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Independent Spent Fuel Storage Installation (Isfsi), Annual Radioactive Effluent Release Report
	ML15105A080
Person / Time
Site:	North Anna
Issue date:	04/10/2015
From:	Gerald Bichof; Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	15-178
	Download: ML15105A080 (137)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 10, 2015 United States Nuclear Regulatory Commission Serial No.15-178 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 2014 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 Page Kemp at (540) 894-2295.

Very truly yours, Gerald T. Bischof 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 k (H'ýSS

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2014 TO DECEMBER 31, 2014)

PREPARED BY:_________________

Supe~rvisor Radiological Analysis and Instrumentation REVIEWED BY:_

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2014 TO DECEMBER 31, 2014 INDEX Subject Section No.

1 2

3 4

Page 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 M anual (O D C M )........................................

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

Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrum e ntation........................................

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

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

Results of Ground Water Protection Initiative S am ple A nalysis.....................................

Carbon-14 Calculations.............................

Annual Effluent Release Report Log............

1-2 2

3-4 4

5 6

7 8

9 10 11 -12 13 - 24 25 - 26 27 Miscellaneous

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 2014 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 Regulatory Guide 1.21 during the period January 1 through December 31, 2014, 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 2014.

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. Also there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6.

10 CFR 50, Appendix I dose calculations were performed on the 2014 effluent release data 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 3.94E-1 mrem, which is 6.57% of the dose limit and the critical organ dose due to liquid effluents was 3.95E-1 mrem, which is 1.98% of the dose limit.

b.

The air dose due to noble gases was 3.34E-3 mrad gamma, which is 1.67E-2% of the annual gamma dose limit, and 2.04E-3 mrad beta, which is 5.10E-3% 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 1.46 mrem, which is 4.87% of the annual dose limit. The bases of C-14 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 6.87E-3 mrem, which is 2.29E-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 were two revisions 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 1st 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.

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 and 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-14 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 piCi/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 and iodine-133, 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 and iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days 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 performed to identify if new location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM.

There were no new sampling locations added. There were two (2) changes made to the land use census in 2014. The nearest garden in the WSW sector changed from 2.36 miles to 2.22 miles.

The nearest garden in the WNW sector moved from 2.59 miles to 2.67 miles.

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.

All milk samples were collected as required. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through April and from November through 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 (01/14 - 12/14)

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 JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/14 - 12/14)

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

A. Fission and Activiation Gases

1. Total Release Curies 1.18E+00 5.37E-01 1.80E+1

2. Average Release Rate For Period jiCi/sec 1.52E-01 6.83E-02 B.

Iodines:

1. Total Iodine-131 Release Curies O.OOE+00 O.OOE+00 2.80E+1

2. Average Release Rate For Period gCi/sec O.OOE+00 O.OOE+00 C.

Particulate (T112 > 8 days):

1. Total Particulate (T1/2> 8 days) Release Curies O.OOE+00 O.OOE+00 2.80E+1

2. Average Release Rate For Period piCi/sec O.OOE+00 O.OOE+00

3. Gross Alpha Radioactivity Release Curies 1.23E-07 3.55E-07 D. Tritium:

1. Total Release Curies 1.93E+00 1.56E+00 3.10E+1

2. Average Release Rate For Period jiCi/sec 2.48E-01 1.98E-01 E. Carbon-14

1. Total Release Curies 5.10E+00 4.13E+00

2. Average Release Rate For Period piCi/sec 6.49E-01 5.25E-01 F.

Percentage Of Technical Specification Limits

1. Total Body Dose Rate 2.06E-03 1.98E-04

2. Skin Dose Rate 5.00E-04 710E-05

3. Critical Organ Dose Rate (with C-14) 1.25E-02 7,33E-03 Critical Organ Dose Rate (without C-14) 3.35E-05 1 00E-04

TABLE JA NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01114 - 12/14)

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

A. Fission and Activiation Gases

1. Total Release Curies 4.OOE+00 9.67E-01 1.80E+1

2. Average Release Rate For Period pCi/sec 5.03E-01 1.22E-01 B.

Iodines:

1. Total Iodine-131 Release Curies 1.12E-04 3.19E-07 2.80E+1

2. Average Release Rate For Period pCi/sec 1.41E-05 4.01E-08 C.

Particulate (T1l2 > 8 days):

1. Total Particulate (T1/2 > 8 days) Release Curies 3.26E-05 4.42E-06 2.80E+1

2. Average Release Rate For Period pCi/sec 4.10E-06 5.56E-07

3. Gross Alpha Radioactivity Release Curies 3.91 E-07 1.54E-07 D.

Tritium:

1. Total Release Curies 6.32E+00 2.11E+00 3.10E+1

2. Average Release Rate For Period pCi/sec 7.95E-01 2.65E-01 F. Carbon-14

1. Total Release Curies 1.73E+01 4.19E+00

2. Average Release Rate For Period pCi/sec 2.18E+00 5.27E-01 F.

Percentage Of Technical Specification Limits

1. Total Body Dose Rate 8.55E-05 2.15E-04

2. Skin Dose Rate 6.44E-05 5.80E-05

3. Critical Organ Dose Rate (with C-14) 1.43E-02 2.97E-03 Critical Organ Dose Rate (without C-14) 5.98E-04 9.40E-05

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01114 - 12114)

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 1.93E-01 N/D Krypton - 85m Ci N/D N/D NID 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 NID N/D N/D Xenon - 133 Ci N/D 4.17E-01 N/D N/D Xenon - 133m Ci NID NID N/D NID Xenon - 135 Ci N/D N/D N/D 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)

NID NID N/D N/D Argon - 41 Ci 5.53E-03 N/D N/D N/D Total For Period Ci 5.53E-03 4.17E-01 1.93E-01 N/D lodines:

Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D NID N/D Iodine - 133 Ci NID 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 N/D N/D 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 (01/14 - 12/14)

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 N/D N/D N/D Cerium-144 Ci N/D N/D N/D N/D Ag-1i0m Ci N/D N/D N/D N/D Total for Period (T1/2 > B days)

Ci N/D N/D NID N/D Total for Period (T11/2 < 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 1.79E+00 4.93E-01 8.38E-05 N/D CARBON-14 Ci 2.39E-02 1.80E+00 8.35E-01 0.OOE+00

TABLE lB NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/14 - 12/14)

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 1.31E+00 5.81E-O1 Krypton - 85m Ci N/D N/D 1.85E-04 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 - 131 m Ci N/D N/D N/D N/D Xenon - 133 Ci 2.53E-01 2.27E-02 1.67E+00 2.19E-01 Xenon - 133m Ci N/D N/D 2.28E-02 N/D Xenon - 135 Ci N/D N/D 2.77E-02 1.40E-02 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 N/D N/D N/D N/D Total For Period Ci 2.53E-01 2.27E-02 3.03E+00 8.14E-01 lodines:

Iodine - 131 Ci 7.66E-07 2.66E-08 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 Total For Period Ci 7.66E-07 2.66E-08 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 Silver-1 10m Ci 6.79E-09 1.19E-08 N/D N/D Cesium - 134 Ci N/D N/D N/D N/D Cesium - 137 Ci N/D N/D N/D N/D

TABLE 1 B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01114 - 12/14)

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 Total for Pedod (T1/2 > 8 days)

Ci 6.79E-09 1.19E-08 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 1.64E+00 1.20E+00 4.53E-03 8.51E-04 CARBON-14 Ci 1.09E+00 9.82E-02 1.31E+01 3.52E+00

TABLE IC NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/14-12/14)

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 N/D 4.12E-01 Krypton - 85m Ci N/D N/D 8.17E-04 1.06E-03 Krypton - 87 Ci N/D NID N/D 8.76E-04 Krypton - 88 Ci N/D N/D 1.30E-03 1.66E-03 Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 7,40E-03 2.23E-02 Xenon - 133m Ci N/D N/D N/D 4.43E-04 Xenon - 135 Ci N/D N/D 8,01 E-03 1.09E-02 Xenon - 135m Ci N/D N/D N/D 2.86E-04 Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D 1.18E-03 Other (Specify)

Argon - 41 Ci N/D N/D 9.63E-01 8.62E-02 Total For Period Ci N/D N/D 9.81E-01 5.37E-01 Iodines:

Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D Nil 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 N/D N/D 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

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/14 - 12114)

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

(cont.)

Cesium - 137 Ci N/D N/D N/D N/D 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 Niobium-95 Ci N/D N/D N/D N/D Zirconium-95 Ci N/D N/D N/D N/D Rubidium-88 (T1/2 < 8 days)

Ci N/D N/D N/D N/D Cerium-143 (T1/2 < 8 days)

Ci N/D N/D N/D N/D Chromium-51 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 (T1/2 < 8 days)

Ci N/D N/D N/D N/D Total For Period Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 GROSS ALPHA:

Ci 1.23E-07 3.55E-07 N/D N/D TRITIUM:

Ci N/D 6.46E-01 1.42E-01 4.19E-01 CARBON-14 Ci N/D N/D 4.24E +00 2.32E +00

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01114 - 12/14)

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 5.72E-01 N/D Krypton - 85m Ci N/D N/D 1.17E-04 1.35E-03 Krypton - 87 Ci N/D N/D 5.01 E-05 1.12E-03 Krypton - 88 Ci N/D N/D 1.02E-04 2.30E-03 Xenon - 131m Ci N/D N/D 1.60E-03 N/D Xenon - 133 Ci N/D N/D 9.86E-02 1.54E-02 Xenon - 133m Ci N/D N/D 2.06E-03 5.41E-04 Xenon - 135 Ci N/D N/D 9.84E-03 1.43E-02 Xenon - 135m Ci N/D N/D 8.16E-05 1.64E-03 Xenon-537 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 2.61E-02 9.40E-02 Total For Period Ci N/D N/D 7.11E-01 1.31 E-01 Iodlines:

Iodine - 131 Ci 1.05E-04 N/D 5.80E-06 2-92E-07 Iodine - 132 Ci 9.97E-05 N/D 4.24E-04 N/D Iodine - 133 Ci 8.81 E-05 N/D 1.16E-06 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 2.93E-04 N/D 4.31 E-04 2.92E-07 Particulates:

Manganese - 54 Ci N/D N/D 3.34E-07 N/D Cobalt - 58 Ci N/D N/D 6.26E-06 N/D Iron - 59 Ci NID N/D N/D N/D Cobalt - 60 Ci N/D 3.28E-06 1.95E-05 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 ICesium - 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 (01/14 - 12/14)

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

(cont.)

Cesium - 137 Ci N/D 7.87E-07 6.59E-07 N/D 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 (T1/2 > 8 days)

Ci N/D N/D N/D N/D Zirconium-95 (T1/2 > 8days)

Ci N/D N/D 6.56E-07 N/D Niobium-95(T1/2 > 8days)

Ci N/D N/D 1.87E-06 3.45E-07 Ru-103 (Tl/2 > 8 days)

Ci 3.33E-06 N/D N/D N/D Total for Period (Tl/2 > 8 days)

Ci 3.33E-06 4.07E-06 2.93E-05 3.45E-07 Total for Period (Tl/2 < 8 days)

Ci N/D N/D N/D N/D Total For Period Ci 3.33E-06 4.07E-06 2.93E-05 3.45E-07 GROSS ALPHA:

Ci 3.91E-07 1.54E-07 N/D N/D TRITIUM:

Ci 2.62E+00 N/D 2.06E+00 9.09E-01 CARBON-14 Ci N/D N/D 3.08E+00 5.67E-01

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01114 -

12114)

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 2.57E-03 6.04E-03 2.OOE+01

2. Average diluted concentration during the period.

pCi/ml 4.OOE-12 7.OOE-12

3. Percent of applicable limit (.S.)

5.55E-06 1.39E-05 B.

Tritium:

1. Total release activity.

Curies 1.95E+01 1.72E+01 2.O0E+01

2. Average diluted concentration during the period.

p.Ci/ml 3.05E-08 1.99E-08

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

3.05E-04 1.99E-04 C. Dissolved and Entrained Gases:

1. Total release activity.

Curies O.00E+00 O.0OE+00 2.OOE+01

2. Average diluted concentration during the period.

ý,Ci/ml O.0OE+00 O.0OE+00

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

O.OOE+00 O.OOE+00 D. Gross Alpha Radioactivity:

1. Total release activity.

Curies O.OOE+00 0.OOE+00 2.OOE+01 E.

Volume of waste released: (prior to dilution).

Liters 8.21E+07 1.12E+08 3.O0E+00 F. Total volume of dilution water used during the period.

Liters 6.41E+11 8.63E+11 3.OOE+0O

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01114 - 12/14)

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 5.19E-04 5.49E-02 2.OOE+01

2. Average diluted concentration during the period.

1iCi/ml 6.59E-13 1.01E-10

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

4.86E-07 7.18E-05 B.

Tritium:

1. Total release activity.

Curies 8.94E+02 1.84E+02 2.OOE+01

2. Average diluted concentration during the period.

ýICi/ml 1.14E-06 3.38E-07

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

1.14E-02 3.38E-03 C.

Dissolved and Entrained Gases:

1. Total release activity.

Curies O.OOE+00 O.OOE+00 2.00E+01

2. Average diluted concentration during the period.

ýLCi/ml O.OOE+00 O.OOE+00

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

O.OOE+00 O.OOE+00 D. Gross Alpha Radioactivity:

1. Total release activity.

Curies 0.OOE+00 O.OOE+00 2.OOE+01 E.

Volume of waste released: (prior to dilution).

Liters 1.13E+08 1.11E+08 3.O0E+00 F. Total volume of dilution water used during the period.

Liters 7.87E+1 1 5.44E+1 1 3.OOE+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01114 - 12114)

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 N/D N/D N/A N/A Iron - 59 Ci 2.06E-05 N/D N/A N/A Cobalt - 58 Ci 1.71 E-03 3.82E-04 N/A N/A Cobalt - 60 Ci 7.86E-04 1.60E-03 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 4.54E-05 N/D N/A N/A Ruthenium-106 Ci N/D N/D N/A N/A Silver - 11Om Ci N/D 3.53E-03 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 N/D N/D N/A N/A Cesium - 137 Ci 4.97E-06 N/D 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 Zirconium - 97 Ci N/D 5.35E-04 N/D N/A Niickel - 63 (T1/2 > 8 days)

Ci N/D N/ID N/A N/A Antimony-1 25 Ci N/D N/D N/A N/A Total for Period Ci 2.57E-03 6.05E-03 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01114 - 12114)

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

Xenon - 133 Ci N/D N/D N/A N/A Xenon - 133m Ci N/D N/D N/A N/A Xenon - 135 Ci N/D N/D N/A N/A Xenon - 135m Ci N/D N/D N/A N/A Other (Specify)

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

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

Ci N/D N/D N/A N/A Total for Period Ci N/D N/D N/A N/A Titium Ci 1.95E+01 1.72E+01 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/14-12/14)

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 N/D 3.17E-04 N/A N/A Iron - 59 Ci N/D 1.17E-04 N/A N/A Cobalt - 58 Ci 4.72E-04 4.84E-02 N/A N/A Cobalt - 60 Ci 4.10E-05 4.20E-03 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 9.98E-05 N/A N/A Zirconium - 95 Ci N/D 3.23E-05 N/A N/A Silver - 110m Ci 5.88E-06 1.58E-04 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 N/D N/D N/A N/A Cesium - 137 Ci N/D N/D 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 Chromium-51 Ci N/D 1.41 E-03 N/A N/A Nickel - 63 (T1/2 > 8 days)

Ci N/D 1.80E-04 N/A N/A Antimony-122 (TI/2 < 8 days)

Ci N/D N/D N/A N/A Antimony-1 25 (T1/2 > 8 days)

Ci N/D N/D N/A N/A Antimony-124 (T1/2 > 8 days)

Ci N/D 2.09E-04 N/A N/A Tellurium-125m (T1/2 > 8 days)

Ci N/D Total for Period Ci 5.19E-04 5.51E-02 N/A N/A

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01114 - 12/14)

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 N/D N/D N/A N/A Xenon - 133m Ci N/D N/D N/A N/A Xenon - 135 Ci N/D N/D N/A N/A Xenon-135m Ci N/D N/D N/A N/A Other (Specify)

Argon - 41 (Tl/2 < 8 days)

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

Ci N/D N/D N/A N/A Total for Period Ci N/D N/D N/A N/A Tritium Ci 8.94E+02 1.84E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

TABLE 3

NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-14 THROUGH 12-31-14 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 1.27E+01 2.50E+01 evaporator bottoms, etc.,

Ci 1.98E+02 2.50E+01

b.

Dry compressible waste, contaminated m3 2.59E+02 2.50E+01 equipment, etc.,

Ci 3.28E+00 2.50E+01

c.

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

Ci 0.OOE+00 2.50E+01

d.

Other (describe)

Used oil/Blast medialSewagelGravel m3 9.71E+01 2.50E+01 Dessicant/Soil/Construction debris Ci 9.70E-02 2.50E+01 Animal Carcasses

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

(%)

(Ci)

Percent Error (%)

a.

Ni-63 3.62E+01 7.18E+01 2.60E+01 Cs-1 37 2.50E+01 4.96E+01 2.50E+01 Co-60 2.25E+01 4.46E+Oi 2.50E+01 Fe-55 5.83E+00 1.16E+01 2.50E+01 Cs-134 5.35E+00 1.06E+01 2.50E+01 Mn-54 1.94E+00 3.85E+00 2.50E+01 Co-58 8.48E-01 1.68E+00 2.50E+01 C-14 4.67E-01 9.27E-01 2.50E+01 Ni-59 4.45E-01 8.83E-01 2.50E+01 Ag-110m 4.05E-01 8.04E-01 2.50E+01

b.

Co-60 2.61E+01 8.55E-01 2.50E+01 Fe-55 2.06E+01 6.76E-01 2.50E+01 Nb-95 1.15E+01 3.78E-01 2.50E+01 Cs-1 37 1.1 5E+01 3.77E-01 2.50E+0i Zr-95 1.06E+01 3.48E-01 2.60E+01 Ni-63 8.03E+00 2.63E-01 2.50E+01 Cr-51 7.89E+00 2.59E-01 2.50E+01 Co-58 4.08E+00 1.34E-01 2.50E+01 Mn-54 1.23E+00 4.04E-02 2.50E+01 Sb-125 6.86E-01 2.25E-02 2.50E+01 Zn-65 3.65E-01 1.20E-02 2.50E+01

c.

NONE

d.

Fe-55 2.54E+01 2.47E-02 2.50E+01 NI-63 2.51 E+01 2.44E-02 2.50E+01 Co-60 2.10E+01 2.03E-02 2.50E+01 Co-58 31.8E+01 1.14E-02 2.50E+01 Ag-110m 6.99E+00 6.78E-03 2.50E+01 H-3 6.38E+00 6.19E-03 2.60E+01 Nb-95 1.36E+00 1.32E-03 2.50E+01 Zr-95 8.23E-01 7.99E-04 2.50E+01 Cs-1 37 4.43E-01 4.30E-04 2.50E+01 C-14 2.86E-01 2.77E-04 2.50E+01 Cs-1 34 2.08E-01 2.02E-04 2.50E+01 Tc-99 1.97E-01 1.91 E-04 2.50E+01 Sb-125 1.95E-01 1.90E-04 2.50E+01 Co-57 1.84E-01 1.79E-04 2.50E+01 Mn-54 1.55E-01 1.50E-04 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01-01-14 THROUGH 12-31-14 Page 2 of 2

3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3

Truck Clive, UT 2

Truck Erwin, TN 12 Truck Oak Ridge, TN 2

Truck Barnwell, SC B.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0

N/A N/A (2) shipments containing resins were shipped to a licensed waste processor for processing (2) shipments containing resins were shipped to a licensed waste processor for disposal (2) shipments containing mechanical filters were shipped to a licensed waste processor for processing (3) shipments containing mechanical filters were shipped to a licensed waste facility for disposal (6) shipments containing dry compactable waste were shipped to a licensed waste processor for processing (3) shipments containing dry compactable waste were shipped to a licensed waste facility for disposal None (2) shipments containing biological material were shipped to a licensed waste processor for processing (1) shipment containing charcoal was shipped to a licensed waste facility for disposal (6) shipments containing construction debris were shipped to a licensed waste processor for processing (2) shipments containing charcoal were shipped to a licensed waste processor for disposal.

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01114 - 12114)

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 nl.nrt4r O~nmnrta nlh.rtar 4th Minurtr Annual Tnfnl Total Body Dose (mrem) 6.95E-3 6.15E-3 3.16E-1 6.52E-2 3.94E-1 Critical Organ Dose (mrem) 7.06E-3 6.31 E-3 3.16E-1 6.55E-2 3.95E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total

-Noble Gas Gamma Dose (mrad) 2.67E-3 2.60E-4 1.20E-4 2.87E-4 3.34E-3 Noble Gas Beta Dose (mrad) 9.56E-4 3.42E-4 5.72E-4 1.67E-4 2.04E-3 Critical Organ (Child bone)

Dose for 1-131, r-P133, H-3, Particulates with T% > 8 days

'including C-14) (mrem) 5.40E-1 3.40E-1 3.95E-1 1.88E-1 1.46E+0

'ritical Organ

'Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T% > 8 days (excluding C-14) (mrem) 3.26E-4 5.68E-4 6.42E-3 5.62E-4 6.88E-3

,ill 6

A'

ATTACHMENT 3

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/14 - 12/14)

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

There were two revisions to the ODCM during this reporting period. Revision 22 was effective on 01/07/14 and was made due to a change in Rated Thermal Power from 2893 MW to 2940 MW. Revision 23 was effective on 07/10/14 and was made to document the change in location description for environmental sector Thermoluminescent Dosimeters at location WSW-23/55. This change was in description only. Dosimeter location remained unchanged.

7

ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01114 - 12114)

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 2014.

8

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/14 - 12114)

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.

1-LW-RM-111, the Clarifier Effluent Radiation Monitor, was inoperable from 05/13/14 until 09/03/14. Degraded condition of this radiation monitor was discovered during annual calibration in September 2014. A subsequent review of available monitor data showed performance degraded over time to the point where it was considered to be non functional on 05/13/14. Other details as well as actions taken to preclude future loss of functionality for this monitor are included in North Anna Condition Report, CR558708, and the follow up assessments generated from this Condition Report.

9

ATTACHMENT 6

UNPLANNED RELEASES (01/14 - 12114)

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 calendar year 2014 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground Water Protection Initiative, NEI 07-07. Elevated results indicated in Attachment 8 are from the on-going investigation/ mitigation for the voluntary communication made in 2010. The hydrological modeling indicates the horizontal groundwater movement around well #6 is < 1 inch per day. However, RP Supervision decided to include one unplanned gaseous release under the requirement of Offsite Dose Calculation Manual, section 6.7.2.a.3 bullet number 4. This release is described below.

On 03/02/14 a High Alarm was received on Vent Vent A (WA) radiation monitor,1-VG-RM-179 and Vent Vent B (VVB) radiation monitor, 1-VG-RM-180 while Chemistry personnel were attempting to obtain a sample of the Unit 1 Volume Control Tank (VCT) gas space. Per procedure CH-1 1.245, when Chemistry obtains a VCT gas space sample, they first purge the sample line to the Gas Strippers to obtain a representative sample. In this instance, the purge header drain valve, 1-SS-56, was found to be in the open position versus it's normally closed position. This open valve position allowed gas being purged to go directly to the Chemistry Sample Sink hood which is ventilated by VVA instead of following the normal flowpath to the Gas Strippers, leading to an unplanned release. The Chemistry Sample Sink release pathway is normally through WA exclusively. However, since Auxiliary Building Central Exhaust was aligned to pass through the Charcoal filter banks for this release, damper leaks within the iodine filtration system caused a release to and subsequent alarm from both release pathways, WA and WB. Peak total release rate was 3.19E-3 Ci/sec. Maximum Percent Technical Specification, based on total body limit of 500 mrem/yr, was a fraction of the allowable limit and calculated to be 5.10%TS. For further information, see North Anna Condition Report, CR541149 and SAA035754.

10

ATTACHMENT 7

LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/14 - 12/14)

Gaseous Effluents:

Required L.L.D.

Typical L.L.D.

Radioisotope gCi/mL LLCi/mnL Krypton - 87 1.OOE-4 2.50E-8 7.50E-8 Krypton - 88 1.OOE-4 1.OOE-7 4.50E-7 Xenon - 133 1.OOE-4 5.OOE-8 1.OOE-7 Xenon - 133m 1.OOE-4 2.OOE-7 4.OOE-7 Xenon - 135 1.OOE-4 2.OOE-8 5.OOE-8 Xenon - 135m 1.OOE-4 5.OOE-8 2.OOE-7 Xenon - 138 1.OOE-4 1.OOE-7 5.OOE-7 Iodine - 131 1.00E-12 6.OOE-14 1.OOE-13 Iodine - 133 1.OOE-10 1.OOE-14 7.OOE-13 Manganese - 54 1.OOE-11 6.OOE-14 8.OOE-14 Cobalt - 58 1.OOE-11 5.OOE-14 8.OOE-14 Iron - 59 1.OOE-1 1 9.OOE-14 2.OOE-13 Cobalt - 60 1.OOE-11 5.OOE-14 2.OOE-13 Zinc - 65 1.OOE-11 9.OOE-14 3.OOE-13 Strontium - 89 1.OOE-11 3.OOE-14 8.OOE-12 Strontium - 90 1.OOE-11 3.OOE-15 9.OOE-12 Molybdenum - 99 1.OOE-11 7.OOE-14 2.OOE-13 Cesium - 134 1.OOE-1 1 5.OOE-14 1.OOE-13 Cesium - 137 1.OOE-11 5.OOE-14 8.OOE-14 Cerium - 141 1.OOE-11 5.OOE-14 2.OOE-13 Cerium - 144 1.OOE-11 2.OOE-13 5.00E-13 Gross Alpha 1.OOE-11 7.OOE-15 2.OOE-14 Tritium 1.OOE-6 4.OOE-09 9.OOE-09 11

ATTACHMENT 7

LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/14 - 12/14)

Liquid Effluents:

Required L.L.D.

Typical L.L.D.

Radioisotope uXCi/mL UCi/mL Krypton - 87 1.OOE-5 4.OOE-8 1.OOE-7 Krypton - 88 1.OOE-5 1.OOE-7 1.OOE-6 Xenon - 133 1.OOE-5 7.00E-8 1.50E-7 Xenon - 133m 1.OOE-5 9.OOE-8 3.OOE-7 Xenon - 135 1.OOE-5 9.OOE-9 5.OOE-8 Xenon - 135m 1.OOE-5 3.OOE-8 2.OOE-7 Xenon - 138 1.OOE-5 1.OOE-7 1.OOE-6 Iodine - 131 1.OOE-6 1.00E-8 5.OOE-8 Manganese - 54 5.OOE-7 2.00E-8 5.OOE-8 Iron - 55 1.OOE-6 3.OOE-7 8.OOE-7 Cobalt - 58 5.OOE-7 2.OOE-8 6.OOE-8 Iron - 59 5.OOE-7 3.OOE-8 7.OOE-8 Cobalt - 60 5.OOE-7 1.OOE-8 5.50E-8 Zinc - 65 5.OOE-7 3.OOE-8 6.OOE-8 Strontium - 89 5.OOE-8 1.OOE-8 4.OOE-8 Strontium - 90 5.00E-8 5.OOE-9 9.OOE-9 Molybdenum - 99 5.OOE-7 2.00E-8 6.OOE-8 Cesium - 134 5.OOE-7 2.OOE-8 5.OOE-8 Cesium - 137 5.OOE-7 3.OOE-8 6.OOE-8 Cerium - 141 5.OOE-7 3.OOE-8 9.OOE-8 Cerium - 144 5.00E-7 1.OOE-7 5.OOE-7 Gross Alpha 1.OOE-7 2.OOE-8 7.OOE-8 Tritium 1.OOE-5 2.OOE-6 5.00E-6 12

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12114)

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 quarterly 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 quarterly basis and analyzed onsite. Finally, samples may be obtained more frequently than normal, if required. 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 Attachments 11 and 12 to VPAP-2103N.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2014. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. 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

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01114 - 12114) s't Quarter 2014 Sample Date Sample H-31' Gamma-Emitting 1-131" Sr-89I9O('

Fe-55(1 ) Ni-63" Alpha Pu-241 Se Media Particulates'1

1 TRU(1)Iu GWP-6 01/09/14 WATER 47335 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/16/14 WATER 29868 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/23/14 WATER 37643 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/30/14 WATER 57427 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/06/14 WATER 24751 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/14/14 WATER 33795 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/20/14 WATER 39592 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 04/09/14 WATER

< 1352 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Yard Drains 02/05/14 WATER

<1560 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Yard drains 02/05/14 WATER

<1560 N/A N/A N/A N/A N/A N/A N/A Discharge Canal Yard 02/05/14 WATER

<1560 N/A N/A N/A N/A N/A N/A N/A Drains Subsurface drains 02/05/14 WATER

<1560 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/27/14 WATER 60687 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/06/14 WATER 66667 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/11/14 WATER 69509 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 03/11/14 WATER 61700 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/20/14 WATER 56078 N/A N/A N/A N/A N/A N/A N/A GWP-6 2 03/27/14 WATER 46796 ND ND N/A N/A N/A N/A N/A PZ-2 03/20/14 WATER Insufficient volume to sample PZ-1 03/20/14 WATER Insufficient volume to sample GWP-3 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A PZ-3 2 03/27/14 WATER 4130 ND ND N/A N/A N/A N/A N/A GWP-4 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-5A 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-7 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-8 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-9 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-13 04/03/14 WATER

<1276 N/A N/A N/A N/A N/A N/A N/A GWP-14 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-15 04/03/14 WATER

<1276 N/A N/A N/A N/A N/A N/A N/A GWP-16 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A GWP-17 04/03/14 WATER

<1272 N/A N/A N/A N/A N/A N/A N/A BTW-1l 2) 04/01/14 WATER

<1520 N/A N/A N/A N/A N/A N/A N/A BTW-2(2) 04/01/14 WATER

<1600 N/A N/A N/A N/A N/A N/A N/A BTW-4(2) 04/01/14 WATER

<1530 N/A N/A N/A N/A N/A N/A N/A TrW-1 Well abandoned in place, pending decommissioning 14

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12114)

Ist Quarter 2014 Sampe Dte edi Patic~ate~ 1

~Fe-5~"Ni-3~"Alpha Pu.241(1 )

Sample H.3 1 Gamma -Emitting Sr-.

TRUA Sample Date Media H31 Particulates(l) 1-131(11 89/90(,)

F-5)N-3' T U, u21l TTW-2(2) 04/01/14 WATER

<1540 N/A N/A N/A N/A N/A N/A N/A TTW-3(2) 04/01/14 WATER

<1510 N/A N/A N/A N/A N/A N/A N/A TTW-4 Well abandoned in place, pending decommissioning TTW5 ( 2) 04/01/14 WATER

<1510 N/A I N/A IN/A I

N/A IN/A N/A N/A (1) pCi/L (2) Vendor Analysis 15

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12/14) 2nd Quarter 2014 Sample Date Sample H.3 1 Gamma -Emitting

.131(1)

Sr.89/90'1 ) Fe-55f1 Ni-63(11 Alpha Pu_241(1)

Media Particulates(1 )

1 TRU(1 GWP-6 04/03/14 WATER 47652 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A U-1 AB/F93 GWMS 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A U-2 AB/F9 GWMS 07/02/14 WATER

< 1170 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/10/14 WATER 37491 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/17/14 WATER 38835 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/24/14 WATER 48965 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 04/24/14 WATER 79559 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/01/14 WATER 49413 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/08/14 WATER 46174 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/15/14 WATER 55165 N/A N/A N/A N/A N/A N/A N/A GWP-6 05/22/14 WATER 47491 ND N/A N/A N/A N/A N/A N/A GWP-6 05/29/14 WATER 34357 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/03/14 WATER 33291 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/12/14 WATER 38348 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/16/14 WATER 42400 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 06/16/14 WATER 51900 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/26/14 WATER 48370 N/A N/A N/A N/A N/A N/A N/A PZ-2 06/12/14 WATER Insufficient volume to sample PZ-1 06/12/14 WATER Insufficient volume to sample GWP-3 06/16/14 WATER

< 1260 N/A N/A N/A N/A N/A N/A N/A GWP-3(2) 06/16/14 WATER

<868 N/A N/A N/A N/A N/A N/A N/A PZ-3 06/19/14 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A PZ-3 2 06/19/14 WATER 4800 ND ND N/A N/A N/A N/A N/A GWP-4 06/16/14 WATER 1835 N/A N/A N/A N/A N/A N/A N/A GWP-4(2) 06/16/14 WATER 2650 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L (2) Vendor Analysis 16

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01114 - 12/14) 2nd Quarter 2014 Sample H.3-1 Gamma -Emitting 1-131")*

Sr-TRAp' Sample Date Media Particulates'")

89/901 Fe-55"'

Ni.63 Alpha Pu.241m 1

GWP-5A 06/16/14 WATER

< 1260 N/A N/A N/A N/A N/A N/A N/A GWP-5A 2 1

06/16/14 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-7 06/17/14 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-7(21 06/17/14 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-8 06/17/14 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-8(2' 06/17/14 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-9 06/16/14 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP.9(2) 06/16/14 WATER

<1940 N/A N/A N/A N/A N/A N/A N/A GWP-13 06/18/2014 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-13 (2) 06/18/2014 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-14 06/18/2014 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-14 (2) 06/18/2014 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-15 06/18/2014 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-15 (2) 06/18/2014 WATER

<1970 N/A N/A N/A N/A N/A N/A N/A GWP-16 06/18/2014 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-16 (2) 06/18/2014 WATER

<1940 N/A N/A N/A N/A N/A N/A N/A GWP-17 06/17/2014 WATER

<1260 N/A N/A N/A N/A N/A N/A N/A GWP-17 (2) 06/17/2014 WATER

<1950 N/A N/A N/A N/A N/A N/A N/A GWP-18 04/03/2014 WATER 3857 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 04/03/2014 WATER 4820 N/A N/A N/A N/A N/A N/A N/A GWP-18 04/17/2014 WATER 4270 N/A N/A N/A N/A N/A N/A N/A GWP-18 04/24/2014 WATER

<1345 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/01/2014 WATER 6065 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 05/01/2014 WATER 4230 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/02/2014 WATER 6578 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 05/02/2014 WATER 3680 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/08/2014 WATER 3674 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/15/2014 WATER 5000 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/22/2014 WATER 3674 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/29/2014 WATER 3957 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/03/2014 WATER 3413 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/12/2014 WATER 3543 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/17/2014 WATER 1804 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 06/17/2014 WATER 3790 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/26/2014 WATER 4182 N/A N/A N/A N/A N/A N/A N/A BTW--1 2) 7/02/14 WATER

<1670 ND ND N/A N/A N/A N/A N/A BTW-2(2) 7/03/14 WATER

<1680 ND ND N/A N/A N/A N/A N/A BTW-4(2) 7/02/14 WATER

<1710 ND ND N/A N/A N/A N/A N/A TTW-1 Well abandoned in place, pending decommissioning TTv-2(2) 7/02/14 WATER

<1690 ND I ND I N/A I

I

/A N/A N/A (1) pCi/L (2) Vendor Analysis 17

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12/14)

I I

TTW-3(2) 7/02/14 WATER 1 <1690 1 ND I ND I N/A I N/A I N/AI N/A I

N/A TTVV-4 Well abandoned in place, pending decommissioning TTW.5(2) 7/02/14 WATER 1 <1680 1 ND I ND I N/A I N/A I N/A I N/A I N/A (1) pCi/L (2) Vendor Analysis 18

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12/14) 3rd Quarter 2014 Sample H-3(1)

Gamma -Emitting 1_1310)

Sr-1Alpha Sample Date Media Particulates()1 89/90(1)

Fe'55R Ni'63*1 AlU(p)

Pu'241("

GWP-3 09/21/14 WATER

<1292 N/A N/A N/A N/A N/A N/A N/A GWP-4 09/21/14 WATER

<1292 N/A N/A N/A N/A N/A N/A N/A GWP-5A 09/21/14 WATER

< 1292 N/A N/A N/A N/A N/A N/A N/A GWP-7 09/21/14 WATER

< 1292 N/A N/A N/A N/A N/A N/A N/A GWP-8 09/21/14 WATER

< 1292 N/A N/A N/A N/A N/A N/A N/A GWP-9 09/21/14 WATER

< 1292 N/A N/A N/A N/A N/A N/A N/A GWP-13 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-14 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-15 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-16 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-17 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-18 07/03/14 WATER 2870 N/A N/A N/A N/A N/A N/A N/A GWP-18 07/09/14 WATER 4174 N/A N/A N/A N/A N/A N/A N/A GWP-18 07/17/14 WATER 3730 N/A N/A N/A N/A N/A N/A N/A GWP-18 07/24/14 WATER 1704 N/A N/A N/A N/A N/A N/A N/A GWP-18 07/31/14 WATER 3274 N/A N/A N/A N/A N/A N/A N/A GWP-18 08/07/14 WATER

<1201 N/A N/A N/A N/A N/A N/A N/A GWP-18 08/14/14 WATER 2060 N/A N/A N/A N/A N/A N/A N/A GWP-18 08/20/14 WATER 2140 N/A N/A N/A N/A N/A N/A N/A BTW-1(2) 09/24/14 WATER

<1920 ND ND N/A N/A N/A N/A N/A BTW-2(2) 09/24/14 WATER

<1920 ND ND N/A N/A N/A N/A N/A BTW-4(2) 09/24/14 WATER

<1910 ND ND N/A N/A N/A N/A N/A TTW-1 Well abandoned in place, pending decommissioning TTW.2(2) 09/24/14 WATER

<1920 NND D

]N/A N/A N/A J N/A N/A TTW_3(2) 09/24/14 WATER

<1910 ND ND I N/A N/A N/A N/A N/A TTW-4 Well abandoned in place, pending decommissioning TTW-5(2) 09/24/14 WATER

<1920 ND ND N/A N/A N/A N/A N/A GWP-6 06/20/14 WATER 50,833 N/A N/A N/A N/A N/A N/A N/A GWP-6 6/27/14 WATER 49,333 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L (2)

Vendor Analysis 19

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12/14) 3rd Quarter 2014 Sampl 13li

-EmittingAlpha Sample Date Sample H-3(1 Gamma-Emitting 1131(

Sr.89/90(1 ) Fe-55(1) Ni-63c*1 TRU(') Pu.2411)

SapeMedia Particulates'1

-TRl 1

GWP-6 07/03/14 WATER 75443 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/09/14 WATER 46900 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/17/14 WATER 57252 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/24/14 WATER 51030 N/A N/A N/A N/A N/A N/A N/A GWP-6 07/31/14 WATER 43948 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/07/14 WATER 41987 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/14/14 WATER 41696 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/20/14 WATER 33870 N/A N/A N/A N/A N/A N/A N/A GWP-6 08/27/14 WATER 38130 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/03/14 WATER 25535 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/11/14 WATER 52717 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/18/14 WATER 29835 N/A N/A N/A N/A N/A N/A N/A GWP-6 09/20/14 WATER 19109 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 09/20/14 WATER 18000 ND ND N/A N/A N/A N/A N/A U-1 Intake Yard Drains 08/06/14 WATER

<1427 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Yard drains 08/06/14 WATER

<1427 N/A N/A N/A N/A N/A N/A N/A Discharge Canal Yard 08/06/14 WATER

<1427 N/A N/A N/A N/A N/A N/A N/A Drains Subsurface drains 08/06/14 WATER

<1427 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 08/28/14 WATER

<1227 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump east 08/28/14 WATER

<1227 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 08/28/14 WATER

<1227 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 09/15/14 WATER

<1320 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 09/18/14 WATER

<1300 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 09/19/14 WATER

<1314 N/A N/A N/A N/A N/A N/A N/A U-2 Inside Mat Sump 08/28/14 WATER

<1227 N/A N/A N/A N/A N/A N/A N/A U-2 Outside Mat Sump 08/28/14 WATER

<1227 ND N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 08/28/14 WATER

<1227 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 09/15/14 WATER

<1320 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 09/18/14 WATER

<1300 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 09/19/14 WATER

<1314 N/A N/A N/A N/A N/A N/A N/A PZ-1 09/21/14 WATER Insufficient volume to sample PZ-2 09/21/14 WATER Insufficient volume to sample PZ-3 08/27/14 WATER 4826 N/A N/A N/A N/A N/A N/A N/A PZ-3 09/03/14 WATER 5252 N/A N/A N/A N/A N/A N/A N/A PZ-3 09/11/14 WATER 6513 N/A N/A N/A N/A N/A N/A N/A PZ-3 09/12/14 WATER 6230 N/A N/A N/A N/A N/A N/A N/A PZ-3 09/18/14 WATER 6313 N/A N/A N/A N/A N/A N/A N/A PZ-3 09/20/14 WATER 5891 ND ND N/A N/A N/A N/A N/A PZ-3 (2) 09/20/14 WATER 5580 N/A N/A N/A N/A N/A N/A N/A GWP-5A 09/17/14 WATER

<1331 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L (2) Vendor Analysis 20

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01114 - 12114) 3rd Quarter 2014 Sample Gamma -Emitting

'31(1 Sr-Alpha Sample Date Media H-.(

Particulates(

1-131 89,90(1)

Fe-55(1 ) Ni-63 1)

TRUAlh Pu-241(l ISFSI WELL #4c2) 07/17/14 WATER e1400 ND ND ND ND ND ND ND ISFS1 WELL #4( 2 )

07/17/14 WATER e1390 ND ND ND ND ND ND ND (1) pCi/L (2) Vendor Analysis 21

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12114) 41h Quarter 2014 Gamma -

Sample Date Sample H-3V Emitting 1-131 Sr-89/90 Fe-55 Ni-63 TRU Pu-241 Particulates GWP-3 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-4 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-5A 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-7 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-8 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-9 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-13 12/18/14 WATER

<1224 N/A N/A N/A N/A N/A N/A N/A GWP-14 12/18/14 WATER

< 1313 N/A N/A N/A N/A N/A N/A N/A GWP-15 01/07/15 WATER

< 1290 N/A N/A N/A N/A N/A N/A N/A GWP-16 01/07/15 WATER

< 1290 N/A N/A N/A N/A N/A N/A N/A GWP-17 01/07/15 WATER

< 1290 N/A N/A N/A N/A N/A N/A N/A GWP-18 10/06/14 WATER

<1313 N/A N/A N/A N/A N/A N/A N/A GWP-18 01/07/15 WATER

<1290 N/A N/A N/A N/A N/A N/A N/A GWP-19 12/16/14 WATER 2610 N/A N/A N/A N/A N/A N/A N/A GWP-20 11/15/14 WATER 2610 N/A N/A N/A N/A N/A N/A N/A BTW-1 (2) 12/03/14 WATER

<1260 IND ND N/A N/A N/A N/A N/A BTW-2 (2) 12/11/14 WATER

<1270 ND ND N/A N/A N/A N/A N/A BTW-4 (2) 12/03/14 WATER

<1280 ND ND N/A N/A N/A N/A N/A TTW-2 (2) 12/03/14 WATER

<1280 ND ND N/A N/A N/A N/A N/A TTW-3 (2) 12/03/14 WATER

<1270 ND ND N/A N/A N/A N/A N/A TTW-5 (2) 12/03/14 WATER

<1270 ND ND N/A N/A N/A N/A N/A TTW-1 12/16/14 WATER Insufficient volume to sample TTW-4 12/16/14 WATER Insufficient volume to sample GWP-6 100214 WATER 16052 N/A N/A N/A N/A N/A N/A 10/08/14 WATER 5565 N/A N/A N/A N/A N/A N/A 10/15/14 WATER 2252 N/A N/A N/A N/A N/A N/A 10/22/14 WATER 4196 N/A N/A N/A N/A N/A N/A 10/29/14 WATER 4183 N/A N/A N/A N/A N/A N/A GW-6 11/05/14 WATER 4174 N/A N/A N/A N/A N/A N/A 11/12/14 WATER 4065 N/A N/A N/A N/A N/A N/A 11/19/14 WATER 2652 N/A N/A N/A N/A N/A N/A I

(1) pCi/L (2) Vendor Analysis 22

ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01114 - 12114) 4th Quarter 2014 Gamma -

Alph Sample Date Sample H-3 (1)

Emitting 1-131 Sr-89/90 Fe-55 Ni-63 a

Pu-241 Particulates TRU GWP-6 11/25/14 WATER 1557 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/05/14 WATER 8000 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/11/14 WATER 3478 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/18/14 WATER 6370 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/23/14 WATER 8361 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/30/14 WATER 7457 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/A Drains I

U-2 Intake Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/A Drains Discharge Canal Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/A Drains Sub Surface Drain 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/A Drains U-1 Mat Ump Sat 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/A Sump SouthI U-1 Mat U-1 Eat 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/A Sump East U-2 Mat U-2 nid 10/16/14 WATER <1345 ND

<MDA

<MDA <MDA <MDA N/A

<MDA Sump InsideI U-2 Mat Sump 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/A Outside U-1 AB/FB 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/A GWMS U-2GAB/B 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/A GWMS I___

I__

PZ-1 12/18/14 WATER Insufficient volume to sample PZ-2 12/18/14 WATER Insufficient volume to sample PZ-3 10/02/14 WATER 6835 N/A N/A N/A N/A N/A N/A N/A Pz-3 10/08/14 WATER 5565 N/A N/A N/A N/A N/A N/A N/A Pz-3 10/15/14 WATER 3587 N/A N/A N/A N/A N/A N/A N/A PZ-3 10/22114 WATER 4652 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L (2) Vendor Analysis 23

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/14 - 12/14) 4 th Quarter 2014 PZ-3 10/29/14 WATER 5248 N/A N/A N/A N/A N/A N/A N/A PZ-3 11/05/14 WATER 6435 N/A N/A N/A N/A N/A N/A N/A PZ-3 11/12/14 WATER 3478 N/A N/A N/A N/A N/A N/A N/A PZ-3 11/19/14 WATER 3761 N/A N/A N/A N/A N/A N/A N/A PZ-3 11/25/14 WATER 4448 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/05/14 WATER 5826 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/11/14 WATER 4796 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/18/14 WATER 5543 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/23/14 WATER 6065 N/A N/A N/A N/A N/A N/A N/A PZ-3 12/30/14 WATER 5661 N/A N/A N/A N/A N/A N/A N/A 24

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/14 - 12114)

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 the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. 0-14 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, Revision 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 Regulatory Guide 1.21, Revision 2.

The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation of C-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 32.8 Ci of C-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 30.7 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 C-14 species initially produced in a Pressurized Water Reactor 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% C02 in its calculations.

25

Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 1.41 E-1 mrem from the inhalation pathway, or 9.39E-03% TS of the 1500 mrem/yr dose rate limit and 1.32E+0 mrem from the ingestion pathway or 4.40E+00% TS of the 10CFR50, 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.

26

Miscellaneous There was one entry,14-001, on the Annual Effluent Release Report Log for 2014. Entry 14-001 was to document that Clarifier Effluent Radiation Monitor, 1-LW-RM-1 11 was inoperable for greater than 31 consecutive days.

27

1&%

Station WDominionw Administrative Procedure

Title:

Offsite Dose Calculation Manual (North Anna)

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

Procedure Number Revision Numb E

ctive Date VPAP-2103N 23

/>

On File Revision Summary Location description changed for WSW-23/55 - Radio

,, as re ved.

- Attachment 10, Page 2 of 5: Changed location to:

0/Ae, o

SE of switchyard, entrance on Rt. 700.

N" V

Approvals on File

DOMINION VPAP-2103N REVISION 23 PAGE 2 OF 87 TABLE OF CONTENTS Section Page 1.0 PURPOSE 2.0 SCOPE 5

5

3.0 REFERENCES

/COMMITMENT DOCUMENTS 4.0 DEFINITIONS 5.0 RESPONSIBILITIES 6.0 INSTRUCTIONS 6.1 Sampling and Monitoring Criteria 6.2 Liquid Radioactive Waste Effluents 6.2.1 Liquid Effluent Concentra 6.2.2 Liquid Monitoring Insrw i

6.2.3 Liquid Effluent D LLi t

6.2.4 Liquid R-adw Tr t.ent 6.2.5 Liquid San1/,,

6 8

12 12 12 12 13 16 18 19 6.3 Gaseous R 6ac) ieWXe Effluents 6.3.1 G o>e uent Dose Rate Limitation 6.3.

Gase nitoring Instrumentation

%8 as EEffluent Air Dose Limit 31, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 6

aseous Radwaste Treatment 6.4 Radioactive Liquid and Gaseous Release Permits 6.4.1 Liquid Waste Batch Release Permits 6.4.2 Continuous Release Permit 6.4.3 Waste Gas Decay Tank (WGDT) Release Permit 6.4.4 Reactor Containment Release Permits 6.4.5 Miscellaneous Gaseous Release Permit 19 19 22 25 27 29 31 31 31 32 32 32

DOMINION VPAP-2103N REVISION 23 PAGE 3 OF 87 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 t

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*i e

e 3.1.35]

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

DOMINION VPAP-2103N REVISION 23 PAGE 4 OF 87 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 5

Surveillance Requirements 62 8

Critical Organ Dose Factors 65 9

Radiological Environmental Monitoring r

67 10 Environmental Sampling Locations 72 11 Detection Capabilities for Enviro a pie Analysis 77 12 Reporting Levels for Radioa it on ations in Environmental Samples 79 13 Meteorological, Liqui d4 se Pathway Analysis 80

DOMINION VPAP-2103N REVISION 23 PAGE 5 OF 87 1.0 PURPOSE The Offsite Dose CalculationManual (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 tha.

" Concentration of radioactive liquid effluents to the unrestr/

we limited to ten times the effluent concentration values of 10 CFR 20,1 B, B le 2, Column 2, for radionuclides other than dissolved or entrained nobt as 2,4 aCi/ml for dissolved or entrained noble gases.

Exposure to the maximum exposed member bl*ii the unrestricted area from radioactive liquid effluents will not res dos er" than the liquid dose limits of 10 CFR 50, Appendix I

Dose rate at and beyond the site ry radioactive gaseous effluents will be limited to:

Noble gases - less th or al t dose rate of 500 mremiyr to the total body and less than or equal to a f

mrem/yr to the skin

1131, 1133, and ar11 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 yradlctive gaseous effluents to the maximum exposed member of the public in th str ea will not result in doses greater than the gaseous dose limits of 10 Ig

,)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 23 PAGE 6 OF 87

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 a aseo ffluents from Light-Water-Cooled Nuclear Power Plants, Rev. 1, U.iR

,n,174 3.1.6 Regulatory Guide 1.109, Calculation of Annual Dos n F "Routine Releases of Reactor Effluents for the Purpose of Evaluata ith 10 CFR 50, Appendix I, Rev. 1, U.S. NRC, October 197sp ercraspr 3.1.7 Regulatory Guide 1.111, Methods for E atin *'

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 e

ual (TRM) 3.1.10 NUREG-0324, XOQ or the Meteorological Evaluation of Routine Effluent Releases uc a wer Stations, U.S. NRC, Septeimber 1977 3.1.11 NUREG/CR-1 s

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

-50564, Rev. 1, Concentration Factors of Chemical Elements in Edible Aq anisms, October, 1972 3.1.13

8 ol. 2, July 1973, Numerical Guides for Design Objectives and Limiting o"i*

r Operation to Meet the Criterion "As Low As Practicable" For otive 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 23 PAGE 7 OF 87 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 mergency 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, i*

3.1.28 SAA001092, Non-SA SO) ect' s4 Review 93-1, Recommendation 3 3.1.29 NEI 07-07, Industry o t#*otection Initiative - Final Guidance Document 3.1.30 CA086406, Land C

su suits 3.1.31 Quality Assu it ort 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

s icensing Commitment) N-2006-4026-R15, Groundwater Monitoring 1

Ian 3.1.36 S

93-1, Diagnosis and Mitigation of RCS Leakage including SGTR 3.2 Commitment Documents None

DOMINION VPAP-2103N REVISION 23 PAGE 8 OF 87 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 ng rat'

. This assessment includes, where possible, comparison of the ch I i nd status with other indications or status derived from independent ins annels measuring the same parameter.

4.3 Channel Operational Test

< § 9 A Channel Operational Test (COT) shall 1ýt-3,ti f a simulated or actual signal into the channel as close to the sensor as prac{E*

h ik OPERABILITY of all devices in the channel required for channel OPE IT ff COT shall include adjustments, as necessary, of the required alar,,,e trip setpoints required for channel OPERABILITY such that s in a ithin the necessary range and accuracy. The COT may be performed by means o r

"e sequential, overlapping, or total channel steps.

4.4 Critical Organ

<,q, /ial, That organ, whic determined to be the maximum exposed organ based on an effluent pathway anad s, theby ensuring the dose and dose rate limitations to any organ will not be excee To e ations to the critical organ will be evaluated in accordance with Techrn ec, ications 5.5.4 dose rate limits specified for any organ to check that 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 1131, 1132, 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 23 PAGE 9 OF 87 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 SA - Semi-annually At least once pe 4

ys R - Refueling At least onc S/U - Start-up Prior to h reahrt-up P-Prior to release Co rete o

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

ce during each release 4.7 Gaseous Radwaste Treatment S A system that reduces radioactv* $/ySp uents by collecting primary coolant system offgases from the primary e

an roviding delay or holdup to reduce total radioactivity prior to release to the envil 1tI system comprises the waste gas decay tanks, regenerative heat e ng as charcoal filters, process vent blowers, waste gas surge tanks, and waste s

agm compressor.

4.8 General No ncla X= 951Z n at a point at a given instant (curies per cubic meter)

D =6(o t : quantity of deposited radioactive material per unit area (curies per square meter)

Q = Source strength (instantaneous; grams, curies)

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

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

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

DOMINION VPAP-2103N REVISION 23 PAGE 10 OF 87 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 ty when it is capable of performing its specified functions and all nec en instrumentation, controls, normal and emergency electrical power sou coo seal 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 0

their related support functions.

4.12 Purge - Purging Controlled discharge of air or gas f ent to maintain temperature, pressure, humidity, concentration, or other er ition, so that replacement air or gas is required.

to purify the confinement.

4.13 Rated Thermal Pow Total reactor core fer e to reactor coolant (i.e., North Anna - 2940 MWt).

4.14 Site Boundary The line o

Dominion does not own, lease, or otherwise control the land.

4.15 Sorc*.

A qualitat 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 23 PAGE 11 OF 87 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

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

_ oa sorbers and High Efficiency Particulate Air (HEPA) filters to remove io 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 Safe e ýVe atmospheric cleanup systems are not Ventilation Exhaust Treatment Sys c.

5.0 RESPONSIBILITIES 5.1 Manager Radiological Protect*

a eft_.l stry The Manager Radiological, ecti nd Chemistry is responsible for:

5.1.1 Establishing a is rocedures for surveying, sampling, and monitoring radioactiv e

s a e environment.

5.1.2 Surveyi g, and analyzing plant effluents and environmental monitoring, and doc ntlng ese activities.

5.1."

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

5.1.4 P

ig 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 23 PAGE 12 OF 87 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 nd ran of radiation or parameter monitored.

6.1.3 A sufficient number of survey points shall be use r

le en to adequately assess the status of the discharge monitored.

6.1.4 Samples shall be representative of the v m a of discharge monitored.

6.1.5 Surveys, sampling, analyses, and to rtds shall be accurately and legibly documented, and sufficiently de meaning and intent of the records are clear.

6.1.6 Surveys, analyses, a 0

ring records shall be reviewed for trends, completeness, and accuracy.

iquid Radioactiv as E

ts 6.2.1 Liquid Concentration Limitations

a. I id e

icentrations discharged from the Station shall not exceed the n1* }nts:

c9nr radionuclides (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 laCi/mld.

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 23 PAGE 13 OF 87

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 Volume of Waste Discharged x,

where:

gCi/m-i = the concentration of nuclide i in the li ef e

arge ACWi

= ten times the effluent concentratio u

u tricted areas of nuclide i, expressed as gCi/ml

, Appendix B, Table 2, Column 2 for radionuclides an n e gases, and 2E-4 jCi/ml for dissolved or entrainedno gay e s 6.2.2 Liquid Monitoring Instrumenta

\\

a. Radioactive Liquid Effiuen'o nstrumentation Radioactive liquid efflu ori nstrumentation channels shown on Radioactive Liquid ue toring Instrumentation (Attachment 1) shall be operable with the ar setpoints set to ensure that Step 6.2.1.a. limits are not exceeded.

1. Ala rtrip-tpo' of these channels shall be determined and adjusted in ai eri.

with Step 6.2.2.d., Setpoint Calculation.

f

",a ra'active liquid effluent monitoring instrumentation channel alarm/trip s

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 23 PAGE 14 OF 87

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 tuithi days. If unsuccessful and the channel is required t c,en explain in the next Annual Radioactive Effluent Release th inoperability was not corrected in a timely manner.

c. Applicable Monitors Liquid effluent monitors for i

are:

DOMINION VPAP-2103N REVISION 23 PAGE 15 OF 87

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 pCi/mi, of the radioaciiy i

srn the radioactivity concentration in the efflu e

r to dilution FD =

dhepiu t

,io n

w ater/flow r the raiact"' *j

asuring h C =

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

maximum design pathwa u n ate FD =

dilution water flow rate d,.

D = FE + (218,000 n

circ. pumps in service)

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

ice er, including component cooling service water, circula, an quid radwaste) in the circulating water discharge tunnel bey r t ast nt of possible radioactive material addition. No dilutio s

d this pathway. Therefore,..Equation (2) becomes:

S =C (3)

The for 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 23 PAGE 16 OF 87

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

S CFDKLW FE 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 on CF S W where:

Ksw

= The fraction oJ nt concentration 10 CFR theý n, attributable to line p I a

6. The sum K, K

1 i,

11 not be greater than 1.0.

(4) to implement vaste effluent es:

(5) limit, used to implement the service water effluent 6.2.3 Liquid At

ýr 31 days, perform the dose calculations in Step 6.2.3.c. to ensure commitment to the maximum exposed member of the public from erials in liquid releases (from each reactor unit) to unrestricted areas I' During any calendar quarter:

Less than or equal to 1.5 mrem to the total body

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

2. During any calendar year:

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

" Less than or equal to 10 mrem to the critical organ

DOMINION VPAP-2103N REVISION 23 PAGE 17 OF 87

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 radionu(

effluents released to unrestricted areas based on: <

W ere:

Subscripts

=

i, refers to in vi utiuclide in liquid (6)

D =

thecui liquid re'nt to the total body or critical organ from the t, in mrem Bi = Dose Valut t'ictors (mrem/Ci) for each age group of interest.

ýovided in code file for North Anna Power Station tical organ calculations Qi -'

activity for the considered 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 laCi/ml

DOMINION VPAP-2103N REVISION 23 PAGE 18 OF 87

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 ofluents released in connection with specific station functions, such as mai t \\ce o efueling outages, shall be used in projections as appropriate.

a. Requirement

1. The Liquid Radwaste Treatment Sy/p all b sed to reduce the radioactive materials in liquid waste prior t *scpIge n projected dose due to liquid effluent, from each reactor it 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 liqu e*e s projected at least once per 31 days.

b. Action i"

If radioactive l ste ldischarged without treatment and in excess of the above 1i q *ubmit to the NRC, within 30 days, a special report in accor a VP

-2802, Notifications and Reports, that includes the follown 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).

DOMINION VPAP-2103N REVISION 23 PAGE 19 OF 87

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 (jiCi/ml).

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

PDTB = DTB(RlFl)

(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 R1 as in Step 6.2.4.c.2.

3. Estimate F1 as in Step6.2.4.c.3

4. Determine PD, = project *,*

'dose in a 31-day period.

-*/* *-D-o(R1 FI1)

(9) 6.2.5 Liquid Sam Radioactiv ast shall be sampled and analyzed according to the sampling and anal'sŽ)

rements in Radioactive Liquid Waste Sampling and Analysis Pro (At hment 3).

6.3 Gase s

c'e 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.

DOMINION VPAP-2103N REVISION 23 PAGE 20 OF 87

2. The dose rate limit for 1 3 1, 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 determined, continuously, to be within Step 6.3.1.a. limits.

3. Dose rates due to 1131, 1133, tritium, and all radi jclid ticulate form with half-lives greater than 8 days, in gaseous ts alI be determined to be within the above limits by obtaining*

mnples and performing analyses in accordance with the sa l1 and a lysis program specified on Radioactive Gaseous Waste Sang sis Program (Attachment 4).

0" Kl "i

DOMINION VPAP-2103N REVISION 23 PAGE 21 OF 87

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:

Y [KivvQivv + KjpvQipv] _ 500mnrem/yr to the total body (10)

OR

[(Livv + 1.1Mivv)Qivv + (Lipv + 1.1Mipv)Qipvj]

3000mrem/yr to th where:

Subscripts

=

vv, refers to vent rele

sfrome uilding ventilation vent pv, refers to the re.

i r, m the process vent; i, refers to ind u

di l1'Ngcide Kivv, Kipv

=

The total o

ac or ventilation vents or process vent release t

missions for each identified noble gas radio

, in em/yr per Curie/sec. Factors are listed in G(

ou)Ef ose Factors (Attachment 5)

Liv, Lipv

-i i

factor for ventilation vents or process vent e e d edue to beta emissions for each identified noble gas i

in mrem/yr per Curie/sec. Factors are listed in Ga us Effluent Dose Factors (Attachment 5)

Mi e 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 23 PAGE 22 OF 87

2. The dose rate limit for 113 1, 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:

S[Pivv!Qivv + PipvQipv] < 1500mrem/yr to the critical organ (12) where:

Pivv, Pipv

= The critical organ dose factor for ven vents or process vent for 1131, 1133, H3, and all radio

,ides i articulate form with half-lives greater than 8 da

, fo in ation pathway, in mrem/yr per Curie/sec. F s

lis>,'n Gaseous Effluent Dose Factors (Attach 5)

Oi=vvipv The release rate for y ati r process vent of 1131, 1133, H3, and all ra nd particulate form with half-lives an gaseous effluents in Curie/sec (per site)

3. All gaseous releases, not tt

ti ss vent, are considered ground level and shall be included in t rn Lation of Qi,,,.

6.3.2 Gaseous Monitoring I u

a

a. Requirement

1. The radioa e

fluent monitoring instrumentation channels shown in Radio 0i ffluent Monitoring Instrumentation (Attachment 6) shall be o with arm/trip setpoints set to ensure that Step 6.3.1.a. noble gas li n*

"iot exceeded. Alarm/trip setpoints of these channels shall be eter *ed and adjusted in accordance with Step 6.3.2.d.

a adioactive 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 23 PAGE 23 OF 87

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 umr nired by tables in Radioactive Gaseous Effluent Monitoring Instý tý onj ttachment 6) take the action shown in those tables.

I

3. Return instruments to operable status wit successful, explain in the next Annual Radioactive Effluen a, e ort why the inoperability was not corrected in a timely manner

c. Applicable Monitors Radioactive gaseous effluent o

o hich alarm/trip setpoints shall be determined are:

Releasef

-'Instrument Number Pro V

t 1-GW-RM-178-1 r

jector J-SV-RM-121 2--SV-RM-22 1 tilation Vent A I-VG-RM-179-1 ilation Vent B 1 -VG-RM-180-1

DOMINION VPAP-2103N REVISION 23 PAGE 24 OF 87

d. Setpoint Calculations

1. Setpoint calculations foreach monitor listed in Step 6.3.2.c. shall maintain this relationship:

D > Dpv + Dcae + Dvv (13) where:

D

=

Step 6.3.1.a. dose limits that implement 10 CFR 20 for the Station, mrem/yr PV The noble gas site boundary dose rate fr roce ent gaseous effluent releases, mrem/yr Dcae

=

The noble gas site boundary dose f

co nser air ejector gaseous effluent releases, mre DVV

=

The noble gas site boundar se ro summation of Ventilation Vent A plusgg us e uent releases, mrem/yr

2. Setpoint values shall be determi*(

.2E-03 m

Fm (14) where:

m he ease pathway, process vent (pv), ventilation vent (vv)

--enser air ejector (cae)

S,,

=

e effluent concentration limit implementing Step 6.3.1.a.

for the Station, paCi/mi

\\

=

The release rate limit for pathway m determined from methodology in Step 6.3.1.c., using Xe133 as nuclide to be released, gCi/sec 12E-03

=

CFM per ml/sec m

= The maximum flow rate for pathway m, CFM

DOMINION VPAP-2103N REVISION 23 PAGE 25 OF 87 NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm/trip setpoints should be based on the radioactive noble gases. It is not practicable to apply instantaneous alarm/trip setpoints to integrating monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.

6.3.3 Noble Gas Effluent Air Dose Limit

a. Requirement

1. The air dose in unrestricted areas due to noble gases rele d in gaseous effluents from each unit at or beyond the site boundw shal.

limited to:

During any calendar quarter: < 5 mrads for ga/a ra ti nd! <10 mrads for beta radiation

During any calendar year: < 10 mrads ation and < 20 mrads for beta radiation

2. Cumulative dose contributions no ga or the current calendar quarter and current calendar year s e

r\\

d in accordance with Step 6.3.3.c.

at least once per 31 days. (2

b. Action If the calculated ai roactive noble gases in gaseous effluents exceeds any of the abo pr' re and submit to the NRC, within 30 days, a special report in ac wit AP-2802, Notifications and Reports, that identifies the caus d

c in, e limits and defines corrective actions that have been taken to re rses and the proposed corrective actions to be taken to assure that se e ases will be in compliance with the limits in Step 6.3.3.a.

DOMINION VPAP-2103N REVISION 23 PAGE 26 OF 87

c. Noble Gas Effluent Air Dose Calculation Gaseous releases, not through the process vent, are considered ground-level and shall be included in the determination of Qivv.

The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following:

For gamma radiation:

Dg = 3.17E-08Z[MivvQivv + Mi.

(15)

For beta radiation:

Db = 3.17E-08 I

ipvQipv (16)

Where:

Subscripts

=

vv, t

leases from the building ventilation vents, i

ci air

tors e vent releases from the process vent 1, e to individual radionuclide D9 e ai ose for gamma radiation, in mrad Db

/

r dose for beta radiation, in mrad M*

e 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) ipv

=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 23 PAGE 27 OF 87 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 critical

2. Cumulative dose contributions to a member of theu

fro )131,

1133, tritium, and radionuclides in particulate form i haliveater than 8 days, in gaseous effluents released to unrestrict e

r urrent calendar quarter and current calendar year shal dete t least once per 31 days in accordance with Step 6.3.4.c.

b. Action If the calculated dose from t

e1133, tritium, and radionuclides in particulate form, with haP e* reat 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 wi PAP-802, Notifications and Reports, that.contains the:

1. C i

ts.

2. Co iv/tion aken to reduce releases.

3. Pro rrective actions to be taken to assure that subsequent releases will in c pliance with limits stated in Step 6.3.4.a.

DOMINION VPAP-2103N REVISION 23 PAGE 28 OF 87

c. Dose Calculations Gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qw. 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

.1131,

1133, tritium, and particulate-form radionuclides with h f gre rthan 8 days, shall be determined by:

Dr = 3.7EO81[RMiv ivy pvQipv]

(17)

Where:

Subscripts vv, refers t

a rom the building ventilation vents; pv, refer o t eases from the process vent Dr

=

the 0-c i

al organ of the maximum exposed member

e*

ifc, nmrem RMivv, RMip

~he fac r for ventilation venqts or process vent release due 1

133, tritium, and from all particulate-form adi clides with half-lives greater than 8 days, in mrem/yr

"~\\4 urie/sec. Factors are listed in' Critical Organ Dose Factors

" ~

ttachment 8)

=

the release for ventilation vents or process vent of 1131, 1133, tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in Curies

-08 the inverse of the number of seconds in a year

DOMINION VPAP-2103N REVISION 23 PAGE 29 OF 87 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 be site undary, would

.exceed 0.2 mrad for gamma radiation and 0.4 be iation, averaged over 31 days.

2. The Ventilation Exhaust Treatment Sy m sha se ed to reduce radioactive materials in gaseous waste before' isc e

en the projected doses due to gaseous effluent releases, from it t a eas at and beyond the site boundary, would exceed 0 e,

tical organ, averaged over 31 days.

3. Doses due to gaseou a

fro the site shall be projected at least once per 31 days, base n t t ions in Step 6.3.5.c.

b. Action If gaseous ex ds the limits in Step 6.3.5.a. is discharged without treatme re a

ubmit to the NRC within 30 days, a special report in acco c

th VPAP-2802, Notifications and Reports, that includes:

n ex Ination why gaseous radwaste was being discharged without treatment, "cation of any inoperable equipment or subsystems, and the reason for the operability.

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 23 PAGE 30 OF 87

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 (jtCi/ml).

4. Determine PDg, the projected 31-day gamma air dose.

PDg = Dg(R x Fg)

(18)

d. Projected Beta Dose

1. Determine Db, the 31-day beta air dose in the ousld per Equation (16).

2. Estimate Rg and Fg as in Steps 6.3.5.c..

nd

3. Determine PDb, the projected 31-be e.

gD

)

(19)

e. Projected Maximu ember of the Public Dose

1. Determine D x, the

-day makimum exposed member of the public dose in the previou y p d, per Equation (14), where Dr = Dmax.

2.th o of the estimated activity from 1131, 1133, radioactive I n* particulate form with half-lives greater than 8 days, and tritium in t~he c

~n* 1-day period to the activity of 1131, i133, radioactive materials in Sltic te form with half-lives greater than 8 days, and tritium in the previous

- ay period (pCi/ml).

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

PDmax = Dmax(Rg X Fi)

(20)

DOMINION VPAP-2103N REVISION 23 PAGE 31 OF 87 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, releases from tanks considered continuous releases.

A Batch Release Permit is required for a reles (or potentially contain) radioactive liqui.

anl,

BRTT

LLWDT

" HLWDT

" Turbine Buildin en secondary coc

CDT 2

/)

wharifier are which contain 6.4.2

)rization befort lant activity exceeds 1.0 E-5 ltCi/ml initiating continuous releases of 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 23 PAGE 32 OF 87 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) ai nt Monitor high alarm 6.4.5 Miscellaneous Gaseous Release Permit Operations shall obtain RP authorizati e

I ng releases of noble gases that may not be accounted for by routine 0,0oj y planned release not being routed through the Process Vent or Ve ati e g., steam driven auxiliary feedwater pump testing if primary to sea ge exists).

6.4.6 Radioactive Liquid lease Controls

a. Operations shay$

tiR, pending releases and request RP to initiate the appropriate /

r'*

n Operations shall provide the necessary information to complet e r uir lease permit.

b. A rep

.t e sample shall be obtained of the source to be released.

I.*

etns 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 23 PAGE 33 OF 87

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

" Maximum authorized release rate I

" 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. Check that the correct source is authorized for rel s

2. Note maximum authorized release rate.

3. Note percent of Technical Specificatio se represents.

4. Note and ensure compliance with i

a ntrols or conditions applicable to the release.

g. When conmmencing release, 0vide RP with required information.

As appropriate, required*

r nI include:

" Date and time relea w t

Starting tank/s

-le

" Beginning p

" Releas

" Dil rflow rate

h.

n ter ating the release, Operations shall return the permit to RP and provide aenfo 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 23 PAGE 34 OF 87 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 mated n

id or gaseous effluents exceed twice the limits in Steps 6.2.3.a., 6.3 a.!

6.3.

., calculate (including direct radiation contribution from the s a fr tside storage tanks) whether limits in Step 6.5.1 have been

b. If the limits in Step 6.5.1 have been exce

prep, ad submit to the NRC within 30 days, a special report in ac a c t

PAP-2802, Notifications and Reports, that defines the corrective b

en to reduce subsequent releases and to prevent recurrence, an c

ule for achieving conformance with the limits. Special reports 10 CFR 20.2203(a)(4), shall include:

1. An analysis that a

raiation exposure (dose) to a real individual

--from uraniu el c sources, including all effluent pathways and direct radiation, ale year that includes the releases. covered by the report.

2.A d ipti o

levels of radiation and concentrations of radioactive rn o olved, and the cause of the exposure levels or concentrations.

f t ated dose exceeds the limits in Step 6.5.1, and if the release n n that violates 40 CFR 190 has not already been corrected, the special Sport 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 23 PAGE 35 OF 87

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 sio

o. I

b. Action

1. If the Radiological Environmental Moni is 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 in a itting to the NRC, in the Annual Radiological Environm

]er rng Report required by Technical Specifications 5.6.2, a des ti

'N

'asons for not conducting the program as required, and the pl ing recurrence.

2. If, when average endar quarter, radioactivity due to station

"-.effluents exc s th orting levels of Reporting Levels.for Radioactivity Concentra s

nvi mental Samples (Attachment 12) prepare and submit to the I

days, a special report in accordance with VPAP-2802, Nand ors, that:

1 Id~f he causes for exceeding the limits, and

,Defi)s the corrective actions to be taken to reduce radioactive effluents so the potential annual dose to a member of the public is less than the Sc calendar year limits of Steps 6.2.3, 6.3.3, and 6.3.4 When more than one of the radionuclides listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 12) are detected in the sampling medium, the report shall be submitted if:

concentration (1) + concentration (2) +... Ž1.0 (21) reporting level (1) reporting level (2)

DOMINION VPAP-2103N REVISION 23 PAGE 36 OF 87

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 accord with VPAP-2802, Notifications and Reports.

<KN\\

4. If milk or fresh leafy vegetable samples are una b

e or more of the sample locations required by Environmental

. gppcations (Attachment ic 10), identify locations for obtaining re e

s es and add them to the radiological environmental monitorig

,ranithin 30 days. The specific locations from which samples u

aimay then be deleted from the monitoring program. Identi ej-ee e unavailability of samples and identify the new locations r.n'eplacement samples in the next Annual Radioactive Effluen a

ee t in accordance with VPAP-2802, Notifications and eode in the report a revised figure and table for the ODCM to re t the locations.

6.6.2 Land U

a. Req

)t Ala

sus shall be conducted and shall identify, within a distance of 8 km es ation in each of the 16 meteorological sectors of the following:

ilk animal rest residence wrest 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 23 PAGE 37 OF 87

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 gJ,,ulate )n 6.3.4.a.2, identify the new locations in the next Annual io iv uent Release Report in accordance with VPAP-2802, No s

Reports.

2. If a land use census identifies locatio t

a culated dose or dose commitment (via the same expos path

)

percent greater than at a location from which samples ar, tly]

ng obtained, add the new locations to the Radiologii Ivir al Monitoring Program within 30 days. Sampling locations, i

the control station location, that have the lowest calculated os mitments (via the same exposure pathway) may be deleted o

ring program. Identify new locations in the next Annual Rai,,t' E'

~ent Release Report and include in the report revised figures s'xk

< re ting the new locations in accordance with VPAP-2802, Not'iti an eports. [Reference 3.1.33]

6.6.3 Interlabo o~ow"'omparison Program a.

re t

e materials (which contain nuclides produced at the Station), supplied as an Interlaboratory Comparison Program, shall be analyzed.

DOMINION VPAP-2103N REVISION 23 PAGE 38 OF 87

b. Action

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

Program Cross-Check of Milk 1131, Gamma, Sr 89 and Sr 90 Water Gross Beta, Gamma, 1131, H3 (Tritium), Sr 89 and Sr 9° (blind - any combinations of above radionuclides)

Air Filter Gross Beta, Gamma, Sr 90

2. If analyses are not performed as required by 3.b, rport in the Annual Radiological Environmental Operating ance with VPAP-2802, Notifications and Reports, the corre i tic aken to prevent recurrence.

c. Results Results shall be reported in the

ua" d*gical Environmental Monitoring Report in accordance with VI*,

' kifications and Reports.

6.7 Reporting Requirements 6.7.1 Annual Radiologicln men al Operating Report Routine Radiolog

'-I iron ntal Operating Reports covering the operation of the units during

)i syv P dar year shall be submitted prior to May 1 of each year.

A singlee i

may made for the Station. Radiological Environmental Operatinr shall include:

ari interpretations, and analysis of trends of results of radiological

(

o nmental 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 23 PAGE 39 OF 87

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 environment onit tg, pg

d. At least two legible maps covering sampling locat' table giving distances and directions from the centerline of on or.

e map shall cover stations near the site boundary; a second s in e

distant stations.

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

f. Discussion of deviations fro e4 a.ronmental sampling schedule per Radiological Environme iori Program (Attachment 9).

g. Discussion of analys nAee lower limit of detection (LLD) required by Detection Capabi es nvironmental Sample Analysis (Attachment 11) was not achievable.

h. Any reIt any groundwater wells described in the environmental prog

\\(K er the results were required by the environmental program or not.

6.7.2 An I Ra "cve Effluent Release Report ae ¢ nt t-Station a active Effluent Release Reports covering operation of the units during the 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 summarized on a quarterly basis following the format of Regulatory Guide 1.21, Appendix B, for liquid and gaseous effluents.

Data shall be summarized on an annual basis following the format of Regulatory Guide 1.21, Appendix B, for solid waste. [Reference 3.1.34]

DOMINION VPAP-2103N REVISION 23 PAGE 40 OF 87

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 k

e wrong liquid radwaste release tank

" Unplanned releases from large leaks t

d valve or pipe failures that result in a quantity of release t a CFR 50.72, Immediate Notification Requirements fo er g

ear Power Reactors or 10 CFR 50.73, Licensee Event R

-S m

.rt is required

Unplanned releases d

n by Radiation Protection Supervision, which may or m qun Condition Report

4. Major than or tive liquid, gaseous, and solid waste treatri. nt systems during the ckjr* iod.

5. Cha PA 103N, Offsite Dose Calculation Manual (North Anna)

S

.7.4).

isi new locations for dose calculations or environmental monitoring

>i i*d by the land use census (See Step 6.6.2).

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 23 PAGE 41 OF 87

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 the Station during the previous calendar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.

Population doses shall not be included in dose assessments.

2. The dose to the maximum exposed member of the p

c radioactive liquid and gaseous effluents from the Station shall or d with the dose assessment performed above. If the dose to th a i u osed member of the public exceeds twice the limits of 6.2.3*.

.3.3.a. 1, or 6.3.4.a. 1, the dose assessment shall include the tribUtt direct radiation.

NOTE: NUREG-0543 states: "There is reasoneKran tat sites with up to four operating reactors that have releaý it dix I design objective values are also in conformance with the ElZJ*

a fuel Cycle Standard, 40 CFR Part 190."

3. Meteorological c i

ng the previous calendar year or historical annualaver at o ric dispersion conditions shall be used todetermine gaseous a os

DOMINION VPAP-2103N REVISION 23 PAGE 42 OF 87 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 th ldo liquid and gaseous effluents from the Station shall b 11 or with the dose assessment performed above. If the dose.

eexposed member of the public exceeds twice the limits of 6...a.

23 2, 6.3.3.a. 1, or 6.3.4.a. 1, the dose assessment shall include thentrj tio m direct radiation.

Meteorological conditions th e i s calendar year or historical annual average atmospheric disper4_:l i ios shall be used to determine gaseous pathway doses.

6.7.3. Annual Meteorolo "i$l

a. Meteorologica ta lect during the previous year shall be in the form of joint frequency wind speed, wind direction, and atmospheric stability.

b. Mete*

data shall be retained in a file on site and shall be made available to Cup r e st.

6.7.4 n

0 ODCM to the ODCM shall be:

a."-viewed and approved by 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 23 PAGE 43 OF 87

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 part of, or concurrent with the Annual Radioactive E period of the report in which any change was mad//

by markings in the margin of the affected pa-c, page that was changed, and shall indicate tiate implemented.

etiNiltire ODCM as a telea)l Report for the hah- *g~hall be identified

ýjating the area of the ith/year) the change was

d. Submitted to NRC in accordance 6.7.5 Groundwater Protection Initit,

a. Notifications and Rep*,)

1. Informal cornmu frti of the next b iess for:

P-J2, Notifications and Reports.

ce 3.1.35]

made to state/local/NRC officials by the end

Any spillN m titng the requirements of Step 6.7.2.a.7.

ample result exceeding the retporting levels of Reporting Radioactivity Concentrations in Environmental Samples nt 12).

1 30- report shall be submitted to the NRC and a copy concurrently

rwarded 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 REVISION 23 PAGE 44 OF 87

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 id >i.jt and retention requirements established for the Nuclear Records Retention e (

S) per RM-AA-100, Record Creation, Transmittal and Retrieval.

Quality Assurance Records

Records of changes to the ODCM in accorda,/

h,

.p 6.7.4

Records of meteorological data in acc a.n.pj2)ik 6.7.3

Records of sampling and analyses

" Records of radioactive materi n

u1fflents released to the environment

" Records of preventive m n

c

.,rveillances, and calibrations 7.2 The following item(s) 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 23 PAGE 45 OF 87 ATTACHMENT 1 (Page 1 of 2)

Radioactive Liquid Effluent Monitoring Instrumentation Instrument

1. Liquid Radwaste Effluent (a) 1-LW-RM-1 11, Liquid Radwaste Effluent Monitor (b) 1-LW-FT-104, Liquid Radwaste Effluent Total Flow Measuring Device (c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel (d) I-LW-i 130, Liquid Waste Effluent Proportional I

(e) 1-SW-RM-108, Service Water Effluent 1

(f) 1-SW-RM-130, Unit 1 Monitor 1

(g) 2-SW-RM-230, Unit 2

.I Monitor 1

2.

(a) 11 (b)

ýr High Capacity Blowdown Flash Tank Outlet Rate Unit 1 I-BD-FT-105 Unit 2 2-BD-FT-205 11 (c) Steam Generator High Capacity Blowdown Proportional Samplini System Collection Tank Unit 1 1-BD-TK-4 Unit 2 2-BD-TK-4 11

DOMINION VPAP-2103N REVISION 23 PAGE 46 OF 87 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 lx10-7 lgCi/g or an isotopic radioactivity at an LLD of at least 5x 10-7 lCi/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 nours during actual releases. Design capacity performance curves d

errd^in may be used to estimate flow.

ACTION 3:

If the number of operable channels is less tn uire ake repairs as soon as possible. Effluent releases via this path ym c

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 c/y

are collected and analyzed for principal gamma emitters as defid i

'I ve Liquid Waste Sampling and Analysis Program (Attachm NOTE 1: The capability for obtaining t least every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months must exist. Grab samples shall conimence if ther in c of radioactivity in the Service Water System or a*n indication from other r n

itors in the Service Water System of an increase in radioactivity.

NOTE 2:

To utilize I-08 as the effluent radiation monitor for the associated loop, 0-PT-75 (1-R"-

108 Flow Verification) must be performed prior to placing the loop in s, re."

ut.'monitoring is not required when discharge flowpath is not in service.

DOMINION VPAP-2103N REVISION 23 PAGE 47 OF 87 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) I-LW-RM-1J N, Liquid Radwaste Effluent Monitor D

D Q (NOTE 1)

(b) I-LW-FT-104, Liquid Radwaste Effluent Total Flow D (NOTE 3)

)

R Q

Measuring Device (c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel D

TE 4)

N N/A N/A (d) 1-LW-1 130, Liquid Waste Effluent Proportional Sam<

OT 4 N/A N/A N/A Valve (e) I-SW-RM-108, SW Effluent Monitor (NOTE D

M R

Q (NOTE 2)

(f) 1-SW-RM-130, Unit I Circul i n Ka2 em D

M R

Q(NOTE2)

Effluent Line Monitor

//

DMR QN)E2 (g) 2-SW-RM-230, Unit 2 i

L 9 ter System D

M R

Q (NOTE 2)

Efflutent Line Monit°/orAV X

/-

2.

Steam Generator (S

~g' pacity Blowdown (a) SGwn Radiation Monitor Unit

- 125 Q (NOTE 6)

Unit 2

-225 D (NOTE 7)

D (NOTE 8)

R (NOTE 5)

(b) SG High Capacity Blowdown Flash Tank Outlet Flow Rate Unit 1 1-BD-FT-105 D (NOTE 8)

N/A N/A Unit 2 2-BD-FT-205 (c) SG High Capacity Blowdown Proportional Sampling System Collection Tank Unit 1 1-BD-TK-4 Unit 2 2-BD-TK-4 D (NOTE4)

N/A N/A N/A

DOMINION VPAP-2103N REVISION 23 PAGE 48 OF 87 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 se "operate" mode.

NOTE 2: The Channel Operational Test shall demonstrate that Control alarnnnunciation occurs if any of the following conditions exists:-\\/

a. Instrument indicates measured levels above the at t.

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

))

NOTE 3:

Channel Check shall consist of checking in aio 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 of in roportional flow exceeds 0.5 mls/gallon.

NOTE 5:

Channel Operational Test*aae that system isolation odcurs on a.radiation monitor High-High Al NOTE 6:

Channel Operatio all onstrate:

a. Trip sign s.

erate at the required setpoints. Isolation is not required.

b. Loc radiat'f kmitor indication occurs if instrument controls are not set in "Operate" t

i strument indicates measured levels are above the alarm/trip setpoint.

NOTE 7:

T monitor automatically performs periodic source checks. The Source Check and Cl Check are satisfied as long as the green light is lit.

NOTE 8: This is confirmed by indicated effluent flow less than or equal to 190 gpm.

NOTE 9:

To utilize I-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 23 PAGE 49 OF 87 ATTACHMENT 3 (Page 1 of 3)

Radioactive Liquid Waste Sampling and Analysis Program Batch Releases (Notes 2 and 7)

Continuous Releases (Note

DOMINION VPAP-2103N REVISION 23 PAGE 50 OF 87 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) Lower (as microcuries per unit mass or Sb

= the standard deviation of the k

rate of a blank sample as te qti'n as defined above section 4.8) inting rate or of the counting ints per minute, cpm)

E V

=

2.22E+06 Y

the counting efficieJ (a

u er disintegration) the sample si nit S or volume) the num 0

1"ntegratlons per minute (dpm) per microcurie r

chemical yield (when applicable) eKioact e decay constant for the particular radionuclide

sed time between the midpoint of sample collection and time of nting of E, V, Y and At should be used in the calculation.

At The LED'-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 23 PAGE 51 OF 87 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: Mn54, Fe59, Co 58, Co 60, Zn65, Mo 99, Cs 134, Cs 137, Ce 141, and Ce 144. This list does not mean that only these nuclides are to be detected and reported.

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

NOTE 4: A composite sample is one in which the quantity of liquid saI, pr 1brtional to the quantity of liquid waste discharged and for which the met of p

e'g{

mployed results in a specimen that is representative of the liquids rele NOTE 5:

A continuous release is the discharge of liquid wa of a i-lscrete 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 o

trat's of radioactive materials in liquid effluents, samples shall be collected nti proportion to the rate of flow of the effluent stream. Prior to analyse e

ken for the composite shall be thoroughly mixed in order for the comp e

e representative of the effluent releases.

NOTE-7:

Whenever the secondar ol n tivity exceeds 10-5-jCi/ml, the turbine building sump pumps shall be placed ual/eration and samples shall be taken and analyzed prior to release. Seco 0

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: The it for which the LLD specification applies exclusively are the following ra

"r-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 23 PAGE 52 OF 87 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 (tCi/ml),

(Note 1)

Prior to Release Prncpa 6am 1X 10-4 Pi toste Release TPrior to Release Emitters (Not A. Waste Gas (Each Tank (Each Tank)

Storage Tank Grab Sample)

H3 I X 10-6 B. Containment Prior to Release Prior to Release Erin 1 X 10-4 Purge (Each PURGE (Each PURGE)

I x 10-6 Grab Sample)

(cP G

C. Ventilation Monthly ri/

7_ri 1 X 10-4 (1) Process Vent (Grab Sample)

<tE ' ters (Note 2)

(2) Vent Vent A (Notes 3 and 5)

(!jte H3 x 10-6 (3) Vent Vent B Continuous ee e

IV31 1 x 10-12 (Note 4 and 5

-mple) 1 x All Release C

t

\\,Weekly Principal Gamma 1 x 10-11 (Note 4-q culate Sample Emitter (Note 2)

s5)X

'/

Monthly Types as listed t

Composite Gross Alpha Ix 10-11 Particulate Sample Co

N,,

Co~tuous Quarterly and 5)

Composite Sr89 and Sr90 1 x 10-11 n

AParticulate C(Nontinuou Noble Gas Monitor Noble Gases Gross 1 x 10-6 (Note 4 and 5)

Beta or Gamma Condenser Air Weekly Weekly Principle 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 Principle Gamma I X 10-4 Vacuum Steam Emitters (Note 2)

(Grab Sample)

Release H3 1 x 10-6 Ejector (Hogger)

(Note 8)

DOMINION VPAP-2103N REVISION 23 PAGE 53 OF 87 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 =

Where:

LLD

=

the "a priori" (before the fact) Lower Lii (as microcuries per unit mass or v Sb

= the standard deviation of the k

n rate of a blank sample as o

t, E

=

the counting efficie (ba5 u

er d(

V

the sample sie nit ss or volt n as defined above section 4.9) inting rate or of the counting nts per minute, cpm) isintegration) 2.22E+06

per minute (dpm) per microcurie Y

decay constant for the particular radionuclide At time between the midpoint of sample collection and time of inting of E, V, Y and At should be used in the calculation.

The L-DLis 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.

NOTE 2:

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr87, Kr 88, Xe13 3, Xe133 m, Xe 13 5, Xe135m, and Xe 138 for gaseous emissions and Mn 54, Fe5 9, Co58, Co6 0, Zn 6 5, Mo 9 9, Cs 13 4, Cs 13 7, Ce 14 1 and Ce 144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

DOMINION VPAP-2103N REVISION 23 PAGE 54 OF 87 ATTACHMENT 4 (Page 3 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program NOTE 3:

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

a. Analysis shows that the dose equivalent 1131 concentration in the rimary coolant is greater than 1.0 laCi/gm; and

b. The noble gas activity monitor shows that effluent activ' as d by more than a factor of 3.

NOTE 4: The ratio of the sample flow rate to the sampled st all be known for the period covered by each dose or dose rate calcu io de) accordance with Steps 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: Samples shall be changed at least onc i e d

and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or a, Iom sampler). Sampling shall also be performed at least once per 24 or o, t seven days following each shutdown, start-up or thermal power c a 15 percent of rated thermal power in one hour and analyses shall be c le d in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are ana oc sponding LLDs may be increased by a factor of 10. This requirement ap

)if

a. Analysis

, 'at the dose equivalent 1131 concentration in the primary coolant is grea han g i/gm and;

b.

o**

tor shows that effluent activity has increased more than a factor of 3.

NOTE 6:

Wheneve e secondary coolant activity exceeds 10-5 pCi/ml, Condenser Air Ejector and Steam enerator 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 applies exclusively are the following radionuclides: Kr8 7, Kr8 8, Xe 133, Xe13 3m, Xe 135, Xe135m, and Xe 13 8 for gaseous emissions. This list does not mean that only these nuclides are to be detected and reported.

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

DOMINION VPAP-2103N REVISION 23 PAGE 55 OF 87 ATTACHMENT 4 (Page 4 of 4)

Radioactive Gaseous Waste Sampling and Analysis Program NOTE 8: If the secondary coolant activity level in any Steam Generator supplying steam to the Hogger exceeds 1.OE-5 ptCi/ml, Steam Generator samples shall be obtained and analyzed prior to release.

DOMINION VPAP-2103N REVISION 23 PAGE 56 OF 87 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

DOMINION VPAP-2103N REVISION 23 PAGE 57 OF 87 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 23 PAGE 58 OF 87 ATTACHMENT 5 (Page 3 of 3)

Gaseous Effluent Dose Factors (Inhalation Pathway Dose Factors)

Ventilation Vent x/Q = 9.3E-06 sec/mr3 at 1416 meters SE Direction Process Vent x/Q = 1.2E-06 sec/mr3 at 1513 meters S Direction Pivv Iipv Radionuclide mrem/yr_

Curie/sec

ýCu serc H-3 1.05E+04 03 Cr-51 7.95E+02 E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND Rb-86 ND Sr-90 ND Y-91 ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-"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 Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND 1-131 1.51E+08 1.95E+07 1-133 3.58E+07 4.62E+06 ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

DOMINION VPAP-2103N REVISION 23 PAGE 59 OF 87 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 I-GW-RM-178-1 (NO1 2,4 (b)

Iodine Sampler I-GW-RM-178-1 2,5 Process Vent Continuous HP Sampler (c)

Particulate Sampler I-GW-RM-178-1 1

Process Vent Continuous HP Sampler (NOTE 3) 2,5 (d)

Total Flow Monitor 1 -GW-FT-10811 (e)

Sampler Flow Rate Measuri MGPI Flow Rate Measu e ic HP Sampler Rotameter (NOTE 3)

2. CONDENSER AIR E

x IM (a)

Gro ss Acti vil,,xqg9 Unit I3-SV-R3 Unit 2.

-RM-

'Iv (b)

Flo e

ng Device Un*

ýFI-IOOA I-

-FI-101A 1(NOTE 1) 1 4*7SV-FI-100B3 1-SV-FI-1011B Unit 2 2-SV-FI-200A 2-SV-FI-20 1 A

) Q17

)AnnJ I(NOTE 2) 1 2-SV-FI-20 1 B

DOMINION VPAP-2103N REVISION 23 PAGE 60 OF 87 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-179-1O(NO 1

2 (b)

Iodine Sampler I-VG-RM-179-1 Vent Vent A Continuous HP Sampler (c)

Particulate Sampler I -VG-RM-179-1 2

Vent Vent A Continuous HP Sampler (NOTE 3)"2 (d)

Total Flow Monitor I -HV-FT-121 2A11 (e)

Sampler Flow Rate Measuri I

MGPI Flow Rate Measui e ic1 HP Sampler Rotameter (NOTE 3) 1

4. VENTILATION VEN,

'/

(a)

Noble Gas A* i nitor"V (NOTE 3)2 Vent Continuous HP Sampler (NOTE 3)

(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 1

I (e)

Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring Device 1

HP Sampler Rotameter (NOTE 3)

DOMINION VPAP-2103N REVISION 23 PAGE 61 OF 87 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

ithis path may continue if grab samples are taken at least once per twelve (12) h and t e 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 f an qu'h,ent for primary-to-secondary leak rate determination. The need to determine th",

nar y--secondary leak rate, e.g., the performance of 1/2-PT-46.3B, shall be deter a*c*"~e with the requirements of TRM TR 3.4.5. However, the same sample ma used tulffll both the requirements of this action and primary-to-secondary leak rate er) tio./

ACTION 4:

If the number of operable channels is less n r

red, contents of the Waste Gas Decay Tanks may be released to the environm 4'

ed t prior to initiation of the release:

a.

At least two independent sampl s of t ontents are analyzed, and:

b. At least two technically qu d

mbeof the Station staff independently check the release rate calculation di har ve lineup.

ACTION 5:

If the number of operablh' I

than required, effluent releases from the Waste Gas Decay Tank may con e p vi'lamples are continuously collected with auxiliary sampling equipment as re e

adi ive Gaseous Waste Sampling and Analysis Program (Attachment NOTE 1:

A channel s C

t of:

a.

The ninstren nstalled in the ejector through which the discharge is routed; either Train

ý4.S 10

, 10lA), or Train B (1-SV-FI-LOOB, l01B) or both.

b. (0*ulr6u nts 101A and 101B provide low range measurement. Flow instruments 100A and p

ide 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 23 PAGE 62 OF 87 ATTACHMENT 7 (Page 1 of 3)

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL DESCRIPTION CHANNEL SOURCE CHANNEL Channel CHECK CHECK CALIBRATION Operational Test

1. PROCESS VENT SYSTEM (a)

Noble Gas Activity Monitor 1-GW-RM-178-1 D

M (NOTE5)

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/

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 "7

I-GW-FT-108 N/A R

Q (e)

Sampler Flow Rate Measurin<

Device MGPI Flow Rate Meas D (_ TE 3)

N/A R

N/A Device HP Sampler Rot 5ter)

(NOTE 3)

N/A Every 18 months N/A

2. CONDENSER JECTOR SYSTEM (a)

Noble Ga ctivity onitor

-221 D

M R

Q, R (NOTE 6)

(b)

Flow easuring Device Unit 1 1-SV-FI-100A I-SV-FI-IO1A D

N/A R

N/A 1-SV-FI-100GB 1-SV-FI-1O1B Unit 2 2-SV-FI-200A 2-SV-FI-201 A 2-SV-FI-200B D

N/A R

N/A 2-SV-FL-201 B

DOMINION VPAP-2103N REVISION 23 PAGE 63 OF 87 ATTACHMENT 7 (Page 2 of 3)

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL DESCRIPTION CHANNEL SOURCE CHANNEL Channel CHECK CHECK CALIBRATION Operational Test

3.

VENTILATION VENT A (a)

Noble Gas Activity Monitor 1-VG-RM-179-1 D

M (NOTE 5)

R Q (NOTE 2)

(b)

Iodine Sampler 1-VG-RM-179-1 W

N/A A

N/A Vent Vent A Continuous HP Sampler D (NOTE 3)

N/A

/

N/A (c)

Particulate Sampler 1 -VG-RM-179-1 N/

Vent Vent A Continuous HP D

A N/

Sampler D (NOTE 3)

N/A N/A (d)

Total Flow Monitor 1-HV-FT-1212A D

N/

R Q

(e)

Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring TEO3 N/A R

N/A Device.,

=

0 HP Sampler Rotameter 0,

-N/A Every 18 months N/A

4. VENTILATION VENT B

/

(a)

Noble Gas.Activity IN/*/

1-VG-RM-180-1 D

M (NOTE 5)

R Q (NOTE 2)

(b)

Iodine S ample rNV I-VG-RM-180-W N/A N/A N/A Vent VeB Cont u

P Sap1r D (NOTE 3)

N/A N/A N/A (c )

P

' u l A ha T -

II 1-W N/A N/A N/A Vent V ontinuous HP Samp elr D (NOTE 3)

N/A N/A N/A (d)

Total Flow Monitor 1-HV-FT-1212B D

N/A R

Q (e)

Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring D (NOTE 3)

N/A R

N/A Device HP Sampler Rotameter D (NOTE 3)

N/A R

N/A

DOMINION VPAP-2103N REVISION 23 PAGE 64 OF 87 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 sel e" mode.

NOTE 2: The Channel Operational Test shall demonstrate:

a. Control Room alarm annunciation occurs if the ii levels are above the alarm/trip setpoint.

b. Alarm annunciation occurs if the instrun con NOTE 3: Channel Checks shall consist of checkin i

.on Channel Checks shall be made at lea pi r periodic, or batch releases are m

. cat nee of one train, either MGPI or Sa NOTE 4: The Channel Operation st demonstrate that

a. Control Room alarb ion occurs if the-i are above ale e se

b. The Intode selection control automatic htes measured set in "operate" mode.

flow during periods of release.

ours on days on which continuous, d only to be done to check operability nstrument indicates measured levels ally resets to "operate" mode when NOTE 5:

M lt-) [

-178-1, l-VG-RM-179-1, and l-VG-RM-180-1 perform periodic so e

s automatically.

NOTE 6: The q -ly, 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 23 PAGE 65 OF 87 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 Directio Rmivv Radionuclide mrem/yr re r

Curie/sec

//u

/sec H-3 1.32E+4 1E+3 Mn-54 ND ND Fe-59 ND ND Cr-Si 1.11E+3/

7.16E+2 Co-58 ND ND Co-60 ND Zn-65 ND Rb-86 N

ND Sr-89 ND Sr-90 ND ND Y-91 ND ND Zr-95 NDND Nb-95 ND ND u-10_3

,ND ND Ru/

ND ND 1ND ND Te-12 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 Ba-140 ND ND Ce-141 ND ND

DOMINION VPAP-2103N REVISION 23 PAGE 66 OF 87 ATTACHMENT 8 (Page 2 of 2)

Critical Organ Dose Factors

DOMINION VPAP-2103N REVISION 23 PAGE 67 OF 87 ATTACHMENT 9 (Page 1 of 5)

Radiological Environmental Monitoring Program Exposure Pathway Number of Sample and Collection Type and Frequency o[

and/or Sample Sample Location (NOTE 2)

Frequency Analysis

1. DIRECT RADIATION (NOTE 3) 36 routine monitoring stations, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:

1) An inner ring of stations, one in each environmental GAMMA DOSE meteorological s t within the sit ary

2) An outer ri fi stations e i ch envirq1rhep~l "

mvr"*ca e tor Quarterly Quarterly thi8 ge from alance of the tio s to be placed in cial interest areas such as population centers, nearby residences, schools, and in I or 2 areas to serve as control stations Additional TFL~s are n aced in anoronriate emer~encv nian sectors. These are not nart of the environmental

?rogram. Collect and report with environmental TLDs.

DOMINION VPAP-2103N REVISION 23 PAGE 68 OF 87 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. AIRBORNE Samples from 5 locations:

a) 3 samples from close to the 3 site boundary locations (in different ioI e Canister sectors) of the highest 1 Analysis, weekly calculated historical annual average ground Conti i Radioiodines and level D/Q sa er Particulates b) 1 sample from the ra.

wi vicinity of a communi,:a eco tion Particulate Sampler having the highest Gross beta radioactivity calculated annu analysis following filter average grou e

change; (NOTE 4)

D/Q A*,*

c) 1 samp om ntrol Gamma isotopic analy-locat 5

kI sis of composite (by i

"tanqin east location) quarterly e*ev ut direction (NOTE 5)

J. WAYERBURNE S

I om 3 locations:

) ample upstream Gamma isotopic analysis a) Surfa b1 sample downstream Grab Monthly mo steyfor tritium c) 1 sample from cooling analysis quarterly lagoon l oamma 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 potential recreational value

DOMINION VPAP-2103N REVISION 23 PAGE 69 OF 87 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. INGi*1TION a) Samples from milking animals in 3 locations within 5 km that have the highest potential. If there are none, then I sample from milking animals in each of 3 areas a) Milk between 5 to 8 km where M

I mma isotopic (NOTE 5)

(NOTE 7) doses are calculated to be and 1131 analysis monthly greater than 1 mrem per yr (NOTE 6) b) I sample from milkin animals at a control I

(15-30 km in the prevalent win ire a) I sampleo n

ia nd recreati lyi p nt species unh, catfish) b) Fish and in I

discharge Gamma isotopic.on edible Invertebrates Seinulyportions s

le of same species in as*I influenced by plant is.N.discharge

.*tiples of an edible broad leaf vegetation grown nearest each of two different offsite locations of highest predicted historical annual average Monthly if groud lvel

/Q f n-ilkGamma isotopic (NOTE 5) c) Food Products ground level D/Q if milk available, or and 1131 analysis sampling is not performed at harvest b) 1 sample of broad leaf vegetation grown 15-30 km in the least prevalent wind direction if milk sampling is not performed

DOMINION VPAP-2103N REVISION 23 PAGE 70 OF 87 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 Sampli ons ttachment 10),

specific parameters of distance and direction sector fronml c

rli the reactor, and additional description where pertinent, shall be provio i n ac nt 10. Refer to Radiological Assessment Branch Technical Positi and t G-0 133, Preparation of Radiological Effluent Technical Specificatio r

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 aal de to complete corrective action before the end of the next samplingp i

o ions from the sampling schedule shall be documented in the An R

io'l cal Environmental Operating Report pursuant to Step 6.7.1. It is rec at imes, it may not be possible or practicable to continue to obtain samp of t me of choice at the most desired location or time. In these instances, su--le rl' native media and locations may be chosen for the particular pathway in questi and roiate substitutions made within 30 days in the radiological env*

e'-

toring 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 rie,"

tions 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 23 PAGE 71 OF 87 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 ni st ions may be reduced according to geographical limitations, e.g., at anan*te, sectors will be over water so that the number of dosimeters may be red cecor ly. The frequency of analysis or readout for TLD systems will depend n t eristics of the specific system used and should be selected to obtainom 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 an es the yearly mean of control samples, gamma isotopic analysis s l',i.d on the individual samples.

NOTE 5: Gamma isotopic anal is idlification and quantification of gamma-emitting radionuclides that triI ble to effluents from the facility.

It

%X'7 NOTE 6:

The dose shal"'

ated r the maximum organ and age group, using the methodology and parameter tN DCM.

NOTE 7: If mi a

in*

not be performed, use item 4.c (Page 3 of 5, Radiological E

ro t-onitoring Program (Attachment 9)).

NOTE:

ally, the following TLDs are placed in the indicated locations for Emergency Plan requirements. This is due to the fact that Emergency Plan and Environmental Plan grid centers are in different locations. These TLDs are collected quarterly in conjunction with Environmental Sector TLDs.

EP Sector TLD Designator Location A

EPSAI/2 On fence, U-2 side, Intake Structure F

EPSF 3/4 On power pole on island (across from FPPH)

R EPSR 5/6 On door of Substation "M" P

EPSP 9/10 On/near Switchyard gate J

EPSJ 7/8 NW corner of the Generator Rewind Bldg.

DOMINION VPAP-2103N REVISION 23 PAGE 72 OF 87 ATTACHMENT 10 (Page 1 of 5)

Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media No.

(Miles)

Frequency Environmental NAPS Sewage 01 0.20 NE Quarterly & On-Site TLDs Treatment Plant A n nualy Frederick's Hall 02 5.30 SSW ualy Mineral,VA 03 7.10 WS Q

ri

)n Wares Crossroads 04 5.10 Frly ally Route 752 05 4.20 NNE uarterly &

Annually Sturgeon's Creek05A Marina Annually Levy, VA 06 Quarterly &

SE_

Annually Bumpass, VA SSE Quarterly &

Annually End of Route 685 1.00 WNW Quarterly & Site Boundary

//

Annually Route 700 1.00 WSW Quarterly & Site Boundary Annually 0.93 SSE Quarterly & Site Boundary Annually "A sp en H i Q u arterlynuall

Orange, 24 22.00 NW Quarterly &Control Bea Co^

g Towe 0.06 N

uartery On-Site eMi*r xe N-2/34 2.04 N

Quarterly P

iLot "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" E-10/42 2.85 E

Quarterly Island Dike ESE-11/43 0.12 ESE Quarterly On-Site

(

toute 622 t,5 L-1 Z144

4. /U L11SL Quarterly

DOMINION VPAP-2103N REVISION 23 PAGE 73 OF 87 ATTACHMENT 10 (Page 2 of 5)

Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media No.

(Miles)

_ciFrequencyR EnvironmentalI TLDs Biology Lab SE-13/45 0.64 SE Quarterly On-Site Route 701 (Dam Entrance)

SE-14/46 5.88 SE

,

GaN "Aspen Hills" SSE-15/47 0.93 5o Btoundary Elk Creek SSE-16/48 2.33

/*/Boudar NAPS Access Road S-17/49 0.36 //

ýuarterly On-Site Elk Creek Church S-18/50

" Quarterly NAPS Access Road SSW-19/51

.2 Quarterly On-Site Route 618 SSW-20/5

\\.<

SSW Quarterly 500KV Tower SW-2 53 SW Quarterly On-Site Route 700 96 SW Quarterly At NAPS, on pole, SE of switchyard, entrance o,

0.38 WSW Quarterly On-Site Route 700

-24/56 1.00 WSW Quarterly Site Boundary S W-25/57 0.32 W

Quarterly On-Site S witchyoý,))/

Route 68 W-26/58 1.55 W

Quarterly F

out 85 WNW-27/59 1.00 WNW Quarterly Bndr Boundary WNW-28/60 1.40 WNW Quarterly d

n Area North NW-29/61 0.52 NW Quarterly On-Site Lake Anna 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 23 PAGE 74 OF 87 ATTACHMENT 10 (Page 3 of 5)

Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media No.

(Miles)

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 yefd \\

Radioiodine Mineral, VA 03 7.10 WSW e

)

Wares Crossroads 04 5.10 WNW k

Route 752 05 4.20 NNE eee Sturgeon's Creek 05A 2.04

<SýN-*

ZW:I Marina Levy, VA

.06 4.70/

Bumpass, VA 07

7.

/

Weekly End of Route 685 21 e"0. 0V Weekly Site Boundary Route 700 22 1

\\WSW Weekly Site Boundary "Aspen Hills"

3-\\

..9.*3 SSE Weekly Site Boundary Orange, VA 4

NW Weekly Control Surtace Water Waste Heat Treatme

[Reference Facility (Second 3.37 SSE Monthly 3.1.311 Cooling Lagoon)

(up. stream

/09A 12.9 WNW Monthly Control Bridge)

No Lnna eY 11 5.80 SE Monthly a

Giroundwater/

(well wate Lab 01A 0.64 SE Quarterly (well water)\\

Aquatic M

eat Treatment Semi-Sediment Faci-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 23 PAGE 75 OF 87 ATTACHMENT 10 (Page 4 of 5)

Environmental Sampling Locations Distance and Direction From Unit No. 1 Sample Location Station Distance Direction Collection Remarks Media No.

(Miles)

Frequency Soil Fredericks Hall 02

-5.30 SSW Once per 3 yrs (continued)

Mineral, VA 03 7.10 WSW Once per 3rs Wares Crossroads 04 5.10 WNW Once Route 752 05 4.20 NNE One 3 yrs)

Sturgeon's Creek2.04 N

/ncp er Marina Levy, VA 06 4.70 EE--yr Bumpass, VA 07 7.30 c

er3 yrs End of Route 685 21 1.00

,S ce per 3 yrs Site Boundary Route 700 22

,,0ý1.0

/ /Sn Once per 3 yrs Site Boundary "Aspen Hills" 23 3.SS Once per 3 yrs Site Boundary Orange, VA 24

2.

Once per 3 yrs Control Milk Lakeside Dairy 1

.50 NW Monthly (Charles Harris)

Waste Heat Treatment Fish Facility (Second 3.37 SSE Semi-Annually Cooling Lagoon)w,,Z Lake Orange,,

16.50 NW Semi-Annually Control Food Products Stagecoac oad))

4B varies NNE Monthly (Edible if available, broadleaf Route 61 15 varies SE or at harvest vegetation')

<\\

veeat~a),lte* *

!1 varies NWControl n

26 varies S

__._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 23 PAGE 76 OF 87 ATTACHMENT 10 (Page 5 of 5)

Environmental Sampling Locations NOTE: Additionally, the following TLDs are placed in the indicated locations for Emergency Plan requirements. This is due to the fact that Emergency Plan and Environmental Plan grid centers are in different locations. These TLDs are collected quarterly in conjunction with Environmental Sector TLDs.

EP Sector TLD Designator Location N

A EPSAI/2 On fence, U-2 side, Intake Stru re F

EPSF 3/4 On power pole on island (acrd frV 1W R

EPSR 5/6 On door of Substation "M" P

EPSP 9/10 On/near Switchyard g J

EPSJ 7/8 NW corner of the G ator i

Bldg.

NOTE: ISFSI well water samples are obtaine on

'onal Use Permit issued by the County of Louisa.

- )

'K,?

'0

DOMINION VPAP-2103N REVISION 23 PAGE 77 OF 87 ATTACHMENT 11 (Page 1 of 2)

Detection Capabilities for Environmental Sample Analysis*

LOWER LIMIT OF DETECTION (LLD)

NOTE 1:

Requ dNNecti kapabilities for thermoluminescent dosimeters used for environmental ma r

given in Regulatory Guide 4.13.

NOTE 2:

This i t not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

NOTE 3:

LLD for the drinking water samples. Drinking water includes samples from Lake Anna and well samples analyzed as part of the REMP. The LLD for the non-drinking water samples is 10 pCi/1.

NOTE 4: No LLD for precipitation water due to short-half lives of these nuclides.

DOMINION VPAP-2103N REVISION 23 PAGE 78 OF 87 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=

b,*.--*(51 E e V

2.22E+06

Y

e-(2-(

Where:

LLD the "a priori" (before the fact) Lowe e

ion as defined above (as microcuries per unit mass or,,e) ee, ubsection 4.9)

Sb=

the standard deviation of the b gr d

ing rate or of the counting rate of a blank sample as a (a

unt 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

=

iochemical yield (when applicable) dt ioactive decay constant for the particular radionuclide At t

elapsed time between sample collection (or end of the sample (o*llection period) and time of counting (for environmental samples, not plant effluent samples)

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

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

DOMINION VPAP-2103N REVISION 23 PAGE 79 OF 87 ATTACHMENT 12 (Page 1 of 1)

Reporting Levels for Radioactivity Concentrations in Environmental Samples Water Airborne Fish Milk Food Products AnalysisParticulate or Analysis (pCi/l)

Gases (pCicm3) (pCi/kg, wet)

(pCi/I)

(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 Zn-65 300 0

Zr-Nb-95 400 1-131 21 11120.9 3

100 Cs-134 30 60 1,000 Cs-137 50 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking water

DOMINION VPAP-2103N REVISION 23 PAGE 80 OF 87 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 i vi at boundary and member of the public. The X/Q and D/Q values resulting in m

u posures were incorporated into the dose factors in Gaseous Effluent D achment 5) and Critical Organ Dose Factors (Attachment 8).

1.2 Meteorological Data, Parameters, and Met lo Onsite meteorological data for the period J r

9, through December 31, 1981, were used in calculations. These data include I

ind direction, and differential temperature for the purpose of dete ig-- in quency distributions for those releases characterized as ground level (e.(.,ve vent), and those characterized as mixed mode (i.e., process vent). The por s

ase characterized as ground level were based on AT158.9ft_28.2ft and 28.2 fo

, and the portions characterized as mixed mode were based on AT1 58,9ft-,

t wind data.

Z/Q's and D/Q's e

culated using the NRC computer code "XOQDOQ - Program for the Meteor ical lu'ion of Routine Effluent Releases at Nuclear Power Stations,"

Septe*

9 code is based upon a straight line airflow model implementing the assumnt ined in Section C (excluding C1a and Clb) of Regulatory Guide 1.111, "Method s'timating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."

The open terrain adjustment factors were applied to the Z/Q values as recommended in Regulatory Guide 1.111. The site region is characterized by gently rolling terrain so open terrain correction factors were considered appropriate. The ground level ventilation vent release calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area.

DOMINION VPAP-2103N REVISION 23 PAGE 81 OF 87 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 Py Final Safety Analysis Report Table 11C.2-8.

X/Q and D/Q values were calculated for the nearest site ent, milk cow, and vegetable garden by sector for process vent and yen i n ven leases at distances specified from North Anna Power Station Annual Environ ta S ata for 1981. X/Q values were also calculated for the nearest lake shoreline b bor e process vent and ventilation vent releases.

According to the definition for sho in G-0133, "Preparation of Radiological Effluent Technical Specification r

Power Stations," October, 1978, some gaseous releases may fit this catego4riri waste gas decay tank releases and containment purges.

However, these releases ar* i de

" ong term for dose calculations as past releases were both random in tim an tion as evidenced by reviewing past release reports.

Therefore, the u al average concentrations is appropriate according to NUREG-0133.

The X/Q an Q

Nalculated from 1981 meteorological data are comparable to the values nte North Anna Power Station IJFSAR.

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 X/Q 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 23 PAGE 82 OF 87 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 1.1 E-09 per m2 at a location 3250 meters For tritium, the Z/Q value from ventilation vent releases resulting in the maximt sure I rthe milk pathway was 7.2E-07 sec/m 3, and 3.9E-07 sec/m 3 for proces n

e a location 3250 meters N sector.

Analysis using 2007 release data indicates that the m

,limiti Cal organ is the child's thyroid. The location is 1593 meters SSE sector r

o t releases, the D/Q is 1.IE-8.

For tritium releases, the X/Q values at this loca" e

--7 for the process vent and 3.3E-6 for the ventilation vents.

2.0 LIQUID PATHWAY ANALYS 2.1 Purpose

'rm The purpose of the liquid an is was to determine the maximum exposed member of the public in unrest a

ai esult of radioactive liquid effluent releases. The analysis includes a determi on/mos estrictive liquid pathway, most restrictive age group, and critical organ. T h-is is required for Subsection 6.2.

2.2 Data, Psa Mthodology

Initial, i e 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-0133.

DOMINION VPAP-2103N REVISION 23 PAGE 83 OF 87 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 dater were set to one. Transit time calculations were based on average flow rates.

pa meters were defaults selected by the LADTAP computer code.

Beginning in 1997, the activity by nuclide released in ti s entered into the North Anna Power Station liquid pathway critical or*

alcu ons spreadsheet, which calculates the most limiting age group total bod I

an. This Process is repeated annually.

2.3 Results Initially, the fish pathway resulted' rg

e. The critical organ each year was the liver, and the adult and teenage age

~

the same organ dose. However, since the adult total body dose was great n

et total body dose for each year, the adult was selected as the most restrictive, a B

ning in 1997, the most limiting age group for both total body and critical or is lcu

, from.the spreadsheet for North Anna Power Station liquid pathway critical a

culations.

DOMINION VPAP-2103N REVISION 23 PAGE 84 OF 87 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 cor liance with Steps 6.3.l.a. and 6.3.3.a. The analysis also included a determinatio<fdi h

tical pathway, location of maximum exposed member of the public, and the c ' al" an the maximum dose due to 1131, 1133, tritium, and for all radionuclides in pa ul for ith half-lives greater than 8 days for use in demonstrating compliance e

s in Step 6.3.4.a. 1. In addition, the analysis included a determination of thc itic y, maximum age group, and sector location of an exposed individual thro th i a

'on pathway from 1131, 1133, tritium, and particulates with half-lives greateK a

demonstrate compliance with Step 6.3.1.a.

3.2 Data, Parameters, and Methodoh Annual average X/Q values were

,s described in Section 1 of this attachment, for the nearest site boundary in h i/'onal sector and at other critical locations beyond the site boundary. The largest uea determined to be 9.3E-06 sec/m 3 at site boundary for ventilation vent rele s a 1416 meters SE direction, a'nd 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 s i a ir doses for gamma and beta radiation due to noble gases, would be at t es

.und locations. The doses from both release points are summed in calcul on a

ate total maximum dose.

Step 6.3.1@

se 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 23 PAGE 85 OF 87 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, 1133, 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 for 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, an I

us Effluent Dose Factors (Attachment 5) were obtained by performing its co rsion of the appropriate dose factors from Table B-1, Regulatory Guide 1.109 ev.

yr per Ci/m 3 or mrad/yr per Ci/m 3, and multiplying by the ventilation vent s nd

',/Q value of 9.3E-06 sec/m 3. The same approach was used in calculating t a

eta dose factors Kipv, Lipv, Mipv, and Nipv in Gaseous Effluent Dose Facto MA'irt 5) using the process vent site boundary X/Q value of 1.2E-06 sec/m3.

The inhalation pathway do act rs and Pipv in Gaseous Effluent Dose Factors (Attachment 5) were calcu sin he following equation:

'(B ) DFAi(x/Q) (mrem/yr per Curie/sec)

(29-1) where:

K' o

f unit conversion, 1E+12 pCi/Ci BR the eathing rate of the child age group, 3700 m3/yr, from Table E-5, Regulatory i lel.109, Rev.1 DFAi the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem/pCi, from Table E-9, Regulatory Guide 1.109, Rev. 1 X/Q the ventilation vent site boundary X/Q, 9.3E-06 sec/m 3, or the process vent site boundary X/Q, 1.2E-06 sec/m 3, as appropriate

DOMINION VPAP-2103N REVISION 23 PAGE 86 OF 87 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 n1d 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 h ke shoreline with the largest annual X/Q of a.OE-04 at a location 274 er, tor. The NRC computer code GASPAR was run to calculate the inhalation do is ii vidual. The GASPAR results were corrected for the fractional year the me r

.c would 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 a t, ember of the public receiving the largest dose beyond site boundary was mj e be located'1432 meters N sector. The critical pathway was vegetation, the maxim pos age group was the child, and the critical organ was the thyroid.

Q Pathway analysis u

dicate that existing pathways, including ground and inhalation, within five tis of Nth nna Power Station, yield Ri dose factors less than those determined for the ati.

erence 3.1.32]

The R I, a

Mipv 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:

K ' _'

A +_

)

-U StL

iSt, h

-)]

=

L[Yv(Xri + w)](DFLi)[UclFLe C+

Ufge j

(29-2) where:

K'

=

a constant of unit conversion, 1E+12 pCi/Ci Yv

=

vegetable areal density in Kg/mi 2

DOMINION VPAP-2103N REVISION 23 PAGE 87 OF 87 ATTACHMENT 13 (Page 8 of 8)

Meteorological, Liquid, and Gaseous Pathway Analysis Ucd

=

child leafy vegetable consumption rate, 26 Kg/yr Uc=

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 em/pCi,-from Table E-13, Regulatory Guide 1.109, Rev. 1 Xi

= decay constant for the ith radionuclide, in sec-1, fro ocr Xw

=

decay constant for removal of activity of leaf an fa by weathering, 5.73E-07 sec-1 (corresponding to a 14 day h tf

= time between harvest of leafy vegetation est 8.60E+4, in seconds th

=

time between harvest of stored eget n n on, 5.18E+6, in seconds fL fraction of annual intake of leaf tI locally, 1.0 (dimensionless) fg

= fraction of annual intake of stol" I.

grown locally, 0.76 (dimensionless)

Parameters used in the above equ re ed from NUREG-0133 and Regulatory Guide 1.109, Revision 1 Since the concentration oti in 'etation is based on the airborne concentration rather than the deposition, t Dose Factors (Attachment 8)for tritium were calculated by multiplying t by the appropriate X/Q:

by multplyinequation

.K K

U fL+ U f](DFLj)a[O.75(O.5/H)]

(29-3) where:

K"' =

a constant of unit conversion 1 E+03 gm/kg H

=

absolute humidity of the atmosphere, 8.0, gm/rm3 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.

ML15105A080: Difference between revisions

Latest revision as of 13:19, 10 January 2025

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Text

SUMMARY

SUMMARY

SUMMARY

Title:

3.0 REFERENCES

3.0 REFERENCES

the sample sie nit ss or volt n as defined above section 4.9) inting rate or of the counting nts per minute, cpm) isintegration) 2.22E+06

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ML15105A080: Difference between revisions

Latest revision as of 13:19, 10 January 2025

Text

SUMMARY

SUMMARY

SUMMARY

Title:

3.0 REFERENCES

3.0 REFERENCES

the sample sie nit ss or volt n as defined above section 4.9) inting rate or of the counting nts per minute, cpm) isintegration) 2.22E+06

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