Text

Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report
	ML11123A214
Person / Time
Site:	North Anna
Issue date:	04/26/2011
From:	Lane N; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	11-214
	Download: ML11123A214 (125)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 2011 United States Nuclear Regulatory Commission Serial No.11-214 Attention: Document Control Desk NAPS/JHL Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2010 Annual Radioactive Effluent Release Report.

This report is provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].

If you have any questions or require additional information, please contact Donald Taylor at (540) 894-2616.

Very truly yours, N. Larry Lane Site Vice President Enclosure Commitments made in this letter: None cc:

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector North Anna Power Station kSA kp

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2010 TO DECEMBER 31, 2010)

PREPARED BY:

62c Supervisor Radiological Analysis and Instrumentation REVIEWED BY: SQ/c -Z Supervisor Health Physics Technical Services APPROVED BY:/

Manager Radiological Protection and Chemistry

FORWARD This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c a

and 10CFR72.44(d)(3).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2010 TO DECEMBER 31, 2010 INDEX Section No.

1 2

3 4

Subject EXECUTIVE

SUMMARY

PURPOSE AND SCOPE...................................

D IS C U S S IO N..................................................

SUPPLEMENTAL INFORMATION.......................

Effluent Release Data.................................

Annual and Quarterly Doses........................

Revisions to Offsite Dose Calculation Manual (ODCM)........................................

Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment S yste m s..................................................

Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrum entation........................................

Unplanned Releases.................................

Lower Limits of Detection (LLD) for Effluent Sample Analysis...........................

Results of Ground Water Protection Initiative Sample Analysis Carbon-14 Calculations 1-2 2

3-4 4

5 6

7 8

9 10 11 -12 13-16 17

1.0 EXECUTIVE

SUMMARY

The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and Independent Spent Fuel Storage Installation (ISFSI) during the 2010 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with R.G.

1.21 during the period January 1 through December 31, 2010, and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.

There were no releases from the ISFSI during 2010.

There were no unplanned releases, meeting the reporting criteria of section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Neither were there any spills or leaks meeting the reporting criteria of the NEI Ground Water Protection Initiative. However, a voluntary communication was made under NEI-07-07 due to sample results from one ground water well, Piezometer Well #3.

Based on the 2010 effluent release data, 10 CFR 50, Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following:

a.

The total body dose due to liquid effluents was 4.51 E-1 mrem, which is 7.52% of the dose limit and the critical organ dose due to liquid effluents was 4.59E-1 mrem, which is 2.30% of the dose limit.

b.

The air dose due to noble gases was 5.12E-3 mrad gamma, which is 2.56E-2% of the annual gamma dose limit, and 1.52E-2 mrad beta, which is 3.80E-2% of the annual beta dose limit.

c.

The critical organ dose for 1-131, 1-133, H-3, and Particulates with half-lives greater than 8 days including C-14 was 1.16E+0 mrem, which is 3.87E+0% of the annual dose limit. The bases of these calculations are described in Attachment 9.

d.

The critical organ dose for 1-131,1-133, H-3, and Particulates with half-lives greater than 8 days not including C-14 was 2.19E-2 mrem, which is 7.30E-2% of the annual dose limit.

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

There was one revision to the Offsite Dose Calculation Manual during this reporting period.

1

1.0 EXECUTIVE

SUMMARY

(cont.)

Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas.

2.0 PURPOSE AND SCOPE The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly basis for Table 1 and 2 and on an annual basis on Table 3. The report submitted before May 1 st of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period, in.

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

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.7.2.a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of FSAR updates.

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

2

3.0 DISCUSSION The basis for the calculation of the percent of Technical Specification for the critical organ in Table 1A of is the ODCM, section 6.3.1, which requires that the dose rate for iodine-1 31 & iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's bone if C-1 4 is included and child's thyroid if C-14 is not included both via the inhalation pathway.

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

The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 gCi/ml.

Percent of Technical Specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases of airborne iodine-131 & iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-1 31 & iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days, excluding carbon-14, is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child, and also as a child for the calculation of critical organ dose, which was determined to be the liver. The age group is exposed via the drinking water and fish ingestion pathways.

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

3

3.0 DISCUSSION (cont.)

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

4.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is made to determine if new location(s) have been identified for the radiological environmental monitoring prograh pursuant to the ODCM.

No changes were made as a result of the land use census in 2009.

Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. Milk samples, ODCM, section 6.6.1, were collected from one station during the period from January to April of 2010. The dairy at Station 12 sold its cows and discontinued milking operations in April 2010. Sampling Station 12 was discontinued and samples were obtained from a dairy at new station designated Station 12A. Vegetation samples were not collected from stations 14a, 15, 16, 21 and 23 from January through March and during November and December due to seasonal unavailability. All other vegetation samples were obtained. contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site. contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14. Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values.

4

ATTACHMENT I

EFFLUENT RELEASE DATA (01/10 - 12/10)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, Appendix B, except that in accordance with Step 6.7.2.a.1 of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.

5

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

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

A. Fission and Activiation Gases:

1. Total Release Curies 5.23E+01 1.24E+01 1.80E+1

2. Average Release Rate For Period ipCi/sec 6.73E+00 1.58E+00 B.

lodines:

1. Total Iodine-131 Release Curies 1.19E-04 3.16E-04 2.80E+1

2. Average Release Rate For Period pCi/sec 1.53E-05 4.02E-05 C.

Particulate (Tl/2 > 8 days):

1. Total Particulate (T1/2 > 8 days) Release Curies 2.93E-05 8.37E-06 2.80E+1

2. Average Release Rate For Period ptCi/sec 3.77E-06 1.06E-06

3. Gross Alpha Radioactivity Release Curies 6.47E-08 1.82E-07 D. Tritium:

1. Total Release Curies 1.93E+00 1.17E+00 3.10E+1

2. Average Release Rate For Period pCi/sec 2.48E-01 1.48E-01 E. Carbon-14

1. Total Release Curies 1.OOE+01 2.39E+00

2. Average Release Rate For Period pCi/sec 1.29E+00 3.04E-01 F.

Percentage Of Technical Specification Limits

1. Total Body Dose Rate 2.86E-03 2.20E-04

2. Skin Dose Rate 1.13E-03 1.03E-04

3. Critical Organ Dose Rate (with C-14) 2.11E-02 1.83E-03 Critical Organ Dose Rate (without C-14) 2.12E-04 4.18E-04

TABLE JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

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

A.

Fission and Activiation Gases:

1. Total Release Curies 2.29E+01 8.47E-01 1.80E+1

2. Average Release Rate For Period laCi/sec 2.88E+00 1.07E-01 B.

Iodines:

1. Total Iodine-131 Release Curies 2.82E-04 9.67E-05 2.80E+1

2. Average Release Rate For Period pCi/sec 3.55E-05 1.22E-05 C.

Particulate (TM/2 > 8 days):

1. Total Particulate (T1/2 > 8 days) Release Curies 8.97E-06 9.88E-06 2.80E+1

2. Average Release Rate For Period pCi/sec 1.13E-06 1.24E-06

3. Gross Alpha Radioactivity Release Curies 4.59E-07 6.01 E-08 D. Tritium:

1. Total Release Curies 1.21E+00 4.74E-01 3.10E+1

2. Average Release Rate For Period pCi/sec 1.53E-01 5.97E-02 F. Carbon-14

1. Total Release Curies 4.39E+00 1.62E-01

2. Average Release Rate For Period pCi/sec 5.52E-01 2.04E-02 F.

Percentage Of Technical Specification Limits

1. Total Body Dose Rate 3.86E-04 7.16E-06

2. Skin Dose Rate 1.65E-04 3.84E-06

3. Critical Organ Dose Rate (with C-14) 3.09E-03 6.72E-05 Critical Organ Dose Rate (without C-14) 4.31 E-04 2.47E-05

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

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

Krypton - 85 Ci N/D N/D 1.44E+00 2.38E+00 Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon-131m Ci N/D N/D 4.73E-01 1.83E-01 Xenon - 133 Ci 7.58E+00 3.75E+00 6.37E+00 4.06E+00 Xenon - 133m Ci N/D N/D 5.71E-02 6.77E-03 Xenon - 135 Ci 2.11E-03 1.02E-02 1.25E-02 N/D Xenon - 135m Ci N/D 7.01E-03 N/D N/D Xenon-137 Ci N/D N/D N/D N/D Xenon-138 Ci N/D N/D N/D N/D Other (Specify)

N/D N/D N/D N/D Argon - 41 Ci 9.84E-03 2.54E-02 N/D N/D Total For Period Ci 7.59E+00 3.79E+00 8.35E+00 6.63E+00 lodines:

Iodine - 131 Ci 6.86E-07 7.67E-07 N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci 1.51E-07 N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci 8.37E-07 7.67E-07 N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D N/D N/D Cesium - 136 Ci N/D N/D N/D N/D Cesium - 137 Ci N/D N/D N/D N/D

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/10 - 12110)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates:

(cont.)

Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D NID N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Total for Period (Tl/2 > 8 days)

Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days)

Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D GROSS ALPHA:

Ci N/D N/D N/D N/D TRITIUM:

Ci 1.42E+00 1.16E+00 4.32E-02 5.72E-04 CARBON-14 Ci 1.46E+00 7.27E-01 1.60E+00 1.27E+00

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D 1.63E+00 1.03E-01 Krypton - 85m Ci N/D N/D N/D NID Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D 3.13E-01 2.44E-02 Xenon - 133 Ci 3.05E+00 1.93E-02 1.45E+01 6.82E-01 Xenon - 133m Ci N/D N/D 1.09E-01 N/D Xenon - 135 Ci 2.74E-03 N/D 6.69E-02 N/D Xenon-135m Ci N/D N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify)

N/D N/D N/D N/D Argon - 41 Ci 5.54E-03 N/D N/D N/D Total For Period Ci 3.06E+00 1.93E-02 1.66E+01 8.09E-01 lodines:

Iodine - 131 Ci 1.05E-05 7.05E-07 N/D N/D Iodine - 132 N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D N

Total For Period Ci 1.05E-05 7.05E-07 N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D N/D N/D Cesium - 136 Ci N/D N/D N/D N/D Cesium - 137 Ci N/D N/D N/D N/D

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates:

(cont.)

Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Total for Period (Tl/2 > 8 days)

Ci N/D N/D N/D N/D Total for Period (Tl/2 < 8 days)

Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D GROSS ALPHA:

Ci N/D N/D N/D N/D TRITIUM:

Ci 2.64E-01 1.66E-01 2.62E-02 1.47E-04 CARBON-14 Ci 5.87E-01 3.70E-03 3.18E+00 1.55E-01

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

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

Krypton - 85 Ci N/D N/D 1.05E-01 2.10E-02 Krypton - 85m Ci N/D N/D 1.63E-04 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D 2.95E-05 N/D Xenon - 131 m Ci N/D N/D 3.09E-02 4.08E-03 Xenon - 133 Ci N/D N/D 3.58E+01 2.02E+00 Xenon - 133m Ci N/D N/D 1.86E-02 N/D Xenon - 135 Ci N/D N/D 3.82E-01 N/D Xenon - 135m Ci N/D N/D 5.78E-02 N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify)

Argon - 41 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 3.64E+01 2.05E+00 Iodines:

Iodine - 131 Ci 1.15E-04 3.15E-04 3.01E-06 1.30E-08 Iodine - 132 Ci N/D N/D 7.64E-09 N/D Iodine - 133 Ci 7.40E-05 N/D 1.71 E-07 N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci 1.89E-04 3.15E-04 3.19E-06 1.30E-08 Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D 1.68E-06 N/D 3.27E-07 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci 1.16E-06 4.68E-06 2.72E-05 4.75E-07 Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D N/D N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates:

(cont.)

Cesium - 137 Ci 9.86E-07 1.21E-06 N/D N/D Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D NID NID Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Rubidium-88 (Tl/2 < 8 days)

Ci N/D N/D 3.85E-05 N/D Cerium-143 (Tl/2 < 8 days)

Ci N/D N/D N/D 1.05E-07 Total for Period (Tl/2 > 8 days)

Ci 2.15E-06 7.57E-06 2.72E-05 8.02E-07 Total for Period (Tl/2 < 8 days)

Ci N/D N/D 3.85E-05 1.05E-07 Total For Period Ci 2.15E-06 7.57E-06 6.57E-05 9.07E-07 GROSS ALPHA:

Ci 6.47E-08 1.82E-07 N/D N/D TRITIUM:

Ci N/D N/D 4.65E-01 6.43E-03 CARBON-14 Ci N/D N/D 6.98E+00 3.91 E-01

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D 1.64E-02 4.47E-03 Krypton - 85m Ci N/D N/D 3.96E-05 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D 1.11E-02 3.12E-03 Xenon - 133 Ci N/D N/D 3.18E+00 1.06E-02 Xenon - 133m Ci N/D N/D 7.24E-03 N/D Xenon - 135 Ci N/D N/D 7.97E-03 N/D Xenon - 135m Ci N/D N/D N/D N/D Xenon-137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify)

Ci Argon - 41 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 3.22E+00 1.82E-02 lodines:

Iodine - 131 Ci 2.69E-04 9.59E-05 2.31E-06 1.10E-07 Iodine-132 Ci N/D N/D 9.16E-08 N/D Iodine-133 Ci 1.28E-05 N/D 1.64E-08 N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci 2.82E-04 9.59E-05 2.42E-06 1.10E-07 Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D 2.47E-07 5.21E-07 Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci 4.06E-06 N/D 8.59E-07 7.15E-07 Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D N/D N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates:

(cont.)

Cesium - 137 Ci 2.45E-06 6.06E-06 N/D 1.08E-06 Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Other (Specify)

Chromium-51 (Tl/2 > 8 days)

Ci N/D N/D N/D 3.89E-07 Zirconium-95 (Tl/2 > 8days)

Ci N/D N/D 4.40E-07 3.64E-07 Niobium-95 (Tl/2 > 8days)

Ci N/D N/D 9.09E-07 7.55E-07 Silver-11Om (Tl/2 > 8 days)

Ci N/D N/D 2.OOE-10 N/D Total for Period (Tl/2 > 8 days)

Ci 6.51 E-06 6.06E-06 2.46E-06 3.82E-06 Total for Period (Tl/2 < 8 days)

Ci N/D N/D N/D N/D Total For Period Ci 6.51 E-06 6.06E-06 2.46E-06 3.82E-06 GROSS ALPHA:

Ci 4.59E-07 6.01E-08 N/D N/D TRITIUM:

Ci N/D N/D 9.23E-01 3.08E-01 CARBON-14 Ci N/D N/D 6.17E-01 3.49E-03

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/10 -

12/10)

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

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha).

Curies 1.38E-03 1.06E-03 2.OOE+01

2. Average diluted concentration during the period.

liCi/ml 4.53E-12 1.58E-12

3. Percent of applicable limit (T.S.)

1.43E-05 4.53E-06 B.

Tritium:

1. Total release activity.

Curies 8.70E+02 1.21 E+02 2.OOE+01

2. Average diluted concentration during the period.

ptCi/mI 2.85E-06 1.81 E-07

3. Percent of applicable limit (T.S.)

2.85E-02 1.81 E-03 C.

Dissolved and Entrained Gases:

1. Total release activity.

Curies 1.43E-02 6.27E-04 2.OOE+01

2. Average diluted concentration during the period.

ýiCi/ml 4.69E-11 9.36E-13

3. Percent of applicable limit (T.S.)

2.35E-05 4.68E-07 D. Gross Alpha Radioactivity:

1. Total release activity.

Curies O.OOE+00 O.OOE+00 2.OOE+01 E.

Volume of waste released: (prior to dilution).

Liters 1.43E+08 1.57E+08 3.OOE+00 F. Total volume of dilution water used during the period.

Liters 3.05E+11 6.70E+1 1 3.OOE+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/10 -

12/10)

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

A.

Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha).

Curies 2.52E-03 2.51 E-03 2.OOE+01

2. Average diluted concentration during the period.

p.Ci/ml 3.16E-12 4.39E-12

3. Percent of applicable limit (T.S.)

9.80E-06 4.81 E-06 B.

Tritium:

1. Total release activity.

Curies 2.74E+02 6.99E+00 2.OOE+01

2. Average diluted concentration during the period.

pCi/ml 3.45E-07 1.22E-08

3. Percent of applicable limit (T.S.)

3.45E-03 1.22E-04 C.

Dissolved and Entrained Gases:

1. Total release activity.

Curies 1.15E-02 O.OOE+00 2.OOE+01

2. Average diluted concentration during the period.

lpCi/ml 1.45E-1 1 O.OOE+00

3. Percent of applicable limit (T.S.)

7.23E-06 O.OOE+00 D. Gross Alpha Radioactivity:

1. Total release activity.

Curies O.OOE+00 O.OOE+00 2.OOE+01 E.

Volume of waste released: (prior to dilution).

Liters 1.52E+08 1.26E+08 3.OOE+00 F. Total volume of dilution water used during the period.

Liters 7.95E+11 5.72E+11 3.OOE+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/10 - 12/10)

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

Manganese - 54 Ci 2.43E-05 N/D N/A N/A Iron - 55 Ci N/D N/D N/A N/A Cobalt - 58 Ci 8.14E-05 3.33E-04 N/A N/A Cobalt - 60 Ci 1.23E-03 6.08E-04 N/A N/A Strontium - 89 Ci N/D N/D N/A N/A Strontium - 90 Ci N/D N/D N/A N/A Niobium - 95 Ci N/D N/D N/A N/A Ruthenium - 106 Ci N/D N/D N/A N/A Silver - 11Om Ci 3.19E-05 3.85E-05 N/A N/A Iodine-131 Ci N/D N/D N/A N/A Iodine-133 Ci N/D N/D N/A N/A Cesium - 134 Ci 7.14E-06 N/D N/A N/A Cesium - 137 Ci 5.93E-06 7.79E-05 N/A N/A Barium-Lathanum - 140 Ci N/D N/D N/A N/A Cerium - 141 Ci N/D N/D N/A N/A Other (Specify)

Ci Niickel - 63 (T1/2 > 8 days)

Ci N/D N/D N/A N/A Total for Period Ci 1.38E-03 1.06E-03 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Kenon - 133 Ci 1.43E-02 6.27E-04 N/A N/D Kenon - 133m Ci N/D N/D N/A N/D Kenon - 135 Ci N/D N/D N/A N/D Kenon - 135m Ci N/D N/D N/A N/D Other (Specify)

Ci N/D N/D N/A N/D Kr-88 ( T1/2 < 8 days)

Ci N/D N/D N/A N/D Kr-85 (Tl/2 > 8 days)

Ci N/D N/D N/A N/D Total for Period Ci 1.43E-02 6.27E-04 N/A N/D Tritium Ci 8.70E+02 1.21E+02 N/A N/D Gross Alpha Ci N/D N/D N/A N/D

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci 1.58E-05 N/D N/D N/D Iron - 55 Ci N/D N/D N/D N/D Cobalt - 58 Ci 1.23E-03 1.94E-03 N/D N/D Cobalt - 60 Ci 8.09E-04 5.31 E-04 N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Niobium - 95 Ci 2.54E-05 4.1OE-05 N/D N/D Ruthenium - 106 Ci N/D N/D N/D N/D Silver - 110m Ci N/D N/D N/D N/D Iodine - 131 Ci 9.32E-05 N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Cesium - 134 Ci 7.74E-05 N/D N/D N/D Cesium - 137 Ci 2.65E-04 N/D N/D N/D Barium-Lathanum - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Other (Specify)

Niickel - 63 (T1/2 > 8 days)

Ci N/D N/D N/D N/D Total for Period Ci 2.52E-03 2.51 E-03 0.OOE+00 0.00E+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/10 - 12/10)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon - 133 Ci 1.15E-02 N/D N/D N/D Xenon - 133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D N/D Xenon - 135m Ci N/D N/D N/D N/D Other (Specify)

Argon - 41 (Tl/2 < 8 days)

Ci N/D N/D N/D N/D Krypton - 85 (Tl/2 > 8 days)

Ci N/D N/D N/D N/D Total for Period Ci 1.15E-02 N/D N/D N/D Tritium Ci 2.74E+02 6.99E+00 N/D N/D Gross Alpha Ci N/D N/D N/D N/D

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-10 THROUGH 12-31-10 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total

1. Type of Waste Unit Period Percent Error (%)

a.

Spent resins, sludges, filters sludge, m3 3.36E+01 2.50E+01 evaporator bottoms, etc.,

Ci 2.88E+02 2.50E+01

b.

Dry compressible waste, contaminated m3 1.61 E+03 2.50E+01 equipment, etc.,

Ci 7.70E+00 2.50E+01

c.

Irradiated components, control rods, m3 0.OOE+00 2.50E+01 etc.,

Ci 0.OOE+00 2.50E+01

d. Other (describe)

Used oil/Blast media/Sewage/Gravel m3 2.12E+00 2.50E+01 Dessicant/Soil/Construction debris Ci 6.32E-04 2.50E+01 Animal Carcasses

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

(%)

(Ci)

Percent Error (%)

a.

Co-58 3.21E+01 9.24E+01 2.50E+01 Co-60 2.03E+01 5.85E+01 2.50E+01 Ni-63 1.91E+01 5.50E+01 2.50E+01 Cs-137 1.05E+01 3.02E+01 2.50E+01 Cs-134 7.14E+00 2.05E+01 2.50E+01 Fe-55 5.09E+00 1.46E+01 2.50E+01 Mn-54 2.54E+00 7.29E+00 2.50E+01 H-3 1.53E+00 4.39E+00 2.50E+01 Ni-59 3.41E-01 9.81E-01 2.50E+01 C-14 2.88E-01 8.29E-01 2.50E+01 Eu-152 2.64E-01 7.59E-01 2.50E+01

b.

Co-60 6.25E+01 4.82E+00 2.50E+01 Fe-55 1.86E+01 1.43E+00 2.50E+01 Cs-137 3.84E+00 2.96E-01 2.50E+01 Mn-54 3.34E+00 2.57E-01 2.50E+01 Co-58 3.24E+00 2.49E-01 2.50E+01 Cr-51 2.90E+00 2.23E-01 2.50E+01 Ni-63 1.54E+00 1.19E-01 2.50E+01 Zr-95 1.46E+00 1.13E-01 2.50E+01 Nb-95 1.24E+00 9.55E-02 2.50E+01 Zn-65 3.66E-01 2.81 E-02 2.50E+01

c.

none

d.

Co-60 6.10E+01 3.86E-04 2.50E+01 Fe-55 1.78E+01 1.12E-04 2.50E+01 Cs-137 1.04E+01 6.55E-05 2.50E+01 Ni-63 4.28E+00 2.70E-05 2.50E+01 Mn-54 2.55E+00 1.61E-05 2.50E+01 Sb-125 7.73E-01 4.89E-06 2.50E+01 Nb-95 5.86E-01 3.71 E-06 2.50E+01 Co-58 5.44E-01 3.44E-06 2.50E+01 Cs-134 4.23E-01 2.67E-06 2.50E+01 Zn-65 3.86E-01 2.44E-06 2.50E+01 Zr-95 3.42E-01 2.16E-06 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-10 THROUGH 12-31-10 Page 2 of 2 3.

Solid Waste Disposition Number of Shipments 2

5 12 Mode of Transportation Truck Truck Truck Destination Clive, UT Erwin, TN Oak Ridge, TN B.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0

N/A N/A (7) shipments containing resins were shipped to a licensed waste processor for processing.

(1) shipment of filters was shipped to licensed facility for disposal.

(shipment also contained de-watered powdered resin)

(1) shipment of filter waste was shipped to a licensed waste processor for processing.

(filters were transported with compactable wastes accounted for below)

(10) shipments containing contaminated equipment, dry compressible waste / incinerable waste were shipped to a licensed waste processor for processing.

(1 shipment also contained filter waste accounted for above)

(1 shipment included oil)

(1 shipment included animal carcasses)

(1) shipment of compactable waste was shipped to a licensed facility for disposal.

(shipment included de-watered powdered resin, charcoal, asbestos)

(1) shipment containing contaminated oil was shipped to a licensed waste processor for incineration.

(Shipment also contained dry compressible waste)

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/10 - 12/10)

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

1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Annual Total Total Body Dose (mrem) 3.07E-1 4.31 E-2 9.79E-2 2.50E-3 4.51 E-1 Critical Organ Dose (mrem) 3.07E-1 4.46E-2 1.04E-1 2.48E-3 4.59E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 4.20E-3 3.28E-4 5.83E-4 1.09E-5 5.12E-3 Noble Gas Beta Dose (mrad) 1.22E-2 1.14E-3 1.86E-3 4.35E-5 1.52E-2 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with TI/ > 8 days (including C-14) (mrem) 8.64E-1 1.06E-1 1.88E-1 5.81 E-3 1.16E+0 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with TA > 8 days excluding C-14 (mrem) 3.46E-3 8.24E-3 7.56E-3 2.62E-3 2.19E-2 6

ATTACHMENT 3

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/10 - 12/10)

As required by Technical Specification 5.5.1, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.

There was one revision made to the ODCM in 2010.

Revision 16, which was effective 05/12/10, replaced station 12 with 12A and changed the calibration frequency of HP sampler flow meter from SA, semiannual, to R, 18 months. Certain Tank Level indicating devices were removed from Attachments 1 and 2 since they are not effluent instrumentation.

See Revision Summary of affected procedure for more details.

7

I MINnion.

Station Administrative Procedure

Title:

Offsite Dose Calculation Manual (North Anna)

Process / Program Owner: Manager Radiological Protection and Chemistry (North Anna)

Procedure Number Revision Numb-A, E

ctive Date VPAP-2103N 16 On File Revision Summary Revised to incorporate SAA005787 Details:

Attachment 6: Rewrote ACTION 3 to provid iti ty to grab sampling expectations (SAA005787)

Other revisions requested by Staff He P

ased on feedback from HP Ops and other departments Details:

Step 7.1: Updated pr VPAP-1701 to RM-AA-101 Moved Commitments

. I ugh.2.6 to References 3.1.31 through 3.1.36. These items are not commitments in ce with fleet procedure LI-AA-1 10, Commitment Management.

" Attachment 1: Delete 2 (Tank Level Indicating Devices). Not liquid effluent monitoring instrumentatio t requi d y NRC. These devices are covered by another process.

" Attachmen

.le d S ion 2 (Tank Level Indicating Device). Not liquid effluent monitoring instrume ifio red by NRC. These devices are covered by another process.

Attachme e

ged the HP Sampler Rotameter channel Calibration Frequency from Semi-Annual (SA) ueling (R) - Consistent with the MGPI monitors

" Attachment IT0-R eplaced Terrell' s Dairy and Holladay Dairy (both dairies closed) with Lakeside Dairy, changed Station number from 12 to 12A, and changed the distance (miles) from Unit 1.

Approvals on File

DOMINION VPAP-2103N REVISION 16 PAGE 2 OF 86 TABLE OF CONTENTS Section Page 1.0 PURPOSE 5

2.0 SCOPE 5

3.0 REFERENCES

/COMMITMENT DOCUMENTS.

6 4.0 DEFINITIONS 8

5.0 RESPONSIBILITIES 11 6.0 INSTRUCTIONS 12 6.1 Sampling and Monitoring Criteria 12 6.2 Liquid Radioactive Waste Effluents 12 6.2.1 Liquid Effluent Concentra

,ml 12 6.2.2 Liquid Monitoring Ins io 13 6.2.3 Liquid Effluent D i

t 16 6.2.4 Liquid Radw Tr ent 18 6.2.5 Liquid Sa N>

19 6.3 Gaseous R 19ie e Effluents 6.3.1 G o"

uent Dose Rate Limitation 19 6.3 *Gase

nitoring Instrumentation 22 as Effluent Air Dose Limit 25 31, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 27 6.-aseous Radwaste Treatment 29 6.4 Radioactive Liquid and Gaseous Release Permits 31 6.4.1 Liquid Waste Batch Release Permits 31 6.4.2 Continuous Release Permit 31 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit 32 6.4.4 Reactor Containment Release Permits 32 6.4.5 Miscellaneous Gaseous Release Permit 32

DOMINION VPAP-2103N REVISION 16 PAGE 3 OF 86 TABLE OF CONTENTS (continued)

Section Page 6.4.6 Radioactive Liquid and Gaseous Release Controls 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 6.6 Radiological Environmental Monitoring 6.6.1 Monitoring Program 6.6.2 Land Use Census 6.6.3 Interlaboratory Comparison Program 6.7 Reporting Requirements 6.7.1 Annual Radiological Environmental Operatin 6.7.2 Annual Radioactive Effluent Release R 6.7.3 Annual Meteorological Data 6.7.4 Changes to the ODCM 6.7.5 Groundwater Protection In' e

e 3.1.35]

7.0 RECORDS C7 32 34 34 34 36 37 38 38 39 42 42 43 44

DOMINION VPAP-2103N REVISION 16 PAGE 4 OF 86 TABLE OF CONTENTS (continued)

Section Page ATTACHMENTS 1

Radioactive Liquid Effluent Monitoring Instrumentation 45 2

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 47 3

Radioactive Liquid Waste Sampling and Analysis Program 49 4

Radioactive Gaseous Waste Sampling and Analysis Program 52 5

Gaseous Effluent Dose Factors 56 6

Radioactive Gaseous Effluent Monitoring Instrumenta 59 7

Radioactive Gaseous Effluent Monitoring Instrume Surveillance Requirements 62 8

Critical Organ Dose Factors 65 9

Radiological Environmental Monitoring r67 10 Environmental Sampling Locations 72 11 Detection Capabilities for Enviro a ple Analysis 76 12 Reporting Levels for Radioa it on rations in Environmental Samples 78 13 Meteorological, Liqui d

se, Pathway Analysis 79

DOMINION VPAP-2103N REVISION 16 PAGE 5 OF 86 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 o oses due to radioactive liquid and gaseous effluents are performed to assure th.

" Concentration of radioactive liquid effluents to the unrestr 4'

W limited to ten times the effluent concentration values of 10 CFR 20, 13B, le 2, Column 2, for radionuclides other than dissolved or entrained nob ases a 2

Ci/ml for dissolved or entrained noble gases.

" Exposure to the maximum exposed member ub"i**

the unrestricted area from radioactive liquid effluents will not res, osN er than the liquid dose limits of 10 CFR 50, Appendix I

" Dose rate at and beyond the site urradioactive gaseous effluents will be limited Noble gases - less th or al t dose rate of 500 mrem/yr to the total body and less than or equal to af 0 mrem/yr to the skin 1131, 1133, and ad1l ra onuclides in particulate form with half-lives greater than 8 days - less th al to a dose rate of 1500 mrem/yr to any organ

" Exposure ^

radl ctive gaseous effluents to the maximum exposed member of the public in th "*

stri ea will not result in doses greater than the gaseous dose limits of 10 pendix I, and

" Exposu 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 North Anna Power Station.

DOMINION VPAP-2103N REVISION 16 PAGE 6 OF 86

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 Reporti activity in Solid Wastes and Releases of Radioactive Materials in Liquid ar aseou ffluents from Light-Water-Cooled Nuclear Power Plants, Rev. 1, U..

RO,n 74 3.1.6 Regulatory Guide 1.109, Calculation of Annual Dos n F Routine Releases of Reactor Effluents for the Purpose of Evaluaf With 10 CFR 50, Appendix I, Rev. 1, U.S. NRC, October 197 3.1.7 Regulatory Guide 1.111, Methods for E atm t

pheric Transport and Dispersion of Gaseous Effluents in R ne

.eas from Light-Water-Cooled Reactors, Rev. 1, U.S. NRC, July, 3.1.8 North Anna Technical Specifica i 3.1.9 North Anna Technical Re ual (TRM) 3.1.10 NUREG-0324, XOQ or the Meteorological Evaluation of Routine Effluent Releases uc a wer Stations, U.S. NRC, September 1977 3.1.11 NUREG/CR-1 s

ual for the LADTAP II Program, U.S. NRC, May, 1980 3.1.12 TID-45Q*

! -50564, Rev. 1, Concentration Factors of Chemical Elements in Edible Aq c

anisms, October, 1972 3.1.13

'258) 'ol.

2, July 1973, Numerical Guides for Design Objectives and Limiting Operation to Meet the Criterion "As Low As Practicable" For ive Material in Light Water-Cooled Nuclear Power Reactor Effluents 3.1.14

-0597, User's Guide to GASPAR Code, U.S. NRC, June, 1980 3.1.15 Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Rev. 1 3.1.16 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations, October, 1978 3.1.17 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.18 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, Proposed Rev. 3, March 1982

DOMINION 3.1.19 3.1.20 3.1.21 3.1.22 VPAP-2103N REVISION 16 PAGE 7 OF 86 Environmental Measurements Laboratory, DOE HASL 300 Manual NRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program North Anna UFSAR Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361 3.1.23 North Anna Circulating Water System Modifications

a. DC-85-37-1 Unit 1

b. DC-85-38-2 Unit 2 3.1.24 Plant Issue (Deviation) N-1994-1137, Improp e

mergen TLDs 3.1.25 ET N-05-0025, Justification for removin S

M-8 from service when not in

use, 3.1.26 VPAP-2802, Notifications and Re 3.1.27 0-PT-75.21, 1-SW-RM-108 Flo 3.1.28 SAA001092, Non-SA SO ect*

s Review 93-1, Recommendation 3 3.1.29 NEI 07-07, Industry 0ootection Initiative - Final Guidance Document 3.1.30 CA086406, Land.C su sults 3.1.31 Quality Assu t

rt Number 91-03, Observation 08N 3.1.32 Quality Asan u

eport Number 92-03, Observation 02N 3.1.33 Quality r

Audit Report Number 92-03, Observation 04NS (Item 2) 3.1.34 Plan ue(

viation) N-1997-0926, Annual Radiological Effluent Release Report 3.1.3 la s

icensing Commitment) N-2006-4026-R15, Groundwater Monitoring io lan 3.1.36 S

-R93-1, Diagnosis and Mitigation of RCS Leakage including SGTR 3.2 Commitment Documents None

DOMINION VPAP-2103N REVISION 16 PAGE 8 OF 86 4.0 DEFINITIONS 4.1 Channel Calibration A channel calibration shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The channel calibration shall encompass all devices in the channel required for channel operability. The channel calibration may be performed by means of any series of sequential, overlapping, or total channel steps.

4.2 Channel Check A qualitative assessment, by observation, of channel behavior assessment includes, where possible, comparison of the chai<

other indications or status derived from independent inJset same parameter.

hi. This I status with measuring the 4.3 Channel Operational Test A Channel Operational Test the channel as close to the se channel required for channel necessary, of the required al OPERABILITY such that s, be performed by means oa (COT) shall J i

t.

f a simulated or actual signal into pnsor as pe, fy OPERABILITY of all devices in the OPE/

IT*:

COT shall include adjustments, as a

rm, e trip setpoints required for channel a

nj

,ithin the necessary range and accuracy. The COT may rie,"?sequential, overlapping, or total channel steps.

4.4 Critical Organ

/( /

V That organ, which determined to be the maximum exposed organ based on an effluent pathway ana

.s, the y ensuring the dose and dose rate limitations to any organ will not be exceeo*

& 'ations to the critical organ will be evaluated in accordance with Techn pe ications 5.5.4 dose rate limits specified for any organ to verify these limits have not exceeded.

4.5 Dose Equivalent 1-131 That concentration of 1131 (gCi/cc) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 131, V132, 1133, 1134, and 1135 actually present. Thyroid dose conversion factors for this calculation are listed in Table III of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used.

DOMINION VPAP-2103N REVISION 16 PAGE 9 OF 86 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W - Weekly At least once per 7 days M - Monthly At least once per 31 day Q - Quarterly At least once per 92 d

)>

SA - Semi-annually At least once pe 4

R - Refueling At least onc r

0 S/U - Start-up Prior to h h rea r

t-up P -' Prior to release Co) iete o

each release N.A. - Not applicable ic DR - During the release a

e during each release 4.7 Gaseous Radwaste Treatment Sy A system that reduces radioact v

/

luents by collecting primary coolant system offgases from the primary e

a roviding delay or holdup to reduce total radioactivity prior to release to the envi

t.

e system comprises the waste gas decay tanks, regenerative heat e ng as charcoal filters, process vent blowers, waste gas surge tanks, and wast e agm compressor.

4.8 General N n

X = 9:ýn n at a point at a given instant (curies per cubic meter)

D = 1 i)*: quantity of deposited radioactive material per unit area (curies per square meter)

O 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.

DOMINION VPAP-2103N REVISION 16 PAGE 10 OF 86 4.10 Members of the Public Individuals who, by virtue of their occupational status, have no formal association with the Station. This category includes non-employees of Dominion who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station functions. This category does not include non-employees such as vending machine servicemen or postal workers who, as part of their formal job function, occasionally enter an area that is controlled by Dominion to protect individuals from exposure to radiation and radioactive materials.

4.11 Operable - Operability A system, subsystem, train, component, or device is operabl h

pe ity when it is capable of performing its specified functions and all nec en instrumentation, controls, normal and emergency electrical power sou cs c

eal water, lubrication or other auxiliary equipment that are required for th ste, u stem, train, component, or device to perform its functions are also capabl or their related support functions.

4.12 Purge - Purging Controlled discharge of air or gas in ent to maintain temperature, pressure, humidity, concentration, or otheition, so that replacement air or gas is required to purify the confinement.

4.13 Rated Thermal Total reactor core Ktr tfer te to reactor coolant (i.e., North Anna - 2893 MWt).

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

A qualita sessment of channel response when a channel sensor is exposed to radiation.

This applies to installed radiation monitoring systems. For MGPI monitors, a source check is the verification of proper computer response to continuous operational checks on the detector and the electronics.

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.

DOMINION VPAP-2103N REVISION 16 PAGE 11 OF 86 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 Dominion for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional and/or recreational purposes.

4.19 Ventilation Exhaust Treatment System A system that reduces gaseous radioiodine or radioactive mat i

e form in effluents by passing ventilation or vent exhaust gases throug

,a sorbers and High Efficiency Particulate Air (HEPA) filters to remove io e

ulates from a gaseous exhaust stream prior to release to the environment c

yste is not considered to have any effect on noble gas effluents). Engineered Saf e

e

) atmospheric cleanup systems are not Ventilation Exhaust Treatment Sys/

c c n

5.0 RESPONSIBILITIES 5.1 Manager Radiological Protect*

a e

tstry The Manager Radiological ecti nd Chemistry is responsible for:

5.1.1 Establishing mi rocedures for surveying, sampling, and monitoring radioactive ue s a e environment.

5.1.2 Surveyin i g, and analyzing plant effluents and environmental monitoring, and doc nting es activities.

5.1.

g plant effluent trends and recommending actions to correct adverse trends.

5.1.

g Effluent and Environmental Monitoring Program records.

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

DOMINION VPAP-2103N REVISION 16 PAGE 12 OF 86 6.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented in Meteorological, Liquid, and Gaseous Pathway Analysis (Attachment 13).

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 typ n

ran of radiation or parameter monitored.

7 6.1.3 A sufficient number of survey points shall be use en to adequately assess the status of the discharge monitored.

6.1.4 Samples shall be representative of the mf discharge monitored.

6.1.5 Surveys, sampling, analyses, and to r

rds shall be accurately and legibly documented, and sufficiently de t

meaning and intent of the records are clear.

7) 6.1.6 Surveys, analyses, a 0Ying records shall be reviewed for trends, completeness, and accuracy.

iquid Radioactiv as EN ai*E a.'

ui d e centrations discharged from the Station shall not exceed the n i ts:

rradionuclides (other than dissolved or entrained noble gases), liquid effluent

~oncentrations 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 gCi/ml.

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

6.2 1

DOMINION VPAP-2103N REVISION 16 PAGE 13 OF 86

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 iC i/mi.

Volume of Waste Discharged X

2 ACW i1 where:

Ce gtCi/mli = the concentration of nuclide i in the li e

e arge ACWi

= ten times the effluent concentratio u

tricted areas of nuclide i, expressed as tCi/ml 1

, Appendix B, Table 2, Column 2 for radionuclides *aJ,"an n e gases, and 2E-4 gCi/ml for dissolved or entrained no ga es 6.2.2 Liquid Monitoring Instrumenta t i

a. Radioactive Liquid Effluen(

o strumentation Radioactive liquid efflufn o rmn nstrumentation channels shown on Radioactive Liquid E*A itooring Instrumentation (Attachment 1) shall be operable with the arn

'tpsetpoints set to ensure that Step 6.2.1.a. limits are not exceeded.

1. Alatr'itp of these channels shall be determined and adjusted in a

with Step 6.2.2.d., Setpoint Calculation.

,ara i active liquid effluent monitoring instrumentation channel alarm/trip is less conservative than required by Step 6.2.2.a., perform one of the llowing:

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

Declare the channel inoperable

Change the setpoint to an acceptable, conservative value

DOMINION VPAP-2103N REVISION 16 PAGE 14 OF 86

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

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

on (Attachment

1) perform the action shown in those tables.

2. Attempt to return the instruments to operable u

thi days. If unsuccessful and the channel is required t en explain in the next Annual Radioactive Effluent Release ort w t

inoperability was not corrected in a timely manner.

c. Applicable Monitors tp..,,s Liquid effluent monitors for ic setpoints shall be determined are:

Release Point Instrument Number Liquid R d t

t Line 1-LW-RM-111 Servic at r em Effluent Line 1-SW-RM-108 Con ir ating Water Line 1-SW-RM-130 2-SW-RM-230 GeneratorHigh Capacity Blow-1-SS-RM-125 Line 2-SS-RM-225

DOMINION VPAP-2103N REVISION 16 PAGE 15 OF 86

d. Setpoint Calculation NOTE: This methodology does not preclude use of more conservative setpoints.

1. Maximum setpoint values shall be calculated by:

CFD S =-

(2)

FE where:

S

=

the setpoint, in gCi/ml, of the radioactf y,

a, the radioactivity concentration in the efflu e pr to dilution C =

the effluent concentration limit sed to implement 10 CFR 20 for the Station, in FE =

maximum design pathwa fl u ate FD =

dilution water flow rate (ed D = FE + (218,00/

f circ. pumps in service)

2. Each of the condense ng ter channels (e.g., SW-130, SW-230) monitors the effL (s

ice er, including component cooling service water, circulai

, an quid radwaste) in the circulating water discharge tunnel bey t

st

nt of possible radioactive material addition. No dilutio e

this pathway. Therefore, Equation (2) becomes:

S = C (3)

\\

qfor Station monitors used to implement 10 CFR 20 for the site the effluent concentration limit.

addition, for added conservatism, setpoints shall be calculated for the liquid radwaste effluent line LW-111 and the Service Water System effluent line SW-108.

DOMINION VPAP-2103N REVISION 16 PAGE 16 OF 86

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

S

=CFDKLWFE (4) where:

KLW

= The fraction of the effluent concentration 10 CFR 20 for the site, attributable to the line pathway

5. For the Service Water System effluent line, E 0

CF w

where:

Ksw

=

The fraction o' f

nt concentration 10 CFR thetf*

, attributable to to implement taste effluent es:

(5) limit, used to implement the service water effluent

6. The sum 6.2.3 Liquid

a. Reqi ine p *wy)

K 11 not be greater than 1.0.

r 31 days, perform the dose calculations in Step 6.2.3.c. to ensure commitment to the maximum exposed member of the public from

ýrials in liquid releases (from each reactor unit) to unrestricted areas 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

DOMINION VPAP-2103N REVISION 16 PAGE 17 OF 86

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.

c. Dose Contribution Calculations Dose contribution shall be calculated for all radionucj4l "entif in liquid effluents released to unrestricted areas based on:

Where:

Subscripts

= i, refers to i

viucli, D = the cumulative se nt to the to liquid efflu, t

d t, in mrem Bi = Dose n

ctors (mrem/Ci) for Val tar9..ovided in code file foi 1"

h itical organ calculations Qi =Q 0 leased activity for the considered (6) tal body or critical organ from the

each age group of interest.

r North Anna Power Station period and the ith nuclide Qi = t x Ci x Waste Flow (7) the period for which Ci 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 gCi/ml

DOMINION VPAP-2103N REVISION 16 PAGE 18 OF 86

d. Quarterly Composite Analyses For radionuclides not determined in each batch or weekly composite, dose contribution to current monthly or calendar quarter cumulative summation may be 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 o fluents released in connection with specific station functions, such as ma t"ce o) efueling outages, sh)all be used in projections as appropriate.

a. Requirement

1. The Liquid Radwaste Treatment Sy all b sed to reduce the radioactive materials in liquid waste prior t f*sc ge n projected dose due to liquid effluent, from each reactor t

res ed areas would exceed 0.06 mrem to total body or 0.2 mrem(

t t/organ in a 31-day period.

2. Doses due to liqui e

s s e projected at least once per 31 days.

b. Action If radioactive i

discharged without treatment and in excess of the above li ubmit to the NRC, within 30 days, a special report in accor la P-2802, Notifications and Reports, that includes the follow e

nation of why liquid radwaste was being discharged without treatment, entification of any inoperable equipment or sub-system, and the reason for the 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. Determine DTB, the total body dose from liquid effluents in the previous 31-day period, per Equation (6).

L

DOMINION VPAP-2103N REVISION 16 PAGE 19 OF 86

2. Estimate R1, 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 F1, 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 (gCi/ml).

4. Determine PDTB, the projected total body dose in a 31-day period.

PDTB = DTB(R1F1)

(8)

d. Projected Critical Organ Dose Calculation 7

1. Determine DO, the critical organ dose from liq ue in the previous 31-day period, per Equation (

2. Estimate RF as in Step 6.2.4.c.2.

3. Estimate F1 as in Step 6.2.4.c.3.

4. Determine PDo = projec t

c dose in a 31-day period.

DO(R 1 F1 )

(9) 6.2.5 Liquid Sam Radioacti wast shall be sampled and analyzed according to the sampling and anal r

ements in Radioactive Liquid Waste Sampling and Analysis 6.3 Gase s

c-ie Waste Effluents 6.3.1 sG 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 < 500 mrem/year to the total body and < 3000 mrem/year to the skin.

a DOMINION VPAP-2103N REVISION 16 PAGE 20 OF 86

2. The dose rate limit for 11", 1133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days shall be < 1500 mrem/year to the critical organ.

b. Action

1. If dose rates exceed Step 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 continuously, to be within Step 6.3.1.a. limits.

3. Dose rates due to 1131, 1133, tritium, and all rad" cli with half-lives greater than 8 days, in gaseous fts be within the above limits by obtaining analyses in accordance with the sa I

a lysis Radioactive Gaseous Waste Sa ing,4p *psis Pro

>nficulate form Il be determined to imples and performing program specified on igram (Attachment 4).

DOMINION VPAP-2103N REVISION 16 PAGE 21 OF 86

c. Calculations of Gaseous Effluent Dose Rates

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:

JKivv ivv + KipvOipv] !00mrem/yr to the total body (10)

OR ELivv +1.Mivv)Qivv + (Lipv + 1.1Mipv)Qjpv] :3000mrem/yrto the i

(11) where:

Subscripts

=

vv, refers to vent rel ing ventilation vent pv, refers to the m the process vent; i, refers to indi u

di lide Kivv, Kipv

= The total ac or ventilation vents or process vent release It mssions for each identified noble gas radi in em/yr per Curie/sec. Factors are listed in ou cose Factors (Attachment 5)

Livv Lipv factor for ventilation vents or process vent due to beta emissions for each identified noble gas io ide i, in mrem/yr per Curie/sec. Factors are listed in us Effluent Dose Factors (Attachment 5)

Miv Ie 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 Gaseous Effluent Dose Factors (Attachment 5)

= The release rate for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents in Curie/sec (per site)

I=

The unit conversion factor that converts air dose to skin dose, in mrem/mrad

DOMINION VPAP-2103N REVISION 16 PAGE 22 OF 86

2. The dose rate limit for 131, 1133, 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:

1PivvQivv + PipvQipv] *1500mrem/yr to the critical organ (12) where:

Pivv, Pipv

=

The critical organ dose factor for ven vents or process vent for 13, I"', H3, and all radio ides i articulate form with half-lives greater than 8 dan, fo in ation pathway, in mrem/yr per Curie/sec. F rs lis n Gaseous Effluent Dose Factors (Attac 5) 2ivviov

=

The release rate for vye r process ventof131, 1133, H3, and all ra ' o ides o,

in particulate form with half-lives greate an gaseous effluents in Curie/sec (per site)

3. All gaseous releases, not t ts vent, are considered ground level and shall be included i* lt ation of !ivv.

6.3.2 Gaseous Monitoring I un

a. Requirement/

A

1. The radioa '*e eosfuent monitoring instrumentation channels shown in Radio o

ffluent Monitoring Instrumentation (Attachment 6) shall be o with arm/trip setpoints set to ensure that Step 6.3.1.a. noble gas lin*

t exceeded. Alarm/trip setpoints of these channels shall be etern*ied and adjusted in accordance with Step 6.3.2.d.

a a radioactive gaseous effluent monitoring instrumentation channel all be demonstrated operable by Channel Checks, Source Checks, Channel Calibrations, and Channel Operational Tests at the frequencies shown in Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 7).

DOMINION VPAP-2103N REVISION 16 PAGE 23 OF 86

b. Action

1. If a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required by Step 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 m uN uired by tables in Radioactive Gaseous Effluent Monitoring Ins [*m ton) ttachment 6) take the action shown in those tables.

~successful,

3. Return instruments to operable stuw explain in the next Annual Radioactive Efflu e R ort why the inoperability was not corrected in a timely manner

c. Applicable Monitors hic Radioactive gaseous effluent o

o h alarm/trip setpoints shall be determined are:

41 Release Instrument Number ro, VWt 1-GW-RM-178-1

Dpv + Dcae + Dvv (13) 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 fr roce ent gaseous effluent releases, mrem/yr Dcae

=

The noble gas site boundary dose e f c

nser air ejector gaseous effluent releases, mre Dvv

=

The noble gas site bounda os summation of Ventilation Vent A plusý g ous e luent releases, mrem/yr

2. Setpoint values shall be deter 0 42E-03 (14) where:
wr
'he ease pathway, process vent (pv), ventilation vent (vv)
C /,
\\~
enser air ejector (cae)
C
,e effluent concentration limit implementing Step 6.3.1.a.
for the Station, ýtCi/ml
\\=
The release rate limit for pathway m determined from methodology in Step 6.3.1.c., using Xe133 as nuclide to be released,.tCi/sec 12E-03
=
CFM per ml/sec M
= The maximum flow rate for pathway m, CFM
DOMINION VPAP-2103N REVISION 16 PAGE 25 OF 86 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 particiulate form, and radionuclides other than noble gases.
6.3.3 Noble Gas Effluent Air Dose Limit
a. Requirement
1. The air dose in unrestricted areas due to noble gases rele*, in gaseous effluents from each unit at or beyond the site bound shall limited to:
" During any calendar quarter: !5 mrads for ga ra nd
10 mrads for beta radiation
" During any calendar year: *<10 mrads ion and <120 mrads for beta radiation frt
2. Cumulative dose contributions no ga r the current calendar quarter and current calendar year s e\\
ed in accordance with Step 6.3.3.c.
at least once per 31 days.
b. Action If the calculated ai o active noble gases in gaseous effluents exceeds any of the abo Pimi* p)re and submit to the NRC, within 30 days, a special report in acprd*
wit AP-2802, Notifications and Reports, that identifies the causes exc in e limits and defines corrective actions that have been taken to red c\\*
ses and the proposed corrective actions to be taken to assure that slQseque eI ases will be in compliance with the limits in Step 6.3.3.a.
DOMINION VPAP-2103N REVISION 16 PAGE 26 OF 86
c. Noble Gas Effluent Air Dose Calculation Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qivv.
The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following:
For gamma radiation:
D g = 3.17E-08 MivvQivv +
(15) 1 For beta radiation:
Db = 3.17E-08 ipv Qipv (16) 1 Where:
Subscripts
=
vv, leases from the building ventilation vents, i
dia ctors S
e vent releases from the process vent 1, e to individual radionuclide D9 e a ose for gamma radiation, in mrad Db
\\,
Kr dose for beta radiation, in mrad Miv ie 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 Gaseous Effluent Dose Factors (Attachment 5) ip 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 Gaseous Effluent Dose Factors (Attachment 5)
Qivv, Qipv the release for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site) 3.17 E-08 the inverse of the number of seconds in a year
DOMINION VPAP-2103N REVISION 16 PAGE 27 OF 86 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 1131, 1133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from the site to unrestricted areas from each reactor unit shall be:
" During any calendar quarter: < 7.5 mrem to the critical organ
" During any calendar year: < 15 mrem to the criticalo
2. Cumulative dose contributions to a member of th u
frof131, 1133, tritium, and radionuclides in particulate form hh iv eater than 8 days, in gaseous effluents released to unrestricte ear or t urrent calendar quarter and current calendar year shalldete*n t least once per 31 days in accordance with Step 6.3.4.c.
b. Action If the calculated dose from t rel 1133, tritium, and radionuclides in particulate form, with ha eat than 8 days, in gaseous effluents exceeds any of the above limi re e a ubmit to the NRC within 30 days, a special report in accorda w
AP-802, Notifications and Reports, that contains the:
1.CocCausesAin mits.
2.
o i
tion aken to reduce releases.
3. Pro e
rrective actions to be taken to assure that subsequent releases will e inc pliance with limits stated in Step 6.3.4.a.
DOMINION VPAP-2103N REVISION 16 PAGE 28 OF 86
c. Dose Calculations Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qiv,. 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, th
.a 131, 1133, tritium, and particulate-form radionuclides with h s grei r than 8 days, shall be determined by:
Dr = 3.17E-08 ZRMiv ivv +
v Qipv ]
(17)
Where:
Subscripts
=
vv, refer t
rom the building ventilation vents; pv, refer o eeases from the process vent Dr
=
the 0
co. al organ of the maximum exposed member e
li, imrem RMivv, R hMip he fac r for ventilation vents or process vent release due
/t133, tritium, and from all particulate-form
,,>. ?tdiy pclides with half-lives greater than 8 days, in mrerr/yr Q
\\/x*
urie/sec. Factors are listed in Critical Organ Dose Factors
< ttachment 8) y
=
the release for ventilation vents or process vent of 1131, 1133, tritium, and from all particulate-form radionuclides with
),
8 half-lives greater than 8 days, in Curies
-08
=
the inverse of the number of seconds in a year
DOMINION VPAP-2103N REVISION 16 PAGE 29 OF 86 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 due to gaseous effluent releases, from each unit to areas at and bey site )undary, would exceed 0.2 mrad for gamma radiation and 0.4 eb iation, averaged over 31 days.
2. The Ventilation Exhaust Treatment S m shae sed to reduce radioactive materials in gaseous waste before is e,
en the projected doses due to gaseous effluent releases, from it t eas at and beyond the site boundary, would exceed 0 m
rtical organ, averaged over 31 days.
3. Doses due to gaseou a
fro he site shall be projected at least once per 31 days, base" n cons in Step 6.3.5.c.
b. Action If gaseous
\\'tex ds the limits in Step 6.3.5.a. is discharged without treatme
$Se~re a ubmit to the NRC within 30 days, a special report in acco-a
-h VPAP-2802, Notifications and Reports, that includes:
n ex nation why gaseous radwaste was being discharged without treatment, ation of any inoperable equipment or subsystems, and the reason for the operability.
'.t*Actions taken to restore the inoperable equipment to operable status.
3. Summary description of actions taken to prevent recurrence.
c. Projected Gamma Dose
1. Determine Dg, the 31-day gamma air dose for the previous 31-day period, per Equation (15).
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.
DOMINION VPAP-2103N REVISION 16 PAGE 30 OF 86
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 (pCi/ml).
4. Determine PDg, the projected 31-day gamma air dose.
PDg =Dg(Rg x Fg)
(18)
d. Projected Beta Dose
1. Determine Db, the 31-day beta air dose in the ousd per Equation (16).
2. Estimate Rg and Fg as in Steps 6.3.5.c.
3. Determine PDb, the projected 31-betr
.e.
PD
~
F 9)
(19)
e. Projected Maximu xn ~e3 mber of the Public Dose
1. Determine D
,, the
-day maximum exposed member of the public dose in the previou y pI ld, per Equation (14), where Dr = Dmax-
2. Est the o of the estimated activity from 113, 1133, radioactive n a
.nparticulate form with half-lives greater than 8 days, and tritium in
the c n,,1-day period to the activity of 1131, 1133, radioactive materials in tic te form with half-lives greater than 8 days, and tritium in the previous
- ay period (gCi/ml).
etermine PDmax, the projected 31-day maximum exposed member of the public dose.
PDmax = Dmax(R x Fi2)
(20)
DOMINION VPAP-2103N REVISION 16 PAGE 31 OF 86 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:
Batch Releases NOTE: If the clarifier is in service, releas considered continuous releases.
A Batch Release Permit is requir (or potentially contain) radioacti
BRTT
LLWDT ses from tanks 7
are
- HLWDT ed for a rele sfrom' IRy'taks/sumps which contain ve liqui.
Kninclude:.
secondary coolant activity exceeds 1.0 E-5 ýtCi/iml rization before initiating continuous releases of
- Turbine Buil
- CDT 6.4.2 Release Permit is required for:
" Clarifier, unless being bypassed
Steam generator blowdown when clarifier is bypassed
" Containment mat sumps and service water reservoir when clarifier is bypassed.
Sampling requirements and control and conditions for service water reservoir blowdown, when no radioactivity is detected, shall be specified on the permit.
DOMINION VPAP-2103N REVISION 16 PAGE 32 OF 86 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) i nt Monitor high alarm N
6.4.5 Miscellaneous Gaseous Release Permit KC7)
Operations shall obtain RP authorizati e*
1 g releases of noble gases that may not be accounted for by routine 0n*
o) y planned release not being routed through the Process Vent or Ve ati e.g., steam driven auxiliary feedwater pump testing if primary to s la ge exists).
6.4.6 Radioactive Liquid*r lease Controls
a. Operations sha oti R'l* pending releases and request RP to initiate the appropriate e* r Operations shall provide the necessary information to compl eru lase permnit.
b. A rep
. e sample shall be obtained of the source to be released.
I.
era ns shall provide RP with liquid samples and sample information (e.g.,
sample) for samples obtained outside the Primary Sample Room, except arifier Proportional Tank and Clarifier Grab Samples.
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.
DOMINION VPAP-2103N REVISION 16 PAGE 33 OF 86
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 shal
1. Verify the correct source is authorized for release
2. Note maximum authorized release rate.
3. Note percent of Technical Specificatio
\\
se represents.
4. Note and ensure compliance with ntrols or conditions applicable to the release.
g. When commencing release, 0 ide RP with required information.
As appropriate, required r
n 11 include:
" Date and time rele Bea pd
" Starting tank/s le
" Beginning p ar
Releas t
" Dil e flow rate
h.
n ter atmg the release, Operations shall return the permit to RP and provide atfo necessary for completion of permit. As appropriate, required
'ation shall include:
ate and time release was stopped
Tank/sump ending level
Release flow rate just prior to termination
Ending pressure
Volume released
DOMINION VPAP-2103N REVISION 16 PAGE 34 OF 86 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 materi i
id or gaseous effluents exceed twice the limits in Steps 6.2.3.a., 6.1 a
3.
, calculate (including direct radiation contribution 'from the s a fr*
utside storage tanks) whether limits in Step 6.5.1 have been
b. If the limits in Step 6.5.1 have been exce prepe a d submit to the NRC within 30 days, a special report in ac a c PAP-2802, Notifications and Reports, that defines the corrective en to reduce subsequent releases and to prevent recurrence, an c d s ule for achieving conformance with the limits. Special reports d *10 CFR 20.2203(a)(4), shall include:
1. An analysis that raiation exposure (dose) to a real individual from uraniu el c sources, including all effluent pathways and direct radiation, alefr year that includes the releases covered by the report.
2. A d ip*
o evels of radiation and concentrations of radioactive n
r o
lved, and the cause of the exposure levels or concentrations.
f the ited dose exceeds the limits in Step 6.5.1, and if the release
. n that violates 40 CFR 190 has not already been corrected, the special port shall include a request for a variance in accordance with the provisions of 0 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 Radiological Environmental Monitoring Program (Attachment 9).
DOMINION VPAP-2103N REVISION 16 PAGE 35 OF 86
2. Samples shall be collected from specific locations specified in Environmental Sampling Locations (Attachment 10). [Reference 3.1.31]
3. Samples shall be analyzed in accordance with:
Radiological Environmental Monitoring Program (Attachment 9) requirements
" Detection capabilities required by Detection Capabilities for Environmental Sample Analysis (Attachment 11)
Guidance of the Radiological Assessment Branch T Position on Environmental Monitoring dated November, 19 $,visio
)\\o.
1
b. Action
1. If the Radiological Environmental Moni
s not being conducted as required in Step 6.6.1.a., report the tion i cc rdance with VPAP-2802, Notifications and Reports, by pre n a
tting to the NRC, in the Annual Radiological Environm per ing Report required by Technical Specifications 5.6.2, a des
.t.i Qsons for not conducting the program as required, and theC ng recurrence.
2. If, when averaged er endar quarter, radioactivity exceeds the reporting levels of Re n
I\\(*s for Radioactivity Concentrations in Environmental Samples (
c ent prepare and submit to the NRC within 30 days, a spec
nce with VPAP-2802, Notifications and Reports, that:
e the causes for exceeding the limits, and e
corrective actions to be taken to reduce radioactive effluents so tt potential annual dose to a member of the public is less than the dar year limits of Steps 6.2.3, 6.3.3, and 6.3.4
~hen more than one of the radionuclides listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 12) are detected in the sampling medium, the report shall be submitted if:
concentration (1) + concentration (2) +... > 1.0 (21) reporting level (1) reporting level (2)
DOMINION VPAP-2103N REVISION 16 PAGE 36 OF 86
3. When radionuclides other than those listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 12) 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 Steps 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 accordp awith VPAP-2802, Notifications and Reports.
4. If milk or fresh leafy vegetable samples are un a
e or more of the sample locations required by Environmental ations (Attachment 10), identify locations for obtaining rei e
es and add them to the radiological environmental monito g
ra ithin 30 days. The specific locations from which samples u
aimay then be deleted from the monitoring program. Identei "
see\\
-e unavailability of samples and identify the new locations *N'r I
eplacement samples in the next Annual Radioactive Effluen in accordance with VPAP-2802, Notifications and o
e in the report a revised figure and table for the ODCM to re t the w locations.
6.6.2 Land U
a. Requir n"
A la s
sus shall be conducted and shall identify, within a distance of 8 km ation in each of the 16 meteorological sectors of the following:
ilk animal est residence earest 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.
DOMINION VPAP-2103N REVISION 16 PAGE 37 OF 86
2. In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted ground deposition (D/Qs). Specifications for broad leaf vegetation sampling in Radiological Environmental Monitoring Program (Attachment 9) shall be followed, including analysis of control samples.
b. Action
1. If a land use census identifies locations that yield a c dose or dose commitment greater than the values currently bei *p,
~llate )n 6.3.4.a.2, identify the new locations in the next Annual io V
iv uent Release Report in accordance with VPAP-2802, Notif s)a Reports.
2. If a land use census identifies locatio yie a
lculated dose or dose commitment (via the same expos p
)a percent greater than at a location from which samples ar,
6 g obtained, add the new locations to the Radiologi vir al Monitoring Program within 30 days. Sampling locations, i
e control station location, that have the lowest calculated e00 mitments (via the same exposure pathway) may be delete o
ring program. Identify new locations in the next Annual Ra c*
nt Release Report and include in the report revised figures re ting the new locations in accordance with VPAP-2802, Not' i an eports. [Reference 3.1.33]
6.6.3 Interlab omparisonProgram
a.
ire t
e materials (which contain nuclides produced at the Station), supplied as f an Interlaboratory Comparison Program, shall be analyzed.
DOMINION VPAP-2103N REVISION 16 PAGE 38 OF 86
b. Action
1. Analyses shall be performed at least semiannually as follows:
Program Cross-Check of Milk 1131, Gamma, Sr89 and Sr 90 Water Gross Beta, Gamma, 1131, H3 (Tritium), Sr 89 and Sr9° (blind - any combinations of above radionuclides)
Air Filter Gross Beta, Gamma, Sr 90
2. If analyses are not performed as required by __port in the Annual Radiological Environmental Operatingl ance iwith VPAP-2802, Notifications and Reports, the corre ction to prevent recurrence.
c. Results Results shall be reported in the u
adj gical Environmental Monitoring Report in accordance with V tifications and Reports.
6.7 Reporting Requirements 6.7.1 Annual Radiologic n1men al Operating Report Routine Radiolo 1
iron ntal Operating Reports covering the operation of the units during V'
ndar year shall be submitted prior to May 1 of each year.
A single t
may e made for the Station. Radiological Environmental Operatin shall include:
U an interpretations, and analysis of trends of results of radiological onmental surveillance activities for the report period, including:
omparison (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 Step 6.6.2
DOMINION VPAP-2103N REVISION 16 PAGE 39 OF 86
b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per Step 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 environmen monit g program.
d. At least two legible maps covering sampling lo giving distances and directions from the centerline of on Lo.
e map shall cover stations near the site boundary; a second s in e
distant stations.
e. Results of Station participation in the rl at Comparison Program, per Step 6.6.3.
f. Discussion of deviations fro e
i vronmental sampling schedule per Radiological Environmen on Program (Attachment 9).
g. Discussion of analys nJ e /lower limit of detection (LLD) required by Detection Capab es ?
vironmental Sample Analysis (Attachment 11) was not achievable.
h. Any sa
reI, any groundwater wells described in the environmental prog
\\
lver the results were required by the environmental program or not.
6.7.2 A I Ra ' cive Effluent Release Report ae n it-Station a
active Effluent Release Reports covering operation of the units during the
< 4 ious 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 sumnmarized 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. [Reference 3.1.34]
DOMINION VPAP-2103N REVISION 16 PAGE 40 OF 86
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 Step 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 Steps 6.2.1 and 6.3.1
" Unplanned releases which require a Condition Re and*
olve the discharge of contents of the wrong Waste Gas ay wrong liquid radwaste release tank
" Unplanned releases from large leaks to x
d valve or pipe failures that result in a quantity of releas,ic at
, CFR 50.72, Immediate Notification Requirements fo pe g
- ear Power Reactors or 10 CFR 50.73, Licensee Event R S
mt ort is required
Unplanned releases in by Radiation Protection Supervision, which may or no u
-Condition Report
4. Major chan o r tive liquid, gaseous, and solid waste treatment systems during the g
iod.
5. Cha s t P'
03N, Offsite Dose Calculation Manual (North Anna)
S n.7.4).
itio new locations for dose calculations or environmental monitoring
~
Jd by the land use census (See Step 6.6.2).
7.
summary of radioactive leaks or spills meeting the following criteria:
An unintended spill or leak with the potential to reach groundwater, as defined in NEI 07-07, and
" The spill or leak must be greater than 100 gallons in volume or the volume cannot be quantified but is estimated to be greater than 100 gallons; or
" Any spill or leak, regardless of volume or activity deemed by the licensee to be reportable.
DOMINION VPAP-2103N REVISION 16 PAGE 41 OF 86
8. Any groundwater sample results from locations not part of the Radiological Environmental Monitoring Program.
b. Dose Assessment
1. Radiation dose to individuals due to radioactive liquid and gaseous effluents from theStation 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 p radioactive liquid and gaseous effluents from the Station shall
- ihcrzor -d with the dose assessment performed above. If the dose to t4 aiu osed member of the public exceeds twice the limits of 6.2. 3a
-.3.3.a. 1, or 6.3.4.a. 1, the dose assessment shall include the otrubu direct radiation.
NOTE: NUREG-0543 states: "There is reasor 4,ran that operating reactors that have relea it h(~~dix I de also in conformnance with the E(
Fuel Cycle St
3. Meteorological c it' g the previous calei annual avera a
o' ric dispersion conditions s]
gaseu i
4os9s, sites with up to four sign objective values are andard, 40 CFR Part 190."
ndar year or historical hall be used to determine
DOMINION VPAP-2103N REVISION 16 PAGE 42 OF 86 NOTE: The Annual Radioactive Effluent Report for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Release Report.
c. ISFSI 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 opulation doses shall not be included in dose assessments.
" The dose to the maximum exposed member of t b, i d>
dioactive liquid and gaseous effluents from the Station shall bei ior with the dose assessment performed above. If the dose e
exposed member of the public exceeds twice the limits of 6.).a.,.2.3 2, 6.3.3.a.1, or 6.3.4.a.1, the dose assessment shall include thentr*tio m direct radiation.
Meteorological conditions t
e *s calendar year or historical annual average atmospheric disper:
iio s shall be used to determine gaseous pathway doses.
6.7.3 Annual MeteorologA lDI
a. Meteorologica 4t lect during the previous year shall be in the form of joint frequenc wind speed, wind direction, and atmospheric stability.
b. Mete data shall be retained in a file on site and shall be made available to u he-St.
6.7.4 nstODCM to the ODCM shall be:
a. ~viewed and approved by Facility Safety Review Committee (FSRC) and Site Vice President before implementation.
b. Documented. Records of reviews shall be retained as Station records.
Documentation shall include:
1. Sufficient information to support changes, together with appropriate analyses or evaluations justifying changes.
DOMINION VPAP-2103N REVISION 16 PAGE 43 OF 86
2. A determination that a change will not adversely impact the accuracy or reliability of effluent doses or setpoint calculations, and will maintain the level of radioactive effluent control required by:
10 CFR 20 Subpart D
40 CFR 190
10 CFR 50.36a
10 CFR 50, Appendix I
c. Submitted to NRC in the form of a complete, legible cop tire ODCM as a part of, or concurrent with the Annual Radioactive E lalelea)
Report for the period of the report in which any change was mad.
hac a all be identified by markings in the margin of the affected pa I
i ating the area of the page that was changed, and shall indicate t ate nth/year) the change was implemented.
d. Submitted to NRC in accordance w (P
2, Notifications and Reports.
6.7.5 Groundwater Protection Initi ve e 3.1.35]
a. Notifications and Repo
1. Informal commurti e made to state/local/NRC officials by the end of the next b ess fr
- Any spil *t ng the requirements of Step 6.7.2.a.7.
An*
o mple result exceeding the reporting levels of Reporting Radioactivity Concentrations in Environmental Samples
, *nt 12).
0-r report shall be submitted to the NRC and a copy concurrently Srwarded to state and local officials for any groundwater sampling result, hether on site or off site, exceeding the reporting levels of Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 12) and having the potential to reach groundwater that is or could be used as a source of drinking water. A 30-day report is only required on the initial discovery of a contaminated groundwater plume.
b. Any spill or leak for which an informal notification is made in accordance with Step 6.7.5.a. shall be summarized in the Annual Radioactive Effluent Report.
DOMINION VPAP-2103N I
SION 16 PAdt 44 OF 86
c. Any groundwater sample result from a groundwater source that is not part of the radiological environmental monitoring program shall be included in the Annual Radioactive Effluent Report.
d. Any groundwater sample result from any groundwater well described in the radiological environmental monitoring program shall be included in the Annual Radiological Environmental Operating Report.
7.0 RECORDS 7.1 The following record(s) completed as a result of this procedure are uired be transmitted to Nuclear Document Management (DNM). The records have/n i nd retention requirements established for the NuclearRecords Retention
,1e S) per RM-AA-100, Record Creation, Transmittal and Retrieval.
Quality Assurance Records
" Records of changes to the ODCM in accorda p 6.7.4
" Records of meteorological data in acc anc 6.7.3
" Records of sampling and analyses
" Records of radioactive materi s'ng uents released to the environment
" Records of preventive min n c rveillances, and calibrations 7.2 The following item(s) d a esult of this procedure are NOT records and are NOT required to be tran tte N
ar Document Management (DNM).
None
DOMINION VPAP-2103N REVISION 16 PAGE 45 OF 86 ATTACHMENT 1 (Page 1 of 2)
Radioactive Liquid Effluent Monitoring Instrumentation Instrument Minimum Operable Action
1. Liquid Radwaste Effluent (a) 1-LW-RM-111, Liquid Radwaste Effluent Monitor 1
(b) 1-LW-FT-104, Liquid Radwaste Effluent Total Flow Measuring Device (c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel 1
(d) 1-LW-1130, Liquid Waste Effluent Proportional S p**e (e) 1-SW-RM-108, Service Water Effluent M
(
I l ote 2)
(f) 1-SW-RM-130, Unit 1 Circulating te'ystei) Effluent Line 13 M onitor
'fluentM (g) 2-SW-RM-230, Unit 2 Circ ti ater ;;Sstem Effluent Line 1
3 Monitor
2. Steam Generator Hi a
owdown (a) Steam Generato city B lowdown Radiation Monitor Unit1 1-
- M1 1
Unit 1S-1 (b) Stea.
er r High Capacity Blowdown Flash Tank Outlet Flow
Rate, Unit 1 1-BD-FT-105 1
2 Unit 2 2-BD-FT-205 1
2 (c) Steam Generator High Capacity Blowdown Proportional Sampling System Collection Tank Unit 1 1-BD-TK-4 1
1 Unit 2 2-BD-TK-4 1
1
DOMINION VPAP-2103N REVISION 16 PAGE 46 OF 86 ATTACHMENT 1 (Page 2 of 2)
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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity (beta and gamma) at an LLD of at least I x 10-7 gCi/g or an isotopic radioactivity at an LLD of at least 5x 10-7 gCi/g.
ACTION 2:
If the number of operable channels is less than required, e re es via this pathway may continue if the flow rate is estimated at le n' "er §)ours during actual releases. Design capacity performance curves er.
d^in. u may be used to estimate flow.
ACTION 3:
If the number of operable channels is less
'uirednake repairs as soon as possible. Effluent releases via this path y m.
c i e provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples from the '-s cy, c~l are collected and analyzed for principal gamma emitters as defi ive Liquid Waste Sampling and Analysis Program (Attachm NOTE 1:
The capability for obtaininA ~*,,t least every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months must exist. Grab samples shall commence if ther inc of radioactivity in the Service Water System or an indication from other r n rnitors in the Service Water System of an increase in radioactivity.
NOTE 2:
To utilize 1-08 as the effluent radiation monitor for the associated loop, 0-PT-75
, (1-
-108 Flow Verification) must be performed prior to placing the loop in,
.pge.
u monitoring is not required when discharge flowpath is not in service.
DOMINION VPAP-2103N REVISION 16 PAGE 47 OF 86 ATTACHMENT 2 (Page 1 of 2)
Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel Channel Check Check Calibration Operational Test
1. Liquid Radwaste Effluent (a) 1-LW-RM-1 11, Liquid Radwaste Effluent Monitor D
D Q (NOTE 1)
(b) I-LW-FT-104, Liquid Radwaste Effluent Total Flow
)
Measuring Device (c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel D (
TE 4)
N N/A N/A (d) 1-LW-1130, Liquid Waste Effluent Proportional Sam<
OT 4 N/A N/A N/A Valve (e) 1-SW-RM-108, SW Effluent Monitor (NOTE D
R Q (NOTE 2)
(f) 1-SW-RM-130, Unit 1 Circul em D
R Q(NOTE 2)
Effluent Line Monitor
/
(g) 2-SW-RM-230, Unit 2 Ci 9
ter System D
M R
Q (NOTE 2)
Effluent Line Monit°or
)
x/
//
Q(OE2
2.
Steam Generator (S,)agpacity Blowdown (a) SG H a
Blo wn Radiation Monitor Unit S-I-125 Q (NOTE 6)
Unit 2
-225 D (NOTE 7) D (NOTE 8)
R R (NOTE 5)
(b) SG High Capacity Blowdown Flash Tank Outlet Flow Rate Unit 1 1-BD-FT-105 Unit 2 2-BD-FT-205 D (NOTE 8)
N/A R
N/A (c) SG High Capacity Blowdown Proportional Sampling System Collection Tank Unit 1 1-BD-TK-4 D (NOTE 4)
N/A N/A N/A Unit 2 2-BD-TK-4
DOMINION VPAP-2103N REVISION 16 PAGE 48 OF 86 ATTACHMENT 2 (Page 2 of 2)
Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1:
The Channel Operational Test shall demonstrate:
a. Automatic 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 s *_operate" mode.
NOTE 2:
The Channel Operational Test shall demonstrate that Control alar nnunciation occurs if any of the following conditions exists:
a. Instrument indicates measured levels above the ale t.
b. Instrument controls not set in "operate" mod NOTE 3:
Channel Check shall consist of verifying i ai oY during periods of release.
Channel Check shall be made at least o p
h?, on days on which continuous, periodic, or batch releases are made.
NOTE 4: Channel Check shall consist o in roportional flow exceeds 0.5 mls/gallon.
NOTE 5:
Channel Operational Test a
e that system isolation occurs on a radiation monitor High-High Al NOTE 6:
Channel Operatio a
onstrate:
a. Trip sign s\\
at the required setpoints. Isolation is not required.
b. Locl-raddia' itor indication occurs if instrument controls are not set in "Operate"
ex istrument indicates measured levels are above the alarm/trip setpoint.
NOTE 7:
monitor automatically performs periodic source checks. The Source Check an* C Check are satisfied as long as the green light is lit.
NOTE 8: This is verified by indicated effluent flow less than or equal to 190 gpm.
NOTE 9: To utilize 1-SW-RM-108 as the effluent radiation monitor for the associated loop, 0-PT-75.21, (1 -SW-RM-108 Flow Verification) must be performed prior to.placing the loop in service. Effluent monitoring is not required when discharge flowpath is not in service.
DOMINION VPAP-2103N REVISION 16 PAGE 49 OF 86 ATTACHMENT 3 (Page 1 of 3)
Radioactive Liquid Waste Sampling and Analysis Program
DOMINION VPAP-2103N REVISION 16 PAGE 50 OF 86 ATTACHMENT 3 (Page 2 of 3)
Radioactive Liquid Waste Sampling and Analysis Program NOTE 1:
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
(9-1)
Where:
LLD
=
the "a priori" (before the fact)
(as microcuries per unit mass Sb
=
the standard deviation of the rate of a blank sample as E
=
the counting efficie (a
V
=
the sample s nit 2.22E+06 =
the numb& oaolons i Lower Lift o
ete hn as defined above or v section 4.8) k i nd) nting rate or of the counting 49 counts per minute, cpm)
Iu r disintegration) ss or volume) per minute (dpm) per microcurie Y
yield (when applicable) decay constant for the particular radionuclide At time between the midpoint of sample collection and time of
,s of E, V, Y and At should be used in the calculation.
The LD-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.
DOMINION VPAP-2103N REVISION 16 PAGE 51 OF 86 ATTACHMENT 3 (Page 3 of 3)
Radioactive Liquid Waste Sampling and Analysis Program NOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn 54, Fe5 9, Co 5 8, Co 60, Zn 65, Mo9 9, Cs 13 4, Cs 13 7, Ce 14 1, and Ce 14 4. 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
' p1 pr*9rtional to the quantity of liquid waste discharged and for which the met
/o/. p employed results in a specimen that is representative of the liquids rel NOTE 5:
A continuous release is the discharge of liquid w of a
-screte volume, e.g., from a volume of a system that has an input flow n th uous release.
NOTE 6:
To be representative of the quantities an s of radioactive materials in liquid effluents, samples shall be collected n
ti proportion to the rate of flow of the effluent stream. Prior to analyse,ls le ken for the composite shall be thoroughly mixed in order for the comp e s e
e representative of the effluent releases.
NOTE 7: Whenever the secondar, ol"n tivity exceeds 10-5 gCi/ml, the turbine building sump pumps shall be placed,u1(uajperation and samples shall be taken and analyzed prior to release. Seco y
o1";
vity samples shall be collected and analyzed on a weekly basis mples are analyzed for gross activity or gamma isotopic activity within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months NOTE 8:
Theg'm t
for which the LLD specification applies exclusively are the following rai'*
-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138. This list does-n t n 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.
DOMINION VPAP-2103N REVISION 16 PAGE 52 OF 86 ATTACHMENT 4 (Page 1 of 4)
Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Sampling Minimum Analysis Type of Activity Detection (LLD)
Type Frequency Frequency Analysis (Cml), (Note 1)
Principal Gamma gim)(Nt1_
A. WastePrior to Release Prior to Release Emitters (Not StoragteGa (Ec Tank (Each Tank)
Storage Tank Grab Sample)
(Each Tank)
H 3 1 x 10-B. Containment Prior to Release Prior to Release nc r o1
_ l0-4 Purge (Each PURGE (Each PURGE)
I x 10-6 Grab Sample)
Z C. Ventilation Monthly M
/"t i n
Gamma 1
1 (1) Process Vent (Grab Sample)
E ters (Note 2)
(2) Vent Vent A (Notes 3, 4, and 5) 1e H3 lxl0-6 (3) Vent Vent B
(
3 5
Continuous eel e
I131 1 x 10-12 (Note 4) **
ample) 1133 1 x 10-10 All Release Contin
\\,Weekly Pnncipal Gamma 1 x 10-11 N
P P culate Sample Emitter (Note 2) m~ s M onthly Types as listed
4)
Composite Gross Alpha 1 x 10-11 Particulate Sample C
Quarterly in A, B, an s
4Composite Sr89 and Sr9° 1 x 10-11 Particulate us Noble Gases Gross 1 x 10-6 eGas Monitor Beta or Gamma Condenser Air Weekly Weekly Fnnciple Gamma I x 10-4 Ejector/Steam Emitters (Note 7)
Generator Grab Sample H3 1 x 10-6 Blowdown Vent /
(Note 6)
BRT Vent Containment Prior to Release Prior to each Frinciple Gamma 1 x 10-4 Vacuum Steam Emitters (Note 2)
Ejector (Hogger)
(Grab Sample)
Release H3 1 x 10-6 Ejco Hge)
(Note 8) 1111
DOMINION VPAP-2103N REVISION 16 PAGE 53 OF 86 ATTACHMENT 4 (Page 2 of 4)
Radioactive Gaseous Waste Sampling and Analysis Program NOTE 1:
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD=
b(111)
E V
2.22E+06 o Y o e-((1A Where:
LLD
= the "a priori" (before the fact) Lower Li ete i n as defined above (as microcuries per unit mass or v section 4.9)
Sb
=
the standard deviation of the kg nd nting rate or of the counting rate of a blank sample as ro te counts per minute, cpm)
E
= the counting efficie (er eradisintegration)
V
= the sample si nit ss or volume) 2.22E+06 = the num o
4 tegrations per minute (dpm) per microcurie Y
=
thelIochemical yield (when applicable)
Sioact'e decay constant for the particular radionuclide At sed time between the midpoint of sample collection and time of nting TY a
s of E, V, Y and At should be used in the calculation.
The L 1 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.
DOMINION VPAP-2103N REVISION 16 PAGE 54 OF 86 ATTACHMENT 4 (Page 3 of 4)
Radioactive Gaseous Waste Sampling and Analysis Program NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr8 7, Kr88, Xe1 3 3, Xe13 3m, Xe1 3 5, Xe13 5m, and Xe1 38 for gaseous emissions and Mn 5 4, Fe59, Co 5 8, Co60, Zn6 5, Mo 99, Cs 134, Cs 13 7, Ce 14 1 and Ce144 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 lev ding the LLD, together with the above nuclides, shall also be identified and p
d.
NOTE 3: Sampling and analysis shall also be performed following Id s
p, and whenever a thermal power change exceeding 15 percent of the r al er occurs within any one-hour period, if:
a. Analysis shows that the dose equivalent c n n in the primary coolant is greater than 1.0 ýtCi/gm; and*,
/,/
/
b. The noble gas activity monitor has increased by more than a factor of 3.
NOTE 4: The ratio of the sample fib pled stream flow rate shall be known for the period covered by eac se rate calculation made in accordance with Steps 6.3.1, 6.3.3, a oc p NOTE 5: Samples shall h
once per seven days and analyses shall be completed within 48 ho changing (or after removal from sampler). Sampling shall also be perform at per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least seven days following each shutdown, sta -
r ower change exceeding 15 percent of rated thermal power in one hour ana1 shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24
,'are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:
a. Analysis shows that the dose equivalent 1131 concentration in the primary coolant is greater than 1.0 pCi/gm and;
b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.
DOMINION VPAP-2103N REVISION 16 PAGE 55 OF 86 ATTACHMENT 4 (Page 4 of 4)
Radioactive Gaseous Waste Sampling and Analysis Program NOTE 6: Whenever the secondary coolant activity exceeds 10-5 RCi/ml, Condenser Air Ejector and Steam Generator Blowdown Vent 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
NOTE 7:
The principal gamma emitters for which the LLD specification l/s lusively are the following radionuclides: Kr87, Kr88, Xe133, Xe133m, Xe 135 1
nd 138 for gaseous emissions. This list does not mean that only these nuclide e
ted and reported.
Other peaks that are measurable and identifiable, at le d
e LLD together with the above nuclides, shall also be identified and re ted.
NOTE 8: If the secondary coolant activity level in any a
r supplying steam to the Hogger exceeds 1.OE-5 gCi/ml, Steam Gen sa les shall be obtained and analyzed prior to release.
DOMINION VPAP-2103N REVISION 16 PAGE 56 OF 86 ATTACHMENT 5 (Page 1 of 3)
Gaseous Effluent Dose Factors (Gamma and Beta Dose Factors) x/Q = 9.3E-06 sec/m 3 at 1416 meters SE Direction Dose Factors for Ventilation Vent Kivv Livv Mivv
-Nivv Noble Gas Total Body Skin Gamma Beta Air Radionuclide mrem/yr mrem/yr m ad Curie/sec Curie/sec C _*,e',sey>
Curie/see Kr-85m 1.09E+04 1.36E+04 1
04 1.83E+04 Kr-85 1.50E+021
+04 Kr-87 5.5 1E+04 9.05E+
E+04 9.58E+04 Kr-88 1.37E+05 2.2,C" 1.41E+05 2.72E+04 Kr-89 1.54E+05
4) 1.61E+05 9.86E+04 Xe-131m 8.51E+02 /
3 1.45E+03 1.03E+04 Xe-133m 2.33E+
2i0 3.04E+03 1.38E+04 Xe-133 2e-P'3
\\2.85E+03 3.28E+03 9.77E+03 Xe-135m
<,9"K<4 6.61E+03 3.12E+04 6.87E+03 Xe-+4 1.73E+04 1.79E+04 2.29E+04 Xe-137
/
21.13E+05 1.40E+04 1.18E+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
DOMINION VPAP-2103N REVISION 16 PAGE 57 OF 86 ATTACHMENT 5 (Page 2 of 3)
Gaseous Effluent Dose Factors (Gamma and Beta Dose Factors)
X/Q = 1.2E-06 sec/m 3 at 1513 meters S Direction Dose Factors for Process Vent
DOMINION VPAP-2103N REVISION 16 PAGE 58 OF 86 ATTACHMENT 5 (Page 3 of 3)
Gaseous Effluent Dose Factors (Inhalation Pathway Dose Factors)
Ventilation Vent X/Q = 9.3E-06 sec/m 3 at 1416 meters SE Direction Process Vent X/Q = 1.2E-06 sec/m 3 at 1513 meters S Direction Pivv Pipv Radionuclide mrem/yr Curie/sec Cu sec H-3 1.05E+04
.3
" 03 Cr-51 7.95E+02
. 2E+02 Mn-54 ND ND Fe-59 ND ND Co-58NDD Co-60 ND ND Zn-65 ND Rb-86 ND Sr-90 N
ND Y-91 ND Zr-95 ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-i 1 O ND ND Te-5.64E+04 7.28E+03 Te 5.88E+04 7.59E+03 Cs-13 ND ND Cs-136 ND ND Cs-137 ND ND B a-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
DOMINION VPAP-2103N REVISION 16 PAGE 59 OF 86 ATTACHMENT 6 (Page 1 of 3)
Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM OPERABLE ACTION CHANNELS
1. PROCESS VENT SYSTEM (a)
Noble Gas Activity Monitor 1-GW-RM-178-1 2,4 (b)
Iodine Sampler 1-GW-RM-178-1 2,5 Process Vent Continuous HP Sampler (c)
Particulate Sampler 1-GW-RM-178-1.1 Process Vent Continuous HP Sampler NOTE 3)
(d)
Total Flow Monitor 1-GW-FT-108 (e)
Sampler Flow Rate Measuri MGPI Flow Rate Measu e ic 1
HP Sampler Rotameter (NOTE 3)
2. CONDENSER AIR E N
M (a)
Gross sacti vi*,,* (9 Unit 3
1-SV-R3 Unit 2
-*RM
-*" 1 (b)
Flo0,1 te ng Device U
FI-100A 1 FI-101A 1 (NOTE 1) 1 FI-100B 1-SV-FI-101B Unit 2 2-SV-FI-200A 2-SV-FI-201A 1 (NOTE 2, 1 (NTE 1
/--3 V -r1-/UVfl 2-SV-FI-201B
DOMINION VPAP-2103N REVISION 16 PAGE 60 OF 86 ATTACHMENT 6 (Page 2 of 3)
Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM OPERABLE ACTION CHANNELS
3.
VENTILATION VENT A (a)
Noble Gas Activity Monitor 1-VG-RM-179-1 (NO 2
(b)
Iodine Sampler 1-VG-RM-179-1 (1
2 Vent Vent A Continuous HP Sampler (c)
Particulate Sampler V
1-VG-RM-179-1 2
Vent Vent A Continuous HP Sampler (NOTE 3) 2 (d)
Total Flow Monitor 1 -HV-FT-121 2Ai1 (e)
Sampler Flow Rate Measuri e 1 MGPI Flow Rate Measur ei*'ect,
.1 HP Sampler Rotameter (NOTE 3)
4. VENTILATION VEN (a)
Noble Gas i
nitor
-VG-R 180-1 (NOTE 3) 2 1
Vent Continuous HP Sampler (NOTE 3) 2 (c)
Particulate Sampler 1 -VG-RM-180-1 1
Vent Vent B Continuous HP Sampler (NOTE 3)
(d)
Total Flow Monitor 1-HV-FT-1212B (e)
Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring Device 1
1 HP Sampler Rotameter (NOTE 3)
DOMINION VPAP-2103N REVISION 16 PAGE 61 OF 86 ATTACHMENT 6 (Page 3 of 3)
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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 3:
If the number of operable channels is less than required, effluent r e
this path may continue if grab samples are taken at least once per twelve (12) h and t e samples are analyzed for gross activity or gamma isotopic activity within (t
ur.
his requirement is for effluent accountability and is distinct and separate a
equ nt for primary-to-secondary leak rate determination. The need to determine t
-secondary leak rate, e.g., the performance of 1/2-PT-46.3B, shall be deter ce with the requirements of TRM TR 3.4.5. However, the same sample ma used uI I both the requirements of this action and primary-to-secondary leak rate/*er i
ACTION 4:
If the number of operable channels is less t Tanks may be released to the environme.aq:
W contents of the Waste Gas Decay
ýprior to initiation of the release:
a.
At least two independent ntents are analyzed, and:
b.
At least two technically release rate calculations lof the Station staff independently verify the e lineup.
ACTION 5:
If the number of operal Decay Tank may conA 9irfes-Zthan required, effluent releases from the Waste Gas amples are continuously collected with auxiliary sampling ive Gaseous Waste Sampling and Analysis Program equipment as re(
(Attachment
)
NOTE 1:
A channel s c
of:
a. The instr en nstalled, in the ejector through which the discharge is routed; either Train K ' S*-10, 10 1A), or Train B (1-SV-FI-100B, 101B) or both.
b.
lo ts 101A and 101B provide low range measurement. Flow instruments 100A and
lSprJide high range measurement.
NOTE 2:
A cha 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 a MGPI monitor; and a MGPI or HP particulate and iodine sampler, and its associated sampler flow rate measuring device or rotameter.
DOMINION VPAP-2103N REVISION 16 PAGE 62 OF 86 ATTACHMENT 7 (Page 1 of 3)
Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL Channel CHANNEL DESCRIPTION CHECK CHECK CALIBRATION Operational Test
1. PROCESS VENT SYSTEM (a)
Noble Gas Activity Monitor 1-GW-RM-178-1 D
M (NOTE 5)
Q (NOTE 1)
(b)
Iodine Sampler 1-GW-RM-178-1 W
N/A A
N/A Process Vent Continuous HP Sampler D (NOTE 3)
N/I N/A (c)
Particulate Sampler 1-GW-RM-178-1 W
N/A N/A Process Vent Continuous HP Sampler D (NO N/A N/A (d)
Total Flow Monitor 1-GW-FT-108 N/A R
Q (e)
Sampler Flow Rate Measurin
ý2 Device MGPI Flow Rate Meas D (,TE
3)
N/A R
N/A Device HP Sampler Rot ter))
D (NOTE 3)
N/A R
N/A
2.
CONDENSER JECTOR SYSTEM (a)
Noble G tivit onitor U22I D
M R
Q, R (NOTE 6)
(b)
Flow easuring Device Unit 1 1-SV-FI-100A 1-SV-FI-101A D
N/A R
N/A 1 -SV-FI-I OOB 1-SV-FI-101B Unit 2 2-SV-FI-200A 2-SV-FI-201A 2-SV-FI-200B 2-SV-FI-201B
DOMINION VPAP-2103N REVISION 16 PAGE 63 OF 86 ATTACHMENT 7 (Page 2 of 3)
Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL DESCRIPTION CHANNEL I
SOURCE CHANNEL Channel CHECK CHECK CALIBRATION I Operational Test
3.
VENTILATION VENT A (a)
Noble Gas Activity Monitor 1-VG-RM-179-1 (b)
Iodine Sampler 1-VG-RM-179-1 Vent Vent A Continuous HP Sampler (c)
Particulate Sampler 1-VG-RM-179-1 Vent Vent A Continuous HP Sampler (d)
Total Flow Monitor 1-HV-FT-1212A (e)
Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring Device HP Sampler Rotameter D
W D (NOTE 3)
W (NOTE 3)
D M (NOTE 5)
N/A N/A N/A
))N/A N/A R
A A
)N/A R
R R
Q (NOTE 2)
N/A N/A N/A N/A Q
N/A N/A x
E(3 0
4. VENTILATION VENT B (a)
Noble Gas Activity 1
1-VG-RM-180-1 7 (b)
Iodine Sample 1-VG-RM-180-Vent Ver,4 Cont u-P (c)
Pa ulat I- - Vent V aV ontinuous HP Sampl el (d)
Total Flow Monitor 1-HV-FT-1212B (e)
Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring Device HP Sampler Rotameter>
W D (NOTE 3)
W D (NOTE 3)
D D (NOTE 3)
D (NOTE 3)
M (NOTE 5)
N/A N/A N/A N/A N/A N/A R
N/A N/A N/A N/A R
R Q (NOTE 2)
N/A N/A N/A N/A Q
N/A N/A R
N/A
DOMINION VPAP-2103N REVISION 16 PAGE 64 OF 86 ATTACHMENT 7 (Page 3 of 3)
Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1:
The Channel Operational 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
ý" mode.
NOTE 2: The Channel Operational Test shall demonstrate:
a. Control Room alarm annunciation occurs if the levels are above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instruni," c0l es measured set in "operate" mode.
NOTE 3:
Channel Checks shall consist of verif in o on flow during periods of release.
Channel Checks shall be made at lea nc""
ours on days on which continuous, periodic, or batch releases are m i
cat' need only to be done to verify operabilit3 of one train, either MGPI or S*a.
NOTE 4: The Channel Operation st s demonstrate that:
a. Control Room alar nci~alion occurs if the instrument indicates measured levels Y
are above al*
b. The Instl2<e"*
selection control automatically resets to "operate" mode when NOTE 5:
!t1(I-178-1, 1-VG-RM-179-1, and 1-VG-RM-180-1 perform periodic automatically.
NOTE 6:
The q 6a*Wly, Q, Channel Operational Test shall demonstrate that Control Room Alarm annuciation occurs if the instrument indicates measured levels above the alarm/trip setpoint and alarm annunciation occurs if the instrument controls are not set in the "operate" mode.
The refueling, R, Channel Operational Test shall demonstrate:
a. Automatic actuation of the valves in this pathway and Control Room Alarm annunciation occur if the instrument indicates above the alarm/trip setpoint.
b. Alarm annunciation occurs if the instrument controls are not set in the "operate" mode.
DOMINION VPAP-2103N REVISION 16 PAGE 65 OF 86 ATTACHMENT 8 (Page 1 of 2)
Critical Organ Dose Factors (Critical Pathway Dose Factors)
Ventilation Vent X/Q = 3.3E-6 at 1593 meters SSE Direction Process Vent X/Q = 9.5E-7 at 1593 meters SSE Direction Ventilation Vent D/Q = 1.7E-8 at 1593 meters SSE Direction Process Vent D/Q
.1.1E-8 at 1593 meters SSE Direction RMivv M
Radionuclide mrem/yr mr'C Curie/sec ec H-3 1.32E+4
'4&E+3 Mn-54 ND N
Fe-59 ND ND Cr-51 1.11E+3 7.16E+2 Co-58 ND ND Co-60 ND Zn-65 ND Rb-86 ND Sr-89 ND Sr-90 X" ND ND Y-91 ND ND Zr-95 NND Nb-9053
\\\\X-1 ND ND Ru-10 ND ND Ru NDND ND ND Te-12Q__*
5.37E+6 3.48E+6 Te-129m 4.61E+6 2.98E+6 1-131 8.08E+8 5.23E+8 1-133 1.38E+7 8.93E+6 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND B a-140 ND ND Ce-141 ND ND
DOMINION VPAP-2103N REVISION 16 PAGE 66 OF 86 ATTACHMENT 8 (Page 2 of 2)
Critical Organ Dose Factors
DOMINION VPAP-2103N REVISION 16 PAGE 67 OF 86 ATTACHMENT 9 (Page 1 of 5)
Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and F'requency of and/or Sample Sample Location (NOTE 2)
Frequency Analysis
1. DIRE(§T 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
(
meteorological s c*t,.
within the sit ary
2) An outer rif stations e i ch emer o*f"cyy9")
n e
ica ctor fth'8
ge from elance of the
'*tio s to be placed in Q.%*cial interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations Quarterly GAMMA DOSE Quarterly
DOMINION VPAP-2103N REVISION 16 PAGE 68 OF 86 ATTACHMENT 9 (Page 2 of 5)
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. AIRBtORNE Samples from 5 locations:
a) 3 samples from close to the 3 site boundary locations (in different ioi e Canister sectors) of the highest
r.
Analysis, weekly calculated historical annual average ground Conti Radioiodines and level D/Q sa e
Particulates b) 1 sample from the ra wi vicinity of a commun a
e co tion Particulate Sampler having the highest Gross beta radioactivity calculated annua analysis following filter average grou.
e change; (NOTE 4)
D/Q "N,.-.
c) 1 samp om ntrol Gamma isotopic analy-locatd k
sis of composite (by location) quarterly eev2 nt direction (NOTE 5)
3. WAIERBURNE S
I om 3 locations:
S ample upstream Gamma isotopic analysis sample u nstream monthly; (NOTE 5) b 1 sample downstream Grab Monthly Composite for tritium 4
)c) 1 sample from cooling analysis quarterly lagoon Gamma isotopic and tritium b) Ground Sample from 1 or 2 sources Grab Quarterly analysis quarterly (NOTE only if likely to be affected 5) 1 sample from downstream Gamma isotopic analysis c) Sediment area with existing or Semi-Annually semi-annually (NOTE 5) potential recreational value
DOMINION VPAP-2103N REVISION 16 PAGE 69 OF 86 ATTACHMENT 9 (Page 3 of 5)
Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency of and/or Sample Sample Location (NOTE 2)
Frequency Analysis
4. INUQESTION 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 lya
'dmma isotopic (NOTE 5)
(NOTE 7) doses are calculated to be and 1131 analysis monthly greater than 1 mrem per yr (NOTE 6) b) 1 sample from milkin animals at a control 1 (15-30 km in the prevalent winl' rer.*
a) 1 sample o nNk*cia nd recreati ly p
nt species sNun lh, catfish) b) Fish and i*
discharge Semiannually mmaisotopic on edible Invertebrates portions 1s lse (of same species in d.di s' influenced by plant
\\ is.arge
'&ýples of an edible broad leaf vegetation grown nearest each of two different offsite locations of highest predicted historical annual average Monthly if groud leel DQ ifmilkGamma isotopic (NOTE 5) c) Food Products ground level DIQ if milk available, or 1131 aa sampling is not performed at harvest and analysis b) 1 sample of broad leaf vegetation grown 15-30 km in the least prevalent wind direction if milk sampling is not performed
DOMINION VPAP-2103N REVISION 16 PAGE 70 OF 86 ATTACHMENT 9 (Page 4 of 5)
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 Environmental Samp t
Attachment 10), specific parameters of distance and direction sector tf en ne of the reactor, and. additional description where pertinent, shall be hment 10. Refer to Radiological Assessment Branch Technical Positi and G-0 133, Preparation of Radiological Effluent Technical Specificatio or ea.ower Plant. Deviations are permitted from the required sampling sche e
eci ns are unattainable due to hazardous conditions, seasonal unava-ty, ction of automatic sampling equipment and other legitimate reaso.
p mens are unattainable due to sampling equipment malfunction, every o
ade to complete corrective action before the end of the next sampling ioio ns from the sampling schedule shall be documented in the An io 'cal Environmental Operating Report pursuant to Step 6.7.1. It is recyg.u at times, it may not be possible or practicable to continue to obtain sampl f t me of choice at the most desired location or time. In these instances, su I
rnative media and locations may be chosen for the particular pathwa ques a
appropriate substitutions made within 30 days in the radiological env)j)ý5 netoring program. In lieu of a Licensee Event Report and pursuant to St entify the cause of the unavailability of samples for that pathway and identify the ne~ltions 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.
DOMINION VPAP-2103N REVISION 16 PAGE 71 OF 86 ATTACHMENT 9 (Page 5 of 5)
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 The 36 stations are not an absolute number. The number of direct radiation n
n st)i ions may be reduced according to geographical limitations, e.g., at an a
te,>
sectors will be over water so that the number of dosimeters may be reduce or*ly. The frequency of analysis or readout for TLD systems will depend in theristics of the specific system used and should be selected to obtain dos nformation with minimal fading.
NOTE 4: Airborne particulate sample filters sh an or gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for r oron daughter decay. If gross beta activity in air particulate samples is gr ran es the yearly mean of control samples, gamma isotopic analysis s I
d on the individual samples.
NOTE 5: Gamma isotopic anal is id ification and quantification of gamma-emitting radionuclides that tri ble to effluents from the facility.
NOTE 6: The dose shal ated r the maximum organ and age group, using the methodology and parameter DCM" NOTE 7: If mi ing not be performed, use item 4.c (Page 3 of 5, Radiological Er*ro t -- onitoring Program (Attachment 9)).
DOMINION VPAP-2103N REVISION 16 PAGE 72 OF 86 ATTACHMENT 10 (Page 1 of 4)
Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media IINo.
I(Miles)
Freqenc Environmental NAPS Sewage TLDs Treatment Plant 01 0.20 NE Quarterly &
Annually On-Site Frederick's Hall 02 5.30 SSW e
-r ually Mineral,VA 03 7.10 Wares Crossroads 04 5.10
< qu*v,-rly &
ually Route 752 05 4.20 NNE uarterly &
out 5Annually Sturgeon's Creek 05A Quarterly &
Marina 0
Annually Levy, VA E6 ESE Quarterly &
Annually Bumpass, VA SSE Quarterly &
_______________________Annually End of Route 685 Z71.00 WNW Quarterly & Site Boundary
___Annually Route 700 1.00 WSW Quarterly & Site Boundary Annually "Aspen Hi 0.93 SSE Quarterly & Site Boundary Annually
Orange, 24 22.00 NW Quarterly & Control Annually Bea kXCoo,*g Towe N-1/33 0.06 N
Quarterly On-Site 8&
dp t eek N-2/34 2.04 N
Quarterly P,ý41 Lot "C" NNE-3/35 0.24 NNE Quarterly On-Site Good Hope Church NNE-4/36 3.77 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" T-142 285 E
Quarterly Island Dike ESE-11/43 0.12 ESE Quarterly Oin-Site
(
Rout 622 E_3._.- 1 2/44t 4I./0U hshP_
tQuarterly
DOMINION VPAP-2103N REVISION 16 PAGE 73 OF 86 ATTACHMENT 10 (Page 2 of 4)
-Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance ct ollection 1 Media No.
I (Miles) Direc t Frequency Remarks Environmental TLDs Biology Lab SE-13/45 0.64 SE Quarterly On-Site Route 701 SE-14/46 5.88 SE ut (Dam Entrance)
E "Aspen Hills" SSE-15/47 0.93 S
rB udr Elk Creek SSE-16/48 2.33 r
/
NAPS Access Road S-17/49 0.47 uarterly On-Site Elk Creek Church S-18/50 NQuarterly NAPS Access Road SSW-19/51
.4 Quarterly On-Site Route 618 SSW-20 0/-ý SSW Quarterly 500KV Tower SW-2 53 SW Quarterly On-Site Route 700
/":
.96 SW Quarterly NAPS Radio Tower 0.38 WSW Quarterly On-Site Route 700
-24/56 1.00 WSW Quarterly Boidte dJ,/
/Y2 I
Boundary South Gate
-of
-25/57 0.32 W
Quarterly On-Site S witchy ardlý
,\\<\\14 Route 6&
N1 W-26/58 1.55 W
Quarterly Site Endf Ro 6"
WNW-27/59 1.00 WNW Quarterly Boundary
\\\\ pI WNW-28/60 1.40 WNW Quarterly L
ea North NW-29/61 0.45 NW Quarterly On-Site L'aZ;nna Campground NW-30/62 2.54 NW Quarterly
1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-Site Route 208 NNW-32/64 2.21 NNW Quarterly Bumpass Post Office C-1/2 7.30 SSE Quarterly Orange, VA C-3/4 22.00 NW Quarterly Control Mineral, VA C-5/6 7.10 WSW Quarterly
(
Louisa, VA C-7/8 11.54 WSW Quarterly Control
DOMINION VPAP-2103N REVISION 16 PAGE 74 OF 86 ATTACHMENT 10 (Page 3 of 4)
Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance r
c ollection Remarks Media No.
(Miles) Direction Frequency Airborne NAPS Sewage 01 0.20 NE Weekly On-Site Treatment Plant Particulate Biology Lab 01-A 0.64 SE Wee On-Site and Frederick's Hall 02 5.30 SSW ly Radioiodine Mineral, VA 03 7.10 WSW
/,e"
)
Wares Crossroads 04 5.10 WNW Route 752 05 4.20 NNE sr(eee Sturgeon's Creek 05A 2.04 kly Marina Levy, VA 06 704.70>*
Weekly Bumpass, VA 07
7.
Weekly End of Route 685 21 Weekly Site Boundary Route 700 22 1
SW Weekly Site Boundary "Aspen Hills" 3
SSE Weekly Site Boundary Orange, VA 4
NW Weekly Control Surtace Water Waste Heat Treatme
[Reference Facility (Second 3.37 SSE Monthly 3.1.31]
Cooling Lagoon),,
North AnnaJ~Sx*
09 (upstream d66*
Bridge 6
/09A 12.9 WNW Monthly Control Bridge)
N°*,A nn e"
11 5.80 SE Monthly (iroundwate N"
(well water)
Lab 01A 0.64 SE Quarterly Aquatic a
eat Treatment Semi-Sediment Facil ity (Second 08 3.37 SSE Annually Sedient Cooling Lagoon)
Anal North Anna River (upstream) Rt 669 09A 12.9 WNW Semi-Control Bridge (Brook's Annually Bridge)
North Anna River 11 5.80 SE Semi-(downstream)
Annually Shoreline Soil Lake Anna 08 3.37 SSE Semi-Annually Soil NAPS Sewage 01 0.20 NE Once per 3 yrs On-Site Treatment Plant
DOMINION VPAP-2103N REVISION 16 PAGE 75 OF 86 ATTACHMENT 10 (Page 4 of 4)
Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media No.
(Miles)
Frequency Noll Fredericks Hall U1_
5.30 SSW Once per 3 yrs (continued)
Mineral, VA 03 7.10 WSW Once per3 rs Wares Crossroads 04 5.10 WNW OnceY
\\
Route 752 05 4.20 NNE Oe 3 yrs Sturgeon's Creek 05A 2.04 N
<I"nc Nr'/\\\\ /p6 Marina Levy, VA 06 4.70 E,5r yrs Bumpass, VA-07 7.30 E
c er 3 yrs End of Route 685 21 1.00,!* WW
!rice per 3 yrs Site Boundary Route 700 22 1.0L
S
,7Once per 3 yrs Site Boundary "Aspen Hills" 23 3,
S Once per 3 yrs Site Boundary Orange, VA 24 E2.
Once per 3 yrs Control Milk Lakeside Dairy 1
5 NW Monthly (Charles Harris)
Waste Heat Treatment (
Z Fish Facility (Second 3.37 SSE Semi-Annually Cooling Lagoon)7,_// /
Lake Orange
\\N,<
16.50 NW Semi-Annually Control Food Products Moody La 4A varies ESE Monthly (Edible if available, broadleaf Route 61 15 varies SE or at harvest vegetationa) 16 varies NW Control Ln 26 varies S
__r__
sp ills" Area 23 varies SSE
a. If edible broa eaf vegetation is unavailable, non-edible vegetation of similar leaf characteristics may be substituted.
DOMINION VPAP-2103N REVISION 16 PAGE 76 OF 86 ATTACHMENT 11 (Page 1 of 2)
Detection Capabilities for Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD)
Airborne Fish Food Sediment Analysis Water Particulate Milk Products (NOTE 2)
(pCi/l) or Gases (wet)
.(pCi/l)
(pCi/kg)
(dry)
(pCi/m3 )
(wet)
(dry)
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 (NOTE 3) 1 0.07 60 Cs-134 15 0.05<<,
15 60 150 Cs-137 18
150 18 80 180 Ba-140 60 60 La-140 15
,15 NOTE 1:
Required de
6 abilities for thermoluminescent dosimeters used for environmental measure ents in Regulatory Guide 4.13.
NOTE 2: Thi'%d ot an that only these nuclides are to be detected and reported. Other peaks th(a ura le and identifiable, together with the above nuclides, shall also be identi e
eid reported.
NOTE 3: LLD for the ground (drinking) water samples. The LLD for the surface (non-drinking) water samples is 10 pCi/l.
DOMINION VPAP-2103N REVISION 16 PAGE 77 OF 86 ATTACHMENT 11 (Page 2 of 2)
Detection Capabilities for Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD) (NOTE 3)
NOTE 1:
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD = *..6 b
(25-1)
E
V
2.22E+06 Y
e Where:
LLD the "a priori" (before the fact) Lowe D
tion as defined above (as microcuries per unit mass or ume))ee ubsection 4.9)
Sb=
the standard deviation of the b gr ind
,ng rate or of the counting rate of a blank sample as a (a
unts per minute, cpm)
E
=
the counting efficie c
nts per disintegration)
V
=
the sample
(
o mass or volume) 2.22E+06 =
the n er di egrations per minute (dpm) per microcurie Y
=ochemical yield (when applicable) x adioactive decay constant for the particular radionuclide At t
elapsed time between sample collection (or end of the sample ollection period) and time of counting (for environmental samples, not
\\Z,*~
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.
DOMINION VPAP-2103N REVISION 16 PAGE 78 OF 86 ATTACHMENT 12 (Page 1 of 1)
Reporting Levels for Radioactivity Concentrations in Environmental Samples Water Airborne Fish Milk Food Products Analysis (pCi/l)
Gases (pCi/i 3) (pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
(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 IO, Zn-65 300 Zr-Nb-95 400 Z;
1-131210,1 1 120
.9 3
1 0 0 Cs-134 30 60 1,000 Cs-137 50 9000 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking wajter
//4"K /
K 2nn
DOMINION VPAP-2103N REVISION 16 PAGE 79 OF 86 ATTACHMENT 13 (Page 1 of 8)
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 valu ere d to perform a dose pathway analysis to determine both the maximum exposed vi I at boundary and member of the public. The X/Q and D/Q values resulting in m
uposures were incorporated into the dose factors in Gaseous Effluent D a
aachment 5) and Critical Organ Dose Factors (Attachment 8).
1.2 Meteorological Data, Parameters, and Metl*
l
",o Onsite meteorological data for the period 19J through December 31, 1981, were used in calculations. These data include i
IXind direction, and differential temperature for the purpose of dete j
quency distributions for those releases characterized as ground level (e..
vent), and those characterized as mixed mode (i.e., process vent). The po sf aecharacterized as ground level were based on AT158.9ft-28.2ft and 28.2 fo d
and the portions characterized as mixed mode were based on AT 158.9ft_-
t wind data.
X/Q's and D/Q's e
culated using the NRC computer code "XOQDOQ - Program for the Meteor ical l
on of Routine Effluent Releases at Nuclear Power Stations,"
Septe**
ode is based upon a straight line airflow model implementing the assum ined in Section C (excluding Cla and Cl b) of Regulatory Guide 1.111, "Methods stimating 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 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.
DOMINION VPAP-2103N REVISION 16 PAGE 80 OF 86 ATTACHMENT 13 (Page 2 of 8)
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 elevae obtained from North Anna Power Station Units 1 and 2, Virginia Electric and m
y Final Safety Analysis Report Table 11C.2-8.
XIQ and D/Q values were calculated for the nearest site ent, milk cow, and vegetable garden by sector for process vent and venl n ven' eleases at distances specified from North Anna Power Station Annual Environ ta ata for 1981. XIQ values were also calculated for the nearest lake shoreline b for e process vent and ventilation vent releases.
According to the definition for sho in EG-0133, "Preparation of Radiological Effluent Technical Specification r
Power Stations," October, 1978, some gaseous releases may fit this categor ri aste gas decay tank releases and containment purges.
However, these releases ar dle ong term for dose calculations as past releases were both random in tim d
an ation as evidenced by reviewing past release reports.
Therefore, the u a
l average concentrations is appropriate according to NUREG-0133.
The X/Q an valQ caculated from 1981 meteorological data are comparable to the values presen the 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/m 3 at a site boundary location 1416 meters SE sector. For process vent releases, the site boundary XIQ value was 1.2E-06 sec/m 3 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.OE-04 sec/m 3 at a location 274 meters NNE sector.
The shoreline X/Q value for process vent was 2.7E-06 sec/m 3 at a location 274 meters NNE sector.
DOMINION VPAP-2103N REVISION 16 PAGE 81 OF 86 ATTACHMENT 13 (Page 3 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis The original pathway analysis indicated that the maximum exposure from 1131, 1133, and from all radionuclides in particulate form with half-lives 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 1.1E-09 per m2 at a location 3250 meters
. For tritium, the X/Q value from ventilation vent releases resulting in the maximu sure r the milk pathway was 7.2E-07 sec/m 3, and 3.9E-07 sec/m 3 for process nt ple a location 3250 meters N sector.
Analysis using 2007 release data indicates that the m limiti critical organ is the child's thyroid. The location is 1593 meters SSE sector r
o t releases, the D/Q is 1.1E-8.
For tritium releases, the X/Q values at this loca N e9
-7 for the process vent and 3.3E-6 for the ventilation vents.
2.0 LIQUID PATHWAY ANALYS 2.1 Purpose
/w as The purpose of the liquid w
an is was to determine the maximum exposed member of the public in unres a
result of radioactive liquid effluent releases. The analysis includes a determin mos i'estrictive liquid pathway, most restrictive age group, and critical organ. Thi--~
s is required for Subsection 6.2.
2.2 Data, P s, a Methodology Initial,
tive liquid effluent release data for the years 1979, 1980, and 1981 were compile o
e North Anna Power Station semi-annual effluent release reports. The data for each year, a ong with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0 133.
DOMINION VPAP-2103N REVISION 16 PAGE 82 OF 86 ATTACHMENT 13 (Page 4 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis 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 d ater were set to one. Transit time calculations were based on average flow rates.
I e" p meters were defaults selected by the LADTAP computer code.
Beginning in 1997, the activity by nuclide released in t is entered into the North Anna Power Station liquid pathway critical o 1calcul1i ons spreadsheet, which calculates the most limiting age group total bod od idii' gan. This Process is repeated annually.
2.3 Results Initially, the fish pathway resulted rg The critical organ each year was the liver, and the adult and teenage ge the same organ dose. However, since the adult total body dose was greate ne total body dose for each year, the adult was selected as the most restrictive a
. B ncling in 1997, the most limiting age group for both total body and critical or is ICU from the spreadsheet for North Anna Power Station liquid pathway critical a
culations.
DOMINION VPAP-2103N REVISION 16 PAGE 83 OF 86 ATTACHMENT 13 (Page 5 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis 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 comniiance with Steps 6.3.1.a. and 6.3.3.a. The analysis also included a determinatio th tical pathway, location of maximum exposed member of the public, and the c aI an the maximum dose due to 1131, 1133, tritium, and for all radionuclides in pa Li 111 o0 th half-lives greater than 8 days for use in demonstrating compliance e
s in Step 6.3.4.a. 1. In greatera addition, the analysis included a determination of the tical y, maximum age group, and sector location of an exposed individual thro the a
on pathway from 1131, 1133, tritium, and particulates with half-lives greate day demonstrate compliance with Step 6.3.1.a.
3.2 Data, Parameters, and Methodoly v.
Annual average XIQ values were cg/'
described in Section 1 of this attachment, for the nearest site boundary in h i
onasector and at other critical locations beyond the site boundary. The largest ue determined to be 9.3E-06 sec/m 3 at site boundary for ventilation vent rele *
1416 meters SE direction, and 1.2E-06 sec/m 3 at site boundary for pr **
releases at a location 1513 meters S direction. The maximum doses to total body and sliaair doses for gamma and beta radiation due to noble gases, would be at the i
und locations. The doses from both release points are summed in calcul on a
ate total maximum dose.
Step 6.3..
ose 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.
DOMINION VPAP-2103N REVISION 16 PAGE 84 OF 86 ATTACHMENT 13 (Page 6 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis The NRC computer code GASPAR, "Evaluation 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 1131, i133, tritium, and particulates for the inhalation pathway were calculated using the 9.3E-06 sec/m 3 site boundary X/Q. Except for the source term data and the X/Q value, computer code default parameters were used. Results forr indicated that the critical age group was the child and the critical organ was th
'd for e inhalation pathway.
The gamma and beta dose factors Kivv, Livv, Mivv, a
,ous Effluent Dose Factors (Attachment 5) were obtained by performin its n of the appropnate dose factors from Table B-i, Regulatory Guide 1
.10s v.
/yr per Ci/m 3 or mrad/yr per Ci/m3, and multiplying by the ventilatio vent nd Q value of 9.3E-06 sec/m 3. The same approach was used in calculating tla}
4 eta dose factors Kipv Lipv Mipv and Nipv in Gaseous Effluent Dose Facto
5) using the process vent site boundary X/Q value of 1.2E-06 sec/m 3.
The inhalation pathway do ct rs v and Pipv in Gaseous Effluent Dose Factors (Attachment 5) were calcu hie following equation:
B un)
DFAi(x/Q) (mrem/yr per Curie/sec)
(29-1) where:/
l K'
of unit conversion, 1E+ 12 pCi/Ci BR the eathing rate of the child age group, 3700 m3/yr, from Table E-5, Regulatory i'de 1. 109, Rev. I 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 X/Q the ventilation vent site boundary XIQ, 9.3E-06 sec/m 3, or the process vent site boundary XIQ, 1.2E-06 sec/m 3, as appropriate
DOMINION VPAP-2103N REVISION 16 PAGE 85 OF 86 ATTACHMENT 13 (Page 7 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis 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 Ann tation Annual Environmental Survey Data for 1981.
It was determined that the member of the public within site n4 xn be using Lake Anna for recreational purposes a maximum of 2232 ho assumed that this member of the public would be located the entire 22 ours a he ake shoreline with the largest annual XrQ of 1OE-04 at a location 22 tor.lThe NRC computer code GASPAR was run to calculate the inhalation do is i
vidual. The GASPAR results were corrected for the fractional year the meta rcwould be using the lake.
Using the NRC computer code G*
an al average X/Q and D/Q values obtained as described in Section 1 of this attmember of the public receiving the largest dose beyond site boundary was e
be located 1432 meters N sector. The critical pathway was vegetation, the maxim apo ge group was the child, and the critical organ was the thyroid.
Pathway analysis dicate that existing pathways, including ground and inhalation, within five s of h nna Power Station, yield Ri dose factors less than those determined for the
.ati erence 3.1.32]
The R iv a RMipv dose factors, except for tritium, in Critical Organ Dose Factors (Attachment 8) were calculated by multiplying the appropriate D/Q value with the following equation:
F
(--0
(
F-UitLF
+
S
-Aith(
Yv(, i+ X w)](DFLi)IclF L
+U fe I (29-2) where:
K'
=
a constant of unit conversion, 1E+12 pCi/Ci Yv
= vegetable areal density in Kg/mi2
DOMINION VPAP-2103N REVISION 16 PAGE 86 OF 86 ATTACHMENT 13 (Page 8 of 8)
Meteorological, Liquid, and Gaseous Pathway Analysis Uc=
child leafy vegetable consumption rate, 26 Kg/yr Ucs
=
child stored vegetable consumption rate, 520 Kg/yr r
= fraction of deposited activity retained on vegetation, 1.0 for radioiodine, and 0.2 for particulates DFLi = thyroid ingestion dose factor for the ith radionuclide for the i
mrem/pCi, from Table E-13, Regulatory Guide 1. 109, Rev. 1
= decay constant for the ith radionuclide, in sec-1, fro oc r
kw
= decay constant for removal of activity of leaf and I rfa by weathering, 5.73E-07 sec-1 (corresponding to a 14 day h)J54'b*
tf
= time between harvest of leafy vegetation iagaestio) ) 8.60E+4, in seconds th
= time between harvest of stored veget h
in on, 5.18E+6, in seconds fL
=
fraction of annual intake of leafyýt sK n locally, 1.0 (dimensionless) fg
= fraction of annual intake of stolI grown locally, 0.76 (dimensionless)
Parameters used in the above equ re, ed from NUREG-0 133 and Regulatory Guide 1.109, Revision 1 Since the concentration o t*
in etation is based on the airborne concentration rather than the deposition, t c
Dose Factors (Attachment 8)for tritium were calculated by multiplying tl g equation by the appropriate X/Q:
fL Ufg]D Lj)a[0.75(0.5/H)]
(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 Other parameters have been previously defined.
ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01/10 - 12/10)
As required by the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable.
There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2010.
8
ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/10- 12/10)
As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment.
There was no radioactive liquid and/or gaseous effluent monitoring instrumentation out-of-service for more than 30 days during 2010.
9
ATTACHMENT 6 UNPLANNED RELEASES (01/10 - 12/10)
As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.
There were no unplanned releases during 2010 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted area and there were no spills, leaks, or sample results that required voluntary communication under the criteria of the NEI Ground Water Protection Initiative, NEI 07-07. However, a voluntary communication was made under NEI 07-07 due to sample results from one ground water well, Piezometer Well #3.
A sample obtained on 10/06/10 from Piezometer Well #3, was reported by the vendor to contain 1.65E4 +/-
1.94E3 pCi/L of H-3. Re-analysis of the sample, producing results of 1.89E4 +/- 2.34E3 pCi/L of H-3, confirmed the original result. No other licensed material was detected in this well or any other well. Al.though these results were not high enough to require voluntary communication under NEI 07-07 for ground water results, a voluntary communication was made in accordance with NEI 07-07 and plant procedures.
10
ATTACHMENT 7
LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/10 - 12/10)
Gaseous Effluents:
Required L.L.D.
Typical L.L.D.
Radioisotope aCi/mL i+/-Ci/mL Krypton - 87 1.OOE-4 2.50E-8 7.50E-8 Krypton - 88 1.OOE-4 1.50E-7 4.60E-7 Xenon - 133 1.00E-4 4.90E-8 9.90E-8 Xenon - 133m 1.00E-4 1.10E-7 3.80E-7 Xenon - 135 1.00E-4 4.30E-8 7.60E-8 Xenon - 135m 1.OOE-4 2.20E-7 3.90E-7 Xenon - 138 1.OOE-4 2.80E-7 7.1OE-7 Iodine-131 1.OOE-12 5.40E-14 1.30E-1 Iodine-133 1.OOE-10 3.80E-13 2.50E-1 Manqanese - 54 1.OOE-11 6.80E-14 8.1OE-1 3
1 4
Cobalt - 58 Iron - 59 Cobalt - 60 Zinc - 65 Strontium - 89 Strontium - 90 Molybdenum - 99 Cesium - 134 Cesium - 137 Cerium - 141 Cerium - 144 Gross Alpha Tritium 1.OOE-1 1 1.OOE-1 1 1.O0E-11 1.00E-11 1.OOE-1 1 1.00E-11 1.00E-1 1 1.OOE-1 1 1.OOE-1 1 1.OOE-1 1 1.OOE-1 1 1.00E-11 1.00E-6 11 5.30E-14 8.20E-14 5.20E-14 7.10E-14 1.00E-14 3.OOE-15 3.50E-1 3 9.60E-1 5 5.20E-14 7.50E-14 3.OOE-13 7.20E-15 4.10E-09 8.80E-14 4.40E-13 2.40E-13 5.20E-13 2.30E-14 6.OOE-12 1.30E-12 3.30E-14 8.10E-14 2.80E-13 8.90E-13 1.10E-14 8.80E-09
ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01110 - 12/10)
Liquid Effluents:
Radioisotope Krypton - 87 Krypton - 88 Xenoh - 133 Xenon - 133m Xenon - 135 Xenon - 135m Xenon - 138 Iodine - 131 Required L.L.D.
UCi/mL 1.OOE-5 1.OOE-5 1.OOE-5 1.OOE-5 1.OOE-5 1.OOE-5 1.OOE-5 1.00E-6 5.OOE-7 1.OOE-6 5.OOE-7 5.OOE-7 iz nAA1 7
Typical L.L.D.
uCi/mL 3.60E-8 6.80E-8 6.OOE-8 9.10E-8 7.20E-9 4.40E-8 8.40E-8 2.50E-8 3.30E-8 1.90E-7 2.20E-8 3.90E-8 A 1rl)
Q 1.70E-7 3.1OE-7 1.40E-7 3.20E-7 5.20E-8 4.60E-7 1.OOE-6 7.70E-8 6.1OE-8 8.60E-7 2.1OE-7 7.20E-8 0 r~InC 0 Manganese - 54 Iron - 55 Cobalt - 58 Iron - 59 f~,
k I
r f/'t Zinc - 65 5.OOE-7 3.10E-8 6.70E-8 Strontium - 89 5.OOE-8 2.20E-8 4.20E-8 Strontium - 90 5.OOE-8 1.40E-8 4.60E-8 Molybdenum - 99 5.OOE-7 5.60E-8 1.80E-7 Cesium - 134 5.OOE-7 9.40E-8 4.50E-7 Cesium - 137 5.OOE-7 3.70E-8 8.80E-8 Cerium - 141 5.OOE-7 7.10E-8 2.50E-7 Cerium - 144 5.OOE-7 1.30E-7 5.OOE-7 Gross Alpha 1.OOE-7 2.90E-8 7.60E-8 Tritium 1.OOE-5 2.70E-6 4.30E-6 12
ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01110 - 12/10)
The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water. It complies with the requirements of NEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials.
Samples are obtained from monitoring wells installed outside the restricted area on a routine basis and analyzed by Teledyne Brown Engineering Laboratories. Additional samples are obtained from wells located inside the restricted area and analyzed by Teledyne Brown. Samples are obtained from sumps and yard drains on a routine basis and analyzed onsite. Finally, samples may be obtained more frequently than routine. These samples may be analyzed on-site or by a vendor such as Teledyne Brown. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments1 1 & 12 to VPAP-2103N, which is attached to this document.
On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2010. All results are report in pCi/L. An "N/A" indicates a sample analysis was not performed for that sample. An "ND" indicates an analysis was performed but the result was less than the Minimum Detectable Activity, MDA, and the required LLD. If a result is greater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, due to the analysis software or interferences from naturally occurring radioactivity. In these cases, instead of the value, an explanatory footnote is provided.
13
A1 ATTACHMENT 8
RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/10 - 12/10)
Sample Date Sample H-3 Particulates 1-131 Sr-89/90 Fe-55 Ni-63 Alpha Pu-241 Media TRU Subsurface Drain Header 02/09/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Intake Structure 02/09/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall U-2 Intake Structure 02/09/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall Discharge Canal Outfall 02/09/10 Water 2720 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 03/04/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 03/04/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump East 03/04/10 Water 1630 N/A N/A N/A N/A N/A N/A N/A (inside)
U-2 Mat Sump South 03/04/10 Water ND N/A N/A N/A N/A N/A N/A N/A (Outside)
U-1 ABGWMS 03/04/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 03/04/10 Water ND N/A N/A N/A N/A N/A N/A N/A BTW #1 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #2 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #4 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #1 04/22/10 Water Insufficient volume to sample TTW #2 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #3 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #4 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A TT-W #5 04/22/10 Water ND ND ND N/A N/A N/A N/A N/A PZ #1 04/22/10 Water ND ND ND ND ND N/A N/A N/A PZ #2 04/22/10 Water ND ND ND ND ND N/A N/A N/A
7330, PZ #3(1) 04/22/10 Water
4690, ND ND ND ND ND N/A N/A 4710 Subsurface Drain Header 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Intake Structure 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall U-2 Intake Structure 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall Discharge Canal Outfall 05/15/10 Water 2808 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump East 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A (Inside)
U-2 Mat Sump South 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A (Outside)
U-1 ABGWMS 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 05/15/10 Water ND N/A N/A N/A N/A N/A N/A N/A ISFSI Well #1 06/11/10 Water ND ND ND ND N/A N/A N/A N/A ISFSI Well #4 06/11/10 Water ND ND ND ND N/A N/A N/A N/A BTW #1 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A BTVV #2 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #4 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #1 06/26/10 Water Insufficient volume to sample TTW #2(2) 06/26/10 Water ND ND ND(2 )
N/A N/A N/A N/A N/A TTW #3 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A (1) Original result was 7330 pCi/L. Re-analysis of sample produced next two results.
(2) 1-131 considered a false positive, due to interference from ingrowth of naturally-occurring radioactive isotopes. Sample counts activity increased with multiple delayed counts. This indicates the activity is not due to 1-131.
14
~14 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/10 - 12/10)
Sample Date Sample H-3 Particulates 1-131 Sr-89/90 Fe-55 Ni-63 Alpha Pu-241 TTW_#406/26/10 WMedia ND ND ND N/A N
TRU N/A TTW #4 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #5 06/26/10 Water ND ND ND N/A N/A N/A N/A N/A PZ #1 06/20/10 Water ND Insufficient volume for these analyses PZ #2(1) 06/20/10 Water ND ND ND(1)
N/A N/A N/A N/A N/A PZ #3 06/20/10 Water 6350 ND ND N/A N/A N/A N/A N/A PZ#3(2 )
07/18/2010 Water
7350, N/A N/A N/A N/A N/A N/A N/A 7680 U-1 Intake Structure 08/11/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall U-2 Intake Structure 08/11/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall Discharge Canal Outfall 08/11/10 Water 2280 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 08/26/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 08/26/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump East 08/26/10 Water 1870 N/A N/A N/A N/A N/A N/A N/A (Inside)
U-2 Mat Sump South 08/26/10 Water ND N/A N/A N/A N/A N/A N/A N/A (Outside)
U-1 ABGWMS 08/26/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 08/26/10 Water ND N/A N/A N/A N/A N/A N/A N/A PZ #1 09/06/10 Water ND Insufficient volume for these analyses PZ #2 09/06/10 Water ND Insufficient volume for these analyses PZ #3 09/06/10 Water 3860 ND ND N/A N/A N/A N/A N/A BTW #1 09/11/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #2(3) 09/11/10 Water ND ND ND(3)
N/A N/A N/A N/A N/A BTW #4(')
09/11/10 Water ND ND ND(3)
N/A N/A N/A N/A N/A TTW #1 09/11/10 Water Insufficient volume to sample TTW #2(3) 09/11/10 Water ND ND ND(3)
N/A N/A N/A N/A N/A TTW #3 09/11/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #4(3) 09/11/10 Water ND ND ND(3)
N/A N/A N/A N/A N/A TTW #50) 09/11/10 Water ND ND ND(3)
N/A N/A N/A N/A N/A U-1 ABGWMS 10/01/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 10/01/10 Water ND N/A N/A N/A N/A N/A N/A' N/A PZ #3(2) 10/06/10 Water
16500, N/A N/A N/A N/A N/A N/A N/A 18900 PZ #3 (Vendor) 10/18/10 Water 3660 ND ND ND ND ND ND ND PZ #3(2) (In-house) 10/18/10 Water 4430 N/A N/A N/A N/A N/A N/A N/A PZ #3 (Vendor) 10/30/10 Water 5030 N/A N/A N/A N/A N/A N/A N/A PZ #3(2) (In-house) 10/30/10 Water 4270 N/A N/A N/A N/A N/A N/A N/A Subsurface Drain Header 11/02/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Intake Structure 11/02/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall U-2 Intake Structure 11/02/10 Water ND N/A N/A N/A N/A N/A N/A N/A Outfall Discharge Canal Outfall 11/02/10 Water 4270 N/A N/A N/A N/A N/A N/A N/A PZ #3 (Vendor) 11/05/10 Water 5390 N/A N/A N/A N/A N/A N/A N/A (1) Only about 809 mL available for analysis due to low water level in well. 1-131 (LL) not able to be performed. 1-131 MDA was 9.34 pCi/L, which is less than the non-drinking water LLD of Attachment 11 to VPAP-2103N.
(2) PZ Wells #1 & 2 were sampled in conjunction with PZ #3. However, there was insufficient volume to obtain a sample in either well (3) 1-131 considered a false positive, due to interference from ingrowth of naturally-occurring radioactive isotopes. Sample counts activity increased with multiple delayed counts. This indicates the activity is not due to 1-131.
15
ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/10 - 12/10)
Date Sample H-3 Particulates 1-131 Sr-89/90 Fe-55 Ni-63 Alpha Pu-241 Sample Media TRU PZ #3(1) (In-house) 11/05/10 Water 4390 N/A N/A N/A N/A N/A N/A N/A PZ #3(1) (In-house) 11/13/10 Water 4360 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 11/17/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 11/17/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump East 11/17/10 Water 1290 N/A N/A N/A N/A N/A N/A N/A (Inside)
U-2 Mat Sump South 11/17/10 Water ND N/A N/A N/A N/A N/A N/A N/A (Outside)
I U-1 ABGWMS 11/17/10 Water ND N/A N/A N/A N/A N/A N/A N/A U-2 ABGWMS 11/17/10 Water ND N/A N/A N/A N/A N/A N/A N/A PZ #3(1) (In-house) 11/20/10 Water 5950 N/A N/A N/A N/A N/A N/A N/A PZ #3(l) (In-house) 11/26/10 Water 5100 N/A N/A N/A N/A N/A N/A N/A PZ #3(1) (In-house) 12/03/10 Water 3900 N/A N/A N/A N/A N/A N/A N/A PZ #1 12/10/10 Water Insufficient volume to sample PZ #2 12/10/10 Water Insufficient volume to sample PZ #3 (Vendor) 12/10/10 Water 3110 ND ND N/A N/A N/A N/A N/A PZ #3 (In-house) 12/10/10 Water 1710 N/A N/A N/A N/A N/A N/A N/A BTW #1 12/11/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #2 12/11/10 Water ND ND ND N/A N/A N/A N/A N/A BTW #4 12/11/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #1 12/11/10 Water Insufficient volume to sample TTW #2(2) 12/11/10 Water ND ND ND(2)
N/A N/A N/A N/A N/A TTW #3 12/11/10 Water ND ND ND N/A N/A N/A N/A N/A TTW #4 12/11/10 Water ND ND ND N/A N/A N/A N/A N/A TT-W #5(2) 12/11/10 Water ND ND ND(2)
N/A N/A N/A N/A N/A PZ #3(1) (In-house) 12/17/10 Water 2790 N/A N/A N/A N/A N/A N/A N/A PZ #3(1) (In-house) 12/21/10 Water 3350 N/A N/A N/A N/A N/A N/A N/A PZ #3(1) (In-house) 12/30/10 Water 1550 N/A N/A N/A N/A N/A N/A N/A (1) PZ Wells #1 & 2 were sampled in conjunction with PZ #3 on a monthly and weekly basis. However, there was insufficient volume to obtain a sample in either well.
(2) 1-131 considered a false positive, due to interference from ingrowth of naturally-occurring radioactive isotopes. Sample counts activity increased with multiple delayed counts. This indicates the activity is not due to 1-131.
16
ATTACHMENT 9 CARBON-14 CALCULATIONS (01/10 - 12/10)
Carbon-14,C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere.
Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Due to its long half-life, 5730 years, a significant portion of the 0-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether 0-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution radionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Rev. 2. Because the dose contribution of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 in liquid effluents is not required by Ref. Reg. Guide 1.21, Rev. 2.
The quantity of gaseous 0-14 released to the environment can be estimated by use of a 0-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation of 0-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 23 Ci of 0-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 17 Ci of C-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter.
Most 0-14 species initially produced in a PWR are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment, a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic. North Anna used a value of 70% organic and 30% 002 in its calculations.
Public dose estimates from airborne 0-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated 0-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 9.68E-2 mrem from the inhalation pathway, or 6.45E-3%TS and 1.16 mrem from the ingestion pathway or 3.87% of the 1 OCFR50, Appendix I, ALARA design objective of 15 mrem/yr per unit. In both cases the critical organ was determined to be the child's bone.
17

ML11123A214

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