Surry: SW-120, SW-220)

(North Anna: SW-130, SW-230) 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 liquid radwaste effluent line (North Anna: LW-111), the service water system effluent line (Surry: SW-107 A, B, C, and D, North Anna: SW-108), and the Radwaste Facility effluent line (Surry: RRM-131).

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 19 OF 140

  • 4. For the liquid radwaste effluent line, Equation (2) becomes:

s = (4) where:

KLw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 for the site, attributable to the liquid radwaste effluent line pathway

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

s = (5) 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

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

s = (6) where:

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

7. The sum KLw + Ksw + KRw shall not be greater than 1.0.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 20 OF 140 6.2.3 Liquid Effluent Dose Limit

a. Requirement At least once per 31 days, perform the dose calculations in 6.2.3.c. and 6.2.3.d. to ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials in liquid releases (from each reactor unit) to umestricted areas is limited to:
1. During arty 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
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 reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 21 OF 140

  • c. Surry 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~C.A. k,./ 1 1 (7) i 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 Ci and F are averaged for all liquid releases, in hours M = the mixing ratio (reciprocal of the dilutiop factor) at the point of exposure, dimensionless, 0.2 from Appendix 1 lA, Surry UFSAR F = the near field average dilution factor for q 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 q = the average concentration of radionuclide, i, in undiluted liquid effluent during the period t, from all liquid releases, in µCi/ml Ai = the site-related ingestion dose commitment factor to the total body or critical organ for a particular age group for each identified principal gamma and beta emitter in mrem-ml per hr-µCi. Values for Ai are provided in the Canberra Source Code file.

A.1 = 1.14 E+05 (21BF.1 + 5BI.) 1 DF.1 (8) where:

1.14 E+o5 = 1 E+06 pCi/µCi x 1 E+03 ml/kg/(8760 hr/yr), units conversion factor

  • 21 = adult fish consumption, kg/yr, from NUREG-0133

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 22 OF 140 5 = adult invertebrate consumption, kg/yr, from NUREG-0133 Bli = the bioaccumulation factor for nuclide i, in invertebrates, pCi/kg per pCi/1 BFi = the bioaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1 DFi = the critical organ dose conversion factor for nuclide i, for adults, in mrem/pCi NOTE: The above parameters were obtained from R.G. 1.109, Rev. 1, LADTAP Il, NUREG/CR-1276, and TID-4500, VCRL-50564, Rev. 1.

d. North Anna Dose Contribution Calculations Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on:

(9)

D = ~Q.xB.

£.,,,i 1 1 1

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 Bi = Dose Commitment Factors (mrem/Ci) for each age group of interest.

Values for Bi are provided in code file for North Anna Power Station liquid pathway critical organ calculations Q. = Total released activity for the considered period and the ith nuclide Qi = t x Ci x Waste Flow (10)

Where:

t = the period for which Ci and F are averaged for all liquid releases, in hours q = the average concentration of radionuclide, i, in undiluted liquid effluent during the period, t, from any liquid releases, in µCi/ml J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 23 OF 140

  • e. 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 approximated by assuming an ijverage monthly concentration based on previous monthly or quarterly composit~ analyses. However, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses.

6.2.4 Liquid Radwaste Treatment Historical data pertaining to the volumes and radioactivity of liquid effluents released in connection with specific station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.

a. Requirement
1. The Liquid Radwaste Treatment System and/or 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 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 Dose Calculation
1. Determine DTB, the total body dose from liquid effluents in the previous 31-day period, per Equation (9) for North Anna.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 24 OF 140

2. Estimate R i, the ratio of the estimated volume of liquid effluent releases in the present 31-day period to the volume released in the previous 31-day period.
3. Estimate F 1, the ratio of the estimated liquid effluent radioactivity concentration in the present 31-day period to liquid effluent concentration in the previous 31-day period (µCi/ml).
4. Determine PDTB, the projected total body dose in a 31-day period.

(11)

d. Projected Critical Organ Dose Calculation (North Anna)
1. Determine D0 , the critical organ dose from liquid effluents in the previous 31-day period, per Equation (9) for North Anna.
2. Estimate R 1 as in 6.2.4.c.2.
3. Estimate F 1 as in 6.2.4.c.3.
4. Determine PD0 = projected critical organ dose in a 31-day period.
e. Projected Dose Calculations (Surry)

(12)

1. Determine DI, the sum of all liquid open release points, in mrem/day, by the ith organ.
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 J

VIRGlNIA VPAP-2103 POWER REVISION9 PAGE 25 OF 140

  • 6.2.5 Liquid Sampling Radioactive liquid wastes shall be sampled a~d analyzed according to the sampling
  • and analysis requirements in Attachments 5 and 6, Radioactive Liquid Waste Sampling and Analysis Program (Surry and North Anna, respectively).

6.3 Gaseous Radioactive Waste Effluents 6.3.1 Gaseous Effluent Dose R11te Limitation

a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to:
1. The dose rate limit for noble gases shall be .::5 500 mrem/year to the total body and .::5 3000 mrem/year to the skin.
2. The dose rate limit for I 131 , I 133 , for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be .::5 1500 mrem/year -

to the critical organ.

b. Action
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, continuously, to be within 6.3.1.a. limits.
3. Dose rates due to 1131 , 1133 , tritium, and all radionuclides in particulate form 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 analyses in accordance with the sampling and analysis program specified on Attachments 7 and 8, Radioactive Gaseous Waste Sampling and Analysis Program.

VIRGINIA VPAP-2103 POWER REVISI0N9

  • PAGE 26 OF 140
c. Calculations of Gaseous Effluent Dose Rates NOTE: The dose factors used in the Gaseous Effluent Dose Rate calculations for Surry Power Station 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 (13), (14), and (15) must be multiplied by the appropriate X/Q value for Surry's Gaseous Effluent Dose Rate calculations.
1. The dose rate limit for noble gases shall be determined to be within the limit by limiting the release rate to the lesser of:

L [KivvQivv + KipvQipvl s; 500mrem/yr to the total body (13) i OR

~

,L,,,/ [(L.lVV + 1.1M.lVV ) Q1*vv + (L.1pv + 1.lM.1pv

  • ) Q1*pv] s; 3000mrem/yr to the skin i (14) 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

= The total body dose {actor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec. Factors are listed in Attachment 9, Gaseous Effluent Dose Factors for North Anna

= 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. Factors are listed in Attachment 9 for North Anna

= 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. Factors are listed in Attachment 9 for North Anna

= 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

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 27 OF 140

  • 2. The dose rate limit for I 131 , I 133 , tritium, and for all radionuclides in particulate form with half-lives greater than 8 days, shall be determined to be within the limit by restricting the release rate to:

~ [PivvQivv + PipvQipvl ~ 1500mrem/yr to the critical organ (15) 1 where:

= The critical orf:an dose factor for ventilation vents or process vent for I 131 , I 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. Factors are listed in Attachment 9 for North Anna *

= The release rate for ventilation vents or process vent of I 131 ,

I 133 , 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 throughthe process vent, are considered ground level and shall be included in the determination of Qivv
  • 6.3.2 Gaseous Monitoring Instrumentation
a. Requirement
1. The radioactive gaseous effluent monitoring instrumentation channels shown in Attachment 10 or 11, Radioactive Gaseous Effluent Monitoring Instrumentation, shall be operable with alarm/trip setpoints set to enst;ll'e that 6.3.1.a. noble gas limits 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 Attachment 12 or 13, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 28 OF 140

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 Attachments 10 and 11, 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.
c. Applicable Monitors Radioactive gaseous effluent monitors for which alarm/trip setpoints shall be determined are:

Release Point Instrument Number North Anna Surry Process Vent 1-GW-RM-102 1-GW-RM-102 1-GW-RM-178-1 1-GW-RM-130-1 Condenser Air Ejector 1-SV-RM-121 1-SV-RM-111 2-SV-RM-221 2-SV-RM-211 Ventilation Vent A 1-VG-RM-104 NIA 1-VG-RM-179-1 Ventilation Vent B 1-VG-RM-113 NIA 1-VG-RM-180-1 Ventilation Vent No. 1 NIA 1-VG-RM-104 Ventilation Vent No. 2 NIA 1-VG-RM-110 1-VG-RM-131-1 Radwaste Facility Vent NIA RRM-101

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 29 OF 140

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

D~Dpv +D cae +Dvv (16) 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:

Surry: Summation of the Ventilation Vents 1, 2, and the Radwaste Facility vent gaseous effluent releases, mrem/yr North Anna:Surnmation of Ventilation Vent A plus B gaseous effluent releases, mrem/yr

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 30 OF 140

2. Setpoint values shall be determined by:

R m x 2.12 E-03 (17) where:

m = The release pathway, process vent (pv), ventilation vent (vv) condenser air ejector (cae), or Radwaste Facility (rv)

Cm = The effluent concentration limit implementing 6.3.1.a. for the Station, µCi/ml Rm = The release rate limit for pathway m determined from methodology in 6.3.1.c., using Xe133 as nuclide to be released,

µCi/sec 2.12E-03 = CFM per ml/sec Fm = The maximum flow rate for pathway m, CFM 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.

6.3.3 Noble Gas Effluent Air Dose Limit NOTE: The dose factors used in the Noble Gas air dose calculations for Surry Power Station are included in the 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 (18) and (19) must be multiplied by the appropriate X/Q value for Surry's 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: S 5 mrads for gamma radiation and S 10 mrads for beta radiation
  • During any calendar year: S 10 mrads for gamma radiation and S20 mrads for beta radiation

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 31 OF 140

  • 2. Cumulative dose 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.
c. Noble Gas Effluent Air Dose Calculation (North Anna)

Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of <hvv*

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-08 L [MivvQivv + MipvQipvJ (18) i

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 32 OF 140 For beta radiation:

Db = 3.17E-08 L [NivvQivv + NipvQipvJ (19) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents, 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 vent release due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per Curie/sec. Factors are listed in Attachment 9 for North Anna

= 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. Factors are listed in Attachment 9 for North Anna

= 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 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 I 131 , I 133 , 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: 5 7 .5 mrem to the critical organ
  • During any calendar year: 5 15 mrem to the critical organ
2. Cumulative dose contributions to a member of the public from I 131 , I 133 ,

tritium, andradionuclides in particulate form with half-lives greater than 8 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. or 6.3.4.d.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 33 OF 140

  • b. Action If the calculated dose from the release of I 131 , I 133 , tritium, and radionuclides 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 special 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 34 OF 140

c. Surry Dose Calculations NOTE: The RMi and Rli dose factors DO NOT include the applicable D/Q and X/Q values respectively for Surry Power Station. Equation (20) 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 Qivv. 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 beyond the site boundary that contain I 131 , I 133 , tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

Dr = 3.l?E-08 ~

,£..- [(RM.1vv Q1*vv + RM.1pv Q1*pv) + (RI.1vv Q1*vv + RI.1pv Q1*pv)] (20) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents, including the Radwaste Facility Ventilation Vent and air 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 RMivv, RMipv= the cow-milk pathway dose factor for ventilation vents or process vent release due to I 131 , I 133 , tritium, and from all particulate-form radionuclides with half-lives greater than eight days, in mrem/yr per µCi/m 3* Factors are included in the Canberra Source Code file.

the inhalation pathway dose factor for ventilation vents or process ventrelease due to I 131 , I 133 , tritium, and from all particulate-form radionuclides with half-lives greater than eight days, in mrem/yr per µCi/m3

  • Factors are included in the Canberra Source Code file.

J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 35 OF 140

  • 3.17 E-08

= the release for ventilation vents or process vent of I 131 , I 133 ,

tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curi.es

= the inverse of the number of seconds* in a year

d. North Anna Dose Calculations Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qivv* 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 beyonq the site boundary~ that contain 1131 , I 133 ,

tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

Dr = 3.17E-08 L [RMivvQivv + RMipvQipvl (21) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents; 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 RMivv, RMipv =the cow-milk dose factor for ventilation vents or process vent release due to I 131 , I 133 , tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in mrem/yr per Curie/sec. Factors are listed in Attachment 14, Critical Organ Dose Factors for North Anna QivvQipv = the release for ventilation vents or process vent of I 131 , I 133 ,

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGEJ6 OF 140 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. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive material in gaseous waste before its discharge, when 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 rnrad for gamma radiation and 0.4 rnrad for beta radiation, averaged over 31 days. (North Anna)
2. Appropriate portions of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when 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 rnrad for gamma radiation and 0.4 rnrad for beta radiation, averaged over 31 days. (Surry)
3. 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 rnrem to the critical organ, averaged over 31 days.
4. 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. and 6.3.5.d.
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 for the inoperability.
2. Actions taken to restore the inoperable equipment to operable status.
3. Summary description of actions taken to prevent recurrence.

__J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 37 OF 140

  • c. Projected Gamma Dose (North Anna)
1. Determine Dg, the 31-day gamma air dose for the previous 31-day period, per Equation (18).
2. Estimate Rg, the ratio of the estimated volume of gaseous effluent in the current 31-day period to the volume released during the previous 31-day period.
3. Estimate Fg, the ratio of the estimated noble gas effluent activity in the current 31-day period to the noble gas effluent activity during the previous 31-day period (µCi/ml).
4. Determine PDg, the projected 31-day gamma air dose.

PD g = D g (R g xF g ) (22)

d. Projected Beta Dose (North Anna)
1. Determine Db, the 31-day beta air dose in the previous 31 days, per Equation (19).
2. Estimate Rg and Fg as in 6.3.5.c.2. and 6.3.5.c.3.
3. Determine PDb, the projected 31-day beta air dose.

(23)

e. Projected Maximum Exposed Member of the Public Dose (North Anna)
1. Determine Dmax, the 31-day maximum exposed member of the public dose in the previoqs 31-day period, per Equation (20) or Equation (21),

where Dr = Dmax*

2. Estimate Fi, the ratio of the estimated activity from I 131 , I 133 , radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the current 31-day period to the activity of 1131 , 1133 , radioactive materials in particulate form with haif-lives greater than 8 days, and tritium in the previous 31-day period (µCi/ml).

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 38 OF 140

3. Determine PDmax, the projected 31-day maximum exposed member of the public dose.

PD max = D max (R g xF.) 1 (24)

f. Projected Dose Calculations (Surry)
1. Determine Dg, the sum of all gaseous open release points, in mrem/day, by the ith organ.
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 = (Dg x P) + 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.

6.4.1 Liquid Waste Batch Release Permits Operations shall obtain RP authorization before initiating batch releases of radioactive liquids. Examples of batch releases include:

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 39 OF 140

a. Surry Batch Releases Release of contents from the following tanks/sumps other than transfers to the Surry Radwaste Facility shall have a Liquid Waste Batch Release Permit before the discharge:
  • Boron Recovery Test Tank (BRTT)
  • Low Level Waste Drain Tank (LLWDT)
  • High Level Waste Drain Tank (HLWOT)
  • Liquid Waste Test Tank (LWTT)
  • Contaminated Drain Tank (CDT)
  • Laundry Drain Surge Tank (LOST)
  • Turbine Building Sumps when RP determines that source activity requires placing pumps in manual mode
  • Condensate Polishing Building Sumps when RP determines the presence of contamination from primary-to-secondary leakage
b. North Anna Batch Releases NOTE: If the clarifier is in service, releases from tanks processed through the clarifier are
  • considered continuous releases.

A Batch Release Permit is required for a release from any tanks/sumps which contain (or potentially cpntain) _radioactive liquid. Tanks/sumps include:

  • BRTT
  • LLWDT
  • HLWDT
  • Turbine Building Sumps when secondary coolant activity exceeds 1.0 E-5 µCi/ml
  • CDT 6.4.2 Continuous Release Permit Operations shall obtain RP authorization before initiating continuous releases of radioactive liquids.

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 40 OF 140

a. Surry Continuous Releases A Continuous release permit is required at Surry for:
  • Component Cooling Water (CCW) heat exchanger to service water leakage, if applicable
  • Turbine Building sumps and/or subsurface drains if source activity concentrations are sufficiently low to allow continuous release
b. North Anna Continuous Releases A Continuous Release Permit is required at North Anna for:
  • Clarifier, unless being bypassed
  • Containment mat sumps and service water reservoir when clarifier is bypassed 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit Operations shall obtain RP authorization before initiating WGDT releases.

6.4.4 Reactor Conuiinment 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
  • Receipt of Radiation Monitoring System (RMS) Containment Gas Monitor high alarm 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorization before initiating releases of noble gases that may not be accounted for by routine sampling, or any planned release not being routed through the Process Vent or Ventilation Vents (e.g., steam driven auxiliary feedwater pump testing if primary to secondary leakage exists).

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 41 OF 140

  • 6.4.6 Radioactive Liquid and Gaseous Release Controls
a. Operations shall notify RP of pending releases and request RP to initiate the appropriate release permit. Operations shall provide the necessary information to complete the req:uired 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, except Clarifier Proportional Tanlc and Clarifier Grab Samples at North Anna.

2. Chemistry shall provide RP with liquid samples and sample information for samples obtained from inside the Primary Sample Room.
3. RP shall obtain gaseous samples.
c. RP shall perform required sample analyses.
d. RP shall calculate and record the following information on a release permit:
  • Maximum authorized release rate
  • Maximum authorized release rate in percentage of limits specified by the ODCM
  • 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 percent of Technical Specification limits the release represents.
4. Note and ensure compliance with any indicated controls or conditions applicable to the release.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 42 OF 140

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
  • Beginning pressure
  • Release flow rate
  • 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 information shall include:
  • Date and time release was stopped
  • Tank/sump ending level
  • Release flow rate just prior to termination
  • Ending pressure
  • Volume released 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 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:

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 43 OF 140

  • 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 Radiological Environmental Monitoring 6.6.1 Monitoring Program

a. Requirement
1. The Radiological Environmental Monitoring Program shall be conducted as specified in Attachment 15 or Attachment 16, Radiological Environmental Monitoring Program.
2. Samples shall be collected from specific locations specified in Attachment 17 or Attachment 18, Environmental Sample Locations. [Commitment 3.2.2]
3. Samples shall be analyzed in accordance with:
  • Attachment 15 or Attachment 16 requirements
  • Detection capabilities required by Attachment 19 or Attachment 20, Detection Capabilities for Environmental Sample Analysis

.. Guidance of the Radiological Assessment Branch Technical Position on 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 Annual Radiological Environmental Operating Report required by Technical Specification (Surry Technical Specification 6.6.B.2 and North Anna Technical
  • Specification 6.9.1.8), a description of the reasons for not conducting the program as required, and the plan for precluding recurrence.

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 44 OF 140

2. If, when averaged over any calendar quarter, radioactivity exceeds the reporting levels of Attachment 21 or Attachment 22, Reporting Levels for Radioactivity Concentrations in Environmental Samples, 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 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 Attachment 21 or Attachment 22 are detected in the sampling medium, the report shall be submitted if:

concentration (1) concentration (2) >

10 (25) reporting level (1) + reporting level (2) + ... - *

3. When radionuclides other than those listed in Attachments 21 and 22 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 Attachment 15 or 16, 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 identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Report in accordance with VPAP-2802, Notifications and Reports. Include in the report a revised figure and table for the ODCM to reflect the new locations .

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 45 OF 140

  • 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 use census results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.
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 Attachment 15 or Attachment 16 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.2, 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 conuni,tment (via the same exposure pathway) 20 percent (Surry) or 25 percent (North Anna) 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) 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 3.2.4]

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 46 OF 140 6.6.3 Interlaboratory Comparison Program

a. Requirement Radioactive materials (which contain nuclides produced at the Stations), supplied as part of an Interlaboratory Comparison Program, shall be analyzed.
b. Action
1. Analyses shall be performed as follows:

Program Cross-Check of Milk 1131 , Gamma, K, Sr89 and Sr90 Water Gross Beta, Gamma, I 131 , H 3 (Tritium), Sr89 and Sr90 (blind-any combinations of above radionuclides)

Air Filter Gross Beta, Gamma, Sr90

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. Methodology and Results
1. Methodology and results of the cross-check program shall be maintained in the contractor-supplied Quality Control Manual.
2. Results shall be reported in the Annual Radiological Environmental Monitoring Report in accordance with VPAP-2802, Notifications and Reports.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE47 OF 140

  • 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 illclude:

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.
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 &hall 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 Attachment 15 or Attachment 16.
g. Discussion of analyses in which the lower limit of detection (LLD) required by Attachment 19 or Attachment 20 was not achievable.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 48 OF 140

6. 7.2 Annual Radioactive Effluent Release Report
a. Requirement - Station Radioactive Effluent Release Reports covering operation of the units during the 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:
1. 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 3.2.5]

[Commitment 3.2.6]

2. An assessment of radiation doses to the maximum exposed members of the public due to the radioactive liquid and gaseous effluents released from 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 Deviation Report and involve the discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release tank
  • 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
  • Unplanned releases as determined by Radiation Protection Supervision, which may or may not require a Deviation Report
4. Major changes to radioactive liquid, gaseous, and solid waste treatment systems during the reporting period.
5. Changes to VPAP-2103, Offsite Dose Calculation Manual (See 6.7.4).

_j

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 49 OF 140

6. A listing of new locations for dose calculations or environmental monitoring identified by the land use census (See 6.6.2).
b. Dose Assessment
1. Radiation dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.

Population doses shall not be included in dose assessments.

2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be 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.l, 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.

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."

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 Rep9rt for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Report. The Annual Radioactive Effluent Reports for Surry Station and Surry ISFSI are separate and not submitted as a combined report.

C. 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. (Surry)
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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 500F 140

3. Dose Assessment
  • Radiation dose to individuals due to radioactive liquid and gaseous effluents during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109. Population doses shall not be included in dose assessments
  • The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be 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. l, or 6.3.4.a.l, the dose assessment shall include the contribution from direct radiation
  • Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine gaseous pathway doses
6. 7.3 Annual Meteorological Data
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.

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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 51 OF 140

  • 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:
  • 40 CFR 190
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 the Management Safety Review Committee (MSRC) Cpordinator.

[Commitment 3.2.1]

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 52 OF 140 7.0 RECORDS 7.1 The following individual and packaged documents and copies 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 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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 53 OF 140 ATTACHMENT 1 (Page 1 of 1)

Surry 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 1
2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1-SW-RM-120 2 2 Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Effluent Line 1-SW-RM-107A 4 2 1-SW-RM-107B 1-SW-RM-107C 1-SW-RM-107D
3. FLOW RATE MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line Instrument Loop RLW-153 1 3 ACTION 1: -If the number of operable channels is less than required, effluent releases shall be suspended.

ACTION 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 Attachment 5, Surry Radioactive Liquid Waste Sampling and Analysis Program.

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 54 OF 140 Intentionally Blank I

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 55 OF 140

  • ATTACHMENT2 (Page 1 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation Minimum Operable Instrument Action Channels

1. .Liquid Radwaste Effluent (a) 1-RM-LW-111, Liquid Radwaste Effluent Monitor 1 1 (b) 1-LW-Ff-104, Liquid Radwaste Effluent Total Flow Measuring Device 1 2 (c) 1-LW-SOV-121, Clarifier Effluent Line Continuous Composite Sampler 1 1 Solenoid Valve (d) 1-LW-TK-20, Liquid Waste Effluent S~ple Vessel 1 1 (e) 1-LW-1130, Liquid Waste Effluent Proportional Sample Valve 1 1 (t) 1-RM-SW-108, Service Water Effluent Monitor 1 1 (g) 1-RM-SW-130, Unit 1 Circulating Water System Effluent Line Monitor 1 4 (h) 2-RM-SW-230, Unit 2 Circulating Water System Effluent Line Monitor 1 4
2. Tank Level Indicating Devices (Note 1)

(a) Refueling Water Storage Tanks Unit 1 1-QS-LT-lOOA 1 3 1-QS-LT-lOOB 1-QS-LT-lOOC 1-QS-LT-lOOD Unit2 2-QS-LT-200A 1 3 2-QS-LT-200B 2-QS-LT-200C 2-QS-LT-200D (b) Casing Cooling Storage Tanks Unit 1 1-RS-LT-103A 1 3 1-RS-LT-103:B Unit2 2-RS-LT-203A 1 3 2-RS-LT-203B (c) PG Water Storage Tanks (Note 2) 1-BR-LT-116A (1-PG-TK-lA) 1 3 1-BR-LT-116B (1-PG-TK-lB) 1 3 (d) Boron Recovery Test Tanks (Note 2) 1-BR-LT-112A (l-BR-TK-2A) 1 3 1-BR-LT-112B (l-BR-TK-2B) 1 3

3. Steam Generator High Capacity Blowdown (a) Steam Generator High Capacity Blowdown Radiation Monitor Unit 1 1-RM-SS-125 1 1 Unit2 2-RM-SS-225 1 1 (b) Steam Generator High Capacity Blowdown Flash Tanlc Outlet Flowrate Unit 1 1-BD-Ff-105 1 2 Unit2 2-BD-Ff-205 1 2 (c) Steam Generator High Capacity Blowdown Proportional Sampling Systerr Collection Tanlc Unit 1 1-BD-TK-4 1 1 Unit2 2-BD-TK-4 1 1

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 56 OF 140 ATTACHMENT2 (Page 2 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via this pathway may continue if, at least once within 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 gross radioactivity (beta and gamma) at an LLD of at least lxl0-7 µCi/g or an isotopic radioactivity at an LLD of at least 5x10-7 µCi/g.

ACTION 2: If the number of operable channels is less than required, effluent releases via this pathway may continue if 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 /> during actual releases. Design capacity performance curves generated in situ may be used to estimate flow.

ACTION 3: If the number of operable channels is less than required, liquid additions to this tank may continue if the tank liquid level is estimated during all liquid additions to the tank.

ACTION 4: If the number of operable channels is less than required, make repairs as soon as possible. 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 from the discharge canal are collected and analyzed for principal gamma emitters as defined in Attachment 6, North Anna Radioactive Liquid Waste *sampling and Analysis Program.

NOTE 1: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents, and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTE 2: This is a shared system between Unit 1 and Unit 2.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 57 OF 140

  • ATTACHMENT 3 (Page 1 of 1)

Surry Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel* Source Channel Channel Check* Cbeck 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 RADIOACTIV-lTY MONITORS PROVIDING ALARM BUT ,;,**

NOT PROVIDING AUTOMATIC TERMI-NATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1-SW-RM-120 D M R Q Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Eftlu entLine '

1-SW-RM-107A D M R .. Q 1-SW-RM-107B 1-SW-RM-107C 1-SW-RM-107D

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 58 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 59 OF 140 ATTACHMENT 4 (Page 1 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel Check Check Calibration Functional Test

1. Liquid Radwaste Effluent (a) 1-RM-LW-111, LiquidRadwasteEffluen~ Monitor D D R Q(NOIB 1)

(b) 1-LW-Ff-104, Liquid Radwaste Effluent Total Flow Measuring Device D(NOIB3) NIA R Q (c) 1-LW-SOV-121, Clarifier Effluent Line Continuous Composite Sampler Solenoid Valve NIA NIA NIA NIA (d) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel D(NOIB9) NIA NIA NIA (e) 1-LW-1130, Liquid Waste Effluent Proportional Sample Valve D(NOIB9) NIA NIA NIA (f) 1-RM-SW-108, Service Water System Effluent Monitor D M R Q(NOIB2)

(g) 1-RM-SW-130, Unit 1 Circulating Water System Effluent Line Monitor D M R Q(NOIB2)

(h) 2-RM-SW-230, Unit 2 Circulating Water System Effluent Line Monitor D M R Q(NOIB2)

2. Tank Level Indicating Device (NOIB 6)

(a) Refueling Water Storage Tanks Unit 1 1-QS-LT-lOOA, 1-QS-LT-lOOB 1-QS-LT-lOOC, 1-QS-LT-lOOD D(NOIB4) NIA R Q(NOIB7)

Unit2 2-QS-LT-200A, 2-QS-LT-200B 2-QS-LT-200C, 2-QS-LT-200D D(NOIB4) NIA R Q(NOIB7)

(b) Casing Cooling Storage Tanks Unit 1 1-RS-LT-103A, 1-RS-LT-103B D(NOIB4) NIA R Q(NOIB7)

Unit2 2-RS-LT-203A, 2-RS-LT-203B D(NOIB4)

  • NIA* R Q(NOIB7)

(c) PG Water Storage Tanks (NOIB 5) 1-BR-LT-116A (1-PG-TK-lA) D(NOIB4) NIA R Q(NOIB8) 1-BR-LT-116B (1-PG-TK-lB) D(NOIB4) NIA R Q(NOTE8)

(d) Boron Recovery Test Tanks (NOIB 5) 1-BR-LT-112A (1-BR-TK-2A) D(NOIB4) NIA R Q(NOIB8) 1-BR-LT-112B (l-BR-TK-2B) D(NOIB4) NIA R Q(NOIB8)

3. Steam Generator (SG) High Capacity Blowdown (a) SG High Capacity Blowdown Radiation Monitor Unit 1 1-RM-SS-125 Q(NOTE11)

Unit2 2-RM-SS-225 D(NOTE12) D(NOTE 12) R R(NOTE 10)

(b) SG High Capacity Blowdown Flash Tank Outlet Flowrate Unit 1 1-BD-Ff-105 D(NOTE 13) NIA R NIA Unit2 2-BD-Ff-205

  • (c) SG High Capacity Blowdown Proportional Sampling Systerr Collectior:i Tank Unit 1 1-BD-TK-4 Unit2 2-BD-TK-4 D (NOTE9) NIA NIA NIA

VIRGINIA VPAP-2103 POWER REV1SION9 PAGE 60 OF 140 ATTACHMENT 4 (Page 2 of 2)

  • North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:

aAutomatic isolation of this pathway and Control Room alarm annunciation occur if the instrument indicates measured levels above alarm/trip setpoint.

b.Alarm annunciation occurs if the instrument controls are not set in "operate" mode.

NOTE 2: The Channel Functional Test shall demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:

alnstrument indicates measured levels above the alann/trip setpoint.

b.Instrument controls not set in "operate" mode.

NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release. Channel Check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

NOTE 4: During liquid additions to the tank, verify indication of level change.

NOTE 5: This is a shared system between Unit 1 and Unit 2.

NOTE 6: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTE 7: The ChannelFunctional Test shall demonstrate that automatic isolation of this pathway and Control Room alarm annunciation occur if instrument indicates measured levels outside the alarm/trip setpoint. Demonstration of automatic isolation may consist of verifying the appropriate signal is generated. Valves need not be operated for this test.

NOTE 8: The Channel Functional Test shall demonstrate that Control Room alarm annunciation occurs if the instrument indicates measured levels are outside alarm setpoint.

NOTE 9: Channel Check shall consist of verifying that proportional flow exceeds 0.5 mls/gallon.

NOTE 10: Channel Functional Test shall demonstrate that system isolation occurs on a radiation monitor High-High Alarm.

NOTE 11: Channel Functional Test shall demonstrate:

a Trip signals are generated at the required setpoints. Isolation is not required.

b.Local radiation monitor indication occurs if instrument controls are not set in "Operate" mode or if the instrument indicates measured levels are above the alann/trip setpoint.

NOTE 12: The radiation monitor automatically performs periodic source checks. The Source Check and Channel Check are satisfied as long as the green light is lit.

NOTE 13: This is verified by indicated effluent flow less than or equal to 190 gpm.

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 61 OF 140

  • ATTACHMENT 5 (Page 1 of 3)

Surry Radioactive Liquid Waste Sampling and Analysis Program Lower Limit of Liquid Release Sampling Minimum Analy- Type of Activity Detection (LLD)

Type Frequency sis Frequency Analysis

(µCi/ml), (Note 1) p p Principle Gamma 5 X 10-1 Emitters (Note 3)

(Each Batch) (Each Batch) 1131 1 X 10-6 p Dissolved and Batch Releases M Entrained Gases 1 X 10-5 (One Batch/M)

(Gamma Emitters)

(Note 2) p MComposite H3 1 X 10-5 (Each Batch) (Note 4) Gross Alpha 1 X 10-1 p Q Composite Sr89 and Sr90 5 X 10-8 (Each Batch) (Note4) Fe55 1 X 10-6 Principal Gamma 5 X 10-1 Continuous WComposite Emitters (Note 6)

(Note 6) (Note 6) 1131 1 X 10-6 Dissolved and Continuous M 1 X 10-5 M Entrained Gases Releases Grab Sample (Gamma Emitters)

(Note 5) Continuous MComposite H3 1 X 10-5 (Note 6) (Note 6) Gross Alpha 1 X 10-7 Continuous QComposite Sr89 and Sr90 5 X 10-8 (Note 6) (Note 6) Fe55 1 X 10-6

VIRGINIA VPAP-2103

.POWER REVISiON9 PAGE 62 OF 140 ATTACHMENT 5 (Page 2 of3)

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

4.66 Sb LLD= (8-1)

E

  • V
  • 2.22E+06
  • Y
  • e-(1.,At)

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)

A = 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.

VIRGINIA VPAP.:.2103 POWER REVISI0N9 PAGE 63 OF 140

  • ATTACHMENT 5 (Page 3 of 3)

Surry Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn54, fe59 , Co58 ~ Co 60, Zn65 , Mo 99 , Cs 134, Cs 137 , Ce 141 , 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 to 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 64 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 65 OF 140

  • ATTACHMENT 6 (Page 1 of 3)

North Anna Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Minimum Analy- Type of Activity Lower Limit of Type Frequency

  • sis Frequency Analysis Detection (LLD)

(µCi/ml), (Note 1) p p Principle Gamma 5 X 10-7 Emitters (Note 3)

(Each Batch) (Each Batch) 1131 1 X 10-6 Batch Releases p M Dissolved and 1 X 10-S (One Batch/M) Entrained Gases (Gamma Emitters) (Note 8)

(Notes 2 and 7) p M Composite H3 1 X 10-S (Each Batch) (Note 4) Gross Alpha 1 X 10-7 p Q Composite Sr89 and Sr90 5 X 10-8 (Each Batch) (Note 4) Fess 1 X 10-6 Principal Gamma 5 X 10-7 Emitters (Note 6)

Continuous WComposite 1131 1 X 10-6 (Note 6) (Note 6)

Continuous lJISSOlved and 1 X 10-:,

Releases M Grab Sample Entrained Gases (Gamma Emitters) (Note 8)

(Note 5) Continuous M Composite H3 1 X 10-S (Note 6) (Note 6) Gross Alpha 1 X 10-7 Continuous Q Composite Sr89 and Sr90 5 X 10-8 (Note 6) (Note 6) Fess 1 X 10-6

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 66 OF 140 ATTACHMENT6 (Page2 of3)

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

4.66 Sb LLD (9-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (A,At)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (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)

A, = 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 then thoroughly mixed as the situation permits, to assure representative sampling.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 67 OF 140 ATTACHMENT 6 (Page 3 of 3)

North Anna Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn54, Fe59 , Co58, Co 60, Zn65 , Mo 99 , Cs 134, Cs 137 , Ce 141 , 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 to the quantity ofliquid 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, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releases.

NOTE 7: Whenever the secondary coolant activity exceeds 10-s µCi/ml, the turbine building sump pumps shall be placed in manual operation and samples shall be taken and analyzed prior to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 8: The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138. 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 68 OF 140 Intentionally Blank

__J

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 69 OF 140

  • ATTACHMENT 7 (Page 1 of 5)

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

Frequency (µCi/ml), (Note 1)

Prior to Release A. Waste Gas Prior to Release Principal Gamma (Each Tank) 1 X 10-4 Storage Tank (Each Tank) Emitters (Note 2)

(Grab Sample)

Principle Gamma Prior to Release Prior to Release 1 X 10-4 B. Containment Emitters (Note 2)

(Each PURGE) H3 Purge (Each PURGE) 1 X 10-6 (Grab Sample)

C. Ventilation Weekly Principle Gamma Weekly 1 X 10-4 (l)Process Vent (Grab Sample) Emitters (Note 2)

  • (2)Vent Vent#l (3)Vent Vent#2 (Note 3) (Note 3) H3 1 X 10-6 (4)SRF Vent 1131 1 X 10- 12 Continuous Weekly (Note 5)

(Note 4) (Charcoal Sample) 1133 1 X 10-lO Continuous Weekly (Note 5) Principal Gamma 1 X 10-ll All Release (Note 4) Particulate Sample Emitter (Note 2)

Weekly Continuous Types as listed Composite Gross Alpha 1 X 10-ll (Note 4)

Particulate Sample in A, B, and C Quarterly Continuous Composite Sr89 and Sr90 1 X 10-ll (Note 4)

Particulate Continuous Noble Gas Noble Gases Gross 1 X 10-6 (Note4) Monitor Beta and Gamma Principle Gamma Weekly Weekly 1 X 10-4 Condenser Air Emitters (Note 2)

Grab Sample (Note 3) H3 Ejector (Note 3) 1 X 10-6

VIRGINIA VPAP-2103 POWER REVISlON9 PAGE 70 OF 140 ATTACHMENT7 (Page 2 of 5)

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

Frequency (µCi/ml), (Note 1)

Principle Gamma 1 X 10-4 Prior to Release Prior to Release Emitters (Grab Sample) (Each Release) H3 1 X 10-6 1131 1 X 10-ll Continuous Charcoal Sample (Note 4) (Note 6) 1133 1 X 10-lO Containment Continuous Particulate Principal Gamma 1 X 10-lO HogDepres-(Note 4) Sample (Note 6) Emitter (Note 2) surization Composite Continuous 1 X 10-lO Particulate Gross Alpha (Note 4)

Sample (Note 6)

Composite Continuous Particulate Sr89 and Sr90 1 X 10-lO (Note 4)

Sample (Note 6)

VIRGINIA VPAP-2103 POWER REVISI0N9

.PAGE 71 OF 140 ATTACHMENT7 (Page 3 of 5)

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

LLD= (10-1)

E

  • V
  • 2.22E+06
  • Y
  • e-(A.At)

Where:

LLD = the "a priori (before the fact) Lower Limit of Detection as defined above (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 min1,1;te (dpm) per microcurie.

Y = the fractional radiochemical yield (when applicable).

A. = 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. .

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 72 OF 140 ATTACHMENT7 (Page 4 of 5)

Surry Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87 , Kr88 , Xe133 , Xe133m, Xe135 , Xe135m, and Xe 138 for gaseous emissions and Mn54, Fe59 , Co58 , Co 60, Zn65 , Mo 99 , Cs 134, Cs 137, Ce141 and Ce 144 for 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 I 131 concentration in the primary coolant has increased more than a factor of 3; and
b. The noble gas activity monitor 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 or dose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: 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 incre~sed by a factor of 10. This requirement applies if:

a. Analysis shows that the dose equivalent I 131 concentration in the primary coolant has increased by a factor of 3; and -.
b. Noble gas monitor shows that effluent activity has increased more than a factor of 3 .

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 73 OF 140

  • ATTACHMENT7 (Page 5 of 5)

Surry Radioactive Gase011s Waste Sampling and Analysis Program NOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseous effluents, composite sampling shall employ appropriate methods that will result in a specimen representative of the effluent release.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 74 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 75 OF 140

  • ATTACHMENT 8 (Page 1 of 4)

North Anna Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Type of Activity Lower Limit of Type Frequency Analysis

  • Analysis Detection (LLD)

Frequency (µCi/ml), (Note 1)

Prior to Release A. Waste Gas Prior to Release Principal Gamma 1 X 10-4 (Each Tanlc Storage Tank (Each Tanlc) Emitters (Note 2)

Grab Sample)

Principle Gamma Prior to Release Prior to Release 1 X 10-4 B. Containment Emitters (Note 2)

(Each PURGE Purge (Each PURGE) H3 1 X 10-6 Grab Sample)

C. Ventilation Monthly Principle Gamma Monthly 1 X 10-4 (1) Process Vent (Grab Sample) Emitters (Note 2)

(2) Vent Vent A (Notes 3, 4, and (Note 3) H3 1 X 10-6 (3) Vent Vent B 5)

Weekly 1131 1 X 10- 12 Continuous (Note4) (Charcoal Sample) 1133 1 X 10-lO '

Continuous Weekly Principal Gamma 1 X 10-ll All Release (Note 4) Particulate Sample Emitter (Note 2)

Monthly Continuous 1 X 10-ll Types as listed Composite Gross Alpha (Note 4)

Particulate Sample in A, B, and C Quarterly Continuous Composite Sr89 and Sr90 1 X 10-ll (Note4)

Particulate Continuous Noble Gas Noble Gases Gross 1 X 10-ti (Note 4) Monitor Beta or Gamma Condenser Air Principle Gamma Weekly Weekly 1 X 10-4 Ejector/Steam Emitters (Note 7)

Generator Grab Sample H3 1 X 10-6 Blowdown Vent (Note 6)

Containment Principle Gamma 1 X 10-4 Prior to Release Prior to each Vacuum Steam Emitters (Note 2)

Ejector (Hogger) (Grab Sample)

Release H3 1 X 10-6 (Note 8)

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 76 OF 140 ATTACHMENT 8 (Page 2 of 4)

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

4.66 Sb LLD (11-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (1.,At)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (as microcuries per unit mass or volume) (See 4.9)

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 2.22E+o6 y

=

=

=

the sample size (in units of mass or volume) the number of disintegrations per minute (dpm) per microcurie the fractional radiochemical yield (when applicable)

A, = 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 as "posteriori" (after the fact) limit for a particular measurement.

__J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 77 OF 140 ATTACHMENT 8 (Page 3 of 4)

North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87 , Kr88 , Xe133 , Xe133 m, Xe135 , Xe 135m, and Xe 138 for gaseous emissions and Mn54, Fe59 , Co58 , Co 60, Zn65 , Mo99 , Cs 134, Cs 137, Ce141 and Ce 144 for particulate emissions. 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 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, if:

a. Analysis shows that the dose equivalent I 131 concentration in the primary coolant is greater than 1.0 µCi/gm; and
b. The noble gas activity monitor 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 or dos~rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: 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 ltours 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 I 131 concentration in the primary coolant is greater than 1.0 µCi/gm and;
b. Noble gas monitor shows that effluent activity has increased more than a factor of 3 .

VIRGINIA VPAP-2103

. POWER REVISI0N9 PAGE 78 OF 140 ATTACHMENT 8 (Page 4 of 4)

North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 6: Whenever the secondary coolant activity exceeds 10-5 µCi/ml, samples shall be obtained and analyzed weekly. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 7: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87 , Kr88 , Xe133 , :X:e 133 m, Xe135 , Xe i 35m, and Xe 138 for gaseous emissions. 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 8: If the secondary coolant activity level in any Steam Generator supplying steam to the Hogger exceeds 1.0E-5 µCi/ml, Steam Generator samples shall be obtained and analyzed prior to release.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 79 OF 140

  • ATTACHMENT 9 (Page 1 of 3)

Gaseous Effluent Dose Factors for North Anna (Gamma and Beta Dose Factors)

'X)Q = 9.3E-06 sec/m3 at 1416 meters SE Direction Dose Factors for Ventilation Vent Noble Gas Kivv 4vv Mivv Nivv Radionuclide Total Body Skin GammaAir Beta Air mrem/yr mrem/yr mrad/yr mrad/yr Curie/sec Curie/sec Curie/sec Curie/sec

- Kr-85m 1.09E+04 1.36E+04 1.14E+04 1.83E+04 Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E+04 Kr-87 5.51E+04 9.05E+04 5.74E+04 9.58E+o4*

Kr-88 1.37E+05 2.20E+04 1.41E+05 2.72E+04 Kr-89 1.54E+05 9.39E+04 1.61E+05 9.86E+04 Xe-131m 8.51E+02 4.43E+03 1.45E+03 1.03E+04 Xe-133m 2.33E+03 9.24E+03 3.04E+03 1.38E+04

  • Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 Xe-135 1.68E+04 1.73E+04 1.79E+04 2.29E+04 Xe-137 l.32E+04 1.13E+05 1.40E+04 l.18E+05 Xe-138 8.21E+04 3.84E+04 8.57E+04
  • 4.42E+04 Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04

VIRGINIA VPAP-2103

.POWER REVISI0N9 PAGE 80 OF 140 ATTACHMENT 9 (Page 2 of 3)

Gaseous Effluent Dose Factors for North Anna (Gamma and Beta Dose Factors) rJQ = l.2E-06 sec/m3 at 1513 meters S Direction Dose Factors for Process Vent Noble Gas Kipv Lipv Mipv Nipv Radionuclide Total Body Skin Gamma Air Beta Air mrem/yr mrem/yr mrad/yr mrad/yr Curie/sec Curie/sec Curie/sec Curie/sec Kr-85m 1.40E+03 1.75E+03 1.48E+03 2.36E+03 Kr-85 1.93E+Ol 1.61E+03 2.06E+Ol 2.34E+03 Kr-87 7.10E+03 1.17E+04 7.40E+03 1.24E+04 Kr-88 1.76E+04 2.84E+03 l.82E+04 3.52E+03 Kr-89 1.99E+04 l.21E+04 2.08E+04 1.27E+04 Xe-131m 1.10E+02 5.71E+02 1.87E+02 1.33E+03 Xe-133m 3.01E+02 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67E+02 4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23E+03 2.30E+03 2.95E+03 Xe-137 1.70E+03 1.46E+04 1.81E+03 l.52E+04 Xe-138 1.06E+04 4.96E+03 1.11E+o4 5.70E+03 Ar-41 1.06E+04 3.23E+03 1.12E+04 3.94E+03

VIRGINIA VPAP-2103 POWER REVIS10N9 PAGE 81 OF 140

  • ATTACHMENT9 (Page 3 of 3)

Gaseous Effluent Dose Factors for North Anna (Inhalation Pathway Dose Factors)

Ventilation Vent xJQ = 9.3E-06 sec/m3 at 1416 meters SE Direction Process Vent x/Q = 1.2E-06 sec/m3 at 1513 meters S Direction Radionuclide Ptvv Pipv mrem/yr mrem/yr Curie/sec Curie/sec H-3 1.05E+04 1.35E+03 Cr-51 7.95E+02 1.02E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND ..

Co-60 ND . ND Zn-65 ND ND Rb-86 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 5.64E+04 7.28E+03 Te-129m 5.88E+04 7.59E+03 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND 1-131 1.51E+08 1.95E+07 1-133 3.58E+07 4.62E+06 ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 82 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 83 OF 140

  • ATTACHMENT 10 (Page 1 of 3)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1-GW-RM-102 1 1 l-GW-RM-130-1 (b) Iodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM-130-1 1 2 (c) Particulate Sampler Process Vent Continuous HP Sampler, or 1 2 1-GW-RM-130-1 (d) Process Vent Flow Rate Monitor l-GW-FT-100 1 3 (e) Sampler Flow Rate Measuring Device KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer
2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1-SV-RM-111 2 (one per unit) 1 2-SV-RM-211 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-lA 1-VP-FI-lB 2 (one per unit) 3 Unit 2: 2-VP-FI-lA 2-VP-FI-lB
3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 1 1 SPS: Vent #l l-VG-RM-104 1 1 Vent #2, 1-VG-RM -110, or 1 1 1-VG-RM-131-1

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 84 OF 140 ATTACHMENT 10 (Page 2 of 3)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS (b) Iodine Sampler SRF: RRM-101 1 2 SPS: Vent#l, 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#l, VG-RM-104 1 2 Vent#2, HP Continuous Sampler, or 1 2 l-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: 01-RHV-FT-156 1 3 SPS: Vent#l, l-VS-FT-119 1 3 Vent#2, 1-VS-FT-116 1 3 (e) Sampler Flow Rate Measuring Device SRF: RRM-101 1 3 SPS: Vent#l, 1-VG-RM-104 1 3 Vent #2, KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer J

VIRGINIA.* VPAP-2103 POWER REVISION9 PAGE 85 OF 140 ATTACHMENT 10 (Page 3 of 3) .

Surry Radioactive Gaseous Effluent Monitoring Instrumentation ACTION 1: If the number of operable cha11nels 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 slampling equipment as required in Attachment 7. I*

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 />.

VIRGINIA VPAP-2103 POWER REV1SION9 PAGE 86 OF 140 I Intentionally Blank I

_J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 87 OF 140

  • ATTACHMENT 11 (Page 1 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM ACTION OPERABLE CHANNELS

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor 1-RM-GW-102 1 1-RM-GW-178-1 2,4 (NOTE 3)

(b) Iodine Sampler 1-RM-GW-178-1 1 Process Vent Continuous HP Sampler 2,5 (NOTE 3)

(c) Particulate Sampler 1-RM-GW-178-1 1 Process Vent Continuous HP Sampler 2,5 (NOTE 3)

(d) Total Flow Monitor 1-GW-Ff-108 1 1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Pevice (Parameter 19) 1 HP Sampler Rotameter 1 (NOTE 3)

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor Unit 1 1-SV-RM-121 Unit2 2-SV-RM-221 1 3 (b) Flow Rate Measuring Device Unit 1 1-SV-FI-lOOA 1-SV-FI-lOlA 1-SV-FI-lOOB 1 (NOTE 1) 1 1-SV-FI-lOlB Unit2 2-SV-FI-200A 2-SV-FI-201A 2-SV-FI-200B 1 (NOTE2) 1 2-SV-FI-201B

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 88 OF 140 ATTACHMENT 11 (Page 2 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS

3. VENTILATION VENT A (a) Noble Gas Activity Monitor 1-RM-VG-104 1 1-RM-VG-179-1 2 (NOTE 3)

(b) Iodine Sampler 1-RM-VG-179-1 1 Vent Vent A Continuous HP Sampler 2 (NOTE 3)

(c) Particulate Sampler l-RM-VG-179-1 1 Vent Vent A Continuous HP Sampler 2 (NOTE 3) I (d) Total Flow Monitor 1-HV-Ff-1212A 1 1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19) 1 HP Sampler Rotameter 1

(NOTE3)

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-113 1 l-RM-VG-180-1 2 (NOTE 3)

(b) Iodine Sampler 1-RM-VG-180-1 1 2

Vent VentB Continuous HP Sampler (NOTE 3)

(c) Particulate Sampler l-RM-VG-180-1 1 2

Vent Vent B Continuous HP Sampler (NOTE 3)

(d) Total Flow Monitor 1-HV-Ff-1212B 1 1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19) 1 HP Sampler Rotameter 1

NOTE3

VIRGINIA VPAP-2103 POWER. REVISI0N9 PAGE 89 OF 140

  • ATTACHMENT 11 (Page 3 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases, via this path, may continue if the flow rate is estimated at least once per four hours.

ACTION 2: If the number of operable channels is less than required, effluent releases, via this path, may continue if 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 or ~amma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 3: If the number of operable channels is less than required, effluent releases, via this path, may continue if the frequency of the grab samples provided by Technical Specification requirement 4.4.6.3. bis incre~sed to at least once per four hours and these samples are analyzed for gross activity or gamma isotopic activity within eight hours.

ACTION 4: If the number of operable channels is less than required, the contents of the Waste Gas Decay Tanks may be released to the environment provided that prior to initiation of the release:

a. At least two independent samples of the tank's contents are analyzed, and:
b. At least two technically qualified members of the Station staff independently verify the release rate calculations and discharge valve lineup.

ACTION 5: If the number of operable channels is less than required,. effluent releases from the Waste Gas Decay Tank may continue provided samples are continuously collected with auxiliary sampling equipment as required in Attachment 8.

NOTE 1: A channel shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (1-SV-FI-lOOA, 101A), or Train B (1-SV-FI-lOOB, 101B) or both.
b. Flow instruments 10 lA and 10 lB provide low range measurement Flow instruments 100A and 100B provide high range measurement.

NOTE 2: A channef shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (2-SV-FI-200A, 201A), or Train B (2-SV-FI-200B, 201B) or both.
b. Flow instruments 20 IA and 20 lB provide low range measurement Flow instruments 200A and 200B provide high range m~~surement.

NOTE 3: A channel shall consist of either the release pathway's Kaman monitor, its associated iodine and particulate sampler and sampler flowrate measuring device or the release pathway's

  • Westinghouse monitor, HP iodine and particulate monitor and HP Sampler Rouµneter.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 90 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 91 OF 140

  • ATTACHMENT 12 (Page 1 of 2)

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

1. PRucESS V.bNl SY:HEM (a) Noble Gas Activity Monitor-Providing Alann and Automatic Tennination of Release l-GW-RM-102 D M,* R Q 1-GW-RM-130-1 (b) Iodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM-130-1 w NIA NIA NIA (c) Particulate Sampler Process Vent Continuous HP Sampler, or 1-GW-RM-130-1 W* NIA NIA NIA (d) Process Vent Flow Rate Monitor l-GW-Ff-100 D NIA R NIA (e) Sampler Flow Rate Measuring Device HP Sampler Rotometer, or D NIA SA NIA KAMAN Flow Rate Measuring D NIA R NIA Device (Parameter #19)
2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor Unit 1: l-SV-RM-111 D M R Q Unit 2: 2-SV-RM-211 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-lA 1-VP-FI-lB Unit 2: 2-VP-FI-lA D NIA R NIA 2-VP-FI-lB
3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 SPS: 1-VG-RM-110 D M R Q l-VG-RM-131-1 l-VG-RM-104

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 92 OF 140 ATTACHMENT 12 (Page 2 of2)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL TEST (b) Iodine Sampler SRF: RRM-101 SPS: Vent#l, 1-VG-RM-104 Vent#2,ContinuousHP w NIA NIA NIA Sampler or 1-VG-RM-131-1 (c) Particulate Sampler SRF: RRM-101 SPS: Vent#l, 1-VG-RM-104 Vent#2,ContinuousHP w NIA NIA NIA Sampler or 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: 01-RHV-FT-156 SPS: Vent#l, 1-VS-FT-119 Vent#2, 1-VS-FT-116 D NIA R NIA

, (e) Sampler Flow Rate Measuring Device SRF: RRM-101 D NIA R NIA SPS: Vent#l, 1-VG-RM-104 D NIA R NIA Vent#2, KAMAN Flow Rate D NIA R NIA Measuring Device (Parameter#19), or HP D NIA NIA Sampler Rotometer SIA

>jC Prior to each waste Uas Vecay Tank release J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 93 OF 140

  • ATTACHMENT 13 (Page 1 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL

_DESCRIPTION CHECK CHE.CK CALIBRATION FUNCTIONAL TEST

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor 1-RM-GW-102 D M R Q (NOTE 1) 1-RM-GW-178-1 D M(NOTE5) R Q (NOTE 1)

(b) Iodine Sampler 1-RM-GW-178-1 w NIA NIA NIA Process Vent Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-GW-178-1 w NIA NIA NIA Process Vent Continuous HP Sampler D(NOTE3) NIA NIA NIA (d) Total Flow Monitor l-GW-Fr-108 D NIA R Q (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE3) NIA R NIA Device (Parameter 19)

HP Sampler Rotameter D(NOTE3) NIA SA NIA

2. CONDENSER AIR EJECTOR SYSTEM (a) Noble Gas Activity Monitor Unit 11-SV-RM-121 D M R Q (NOTE 1)

Unit 2 2-SV-RM-221 (b) Flow Rate Measuring Device Unit 1 1-SV-Fl-lOOA 1-SV-Fl-lOlA 1-SV-FI-lOOB D NIA R NIA 1-SV-Fl-lOlB Unit2 2-SV-Fl-200A

  • 2-SV-FI-201A 2-SV-Fl-200B 2-SV-Fl-201B D NIA R NIA

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 94 OF 140 ATTACHMENT 13 (Page 2 of 3)

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

3. VENTILATIONVENT A (a) Noble Gas Activity Monitor 1-RM-VG-104 D M R Q(NOTE2) 1-RM-VG-179-1 D M(NOTE5) R Q(NOTE2)

(b) Iodine Sampler 1-RM-VG-179-1 w NIA NIA . NIA Vent Vent A Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-VG-179-1 w NIA NIA NIA Vent Vent A Continuous HP Sampler D(NOTE3) NIA NIA NIA (d) Total Flow Monitor 1-HV-FI'-1212A (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19)

HP Sampler Rotameter D

D(NOTE3)

D(NOTE3)

NIA NIA NIA R

R SA Q

NIA NIA

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-113 D M R Q(NOTE4) 1-RM-VG-180-1 D M(NOTE5) R Q(NOTE2)

(b) Iodine Sampler 1-RM-VG-180-1 w NIA NIA NIA Vent Vent B Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-VG-180-1 w NIA NIA NIA Vent Vent B Continuous HP Sampler D(NOTE3) NIA NIA NIA (d) Total Flow Monitor 1-HV-FI'-1212B D NIA R Q (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE3) NIA R NIA Device (Parameter 19)

HP Sampler Rotameter D(NOTE3) NIA SA NIA J

VIRGINIA* VPAP-2103 POWER REVIS10N9 PAGE 95 OF 140 ATTACHMENT 13 (Page 3 of 3)

North Anna Radioactive Gaseous Effluent Monitoring InstrumentationSurveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:

}

a. Automatic actuation of the valves in this pathway and Control Room alarm annunciation occur if the instrument indicates measured levels above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instrument controls not set in "operate" mode.

NOTE 2: The Channel Functional Test sh~ demonstrate:

a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instrument controls not set in "operate" mode.

NOTE 3: Channel Checks shall consist of verifying indication of flow during periods of release.

Ch~nnel Checks shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

NOTE 4: The Channel Functional Test shall demonstrate that:

a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above alarm/trip setpoint
b. The Instrument mode selection control automatically resets to "operate" mode when released.

NOTE 5: Monitors 1-RM-GW-178-1, 1-RM-VG-179-1, and 1-RM-VG-180-1 are electronically source checked using an LED.

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.VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 97 OF 140

  • ATTACHMENT 14 (Page 1 of 1)

Critical Organ Dose Factors for North Anna (Critic~ Pathway Dose Factors)

Ventilation Vent D/Q = 2.4E-09 m*2 at 3250 meters N Direction Process Vent D/Q = 1.lE-09 m*2 at 3250 meters N Direction Radionuclide RMivv RMipv mrern/yr mrem/yr Curie/sec Curie/sec H-3 1.73E+03 9.36E+02 Mn-54 ND ND Fe-59 ND ND Cr-51 1.50E+02 6.89E+Ol Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 1.97E+05 9.04E+04 Te-129m 2.95E+05 1.35E+05 I-131 1.45E+09 6.72E+08 I-133 1.33E+07 6.12E+06 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND

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VIRGINIA VPAP-2103.

POWER REVISI0N9 PAGE 99 OF 140

  • ATTACHMENT IS (Page 1 of 3)

Surry 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 Monitoring Stations to be placed as follows:
1) Inner Ring in general area of site boundary with station in each GAMMA DOSE sector
2) Outer Ring 6 to 8 km from the site with a Quarterly Quarterly station in each sector
3) The balance of the 8 dosimeters should be placed in special interest areas such as population centers, nearby residents, schools, and in 2 or 3 areas to serve as controls
2. AIRBORNE Samples from 7 locations:

a) 1 sample from close to the site boundary location of the highest Radioiodine Canister calculated annual 1131 Analysis Weekly average ground level Continuous Radioiodines and D/Q Sampler Particulates b) 5 sample locations 6-8 operation with Particulate 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 15-30 km Gamma isotopic analysis distant, providing valid of composite (by background data location) quarterly

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 100 OF 140 ATTACHMENT 15 (Page 2 of 3)

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

3. WATERBORNE Gamma isotopic analysis a) 1 sample upstream monthly; a) Surface Monthly Sample b) 1 sample downstream Composite for tritium analysis quarterly Sample from 1 or 2 sources Gamma isotopic and tritium b) Ground Quarterly analysis quarterly c) Sediment a) 1 sample upstream Gamma isotopic analysis from Semi-Annually b) 1 sample downstream semi-annually shoreline 2 samples from vicinity of Gamma isotopic analysis d) Silt Semi-Annually the Station
  • semi-annually
4. INGESTION a) Milk a) 3 samples from milking animals in the vicinity of Composite for Sr89/Sr90 (NOTE 1) the Station analysis quarterly b) 1 sample from milking Monthly animals at a control Gamma isotopic and I 131 location (15-30 km analysis monthly distant) a) 2 samples of oysters in the vicinity of the Semi-Annually Gamma isotopic on edibles Station b) 4 samples of clams in the vicinity of the Semi-Annually Gamma isotopic on edibles b) Fish and Station Invertebrates c) 1 sampling of crabs from the vicinity of the Annually Gamma isotopic on edibles Station d) 2 samples of fish from the vicinity of the Semi-Annually Gamma isotopic on edibles Station (catfish, white perch, eel)

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 101 OF 140

  • ATTACHMENT 15 (Page 3 of 3)

Surry Radiological Environmental Monitoring Program 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 portion c) 1 sample peanuts d) 1 sample of a broadleaf vegetation of two different available offsite locations with highest annual average c) Food ground level D/Q, if one Products or more milk samples Monthly, if Gamma isotopic and I 131 are unavailable available, or at analysis e) 1 sample of a broadleaf harvest vegetation grown 15-30 kmin the available, least prevalent wind direction, if one or more milk samples are unavailable NOTE 1: If milk sampling cannot be performed, use item 4.c (d) .

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VIRGINIA VPAP-2103 POWER REVISION9 PAGE 103 OF 140 ATTACHMENT 16 (Page 1 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2) Frequency Analysis

1. DIRECT RADIATION (NOTE3) 36 routine monitoring stations, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:
1) An inner ring of stations, one in each emergency GAMMA DOSE meteorological sector within the site boundary
2) An outer ring of stations, one in each emergency Quarterly Quarterly meteorological sector within 8 km range from the site
3) The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 104 OF 140 ATTACHMENT 16 (Page 2 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2) Frequency Analysis

2. AIRBORNE Samples from 5 locations:

a) 3 samples from close to the 3 site boundary locations (in different sectors) of the highest Radioiodine Canister calculated historical 1131 Analysis, weekly annual average ground Continuous Radioiodines and levelD/Q sampler, Particulates b) 1 sample from the operation with vicinity of a community sample Particulate Sampler having the highest collection Gross beta radioactivity calculated annual weekly analysis following filter average ground level change; (NOTE 4)

DJQ c) 1 sample from a control Gamma isotopic analysis location 15-40 km of composite (by distant and in the least location) quarterly prevalent wind directio11 (NOTE 5)

3. WATERBORNE Samples from 3 locations:

Gamma isotopic analysis a) 1 sample upstream monthly; (NOTE 5) a) Surface b) 1 sample downstream Grab Monthly Composite for tritium c) 1 sample from cooling analysis quarterly lagoon Sample from 1 or 2 sources Gamma isotopic and tritium b) Ground only if likely to be affected Grab Quarterly analysis quarterly (NOTE 5) 1 sample from downstream area with existing or Gamma isotopic analysis c) Sediment Semi-Annually semi-annually (NOTE 5) potential recreational value

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 105 OF 140 ATTACHMENT 16 (Page 3 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Sample Collection Type and Frequency of and/or Sample Location (NOTE 2) Frequency Analysis

4. INGESTION a) Samples from milking animals in 3 locations wit}lin 5 km that have the highest potential. If there are none, then 1 sample from milki.tig animals in each of 3 areas a) Milk between 5 to 8 km where Monthly at all Gamma isotopic (NOTE 5)

(NOTE 7) doses are calculated to be times and 1131 analysis monthly greater than 1 mrem per yr (NOTE6) b) 1 sample from milking animals at a control location (15-30 km in the least prevalent wind direction) a) 1 sample of commercially and recreationally important species(bass,sunfish,catfish) b) Fish and in vicinity of plant discharge Gamma isotopic on edible Semiannually Invertebrates area portions b) 1 sample of same species in areas not influenced by plant discharge a) Samples of an edible broad leaf vegetation grown nearest each of two different offsite locations of highest predicted historical annual average Monthly if c) Food ground level D/Q if milk Gamma isotopic (NOTE 5) available, or Products sampling is not performed and I 131 analysis at harvest b) 1 sample of broad leaf vegetation grown 15-30kmin the least prevalent wind direction if milk sampling is not performed

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 106 OF 140 ATTACHMENT 16 (Page 4 of 5)

North Anna Radiological Environmental Monitoring Program NOTE 1: The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable.

Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and be included in the sampling program.

NOTE 2: For each and every sample location in Attachment 18, specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, shall be provided in Attachment 18. Refer to Radiological Assessment Branch Technical Positions and to NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plant. Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous _conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

If specimens are unattainable due to sampling equipment malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to 6.7 .1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to 6.7 .2, identify the cause of the unavailability of samples for that pathway and identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report.

J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 107 OF 140 ATTACHMENT 16 (Page 5 of 5)

North Anna Radiological Environmental Monitoring Program NOTE 3: One or more instruments, s~ch a.s a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a thepnoluminescent dosimeter (TLI>) is considered to be one phosphor; two or more phosphors in apacket are considered as two or more dosimeters.

Film badges shall not be used as qosimeters for measuring direct radiation. The 36 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be. reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with ~ a l fading.

NOTE 4: Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

  • NOTE 5: Gamma isotopic analysis is the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from the facility.

NOTE 6: The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

NOTE 7: If milk sampling cannot be performed, use item 4.c (Page 3 of 5, Attachment 16).

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VIRGINIA VPAP-2103 POWER REVISION9 PAGE 109 OF 140 ATTACHMENT 17 (Page 1 of 4)

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

Air Charcoal Site Boundary and Particulate Surry Station .(SS) 0.37 NNE Location at Sector with Highest D/Q Hog Island Reserve (HIR) 2.0 NNE Bacons Castle (BC) 4.5 SSW Alliance (ALL) -5.1 WSW Colonial Parkway (CP) 3.7 NNW Dow Chemical (DOW) 5.1 ENE Fort Eustis (FE) 4.8 ESE Newport News (NN) 16.5 ESE Control Location Environmental Control (00) Onsite **

TLDs West North West (02) 0.17 WNW Site Boundary Surry Station Discharge (03) 0.6 NW Site Boundary North North West (04) 0.4 NNW Site Boundary North (05) 0.29 N Site Boundary North North East (06) 0.28 NNE Site Boundary North East (07) 0.31 NE Site Boundary East North East (08) 0.43 ENE Site Boundary East (Exclusion) (09) 0.31 E Exclusion Area Boundary West (10) 0.40 w Site Boundary West South West (11) 0.45 WSW Site Boundary South West (12) 0.30 SW Site Boundary South South West (13) 0.43 SSW Site Boundary South (14) 0.48 s Site Boundary South South East (15)- 0.74 SSE Site Boundary South East (16) 1.00 SE Site Boundary East (17) 0.57 E Site Boundary Station Intake (18) 1.23 ESE Site Boundary Hog Island Reserve (19) 1.94 NNE Near Resident

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 110 OF 140 ATTACHMENT 17 (Page 2 of 4)

Surry Environmental Sampling Locations SAMPLE LOCATION DISTANCE DffiECTION REMARKS MEDIA (MILES)

Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21) 5.0 SW Approx. 5 miles Alliance (22) 5.1 WSW Approx. 5 miles Surry (23) 8.0 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) 3.7 NNW Approx. 5 miles Route 617 and 618 (28) 4.7 NNW Approx. 5 miles Kingsmill (29) 4.8 N Approx. 5 miles Williamsburg (30) 7.8 N Population Center Kingsmill North (31) 5.6 NNE Approx. 5 miles Budweiser (32) 5.7 NNE Population Center Water Plant (33) 4.8 NE Approx. 5 miles Dow (34) 5.1 ENE Approx. 5 miles Lee Hall (35) 7.1 ENE Population Center Goose Island (36) 5.0 E Approx. 5 miles Fort Eustis (37) 4.8 ESE Approx. 5 miles Newport News (38) 16.5 ESE Population Center James River Bridge (39) 14.8 SSE Control Benn's Church (40) 14.5 s Control Smithfield (41) 11.5 s Control Rushmere (42) 5.2 SSE Approx. 5 miles Route 628 (43) 5.0 s Approx. 5 miles Milk Epp's 4.8 SSW Colonial Parkway 3.7 NNW Judkin's 6.2 SSW Pivarnik 21.5 NE Control Location

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 111 OF 140 ATTACHMENT 17 (Page 3 of 4)

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

Well Water Surry Station Onsite***

Hog Island Reserve 2.0 NNE Crops (Com, s Slade's Farm 2.4 Peanuts, Soybeans) Brock's Farm 3.8 s Crops Spratley's Garden 3.2 s (Cabbage, Kale) Carter's Grove Garden. 4.8 NE Control Location Lucas's Garden (Chester, Va.)

River Water Surry Discharge 0.17 NW (Monthly) Scotland Wharf 5.0 WNW Control Location Sediment Chickahominy River 11.2 WNW Control Location (Silt) Surry Station Discharge 1.0 NW

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 112 OF 140 ATTACHMENT 17 (Page 4 of 4)

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

Clams Chickahominy River 11.2 WNW Control Location Surry Station Discharge 1.3 NW Hog Island Point 2.4 NNE Lawne's Creek 2.4 SE Oysters Kingsmill 2.9 NNE Mulberry Point 4.9 SE Crabs Surry Station Discharge 0.6 NW Fish Surry Station Discharge 0.6 NW Shoreline Hog Island Reserve 0.8 N Sediment Chickahominy River 11.2 WNW Control Location

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 113 OF 140

  • ATTACHMENT 18 (Page 1 of 4)

Nor.th Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction. Collection REMARKS Media No. (Miles) Frequency Environment NAPS Sewage Treatment Quarterly &

01 0.20 NE On-Site al Plant Annually TLDs Frederick's Hall 02 5.30 SSW Quarterly &

Annually Mineral,VA 03 7.10 WSW Quarterly &

Annually Wares Crossroads 04 5.10 WNW Quarterly &

Annually Route 752 4.20 NNE Quarterly &

05 Annually Sturgeon's Creek Marina 05A N Quarterly &.

3.20 Annually, ,

Levy.VA 06 4.70 ESE Qmµ1erly&

Annually

  • Bumpass, VA 07 7.30 SSE Quarterly &

Annually End of Route 685 21 1.00 WNW Quarterly & Site Boundary*

Annually Route 700 22 1.00 WSW Quarterly & Site Boundary Annually "Aspen Hills" 23 0.93 SSE Quarterly & Site Boundary Annually Orange, VA 24 22.00 NW Quarterly & Control Annually Bearing Cooling Tower I N-1/33 0.06 N Quarterly On-Site Sturgeon's Creek Marina . N-2/34 3.20 N Quarterly Parking Lot "C" NNE-3/35 0.24 NNE Quarterly On-Site Good Hope Church NNE-4/36 4.96 NNE Quarterly Parking Lot "B" NE-5/37 0.20 NE Quarterly On-Site Bogg'sDrive NE-6/38 1.46 NE Quarterly Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-Site Route 689 ENE-8/40 2.43 ENE Quarterly Near Training .Facility E-9/41 0.30 E Quarterly On-Site "Morning Glory Hill" E-10/42 2.85 E Quarterly Island Dike ESE-11/43 0.12 ESE Quarterly On-Site Route 622 ESE-12/44 4.70 ESE Quarterly

VIRGINIA VPAP-2103

  • .. POWER REVISI0N9 PAGE 114 OF 140 ATTACHMENT 18 (Page 2 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Frequency Environment Biology Lab SE-13/45 0.75 SE Quarterly On-Site al TLDs Route 701 (Dam Entrance SE-14/46 5.88 SE Quarterly "Aspen Hills" SSE-15/47 0.93 SSE Quarterly Site Bound311 Elk Creek SSE-16/48 2.33 SSE Quarterly NAPS Access Road S-17/49 0.47 s Quarterly On-Site Elk Creek Church S-18/50 1.55 *. s Quarterly NAPS Access Road SSW-19/51 0.42 SSW Quarterly On-Site Route 618 SSW-20/52 5.30 SSW Quarterly 500KVTower SW-21/53 0.60 SW Quarterly On-Site Route 700 SW-22/54 4.36 SW Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW Quarterly On-Site Route700 WSW-24/56 1.00 WSW Quarterly Site Boundary South Gate of Switchyard W-25/57 0.32 w Quarterly On-Site Route 685 W-26/58 1.55 w Quarterly End of Route 685 WNW-27/59 1.00 WNW Quarterly Site Boundary Route 685 WNW-28/60 1.40 WNW Quarterly LaydownArea North Gate NW-29/61 0.45. NW Quarterly On-Site Lake Anna Campground NW-30/62 2.54 NW Quarterly

  1. 1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-Site Route208 NNW-32/64 3.43 NNW Quarterly Bumpass Post Office C-1/2 7.30 SSE Quarterly Control Orange;VA C-3/4 22.00 NW Quarterly Control Mineral, VA C-5/6 7.10 WSW
  • Quarterly Control Louisa, VA C-7/8 11.54 WSW Quarterly Control

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 115 OF 140

  • ATTACHMENT 18 (Page 3 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Frequency Airborne NAPS Sewage Treatment 01 0.20 NE Weekly On-Site Plant Particulate Frederick's Hall 02 5.30 SSW Weekly and Mineral, VA 03 7.10 WSW Weekly Radioiodine Wares Crossroads 04 5.10 WNW Weekly Route 752 05 4.20 NNE Weekly.

Sturgeon's Creek Marina 05A 3.20 N Weekly Levy, VA 06 4.70 ESE Weekly Bumpass, VA 07 7.30 SSE Weekly End of Route 685 21 1.00 WNW Weekly

  • Site Boundary Route 700 22 1.00 WSW Weekly:
  • Site Boundary "Aspen Hills" 23 0.93 SSE Weekly Site Boundary 24 22.00 NW Weekly Control Oran~e. VA Surface Water Waste Heat Treatment

[Commitment Facility (Second Cooling 08 1.10 SSE Monthly 3.2.2] Lagoon)

North Anna River (upstream) Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brook's Bridge)

North Anna River 11 5.80 SE Monthly (downstream)

Ground Water OlA 0.75 SE Quarterly Biology Lab (well water)

Aquatic Waste Heat Treatment Sediment Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon)

North Anna River (upstream) Rt 669 Bridge 09A 12.9 WNW Semi-Annually .Control (Brook's Bridge)

North Anna River 11 5.80 SE Semi-Annually (downstream)

Shoreline Soil LakeAnna 08 1.10 SSE Semi-Annually Soil NAPS Sewage Treatment 01 0.20 NE Once per 3 yrs On-Site Plant

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 116 OF 140 ATTACHMENT 18 (Page 4 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Frequency Soil Fredericks Hall 02 5.30 SSW Once per 3 yrs (continued) Mineral, VA 03 7.10 WSW Once per 3 yrs Wares Crossroads 04 5.10 WNW Once per 3 yrs Route 752 05 4.20 NNE Once per 3 yrs Sturgeon's Creek Marina 05A 3.20 N Once per 3 yrs Levy, VA 06 4.70 ESE Once per 3 yrs Bumpass, VA 07 7.30 SSE Once per 3 yrs End of Route 685 21 1.00 WNW Once per 3 yrs Site Boundary Route 700 22 1.00 WSW Once per 3 yrs Site Boundary "Aspen Hills" 23 0.93 SSE Once per 3 yrs Site Boundary Orange, VA 24 22.00 NW Once per 3 yrs Control Milk Holladay Dairy 12 8.30 NW Monthly (R.C. Goodwin)

Terrell's Dairy 13 5.60 SSE Monthly (Frederick's Hall)

Fish Waste Heat Treatment Semi-Facility (Second Cooling 08 1.10 SSE Annually Lagoon) 25 16.50 NW Semi-Lake Orange Control Annually Food Products Route713 14 varies NE (Edible 15 varies SE Monthly Route 614 broadleaf if available, vegetationa) Route 629/522 16 varies NW Control or at harvest Route 685 21 varies WNW "Aspen Hills" Area 23 varies SSE

a. If edible broadleaf vegetation is unavailable, non-edible vegetation of similar leaf characteristics may be substituted.

J

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 117 OF 140 ATTACHMENT 19 (Page 1 of 2)

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

Airborne Food Fish Sediment Analysis Water Particufa,te Milk Products (pCi/kg) (pCi/kg)

(NOTE2) (pCi/1) or Gases (pCi/1) (pCi/kg)

(wet) (wet)

(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 Nb-95 15 1-131 (NOTE3) 1* 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks 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) water samples is 10 pCi/1.

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 118 OF 140 ATTACHMENT 19 (Page 2 of2)

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

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

4.66 Sb LLD= (24-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (11.At)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (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)

A = 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 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 measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 119 OF 140

  • ATTACHMENT 20 (Page 1 of 2)

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

Airborne Food Fish Sediment Analysis Water Particulate Milk Products (pCi/kg) (pCi/kg)

(NOTE2) (pCi/1) or Gases (pCi/l) (pCi/kg)

(wet) (wet)

(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 Nb-95 15 1-131 (NOTE3) 1 **0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

NOTE 2: This list does not mean that only these nuclides are to be detected and reported. *Other peaks 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) water samples is 10 pCi/1.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 120 OF 140 ATTACHMENT 20 (Page 2 of 2)

Detection Capabilities for North Anna Environmental Sample Analysis

\

LOWER LIMIT OF DETECTION (LLD) (NOTE 3)

NOTE 3: For a particular measurement system (which may include radiochemical separation):

4.66 Sb LLD= (25-1)

E

  • V
  • 2.22E+06
  • Y
  • e-(AAt)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above

  • (as microcuries per unit mass or volume) (See 4.9)

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+o6 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

A = 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 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 measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 121 OF 140

  • ATTACHMENT 21 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples at Surry Airborne Water Fish Milk Food Products Analysis Particub1te or (pCi/1) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

Gases (pCi/m3)

H-3 30,000 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 1-131 (NOTE 1) 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000

  • Cs-137 Ba-La-140 50 200 20 2,000 70 300 2,000 NOTE 1: Reporting level for the ground (drinking) water samples required by Attachment 15. The reporting level for the surface (non-drinking) water samples required by Attachment 15 is 20 pCi/1.

L -

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VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 123 OF 140

  • ATTACHMENT 22 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples at North Anna Airborne Water Fish Milk Food Products Analysis Particulate or (pCi/1) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

Gases (pCi/m3)

(NOTE 1)

H-3 20,000 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 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking water samples

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 124 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 125 OF 140 ATTACHMENT 23 (Page 1 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis 1.0 METEORLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the five (5) year average X/Q 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 X/Q 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, 1992 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 mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT1s8.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on AT1s8.9ft-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 line 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 XIQ values as recommended in Regulatory Guide 1.111. The site region is characterized 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 calculations 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.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 126 OF 140 ATTACHMENT 23 (Page 2 of 8)

Surry 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 llA-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 is appropriate according to NUREG-0133.

1.3 Results The X/Q value that would result in the maximum total body, skin, and inhalation exposure for ventilation vent releases was 6.0E-05 sec/m3 at a site boundary location 532 meters NNE sector. For process vent releases, the site boundary X/Q value was 3.7E-07 sec/m3 at a 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/m3 at a location 290 meters NW sector. The discharge canal bank X/Q value for process vent was 6.9E-07 sec/m3 at a location 290 meters NW sector.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 127 OF 140

  • ATTACHMENT 23 (Page 3 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis The grass-cow-milk pathway analysis, which is performed to derive the maximum exposure from I 131 , I 133 , and from all radionu~lides 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 releases that would result in the maximum exposure for the grass-cow-milk pathway was 1.5E-06 sec/m3 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 X/Q 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 .

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 128 OF 140 ATTACHMENT 23 (Page 4 of 8)

Surry 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 Virginia Power 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 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.

2.3 Results For the years 197 6, 1977, 1979, 1980, and 1981, the invertebrate pathway resulted in the largest 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 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.

_J

  • VIRGINIA: VPAP-2103 POWER REVISI0N9 PAGE 129 OF 140 ATTACHMENT 23 (Page 5 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis 3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose Gaseous effluent pathway analyses are perfonned 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.

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 I 131 , I 133 , tritium, 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 through the inhalation pathway from I 131 , I 133 , tritium, and particulates to demonstrate coll}~li~ce with 6.3.1.a..

3.2 Data, Parameters, and Methodology Five year average 'X/Q 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 the public inside site boundary. The l~gest 'X/Q value was determined to be 6.0E-05 sec/m3 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 WSW 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.

Step 6.3. La.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and 'XIQ values determined for maximum noble gas doses can be used to determine the maximum dose from I 131 , I 133 , tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 130 OF 140 ATTACHMENT 23 (Page 6 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis The maximum exposed individual for 10CFR50 Appendix 1 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. 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 Pivv and Pipv are calculated using the following equation:

(28-1) where:

K' =a constant of unit conversion, lE+ 12 pCi/Ci BR = the breathing rate of the particular age group, m3/yr, from Table E-5, Regulatory Guide 1.109, Rev .1 DFAi = the critical organ inhalation dose factor for particular age group for the ith radionuclide, in mrem/pCi Parameters used above were obtained from NUREG-0133, R.G. 1.109, Rev. 1, and LADTAP II, NUREG/CR-1276 I 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 X/Q at this location was determined to be 1.6E-04 sec/m3 at 290 meters NW direction.

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

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 131 OF 140

  • ATTACHMENT 23 (Page 7 of 8)

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

(28-2) where:

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

Uap = infant milk consumption rate, 330, liters/yr Yp = agricultural productivity by unit area of pasture feed grass, 0. 7 Kg!m2 Y8 agricultural productivity by unit area of stored feed, 2.0, in Kg!m2 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 Ai = decay constant for the ith radionuclide, in sec*l Aw = decay constant for removal of activity of leaf and plant surfaces by weathering, 5.73E-07 sec*l (corresponding to a 14 day half-life) tf = transport time from pasture to cow, to milk, to receptor, 1.73+o5, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+o6, 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 .1,

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 132 OF 140 ATTACHMENT 23 (Page 8 of 8)

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

(28-3) where:

K'" = a constant of unit conversion 1E+o3 gm/kg H = absolute humidity of the atmosphere, 8.0, gmfm3 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.

The inhalation pathway dose factors Rlivv and Rlipv were calculated using the following equation:

Rli = K' (BR) DFA1 (mrem/yrpe1 µCi/m3)

(28-4) where:

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

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 133 OF 140 ATTACHMENT 24 (Page 1 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 1.0 METEOROLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the Station for ventilation vent (ground level) and process vent (mixed mode) releases. The annual average X/Q and D/Q values were used to perform a dose pathway analysis to determine both the maximum exposed individual at site boundary and member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 9 and 14.

1.2 Meteorological D~ta, Parameters, and Methodology Onsite meteorological data for the period January 1, 1981, through December 31, 1981, were used in calculations. These data included wind speed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (e.g., ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT1s8.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on AT1s8.9ft-28.2ft and 158.9 ft wind data.

X/Q's and D/Q's were calculated using the NRC computer code "XOQDOQ - Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,"

  • September, 1977. The code is based upon a straight line 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 by gently rolling terrain so open terrain correction factors were considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 134 OF 140 ATTACHMENT 24 (Page 2 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis The effective release height used in mixed mode release calculations was based on a process vent release height of 157 .5 ft, and plume rise due to momentum for a vent diameter of 3 in.

with plume exit velocity of 100 ft/sec. 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 North Anna Power Station Units 1 and 2, Virginia Electric and Power Company Final Safety Analysis Report Table llC.2-8.

X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases at distances specified from North Anna Power Station Annual Environmental Survey Data for 1981. X/Q values were also calculated for the nearest lake shoreline by sector for the 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 is appropriate according to NUREG-0133.

The X/Q and D/Q values calculated from 1981 meteorological data are comparable to the values presented in the North Anna Power Station UFSAR.

1.3 Results The X/Q value that resulted in the maximum total body, skin and inhalation exposure for ventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 1416 meters SE sector. For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m3 at a location 1513 meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m3 at a location 274 meters NNE sector. The shoreline X/Q value for process vent was 2.7E-06 sec/m3 at a location 274 meters NNE sector.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 135 OF 140 ATTACHMENT 24 (Page 3 of 8)

North Ann.a Meteorologic~I, Liquid, and Gaseous Pathway Analysis Pathway analysis indicated that the maximum exposure from I-131, 1133, and from all radionuclides in particulate form with half-liv~s greater than 8 days was through the grass-cow-milk pathway. The D/Q value from.ventilation vent releases resulting in the maximum exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For process vent releases, the D/Q value was 1.lE-09 per m2 at a location 3250 meters N sector. For tritium, the X/Q value from ventilation vent releases resulting in the maximum exposure for the milk pathway was 7 .2E-07 sec/m3, and 3.9E-07 sec/m3 for process vent releases at a location 3250 meters N sector.

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 includes a determination of :qiost restrictive liquid pathway, most restrictive age group, and criticai organ. This analysis is required for Subsection 6.2.

2.2 Data, Parameters, and Methodology Initially, radioactive liquid effluent release data for the years 1979, 1980, and 198L were compiled from the North Anna Power Station semi-annual 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.

Re-concentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for Reservoir and Waste Heat Treatment Facility from Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2, March 15, 1972. Dilution factors for aquatic foods, shoreline, and drinking water were set to one. Transit time calculations were based on average flow rates. All other parameters were defaults selected by the LADTAP computer code.

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 136 OF 140 ATTACHMENT 24 (Page 4 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Beginning in 1997, the activity by nuclide released in the previous year is entered into the North Anna Power Station liquid pathway critical organ calculations spreadsheet, which calculates the most limiting age group total body and critical organ. This Process is repeated annually.

2.3 Results Initially, the fish pathway resulted in the largest dose. The critical organ each year was the liver, and the adult and teenage age groups received the S<Jme organ dose. However, since the adult total body dose was greater than the teen total body dose for each year, the adult was selected as the most restrictive age group. Beginning in 1997, the most limiting age group for both total body and critical organ is calculated from the spreadsheet for North Anna Power Station liquid pathway critical organ calculations.

3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was 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.

and 6.3.3.a. The analysis also included a determination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 1131 , 1133 , tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with requirements in 6.3.4.a.1. In addition, the analysis included a determination of the critical pathway, maximum age group, and sector location of an exposed individual through the inhalation pathway from 1131 , 1133 , tritium, and particulates with half-lives greater than 8 days to demonstrate compliance with 6.3.1.a..

VIRGINIA VPAP-2103 POWER REVISION9 PAGE 137 OF 140 ATTACHMENT 24 (Page 5 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 3.2 Data, Parameters, and Methodology Annual average 'X/Q 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 beyond the site boundary. The largest 'X/Q value was determined to be 9 .3E-06 sec/m3 at site boundary for ventilation vent releases at a location 1416 meters SE direction, and l.2E-06 sec/m3 at site boundary for process vent releases at a location 1513 meters S 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.

Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore,,.the locations and 'X/Q 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.

The NRC computer code GASPAR, "Evalµation of Atmospheric Releases," Revised 8/19/77, was run using 1979, 1980 and 1981 North Anna Power Station Gaseous Effluent Release Report data. Doses from I 131 , I 133 , tritium, and particulates for the inhalation pathway were calculated using the 9.3E-06 sec/m3 site boundary 'X/Q. Except for the source tenn.'data and the 'X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway.

The gamma and beta dose factors Kivv, Livv, Mivv, and Nivv in Attachment 9 were obtained by performing a units conversion.of the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev. 1, to mrem/yr per Cifm3 or mrad/yr per Cifm3, and multiplying by the ventilation vent site boundary 'XIQ value of 9.3E-06 sec/m3. The same approach was used in calculating the gamma and beta dose factors Kipv, Lipv, Mipv, and Nipv in Attachment 9 using the process vent site boundary 'XIQ value of 1.2E-06 sec/m3 .

VIRGINIA VPAP-2103 POWER REV1SI0N9 PAGE 138 OF 140 ATTACHMENT 24 (Page 6 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis The inhalation pathway dose factors Pivv and Pipv in Attachment 9 were calculated using the following equation:

Pi = K'(BR) DFA/x/Q) (mrem/yrper Curie/sec) (29-1) where:

K' = a constant of unit conversion, lE+ 12 pCi/Ci BR = the breathing rate of the child age group, 3700 m3/yr, from Table E-5, Regulatory Guide 1.109, Rev .1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem/pCi, from Table E-9, Regulatory Guide 1.109, Rev. 1

'XIQ = the ventilation vent site boundary 'X/Q, 9.3E-06 sec/m3, or the process vent site boundary 'X/Q, 1.2E-06 sec/m3, as appropriate.

Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from 1131 ,

1133 , tritium, and from all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, and to an exposed member of the public beyond site boundary at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981.

It was determined that the member of the public within site boundary would be using Lake Anna for recreational purposes a maximum of 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> per year. It is assumed that this member of the public would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake shoreline with the largest annual 'X/Q of 1.0E-04 at a location 274 meters NNE sector. The NRC computer code GASPAR was run to calculate the inhalation dose to this individual. The GASPAR results were corrected for the fractional year the member of the public would be using the lake.

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 139 OF 140

  • ATTACHMENT 24 (Page 7 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Using the NRC computer code GASPAR and annual average X/Q and D/Q values obtained as described in Section 1 of this attachment, the member of the public receiving the largest dose beyond site boundary was determip.ed to be located 3250 meters N sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1979, 1980, and 1981 the dose to*the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary.

Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters N sector.

Pathway analysis results indicate that existing pathways, including ground and inhalation, within five miles of North Anna Power Station, yield Ri dose factors less than those determined for the cow-milk pathway. Although the cow-milk pathway does not exist within five miles of the Station, NUREG-0133 requires the use of cow-milk Ri dose factors since these values result in the most limiting doses. There is no requirement to include the other pathways.

[Commitment 3.2.3]

The RMivv and RMipv dose factors, except for tritium, in Attachment 14 were calculated by multiplying the appropriate D/Q value with the following equation:

(29-2) where:

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

Uap = infant milk consumption rate, 330 liters/yr Yp = agricultural productivity by unit area of pasture feed grass, 0. 7 Kg!m2 Ys = agricultural productivity by unit area of stored feed, 2.0, in Kg!m2 Fm = stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev. 1

VIRGINIA VPAP-2103 POWER REVISI0N9 PAGE 140 OF 140 ATTACHMENT24 (Page 8 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis r = fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and 0.2 for particulates DFLi= thyroid ingestion dose factor for the ith radionuclide for the infant, in rnrem/pCi, from Table E-14, Regulatory Guide 1.109, Rev. 1 Ai = decay constant for the ith radionuclide, in sec-1, from Table of Isotopes, Lederer, Hollander, and Perlman, sixth Edition.

Aw = 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, 1.73E+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, 0.58 (dimensionless), 7 months per year from NUREG-0597 fs = fraction of cow feed that is pasture grass while cow is on pasture, 1.0, dimensionless Parameters used in the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev .1.

Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:

(29-3) where:

K' = a constant of unit conversion 1E+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

=

XIQ the annual average concentration at a location 3250 meters N sector, 7.2E-07 sec/m3 for ventilation vent releases, and 3.9E-07 sec/m3 for the process vent releases

VIRGINIA POWER Administrative Procedures Action Request (A-PAR)

VPAP-0502 - Attachment 22 VPAP-2103 10 1

4. Effective Date ; Z... ,

21 ~) g*

5. Procedure Title 6. Expiration Date Offsite Dose Calculation Manual NIA
7. Type of Request D New Procedure [2g Procedure Revision D Procedure Deletion
8. Brief description of the modification See Revision Summary on affected document.

9* Location ~ SPS D NAPS D CORP

10. Requested by Name (Please Print) 11. Date Doug Noce 10-30-98 Is this a new procedure or does procedure meet requirements of NOTE below*?

Does this procedure require a Safety Evaluation?

e there any new sections or steps designated North Anna or Surry? 0Yes o the reason for the station-specific instructions due to differences in regulatory requirements? (id'NIA

20. Is the reason for the station-specific instructions due to differences in construction? [iJ1(J1A
21. Is the reason for the station-specific instructions due to station preferences? 0Yes D No (91:JIA If all answers are No or NIA, approval is required by PPOs as identified on the Procedure Cover Page. Check block 29.

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 app~opriate NOTE: VPAP-2101 and VPAP-2201 require SNSOC approval.

VPAP-2103, VPAP-2104, and VPAP-2401 require SNSOC and Site Vice President approval.

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; Sit-e*Vice Presidents, and Vice President (Corporate). Checkillocks 29, 31; and 32.

22. Location ~ SPS D NAPS D CORP Location D SPS ~ NAPS
23. PPO Name {Please Print) 26. PPO Name (Please Print)

W. A. Thornton A. H. Stafford

35. PPO (Signature) .

L,u~., 6.-Jon.~5

39. SNSOC Chairman (Signature) 40. Date D.A . (kctece-k 12 -lo"lk
43. Site Vice President (Signa

\N.(L. M/~)

46. Date Key: A-Par - Administrative Procedures Action Request; SPS - Surry Power Station; NAPS - North Anna Power Station; CORP - Corporate; PPO(s) - Process Program Owner(s); SNSOC - Station Nuclear Safety Operating Commltee Form No. 720457(June 98)

Station A-dministrative Procedure VIRGINIA POWER e 1998 by Virginia Power. All Rights Reserved

Title:

Offsite Dose Calculation Manual Process/ Program Owner:Superintendent - Radiological Protection Procedure Number Revision Number Effective Date VPAP-2103 10 IZ.*Z.~-'18 Revision Summary Revised to update Surry environmental sampling locations for milk sample media:

  • Deleted "Judkin's" from Surry Environmental Sampling Locations (Attachment 17) since dairy no longer supplies milk to Surry.

Approvals on File

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE2 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 3 OF 140 TABLE OF CONTENTS Section Page 1.0 PURPOSE 7 2.0 SCOPE 7

3.0 REFERENCES

/COMMITMENT DOCUMENTS 8 4.0 DEFINITIONS 9 5.0 RESPONSIBILITIES. 13 6.0 INSTRUCTIONS 15 6.1 Sampling and Monitoring Criteria 15 6.2 Liquid Radioactive Waste Effluents 15 6.2.1 Liquid Effluent Concentration Limitations 15 6.2.2 Liquid Monitoring Instrumentation 16 6.2.3 Liquid Effluent Dose Limit 20 6.2.4 Liquid Radwaste Treatment 23 6.2.5 Liquid Sampling 25 6.3 Gaseous Radioactive Waste Effluents 25 6.3.1 Gaseous Effluent Dose Rate Limitation 25 6.3.2 Gaseous Monitoring Instrumentation 27 6.3.3 Noble Gas Effluent Air Dose Limit 30 6.3.4 I-131, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 32 6.3.5 Gaseous Radwaste Treatment 36 6.4 Radioactive Liquid and Gaseous Release Permits 38 6.4.1 Liquid Waste Batch Release Permits 38 6.4.2 Continuous Release Permit 39 6.4.3 Waste Gas Decay Tank (WGDn Release Permit 40 6.4.4 Reactor Containment Release Permits 40 6.4.5 Miscellaneous Gaseous Release Permit 40

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE40F 140 TABLE OF CONTENTS (continued)

Section Page 6.4.6 Radioactive Liquid and Gaseous Release Controls 41 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 42 6.6 Radiological Environmental Monitoring 43 6.6.1 Monitoring Program 43 6.6.2 Land Use Census 45 6.6.3 Interlaboratory Comparison Program 46 6.7 Reporting Requirements 47 6.7.1 Annual Radiological Environmental Operating Report 47 6.7.2 Annual Radioactive Effluent Release Report 48 6.7.3 Annual Meteorological Data 50 6.7.4 Changes to the ODCM 50 7.0 RECORDS 52 ATTACHMENTS 1 Surry Radioactive Liquid Effluent Monitoring Instrumentation 53 2 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 55 3 Surry Radioactive Liquid Effluent Monitoring Instrumentation 57 Surveillance Requirements 4 North Anna Radioactive Liquid Effluent Monitoring Instrumentation 59 Surveillance Requirements 5 Surry Radioactive Liquid Waste Sampling and Analysis Program 61 6 North Anna Radioactive Liquid Waste Sampling and Analysis Program 65 7 Surry Radioactive Gaseous Waste Sampling and Analysis Program 69 8 North Anna Radioactive Gaseous Waste Sampling and Analysis Program 75 9 Gaseous Effluent Dose Factors for North Anna 79 I

_J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE5 OF 140 TABLE OF CONTENTS (continued)

Section Page 10 Surry Radioactive Gaseous Effluent Monitoring Instrumentation 83 11 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 87 12 Surry Radioactive Gaseous Effluent Monitoring Instrumentation 91 Surveillance Requirements 13 North Anna Radioactive Gaseous Effluent Monitoring Instrumentation 93 Surveillance Requirements 14 Critical Organ Dose Factors for North Anna 97 15 Surry Radiological Environmental Monitoring Program 99 16 North Anna Radiological Environmental Monitoring Program 103 17 Surry Environmental Sampling Locations 109 18 North Anna Environmental Sampling Locations 113 19 Detection Capabilities for Surry Environmental Sample Analysis 117 20 Detection Capabilities for North Anna Environmental Sample Analysis 119 21 Reporting Levels for Radioactivity Concentrations in Environmental 121 Samples at Surry 22 Reporting Levels for Radioactivity Concentrations in Environmental 123 Samples at North Anna 23 Surry Meteorological, Liquid, and Gaseous Pathway Analysis 125 24 North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 133

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 6 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 7 OF 140 1.0 PURPOSE The 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 µCi/ml for dissolved 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 CPR 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
    • 1131 , 1133 , and H3 , and all radionuclides in particulate form 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 and North Anna Stations.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 8 OF 140

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 3.1.8 Surry and North Anna Technical Specifications (Units 1 and 2) 3.1.9 NUREG-0324, XOQDOQ, Program for the Meteorological Evaluation of Routine 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 3.1.14 Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Rev. 1 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, Rev. 3, March 1982

  • 3.1.18 Environmental Measurements Laboratory, DOE HASL 300 Manual

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE90F 140

a. DC-85-37-1 Unit 1
b. DC-85-38-2 Unit 2 3.1.24 Deviation Report N94-1137, Improper Placement of Emergency TLDs
  • 3.2 Commitment Documents 3.2.1 Quality Assurance Audit Report Number C 90-22, Management Safety Review Committee, Observation 03C, January 17, 1991 3.2.2 Quality Assurance Audit Report Number 91-03, Observation 08N
  • 3.2.3 Quality Assurance Audit Report Number 92-03, Observation 02N 3.2.4 Quality Assurance Audit Report Number 92-03, Observation 04NS (Item 2) 3.2.5 North Anna DR N-97-0926, Annual Radiological Effluent Release Report 3.2.6 Surry DR S-97-1281, Annual Radiological Effluent Release Report 4.0 DEFINITIONS 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, wh.ere possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 10 OF 140 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.

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 That concentration of I 131 (µCi/cc) that alone would produce the same thyroid dose as the quantity and isot-opic mixture ofl 131 , I 132, ! 133 , I 134, and I 135 actually present. Thyroid dose conversion factors for this calculation are listed in Table ill 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 (Surry).

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 11 OF 140 4.6

  • Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.

NOTATION FREQUENCY D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W-Weekly At least once per 7 days M-Monthly At least once per 31 days Q - Quarterly At least once per 92 days SA - Semi-annually At least once per 184 days R - Refueling At least once per 18 months SIU - Start-up Prior to each reactor start-up P - Prior to release Completed prior to each release N .A. - Not applicable Not applicable DR - During the release At least once during each release 4.7 Gaseous Rad waste 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, waste gas surge tanks, and waste gas diaphragm compressor (North Anna).

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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 12 OF 140 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 Virginia Power 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 servicemen or postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Virginia Power 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 4.13 Rated Thermal Power Total reactor core heat transfer rate to reactor coolant.

    • Surry - 2546 Megawatts Thermal (MWt)
  • North Anna - 2893 MWt 4.14 Site Boundary The line beyond which Virginia Power 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.

.VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 13 OF 140 4.17 Thermal Power 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 Virginia Power 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 A system that reduces gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and High 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 effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems

  • are not Ventilation Exhaust Treatment System components.

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

5.1.1 Establishing and maintaining procedures for surveying, sampling, and m9nitoring radioactive effluents and the environment.

5.1.2 Surveying, sampling, and analyzing plant effluents and environmental monitoring, 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 Superintendent Operations The Superintendent Operations is responsible for requesting samples, analyses, and authorization to release effluents.

VIRGINIA VPAP-2103

.POWER REVISION 10 PAGE 14 OF 140
  • I..___1_n_1e_n_ti_o_n_a1_1y_e_1a_n_k_ _ _l

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 15 OF 140

  • 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Attachments 23 and 24, Meteorological, Liquid, and Gaseous Pathway Analysis for Surry and North Anna, respectively.

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.

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 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.

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:
1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to unrestricted areas shall not exceed ten times the effluent concentration values specified in 10 CFR 20, Appendix B, Table 2, Column 2.
2. For dissolved or entrained noble gases, concentrations shall not exceed 2E-4 µCi/ml.
b. If the concentration of liquid effluent exceeds the limits in 6.2.1.a., promptly reduce concentrations to within limits.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 16 OF 140

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> (I)

. µCi/ml. . - 1 Volume of Waste Discharged x L ACW.

1

. i 1 where:

µCi/mli = 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 µCi/ml from 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases, and 2E-4 µCi/ml for dissolved or entrained noble gases 6.2~2 Liquid Monitoring Instrumentation

a. Radioactive Liquid Effluent Monitoring Instrumentation Radieactive liquid effluent monitoring instrumentation channels shown on Attachments 1 and 2, Radioactive Liquid Effluent Monitoring Instrumentation, 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
  • Change the setpoint to an acceptable, conservative value

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 17 OF 140

  • b. ~adioactive Liquid Effluent Monitoring Iostrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performing a Channel Check, Source Check, Channel Calibration, and Channel Functional Test at the frequencies shown in Attachments 3 and 4, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance
  • Requirements.
1. If the number of operable channels is less than the minimum required by the tables in Attachment 1 or 2, 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:

Release Point Instrument Number ...

North Anna Surry Liquid Radwaste Effluent Line l-LW-RM-111 NIA Service Water System Effluent Line l-SW-RM-108 l-SW-RM-107 A, B,C,D Condenser Circulating Water Line l-SW-RM-130 l-SW-RM-120 2-SW-RM-230 2-SW-RM-220 .

Radwaste Facility Effluent Line NIA l-RRM-RITS-131 Steam Generator High Capacity l-RM-SS-125 NIA

  • mowdown Line 2-RM-SS-125

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 18 OF 140 6.2.2 Liquid Monitoring Instrumentation (continued)-*

d. Setpoint Calculation NOTE: This. methodology does not preclude use of more conservative setpoints.
1. Maximum setpoint values shall be calculated by:

s = (2) where:

S = the setpoint, in µCi/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 CPR 20 for the Station, in µCi/ml FE = maximum design pathway effluent flow rate F0 = dilution water flow rate calculated as: *

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

(N. Anna) D =FE+ (218,000 gpm x number of circ. pumps in service)

2. Each of the condenser circulating water channels (Surry: SW-120, SW-220)

(North Anna: SW-130, SW-230) 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 CPR 20 for the site becomes the effluent concentration limit.

3. In addition, for added conservatism, setpoints shall be calculated for the liquid radwaste effluent line (North Anna: LW-111), the service water system effluent line (Surry: SW-107 A, B, C, and D, North Anna: SW-108), and the Radwaste Facility effluent line (Surry: RRM-131).

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 19 OF 140

  • 4. For the liquid rad waste effluent line, Equation (2) becomes:

s = (4) where:

KLw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 for the site, attributable to the liquid radwaste effluent line pathway

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

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

s = (6) where:

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

7. The sum KLw + Ksw + KRw shall not be greater than 1.0.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 20 OF 140 6.2.3 Liquid Effluent Dose Limit

a. Requirement At least once per 31 days, perform the dose calculations in 6.2.3.c. and 6.2.3.d. to ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials in liquid releases (from each rel:_lctor unit) to unrestricted areas 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
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 reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 21 OF 140

c. Surry 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 £..J ~C.A.1 1 (7) i 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 q 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 1 lA, Surry UFSAR F = the near field average dilution factor for q 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 q = the average concentration of radionuclide, i, in undiluted liquid effluent during the period t, from all liquid releases, in µCi/ml Ai = the site-related ingestion dose commitment factor to the total body or critical organ for a particular age group for each identified principal gamma and beta emitter in mrem-ml per hr-µCi. Values for Ai are provided in the Canberra Source Code file.

A.1 = 1.14 E+OS (21BF.1 + SBI.) 1 OF.1 (8) where:

1.14 E+05 = 1 E+06 pCi/µCi x 1 E+03 ml/k:g/(8760 hr/yr), units conversion factor 21 = adult fish consumption, kg/yr, from NUREG-0133 L'.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 22 OF 140 5 = adult invertebrate consumption, kg/yr,-from NUREG-0133 Bii = the bioaccumulatiori factor for nuclide i, in invertebrates, pCi/kg per pCi/1 BFi = the bioaccumulation factor for nuclide i, in fish, pCi/kg per pCi/1 DFi = the critical organ dose conversion factor for 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.

d. North Anna Dose Contribution Calculations Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on:

(9)

D = ~Q.xB.

£..iJ 1 1 i

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 Bi = Dose Commitment Factors (mrem/Ci) for each age group of interest.

Values for Bi are provided in code file for North Anna Power Station liquid pathway critical organ calculations Qj = Total released activity for the considered period and the ith nuclide Q.1 = txC.xWasteFlow 1

(10)

Where:

t = the period for which q and F are averaged for all liquid releases, in hours Ci = the average concentration of radionuclide, i, in undiluted liquid effluent during the period, t, from any liquid releases, in µCi/ml

  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 23 OF 140
  • e. Quarterly Composite Analyses.

For radionuclides not detennined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative summation may be 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.

6.2.4 Liquid Radwaste Treatment Historical data pertaining to the volumes and radioactivity of liquid effluents released in connection with specific station functions, such as maintenance or refueling outages, shall be used in projections as appropriate.

a. Requirement
1. The Liquid Radwaste Treatment System and/or 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 ff 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 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 in operability.
2. Actions taken to restore inoperable equipment to operable status.
3. Summary description of actions taken to prevent recurrence.
c. Projected Total Body Dose Calculation
1. Detennine DTB, the total body dose from liquid effluents in the previous 31-day period, per Equation (9) for North Anna.

VIRGINIA

  • VPAP-2103 POWER REVISION 10 PAGE 24 OF 140
2. Estimate R 1, the ratio of the estimated volume.of liquid effluent releases in the present 31-day period to the volume released in the previous 31-day period.
3. Estimate F 1, the ratio of the estimated liquid effluent radioactivity concentration in the present 31-day period to liquid effluent concentration in the previous 31-day period (µCi/ml).
4. Determine PDTB, the projected total body dose in a 31-day period.

(11)

d. Projected Critical Organ Dose Calculation (North Anna)
1. Determine D 0 , the critical organ dose from liquid effluents in the previous 31-day period, per Equation (9) for North Anna.
2. Estimate R 1 as in 6.2.4.c.2.
3. Estimate F 1 as in 6.2.4.c.3.
4. Determine PD0 = projected critical organ dose in a 31-day period.

(12)

e. Projected Dose Calculations (Surry)
1. Determine DI, the sum of all liquid open release points, in mrem/day, by the ith organ.
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 Op, the 31 day projected dose by the ith organ Dp = (DI x P) + Da

VIRGINIA VPAP-2103

  • POWER REVISION 10 PAGE 25 OF 140
  • 6.2.5 Liquid Sampling Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis requirements in Attachments 5 and 6, Radioactive Liquid Waste Sampling and Analysis Program (Surry and North Anna, respectively).

6.3 Gaseous Radioactive Waste Effluents 6.3.1 Gaseous Effluent Dose Rate Limitation

a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to:
1. The dose rate limit for noble gases shall be 5 500 mrem/year to the total body and 5 3000 mrem/year to the skin.
2. The dose rate limit for I 131 , I 133 , for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be 5 1500 mrem/year to the critical organ.
b. Action
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, continuously, to be within 6.3.1.a. limits.
3. Dose rates due to 1131 , 1133 , tritium, and all radionuclides in particulate form 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 analyses in.accordance with the sampling and analysis program specified on Attachments 7 and 8, Radioactive Gaseous Waste Sampling and Analysis Program.

l,

'VlKuli~lA VPAP-21U3 POWER REVISION 10 PAGE 26 OF 140

c. Calculations of Gaseous Effluent Dose Rates

. NOTE: The dose factors used in the Gaseous Effluent Dose.Rate calculations for Surry Power Station 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 (13), (14), and (15) must be multiplied by the appropriate X/Q value for Surry's.Gaseous Effluent Dose Rate calculations.

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

L [KivvQivv + KipvQipv] :s; 500mrem/yr to the total body (13) i OR

~ [(L.1vv + 1.lM.1vv ) Q1*vv + (L.1pv + 1.lM.1pv ) Q1*pv] :s; 3000mrem/yr to the skin

£..J i (14) 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. Factors are listed in Attachment 9, Gaseous Effluent Dose Factors for North Anna

= The skin dose factor for ventilation vents cir process vent release due to beta emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec. Factors are listed in Attachment 9 for North Anna

= 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. Factors are listed in Attachment 9 for North Anna

= 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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 27 OF 140

2. The dose rate limit for I 131 , I 133 , tritium, and for all radionuclides in particulate form with half-lives greater than 8 days, shall be determined to be within the limit by restricting the release rate to:

4' I

[P ivvQivv + P ipvQipvl s;; 1500mrem/yr to the critical organ (15) where:

= The critical orf:an dose factor for ventilation vents or process vent for I 131 , I 33 , H 3 , and all radionuclides in particulate form with half-lives greater than 8 days, for the inhalation pathway, in mrem/yr per Curie/sec. Factors are listed in Attachment 9 for North Anna

= The release rate for ventilation vents or process vent of I 131 ,

1133 , 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 Q;vv
  • 6.3.2 Gaseous Monitoring Instrumentation
a. Requirement
1. The radioactive gaseous effluent monitoring instrumentation channels shown in Attachment 10 or 11, Radioactive Gaseous Effluent Monitoring Instrumentation, shall be operable with alarm/trip setpoints set to ensure that 6.3.1.a. noble gas limits 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 Attachment 12 or 13, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 28 OF 140

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 Attachments 10 and 11, 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.
c. Applicable Monitors Radioactive gaseous effluent monitors for which alarm/trip setpoints shall be determined are:

Release Point Instrument Number North Anna Surry Process Vent 1-GW-RM-102 1-GW-RM-102 1-GW-RM-178-1 1-GW-RM-130-1 Condenser Air Ejector l-SV-RM-121 1-SV-RM-111 2-SV-RM-221 2-SV-RM-211 Ventilation Vent A 1-VG-RM-104 NIA 1-VG-RM-179:.1 Ventilation Vent B 1-VG-RM-113 NIA 1-VG-RM-180-1 Ventilation Vent No. 1 NIA 1-VG-RM-104 Ventilation Vent No. 2 NIA 1-VG-RM-110 1-VG-RM-131-1 Radwaste Facility Vent NIA RRM-101

VlRGINIA VPAP-2103 POWER REVISION 10 PAGE 29 OF 140

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

D~D pv +D cae +D vv (16) 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:

Surry: Summation of the Ventilation Vents 1, 2, and the Radwaste Facility vent gaseous effluent releases, mrem/yr North Anna:Summation of Ventilation Vent A plus B gaseous:

effluent releases, mrem/yr

VIRGINIA Vl>AP-2103 "POWER REVISION 10 PAGE 30 OF 140

2. Setpoint values shall be determined by: -- -- -

R m x 2.12 E-03 cm= (17)

Fm where:

m = The release pathway, process vent (pv), ventilation vent (vv) condenser air ejector (cae), or Radwaste Facility (rv)

Cm = The effluent concentration limit implementing 6.3.1.a. for the Station, µCi/ml Rm = The release rate limit for pathway133m determined from methodology in 6.3.1.c., using Xe as nuclide to be released,

µCi/sec 2.12E-03 = CFM per ml/sec Fm = The maximum flow rate for pathway m, CFM 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.

6.3.3 Noble Gas Effluent Air Dose Limit NOTE: The dose factors used in the Noble Gas air dose calculations for Surry Power Station are included in the 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 (18) and (19) must be multiplied by the appropriate X/Q value for Surry's 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 5 mrads for gamma radiation and 510 mrads for beta radiation
  • During any calendar year: 510 mrads for gamma radiation and 520 mrads for beta radiation

_J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 31 OF 140

2. Cumulative dose 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.
c. Noble Gas Effluent Air Dose Calculation (North Anna)

Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Oivv*

The air dose to areas at or beyond the site boundary due to noble gases shall qe

  • determined by the following:

For gamma radiation:

Dg = 3.17E-081: [MivvQivv+MipvQipv]

i (18)

VIRGINIA VPAP-2103 POWER REVISION IO PAGE 32 OF 140 For beta radiation:

Db = 3.17E-08L [NivvQivv +NipvQipvJ (19) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents, including the Radwaste Facility Ventilation Vent and air ejectors pv, refers to the vent releases from the process vent i, refers to individual radionuclide

= the air dose for gamma radiation, in mrad

= the air dose for beta radiation, in mrad

= the air dose factors for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per Curie/sec. Factors are listed in Attachment 9 for North Anna

= 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. Factors are listed in Attachment 9 for North Anna

= 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 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 I 131 , I 133, 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: .:5 7 .5 mrem to the critical organ
  • During any calendar year: .:5 15 mrem to the critical organ
2. Cumulative dose ~ontributions to a member of the public from I 131 , I 133 ,

tritium, and radionuclides in particulate form with half-lives greater than 8 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. or 6.3.4.d.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 33 OF 140

b. Action If the calculated dose from the release of I 131 , I 133 , tritium, and radionuclides 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 special 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 34 OF 140

c. Surry Dose Calculations NOTE: The RMi and Rli dose factors DO NOT include the applicable D/Q and X/Q values respectively for Surry Power Station. Equation (20) 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 Q;vv. 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 beyond the site boundary that contain I 131 , I 133 , tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

0r = 3.i 7E-OS Lr(RMivvQivv + RMipvQipv) + (RlivvQivv + RlipvQipv)] c2 o) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents, including the Radwaste Facility Ventilation Vent and air 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 RMivv, RMipv= 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 µCi/m 3* Factors are included in the Canberra Source Code file.

the inhalation pathway dose factor for ventilation vents or

  • process vent release due to I 131 , I 133 , tritium, and from all particulate-form radionuclides with half-lives greater than
  • eight days, in mrem/yr per µCi/m 3
  • Factors are included in the Canberra Source Code file.

. VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 35 OF 140

  • 3.17 E-08

=

=

the release for ventilation vents or process vent of I 131 , I 133 ,

tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curies the inverse of the number of seconds in a year

d. North Anna Dose Calculations Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qiw* 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 beyond the site boundary, that contain I 131 , I 133 ,

tritium, and particulate-form radionuclides with half-lives greater than 8 days, shall be determined by:

Dr = 3.17E-08 L [RMivvQivv + RMipvQipvJ (21) i Where:

Subscripts = vv, refers to vent releases from the building ventilation vents; 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 .

RMivv, RMipv =the cow-milk dose factor for ventilation vents or process vent

  • release due to I 131 , I 133 , tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in mrem/yr per Curie/sec. Factors are listed in Attachment 14, Critical Organ Dose Factors for North Anna QiwQipv - the release for ventilation vents or process vent of I l3 l, I 133, tritium, and from all P.articulate-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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 36 OF 140 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. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive material in gaseous waste before its discharge, when 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. (North Anna)
2. Appropriate portions of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in gaseous waste before its discharge, when 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. (Surry)
3. 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.
4. Doses due to gaseous releases froin the site shall be projected at least once per 31 days, based on the calculations in 6.3.5.c. and 6.3.5.d.
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 for the inoperability.
2. Actions taken to restore the inoperable equipment to operable status.
3. Summary description of actions taken to prevent recurrence.

VIRGINIA VPAP-2103 POWER REVISION IO PAGE 37 OF 140

  • c. Projected Gamma Dose (North Anna)_
1. Determine Dg, the 31-day gamma air dose for the previous 31-day period, per Equation ( 18).
2. Estimate Rg, the ratio of the estimated volume of gaseous effluent in the current 31-day period to the volume released during the previous 31-day period.
3. Estimate Fg, the ratio of the estimated noble gas effluent activity in the current 31-day period to the noble gas effluent activity during the previous 31-day period (µCi/ml).
4. Determine PDg, the projected 31-day gamma air dose.

PD g = D g (R g xFg ) (22)

d. Projected Beta Dose (North Anna)
1. Determine Db, the 31-day beta air dose in the previous 31 days, per Equation (19).
2. Estimate Rg and Fg as in 6.3.5.c.2. and 6.3.5.c.3.
3. Determine PDb, the projected 31-day beta air dose.

(23)

e. Projected Maximum Exposed Member of the Public Dose (North Anna) _.
1. Determine Dmax, the 31-day maximum exposed member of the public dose in the previous 31-day period, per Equation (20) or Equation (21 ),

where Dr= Dmax'.

2. Estimate Fi, the ratio of the estimated activity from I 131 , I 133 , radioactive materials in particulate form with half-lives greater than 8 d~ys, and tritium in the current 31-day period to the activity of I 131 , I 133 , radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the previous 31-day period (µCi/ml).

Vl.KLJ1N1A VPAP-2103 POWER REVISION 10 PAGE 38 OF 140

3. Determine PDmax, the projected 31-day maximum exposed member of the public dose.

PDmax = D max (R g xF.) 1 (24)

f. Projected Dose Calculations (Surry)
1. Determine Dg, the sum of all gaseous open release points, in mrem/day, by the ith organ.
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 = (Dg x P) + 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.

6.4.1 Liquid Waste Batch Release Permits Operations shall obtain RP authorization before initiating batch releases of radioactive liquids. Examples of batch releases include:

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 39 OF 140

a. Surry Batch Releases Release of contents from the following tanks/sumps other than transfers to the Surry Radwaste Facility shall have a Liquid Waste Batch Release Permit before the discharge:
  • Boron Recovery Test Tank (BRTT)
  • Low Level Waste Drain Tank (LLWDT)
  • High Level Waste Drain Tank (HLWDT)
  • Liquid Waste Test Tank (LWTT)
  • Contaminated Drain Tank (CDT)
  • Laundry Drain Surge Tank (LOST)
  • Turbine Building Sumps when RP determines that source activity requires placing pumps in manual mode
  • Condensate Polishing Building Sumps when RP determines the presence of contamination from primary-to-secondary leakage
b. North Anna Batch Releases NOTE: If the clarifier is in service, releases from tanks processed through the clarifier are considered continuous releases.

A Batch Release Permit is required for a release from any tanks/sumps which contain (or potentially contain) radioactive liquid. Tanks/sumps include:

  • BRTT
  • LLWDT
  • HLWDT
  • Turbine Building Sumps when secondary coolant activity exceeds 1.0 E-5 µCi/ml
  • CDT 6.4.2 Continuous Release Permit Operations shall obtain RP authorization before initiating continuous releases of radioactive liquids.
  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 40 OF 140
a. Surry Continuous Releases A Continuous release permit is required at Surry for:
  • Component Cooling Water (CCW) heat exchanger to service water leakage, if applicable
  • Turbine Building sumps and/or subsurface drains if source activity concentrations are sufficiently low to allow continuous release
b. North Anna Continuous Releases A Continuous Release Permit is required at North Anna for:
  • Clarifier, unless being bypassed
  • Containment mat sumps and service water reservoir when clarifier is bypassed 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
  • Receipt of Radiation Monitoring System (RMS) Containment Gas Monitor high alarm 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorization before initiating releases of noble gases that may not be accounted for by routine sampling, or any planned release not being routed through the Process Vent or Ventilation Vents (e.g., steam driven auxiliary feedwater pump testing if primary to secondary leakage exists).

~

. VIRGINIA VPAP-2103 POWER REVISION 10 .

  • PAGE 41 OF 140 6.4.6 Radioactive Liquid and Gaseous Release. Controls
a. Operations shall notify RP of pending releases and request RP to initiate the 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, except Clarifier Proportional Tanlc and Clarifier Grab Samples at North Anna.

2. Chemistry shall provide RP with liquid samples and sample information for samples obtained from inside the Primary Sample Room.
3. RP shall obtain gaseous samples.
c. RP shall perform required sample analyses.
d. RP shall calculate and record the following information on a release permit:
  • Maximum authorized release rate
  • . Maximum authorized release rate in percentage of limits specified by the ODCM
  • 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 percent of Technical Specification limits the release represents.

'*\

4. Note and ensure compliance with any in~.i~?-ted controls or conditions applicable to the release .

.;,I

  • VIRGINIA VPAP-2103
  • POWER REVISION 10 PAGE 42 OF 140
g. When commencing release, Operations shall provide RP with required infomiation.

As appropriate, required information shall include:

  • Date and time release was started
  • Starting tank/sump level
  • Beginning pressure
  • Release flow rate
  • 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 information shall include:
  • Date and time release was stopped
  • Tank/sump ending level
  • Release flow rate just prior to termination
  • Ending pressure
  • Volume released

,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 radiatio.~ c,ontributi9n,.fi:'om 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 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:

___J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 43 OF 140

1. An analysis that estimates the radiation e1Cposure (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 Radiological Environmental Monitoring 6.6.1 Monitoring Program

a. Requirement
1. The Radiological Environmental Monitoring Program shall be conducted as specified in Attachment 15 or Attachment 16, Radiological Environmental.

Monitoring Program.

2. Samples shall be collected from specific locations specified in Attachment 17 or Attachment 18, Environmental Sample Locations. [Commitment 3.2.2]
3. Samples shall be analyzed in accordance with:
  • Attachment 15 or Attachment 16 requirements
  • Detection capabilities required by Attachment 19 or Attachment 20, Detection Capabilities for Environmental Sample Analysis .
  • Guidance of the Radiological Assessment Branch Technical Position on 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 Annual Radiological Environmental Operating Report required by Technical Specification (Surry Technical Specification 6.6.B.2 and North Anna Technical, Specification 6.9.1.8), a description of the reasons for not conducting the program as required, and the plan for precluding recurrence.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 44 OF 140

2. If, when averaged over any calendar quarter,.:radioactivity exceeds the reporting levels of Attachment 21 or Attachment 22, Reporting Levels for Radioactivity Concentrations in Environmental Samples, 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 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 Attachment 21 or Attachment 22 are detected in the sampling medium, the report shall be submitted if:

concentration (1) concentration (2) >

10 (25) repolt!flg level (1) + reporting level (2) + *** - *

3. When radionuclides other than those listed in Attachments 21 and 22 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 Attachment 15 or 16, identify locations for obtaining replacement samples and add them to th~ radioiogical 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 identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Report in accordance with VPAP-2802, Notifications and Reports. Include in the report a revised figure and table for the ODCM to reflect the new locations .

.~J

I~---~~

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 45 OF 140

  • 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 use census
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 Attachment 15 or Attachment 16 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.2, 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 (Surry) or 25 percent .

(North Anna) 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) 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 3.2.4]

i

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 46 OF 140 6.6.3 Interlaboratory Comparison Program

a. Requirement Radioactive materials (which contain nuclides produced at the Stations), supplied as part of an Interlaboratory Comparison Program, shall be analyzed.
b. Action
1. Analyses shall be performed as follows:

Program Cross-Check of Mille I 131 , Gamma, K, Sr89 and Sr90 Water Gross Beta, Gamma, I 131 , H 3 (Tritium), Sr89 and Sr90 (blind-any combinations of above radionuclides)

Air Filter Gross Beta, Gamma, Sr90

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. Methodology and Results
1. Methodology and results of the cross-check program shall be maintained in the contractor-supplied Quality Control Manual.
2. Results shall be reported in the Annual Radiological Environmental Monitoring Report in accordance with VPAP-2802, Notifications and Reports.

~J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 47 OF 140

  • 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.
1. ff 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 lnterlaboratory Comparison Program, per 6.6.3.
f. Discussion of deviations from the Station's environmental sampling schedule per Attachment 15 or Attachment 16.
g. Discussion of analyses in which the lower limit of detection (LLD) required by Attachment 19 or Attachment 20 was not achievable.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 48 OF 140

6. 7.2 Annual Radioactive Effluent Release Report_
a. Requirement - Station Radioactive Effluent Release Reports covering operation of the units during the 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:
1. 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 3.2.5]

[Commitment 3.2.6]

2. An assessment of radiation doses to the maximum exposed members of the public due to the radioactive liquid and gaseous effluents released from 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 Deviation Report and involve the discharge of contents of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release tank
  • 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 CPR 50.73, Licensee Event Report System, report is required
  • Unplanned releases as determined by Radiation Protection Supervision, which may or may not require a Deviation Report
4. *Major changes to radioactive liquid, gaseous, and solid waste treatment systems during the reporting period.
5. Changes to VPAP-2103, Offsite Dose Calculation Manual (See 6.7.4).

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 49 OF 140

6. A listing of new locations for dose calculations or environmental monitoring identified by the land use census (See 6.6.2).
b. Dose Assessment 1~ Radiation dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.

Population doses shall not be included in dose assessments.

2. The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be 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.

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."

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 Report for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Report. The Annual Radioactive Effluent Reports for Surry Station and Surry ISFSI are separate and not submitted as a combined report

c. ISFSI i .. 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. (Surry)
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.

l

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 50 OF 140

3. Dose Assessment
  • Radiation dose to individuals due to radioactive liquid and gaseous effluents during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109. Population doses shall not be included in dose assessments
  • The dose to the maximum exposed member of the public due to radioactive liquid and gaseous effluents from the Station shall be 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.l, the dose assessment shall include the contribution from direct radiation
  • Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine gaseous pathway doses
6. 7.3 Annual Meteorological Data
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.

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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 51 OF 140

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:
  • 40 CFR 190
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 the Management Safety Review Committee (MSRC) Coordinator.

[Commitment 3.2.1]

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 52 OF 140 7.0 RECORDS 7.1 The following individual and packaged documents and copies 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 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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 53 OF 140

  • ATTACHMENT 1 (Page 1 of 1)

Surry Radioactive Liquid Effluent Monitoring Instrumentation Instrument Minimum Action Operable Channels

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC 1ERMINATION OF RELEASE (a) Rad waste Facility Liquid Effluent Line RM-RRM-131 1 1
2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1-SW-RM-120 '2 2 Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Effluent Line 1-SW-RM-107A 4 2 1-SW-RM-107B l-SW-RM-107C 1-SW-RM-107D
3. FLOW RATE MEASUREMENT DEVICES Rad waste Facility Liquid Effluent Line Instrument Loop RLW-153 1 3 ACTION 1: If the number of operable channels is less than required, effluent releases shall be suspended.

ACTION 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 Attachment 5, Surry Radioactive Liquid Waste Sampling and Analysis Program.

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 54 OF 140 Intentionally Blank J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 55 OF 140

  • ATTACHMENT 2 (Page 1 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation Minimum Operable Instrument Action Channels

1. Liquid Radwaste Effluent (a) 1-RM-LW-111, Liquid Radwaste Effluent Monitor 1 1 (b) l-LW-Ff-104, Liquid Radwaste Effluent Total Flow Measuring Device 1 2 (c) 1-LW-SOV-121, Clarifier Effluent Line Continuous Composite Sampler 1 1 Solenoid Valve (d) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel 1 1 (e) 1-LW-1130, Liquid Waste Effluent Proportional Sample Valve 1 1 (t) 1-RM-SW-108, Service Water Effluent Monitor 1 1 (g) 1-RM-SW-130, Unit 1 Circulating Water System Effluent Line Monitor 1 4 (h) 2-RM-SW-230, Unit 2 Circulating Water System Effluent Line Monitor 1 4
2. Tank Level Indicating Devices (Note 1)

(a) Refueling Water Storage Tanks Unit 1 1-QS-LT-lOOA 1 3 1-QS-LT-lOOB 1-QS-LT-lOOC 1-QS-LT-lOOD Unit2 2-QS-LT-200A 1 3 2-QS-LT-200B 2-QS-LT-200C 2-QS-LT-200D (b) Casing Cooling Storage Tanks Unit l 1-RS-LT-I03A 1 3 1-RS-LT-103B Unit2 2-RS-LT-203A 1 3 2-RS-LT-203B (c) PG Water Storage Tanks (Note 2) 1-BR-LT-116A (1-PG-TK-lA) 1 3 l-BR-LT-116B (1-PG-TK-lB) 1 3 (d) Boron Recovery Test Tanks (Note 2) 1-BR-LT-112A (1-BR-TK-2A) 1 3 l-BR-LT-112B (1-BR-TK-2B) 1 3

3. Steam Generator High Capacity Blowdown (a) Steam Generator High Capacity Blowdown Radiation Monitor Unit 1 l-RM-SS-125 1 1 Unit2 2-RM-SS-225 1 1 (b) Steam Generator High Capacity Blowdown Flash Tank Outlet Flowrate Unit 1 1-BD-Ff-105 1 2 Unit2 2-BD-Fr-205 1 2 (c) Steam Generator High Capacity Blowdown Proportional Sampling System Collection Tank Unit 1 1-BD-TK-4 1 1 Unit2 2-BD-TK-4 1 1 L

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 56 OF 140 ATTACHMENT 2 (Page 2 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via this pathway may continue if, at least once within 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 gross radioactivity (beta and gamma) at an LLD of at least lxlQ-7 µCi/g or an isotopic radioactivity at an LLD of at least 5x10-7 µCi/g.

ACTION 2: If the number of operable channels is less than required, effluent releases via this pathway may continue if 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 /> during actual releases. Design capacity performance curves generated in situ may be used to estimate flow.

ACTION 3: If the number of operable channels is less than required, liquid additions to this tank may continue if the tank liquid level is estimated during all liquid additions to the tank.

ACTION 4: If the number of operable channels is less than required, make repairs as soon as

  • possible. 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 from the discharge canal are collected and analyzed for principal gamma emitters as defined in Attachment 6, North Anna Radioactive Liquid Waste Sampling and Analysis Program.

NOTE 1: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents, and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTE 2: This is a shared system between Unit 1 and Unit 2.

VIR.GlNIA VPAP-2103 POWER REVISION 10 PAGE 57 OF 140

  • ATIACHMENT 3 (Page 1 of I)

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

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC 1ERMINATI0N OF RELEASE (a) Rad waste Facility Liquid Effluent Line RM-RRM-131 D p R Q
2. GROSS BETA OR GAMMA RADIOACTIV-ITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMI-NATION OF RELEASE (a) Circulating Water Discharge Line Unit 1: 1-SW-RM-120 D M R Q Unit 2: 2-SW-RM-220 (b) Component Cooling Service Water Efflu entLine 1-SW-RM-107A D M R ... Q 1-SW-RM-107B 1-SW-RM-107C 1-SW-RM-107D
3. FLOW RA1E MEASUREMENT DEVICES Radwaste Facility Liquid Effluent Line lnsttument Loop RLW-153 DR NIA R NIA

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 58 OF 140 Intentionally Blank

.VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 59 OF 140 ATTACHMENT 4

  • (Page 1 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel Check Check Calibration Functional Test

1. Liquid Radwaste Effluent (a) 1-RM-LW-111. LiquidRadwasteEffluent Monitor D D R Q(NOTE 1)

(b) 1-LW-FI'-104, Liquid Radwaste Effluent Total Flow D (NOTE 3)

Measuring Device NIA R Q (c) 1-LW-SOV-121. Clarifier Effluent Line Continuous Composite Sampler Solenoid Valve NIA NIA NIA NIA (d) l-LW-TK-20, Liquid Waste Effluent Sample Vessel D(NOTE9) NIA NIA NIA (e) 1-LW-1130. Liquid Waste Effluent Proportional Sample D (NOTE 9)

Valve NIA NIA NIA (0 1-RM-SW-108. Service Water System Effluent Monitor D M R Q (NOTE2)

(g) 1-RM-SW-130, Unit 1 Circulating Water System Effluent Line Monitor D M R Q(NOTE2)

(h) 2-RM-SW-230, Unit 2 Circulating Water System Effluent Line Monitor D M R Q(NOTE2)

2. Tank Level Indicating Device (NOTE 6)

{a) Refueling Water Storage Tanks Unit 1 1-QS-LT-lOOA, 1-QS-LT-lOOB 1-QS-LT-lOOC, 1-QS-LT-lOOD D(NOTE4) NIA R Q(NOTE7)

Unit2 2-QS-LT-200A, 2-QS-LT-200B 2-QS-LT-200C. 2-QS-LT-200D D (NOTE4) NIA R Q(NOTE7)

(b) Casing Cooling Storage Tanks Unit 1 1-RS-LT-103A, 1-RS-LT-103B D(NOTE4) NIA R Q(NOTE7)

Unit 2 2-RS-LT-203A. 2-RS-LT-203B D (NOTE4) NIA R Q(NOTE7)

(c) PG Water Storage Tanks (NOTE 5) 1-BR-LT-116A (1-PG-TK-lA) D(NOTE4) NIA R Q(NOTE8) 1-BR-LT-116B (1-PG-TK-lB) D(NOTE4) NIA R Q(NOTE8)

(d) Boron Recovery Test Tanks (NOTE 5) 1-BR-LT-112A (1-BR-TK-2A) D(NOTE4) NIA R Q(NOTE8) 1-BR-LT-112B (1-BR-TK-2B) D (NOTE4) NIA R Q(NOTE8)

3. Steam Generator (SG) High Capacity Blowdown (a) SG High Capacity Blowdown Radiation Monitor Unit 1 1-RM-SS-125 Q(NOTE 11)

Unit 2 2-RM-SS-225 D (NOTE 12) D (NOTE 12) R R(NOTE 10)

(b) SG High Capacity Blowdown Flash Tank Outlet Flowrate Unit 1 J-BD-FI'-105 D(NOTE 13) NIA R NIA Unit 2 2-BD-FI'-205 (c) SG High Capacity Blowdown Proportional Sampling System Collection Tank Unit 1 1-BD-TK-4 Unit 2 2-BD-TK-4 D (NOTE 9) NIA NIA NIA

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 60 OF 140 ATTACHMENT 4 (Page 2 of 2)

North Anna Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:

a.Automatic isolation of this pathway and Control Room alann annunciation occur if the instrument indicates measured levels above alann/trip setpoint.

b.Alarm annunciation occurs if the instrument controls are not set in "operate" mode.

NOTE 2: The Channel Functional Test shall demonstrate that Control Room alann annunciation occurs if any of the following conditions exists:

  • a.Instrument indicates measured levels above the alarm/trip setpoint b.lnstrument controls not set in "operate" mode.

NOTE 3: Channel Check shall consist of verifying indication of flow during periods of release. Channel Check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

NOTE 4: During liquid additions to the tank, verify indication of level change.

NOTE 5: This is a shared system between Unit 1 and Unit 2.

NOTE 6: Tanks included in this requirement are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTE 7: The Channel Functional Test shall demonstrate that automatic isolation of this pathway and Control Room alann annunciation occur if instrument indicates measured levels outside the alarm/trip setpoint. Demonstration of automatic isolation may consist of verifying the appropriate signal is generated. Valves need not be operated for this test.

NOTE 8: The Channel Functional Test shall demonstrate that Control Room alann annunciation occurs if the

  • instrument indicates measured levels are outside alann setpoint.

NOTE 9: Channel Check shall consist of verifying that proportional flow exceeds 0.5 mis/gallon.

NOTE 10: Channel Functional Test shall demonstrate that system isolation occurs on a radiation monitor High-High Alann.

NOTE 1-1: Channel Functional Test shall demonstrate:

a.Trip signals are generated at the required setpoints. Isolation is not required.

b.Local radiation monitor indication occurs if instrument controls are not set in "Operate" mode or if the instrument indicates measured levels are above the alarm/trip setpoint.

NOTE 12: The radiation monitor automatically performs periodic source checks. The Source Check and Channel Check are satisfied as long as the green light is lit.

NOTE 13: This is verified by indicated effluent flow less than or equal to 190 gpm.

VIRGINIA VPAP-2103.

POWER REVISION 10 PAGE 62 OF 140 A'ITACHMENT 5 (Page 2 of 3)

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

LLD= (8-1)

E

  • V
  • 2.22E+06
  • Y
  • e-(lAt)

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+o6 = the number of disintegrations per minute (dpm) per microcurie y = the fractional radiochemical yield (when applicable)

= 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.

I

)

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 61 OF 140 ATTACHMENT 5 (Page 1 of 3)

Surry Radioactive Liquid Waste Sampling and Analysis Program e

Lower Limit of Liquid Release Sampling Minimum Analy- Type of Activity Detection (LLD)

Type Frequency sis Frequency Analysis

(µCi/ml), (Note 1) p p Principle Gamma 5 X 10-1 Emitters (Note 3)

(Each Batch) (Each Batch) 1131 1 X 10-6 p Dissolved and Batch Releases M Entrained Gases 1 X 10-5 (One Batch/M)

(Gamma Emitters)

(Note 2) p M Composite H3 1 X 10-5 (Each Batch) (Note 4) Gross Alpha 1 X 10-1 .

p QComposite Sr89 and Sr90 5 X 10-8

  • (Each Batch)

Continuous (Note 6)

(Note 4)

W Composite (Note 6)

Fe55 Principal Gamma Emitters (Note 6) 1131 1 X 10-6 5 X 10-1 1 X 10-6 Dissolved and Continuous M 1 X 10-5 M Entrained Gases .

Releases Grab Sample (Gamma Emitters)

(Note 5) Continuous

  • M Composite H3 1 X 10-5 (Note 6) (Note 6) Gross Alpha 1 X 10-1 -..:::;. :

f.

Continuous QComposite Sr89 and Sr90 .. 5 X 10-8 (Note 6) (Note 6) Fe55 1 X 10-6 .-

>1i

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 63 OF 140 ATTACHMENT 5 (Page 3 of 3)

Surry Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn54, Fe59 , Co58 , Co 60, Zn65 , Mo 99 , Cs 134, Cs 137, Ce 141 , 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 to the quantity ofliquid 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 64 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 65 OF 140

  • ATTACHMENT 6 (Page 1 of 3)

North Anna Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Sampling Minimum Analy- Type of Activity Lower Limit of Type Frequency sis Frequency Analysis Detection (LLD)

(µCi/ml), (Note 1) p p Principle Gamma 5 X 10-7 Emitters (Note 3)

(Each Batch) (Each Batch) 1131 1 X 10-6 Batch Releases p M Dissolved and 1 X 10-S (One Batch/M) Entrained Gases (Gamma Emitters) (Note 8)

(Notes 2 and 7) p M Composite H3 1 X 10-S (Each Batch) (Note 4) 1 X 10-1 Gross Alpha p Q Composite Sr89 and Sr90 5 X 10-8 (Each Batch) (Note 4) Fess 1 X 10-6 Principal Gamma 5 X 10-1 Emitters (Note 6)

Continuous W Composite 1131 1 X 10-6 (Note 6) (Note 6)

Continuous u1sso1vea ana 1 X 10-.:,

Releases M Grab Sample Entrained Gases (Gamma Emitters) (Note 8) *

(Note 5) Continuous M Composite H3 1 X 10-S (Note 6) (Note 6) Gross Alpha 1 X 10-7 Continuous QComposite Sr89 and Sr90 5 X 10-8 (Note 6) (Note 6) Fess 1 X 10-6

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 66 OF 140

  • ATTACHMENT 6 (Page 2 of3)

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

LLD= (9-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (A.M)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (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+o6 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

A. = 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 then thoroughly mixed as the situation permits, to assure representative sampling.

j

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 67 OF 140 ATTACHMENT 6 (Page 3 of 3)

North Anna Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn54, Fe59 , Co58 , Co60, Zn 65 , Mo 99 , Cs 134, Cs 137, Ce 141 , 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 to the quantity ofliquid 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, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releases.

NOTE 7: Whenever the secondary coolant activity exceeds I0-5 µCi/ml, the turbine building sump pumps shall be placed in manual operation and samples shall be taken and analyzed prior to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 8: The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138. 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 68 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 69 OF 140 ATTACHMENT 7 (Page 1 of 5)

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

Frequency (µCi/ml), (Note 1)

Prior to Release A. Waste Gas Prior to Release Principal Gamma (Each Tanlc) 1 X 10-4 Storage Tank (Each Tanlc) Emitters (Note 2)

(Grab Sample)

Principle Gamma Prior to Release Prior to Release 1 X 10-4 B. Containment Emitters (Note 2)

(Each PURGE)

Purge (Each PURGE) H3 1 X 10-6 (Grab Sample)

C. Ventilation Weekly Principle Gamma Weekly 1 X 10-4 (l)Process Vent (Grab Sample) Emitters (Note 2)

(2)Vent Vent#l (3)Vent Vent#2 (Note 3) (Note 3) H3 1 X 10-6 (4)SRF Vent 1131 1 X 10- 12 Continuous Weekly (Note 5)

(Note 4) (Charcoal Sample) 1133 1 X 10-lO Continuous Weekly (Note 5) Principal Gamma 1 X 10-ll All Release (Note 4) Particulate Sample Emitter (Note 2)

Weekly Continuous Types as listed Composite Gross Alpha . 1 X 10- 11 (Note 4)

Particulate Sample in A, B, and C Quarterly Continuous Composite Sr89 and Sr90 1 X 10-ll (Note 4)

Particulate Continuous Noble Gas Noble Gases Gross (Note 4) Monitor 1 X 10-6 Beta and Gamma Principle Gamma Weekly Weekly 1 X 10-4 Condenser Air Emitters (Note 2)

Grab Sample (Note 3)

Ejector H3 1 X 10-6 (Note 3)

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 70 OF 140

  • ATTACHMENT 7 (Page 2 of 5)

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

Frequency (µCi/ml), (Note 1)

Principle Gamma 1 X 10-4 Prior to Release Prior to Release Emitters (Grab Sample) (Each Release) H3 1 X 10-6 1131 1 X 10-ll Continuous Charcoal Sample (Note 4) (Note 6) 1133 1 X 10-lO Containment Continuous Particulate Principal Gamma 1 X 10-lO Hog Depres-(Note 4) Sample (Note 6) Emitter (Note 2) surization Composite Continuous 1 X 10-lO Particulate Gross Alpha

  • (Note 4)

Sample (Note 6)

Composite Continuous Particulate Sr89 and Sr90 1 X 10-lO (Note 4)

Sample (Note 6)

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 71 OF 140 ATTACHMENT 7 (Page 3 of 5)

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

4.66 Sb LLD= (10-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (lAt)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (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+o6 = the number of disintegrations per minute (dpm) per microcurie.

Y = the fractional radiochemical yield (when applicable).

l = 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.

VIRGINIA VPAP-2103

.POWER REVISION 10 PAGE 72 OF 140 ATIACHMENT 7 (Page 4 of 5)

Surry Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87 , Kr88 , Xe 133 , Xe 133m, Xe 135 , Xe 135 m, and Xe 138 for gaseous emissions and Mn54 , Fe59 , Co58 , Co 60 , Zn65 , Mo 99 , Cs 134, Cs137 , Ce 141 and Ce 144 for 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, whe,n:

a. Analysis shows that the dose equivalent I 131 concentration in the primary coolant has increased more than a factor of 3; and
b. The noble gas activity monitor 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 or dose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: 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 I 131 concentration in the primary coolant has increased by a factor of 3; and
b. Noble gas monitor shows that effluent activity has increased more than a factor of 3 .

J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 73 OF 140

  • ATTACHMENT 7 (Page 5 of 5)

Surry Radioactiv:e Gaseous Waste Sampling and Analysis Program NOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseous effluents, composite sampling shall employ appropriate methods that will result in a specimen representative of the effluent release .

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 74 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 75 OF 140 ATTACHMENT 8 (Page 1 of 4)

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

Frequency (µCi/ml), (Note 1)

Prior to Release A. Waste Gas Prior to Release Principal Gamma 1 X 10-4 (Each Tanlc Storage Tank (Each Tank) Emitters (Note 2)

Grab Sample)

Principle Gamma Prior to Release Prior to Release 1 X 10-4 B. Containment Emitters (Note 2)

(Each PURGE Purge (Each PURGE) H3 1 X 10- 6 Grab Sample)

C. Ventilation Monthly Principle Gamma Monthly 1 X 10-4 (1) Process Vent (Grab Sample) Emitters (Note 2)

(2) Vent Vent A (Notes 3, 4, and (Note 3) H3 1 X 10-6 (3) Vent Vent B 5)

Continuous Weekly 1131 1 X 10- 12 (Note 4) (Charcoal Sample) 1133 1 X 10-lO Continuous Weekly Principal Gamma 1 X 10-ll All Release (Note 4) Particulate Sample Emitter (Note 2)

Monthly Continuous 1 X 10-ll Types as listed Composite Gross Alpha (Note 4)

Particulate Sample in A, B, and C Quarterly Continuous Composite Sr89 and Sr90 1 X 10-ll (Note 4)

Particulate Continuous Noble Gas Noble Gases Gross 1 X 10-6 (Note 4) Monitor Beta or Gamma Condenser Air Principle Gamma Weekly Weekly 1 X 10-4 Ejector/Steam Emitters (Note 7)

Generator Grab Sample H3 1 X 10-6 Blowdown Vent (Note 6)

Containment Prior to Release Principle Gamma 1 X 10-4 Prior to each Vacuum Steam Emitters (Note 2)

Ejector (Hogger) (Grab Sample)

Release H3 1 X 10-6 (Note 8)

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 76 OF 140 ATTACHMENT 8 (Page 2 of 4)

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

4.66 Sb LLD= (11-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (ALlt)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (as microcuries per unit mass or volume) (See 4.9)

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+o6 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

A = 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 as "posteriori" (after the fact) limit for a particular measurement.

_J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 77 OF 140

  • ATTACHMENT 8 (Page 3 of 4)

North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr8 7, Kr88 , Xe 133 , Xe 133 m, Xe 135 , Xe 135 m, and Xe 138 for gaseous emissions and Mn54, Fe59 , Co58 , Co 60, Zn65 , Mo 99 , Cs 134, Cs 137 , Ce 141 and Ce 144 for particulate emissions. 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 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, if:

a. Analysis shows that the dose equivalent 1131 concentration in the primary coolant is greater than 1.0 µCi/gm; and
b. The noble gas activity monitor 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 or dose rate calculation made in accordance with 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: 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 I 131 concentration in the primary coolant is greater than 1.0 µCi/gm and;
b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 78 OF 140 ATTACHMENTS (Page 4 of 4)

North Anna Radioactive Gaseous Waste Sampling and Analysis Program NOTE 6: Whenever the secondary coolant activity exceeds 10-s µCi/ml, samples shall be obtained and analyzed weekly. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 7: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87 , Kr8 8 , Xe 133 , Xe 133 m, Xe 135 , Xe 135 m, and Xe 138 for gaseous emissions. 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 8: If the secondary coolant activity level in any Steam Generator supplying steam to the Hogger exceeds 1.0E-5 µCi/ml, Steam Generator samples shall be obtained and analyzed prior to release.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 79 OF 140 ATTACHMENT 9 (Page 1 of 3)

Gaseous Effluent Dose Factors for North Anna (Gamma and Beta Dose Factors)

X}Q = 9.3E-06 sec/m3 at 1416 meters SE Direction Dose Factors for Ventilation Vent Noble Gas Kivv ~vv Mivv Nivv Radionuclide Total Body Skin Gamma Air Beta Air mrem/yr mrem/yr mrad/yr mrad/yr Curie/sec Curie/sec Curie/sec Curie/sec Kr-85m 1.09E+04 1.36E+04 1.14E+04 1.83E+04 Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E+04 Kr-87 5.51E+04 9.05E+04 5.74E+04 9.58E+04 Kr-88 1.37E+05 2.20E+04 1.41E+05 2.72E+04 Kr-89 1.54E+05 9.39E+04 1.61E+05 9.86E+04 Xe-131m 8.51E+02 4.43E+03 1.45E+03 l.03E+04 Xe-133m 2.33E+03 9.24E+03 3.04E+03 1.38E+04 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 Xe-135 1.68E+04 1.73E+04 1.79E+04 2.29E+04 Xe-137 1.32E+04 1.13E+05 1.40E+04 l.18E+05 Xe-138 8.21E+04 3.84E+04 8.57E+04 4.42E+04 Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 80 OF 140 ATTACHMENT 9 (Page 2 of 3)

Gaseous Effluent Dose Factors for North Anna (Gamma and Beta Dose Factors) x/Q = l.2E-06 sec/m3 at 1513 meters S Direction

  • Dose Factors for Process Vent Noble Gas Kipv Lipv Mipv Nipv Radionuclide Total Body Skin Gamma Air Beta Air mrem/yr mrem/yr mrad/yr mrad/yr Curie/sec Curie/sec Curie/sec Curie/sec Kr-85m l.40E+03 l.75E+03 l.48E+03 2.36E+03 Kr-85 l.93E+Ol l.61E+03 2.06E+Ol 2.34E+03 Kr-87 7.I0E+03 1.17E+04 7.40E+03 1.24E+04 Kr-88 l.76E+04 2.84E+03 l.82E+04 3.52E+03 Kr-89
  • l.99E+04 l.21E+04 2.08E+04 l.27E+04 Xe-131m 1.I0E+02 5.71E+02 l.87E+02 l.33E+03 Xe-133m 3.01E+02 l.19E+03 3.92E+02 l.78E+03 Xe-133 3.53E+02 3.67E+02 4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23E+03 2.30E+03 2.95E+03 Xe-137 1.70E+o3 l.46E+04 l.81E+03 l.52E+04 Xe-138 l.06E+04 4.96E+03 l.11E+o4 5.70E+03 Ar-41 l.06E+04 3.23E+03 l.12E+04 3.94E+03

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 81 OF 140 A'ITACHMENT 9 (Page 3 of 3)

Gaseous Effluent Dose Factors for North Anna (Inhalation Pathway Dose Factors)

Ventilation Vent X)Q = 9.3E-06 sec/m3 at 1416 meters SE Direction Process Vent X)Q = 1.2E-06 sec/m3 at 1513 meters S Direction Radionuclide Pivv Pipv mrem/yr mrem/yr Curie/sec Curie/sec H-3 1.05E+04 1.35E+03 Cr-51 7.95E+02 1.02E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 5.64E+04 7.28E+03 Te-129m 5.88E+04 7.59E+03 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND 1-131 1.51E+08 1.95E+07 1-133 3.58E+07 4.62E+06 ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 82 OF 140 fl Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 83 OF 140 ATTACHMENT 10 (Page 1 of 3)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION 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 Process Vent Continuous HP Sampler, or 1 2 l-GW-RM-130-1 (d) Process Vent Flow Rate Monitor ..

1-GW-FI'~lOO 1 3 (e) Sampler Flow Rate Measuring Device KAMAN Flow Rate Measuring Device 1 3 (Parameter #19), or HP Sampler Rotometer

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor 1-SV-RM-111 2 (one per unit) 1 2-SV-RM-211 (b) Air Ejector Flow Rate Measuring Device Unit 1: 1-VP-FI-lA 1-VP-FI-lB 2 (one per unit) 3 Unit 2: 2:-VP-FI-lA 2-VP-FI-lB
3. VENTILATION VENT SYSTEM (a) Noble Gas Activity Monitor SRF: RRM-101 1 1 SPS: Vent#l l-VG-RM-104 1 1 Vent#2, 1-VG-RM-110, or 1 1 1-VG-RM-131-1

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 84 OF 140 ATTACHMENT 10 (Page 2 of 3)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS (b) Iodine Sampler SRF: RRM-101 1 2 SPS: Vent#l, 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#l, 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: 01-RHV-Ff-156 1 3 SPS: Vent #1, 1-VS-Ff-119 1 3 Vent #2, 1-VS-Ff-116 1 3 (e) Sampler Flow Rate Measuring 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

_J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 85 OF 140

  • ACTION 1:

ATTACHMENT 10 (Page 3 of 3)

Surry Radioactive Gaseous Effluent Monitoring. Instrumentation 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 Attachment 7.

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 />.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 86 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 87 OF 140

  • ATTACHMENT 11 (Page 1 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM ACTION OPERABLE CHANNELS

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor l-RM-GW-102 1 2,4 l-RM-GW-178-1 (NOTE 3)

(b) Iodine Sampler l-RM-GW-178-1 1 2,5 Process Vent Continuous HP Sampler (NOTE3)

(c) Particulate Sampler l-RM-GW-178-1 1 2,5 Process Vent Continuous HP Sampler (NOTE 3)

(d) Total Flow Monitor l-GW-Ff-108 1 1 (e) Sampler Flow Rate Measuring Device K.AMANS Flow Rate Measuring Device (Parameter 19) 1 HP Sampler Rotameter 1 (NOTE 3)

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity Monitor Unit 1 1-SV-RM-121 Unit2 2-SV-RM-221 1 3 (b) Flow Rate Measuring Device Unit I 1-SV-FI-IOOA 1-SV-FI-IOIA 1-SV-FI-IOOB 1 (NOTE 1) 1 1-SV-FI-lOIB Unit2 2-SV-FI-200A 2-SV-FI-201A 2-SV-FI-200B - 1 (NOTE 2) 1 2-SV-FI-201B

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 88 OF 140 ATTACHMENT 11 (Page 2 of3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation MINIMUM INSTRUMENT OPERABLE ACTION CHANNELS

3. VENTILATION VENT A (a) Noble Gas Activity Monitor 1-RM-VG-104 1 1-RM-VG-179-1 2 (NOTE 3)

(b) Iodine Sampler 1-RM-VG-179-1 1 Vent Vent A Continuous HP Sampler 2

(NOTE3)

(c) Particulate Sampler 1-RM-VG-179-1 1 2

Vent Vent A Continuous HP Sampler (NOTE 3)

(d)

(e)

Total Flow Monitor 1-HV-Ff-1212A Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19)

HP Sampler Rotameter 1

1 (NOTE 3) 1 1

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-1_13 1 1-RM-VG-180-1 2

(NOTE 3)

(b) Iodine Sampler 1-RM-VG-180-1 1 2

Vent Vent B Continuous HP Sampler (NOTE 3)

(c) Particulate Sampler 1-RM-VG-180-1 1 2

Vent Vent B Continuous HP Sampler (NOTE 3)

(d) Total Flow Monitor 1-HV-Ff-1212B 1 1 (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring Device (Parameter 19) 1 HP Sampler Rotameter 1

NOTE3

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 89 OF 140

  • ATTACHMENT 11 (Page 3 of 3)

North Anna Radioactive Gaseous Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases, via this path, may continue if the flow rate is estimated at least once per four hours.

ACTION 2: If the number of operable channels is less than required, effluent releases, via this path, may continue if 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 or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 3: If the number of operable channels is less than required, effluent releases, via this path, may continue if the frequency of the grab samples provided by Technical Specification requirement 4.4.6.3.b is increased to at least once per four hours and these samples are analyzed for gross activity or gamma isotopic activity within eight hours.

ACTION 4: If the number of operable channels is less than required, the contents of the Waste Gas Decay Tanks may be released to the environment provided that prior to initiation of the release:

a. At least two independent samples of the tank's contents are analyzed, and:
b. At least two technically qualified members of the Station staff independently verify

~e release rate calculations and discharge valve lineup.

  • ACTION 5: If the number of operable channels is less than required, effluent releases from the Waste Gas Decay Tank may continue provided samples are continuously collected with auxiliary sampling equipment as required in Attachment 8.

NOTE 1: A channel shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (1-SV-FI-lOOA, 101A), or Train B (1-SV-FI-lOOB, 101B) or both.
b. Flow instruments 101A and 101B provide low range measurement. Flow instruments lOOA and lOOB provide high range measurement.

NOTE 2: A channel shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (2-SV-FI-200A, 201A), or Train B (2-SV-FI-200B, 201B) or both.
b. Flow instruments 201A and 201B provide low range measurement Flow instruments 200A and 200B provide high range measurement.

NOTE 3: A channel shall consist of either the release pathway's Kaman monitor, its associated iodine and particulate sampler and sampler flowrate measuring device or the release pathway's Westinghouse monitor, HP iodine and particulate monitor and HP Sampler Rotameter.

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  • ATTACHMENT 12 (Page 1 of 2)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation SurveiJlance Requirements CHANNEL CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL TEST

l. .t'ROC.E.S.S V 1.:sr.:sfEM (a) Noble Gas Activity Monitor -

Providing Alann and Automatic Termination of Release l-GW-RM-102 D M,* R Q l-GW-RM-130-1 (b) Iodine Sampler Process Vent Continuous HP Sampler, or 1-GW-RM- 130-1 w NIA NIA NIA (c) Particulate Sampler Process Vent Continuous HP Sampler, or 1-GW-RM- 130-1 w NIA NIA NIA (d) Process Vent Flow Rate Monitor I-GW-Ff-100 D NIA R NIA (e) Sampler Flow Rate Measuring Device HP Sampler Rotometer, or D NIA SA NIA KAMAN Flow Rate Measuring D NIA R NIA Device (Parameter#19)

2. CONDENSER AIR EJECTOR SYSTEN.

(a) Gross Activity Monitor Unit I: 1-SV-RM-111 D M R Q Unit2: 2-SV-RM-211 (b) Air Ejector Flow Rate Measuring '*.

Device Unit I: I-VP-FI-IA 1-VP-FI-IB Unit 2: 2-VP-FI-lA D NIA R NIA 2-VP-FI-IB

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 92 OF 140 ATTACHMENT 12 (Page 2 of 2)

Surry Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL - CHANNEL SOURCE CHANNEL CHANNEL DESCRIPTION CHECK CHECK CALIBRATION FUNCTIONAL TEST (b) Iodine Sampler SRF: RRM-101 SPS: Vent#l, 1-VG-RM-104 Vent#2,ContinuousHP w NIA NIA NIA Sampler or 1-VG-RM-131-1 (c) Particulate Sampler SRF: RRM-101 SPS: Vent#l, 1-VG-RM-104 Vent #2, Continuous HP w NIA NIA NIA Sampleror 1-VG-RM-131-1 (d) Ventilation Vent Flow Rate Monitor SRF: Ol-RHV-FT-156 SPS: Vent#l, 1-VS-FT-119 Vent#2~ 1-VS-FT-116 D NIA R NIA (e) Sampler Flow Rate Measuring Device SRF: RRM-101 D NIA R NIA SPS: Vent#l, 1-VG-RM-104 D NIA R NIA Vent#2,KAMANFiowRate D NIA R NIA Measuring Device (Parameter #19), or HP D NIA NIA Sampler Rotometer SIA

"' .t'Ilor to each waste Uas lJecay 1an1c release

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 93 OF 140

  • ATTACHMENT 13 (Page 1 of 3)

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

1. PROCESS VENT SYSTEM (a) Noble Gas Activity Monitor 1-RM-GW-102 D M R Q (NOTE 1) 1-RM-GW-178-1 D M(NOTE5) R Q (NOTE 1)

(b) Iodine Sampler 1-RM-GW-178-1 w NIA NIA NIA Process Vent Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-GW-178-1 w NIA NIA NIA Process Vent Continuous HP D(NOTE3) NIA NIA NIA Sampler*

(d) Total Flow Monitor 1-GW-FT-108 D NIA R Q (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE3) NIA R NIA Device (Parameter 19)

HP Sampler Rotameter D(NOTE3) NIA SA NIA

2. CONDENSER AIR EJECTOR SYSTEM (a) Noble Gas Activity Monitor Unit 1 1-SV-RM-121 D M R Q (NOTE 1)

Unit 2 2-SV-RM-221 (b) Flow Rate Measuring Device Unit 1 1-SV-FI-lOOA 1-SV-FI-lOlA 1-SV-FI-lOOB D NIA R NIA 1-SV-FI-lOIB Unit2 2-SV-FI-200A 2-SV-FI-201A 2-SV-FI-200B D NIA R NIA 2-SV-FI-20IB

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 94 OF 140 ATTACHMENT 13 (Page 2 of 3)

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

3. VENTILATION VENT A (a) Noble Gas Activity Monitor 1-RM-VG-104 D M R Q (NOTE2) 1-RM-VG-179-1 D M(NOTES) R Q(NOTE2)

(b) Iodine Sampler 1-RM-VG-179-1 w NIA NIA NIA Vent Vent A Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-VG-179-1 w NIA NIA NIA Vent Vent A Continuous HP Sampler D(NOTE3) NIA NIA NIA (d) Total Flow Monitor 1-HV-FI'-1212A D NIA Q R

(e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE3) NIA R NIA Device (Parameter 19)

HP Sampler Rotameter D(NOTE3) NIA SA NIA

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-RM-VG-113 D M R Q (NOTE4) 1-RM-VG-180-1 D M(NOTES) R Q(NOTE2)

(b) Iodine Sampler 1-RM-VG-180-1 w NIA NIA NIA Vent Vent B Continuous HP Sampler D(NOTE3) NIA NIA NIA (c) Particulate Sampler 1-RM-VG-180-1 w NIA NIA NIA Vent Vent B Continuous HP Sampler D(NOTE3) NIA NIA NIA (d) Total Flow Monitor 1-HV-FI'-1212B D NIA R Q (e) Sampler Flow Rate Measuring Device KAMANS Flow Rate Measuring D(NOTE3) NIA R NIA Device (Parameter 19)

HP Sampler Rotameter D(NOTE3) NIA SA NIA

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  • ATTACHMENT 13 (Page 3 of 3)

North Anna Radioactive Gaseous Effluent Monitoring InstrumentationSurveillance Requirements NOTE 1: The Channel Functional Test shall demonstrate:

a. Automatic actuation of the valves in this pathway and Control Room alarm annunciation occur if the instrument indicates measured levels above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instrument controls not set in "operate" mode.

NOTE 2: The Channel Functional Test shall demonstrate:

a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instrument controls not set in "operate" mode.

NOTE 3: Channel Checks shall consist of verifying indication of flow during periods of release.

Channel .Checks shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous,

  • periodic, or batch releases are made.

NOTE 4: The Channel Functional Test shall demonstrate that:

a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above alarm/trip setpoint
b. The Instrument mode selection control automatically resets to "operate" mode when released.

NOTE 5: Monitors 1-RM-GW-178-1, 1-RM-VG-179-1, and 1-RM-VG-180-1 are electronically source checked using an LED .

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  • ATTACHMENT 14 (Page 1 of 1)

Critical Organ Dose Factors for North Anna (Critical Pathway Dose Factors)

Ventilation Vent D/Q = 2.4E-09. m- 2 at 3250 meters N Direction

  • Process Vent D/Q = 1.lE-09 m-2 at 3250 meters N Direction Radionuclide RMivv RMipv mrem/yr mrem/yr Curie/sec Curie/sec H-3 1.73E+03 9.36E+02 Mn-54 ND ND Fe-59 ND ND Cr-51 1.50E+02 6.89E+Ol Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND
  • Sr-90 Y-91 Zr-95 Nb-95 ND ND ND ND ND ND ND ND Ru-103 ND* ND Ru-106 ND ND Ag-llOm ND ND Te-127m 1.97E+05 9.04E+04 Te-129m 2.95E+05 1.35E+05 I-131 1.45E+09 6.72E+08 I-133 1.33E+07 6.12E+06 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND ND - No data for dose factor accordmg to Regulatory Gmde 1.109, Rev1s10n 1

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_J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 99 OF 140

  • ATTACHMENT 15 (Page 1 of 3)

Surry 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 Monitoring Stations to be placed as follows:
1) Inner Ring in general area of site boundary with station in each GAMMA DOSE sector
2) Outer Ring 6 to 8 km from the site with a Quarterly Quarterly station in each sector
3) The balance of the 8 dosimeters should be
  • placed in special interest areas such as population centers, nearby residents, schools, and in 2 or 3 areas to serve as controls
2. AIRBORNE Samples from 7 locations:

a) 1 sample from close to the site boundary location of the highest Radioiodine Canister calculated annual I 131 Analysis Weekly average ground level Continuous Radioiodines and D/Q Sampler Particulates b) 5 sample locations 6-8 operation with Particulate 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 15-30 km Gamma isotopic analysis distant, providing valid of composite (by background data location) quarterly

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 100 OF 140 ATTACHMENT 15 (Page 2 of 3)

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

3. WATERBORNE Gamma isotopic analysis a) 1 sample upstream monthly; a) Surface Monthly Sample b) 1 sample downstream Composite for tritium analysis quarterly Sample from 1 or 2 sources Gamma isotopic and tritium b) Ground Quarterly analysis quarterly c) Sediment a) 1 sample upstream Gamma isotopic analysis from Semi-Annually b) 1 sample downstream semi-annually shoreline 2 samples from vicinity of Gamma isotopic analysis d) Silt Semi-Annually the Station semi-annually .
4. INGESTION a) Milk *a) 3 samples from milking animals in the vicinity of Composite for Sr89/Sr 90 (NOTE 1) the Station analysis quarterly b) 1 sample from milking Monthly animals at a control Gamma isotopic and I 131 location (15-30 km analysis monthly distant) a) 2 samples of oysters in the vicinity of the Semi-Annually Gamma isotopic on edibles Station b) 4 samples of clams in the vicinity of the Semi-Annually Gamma isotopic on edibles b) Fish and Station Invertebrates c) 1 sampling of crabs from the vicinity of the Annually Gamma isotopic on edibles Station d) 2 samples of fish from the vicinity of the Semi-Annually Gamma isotopic on edibles Station (catfish, white perch, eel)

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  • ATTACHMENT 15 (Page 3 of 3)

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

4. INGESTION (Continued) a) 1 sample com Gamma isotopic on edible b) 1 sample soybeans Annually portion c) 1 sample peanuts d) 1 sample of a broadleaf vegetation of two different available offsite locations with highest annual average -,.,,.

c) Food ground level D/Q, if one Products or more milk samples Monthly, if Gamma isotopic and I 131 are unavailable available, or at analysis e) 1 sample of a broadleaf harvest vegetation grown 15-30 km in the available, least prevalent wind direction, if one or more milk samples are unavailable NOTE 1: If milk sampling cannot be performed, use item 4.c (d).

  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 102 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 103 OF 140

  • ATTACHMENT 16 (Page 1 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2) Frequency Analysis

1. DIRECT RADIATION (NOTE 3) 36 routine monitoring stations, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:
1) An inner ring of stations, one in each emergency GAMMA DOSE meteorological sector within the site boundary
2) An outer ring of stations, one in each emergency meteorological sector Quarterly Quarterly within 8 km range from the site
3) The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 104 OF 140 ATTACHMENT 16 (Page 2 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2) Frequency Analysis .

2. AIRBORNE Samples from 5 locations:

a) 3 samples from close to the 3 site boundary locations (in different sectors) of the highest Radioiodine Canister I 131 Analysis, weekly calculated historical annual average ground Continuous Radioiodines and levelD/Q sampler, Particulates b) 1 sample from the operation with vicinity of a community sample Particulate Sampler ..

having the highest collection Gross beta radioactivity calculated annual weekly analysis following filter average ground level change; (NOTE 4) 0/Q c) 1 sample from a control Gamma isotopic analysis location 15-40 km of composite (by distant and in the least location) quarterly prevalent wind directio11 (NOTE5)

3. WATERBORNE Samples from 3 locations:

Gamma isotopic analysis a) 1 sample upstream monthly; (NOTE 5) a) Surface b) 1 sample downstream Grab Monthly Composite for tritium c) 1 sample from cooling analysis quarterly lagoon Sample from I or 2 sources Gamma isotopic and tritium b) Ground only if likely to be affected Grab Quarterly analysis quarterly (NOTE 5) 1 sample from downstream Gamma isotopic analysis c) Sediment area with existing or Semi-Annually semi-annually (NOTE 5) potential recreational value

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  • ATTACHMENT 16 (Page 3 of 5)

North Anna Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Sample Collection Type and Frequency of and/or Sample Location (NOTE 2) Frequency Analysis

4. INGESTION a) Samples from milking animals in 3 locations within 5 km that have the highest potential. If there are none, then 1 sample from milking animals in each of 3 areas a) Milk between 5 to 8 km where Monthly at all Gamma isotopic (NOTE 5)

(NOTE 7) doses are calculated to be times and I 131 analysis monthly greater than 1 mrem per yr (NOTE 6) b) 1 sample from millcing animals at a control location (15-30 km in the least prevalent wind direction) a) 1 sample of commercially and recreationally important species (bass, sunfish, catfish) b) Fish and in vicinity of plant discharge Gamma isotopic on edible Semiannually Invertebrates area portions b) 1 sample of same species in areas not influenced by plant discharge a) Samples of an edible broad leaf vegetation grown nearest each of two different offsite locations of highest predicted historical annual average Monthly if c) Food ground level 0/Q if millc Gamma isotopic (NOTE 5) available, or Products sampling is not performed and I 131 analysis at harvest b) 1 sample of broad leaf vegetation grown 15-30 km in the least prevalent wind direction if milk sampling is not performed

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 106 OF 140 ATTACHMENT 16 (Page 4 of 5)

North Anna Radiological Environmental Monitoring Program NOTE 1: The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable.

Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and be included in the sampling program.

NOTE 2: For each and every sample location in Attachment 18, specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, shall be provided in Attachment 18. Refer to Radiological Assessment Branch Technical Positions and to NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plant Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

If specimens are unattainable due to sampling equipment malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to 6.7 .1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. In lieu of a Licensee Event Report and pursuant to 6.7.2, identify the cause of the unavailability of samples for that pathway and identify the new locations for obtaining replacement samples in the next Annual Radioactive Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report

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  • ATTACHMENT 16 (Page 5 of 5)

North Anna Radiological Environmental Monitoring Program NOTE 3: One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The 36 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

NOTE 4: Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> .

or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

NOTE 5: Gamma isotopic analysis is the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from the facility. *

  • NOTE 6: The dose shall be calculated for the maximum organ and age group, using the m~thodology and parameters in the ODCM.

NOTE 7: If milk sampling cannot be performed, use item 4.c (Page 3 of 5, Attachment 16) .

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  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 109 OF 140
  • ATTACHMENT 17 (Page 1 of 4)

Surry Environmental Sampling Locations SAMPLE LOCATION DISTANCE DffiECTION REMARKS MEDIA (MILES)

Air Charcoal Site Boundary and Particulate Surry Station (SS) 0.37 NNE Location at Sector with Highest D/Q Hog Island Reserve (HIR) 2.0 NNE Bacons Castle (BC) 4.5 SSW Alliance (ALL) 5.1 WSW

  • Colonial Parkway (CP) 3.7 NNW Dow Chemical (DOW) 5.1 ENE Fort Eustis (FE) 4.8 ESE Newport News (NN) 16.5 ESE Control Location Environmental Control (00). Onsite **

TLDs West North West (02) 0.17 WNW Site Boundary Surry Station Discharge (03) 0.6 NW Site Boundary North North West (04) 0.4 NNW Site Boundary North (05) 0.29 N Site Boundary North North East (06) 0.28 NNE Site Boundary North East (07) 0.31 NE Site Boundary East North East (08) 0.43 ENE Site Boundary East (Exclusion) (09) 0.31 E Exclusion Area Boundary West (10) 0.40 w Site Boundary West South West (11) 0.45 WSW Site Boundary South West (12) 0.30 SW Site Boundary South South West (13) 0.43 SSW Site Boundary South (14) 0.48 s Site Boundary South South East (15) 0.74 SSE Site Boundary South East (16) 1.00 SE Site Boundary East (17) 0.57 E Site Boundary Station Intake (18) 1.23 ESE Site Boundary Hog Island Reserve (19) 1.94 NNE Near Resident

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 110 OF 140 ATTACHMENT 17 (Page 2 of 4)

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

Environmental Bacons Castle (20) 4.45 SSW Approx. 5 miles TLDs Route 633 (21) 5.0 SW Approx. 5 miles Alliance (22) 5.1 WSW Approx. 5 miles

  • surry (23) 8.0 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) 3.7 NNW Approx. 5 miles Route 617 and 618 (28) 4.7 NNW Approx. 5 miles Kingsmill (29) 4.8 N Approx. 5. miles Williamsburg (30) 7.8 N Population Center Kingsmill North (31) 5.6 NNE Approx. 5 miles Budweiser (32) 5.7 NNE Population Center Water Plant (33) 4.8 NE Approx. 5 miles Dow (34) 5.1 ENE Approx. 5 miles Lee Hall (35) 7.1 ENE Population Center Goose Island (36) 5.0 E Approx. 5 miles Fort Eustis (37) 4.8 ESE Approx. 5 miles Newport News (38) 16.5 ESE Population Center James River Bridge (39) 14.8 SSE Control Benn's Church (40) 14.5 s Control Smithfield (41) 11.5 s Control Rushmere (42) 5.2 SSE Approx. 5 miles Route 628 (43) 5.0 s Approx. 5 miles Milk Epp's 4.8 SSW Colonial Parkway 3.7 NNW Pivamik 21.5 NE Control Location

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  • ATTACHMENT 17 (Page 3 of 4)

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

Well Water Surry Station Onsite***

Hog Island Reserve 2.0 NNE Crops (Com, Slade's Fann 2.4 s Peanuts, Soybeans) Brock's Fann 3.8 s Crops Spratley's Garden 3.2 s (Cabbage, Kale) Carter's Grove Garden 4.8 NE Control Location Lucas's Garden (Chester, Va.)

River Water Surry Discharge 0.17 NW (Monthly) Scotland Wharf 5.0 WNW Control Location Sediment Chickahominy River 11.2 *WNW Control Location (Silt) Surry Station Discharge 1.0 NW

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 112 OF 140 ATTACHMENT 17 (Page 4 of 4)

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

Clams Chickahominy River 11.2 WNW Control Location Surry Station Discharge 1.3 NW Hog Island Point 2.4 NNE Lawne's Creek 2.4 SE Oysters Kingsmill 2.9 NNE Mulberry Point 4.9 SE Crabs Surry Station Discharge 0.6 NW Fish Surry Station Discharge 0.6 NW Shoreline Hog Island Reserve 0.8 N Sediment Chi~kahominy River 11.2 WNW Control Location Onsite Location - in Lead Shield Onsite sample of Well Water-taken from tap-water at Surry Environmental Building

  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 113 OF 140
  • ATTACHMENT 18 (Page 1 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Frequency Environment NAPS Sewage Treatment Quarterly &

01 0.20 NE On-Site al Plant Annually TI.Os 02 SSW Quarterly &

Frederick's Hall 5.30 Annually Mineral.VA 03 7.10 WSW Quarterly &

Annually Quarterly &

Wares Crossroads 04 5.10 WNW Annually Quarterly &

Route 752 05 4.20 NNE Annually Quarterly &

Sturgeon's Creek Marina 05A 3.20 N .....

Annually Levy, VA 06 4.70 Quarterly &

ESE Annually Bumpass, VA 07 SSE Quarterly&

7.30 Annually.

End of Route 685 21 1.00 WNW Quarterly & Site Boundary Annually Route 700 22 WSW IQuarterly & Site Boundary 1.00 Annually "Aspen Hills" 23 Quarterly & Site Boundary 0.93 SSE Annually Orange, VA 24 22.00 NW Quarterly & Control Annually Bearing Cooling Tower N-1/33 0.06 N Quarterly On-Site Sturgeon's Creek Marina N-2/34 3.20 N Quarterly*

Parking Lot "C" NNE-3/35 0.24 NNE Quarterly On-Site Good Hope Church NNE-4/36 4.96 NNE Quarterly Parking Lot "B" NE-5/37 0.20 NE Quarterly On-Site Bogg's Drive NE-6/38 1.46 NE Quarterly Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-Site Route 689 ENE-8/40 2.43 ENE Quarterly Near Training Facility E-9/41 0.30 E Quarterly On-Site "Morning Glory Hill" E-10/42 2.85 E Quarterly Island Dike ESE-11/43 0.12 ESE Quarterly On-Site Route 622 ESE-12/44 4.70 ESE Quarterly

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 114 OF 140 ATTACHMENT 18 (Page 2 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Freauency Environment Quarterly Biology Lab SE-13/45 0.75 SE On-Site al Tl.Os Route 701 (Dam Entrance SE-14/46 5.88 SE Quarterly "Aspen Hills" SSE-15/47 0.93 SSE Quarterly Site Bounda.I)

Elk Creek SSE-16/48 2.33 SSE Quarterly NAPS Access Road S-17/49 0.47 s Quarterly On-Site Elk Creek Church S-18/50 1.55 s Quarterly NAPS Access Road SSW-19/51 0.42 SSW Quarterly On-Site Route 618 SSW-20/52 5.30 SSW Quarterly 500KVTower SW-21/53 0.60 SW Quarterly On-Site Route 700 SW-22/54 4.36 SW Quarterly NAPS Radio Tower WSW-23/55 0.38 WSW Quarterly On-Site Route 700 South Gate of Switchyard Route 685 End of Route 685 Route 685 WSW-24/56 W-25/57 W-26/58 WNW-27/59 WNW-28/60 1.00 0.32 1.55 1.00 1.40 WSW WNW WNW w

w Quarterly Site Boundary Quarterly On-Site Quarterly Quarterly Site Boundary Quarterly Laydown Area North Gate NW-29/61 0.45 NW Quarterly On-Site Lake Anna Campground NW-30/62 2.54 NW Quarterly*

  1. 1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-Site Route 208 NNW-32/64 3.43 NNW Quarterly Bumpass Post Office C-1/2 7.30 SSE Quarterly Control Orange, VA C-3/4 22.00 NW Quarterly Control Mineral, VA C-5/6 7.10 WSW Quarterly Control Louisa, VA C-7/8 11.54 .WSW Quarterly Control

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 115 OF 140

  • ATTACHMENT 18 (Page 3 of 4)

.North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS

  • Media No. (Miles) Frequency Airborne NAPS Sewage Treatment 01 0.20 NE Weekly On-Site Plant Particulate Frederick's Hall 02 5.30 SSW Weekly and Mineral, VA 03 7.10 WSW Weekly Radioiodine Wares Crossroads 04 5.10 WNW Weekly Route 752 05 4.20 NNE Weekly Sturgeon's Creek Marina 05A 3.20 N Weekly Levy, VA 06 4.70 ESE Weekly Bumpass, VA 07 7.30 SSE Weekly End of Route 685 21 1.00 WNW Weekly Site Boundary Route700 22 1.00 WSW Weekly Site .Boundary "Aspen Hills" 23 0.93 SSE Weekly Site Boundary Orange, VA 24 22.00 NW Weekly Control Surface Water Waste Heat Treatment
  • [Commitment Facility (Second Cooling 08 1.10 SSE Monthly 3.2.2) Lagoon)

North Anna River (upstream) Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brook's Bridge)

North Anna River 11 5.80 SE Monthly (downstream) '<'**

Ground Water OlA SE Quarterly Biology Lab 0.75 (well water) .

Aquatic. Waste Heat Treatment

  • Sediment Facility (Second Cooling 08 1.10 SSE Semi-Annually Lagoon)

North Anna River (upstream) Rt 669 Bridge 09A 12.9 WNW Semi-Annually Control (Brook's Bridge)

North Anna River 11 5.80 SE Semi-Annually (downstream)

Shoreline Soil LakeAnna 08 1.10 SSE Semi-Annually Soil NAPS Sewage Treatment 01 0.20 NE Once per 3 yrs On-Site Plant

viRGINIA VPAP-2103 POWER REVISION 10 PAGE 116 OF 140 ATTACHMENT 18 (Page 4 of 4)

North Anna Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection REMARKS Media No. (Miles) Freouency Soil Fredericks Hall 02 5.30 SSW Once per 3 yrs (continued) Mineral, VA 03 7.10 WSW Once per 3 yrs Wares Crossroads 04 5.10 WNW Once per 3 yrs Route 752 05 4.20 NNE Once per 3 yrs Sturgeon's Creek Marina 05A 3.20 N Once per 3 yrs Levy, VA 06 4.70 ESE Once per 3 yrs Bumpass, VA 07 7.30 SSE Once per 3 yrs End of Route 685 21 1.00 WNW. Once per 3 yrs Site Boundary Route 700 22 1.00 WSW Once per 3 yrs Site Boundary "Aspen Hills" 23 0.93 SSE Once per 3 yrs Site Boundary Orange, VA 24 22.00 NW Once per 3 yrs Control Milk Holladay Dairy 12 8.30 NW Monthly (R.C. Goodwin)

Fish Terrell's Dairy (Frederick's Hall)

Waste Heat Treabnent Facility (Second Cooling Lagoon) 13 08 5.60 1.10 SSE SSE Monthly Semi-Annually

  • Semi-Lake Orange 25 16.50 NW Control Annually Food Products Route 713 14 varies NE (Edible varies*

Route 614 15 SE Monthly broadleaf if available, vegetation8 ) Route 629/522 16 varies NW Control or at harvest Route 685 21 varies WNW "Aspen Hills" Area 23 varies SSE

a. If edible broadleaf vegetation is unavailable, non-edible vegetation of similar leaf characteristics may be substituted.
  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 117 OF 140
  • ATTACHMENT 19 (Page 1 of 2)

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

Airborne Food Fish Sediment Analysis Water Particulate Milk Products (pCi/kg) (pCi/kg)

(NOTE2) (pCi/1) or Gases (pCi/1) (pCi/kg)

(wet) (wet)

(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 Nb-95 15 I-131 (NOTE 3) I 0.07 I 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 NOTE I: Required detection capabilities for thermoluminescent dosimeters used for environmental

NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above miclides, shall also be identified and reported.

NOTE 3: LLD for the Ground (drinking) Water Samples. The LLD for the surface (non-drinking) water samples is 10 pCi/1.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 118 OF 140 ATTACHMENT 19 (Page 2 of 2)

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

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

4.66 Sb LLD= (24-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (A.At)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (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+o6 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

A = 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 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 measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 119 OF 140 ATTACHMENT20 (Page 1 of 2)

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

Airborne Food Fish Sediment Analysis Water Particulate Milk Products (pCi/kg) (pCi/kg)

(NOTE2) (pCi/1) or Gases (pCi/1) (pCi/kg)

(wet) (wet)

(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 Nb-95 15 1-131 (NOTE3) 1 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks 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)

  • water samples is 10 pCi/1.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 120 OF 140 ATTACHMENT20 (Page 2 of 2)

Detection Capabilities for North Anna Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD) (NOTE 3)

NOTE 3: For a particular measurement system (which may include radiochemical separation):

LLD= (25-1)

E

  • V
  • 2.22E+06
  • Y
  • e- (11.At)

Where:

LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above (as microcuries per unit mass or volume) (See 4.9)

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+o6 = the number of disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical yield (when applicable)

11. = the radioactive decay constant for the particular radionuclide At = the elapsed time between sample collection (or end of the sample collection period) and ti.me of counting (for environmental samples, not 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 measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 121 OF 140

  • ATTACHMENT 21 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples at Surry Airborne . Milk Water Fish Food Products Analysis Particulate or (pCi/1) (pCi/kg, wet) (pCi/J) (pCi/kg, wet)

Gases (pCi/m3)

H-3 30,000 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 1-131 (NOTE 1) 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NOTE 1: Reporting level for the ground (drinking) water samples required by Attachment 15. The reporting level for the surface (non-drinking) water samples required by Attachment 15 is 20 pCi/1.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 122 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 123 OF 140

  • ATTACHMENT 22 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples at North Anna Airborne Water Fish Milk Food Products Analysis Particulate or (pCi/1) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

Gases (pCifm3)

(NOTE 1)

H-3 20,000 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 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking water samples

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 124 OF 140 Intentionally Blank

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 125 OF 140

  • 1.0 ATTACHMENT 23 (Page 1 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis METEORLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the five (5) year average X/Q 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 X/Q 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, 1992 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 mixed mode (i.e., process vent). The portions of release characterized as ground level were based on AT1s8.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on AT1s8.9ft-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 line 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 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 calculations 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 126 OF 140 ATTACHMENT 23 (Page 2 of 8)

Surry 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 1 lA-8.

XIQ 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 is appropriate according to NUREG-0133.

1.3 Results The X/Q value that would result in the maximum total body, skin, and inhalation exposure for

.ventilation vent releases was 6.0E-05 sec/m3 at a site boundary location 532 meters NNE sector. For process vent releases, the site boundary XIQ value was 3.7E-07 sec/m3 at a 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/m3 at a

  • location 290 meters NW sector. The discharge canal bank X/Q value for process vent was 6.9E-07 sec/m3 at a location 290 meters NW sector.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 127 OF 140 ATTACHMENT 23 (Page 3 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis The grass-cow-milk pathway analysis, which is performed to derive the maximum exposure from I 131 , I 133 , 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 releases that would result in the maximum exposure for the grass-cow-milk pathway was 1.5E-06 sec/m3 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 X/Q 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 effluentrelease 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 128 OF 140 ATTACHMENT 23 (Page 4 of 8)

Surry 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 Virginia Power 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, aq.d the fish, invertebrate, and shoreline pathways were considered to exist.

Dose 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.

2.3 Results For the years 1976, 1977, 1979, 1980, and 1981, the invertebrate pathway resulted in the largest.

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 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.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 129 OF 140 ATTACHMENT 23 (Page 5 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis 3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose Gaseous effluent pathway analyses are performed to detennine the location that.would result

  • in the maximum doses due to noble gases, for use in demonstrating compliance with 6.3.1.a.

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! 131 , I 133 , tritium, 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 detennination of the critical organ, maximum age group, and sector location of an exposed individual through the inhalation pathway from I 131 , l 133 , tritium, and particulates to demonstrate compliance with 6.3.1.a.. , ..

3.2 Data, Parameters, and Methodology Five year average X/Q 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 the public inside site boundary. The largest XIQ value was determined to be 6.0E-05 sec/m3 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 WSW 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.

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 130 OF 140 ATTACHMENT 23 (Page 6 of 8)

Surry Meteorological, Liquid, and Gaseous Pathway Analysis The maximum exposed individual for 10CFR50 Appendix 1 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. 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 Pivv and Pipv are calculated using the following equation:

Pi = K' (BR) DFAi (mrem/yr per µCi/m 3) (28-1) where:

K' = a constant of unit conversion, IE+ 12 pCi/Ci BR =the breathing rate of the particular age group, m3/yr, from Table E-5, Regulatory Guide 1.109, Rev .1 DFAi =the critical organ inhalation dose factor for particular age group for the ith ' -

radionuclide, in mrem/pCi 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 X/Q at this location was determined to be 1.6E-04 sec/m3 at 290 meters NW direction.

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 131 OF 140

  • ATTACHMENT23 (Page 7 of 8)

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

(28-2) where:

K' = a constant of unit conversion, 1E+I2 pCi/Ci Qp = cow's consumption rate, 50, in Kg/day (wet weight)

Uap = infant milk consumption rate, 330, liters/yr YP = agricultural productivity by unfr area of pasture feed grass, 0. 7 Kgfm2 Ys = agricultural productivity by unit area of stored feed, 2.0, in Kgfm2 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 DFLj = critical organ ingestion dose factor for the ith radionuclide for the particular age group, in mrem/pCi Ai = decay constant for the ith radionuclide, in sec-1 Aw = decay constant for removal of activity of leaf and plant surfaces by weathering, s~73E-07 sec-I (corresponding to a 14 day half-life) tr = transport time from pasture to cow, to milk, to receptor, 1.73+o5, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+o6, 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 fromNUREG-0133 and Regulatory Guide 1.109, Rev.I, and LADTAP II, NUREG/CR-1276.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 132 OF 140 ATTACHMENT 23 (Page 8 of 8)

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

(28-3) where:

K"' = a constant of unit conversion 1E+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.

The inhalation p~thway dose factors Riivv and Rlipv were calculated using the following equation:

Rli = K' (BR) DFAi (mrem/yrpet µCi/m 3)

(28-4) where:

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

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 133 OF 140

  • 1.0 ATTACHMENT 24 (Page 1 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis METEOROLOGICAL ANALYSIS 1.1 Purpose The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the Station for ventilation vent (ground level) and process vent (mixed mode) releases. The annual average X/Q and D/Q values were used to perform a dose pathway analysis to determine both the maximum exposed individual at site boundary and member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Attachments 9 and 14.

1.2 Meteorological Data, Parameters, and Methodology Onsite meteorological data for the period January 1, 1981, through December 31~* 1981, were used in calculations. These data included wind speed, wind direction, and differential.

temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (e.g., ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions of release characterized as ground level were based on

.1Tts8.9ft-28.2ft and 28.2 foot wind data, and the portions characterized as mixed mode were based on .!\T1s8.9ft-28.2ft and 158.9 ft wind data.

X/Q's and D/Q's were calculated using the NRC computer code "XOQDOQ- Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,"

September, 1977. The code is based upon a straight line 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 by gently rolling terrain so open terrain correction factors were considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 134 OF 140 ATTACHMENT 24 (Page 2 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis The effective release height used in mixed mode release calculations was based on a process vent release height of 157 .5 ft, and plume rise due to momentum for a vent diameter of 3 in.

with plume exit velocity of 100 ft/sec. 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 North Anna Power Station Units 1 and 2, Virginia Electric and Power Company Final Safety Analysis Report Table 11 C.2-8.

XIQ and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent rel~ases at distances specified from North Anna Power Station Annual Environmental Survey Data for 1981. X/Q values were also calculated for the nearest lake shoreline by sector for the 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 is appropriate according to NUREG-0133.

The XIQ and D/Q values calculated from 1981 meteorological data are comparable to the values presented in the North Anna Power Station UFSAR.

1.3 Results The X/Q value that resulted in the maximum total body, skin and inhalation exposure for ventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 14l6 meters SE sector. For process vent releases, the site boundary X!Q value was 1.2E-06 sec/m3 at a location 1513 meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m3 at a location 274 meters NNE sector. The shoreline X/Q value for process vent was 2.7E-06 sec/m3 at a location 274 meters NNE sector.

J

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 135 OF 140

  • ATTACHMENT 24 (Page 3 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Pathway analysis indicated that the 111aximum exposure from 1-131, 1133 , and from all radionuclides in particulate form with half-lives greater than 8 days was through the grass-cow-milk pathway. The 0/Q value from ventilation vent releases resulting in the maximum exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For process vent releases, the D/Q value was l.lE-09 per m2 at a location 3250 meters N sector. For tritium, the X/Q value from ventilation vent releases resulting in the maximum exposure for the milk pathway was 7 .2E-07 sec/m3, and 3. 9E-07 sec/m3 for process vent releases at a location 3250 meters N sector.

2.0 LIQUID PATHWAY ANALYSIS 2.1 Purpose The purpose of the liquid pathway analysis was to determine the maximum expci~ed member of the public in unrestricted areas as a result of radioactive liquid effluent releases.* The analysis includes a determination of most restrictive liquid pathway, most restrictive age group, and critical organ. This analysis is required for Subsection 6.2.

2.2 Data, Parameters, and Methodology Initially, radioactive liquid effluent release data for the years 1979, 1980, and 1981 were compiled from the North Anna Power Station semi-annual 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.

Re-concentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for Reservoir and Waste Heat Treatment Facility from Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2, March 15, 1972. Dilution factors for aquatic foods, shoreline, and drinking water were set to one. Transit time calculations were based on average flow rates. All other parameters were defaults selected by the LADTAP computer code.

  • VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 136 OF 140 ATTACHMENT24 (Page 4 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Beginning in 1997, the activity by nuclide released in the previous year is entered into the North Anna Power Station liquid pathway critical organ calculations spreadsheet, which calculates the most limiting age group total body and critical organ. This Process is repeated annually.

2.3 Results Initially, the fish pathway resulted in the largest dose. The critical organ each year was the liver, and the adult and teenage age groups received the same organ dose. However, since the adult total body dose was greater than the teen total body dose for each year, the adult was selected as the most restrictive age group. Beginning in 1997, the most limiting age group for both total body and critical organ is calculated from the spreadsheet for North Anna Power Station liquid pathway critical organ calculations.

3.0 GASEOUS PATHWAY ANALYSIS 3.1 Purpose A gaseous effluent pathway analysis was 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.

and 6.3.3.a. The analysis also included a determination of the critical pathway, location of maximum exposed member of the public, and the critical organ for the maximum dose due to 1131 , 1133 , tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with requirements in 6.3.4.a.1. In addition, the

  • analysis includcro a determination of the critical pathway, maximum age group, and sector location of an exposed individual through the inhalation pathway from I 131 , I 133 , tritium, and particulates with half-lives greater than 8 days to demonstrate compliance with. 6.3.1.a..

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 137 OF 140 ATTACHMENT 24 (Page 5 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis 3.2 Data, Parameters, and Methodology Annual average X/Q 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 beyond the site boundary. The largest X/Q value was determined to be 9 .3E-06 sec/m3 at site boundary for ventilation vent releases at a location 1416 meters SE direction, and l.2E-06 sec/m3 at site boundary for process vent releases at a location 1513 meters S 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.

Step 6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q 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 gr~ater than 8 days for the inhalation pathway.

The NRC computer code GASPAR, "Evaluation of Atmospheric Releases," Revised 8/19n7, was run using 1979, 1980 and 1981 North Anna Power Station Gaseous Effluent Release Report data. Doses from 1131 , 1133 , tritium, and particulates for the inhalation pathway were calculated using the 9.3E-06 sec/m3 site boundary X/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway.

The gamma and beta dose factors Kivv, Livv, Mivv, and Nivv in Attachment 9 were obtained by performing a units conversion of the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev. 1. to mrem/yr per Ci/m3 or mrad/yr per Ci/m3, and multiplying by the ventilation vent site boundary XIQ value of 9.3E-06 sec/m3. The same approach was used in calculating the gamma and beta dose factors Kipv, Lipv, Mipv, and Nipv in Attachment 9 using the process vent site boundary XIQ value of 1.2E-06 sec/m3.

VIRGINIA VPAP-2103 POWER REVISION 10 PAGE 138 OF 140

'ATTACHMENT 24 (Page 6 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis The inhalation pathway dose factors Pivv and Pipv in Attachment 9 were calculated using the following equation:

P.1 = K'(BR) DFA.1 (x!Q) (mrem/yrper Curie/sec) (29-1) where:

K' = a constant of unit conversion, lE+ 12 pCi/Ci BR = the breathing rate of the child age group, 3700 m3/yr, from Table E-5, Regulatory Guide 1.109, Rev .1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem/pCi, from Table E-9, Regulatory Guide 1.109, Rev. 1 XIQ = the ventilation vent site boundary X/Q, 9.3E-06 sec/m3, or the process vent site boundary 'X/Q, 1.2E-06 sec/m3, as appropriate.

Step 6.3.4.a., requires that the dose to the maximum exposed member of the public from I 131 ,

1133 , tritium, and from all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, and to an exposed member of the public beyond site boundary at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981. .

It was determined that the member of the public within site boundary would be using Lake Anna for recreational purposes a maximum of 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> per year. It is assumed that this member of the public would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake shoreline with the largest annual 'X/Q of 1.0E-04 at a location 274 meters NNE sector. The NRC computer code GASPAR was run to calculate the inhalation dose to this individual. The GASPAR results were corrected for the fractional year the member of the public would be using the lake.

VIRGINIA VPAP-2103 POWER REVISION 10

. PAGE 139 OF 140 ATTACHMENT 24 (Page 7 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis Using the NRC computer code GASPAR and annual average 'X/Q and D/Q values obtained as described in Section 1 of this attachment, the member of the public receiving the largest dose beyond site boundary was determined to be located 3250 meters N sector. The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid. For each year 1979, 1980, and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary.

Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters N sector.

Pathway analysis results indicate that existing pathways, including ground and inhalation, within five miles of North Anna Power Station, yield Ri dose factors less than those determined for the cow-milk pathway. Although the cow-milk pathway does not exist within five miles of the Station, ~G-0133 requires the use of cow-milk Ri dose factors since these values result in the most limiting doses. There is no requirement to include the other pathways.

[Commitment 3.2.3]

The RMivv and RMipv dose factors, except for tritium, in Attachment 14 were calculated by multiplying the appropriate D/Q value with the following equation:

RM. = K' QF (U ap ) F (r) (DFL.) [fpfs + (1 - fpfs )e-Aitj e-\tf (29-2) 1 'A,.+')..,

1 W m 1 Yp y s

where:

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

Uap = infant milk consumption rate, 330 liters/yr Yp = agricultural productivity by unit area of pasture feed grass, 0. 7 Kg!m2 Ys = agricultural productivity by unit area of stored feed, 2.0, in Kg!m2 Fm = stable element transfer coefficients, from Table E-1, Regulatory Guide 1.109, Rev. 1

  • VIRGINIA VPAP-2103 POWER REVISION 10 ",

PAGE 140 OF 140 ATTACHMENT24 (Page 8 of 8)

North Anna Meteorological, Liquid, and Gaseous Pathway Analysis r = fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and 0.2 for particulates DF'Li= thyroid ingestion dose factor for the ith radionuclide for the infant, in mrem/pCi, from Table E-14, Regulatory Guide 1.109, Rev. 1 Ai = decay constant for the ith radionuclide, in sec-1, from Table of Isotopes, Lederer, Hollander, and Perlman, sixth Edition.

Aw = 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) tr = transport time from pasture to cow, to milk, to receptor, 1.73E+o5, in seconds th = transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+o6, in seconds fp -* fraction of year that cow is on pasture, 0.58 (dimensionless), 7 months per year from NUREG-0597 fs = fractioi:i of cow feed that is pasture grass while cow is on pasture, 1.0, dimensionless PGai:amdeter s usRed in the above equation were obtained from NUREG-0133 and Regulatory

  • m e 1. 10 9, ev.. 1 Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:

(29-3) where:

K"' = a constant of unit conversion IE+o3 gm/kg H = absolute humidity of the atmosphere,: 8.0, gmJm3 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 XIQ = the annual average concentration at a location 3250*meters N sector, 7.2E-07 sec/m3

  • for v~ntilation vent releases, and 3.9E-07 sec/m3 for the process vent releases

Attachment 4 Page I of6

  • MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS Changes were implemented to the liquid waste disposal system at Surry Power Station's Radwaste Facility (RF) in 1998. The changes were reviewed and approved by the Station Nuclear Safety and Operating Committee under Safety Evaluation 97-121. The changes were initiated to improve the economy and efficiency of the liquid waste disposal system. The RF can process liquid waste using an evaporator system, a reverse osmosis/demineralizer system (Thermex) or both. In 1998, Chem Nuclear Systems, Inc. and Surry Power Station made changes to the Thermex system at the RF.

In accordance with 10CFR50.59, the safety evaluation concluded that neither Technical Specifications nor unreviewed safety questions were involved with these changes. The changes to the RF Thermex system are bounded by the accident analyses in the Safety Analysis Report (SAR) as there is no increase in the probability of, consequences of, nor the possibility for an accident of a different type than previously evaluated in the SAR. No new radioactive source material is added and the system designs maintain the level of confinements equal to that of the original installation if a system leak would occur. Additionally, there is no safety related equipment associated with

  • this system or in the RF, and the margin of safety in any Technical Specification is not affected by these changes. The safety evaluation also conservatively concluded that there will be no change in the maximum exposure to an individual in the unrestricted area and no change in the predicted release of radioactive materials in liquid or gaseous effluents as previously identified in licensing documents.

Description of Changes The changes to the Thermex system were implemented in February, 1998. The changes were approved and documented by Engineering Transmittal #S-97-100, Revision 1 and Safety Evaluation 97-121. Thermex was modified because the system could not meet the contractual effluent specification of less than 0.1 Curie/year, to reduce solid radioactive waste disposal costs and to implement ALARA concepts. Low process flow rates and premature fouling of filters and reverse osmosis (RO) membranes were the primary contributors to the processing system inefficiency.

The Thermex process is a combination of demineralization and reverse osmosis which processes liquid waste as originally installed and outlined in the figure on page four of this attachment. The system as revised is outlined in the figure on page five of this attachment. Influent waste is received from the liquid waste collection tanks (L WCT), Liquid waste storage tanks (LWST) or from the

Attachment 4 Page 2 of6

  • liquid waste evaporator. The waste is first processed, at flow rates up to 25 gpm, through a 29 cubic foot demineralizer containing granular activated carbon which removes suspended solids by filtration. From the demineralizer the waste flows through an RO prefilter. The prefilter is a cartridge filter designed to remove particulates. Low process flow rate and premature fouling of this filter were experienced. An additional prefilter was installed in parallel to improve flow rate efficiency. A water softening demineralizer was also installed upstream of the prefilters to reduce filter and RO membrane fouling and to reduce filter change rates. The water softening demineralizer contains sodium based cation resin to remove calcium, iron and other metals.

The effluent flows from the RO prefilters to the Process Feed Tank (PFT) through~ level control valve. This level control valve is integrated into the level sensing and control circuitry of the PFT and will close when PFT level alarms are received, thus preventing overfill. The PFT is both a collection and feed tank. It feeds waste to the reverse osmosis unit and receives waste from the RO prefilters and concentrated waste from the RO unit. When processing is complete, the waste in the PFT may be transferred to a spent resin collection tank for waste disposal or remain in the PFT and processed with another batch of liquid waste.

Liquid waste is pumped from the PFT by the Thermex feed pump at a flow rate of up to 70 gpm at 80 psig. The waste is filtered through the RO filter. This cartridge filter is designed to remove *

  • smaller sized particulates than the RO prefilter. Removal of the smaller particulates helps to prevent fouling of the RO units. Waste exiting the RO filter may be treated for pH control using chemical injection. A centrifugal booster.pump, designed to provide a flow rate of 134 gpm at 190 psig, is used to pump the waste through the Reverse Osmosis units. The RO units consist of two fiberglass membrane vessels rated at 600 psig at 120 degrees F. Each vessel is loaded with three Reverse Osmosis Membranes rated to operate at 250 psig at 85 gpm feed flow and 95 degrees F maximum operating temperature. Waste water is pumped across and through the membranes which separate dissolved solids from the waste. Premature membrane fouling of the RO units has been experienced since original installation. The previously discussed changes (additional prefilter and water softener) and the addition of two RO units were designed and implemented to also reduce the fouling of the RO membranes. Increasing the number of RO units from two to four improved the flow characteristics of the filters and RO units by allowing for reduced individual equipment flow rates. Concentrated waste solids from the RO units are then returned to the PFT as previously described. The resultant permeate water flows through two liquid waste demineralizers at a flow rate of up to 25 gpm. Both demineralizers remove radionuclides by ion exchange. The first demineralizer is a cesium specific demineralizer, while the second is a mixed bed demineralizer. The effluent from the demineralizers is then transferred to the liquid waste monitoring tanks for sampling and discharge permitting.

Attachment 4 Page 3 of6

  • Another change implemented to the system in 1998 was made to the cesium specific zeolite demineralizer. It was moved in the process train to upstream of the water softener demineralizer.

In this location, the demineralizer acts as a filter for the carbon demineralizer effluent, removes cesiums early in the process and protects the water softener demineralizer. These changes implemented to the liquid radwaste treatment system at the Radwaste Facility reduced the processed liquid effluent activity from 3.91E-01 curies in 1997 to 8.61E-02 curies in 1998.

ALARA concepts incorporated into the system changes were the repositioning of the cesium demineralizer in the process train and the relocation of the RO units to minimize exposure to personnel at the system operating deck. Replacement of manually operated valves with remotely operated valves in higher dose rate areas around the Process Feed Tank and shielding of the new prefilter and RO units were also employed to reduce personnel exposure. Personnel exposure for routine operations and replacement ofThermex filters was reduced from 2.919 manRem in 1997 to 1.052 manRem in 1998.

1-------<==i From LWCT, LWST To Spent Resin or Evaporator Collection Tank Chemical Injection Reverse Osmosis Skid

[]

1~<:J---*

Feedpump RO Filter LW Demineralizer Booster Pump RO Prefilter Level Control Process Feed Tank Valve To Liquid Waste Monitor Tank L W Demineralizers Reverse Osmosis Units (2)

From LWCT, LWST To Spent Resin or Evaporator Collection Tank Chemical Injection Reverse Osmosis Skid Water Feedpump RO Filter Carbon Zeolite Level Control Booster Pump Softener Process Feed Tank Valve LW Demineralizers RO Prefilters To Liquid Waste Monitor Tank Mixed Bed LW Demineralizer Reverse Osmosis Units (4)

.* .J*

    • . Safety Evaluation
  • Page 1 of 1? . _.

Attachment 4 Page 6 of6

.GIN/A POWER *.

VPAP-3001 Rev. 3 GOV02

1. Saf_etY. Evaluat;on Nuiber 2. Appl;cable Stat;on* 3. Appl foable Un;t Y',,..,~ [ l North Annl!I Power Stat;on 97-0_ Rev Q

[Xl Surry Power Station [Xl Unit 1 . . [Xl Unit 2 rnitt\Ml]!l~ij~:9.(J@;fl~~tttMriit~ftil]l))IlitI]f))jJftlfIIffiti))]flI!]IH!]l]!:::rrtII]!::::1::=]::11r111r11ttltififftftftififififililifII

4. List _the governing documents for which this safety evaluation was performed.

ET 97-0100 UFSAR Change °I(\ -\.\. \

5. SlJllll8r;ze the change, test, or experiment-evaluated ...
  • The Chem-Nuclear supplied Thermex reverse osmosis system flow rate and output chemistry do not meet design process specification.
6. State the purpose for this change, test, or experiment.

Chem-Nuclear proposes adding equipment in order to iq,rove flow rate, filter life, and efficiency, and to reduce dose rates and iq,rove ease of operation. Addition of a parallel meni>rane prefilter and RO vessels should iq,rove flow characteristics and efficiency of the equipment. The purpose of placing an additional demineralizer in service is to remove metals suspected of forming silicates, oxides and sulfates in the system contributing to premature filter fouling.

7. List the limiting conditions and special requirements identified or assuned by this safety analysis. For each item, indicate the formal tracking mechanism that will be used to ensure that these conditions and/or requirements will be met.

No limiting conditions exist. Addition of equipment will be coq>leted within the SRF in accordance with the governing documents.

8. Will the proposed activity/condition result in or constitute an unreviewed safety question, an unreviewed environmental question, a change to the Fire Protection Program that affects the [ l Yes [X] No ability of the stat;on to achieve and maintain safe shutdown in the event of a fire, or require a license amenanent or Technical Specification change? *
9. Preparer Name (Print) 10. 11. Date T S~t--L cr-f'-97
12. Cognizant Supervisor Name (Print) 13. 14. Date

-~R..Yht<~ S~0

15. Disposition

[~roved [ l Disapproved [ ] Approved As Modified [ l Requires Further Evaluation

16. SHSOC Cha;""" s ; g ~ 17. Date Conments

- MS - anagement a ly e w e L

Attachment 5 Page 1 of 1

  • INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitors required by the ODCM Attachments 1 and 10, which were determined inoperable, were not returned to operable status within 30 days. None of the above referenced monitors were inoperable for 30 days during this reporting period .

Attachment 6 Page 1 of 1

  • UNPLANNED RELEASES There were no unplanned liquid or gaseous releases during this reporting period.

1*

l~ -

Attachment 7 Page I of I LOWER LEVEL OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS

  • GASEOUS: Isotope Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Reguired LLD 1.00E-04 l.OOE-04 l.OOE-04 1.00E-04 1.00E-04 Typical 2.38E 2.03E 1.0SE 4.37E 6.07E LLD 3.24E-06 3.47E-06 2.37E-06 9.14E-06 1.20E-06 Xe-135m 1.00E-04 2.75E 5.48E-06 Xe-138 1.00E-04 7.32E 9.06E-06 1-131 1.00E-12 5.72E 1.14E-13 1-133 1.00E-10 1.3 lE-12 2.0lE-12 Sr-89 1.00E-11 2.00E 9.00E-13 Sr-90 1.00E-11 2.00E 2.00E-13 Cs-134 1.00E-11 3.36E 7.80E-14 Cs-137 l.OOE-11 4.57E l.35E-13 Mn-54 1.00E-11 3.35E l.07E-13 Fe-59 l.OOE-11 8.72E 1.47E-13 Co-58 1.00E-11 3.64E l.17E-13 Co-60 1.00E-11 4.61E l.09E-13 Zn-65 l.OOE-11 1.18E 2.48E-13 Mo-99 l.OOE-11 3.41E 5.95E-13 Ce-141 l.OOE-11 4.47E 6.66E-14 Ce-144 l.OOE-11 2.00E 3.00E-13 Alpha 1.00E-11 l.OSE 2.48E-12 Tritium 1.00E-06 5.42E 7.06E-08 LIQUID Sr-89 5.00E-08 2.00E-08 - 5.00E-08 Sr-90 5.00E-08 6.00E-09 - 2.00E-08 Cs-134 5.00E-07 7.37E-09 - 2.03E-08 Cs-137 5.00E-07 8.56E-09 - 2.61E-08 I-131 l.OOE-06 7.91E-09 - 1.97E-08 Co-58 5.00E-07 7.l 7E 2.llE-08 Co-60 5.00E-07 7.96E-09 - 2.32E-08 Fe-59 5.00E-07 l.36E-08 - 4.08E-08 Zn-65 5.00E-07 1.85E-08 - 4.37E-08 Mn-54 5.00E-07 5.87E-09 - 2.29E-08 Mo-99 5.00E-07 4.98E-08 - 2.34E-07 Ce-141 5.00E-07 l.09E-08 - 1.79E-08 Ce-144 5.00E-07 4.52E-08 - 8.74E-08 Fe-55 1.00E-06 4.00E-07 - 7.00E-07 Alpha 1.00E-07 5.94E-09 - l.41E-08 Tritium 1.00E-05 1.49E-06 - 1.95E-06 Xe-133 1.00E-05 1.45E-08 - 3.78E-08
  • Xe-135 1.00E-05 7.64E-09 - 1.56E-08 Xe-133m 1.00E-05 5.34E-08 - 1.02E-07 Xe-135m l.OOE-05 6.76E-07 - 3.39E-08 Xe-138 l.OOE-05 1.70E-06 - 6.57E-08 Kr-87 1.00E-05 2.04E-08 - 3.85E-08 l

Kr-88 1.00E-05 2.82E-08 - 3.83E-08

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